· administrative job performance measure a1jpm-ro-pms1 page 1 of 7 a1 unit: 1 rev # 4 date:...

ADMINISTRATIVE JOB PERFORMANCE MEASURE

A1JPM-RO-PMS1 of 7A1

UNIT: 1 REV # 4 DATE: ___________________

SYSTEM/DUTY AREA: ADMINISTRATIVE TOPIC – CONDUCT OF OPERATIONS

TASK: OPERATE THE PLANT COMPUTER

JTA#: ANO1-RO-PMS-NORM-4

KA VALUE RO: 3.9 SRO: 3.8 KA REFERENCE: 2.1.19

APPROVED FOR ADMINISTRATION TO: RO: X SRO:

TASK LOCATION: INSIDE CR: X OUTSIDE CR:_________ BOTH:________

SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE:_______________ SIMULATOR: PERFORM LAB:__________

POSITION EVALUATED: RO:_______ SRO:___________

ACTUAL TESTING ENVIRONMENT: SIMULATOR: X PLANT SITE:__________ LAB:________

TESTING METHOD: SIMULATE:_________ PERFORM: X

APPROXIMATE COMPLETION TIME IN MINUTES: 10 MINUTES

REFERENCE(S): 1103.004, Chg. 032

______________________________________________________________________

EXAMINEE'S NAME:________________________________ Logon: _______________________

EVALUATOR'S NAME:__________________________________________________________________

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDSCONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY:________________ UNSATISFACTORY:_________________

PERFORMANCE CHECKLIST COMMENTS:

___________________________________________________________________________________

___________________________________________________________________________________

___________________________________________________________________________________

Start Time ____________ Stop Time ____________ Total Time ______________

SIGNED _Robert Possage_______________________________ DATE: _______________________

SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY AQUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.



THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall ensure that the examinee has been briefed on NUREG 1021 Appendix E.

JPM INITIAL TASK CONDITIONS: The plant is at 100% power operations. The Makeup Tank

level is at 58 inches. RCS boron concentration is 800 ppm. BAAT boron concentration is

12,000 ppm.

TASK STANDARD: The examinee uses the plant computer “BORON” program to calculate a

total addition to the Makeup Tank of approximately 680 gallons consisting of 45.3 gallons of

boric acid and 633.7 gallons of DI water. (+/- 5%)

TASK PERFORMANCE AIDS: 1103.004, SOLUBLE POISON CONCENTRATION CONTROL

NOTE: Procedure 1103.004 provides direction to use Attachment A.4 or the Plant MonitoringSystem. The manipulations related to PMS for this task are within the “skill of the craft.” If theapplicant chooses to use Attachment A.4, direct them to utilize the Plant MonitoringSystem.



INITIATING CUE:

The CRS directs you to use the plant computer to calculate a “No Concentration Change” to raise the MakeupTank level to ~80 inches.

CRITICAL ELEMENTS (C) 2, 3, 4, 5

(C) PERFORMANCE CHECKLIST STANDARD N/A SAT UNSAT

1. Select NASP on PMS screen orkeyboard.

Selected NAS (NASP Menu) on PMS._____ _____ _____

(C) 2. Select BORON program. Selected BORON program on PMS._____ _____ _____

(C) 3. Select option No. 5, NoConcentration Change.

Typed “5” and pressed ENTER keyon PMS keyboard. _____ _____ _____

(C) 4. Select option 0, boric acid and DIwater addition.

Typed “0” and pressed ENTER keyon PMS keyboard. _____ _____ _____

(C) 5. Enter values requested by BORONprogram.

Examinee entered the followingvalues:· Makeup volume required

(gallons) = 660 to 690 (traineeshould calculate the valueneeded using 22 inches x 30.86gallons/in. which is 679 gallons)

· Makeup boron concentrationrequired (ppm) = 800

· Available feed solution Boronconcentration (ppm) = 12,000

The PMS displayed the followingvalues after entry of final value:· Feed volume DI H2O – 633.7

602 to 665 gallons· Feed volume boric acid – 45.3

43 to 47.5 gallons

_____ _____ _____

END



KEY

JPM INITIAL TASK CONDITIONS:

· The plant is at 100% power operations.· The Makeup Tank level is at 58 inches.· RCS boron concentration = 800 ppm· BAAT boron concentration = 12,000 ppm

INITIATING CUE:

The CRS directs you to use 1103.004, SOLUBLE POISON CONCENTRATIONCONTROL, and the “BORON” program on the plant computer to calculate a “NoConcentration Change” to raise the Makeup Tank level to ~80 inches.

Feed Volume required

Gallons of DI Water: 602 – 665 (633.7) .

Gallons of Acid: 43 – 47.5 (45.3) .



EXAMINEE’S COPY


· The plant is at 100% power operations.· The Makeup Tank level is at 58 inches.· RCS boron concentration = 800 ppm· BAAT boron concentration = 12,000 ppm

INITIATING CUE:

The CRS directs you to use 1103.004, SOLUBLE POISON CONCENTRATIONCONTROL, and the “BORON” program on the plant computer to calculate a “NoConcentration Change” to raise the Makeup Tank level to ~80 inches.

Feed Volume required

Gallons of DI Water: .

Gallons of Acid: .


A1JPM-RO-PMS1 of 7A18.0 BORATION – MANUAL BATCH FEED

8.1 Initial Conditions

CAUTIONThe following section has Reactivity Addition Potential (RAP) and is classifiedRisk Level R2.

· ENSURE a Reactivity Management Brief is conducted with an SRO perCOPD-030, ANO Reactivity Management Program.

· CHECK ONE of the following:

- Makeup and Purification system is aligned per 1015.001, Conduct ofOperations, "System Alignment Verification" and in operation per 1104.002,Makeup & Purification System Operation, "System Startup" section.

- RCS fill and vent is being performed and is aligned per 1103.002, Filling andVenting the Reactor Coolant System.

· CHECK Chemical Addition system aligned per 1015.001, Conduct of Operations,"System Alignment Verification" section.

· IF boration is for other than normal activities such as significant boration to maintainrod position following power change,THEN NOTIFY Chemistry of boration and DIRECT Chemistry to evaluate thepotential effect of the shift in boron on lithium control band

NOTESimultaneous boric acid addition to the Makeup System using both batch controller andbypassing batch controller flow paths is permitted during RCS cooldown in Modes 3 and 4.

· IF NOT performing plant cooldown,THEN CHECK no other transfer of boric acid from BAAT in progress.

RAP



NOTE· When using the BORON program, any operating conditions may be input.

· Attachment C, Mass of Reactor Coolant vs. Pressurizer Level and the BORON programautomatically add 167,000 pounds to the reactor coolant mass when RCS temperature is lessthan or equal to 250.0°F, to account for the Decay Heat system.

8.1.1 PERFORM the following calculations:

A. IF feeding boric acid or DI Water only,THEN USE Attachment A.3, Feed Volume for BatchBoration or use Dilution Plant Monitoring System BORONprogram to determine volume needed.

NOTE· The method of boration during cooldown is to initially borate to the maximum concentration

required during the cooldown as determined in 1103.015, Reactivity Balance Calculations.

· Batches made to Makeup Tank with boric acid followed by DI water should typically be500-1000 gallons.

B. IF performing a cooldown,THEN USE Attachment A.5, Boration During Cooldown oruse Plant Monitoring System BORON program to determinevolume needed.

C. IF feeding boric acid and DI water to maintainconstant RCS concentration,THEN USE Attachment A.4, Maintain Constant RCS BoronConcentration or use Plant Monitoring System BORONprogram, to determine the volume ratios needed.

D. IF intending to change RCS concentration while feedingboth acid and water (requires at least two calcs),THEN water volumes or acid volumes may be combined asone batch.

E. RECORD volume of each batch to be added onAttachment B, RCS Liquid Addition Data Sheet.

· DIVIDE total feed volume into multiple smaller batches ontoseparate lines on Attachment B, RCS Liquid Addition DataSheet for each intended batch as needed to help controlevolution.

F. RECORD RO/SRO independent review of calculations andon Attachment B, RCS Liquid Addition Data Sheet.

ADMINISTRATIVE JOB PERFORMANCE MEASURE PAGE 1 OF 9

A1-JPM-RO-SFPMUA2

UNIT: 1 REV #: 3 DATE:

SYSTEM/DUTY AREA: Administrative Topic – Conduct of Operations

TASK: Perform Spent Fuel Pool Makeup Calculation.

JTA#: ANO1-RO-SFC-NORM-17



TASK LOCATION: INSIDE CR: OUTSIDE CR: BOTH: X


PLANT SITE: SIMULATOR: Perform Classroom: Perform

POSITION EVALUATED: RO: X SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: Classroom:

TESTING METHOD: SIMULATE: PERFORM: X

APPROXIMATE COMPLETION TIME IN MINUTES: 30 Minutes

REFERENCE(S): 1104.003, Att. C2

EXAMINEE'S NAME: Logon:

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THISJPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:


Start Time Stop Time Total Time

SIGNED: Robert Possage DATE:



A1-JPM-RO-SFPMUA2


The examiner shall ensure that the examinee has been briefed on NUREG 1021 AppendixE.


Given the following Plant conditions:

· Plant is at 100% power.

· SFP level is -0.4 ft.

· SFP Boron concentration 2300 ppm.

· BAAT Boron concentration 12,250 ppm.

· Tilt Pit and cask pit gates are removed.

TASK STANDARD:Determined volume is 362,843 gallons from Table 2.

Determined feed volume to be 4429 + 2 gallons.

Determined final SF Pool volume to be 367,272 + 5 gallons.

Determined final SF Pool level is from +0.0 to +0.1 ft.

TASK PERFORMANCE AIDS:

1104.003, Attachment C2

SIMULATOR SETUP:

NA

EXAMINER'S NOTES:


A1-JPM-RO-SFPMUA2

INITIATING CUE:CRS directs you to perform 1104.003, Chemical Addition, Attachment C2, for makeup to SFP to raise Boronconcentration to 2420 ppm. Determine amount of Boric Acid volume needed and final SFP level after BoricAcid addition.

PERFORMANCE CHECKLIST STANDARDS (Circle One)

1.

(C) 1.1 Determine initial SF Poolvolume from TABLE 2.Interpolate if necessary.

Determined volume is 362,843gallons from Table 2. N/A SAT UNSAT

2.1.2 Record the following data: Recorded data. (See key) N/A SAT UNSAT

3.

(C) 1.3 Determine feed volume to beadded to the SF Pool.

Determined feed volume to be4429 gallons. (See key)

N/A SAT UNSAT

4.

(C) 1.4 Determine final SF Pool volume. Determined final SF Pool volumeto be 367,272 gallons. (See key)

N/A SAT UNSAT

5.

(C) 1.5 Determine final SF Pool levelfrom TABLE 2, interpolate asnecessary.

Determined final SF Pool level isfrom +0.0 to +0.1 ft. (See key)

N/A SAT UNSAT

END


A1-JPM-RO-SFPMUA2

ANSWER KEY




· SF Pool level is -0.4 ft.

· SF Pool Boron concentration 2300 ppm.

· BAAT Boron concentration 12,250 ppm.

· Tilt Pit and Cask Pit gates are removed.

INITIATING CUE:

CRS directs you to perform 1104.003, Chemical Addition, Attachment C2, for makeup toSFP to raise Boron concentration to 2420 ppm.Determine amount of Boric Acid volume needed.Determine final SF Pool volume.Determine final SF Pool level.

(C) Determined initial SF Pool volume is currently 362,843 gallons from Table 2.

(C) Determined feed volume to be 4429 ± 2 gallons.

(C) Determined final SF Pool volume to be 367,272 ± 5 gallons.

(C) Determined final SF Pool level is from 0.0 to + 0.1 ft. (400.5 – 400.6 elevation)

Final Level interpolation:

(367655 - 366692) = 0.1 .

(367272 - 366692) X

X = 0.1 (580) = 0.06 feet

963

Final Level = + 0.06 feet OR 400.56 Elevation


A1-JPM-RO-SFPMUA2

KEY


Given the following Plant conditions:· Plant is at 100% power.· SFP level is -0.4 ft.· SFP Boron concentration 2300 ppm.· BAAT Boron concentration 12,250 ppm.· Tilt Pit and cask pit gates are removed.

INITIATING CUE:

CRS directs you to perform 1104.003, Chemical Addition,Attachment C2, for makeup to SFP to raise Boron concentration to2420 ppm.Determine amount of Boric Acid volume needed AND final SFP levelafter Boric Acid addition.

Document your answer below.

Boric Acid Volume added: _________4429.4_+/- 2 gallons___

Final SFP Volume after addition: ____367,272_+/- 5 gallons__

Final SFP Level: _+0.06 feet or 400.56 feet elevation______

Acceptance criteria: 0.0 to +0.1 feet or 400.5 to 400.6 feet elevation


A1-JPM-RO-SFPMUA2

KEYTABLE 1

Spent Fuel Pool and Systems Volume/Ft Depth

SF Pool(gal/ft)

SFPool+ CaskPit

(gal/ft)

SFPool+ TiltPit

(gal/ft)

SFPool+ CaskPit

+ TiltPit(gal/ft

)

Refueling

Canal(gal/ft

)

IncoreTank

(gal/ft)

7,570 8,349 8,845 9,624 11,070 1,141

TABLE 2Spent Fuel Pool and Systems Volume (gallons)

Elev.(ft)

LI-2004 SF Pool SFPool+ CaskPit

SFPool+ TiltPit (1)

SFPool+ CaskPit+ TiltPit (1)

Refueling

Canal

IncoreTank

401.5 +1.0 ft 298,120 330,899 343,537 376,316

401.4 +0.9 ft 297,363 330,064 342,653 375,354401.3 +0.8 ft 296,606 329,229 341,768 374,392401.2 +0.7 ft 295,849 328,394 340,884 373,429401.1 +0.6 ft 295,092 327,559 339,999 372,467401.0 +0.5 ft 294,335 326,725 339,115 371,504

400.9 +0.4 ft 293,578 325,890 338,230 370,542400.8 +0.3 ft 292,821 325,055 337,346 369,580400.7 +0.2 ft 292,064 324,220 336,461 368,617400.6 +0.1 ft 291,307 323,385 335,577 367,655400.5 0.0 ft 290,550 322,550 334,692 366,692 342,800 27,400

400.4 -0.1 ft 289,793 321,715 333,808 365,730 341,693 27,286400.3 -0.2 ft 289,036 320,880 332,923 364,768 340,586 27,172400.2 -0.3 ft 288,279 320,045 332,039 363,805 339,479 27,058400.1 -0.4 ft 287,522 319,210 331,154 362,843 338,372 26,944400.0 -0.5 ft 286,765 318,376 330,270 361,880 337,265 26,830

399.9 -0.6 ft 286,008 317,541 329,385 360,918 336,158 26,715399.8 -0.7 ft 285,251 316,706 328,501 359,956 335,051 26,601399.7 -0.8 ft 284,494 315,871 327,616 358,993 333,944 26,487399.6 -0.9 ft 283,737 315,036 326,732 358,031 332,837 26,373399.5 -1.0 ft 282,980 314,201 325,847 357,068 331,730 26,259

399.4 -1.1 ft 282,223 313,366 324,963 356,106 330,623 26,145399.3 -1.2 ft 281,466 312,531 324,078 355,143 329,516 26,031399.2 -1.3 ft 280,709 311,696 323,194 354,181 328,409 25,917399.1 -1.4 ft 279,952 310,861 322,309 353,219 327,302 25,803399.0 -1.5 ft 279,195 310,026 321,425 352,256 326,195 25,689

(1) Tilt Pit volume from CR-ANO-1-2008-1859-CA2.

Duringrefueling, canal

level ismaintained

between -0.5and 0.0 on the

SFP Levelindicator

InitialLevel

FinalLevel


A1-JPM-RO-SFPMUA2

KEYATTACHMENT C2

Page 2 of 7

CAUTIONPerformance of this section could result in overflowing of theSFP or other attached volumes.

NOTE· It is necessary to coordinate with Dry Fuel Personnel when

making up to the Spent Fuel Pool during Dry Fuel Operations.

· Step 1.0 is solely performed to determine volume of boricacid at a known concentration to achieve a desired final SFPboron concentration, and generally is not used.

1.0 IF it is desired to calculate the volume of boric acid requiredto achieve a specific final SFP concentration,THEN perform the following:

1.1 Determine initial volume from TABLE 2, interpolating as necessary.

IF appropriate,THEN add Refueling Canal and Incore Tank volume.

Vi = ___362,843___gal = Initial Volume from TABLE 2

1.2 Record the following data:

Ci = __2300____ppmB = Initial SF Pool concentration

Cf = __2420____ppmB = Final desired SF Pool concentration

Cfd = __12,250__ppmB = Feed concentration to be added to SF Pool

1.3 Determine feed volume to be added to the SF Pool

Vfd = ( Vi ) x ( Cf - Ci )

( Cfd - Cf )

Vfd = ( 362,843 ) x ( 2420 - 2300 )

( 12,250 - 2420 )

Vfd = _4429.4_gal.


A1-JPM-RO-SFPMUA2

KEYATTACHMENT C2

Page 3 of 7

1.4 Determine final SF Pool volume

Final volume = ( Vfd ) + ( Vi )

Final volume = ( 4429 ) + ( 362,843 )

Final =_367,272_gal.Volume

NOTEIf final SF Pool level is determined to be greater than +1.0 ftor greater than zero when refueling, then the addition is madein separate additions to prevent overflow.

1.5 Determine final SF Pool level from TABLE 2, interpolate asnecessary.

1.5.1 IF Final volume greater than table valuesTHEN perform separate additions.

1.6 Perform the other sections of this Attachment as required.

2.0 IF needed,THEN find the volume of feed (Vfd) AND use TABLE 1 for SF Pool gal/ft.IF Refueling Canal or Incore Tank is connected to SF Cooling SystemTHEN add appropriate gal/ft to the SF Pool gal/ft.

Vfd = [(Final level) - (Initial level)] x ( gal/ft )

Vfd = [(________ft.) - (__________ft.)] x (________gal/ft)

Vfd =__________gal.


A1-JPM-RO-SFPMUA2

Applicant’s Copy


Given the following Plant conditions:· Plant is at 100% power.· SFP level is -0.4 ft.· SFP Boron concentration 2300 ppm.· BAAT Boron concentration 12,250 ppm.· Tilt Pit and cask pit gates are removed.

INITIATING CUE:

CRS directs you to perform 1104.003, Chemical Addition,Attachment C2, for makeup to SFP to raise Boron concentration to2420 ppm.Determine amount of Boric Acid volume needed AND final SFP levelafter Boric Acid addition.

Document your answer below.

Boric Acid Volume added: ____________________________

Final SFP Volume after addition: _______________________

Final SFP Level after addition: _________________________


A1JPM-RO-HCRD6A3


SYSTEM/DUTY AREA: Administrative Topic – Equipment Control

TASK: Perform identification of components that need to be isolated and Danger Tagged for

a check valve replacement on Spent Fuel Pool Cooling Pump P-40B (SF-4B).

JTA#: ANO-RO-ADMIN-NORM-078





PLANT SITE: SIMULATOR: Classroom: Perform

POSITION EVALUATED: RO: X SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: Classroom: X

TESTING METHOD: SIMULATE: PERFORM: X


REFERENCE(S): EN-OP-102, PROTECTIVE AND CAUTION TAGGING, P&ID M-235

Electrical Print E-266, OP-1107.002, ES ELECTRICAL SYSTEM OPERATION

EXAMINEE'S NAME: Logon ID:

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THISJPM AND IS DETERMINED TO BE:







A1JPM-RO-HCRD6A3






· SF-4B, SFP Cooling Pump P-40B Discharge Check Valve, needs to be repaired.

TASK STANDARD:Examinee correctly identifies the fluid boundary isolation valves and electrical power supply for work on SF-4B

See table in answer key for specific components and required positions.


EN-OP-102, PROTECTIVE AND CAUTION TAGGING, P&ID M-235 SPENT FUEL COOLING SYSTEM

Electrical Print E-244, OP-1107.002, ES ELECTRICAL SYSTEM OPERATION

SIMULATOR SETUP:

NA

EXAMINER'S NOTES:


A1JPM-RO-HCRD6A3

INITIATING CUE:

The SM/CRS has directed you to identify the components that need to be danger tagged to electrically andmechanically isolate and drain P-40B discharge check valve, SF-4B.

CRITICAL ELEMENTS (C):


(C)1. Reviews controlled documentation

to determine source of power to P-40B to add to the tagout(E-Print E-244 or OP-1107.002Attachment D)

Determines that Electrical CircuitBreaker B-5521 will need to beOpened and added to the tagout. _____ _____ _____

Note: Typical tagging verbiage is Breaker Open/Removed, which allows for breaker maintenance withoutviolating the hold card. In this case either Breaker Open or Breaker Open/Removed is acceptable.

The Candidate may add either a Caution Tag or an Equipment Protection Tag to be placed on the Spent FuelCooling Pump P-40B Remote Hand Switch. This may not be happen since the applicant is asked specificallyfor necessary danger tags.


to determine the P-40B pumpdischarge Isolation will need to beadded to the tagout (P&ID M-235)

Determines that P-40B DischargeIsolation SF-5B will need to beClosed and added to the tagout.

_____ _____ _____


to determine the P-40B pumpsuction Isolation will need to beadded to the tagout (P&ID M-235)

Determines that P-40B SuctionIsolation SF-3B will need to beClosed and added to the tagout. _____ _____ _____


to determine the P-40B pump drainIsolation will need to be added tothe tagout (P&ID M-235)

Determines that P-40B drain IsolationDWD-15B AND/OR SF-1009 willneed to be Opened and added to thetagout.

_____ _____ _____

NOTE: Either DWD-15B or SF-1009 will drain the pump. It is acceptable for the applicant to select either oneor both for the tagging boundary.


to determine the P-40B pump ventIsolation will need to be added tothe tagout (P&ID M-235)

Determines that P-40B vent IsolationGCH-14B will need to be Openedand added to the tagout. _____ _____ _____

NOTE: Inform examinee that JPM is complete.

END


A1JPM-RO-HCRD6A3

EXAMINER ANSWER KEY

Component # Component Name Component Position

HS-2001 Spent Fuel Pool Cooling Pump P-40BHandswitch

Caution Tag OREquipment ProtectionTag Installed (1)

B-5521 Spent Fuel Pool Cooling Pump P-40Bpower supply Breaker Open (2)

SF-5B P-40B Discharge Valve Closed

SF-3B P-40B Suction Isolation Closed

DWD-15B P-40B Drain Open (3)

SF-1009 P-40B Discharge Line Drain Open (3)

GCH-14B P-40B Vent Open (3)

Examiner Notes

Note 1: The control switch will be tagged with either a Caution Tag or EquipmentProtection Tag to provide information on equipment status. The handswitch is a springreturn to center, so a position is not required. This tag may not be listed since the task isto identify the Danger Tags required to isolate and drain the equipment.

Note 2: Typical tagging verbiage is Breaker Open/Removed, which allows for breakermaintenance without violating the hold card. In this case either Breaker Open or BreakerOpen/Removed is acceptable.

Note 3: Either drain (DWD-15B or SF-1009) or vent (GCH-14B) is acceptable.Per EN-OP-102, Protective and Caution Tagging, Step 2.5 reads as follows.

2.5 Vents and drains must also be opened as required to release dangerous pressuresor harmful substances. One vent or drain should normally be Danger or EquipmentProtection Tagged open to depressurize systems and to prevent them from re-pressurizing. There will be cases when this is not possible due to system designs.

Therefore only one of the three is required to be Danger Tagged open.


A1JPM-RO-HCRD6A3

EXAMINEE’S COPY


· The plant is at 100% power.· SF-4B, Spent Fuel Pool Cooling Pump P-40B Discharge Check

Valve requires repairs.· A Danger Tag will need to be generated to isolate and drain SF-4B.

INITIATING CUE:

The SM/CRS has directed you to identify the components that need tobe danger tagged to electrically and mechanically isolate and drain SF-4B, Spent Fuel Pool Cooling Pump P-40B, Discharge Check Valve.

Also provide the component danger tag position required.


A1JPM-RO-HCRD6A3

EXAMINEE’S COPY

Component # Component Name Position

ADMINISTRATIVE JOB PERFORMANCE MEASURE Page 1 of 5

A1JPM-RO-RWP3A4

UNIT: 1 REV # 1 DATE: ______________________________

TUOI NUMBER: A1JPM-RO-RWP3

SYSTEM/DUTY AREA: ADMINISTRATIVE TOPIC – Radiation Control

TASK: Ability to comply with radiation work permit requirements

JTA#: ANO1-RO-MUP-NORM-16



TASK LOCATION: INSIDE CR: OUTSIDE CR:_______ CLASSROOM:___X____


PLANT SITE:_____________ SIMULATOR: Classroom: ________X_________

POSITION EVALUATED: RO:____X______ SRO:__________

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE:______ Classroom:__ X___

TESTING METHOD: SIMULATE:_________ PERFORM:___X________


REFERENCE(S): RWP 2018-1002

______________________________________________________________________

EXAMINEE'S NAME:_______________________________ Logon: _______ ____________

EVALUATOR'S NAME:__________________________________________________________________




___________________________________________________________________________

___________________________________________________________________________

___________________________________________________________________________

____________ Start Time ____________ Stop Time ____________ Total Time

SIGNED Robert Possage ________________________________ DATE: _______________________



A1JPM-RO-RWP3A4



INITIAL PLANT CONDITIONS

· Refueling outage is in progress.· Maintenance requires your assistance in T-36 lower valve gallery area.· The dose rate in the area is 55 mR/hr.

TASK STANDARD:

Refer to the attached RWP.

Using the above information determined the MAXIMUM stay time in the lower valve gallery is9.9 to 10.9 minutes.

TASK PERFORMANCE AIDS: RWP 2018-1002 .

SIMULATOR SETUP: NA


A1JPM-RO-RWP3A4

INITIATING CUE:


Using the above information determine your MAXIMUM stay time in the lower valve gallery.


(C) 1. Recognize the dose limit perthe RWP is 10 mR.

Applicant identifies that the RWPDose Alarm is set at 10 mR

Applicant may also identify that the

Dose Rate Alarm is set at 150 mR/hr.

_____ _____ _____

(C) 2. Determine stay time based onthe given dose in the area notto exceed RWP limit of 10 mR.

10 mR X 60 min = 10.9minutes

55 mR/hr 1 hr

Applicant determines that the RWPDose Alarm limit is set at 10 mRwhich would allow him to stay 10.9minutes.

Acceptable answer 9.9 to <10.9minutes.

_____ _____ _____

END


A1JPM-RO-RWP3A4

Key


· Refueling outage is in progress.· Maintenance requires your assistance in the

lower T-36 Valve Gallery.· The dose rate in the area is 55 mR/hr.

INITIATING CUE:


Using the above information determine yourMAXIMUM stay time in the lower valve gallery.

Maximum stay time based on RWP limit is 10.9 minutes. An acceptance criterion is 9.9 to 10.9 minutes.


A1JPM-RO-RWP3A4

Applicant’s Copy


· Refueling outage is in progress.· Maintenance requires your assistance in the

lower T-36 Valve Gallery.· The dose rate in the area is 55 mR/hr.

INITIATING CUE:


Using the above information determine yourMAXIMUM stay time in the lower valve gallery.


A1JPM-SRO-ADMINRILA5

UNIT: 1 REV # 0 DATE: ______________________________

JPM ID: A1JPM-SRO-ADMINRIL

SYSTEM/DUTY AREA: ADMINISTRATIVE TOPIC – CONDUCT OF OPERATIONS

TASK: Ability to Interpret Rod Insertion Limits per COLR for operability

JTA#: ANO1-SRO-CRD-OFFNORM-393


APPROVED FOR ADMINISTRATION TO: RO: SRO: X

TASK LOCATION: INSIDE CR: OUTSIDE CR:____X_____ BOTH:________


PLANT SITE:_____________ SIMULATOR: CLASSROOM:_________X____

POSITION EVALUATED: RO:____ ______ SRO:____ X_______

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE:______ CR:__X___

TESTING METHOD: SIMULATE:_________ PERFORM:___X________


REFERENCE(S): 1203.012G, Tech Specs, COLR

______________________________________________________________________

EXAMINEE'S NAME:_______________________________ LOGIN ID __________________

EVALUATOR'S NAME:__________________________________________________________________




___________________________________________________________________________

___________________________________________________________________________

___________________________________________________________________________

____________ Start Time ____________ Stop Time ____________ Total Time

SIGNED Robert Possage ________________________________ DATE: _______________________






JPM INITIAL TASK CONDITIONS: Following a transient, the plant is at 40% power. Alarm

K08-D4 is received POWER Distribution Alarm. Core at 250 EFPD, rod index 148%, Rx

power 40%.

TASK STANDARD: The examinee has determined rod insertion limits are violated, LCO 3.2.1

Condition A should, be entered, and Required Actions A.1 and A.2 must be performed.

TASK PERFORMANCE AIDS: Cycle 26 COLR, 1203.012G, Tech Specs. 3.2.1



INITIATING CUE:

The SM directs you to perform actions per 1203.012G Annunciator Corrective Action K08-D4 Powerdistribution alarm due to approaching rod index limits. Determine if any TS LCOs are in effect, and if anyactions are required.

CRITICAL ELEMENTS (C): 3, 5, 6, 7

(C) PERFORMANCE CHECKLIST STANDARD SAT UNSAT NA

1. Reference guidance in AnnunciatorCorrective Actions (ACA) forK08-D4 alarm.

Used OP 1203.012G Window K08-D4for guidance with the rod insertionlimit.

_____ _____ _____

2. Reference Technical Specificationfor Regulating Rod Insertion LimitsT.S. 3.2.1.

Used T.S. 3.2.1 to transition to theCore Operating Limits Report(COLR).

_____ _____ _____

(C) 3. Determine the correct COLR figurefor given plant conditions.

Determined based on given plantconditions that COLR Figure 3-B isapplicable.

_____ _____ _____

4. Obtain Rod Index and compare toCOLR figure 3-B.

Used COLR Figure 3-B and a rodindex of 148% and 40% power toverify what region rods are in.

_____ _____ _____

(C)5. Determine alarm is valid.

Used COLR Figure 3-B, determinedalarm is valid, rod insertion limits areexceeded, and the rods fall into the“Operation Restricted” area of thecurve.

_____ _____ _____

(C) 6. Determine TS 3.2.1 is applicable. Informed SM that TS LCO 3.2.1 isapplicable for the given conditions. _____ _____ _____

(C) 7. Determine Condition A of TS 3.2.1is applicable and Required ActionsA.1 and A.2 should beimplemented.

Determined SR 3.2.5.1 should beperformed every 2 hours AND theregulating rod groups should berestored to within acceptable limitswithin 24 hours from discovery offailure to meet the LCO.

_____ _____ _____

END



KEY


· All RCPs are running· “A” MFW Pump tripped.· Alarm K08-D4 is received “POWER DISTRIBUTION ALARM”.

oDue to Rod Index Limits

Current Conditions:· Core at 250 EFPD· Rod index 148%· Rx power 40%

INITIATING CUE:

The SM directs you to perform actions per 1203.012G AnnunciatorCorrective Action K08-D4 Power distribution alarm due toapproaching rod index limits. Determine if any TS LCOs are ineffect, and if any actions are required.

LOC 3.2.1 Condition A should be enteredRequired Actions A.1 AND A.2 must be performedA.1 Perform SR 3.2.5.1 every 2 hoursA.2 Restore regulating rod group to within acceptable regionwithin24 hours from discovery of failure to meet the LCOThe black text just explains the required red text and is not necessaryfor successful completion of the JPM



Applicant’s Copy


· All RCPs are running· “A” MFW Pump tripped.· Alarm K08-D4 is received “POWER DISTRIBUTION ALARM”.

oDue to Rod Index Limits

Current Conditions:· Core at 250 EFPD· Rod index 148%· Rx power 40%

INITIATING CUE:

The SM directs you to perform actions per 1203.012G AnnunciatorCorrective Action K08-D4 Power distribution alarm due toapproaching rod index limits. Determine if any TS LCOs are ineffect, and if any actions are required.


A1JPM-SRO-ADMINREPORTPage 1 of 5

A6

UNIT: 1 REV # 0 DATE: ___________________

SYSTEM/DUTY AREA: Reportability

TASK: Determine Immediate Notification Requirement for a given plant condition

JTA: ANO-SRO-ADMIN-OFFNORM-163



TASK LOCATION: INSIDE CR: OUTSIDE CR:___X______ BOTH:________


PLANT SITE _____________ SIMULATOR: Classroom: ____X______


ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE:__________ Classroom: ____X______



REFERENCE(S): 10CFR50.72, 10CFR50.73, EN-LI-108, REAP

______________________________________________________________________

EXAMINEE'S NAME:________________________________ Logon ID: _______________________

EVALUATOR'S NAME:__________________________________________________________________




___________________________________________________________________________________

___________________________________________________________________________________

___________________________________________________________________________________






A6

JPM ID: A1JPM-SRO-ADMINREPORT




The unit is operating at 40% power when a failure in the Turbine EHC System results in turbineoscillations. As a result of the oscillations the CBOR manually trips the reactor. No othercomplications occurs post trip.

TASK STANDARD:

Identify that based on the manual reactor trip while critical, 10CFR50.72(b)(2)(iv)(B) requires aFour-hour report made to the NRC Operations Center.

TASK PERFORMANCE AIDS: 10CFR50.72, EN-LI-108, REAP (Reportability EvaluationAssistance Program)



A6

JPM ID: A1JPM-SRO-ADMINREPORT

INITIATING CUE: The SM directs you to determine the most time restrictive Immediate Notification requirement perEN-LI-108, to the NRC Operations Center, based on the given conditions.

Critical Tasks: Steps 2 and 4.

C PERFORMANCE CHECKLIST STANDARD N/A SAT UNSAT1) Reference EN-LI-108, Event

Notification and Reportingprocedure.

Applicant references EN-LI-108,Event Notification and Reportingprocedure.

2) Reference REAP (ReportabilityEvaluation Assistance Program) todetermine applicability of the givenconditions.

Applicant references REAP todetermine applicability of the givencondition and identifies that SAF 1.12provides guidance to 10CFR50.72and 10CFR50.73

____ ____ ____

C

3) Reference 10CFR50.72 to determineapplicability of the given conditions.

Applicant references 10CFR50.72and determines that (b)(2)(iv)(B) isapplicable for the given conditions.

Applicant references 10CFR50.72and determines that (b)(3)(iv)(A) isNOT applicable for the givenconditions.

____ ____ ____

4) Reference 10CFR50.73 to determineapplicability of the given conditions.

Applicant references 10CFR50.73and determines that this section is notapplicable since it refers to LERs ____ ____ ____

C

5) Reference 10CFR50.72 to determinenotification requirements.

Applicant references 10CFR50.72and determines that (b)(2)(iv)(B)requires a Four-Hour report to theNRC Operations Center is required. ____ ____ ____

END



A6

KEY

INITIAL CONDITIONS:

Unit at 40% powerFailure in the Turbine EHC System results in turbine oscillationsCBOR manually trips the reactorNo other complications post trip

INITIATING CUE:

The SM directs you to determine the most time restrictive ImmediateNotification requirements per EN-LI-108 to the NRC OperationsCenter for the above condition.

Four-Hour report per 10CFR50.72(b)(2)(iv)(B) is required to be made to the NRC Operations Center.

NOTE: Only the bold information required for full credit.



A6

Applicant’s Copy

INITIAL CONDITIONS:

Unit at 40% powerFailure in the Turbine EHC System results in turbine oscillationsCBOR manually trips the reactorNo other complications post trip

INITIATING CUE:

The SM directs you to determine the most time restrictive ImmediateNotification requirements per EN-LI-108 to the NRC OperationsCenter for the above condition.

ADMINISTRATIVE JOB PERFORMANC MEASUREA1JPM-SRO-ADMINMSSVA7

Page 1 of 7

UNIT: 1 REV # 0 DATE: ___________________

SYSTEM/DUTY AREA: Main and Reheat Steam Systems (MRSS)

TASK: Determine Operability of MSSV and apply Technical Specifications

JTA: ANO-SRO-ADMIN-NORM-103





PLANT SITE _____________ SIMULATOR: Classroom: __Perform________


ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE:__________ Classroom: __X____



REFERENCE(S): Technical Specification (T.S. 3.7.1 & B3.7.1), OP-1306.017

______________________________________________________________________


EVALUATOR'S NAME:__________________________________________________________________




___________________________________________________________________________________

___________________________________________________________________________________

___________________________________________________________________________________





Page 2 of 7

JPM ID: A1JPM-SRO-MSSV




Maintenance reports the following as found lift setpoints for the Main Steam Safety Valves.Determine which MSSVs are OPERABLE / INOPERABLE and apply Technical Specifications to includeCONDITION, REQUIRED ACTION and COMPLETION TIMES

TASK STANDARD:

Identify that PSV-2698 and PSV-2694 for the A Steam Generator and PSV-2684, PSV-2686 and PSV-2691for the B Steam Generator are INOPERABLE based on their as found lift setpoints.This requires entry into T.S. 3.7.1 Condition A.Required Actions:A.1 Reduce power in accordance with Table 3.7.1-1 within 4 hoursANDA.2 Reduce the nuclear overpower trip setpoint in accordance with Table 3.7.1-1 within 36 hours.MAXIMUM ALLOWABLE POWER LEVEL < 71.4% (RTP)RPS NUCLEAR OVERPOWER TRIP ALLOWABLE VALUE < 74.9% (RTP)

TASK PERFORMANCE AIDS: T.S. 3.7.1 and T.S. Bases for 3.7.1, OP-1306.017


Page 3 of 7


INITIATING CUE: The CRS/SM directs you to determine which MSSVs are OPERABLE / INOPERABLE and applyTechnical Specifications to include CONDITION, REQUIRED ACTION and COMPLETION TIMES. (OP-1306.017 is still inprogress.)

Critical Tasks: 3, 4, 5, 6, 7, and 8

C PERFORMANCE CHECKLIST STANDARD N/A SAT UNSAT1) Determine nominal setpoint for eachMain Steam Safety Valve.

Applicant references necessarydocuments to determine the following:PSV-2699 and PSV-2684 – 1050 psigPSV-2698 and PSV-2685 – 1060 psigPSV-2696, PSV-2697, PSV-2686 andPSV-2687 – 1070 psigPSV-2694, PSV-2695, PSV-2688 andPSV-2689 – 1090 psigPSV-2692, PSV-2693, PSV-2690 andPSV-2691 – 1100 psig

____ ____ ____

2) Determine Allowable Tolerance bandfor each group of MSSVs per the T.S.Bases.

Applicant calculates the followingband for Allowable Tolerance:1050 - 3.0% = 1018.5 psig1050 + 3.0% = 1081.5 psig

1060 – 3.9% = 1018.7 psig1060 + 3.0% = 1091.8 psig

1070 – 4.8% = 1018.7 psig1070 + 3.0% = 1102.1 psig

1090 – 6.5% = 1019.2 psig1090 + 3.0% = 1122.7 psig

1100 – 7.4% = 1018.6 psig1100 + 3.0% = 1133 psig

____ ____ ____

C

3) Determine which MSSVs areINOPERABLE for each SteamGenerator.

Applicant identifies that for A SteamGenerator PSV-2698 and PSV-2694are INOPERABLE and for B SteamGenerator PSV-2684, PSV-2686 andPSV-2691 are INOPERABLE.

____ ____ ____


Page 4 of 7


C PERFORMANCE CHECKLIST STANDARD N/A SAT UNSAT

C

4) Identify T.S. CONDITION for theINOPERABLE MSSVs

Applicant determines that entry intoT.S. 3.7.1 Condition A is required

____ ____ ____

C

5) Identify T.S. REQUIRED ACTION forthe INOPERABLE MSSVs

Applicant determines that REQUIREDACTIONs A1 AND A2 must beperformed.

____ ____ ____

C

6) Identify T.S. COMPLETION TIME forthe INOPERABLE MSSVs

Applicant determines A1 must becompleted within 4 hours AND A2must be completed within 36 hours.

____ ____ ____

C

7) Identify MAXIMUM ALLOWABLEPOWER LEVEL for the INOPERABLEMSSVs

Applicant determines using Table3.7.1-1 that MAXIMUM ALLOWABLEPOWER LEVEL is 71.4% RatedThermal Power ____ ____ ____

C

8) Identify RPS NUCLEAROVERPOWER TRIP ALLOWABLEVALUE for the INOPERABLE MSSVs

Applicant determines using Table3.7.1-1that RPS NUCLEAROVERPOWER TRIP ALLOWABLEVALUE is 74.9% Rated ThermalPower

____ ____ ____

END


Page 5 of 7

MSSVAs FoundLift Setting

(psig)

OperableYes / No KEY

A - OTSGPSV-2699 1078 YESPSV-2698 1095 NOPSV-2697 1040 YESPSV-2696 1075 YESPSV-2695 1030 YESPSV-2694 1125 NOPSV-2693 1115 YESPSV-2692 1120 YES

B - OTSGPSV-2684 1085 NOPSV-2685 1025 YESPSV-2686 1105 NOPSV-2687 1095 YESPSV-2688 1100 YESPSV-2689 1025 YESPSV-2690 1120 YESPSV-2691 1135 NO

Using the above table, determine if the MSSV is OPERABLE and enter Yes or NO.

Based on your determination, state the Tech Spec CONDITION, REQUIRED ACTION, andCOMPLETION TIMES.

T.S. 3.7.1 CONDITION A is applicable

A.1 Reduce power in accordance with Table 3.7.1-1 within 4 hours AND

A.2 Reduce the nuclear overpower trip setpoint in accordance with Table 3.7.1-1 within 36 hours.

Based on your determination, state the MAXIMUM ALLOWABLE POWER LEVEL.

71.4% (RTP)

Based on your determination, state the RPS NUCLEAR OVERPOWER TRIP ALLOWABLEVALUE.

74.9% (RTP)


Page 6 of 7

Applicant’s Copy

INITIAL CONDITIONS:· Plant at 95% power.· OP-1306.017, Unit 1 Main Steam Safety Valve Test is still in progress.· Maintenance reports the following as found lift setpoints for the Main

Steam Safety Valves.

INITIATING CUE:The CRS/SM directs you to determine which MSSVs are OPERABLE /INOPERABLE and apply Technical Specifications to include CONDITION,REQUIRED ACTION and COMPLETION TIMES, MAXIMUM ALLOWABLEPOWER LEVEL, and RPS NUCLEAR OVERPOWER TRIP ALLOWABLEVALUE.

MSSVAs FoundLift Setting

(psig)

OperableYes / No

(Spell out Yes or No so thereis no confusion during grading)

A - OTSGPSV-2699 1078PSV-2698 1095PSV-2697 1040PSV-2696 1075PSV-2695 1030PSV-2694 1125PSV-2693 1115PSV-2692 1120

B - OTSGPSV-2684 1085PSV-2685 1025PSV-2686 1105PSV-2687 1095PSV-2688 1100PSV-2689 1025PSV-2690 1120PSV-2691 1135

Using the above table, determine if the MSSV is OPERABLE and enter Yes or NO.


Page 7 of 7

Based on your determination, state the Tech Spec CONDITION, REQUIRED ACTION,and COMPLETION TIMES.

Based on your determination, state the MAXIMUM ALLOWABLE POWER LEVEL.

Based on your determination, state the RPS NUCLEAR OVERPOWER TRIP ALLOWABLE VALUE.


A1JPM-SRO-KIA8


SYSTEM/DUTY AREA: Radiation Control

TASK: Direct Administration of Potassium Iodide

JTA#: ANO-SRO-EPLAN-EMERG-292





PLANT SITE: SIMULATOR: Classroom: Perform

POSITION EVALUATED: RO: SRO: X

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: Classroom:

TESTING METHOD: SIMULATE: PERFORM:


REFERENCE(S): 1903.035

EXAMINEE'S NAME: Logon:

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED INTHIS JPM AND IS DETERMINED TO BE:



StartTime

StopTime

Total Time



A1JPM-SRO-KIA8



A1JPM-SRO-KIA8




The plant tripped from 100% power due to a Loss of Offsite Power. A large break LOCA is in progress and a

Site Area Emergency has been declared due to containment breach. RDACS indicates an off site release.

Repairs are needed in Upper North Piping Penetration Room to stop the release. Data indicates I-131

concentration of 8.0 E-05 uci/cc in area of work in Upper North Piping Penetration Room. Whole Body doserates

in the area are 1 Rem/hr. Repairs are estimated to take 15 minutes and all RP required controls/authorizationare complete. Air Purifying Respirators with Iodine Canisters with a protection factor of 1.0 will be used inplace of

SCBA due to piping interference in work location.

TASK STANDARD:The applicant has authorized the administration of Potassium Iodide (KI)


1903.035, Form 1903.035C and Form 1903.035A

SIMULATOR SETUP:

NA

EXAMINER'S NOTES:


A1JPM-SRO-KIA8


A1JPM-SRO-KIA8

INITIATING CUE:

Determine if KI, Potassium Iodide, should be issued and complete necessary paperwork, using OP-1903.035

PERFORMANCE CHECKLIST STANDARDS (Circle One)

1. Review 1903.035,Administration ofPotassium Iodide todetermine criteria foradministering KI.

(Step 6.1.1)

Applicant determined thecriteria for administration ofKI is 5 REM exposure tothyroid committed doseequivalent (CDE) or ifconcentration is unknown,the possibility exists forreceiving large amounts ofradioactive airborne iodine.

N/A SAT UNSAT

(C) 2. Using graph on1903.035 Attachment1 and informationprovided in initialconditions,determine that JoeMechanic will exceed5 REM CDE duringthe maintenanceevolution.

(Step 6.2.5)

Determined that expectedexposure will exceed the 5REM CDE threshold.

N/A SAT UNSAT

Examiner Note: Provide the applicant a KI Administration Form 1903.035A and aMedical Questionnaire-Iodine Sensitivity Form 1903.035C that has been completedby Joe Mechanic

3. Complete form1903.035A.

(Step 6.3)

Completed all areas of form1903.035A, PotassiumIodide Administration, frominitial conditions:

· Estimated Thyroid dosecommitment.

· Date.· Respiratory Protection

Factor.

N/A SAT UNSAT


A1JPM-SRO-KIA8

PERFORMANCE CHECKLIST STANDARDS (Circle One)(C) 4. Determine that Joe

Mechanic is anacceptable candidate forreceiving KI

(Step 6.4)

Reviewed 1903.035C formand determined that JoeMechanic is an acceptablecandidate for receiving KI

N/A SAT UNSAT

(C) 5. Determine that KIshould be approvedfor distribution to JoeMechanic during theUpper South Pipingpenetration work.

Examinee approveddistribution of KI to JoeMechanic.

· Sign and date1903.035A

N/A SAT UNSAT

END


A1JPM-SRO-KIA8

Key


Given the following Plant conditions:· The plant is tripped from 100% power· Large Break LOCA in progress· Loss of Offsite power is in progress· RDACS indicates an off-site release in progress· Data indicates I-131 concentration of 8.0 E-05 mci/cc in area of work in

Upper South Piping Penetration room· Whole body dose rates in area of work are 1 Rem/hr· Site Area Emergency has been declared· RP estimates that it will take approximately 15 minutes to complete

emergency actions and stop the release and all RP requiredcontrols/authorizations are complete

· Air Purifying Respirator with Iodine Canister having a protection factor of 1.0will be used in place of a SCBA due to piping interference

· EOF, OSC, and TSC are being staffed but are NOT operational· You ARE the SHIFT MANAGER

INITIATING CUE:

Determine if KI, Potassium Iodide, should be issued and complete necessarypaperwork, using OP 1903.035.

Determined that expected exposure will exceed the 5 REM CDE threshold.Reviewed 1903.035C form and determined that Joe Mechanic is an acceptablecandidate for receiving KI.Approve distribution of KI to Joe Mechanic, sign and date 1903.035A.


A1JPM-SRO-KIA8

EXAMINEEE’S COPY


Given the following Plant conditions:· The plant is tripped from 100% power· Large Break LOCA in progress· Loss of Offsite power is in progress· RDACS indicates an off-site release in progress· Data indicates I-131 concentration of 8.0 E-05 mci/cc in area of work in

Upper South Piping Penetration room· Whole body dose rates in area of work are 1 Rem/hr· Site Area Emergency has been declared· RP estimates that it will take approximately 15 minutes to complete

emergency actions and stop the release and all RP requiredcontrols/authorizations are complete

· Air Purifying Respirator with Iodine Canister having a protection factor of 1.0will be used in place of a SCBA due to piping interference

· EOF, OSC, and TSC are being staffed but are NOT operational· You ARE the SHIFT MANAGER

INITIATING CUE:

Determine if KI, Potassium Iodide, should be issued and complete necessarypaperwork, using OP 1903.035.


A1JPM-SRO-EAL16A9

Page 1 of 5

Unit: 1 Rev # 4 Date:

JPM ID: A1JPM-SRO-EAL16

System/Duty Area: Administrative Topic – Emergency Procedures/Plan

Task: Classify an Emergency Event

JTA# ANO-SRO-EPLAN-EMERG-278

KA Value RO 2.9 SRO 4.6 KA Reference: 2.4.41

Approved For Administration To: RO SRO X

Task Location: Inside CR Outside CR Both X

Suggested Testing Environment and Method (Perform or Simulate ):

Plant Site: Simulator: Classroom: Perform

Position Evaluated: RO: SRO: X

Actual Testing Environment: Plant Site Simulator Classroom X

Testing Method: Perform X Simulate

Approximate Completion Time in Minutes: 15 Minutes

Reference(s): 1903.010 EAL Classification

Examinee's Name: Logon ID:

Evaluator's Name:

The Examinee's performance was evaluated against the standards contained in this JPM and is determined to be:

Satisfactory: Unsatisfactory:

Performance Checklist Comments:


*Signed Robert Possage Date

*Signature indicates this JPM has been compared to its applicable procedure by a qualified individual (not the examinee)and is current with that revision.


A1JPM-SRO-EAL16A9

Page 2 of 5




· There are no Security Events in progress.· Unit 1 is in cold shutdown MODE 5 for an unplanned outage.· “A” Decay Heat pump is in service.· #2 EDG is out of service for generator excitation repair work.· A loss of offsite power occurs.· #1 EDG autostarts, but immediately trips on low lube oil pressure.· Unit 2 trips on loss of offsite power and is experiencing some post trip difficulties.· 15 minutes has elapsed since the loss of offsite power. Unit 2 has been requested to supply

the AAC generator but they have not completed the request.

TASK STANDARD:

Examinee correctly classifies this event (within 15 minutes of the completion of reading the initiatingcue to the examinee) as an ALERT per CA5, Loss of all offsite and onsite AC power to vital 4.16 KVbusses ≥ 15 minutes.


1903.010 Emergency Action Level Classification procedure

THIS IS A TIME CRITICAL JPM.

Instructor Note: Read the Initiating Cue and record start time. The clock start time begins afterthe Initiating Cues have been read and acknowledged using three part communication (EN-TQ-114 Attachment 9.5).


A1JPM-SRO-EAL16A9

Page 3 of 5

JPM ID: A1JPM-SRO-EAL16

INITIATING CUE: For the given plant conditions, determine the applicable EAL classification.

C PERFORMANCE CHECKLIST STANDARD N/A SATUNSAT

1. If EAL classification is known, then proceed toappropriate tab or location on EAL Matrix Chart.

Proceeded to Tab C, ColdShutdown/Refueling SystemMalfunction section of1903.010 or on EAL MatrixChart.

____ ____ ____

2. If EAL classification is not known, thencompare the abnormal conditions with thoselisted in Attachment 1 "Index of EmergencyAction Levels" or on EAL Matrix Chart.

Turned to Attachment 1 of1903.010, Index of EALs orreviewed EAL Matrix Chart.

____ ____ ____

3. Turn to the appropriate tab which correspondsto the condition picked from the Index of EALs oron EAL Matrix Chart.

Proceeded to Tab C, ColdShutdown/Refueling SystemMalfunction section of1903.010 or on EAL MatrixChart.

____ ____ ____

C

4. Assess the information available from validindications or reports. Turn to appropriate EALand compare EAL criteria with event conditions.Also review any related EALs.

Turned to the specific EAL inTab C, ColdShutdown/Refueling SystemMalfunction section of1903.010 or on EAL MatrixChart.

____ ____ ____

C

5. Declare the Emergency Classification. Declared an “ALERT” inaccordance with CA5, Loss ofall offsite and onsite AC powerto vital 4.16 KV busses ≥ 15minutes (Must be completedwithin 15 minutes of beinggiven the initial conditions).

____ ____ ____

EXAMINER’s CUE: This concludes the JPM.

END


A1JPM-SRO-EAL16A9

Page 4 of 5

KEY


INITIAL CONDITIONS:

· There are no Security Events in progress.· Unit 1 is in cold shutdown MODE 5 for an unplanned outage.· “A” Decay Heat pump is in service.· #2 EDG is out of service for generator excitation repair work.· A loss of offsite power occurs.· #1 EDG autostarts, but immediately trips on low lube oil pressure.· Unit 2 trips on loss of offsite power and is experiencing some post

trip difficulties.· 15 minutes has elapsed since the loss of offsite power. Unit 2 has

been requested to supply the AAC generator but they have notcompleted the request.

INITIATING CUE:

For the given plant conditions, determine the applicable EALclassification.

TIME BEGINS NOW Record Start Time ________

EAL Number __CA5_______

Description Loss of all offsite and onsite power to vital 4.16 KVbusses > 15 minutes.

NRC Record Finish Time _________


A1JPM-SRO-EAL16A9

Page 5 of 5

Applicant’s Copy


INITIAL CONDITIONS:

· There are no Security Events in progress.· Unit 1 is in cold shutdown MODE 5 for an unplanned outage.· “A” Decay Heat pump is in service.· #2 EDG is out of service for generator excitation repair work.· A loss of offsite power occurs.· #1 EDG autostarts, but immediately trips on low lube oil pressure.· Unit 2 trips on loss of offsite power and is experiencing some post

trip difficulties.· 15 minutes has elapsed since the loss of offsite power. Unit 2 has

been requested to supply the AAC generator but they have notcompleted the request.

INITIATING CUE:

For the given plant conditions, determine the applicable EALclassification.

TIME BEGINS NOW Record Start Time ________

EAL Number _________

Description ____________________________________________

NRC Record Finish Time _________

SIMULATOR JOB PERFORMANCE MEASURE Page 1 of 6

A1JPM-RO-CRD04S1

UNIT: 1 REV # 0 DATE: ___________________

SYSTEM/DUTY AREA: Control Rod Drive System

TASK: Perform Transfer of Group 6 Rods to Auxiliary Power Supply

JTA#: ANO1-RO-CRD-NORM-12

KA VALUE RO: 3.3 SRO: 3.3 KA REFERENCE: 001 A4.07




PLANT SITE _____________ SIMULATOR: Perform LAB:__________


ACTUAL TESTING ENVIRONMENT: SIMULATOR: X PLANT SITE:____ ______ LAB:________



REFERENCE(S): 1105.009 CRD System Operating Procedure, Section 8.0 Transfer to Auxiliary Supply

______________________________________________________________________


EVALUATOR'S NAME:__________________________________________________________________




___________________________________________________________________________________

___________________________________________________________________________________

___________________________________________________________________________________





A1JPM-RO-CRD04S1



JPM INITIAL TASK CONDITIONS: The ICS is in manual per 1105.004 Section 7.0, Transferring ICS

Control Stations to HAND. Group 7 is NOT aligned to the Auxiliary Supply.

TASK STANDARD: Group 6 rods have been transferred to the Auxiliary Power Supply and are

enabled for being moved on that power supply in run speed.

TASK PERFORMANCE AIDS: Copy of 1105.009 Section 8.0.

Simulator Setup: IC-222


A1JPM-RO-CRD04S1

JPM ID: A1JPM-RO-CRD02

INITIATING CUE: The CRS/SM directs you to transfer Group 6 Rods to the Auxiliary Power Supply for movement of Group 6 at runspeed in accordance with 1105.009 Section 8.0.


INSTRUCTOR NOTE: Verify ICS in HAND per 1105.004 Section 7.0.

EXAMINER NOTE: Step 8.1.1 is not applicable. Step 8.1.3 was completed as part of the setup for the JPM.

8.1.2 CHECK the following:

· TRANS RESET lamp lit· TR CF lamp off

POSITIVE CUE:

Transfer reset lamp is ON and TR CF lamp isOFF.

On CRD Diamond Panel, thestatus of both lights waschecked. The transfer resetlamp was ON and TR CFlamp was OFF.

____ ____ ____

C

8.2 PLACE GROUP SELECT SWITCH todesired Group 1-8.

POSITIVE CUE:

Group select switch is in Group 6 position.

On CRD Diamond Panel,Group Select Switch wasplaced in Group 6 position. ____ ____ ____

C

8.3 PLACE SINGLE SELECT SWITCH todesired CRDM: 1-12 or ALL.

POSITIVE CUE:

Single Select Switch is at ALL position.

On CRD Diamond Panel,Single select switch wasselected to ALL.

____ ____ ____

C

8.4 PLACE AUTO-MANUAL switch toMANUAL.

POSITIVE CUE:

Manual lamp is ON.

On CRD Diamond Panel,verified manual lamp on orAuto/Manual pushbuttondepressed to selectMANUAL.

____ ____ ____

C

8.5 PLACE SEQ-SEQ OR switch to SEQ OR.

POSITIVE CUE:

SEQ OR backlight lamp is ON.

On CRD Diamond Panel,SEQ.- SEQ OR. switch wasselected to SEQ OR position. ____ ____ ____

C

8.6 PLACE GROUP-AUXIL switch to AUXIL.

POSITIVE CUE:

AUX PB backlight is ON.

On CRD Diamond Panel,Group/AUX PB was selectedto AUX. ____ ____ ____


A1JPM-RO-CRD04S1


EXAMINER NOTE: Step 8.7.1 and 8.10 are not applicable.

C

8.7 PLACE SPEED SELECTOR switch to JOG.

POSITIVE CUE:

SY backlight is ON.

On CRD Diamond Panel,Speed Select Switch wasselected to JOG position. ____ ____ ____

C8.8 PLACE CLAMP-CLAMP REL switch to

CLAMP.

POSITIVE CUE:

CLAMP CONFIRM (amber) light is on.

On CRD Diamond Panel,selected Clamp/ClampRelease Switch to CLAMP. ____ ____ ____

C

8.9 DEPRESS MAN TRANS switch andRELEASE.

POSITIVE CUE:

Group 6 Control on White lights on the PI Panelare on.

On CRD Diamond Panel,manual transfer PB wasdepressed. ____ ____ ____

C

8.11 PLACE CLAMP-CLAMP REL switch toCLAMP REL.

POSITIVE CUE:

Clamp Release and Clamp Release Confirm lightsare on.

NEGATIVE CUE:Group 6 Rods will not move.

On CRD Diamond Panel,depressed Clamp/ClampRelease Switch. ____ ____ ____

8.12 PLACE GROUP-AUXIL switch to GROUP.

POSITIVE CUE:

SY backlight is off.


On CRD Diamond Panel,Group/ AUX PB was selectedto Group.

____ ____ ____

C

8.13 IF movement at RUN speed is desired,THEN PLACE speed switch to RUN.

POSITIVE CUE:

SY backlight is off. Rods will move in RUN speed.


On CRD Diamond Panel,Speed Select Switch wasselected to RUN position.

____ ____ ____

END


A1JPM-RO-CRD04S1

JPM ID: A1JPM-RO-CRD02

INITIAL CONDITIONS:

The ICS is in manual per 1105.004, Integrated Control SystemSection 7.0 “Transferring ICS Control Stations to HAND.”

Group 7 is NOT aligned to the Auxiliary Supply

INITIATING CUE:

The CRS/SM directs you to transfer Group 6 Rods to theAuxiliary Power Supply for movement of Group 6 at RUN speedin accordance with 1105.009 Section 8.0.


A1JPM-RO-CRD04S1

Applicant’s Copy

INITIAL CONDITIONS:

The ICS is in manual per 1105.004, Integrated Control SystemSection 7.0 “Transferring ICS Control Stations to HAND.”

Group 7 is NOT aligned to the Auxiliary Supply

INITIATING CUE:

The CRS/SM directs you to transfer Group 6 Rods to theAuxiliary Power Supply for movement of Group 6 at RUN speedin accordance with 1105.009 Section 8.0.


A1JPM-RO-EOP13S2

UNIT: 1 REV # 9 DATE: ___________________

SYSTEM/DUTY AREA: Emergency and Abnormal Operations

TASK: Perform Emergency Boration

JTA#: ANO1-RO-EOP-EMERG-55


APPROVED FOR ADMINISTRATION TO: RO: X SRO: X








REFERENCE(S): 1202.012 Repetitive Tasks (RT-12 Emergency Boration and RT-2 Initiate HPI)

______________________________________________________________________


EVALUATOR'S NAME:__________________________________________________________________




___________________________________________________________________________________

___________________________________________________________________________________

___________________________________________________________________________________





A1JPM-RO-EOP13S2



JPM INITIAL TASK CONDITIONS: Reactor Power is at 60% and the CRS directs you to trip the

reactor. Two control rods failed to insert upon a reactor trip.

TASK STANDARD: Boric acid is being injected into the RCS by the OP or STBY HPI pump from the

BWST with one HPI Block Valve fully opened.

TASK PERFORMANCE AIDS: Copy of 1202.012, RT-12 Emergency Boration and RT-2 Initiate HPI

This is an Alternate Path JPM

SUGGESTED SIMULATOR SETUP:

· Fail CV-1250 in the closed position; this forces the alternate option for Emergency Boration· Trip the reactor from an at-power IC with two control rods stuck out at 100%.· Minimize letdown· Ensure BWST outlet to Operating Makeup Pump is closed (CV-1407/CV-1408).

Simulator setup: IC-223


A1JPM-RO-EOP13S2

JPM ID: A1JPM-RO-EOP13

INITIATING CUE: The CRS/SM directs you to perform Emergency Boration per RT-12.


EXAMINER NOTE: RT-12 Step 1.A. third bullet states to “GO TO step 2 if an unexpected delay occurs inimplementation of Step 1.”

B. Set Batch Controller for maximum batchsize as follows:

POSITIVE CUE:Batch Controller set to add 999999 gallons.

-Depressed lower DISPLAY key.-Depressed TOTAL key.-Depressed TOTAL RESET key.-Depressed BATCH SET key.-Depressed 999999.-Depressed ENTER key.-Depressed lower DISPLAY key.

____ ____ ____

C. Verify Condensate to Batch Controller(CV-1251) closed.

POSITIVE CUE:Green light ON, red light OFF.

On C04, verified Condensate toBatch Controller (CV-1251)closed. ____ ____ ____

D. Open Batch Controller Outlet (CV-1250).

FAULTED CUE (ALTERNATE PATH):CV-1250 green light ON and red light OFF.

On C04, attempted to open BatchController Outlet CV-1250;identified that CV-1250 failed toopen.

____ ____ ____

EXAMINER NOTE: RT-12 directs that the applicant to go to Step 2 and Initiate Emergency Boration usingHPI per RT-2EXAMINER NOTE: Step 1 of RT-2 will be N/A (Letdown will not be isolated due to performing EmergencyBoration).

2. IF OP or STBY HPI pump is running,THEN perform the following:

POSITIVE CUE:OP HPI pump is running.

Continue on

____ ____ ____

C

A. Verify BWST Outlet to the OP or STBYHPI pump (CV-1407 or CV-1408).

POSITIVE CUE:Red light ON, green light OFF.

Opened BWST Outlet to the OP orSTBY HPI pump CV-1408.

____ ____ ____


A1JPM-RO-EOP13S2


B. IF RCP Seal Injection is in service,THEN place RCP Seal INJ Block (CV-1206) in OVRD.

POSITIVE CUE:CV-1206 in OVRD.

On C04, placed RCP Seal INJ Block(CV-1206) in OVRD.

____ ____ ____

C

C. WHEN associated BWST Outlet isopen, THEN open HPI Block valveassociated with OP or STBY HPI pump (CV-1220 or CV-1285) to maintain PZR level andRCS pressure.


Opened HPI Block valve associatedwith the OP or STBY HPI pumpCV-1285.

____ ____ ____

EXAMINER NOTE: Examinee will now leave RT-2 and go to RT-12 Step 2.B.

B. Verify HPI Block valve (CV-1220 or CV-1285) associated with running HPIpump open.


Verified HPI Block valve CV-1285associated with running HPI pumpopen.

____ ____ ____

CC. IF Letdown is in service, THEN place 3-

Way valve (CV-1248) in BLEED.

POSITIVE CUE:Blue light ON, red light OFF.

Placed 3-Way valve in the BLEEDposition on C04.

____ ____ ____

EXAMINER CUE: If PZR level is less than 100 inches then inform Examinee that PZR level is 110 inches and slowlyrising.

D. WHEN PZR level is ≥ 100 inches, THENestablish maximum Letdown flow allowed bycooling capacity and component limitations.

POSITIVE CUE:Letdown flow is maximized.

NEGATIVE CUE:Letdown flow is 40 gpm.

On C04, adjusted CV-1223 to raiseLetdown flow to at least 60-120 gpm.

____ ____ ____

END


A1JPM-RO-EOP13S2

JPM ID: A1JPM-RO-EOP13

INITIAL CONDITIONS:

· Reactor Power at 60% power

INITIATING CUE:

· CRS directs you to trip the reactor and carry out yourimmediate actions.


A1JPM-RO-EOP13S2

Applicant’s Copy

INITIAL CONDITIONS:

· Reactor Power at 60% power

INITIATING CUE:

· CRS directs you to trip the reactor and carry out yourimmediate actions.


A1JPM-RO-ESAS1S3

Unit: 1 Rev # 6 Date: 3/9/2016

JPM ID: A1JPM-RO-ESAS1

System/Duty Area: ENGINEERED SAFEGUARDS ACTUATION SYSTEM

Task: Verify Proper ESAS Actuation (and Perform ESAS Operation After Actuation)

JTA# ANO1-RO-ESAS-NORM-5

KA Value RO 4.5 SRO 4.8 KA Reference 013 A4.01

Approved For Administration To: RO X SRO X

Task Location: Inside CR: X Outside CR: Both:

Suggested Testing Environment And Method (Perform or Simulate ):

Plant Site: Simulator: Perform Lab:

Position Evaluated: RO: SRO:

Actual Testing Environment: Simulator : Plant Site: Lab:

Testing Method: Simulate: Perform:

Approximate Completion Time In Minutes: 15 Minutes

Reference(s): 1202.012, RT-10, Verify proper ESAS actuation (Revision 17)

Examinee's Name: ID:

Evaluator's Name:

The Examinee's performance was evaluated against the standards contained in this JPM and is determined to be:

Satisfactory: Unsatisfactory:

Performance Checklist Comments:


*Signed Robert Possage Date:*Signature indicates this JPM has been compared to its applicable procedure by a qualified individual (not the examinee)and is current with that revision.


A1JPM-RO-ESAS1S3



The examiner shall ensure that the examinee has been briefed on the JPM Examination BriefingSheet EN-TQ-114 Attachment 9.5 or NUREG 1021 Appendix E.


ESAS has actuated on low RCS pressure.Reactor Coolant Pumps have been tripped due to LOSM.CV-1206 (RCP Seal INJ Block) is open in OVRD.

TASK STANDARD:

LPI Pump P-34B must be securedHPI Block valve CV-1278 throttled back so that its flow is within ~20 gpm of the next highest flow HPI flow.

This is an alternate success path JPM.


1202.012, RT-10, Verify proper ESAS actuation.


Use IC-285.

Align P-36C as the ES Pump and P-36A as OP HPI Pump.IMF CV1408 (CV-1408 fails to open on ESAS CH 2 and 4)Place CV-1206 in override and verify open.IMF RC462 2.5 (RCS leak downstream of MU45A) (RCS leak causes ESAS to actuate on low RCS pressure.CV-1278 will have to be throttled back to within 20 gpm of the next highest HPI flow).Trip all RCPs.Verify that CV-1278 should be throttled per RT10.Snapshot can now be made.

Revision 6 Note:Added failure of CV-1408 to make the JPM have more than one critical step.Updated for procedure revision.


A1JPM-RO-ESAS1S3


INITIATING CUE: The SM/CRS directs you to perform RT-10 (Verify proper ESAS actuation).


1. Verify BWST Outlets open:· CV-1407· CV-1408).

NEGATIVE CUE:CV-1407 has red light ON, green light OFF.CV-1408 had green light ON, red light OFF.

On panel C16 recognized CV-1408 closed. On panel C18verified CV-1407 open.

____ ____ ____

EXAMINER CUE: Acknowledge that the applicant has ask permission to override and stop P-34B and P-36C

C A. IF BWST T3 Outlet (CV-1407 orCV-1408) fails to open,THEN override AND stop associatedHPI, LPI, and RB Spray pumps untilfailed valve is opened:

POSITIVE CUE:HPI, LPI, and RB Spray pumps in override andstopped as appropriate.

On panel C16 placed P-34Band P-36C in override andstopped.

P-35B does not have anactuation signal and istherefore N/A

____ ____ ____

2. Verify service water to DG1 and DG2 coolersopen:

· CV-3806· CV-3807

POSITIVE CUE:Red lights ON, green lights OFF for CV-3806 andCV-3807.

On panel C19, verified servicewater to DG1 and DG2 coolersopen, CV-3806 and CV-3807.

____ ____ ____

EXAMINER NOTE: Step 3. of RT10 is N/A due to RCPs off.

3. IF any RCP is running, THEN perform thefollowing:

POSITIVE CUE:All RCPs are off.

N/A, all RCPs were secureddue to LOSM.

____ ____ ____


A1JPM-RO-ESAS1S3


4. Verify proper ESAS channels tripped.

POSITIVE CUE:Channels 1, 2, 3 and 4 are tripped.

Verified that ESAS Channels1-4 are tripped by observingthat annunciators K11-A2 (HPIChannel 1), K11-A3 (HPIChannel 2), K11-B2 (LPIChannel 3) and K11-B3 (LPIChannel 4) in alarm or byobserving appropriatecomponents have repositionedon C16 and C18.

____ ____ ____

5. Perform the following:A. Verify each component properlyactuated on C16 and C18, except thoseoverridden in previous steps.B. Verify proper ES system flow rates.

1. IF any of the following conditionsexist:

· A HPI FLOW HI/LO (K11-A4)· B HPI FLOW HI/LO (K11-A5)· A LPI FLOW HI/LO (K11-B4)· B LPI FLOW HI/LO (K11-B4)· A RB SPRAY FLOW HI/LO (K11-

C4)· B RB SPRAY FLOW HI/LO (K11-

C5)

POSITIVE CUE:All ES components on C16 and C18 are in theirproper position except P-34B and P-36C.

On panels C16/18, verifiedeach component in its properES position except that P-36Cand P-34B are off.

____ ____ ____

EXAMINER NOTE: The only ES flows that are in service at this time will be HPI flow from the A HPI pumpP-36A. RCS pressure is too high for LPI flow and RB Spray has not actuated. LPI flow low alarm cannot becorrected by ACA at current RCS pressure.


A1JPM-RO-ESAS1S3


EXAMINER CUE: Acknowledge that the applicant has ask permission to override and throttle closed onCV-1278

(C)

5.C. If only one train of HPI is available

AND RCS press is > 600 psig, THENthrottle HPI Block valve with the highestflow to within 20 gpm of the next highestflow.

POSITIVE CUE:MAN switch backlit (White).All HPI flows from P-36A are within 20 gpm ofeach other.

NEGATIVE CUE:AUTO switch backlit (Red).ESAS components are not properly adjusted.

On panel C18, depressedMAN pushbutton associatedwith CV-1278. Throttled HPIblock valve CV-1278 back sothat its flow is within ~20 gpmof the next highest flowindicated on FIRS-1209 (onC18) or on SPDS HPI P-36ADiagnostic screen.

____ ____ ____

EXAMINER CUE: Notify applicant that the JPM is complete after he balances flow per the standardabove.

NOTES:_________________________________________________________________________________

________________________________________________________________________________________

________________________________________________________________________________________

________________________________________________________________________________________

________________________________________________________________________________________

END


A1JPM-RO-ESAS1S3


INITIAL CONDITIONS:

ESAS has actuated on low RCS pressure.Reactor Coolant Pumps have been tripped due to LOSM.CV-1206 (RCP Seal INJ Block) is open in OVRD.

INITIATING CUE:

The SM/CRS directs you to perform RT10 (Verify proper ESASactuation).

SIMULATOR JOB PERFORMACE MEASURE Page 1 of 8

A1JPM-RO-RCP04S4

UNIT: 1 REV # 6 DATE: ___________________

SYSTEM/DUTY AREA: Reactor Coolant System

TASK: Shutdown RCP P-32A at Power

JTA#: ANO1-RO-RCP-NORM-3










REFERENCE(S): 1103.006 RCP Operation (Section 11.0)

______________________________________________________________________


EVALUATOR'S NAME:__________________________________________________________________




___________________________________________________________________________________

___________________________________________________________________________________

___________________________________________________________________________________





A1JPM-RO-RCP04S4



JPM INITIAL TASK CONDITIONS: Reactor power is <60% steady state with four RCPs running.

RCP P-32A must be secured due to a significant oil leak.

TASK STANDARD: P-32A secured, reactor manually tripped and ALL RCPs tripped.

TASK PERFORMANCE AIDS: Copy of 1103.006 RCP Operations Section 11.0.

This is an alternate success path JPM


Power 60%P-8B securedLow Level Condenser Sprays (HS-2907) openMalfunction: RC466 RCP ‘A’ Anti Reverse Rotation Device Failure

Simulator setup: IC-223


A1JPM-RO-RCP04S4

JPM ID: A1JPM-RO-RCP04

INITIATING CUE: The CRS/SM directs you to stop the “A” RCP per 1103.006 Section 11.0 (starting at Step 11.7.1).


NOTEPMS Computer alarm BACKSTOP LO FLOW will not clear until BOTH backstop oil pumps are running withadequate flow. (not applicable for P-32B)

CAUTION· Single RCP operation in excess of 2 minutes can cause pump damage due to inadequate flow through

the hydrostatic bearing.· Simultaneous operation of the Normal and Emergency HP Oil Lift Pump (P-63 and P-80) can result in

reduced oil pressure and lift pump cavitation.

11.7 PERFORM the following to stop RCP(s):

11.7.1 IF stopping Reactor Coolant Pump(P-32A), THEN:

POSITIVE CUE:P-32A is the pump to stop/

No action to take, continue onwith the step. ____ ____ ____

A. START ONE HP Oil Lift Pump:

· HP Oil Lift Pump (P-63A)

· Emergency HP Oil Lift Pump (P-80A)

POSITIVE CUE:Red light ON, green light OFF for P-63A (or P-

80A).

On panel C13, started HP Oil LiftPump (P-63A) OR Emergency HPOil Lift Pump (P-80A).

____ ____ ____

B. PLACE pump NOT started inPULL-TO-LOCK:

· HP Oil Lift Pump (P-63A)

· Emergency HP Oil Lift Pump (P-80A)

POSITIVE CUE:Pump in Pull to Lock.

On panel C13, placed HP Oil LiftPump NOT started in Pull to Lock(P-63A OR P-80A).

____ ____ ____


A1JPM-RO-RCP04S4


C. START BOTH Backstop Oil Pumps:

· Backstop Lube Oil Pump (P-81A)

· Backup Backstop Lube Oil Pump(P-82A)

POSITIVE CUE:Red light ON, green light OFF for P-81A and P-82A.

On panel C13, started bothBackup Backstop Lube Oil Pumps(P-81A and P-82A).

____ ____ ____

D. At PMS Computer, CHECK backstop oilflow:

· For P-81A, PMS point FS6520indicates RUNNING

· For P-82A, PMS point FS6525indicates RUNNING

POSITIVE CUE:PMS points FS6520 and FS6525 indicateRUNNING

Verified on PMS that pointsFS6520 and FS6525 have astatus of running. ____ ____ ____

C

E. STOP Reactor Coolant Pump P-32A.

POSITIVE CUE:Green light ON, red light OFF for P-32A. RCSflow lowering in the “B” RCS Loop.

NEGATIVE CUE:Red light ON, green light OFF for P-32A. RCSflows are matched.

On panel C13, stopped RCPP-32A.

____ ____ ____

EXAMINER NOTE: Step F is not applicable.Steps 11.7.2, 11.7.3, and 11.7.4 are for stopping RCP-32B, C, and D and are not applicable.

11.8 During RCP coast down, ENSURE oilpumps running:

POSITIVE CUE:Red lights ON, green lights OFF for P-63A and P-

81A.

Verified HP Oil Lift Pump (P-63Aor P-80A) and Backstop Lube OilPumps (P-81A and P-82A)remained on during P-32A coastdown.

____ ____ ____


A1JPM-RO-RCP04S4



EXAMINER CUE: If asked inform applicant that the installed backup indication is NOT at zero speed.If asked inform the applicant that vibrations and temperature are indicating abnormally high values

11.9 PERFORM the following to check RCP shafthas stopped and NO reverse rotation:

· IF accessible AND directed by CRS,THEN CHECK shaft stopped locally atRCP.

· IF directed by CRS, THEN CHECK zerospeed with portable instrumentation perAttachment H, RCP Zero SpeedDetection Portable Equipment Use.

· CHECK PMS Computer reverse rotationalarm remains clear.(not applicable to P-32B)

- RCP P32-D REVERSE ROTATION(FS6513)

- RCP P32-C REVERSE ROTATION(FS6512)

- RCP P32-A REVERSE ROTATION(FS6510)

· CHECK associated loop RCS flow stopsdropping and stabilizes to expected valuefor number of pumps running.

· CHECK RCP motor vibration normal.

· CHECK RCP motor bearing temperaturenormal.

FAULTED CUE(S):· Plant computer reverse rotation alarm FS6510

is in alarm.· Loop B flow lower than expected.· P-32A vibration is high, motor bearing temp is

high.

Performed steps to verify P-32Ashaft stopped, without reverserotation.

Determined that P-32A is rotatingin the reverse direction.

____ ____ ____


A1JPM-RO-RCP04S4


C

11.10 IF reverse rotation indicated, THEN:

11.10.1 TRIP the reactor.

POSITIVE CUE:Rod bottom lights all ON for groups 1-7, reactor powerdropping in the intermediate range on panel C03.

Depressed the Reactor Tripmanual pushbutton on panel C03.

____ ____ ____

C

11.10.2 PERFORM immediate actionsof 1202.001, Reactor Trip.

POSITIVE CUE:Turbine is tripped, all Turbine Throttle and GovernorValves are closed. Subcooling Margin is Adequate.

NEGATIVE CUE:Turbine is latched.

Depress the Turbine Trip manualpushbutton on panel C01 andverify Turbine Throttle andGovernor Valves Closed.

Verify Subcooling MarginAdequate (>50 F)

____ ____ ____

C

11.10.3 TRIP running RCP(s).

POSITIVE CUE:Green lights ON, red lights OFF for tripped RCPs.

NEGATIVE CUE:P-32A vibration is high and rising.

On panel C13, tripped RCPsP-32B, P-32C and P-32D.

____ ____ ____

EXAMINER CUE: The next step in the Reactor Coolant Pump Operation procedure states “GO TO Emergency OperatingProcedure (1202.XXX series).” Tell the Examinee that the crew will perform the remainder of the Reactor Trip procedure– JPM is complete.

END


A1JPM-RO-RCP04S4


INITIAL CONDITIONS:

· Dispatcher is cognizant of current turbine loading.· Reactor power is 60% steady state with four RCPs on.· RCP P-32A must be secured due to a significant oil leak.

INITIATING CUE:

The CRS/SM directs you to stop the “A” RCP per 1103.006Section 11.0. (starting at Step 11.7.1)


A1JPM-RO-RCP04S4

Applicant’s Copy

INITIAL CONDITIONS:

· Dispatcher is cognizant of current turbine loading.· Reactor power is 60% steady state with four RCPs on.· RCP P-32A must be secured due to a significant oil leak.

INITIATING CUE:

The CRS/SM directs you to stop the “A” RCP per 1103.006Section 11.0. (starting at Step 11.7.1)


A1JPM-RO-HYD03S5

UNIT: 1 REV # 3 DATE: ___________________

SYSTEM/DUTY AREA: Hydrogen Recombiner and Purge Control System

TASK: Place Hydrogen Recombiner M55B in Operation

JTA#: ANO1-RO-RBH2-NORM-1










REFERENCE(S): 1104.031

______________________________________________________________________


EVALUATOR'S NAME:__________________________________________________________________




___________________________________________________________________________________

___________________________________________________________________________________

___________________________________________________________________________________





A1JPM-RO-HYD03S5



JPM INITIAL TASK CONDITIONS: A LOCA has occurred. Containment hydrogen concentration is

2.5%. Both Hydrogen Recombiners are shutdown. Containment pressure is 26.0 psia. Pre-LOCA

containment temperature was 120 oF.

TASK STANDARD: Hydrogen Recombiner M55B in operation at power setting of 67.0 KW to 69.0 KW

on JI-1001.

TASK PERFORMANCE AIDS: Copy of 1104.031 Section 8.0 and Attachment B2

Simulator Setup: IC-285· Place Hydrogen Samplers in service per 1104.031 Exhibit A.


A1JPM-RO-HYD03S5

INITIATING CUE: The CRS/SM directs you to place hydrogen recombiner (M55B) in operation.Note: Your task is complete when the power you have determined for recombiner operation is achieved.


CAUTIONTo stop buildup of explosive hydrogen, Hydrogen Recombiner, M-55A or M-55B is required to be operatingprior to hydrogen concentration reaching 3.0% as indicated on the highest reading hydrogen analyzer.

8.1.1 ENSURE Hydrogen Recombiner M-55BPower Adjust Potentiometer (HS-7473) isset at zero.

POSITIVE CUE:Power adjust potentiometer for M55B is set atzero on C26.

Verified power adjustpotentiometer set to zero onC26 (if not already at zeroused knurled knob on poweradjust potentiometer on C26and turned to the left and setat zero using HS-7473).

____ ____ ____

C

8.1.2 PLACE Hydrogen Recombiner M55Bhandswitch (HS-7471) to ON.

POSITIVE CUE:M55B red light ON.

NEGATIVE CUE:M55B green light ON.

Turned on hydrogenrecombiner M55B usingHS-7471 on C26. ____ ____ ____

CAUTIONSelecting OFF on Thermocouple Selector handswitch (HS-7475) causes excessive current in HydrogenRecombiner (M55B) Temperature (TI-2301) leading to frequent failure.

8.1.3 On Thermocouple Selector handswitch(HS-7475), ENSURE thermocouple #1, 2,or 3 is selected to input to HydrogenRecombiner (M55B) Temperature(TI-2301).

POSITIVE CUE:Thermocouple #1, 2 or 3 selected as desired toinput toTI-2301.

Thermocouple #1, 2 or 3selected to input to TI-2301using handswitch HS-7475 onC26.

____ ____ ____

C

8.1.4 Slowly TURN (slow enough to observe KWrise without overshooting) Power AdjustPotentiometer (HS-7473) clockwise to raisepower to 5 KW on M55B Power (JI-1001).

POSITIVE CUE:Power on JI-1001 indicates 5KW.

Slowly adjusted potentiometerclockwise until power onJI-1001 on C26 indicates~5 KW.

____ ____ ____


A1JPM-RO-HYD03S5


C

8.1.5 Slowly TURN (slow enough to observe KWrise without overshooting) Power AdjustPotentiometer (HS-7473) clockwise to raisepower to 10 KW on M55B Power (JI-1001).

A. RECORD initial time at 10 KW:__________.

B. MAINTAIN 10 KW output forheatup/standby service.

POSITIVE CUE:Power is at 10 KW on JI-1001.

Increased power to ~10 KWusing power adjustpotentiometer on C26.Recorded time 10 KW wasachieved.

____ ____ ____

EXAMINER CUE:· Inform examinee that taking data every 30 minutes on Attachment E will be simulated.· Inform examinee that ten minutes have elapsed after achieving 10 KW.8.2 Placing Hydrogen Recombiner (M-55B) into

Service:8.2.1 ENSURE Hydrogen Recombiner

(M-55B) has been at 10 KW for atleast 10 minutes.

POSITIVE CUE:Power at 10 KW on JI-1001 AND 10 minutes haveelapsed.

Acknowledge that 10 minuteshave elapsed

____ ____ ____

C

8.2.2 Slowly TURN (slow enough toobserve KW rise withoutovershooting) Power AdjustPotentiometer (HS-7473) clockwiseto raise power to 20 KW on M55BPower (JI-1001).

A. RECORD initial time at 20 KW:__________.

POSITIVE CUE:Power at 20 KW on JI-1001.

Increased power on M55B to~20 KW using power adjustpotentiometer on C26. ____ ____ ____

C

8.2.3 DETERMINE power required forContainment pressure perAttachment B2, Recombiner Power(M-55B) Versus ContainmentPressure.

A. KW setting __________

Determined Recombinerpower to be from 67.0 to 69.0KW using Attachment B of1104.031.

____ ____ ____

EXAMINER CUE:· Inform examinee that five minutes have elapsed after they have determined final power level.

CAUTIONRecombiner power greater than 75 KW and temperature greater than 1450°F could cause heater failure.


A1JPM-RO-HYD03S5


C

B. WHEN M-55B has been at 20 KW for 5minutes, THEN slowly TURN Power AdjustPotentiometer (HS-7473) clockwise to raisepower to the value determined above asindicated on M55B Power (JI-1001) whilemaintaining the following limits:· M55B Temperature (TI-2301) less

than 1450°F· M55B Power (JI-1001) less than 75

KW

POSITIVE CUE:Hydrogen concentration dropping on QI-7459 andM55B maintaining power at determined value.

NEGATIVE CUE:Hydrogen concentration rising or steady on QI-7459.

Power increased to 67.0 to69.0 KW range using poweradjust potentiometer on C26. ____ ____ ____

END


A1JPM-RO-HYD03S5

INITIAL CONDITIONS:

· A LOCA has occurred.· Containment hydrogen concentration is 2.5%.· Both hydrogen recombiners are shutdown.· Containment pressure is 26.0 psia.· Pre-LOCA containment temperature was 120°F.

INITIATING CUE:

The CRS/SM directs you to place hydrogen recombiner (M55B) inoperation.

Note: Your task is complete when the power you have determinedfor recombiner operation is achieved.


A1JPM-RO-HYD03S5

Applicant’s Copy

INITIAL CONDITIONS:

· A LOCA has occurred.· Containment hydrogen concentration is 2.5%.· Both hydrogen recombiners are shutdown.· Containment pressure is 26.0 psia.· Pre-LOCA containment temperature was 120°F.

INITIATING CUE:

The CRS/SM directs you to place hydrogen recombiner (M55B) inoperation.

Note: Your task is complete when the power you have determinedfor recombiner operation is achieved.


A1JPM-RO-EDG04S6

UNIT: 1 REV # 4 DATE: ___________________

SYSTEM/DUTY AREA: Emergency Diesel Generator (EDG) System

TASK: Parallel DG1 to the Grid

JTA#: ANO1-RO-EDG-NORM-10










REFERENCE(S): 1104.036 Emergency Diesel Generator Operations

______________________________________________________________________


EVALUATOR'S NAME:__________________________________________________________________




___________________________________________________________________________________

___________________________________________________________________________________

___________________________________________________________________________________





A1JPM-RO-EDG04S6



JPM INITIAL TASK CONDITIONS: DG1 is running with its output breaker open and its Service Waterinlet

valve (CV-3806) open.

TASK STANDARD: DG1 tripped due to its load continuing to rise uncontrollably.

TASK PERFORMANCE AIDS: Copy of 1104.036 Section 7.0 and Synch Switch Handle

This is an alternate success path JPM

SIMULATOR SETUP:

· Start VEF-24A and VEF-24B DG Room Exhaust Fans on C19.· Verify DG1 Volts Select switch NOT in OFF on C10.· Start DG1 on C10.· Verify CV-3806 open (SW to DG1).

When the DG1 output breaker is closed, then insert switch override C10 DI_DG1_GV_LW Lower,DG1, Governor Control to FALSE and insert switch override C10 DI_DG1_GV_RA Raise, DG1,Governor Control to TRUE which will fail the governor handswitch in the raise position, this willcause the DG1 load to rise without control.

· IOR DI_DG1_GV_LW False

· IOR DI_DG1_GV_RA True



A1JPM-RO-EDG04S6

INITIATING CUE: The CRS/SM directs you to parallel DG1 to the grid and load DG1 to ~2750 KW starting at 1104.036Step 7.9.5. All procedural steps from 7.1 through 7.9.4 have been performed and/or acknowledged for DG1.


C

7.9.5 PLACE Synchronize switchfor DG1 Output Breaker A-308 toON.

POSITIVE CUE:Incoming and running voltmetersindicating; synchroscope rotating.

NEGATIVE CUE:Synchroscope off.

On C10, placed Synchronizeswitch for breaker A-308 to ONposition.

____ ____ ____

NOTESPDS points (E1A3), ES Bus A3 voltage (Running) and (E1DG1), DG1 voltage (Incoming) can be used ascomparison points.

7.9.6ADJUST DG1 voltageregulator (INCOMING) to eithermatch or be no greater than 20 voltsof A3 (Running) voltage.

POSITIVE CUE:INCOMING and RUNNING voltagesare matched.

NOTE: Voltages may be verifiedmatched on C10 or SPDS or onplant computer.

On C10, adjusted DG1 voltageregulator control switch to matchINCOMING voltage to within arange of RUNNING voltage -0/+20volts. ____ ____ ____

EXAMINER CUE: The procedure calls for a peer check of voltage comparison. Provide feedback that a peer checkhas been received.

C

7.9.7ADJUST DG1 governorcontrol until frequency is 60 Hz withsynchroscope rotating slowly inFAST direction (clockwise).

POSITIVE CUE:Frequency ~60 Hz, synchroscoperotatingslowly in FAST direction.

NEGATIVE CUE:Synchroscope rotating in the SLOWdirection.

On C10, adjusted DG1 governorcontrol switch to achievefrequency at ~60 Hz withsynchroscope rotating slowly inFAST direction (clockwise). ____ ____ ____

CONTINUED


A1JPM-RO-EDG04S6


NOTE: IA Operator ® When the Applicant goes to raise load, then insert switch override C10 DI_DG1_GV_LWLower, DG1, Governor Control to FALSE and insert switch override C10 DI_DG1_GV_RA Raise, DG1, GovernorControl to TRUE which will fail the governor handswitch in the raise position, this will cause the DG1 load to risewithout control.

· IOR DI_DG1_GV_LW False· IOR DI_DG1_GV_RA True

NOTE· If synchroscope is rotating too fast, sync-check relay will prevent breaker from closing.

· Gradual and uniform load changes minimize engine wear and internal stresses. A 100% load change to 2750KW, typically takes 90 sec. Longer loading times are acceptable when delays are caused by reactive loadadjustments or equipment monitoring.

CAUTIONA delay in loading diesel after closing output breaker can result in generator motoring which causes lockout relay toactuate, tripping DG output breaker and shutdown of the engine.

C

7.9.8 As synchroscopeapproaches 12 o’clock position (5min. ‘til) CLOSE DG1 OutputBreaker (A-308).

POSITIVE CUE:A-308 red light ON, green light OFF.

On C10, closed DG1 Output BreakerA-308.

____ ____ ____

EXAMINER NOTE: ***Alternate Path begins here***

C

7.9.8A. Using DG1 governor control,

RAISE load to 2625 to 2750KW.

POSITIVE CUE:DG1 green light ON, red light OFF.

NEGATIVE CUE:DG1 load rising without signal / demandpresent.

On C10, begin raising load with thegovernor control switch.

____ ____ ____

C

5. Operator identifies uncontrollablerising load and trips DG1.

POSITIVE CUE:DG1 green light ON, red light OFF.

NEGATIVE CUE:DG1 load at 2800 KW and rising.

On C10, tripped DG1 (stoppushbutton or to lockout).

____ ____ ____

END


A1JPM-RO-EDG04S6

JPM ID: A1JPM-RO-EDG04

INITIAL CONDITIONS:

DG1 is running with its output breaker open and its servicewater inlet valve (CV-3806) open.

INITIATING CUE:

The CRS/SM directs you to parallel DG1 to the grid and loadDG1 to ~2750 KW starting at 1104.036 Step 7.9.5. All proceduralsteps from 7.1 through 7.9.4 have been performed and/oracknowledged for DG1.


A1JPM-RO-EDG04S6

Applicant’s Copy

INITIAL CONDITIONS:

DG1 is running with its output breaker open and its servicewater inlet valve (CV-3806) open.

INITIATING CUE:

The CRS/SM directs you to parallel DG1 to the grid and loadDG1 to ~2750 KW starting at 1104.036 Step 7.9.5. All proceduralsteps from 7.1 through 7.9.4 have been performed and/oracknowledged for DG1.


A1JPM-RO-RPS06S7

UNIT: 1 REV # 0 DATE: ___________________

SYSTEM/DUTY AREA: Reactor Protection System

TASK: Reset RPS Channel “A”

JTA#: ANO1-RO-RPS-NORM-7










REFERENCE(S): 1105.001 NI & RPS Operating Procedure

______________________________________________________________________


EVALUATOR'S NAME:__________________________________________________________________




___________________________________________________________________________________

___________________________________________________________________________________

___________________________________________________________________________________





A1JPM-RO-RPS06S7



JPM INITIAL TASK CONDITIONS: Plant at any power level with no EFIC or RPS channels in bypass.

Channel A tripped with Building Pressure Contact Buffer lights lit.

TASK STANDARD: RPS Channel “A” reset

TASK PERFORMANCE AIDS: Copy of 1105.001 Section 7.0.



A1JPM-RO-RPS06S7

JPM ID: A1-JPM-RO-RPS05

INITIATING CUE: The CRS directs you to Reset RPS Channel “A” in accordance with 1105.001 Section 7.0


EXAMINER NOTE: Step 7.1 is not applicable.

7.2.1 ENSURE ALL Test modules are inOPERATE with the On Test lamps dimly lit.

POSITIVE CUE:All Test modules are in the OPERATE position.All On Test lamps dim

Observed all Test modules arein the OPERATE position.

(Source Range Test, ContactMonitor Test, Flow Test, WideRange Temperature Test,Power Range Test, PressureTest, and Temperature Test)

____ ____ ____

7.2.2 IF any bistables have Output State and/orOutput Memory lamps are brightly lit,THEN:

· PLACE Output State toggle switch inRESET and RELEASE.

· PLACE Output Memory toggle switchin RESET and RELEASE.

POSITIVE CUE:All bistable output lamps dim, except for power>5% and >10% power which will not clear.

Observed all bistable OutputState and/or Output Memorylamps are dim except forpower >5% and power >10%which will not reset due tocurrent plant conditions.

____ ____ ____

C

7.2.3 ENSURE RB Pressure contact buffer resetby placing BLD High Press Trip Resettoggle switch in reset and releasing.

POSITIVE CUE:RB Pressure contact buffer lower toggledepressed.

(End of Row 4 in left cabinet)

Placed reset switch (bottomtoggle) on RB Pressurecontact buffer in lower(RESET) position. ____ ____ ____

Continued


A1JPM-RO-RPS06S7


7.2.4 CHECK RB Pressure contact buffer resetindicated by the following lamps off:

· BLD High Press Trip Input State lamp

· BLD High Press Trip Reset InputState lamp

POSITIVE CUE:Both light out

NEGATIVE CUE:Bothe lights lit

Observed that both BLDGHigh Press Trip and BLD HighPress Trip Reset Input Statelamps go out.

____ ____ ____

C

7.2.5 PLACE Reactor Trip Module SubsystemTrip toggle switch in RESET and RELEASEto reset Channel A Reactor Trip Module.

POSITIVE CUE:No. 1 light goes dim on Rx Trip Module(Middle of Row 2 in right cabinet)

Placed Reactor Trip ModuleSubsystem Trip toggle in thelower (Reset) position andreleased. ____ ____ ____

C

7.2.6 CHECK Subsystem No 1 lamps dimly lit forthe following:

· Channel A Reactor Trip module· Channel A Cabinet Indicating Panel· Channel B Reactor Trip module· Channel B Cabinet Indicating Panel· Channel C Reactor Trip module· Channel C Cabinet Indicating Panel· Channel D Reactor Trip module· Channel D Cabinet Indicating Panel

POSITIVE CUE:All No. 1 lights on dimInform applicant that Channel B, C, and D ReactorTrip modules look just like the Channel A ReactorTrip module. (they are not simulated)

Observed the No. 1 lamps godim in the Channel A ReactorTrip module, Channel ACabinet Indicating Panel andthe “mimic” Cabinet IndicatingPanels for Channels B, C, andD.

____ ____ ____

END


A1JPM-RO-RPS06S7

JPM NUMBER: A1-JPM-RO-RPS05

INITIAL CONDITIONS:

Plant is at 100% power

INITIATING CUE:

The CRS directs you to Reset RPS Channel “A”in accordance with 1105.001 Section 7.0


A1JPM-RO-RPS06S7

Applicant’s Copy

INITIAL CONDITIONS:

Plant is at 100% power

INITIATING CUE:

The CRS directs you to Reset RPS Channel “A”in accordance with 1105.001 Section 7.0


A1LPM-RO-ICW01S8

UNIT: 1 REV # 4 DATE: ___________________

SYSTEM/DUTY AREA: Intermediate Cooling Water System

TASK: Contingency Actions for Loss of Two ICW Pumps

JTA#: ANO1-RO-ICW-NORM-4










REFERENCE(S): 1203.052 Loss of Intermediate Cooling Water

______________________________________________________________________


EVALUATOR'S NAME:__________________________________________________________________




___________________________________________________________________________________

___________________________________________________________________________________

___________________________________________________________________________________





A1LPM-RO-ICW01S8



JPM INITIAL TASK CONDITIONS: ICW Pump P-33A is OOS for bearing replacement.

ICW Pump P-33B has just tripped.

TASK STANDARD: ICW Pump P-33C running with all cross-connect valves open, total ICW flow

<2500 gpm and letdown re-established to ~60 gpm.

TASK PERFORMANCE AIDS: Copy of 1203.052 Loss of Intermediate Cooling Water

SIMULATOR SETUP:

IC with P-33B and P-33C in service per 1104.028. Breaker for P-33A is open IRF B1264 OPEN.Adjust letdown flow to ~60 gpm.

To trip P-33B use IRF B2214 OPEN. Ensure that letdown didn’t isolate on high temperature.

Place the simulator in Freeze and go to run after giving initial conditions and initiating cue.



A1LPM-RO-ICW01S8

INITIATING CUE: The SM/CRS directs you to perform the actions for Loss of Two ICW Pumps in procedure 1203.052.


NOTEA failure of ICW Crossconnect will cause ICW Surge Tank overflow.

CAUTIONOperation of one ICW Pump with the cross-connect valves open will result in operation at runout condition.Pump cavitation can occur and there is elevated risk for motor breaker trip until ICW loads are reduced.

A. PLACE failed ICW Pump(s) inPULL-TO-LOCK.

POSITIVE CUE:P-33B Handswitch is in P-T-L.

On C09, the handswitch for P-33B is placed in the P-T-Lposition. ____ ____ ____

C

B. OPEN the following valves:· P-33A/B Discharge Crossconnect

(CV-2238)· P-33B/C Discharge Crossconnect

(CV-2239)· P-33A/B Suction Crossconnect (CV-2240)· P-33B/C Suction Crossconnect (CV-2241)

POSITIVE CUE:Red lights ON, green lights OFF for all fourvalves.

On C09, the handswitches forCV-2238, CV-2239, CV-2240and CV-2241 are placed in the“OPEN” position and the REDlights are “ON” and theGREEN lights are “OFF”. ____ ____ ____

EXAMINER CUE: Step 1.C.1 is not applicable.Inform applicant that another crew member will take care of Step 1.C.2 (Perform applicable procedures).

D. CLOSE the following valves to isolateletdown:· Orifice Bypass (CV-1223)· Orifice Block (CV-1222)

POSITIVE CUE:Letdown flow at zero.

On C04, isolated letdown byrotating the setpoint knob onCV-1223 to “zero” and placedthe handswitch for CV-1222 toclose. Monitored FI-1236 andverified flow drops to ~0 GPM.

____ ____ ____

NOTEOn a loss of Load Center B-2, only Letdown Cooler E-29A isolation valves will be available.

CONTINUED


A1LPM-RO-ICW01S8


C

E. On C04, CLOSE available ICW/Letdownvalve pairs using associated handswitch(es)to isolate Letdown Cooler(s) (E-29A, E-29B):· HS-2216- ICW to Letdown Cooler E-29A (CV-2216)- RC to Letdown Cooler E-29A (CV-1213)· HS-2217- ICW to Letdown Cooler E-29B (CV-2217)- RC to Letdown Cooler E-29B (CV-1215)

POSITIVE CUE:Green lights only ON for CV-2216, CV-1213, CV-2217 and CV-1215.

On C04, placed HS-2216 andHS-2217 in the close positionto isolate both LetdownCoolers.

____ ____ ____

BOOTH NOTE: When called as WCO to close ICW-121A/B then close ICW-120A/B cooler inlets due to cooler outlets arenot modeled on the simulator. IRF ICW120A 0 and IRF ICW120B 0

C

F. CLOSE the following to isolate ICW toBOTH Spent Fuel Coolers (E-27A andE-27B):

· SFP CLR E-27A ICW Outlet (ICW-121A)· SFP CLR E-27B ICW Outlet (ICW-121B)

POSITIVE CUE:WCO reports ICW-121A/B are closed.

Contacted WCO to close ICW-121A and ICW-121B.

____ ____ ____

EXAMINER CUE: Inform applicant that another crew member will perform 1203.050, Unit 1 Spent Fuel Pool Emerg.If asked inform applicant to return E-29A Letdown Cooler to service. (It doesn’t matter which one is placed into service.)

C

I. On C04, OPEN ONE ICW/Letdown valvepair using associated handswitch to returnONE Letdown Cooler to service:

· HS-2216- ICW to Letdown Cooler E-29A (CV-2216)- RC to Letdown Cooler E-29A (CV-1213)

· HS-2217- ICW to Letdown Cooler E-29B (CV-2217)- RC to Letdown Cooler E-29B (CV-1215)

POSITIVE CUE:Red lights ON, green lights OFF for CV-2216 and CV-1213.

On C04, placed HS-2216 in theopen position to open CV-2216and CV-1213.

OR

On C04, placed HS-2217 in theopen position to open CV-2217and CV-1215.

____ ____ ____

CONTINUED


A1LPM-RO-ICW01S8


J. CHECK total ICW flow is 2500 gpm orless:

ICW Coolers Inlet Flow Nuclear Loop(FI-2219)

ICW Coolers Inlet Flow Non-Nuclear Loop(FI-2218)

Total ICW flow

POSITIVE CUE:Flow is <2500 gpm.

Using the ICW flow indicators onC09, calculated the total flow ofboth nuclear and non-nuclearloops to be < 2500 gpm.

____ ____ ____

EXAMINER CUE: Inform applicant that another crew member will perform Step 1.K, Secure non-essential ICW loads inorder to maintain flow less than 2500 gpm

C

L. OPEN Orifice Block (CV-1222).

POSITIVE CUE:~45 gpm letdown flow indicated on C04.

On panel C04, positioned thehandswitch for CV-1222 to theopen position.

____ ____ ____

M. IF letdown isolated on high temperature,THEN PERFORM 1104.002, Makeup &Purification System Operation, Recovery ofLetdown Following High LetdownTemperature section.

POSITIVE CUE:Letdown temperature on C04 is at ~100°F.(It should not automatically isolate)

If letdown isolated on hightemperature, then performed“Recovery of Letdown FollowingHigh Letdown Temperature”section of MU&P System1104.002.

____ ____ ____

EXAMINER CUE: Inform Examinee to raise letdown flow to ~60 gpm.

C

N. While maintaining letdown flow less than87.5 gpm, ADJUST letdown flow asdesired by CRS/SM using Orifice Bypass(CV-1223).

POSITIVE CUE:Letdown flow is ~ 60 gpm.

On C04, rotated the setpoint knobon CV-1223 to achieve ~60 gpmletdown flow.

____ ____ ____

END


A1LPM-RO-ICW01S8

JPM ID: A1JPM-RO-ICW01

INITIAL CONDITIONS:

ICW Pump P-33A is OOS for bearing replacement.ICW Pump P-33B has just tripped.

INITIATING CUE:

The SM/CRS directs you to perform the actions for Loss of TwoICW Pumps in procedure 1203.052.


A1LPM-RO-ICW01S8

Applicant’s Copy

INITIAL CONDITIONS:

ICW Pump P-33A is OOS for bearing replacement.ICW Pump P-33B has just tripped.

INITIATING CUE:

The SM/CRS directs you to perform the actions for Loss of TwoICW Pumps in procedure 1203.052.

IN PLANT JOB PERFORMANCE MEASURE Page 1 of 6

A1JPM-RO-EFW02P1

UNIT: 1 REV # 10 DATE: ___________________

SYSTEM/DUTY AREA: Emergency Feedwater

TASK: Manual Control of Emergency Feedwater Pump P-7A at the turbine

JTA#: ANO1-RO-EFW-NORM-7

KA VALUE RO: 3.1 SRO: 3.4 KA REFERENCE: 061-A2.05




PLANT SITE:__ Simulate_____________ SIMULATOR: LAB:__________

POSITION EVALUATED: RO:___X____ SRO:___________

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE:____X______ LAB:________

TESTING METHOD: SIMULATE:___X______ PERFORM:


REFERENCE(S): 1106.006 EFW Pump Operation Exhibit C (Manual Control of EFW Pump (P-7A))

______________________________________________________________________


EVALUATOR'S NAME:__________________________________________________________________




___________________________________________________________________________________

___________________________________________________________________________________

___________________________________________________________________________________





A1JPM-RO-EFW02P1



JPM INITIAL TASK CONDITIONS: EFW Pump Turbine K3 tripped on overspeed due to a loss of

electric signal to the speed controller. Power is unavailable to the speed controller/turbine control

cabinet. P-7A turbine has been reset per Exhibit A (EFW Pump P-7A Overspeed Trip Reset).

TASK STANDARD: EFW Pump P-7A running at ~1400 psig discharge pressure.

TASK PERFORMANCE AIDS: Copy of 1106.006 Exhibit C (Manual Control of EFW Pump P-7A).

EXAMINER NOTE: FYI EFW Pump Turbine K3 steam admission valves are closed and the tripthrottle valve is opened in 1106.006 Exhibit A.


A1JPM-RO-EFW02P1

JPM ID: A1JPM-RO-EFW02

INITIATING CUE: The CRS/SM directs you to manually start EFW Pump P-7A and control at approximately 1400 psigdischarge pressure per 1106.006 Exhibit C starting at Step 1.2.


TRANSITION NOTE: Proceed to EFW pump room on 335’ elevation in Controlled Access of Auxiliary Building.

C

1.2 TURN EFW Turbine K3 Trip/Throttle Valve(CV-6601A) handwheel fully clockwise toclose valve.

POSITIVE CUE:Handwheel does NOT move any further, valve isclosed.

Closed CV-6601A by rotatinghand wheel in close direction(clockwise). ____ ____ ____

C

1.3 OPEN EITHER or BOTH of the following:

· EFW Pump Turbine K3 SteamAdmission (CV-2613)

· EFW Pump Turbine K3 SteamAdmission (CV-2663)

POSITIVE CUE:Control Room reports valve(s) are open.(Platform in overhead inside DR-19)

Called control room andrequested CV-2613 and /orCV-2663 to be opened. ____ ____ ____

CAUTIONExceeding turbine speed of 3776 RPM can result in excessive discharge pressure with P-7A suction aligned toService Water.

C

1.4 While monitoring EFW Pump Turbine(K-3) speed and/or EFW Pump (P-7A)discharge pressure:

1.4.1 Slowly TURN EFW Turbine K3Trip/Throttle Valve (CV-6601A)handwheel counterclockwise untildesired speed and/or pressure isreached.

POSITIVE CUE:Pump discharge pressure is rising.(PI-2811A just left of DR-19)

NEGATIVE CUE:Pump discharge pressure is approximately 0 psig.

Slowly opened CV-6601A(counter clockwise) whilemonitoring discharge pressure.

____ ____ ____


A1JPM-RO-EFW02P1


EXAMINER NOTE: With a loss of power to the control cabinet, speed would not be indicated on SI-6601A. The vibratingreed speed indicator is near the back wall behind the turbine. Discharge pressure is available on an instrument rack nearthe door going to Lower South Piping Penetration Room.

C

1.4.2 THROTTLE CV-6601A as necessaryto maintain pump dischargepressure ~1400 psig at EFW P-7ADischarge Pressure (PI-2811A) oras directed by Control Room.

POSITIVE CUE:Pump discharge pressure ~1400 psig.

NEGATIVE CUE:Pump discharge pressure is approximately 500psig.

Slowly opened CV-6601A(counter clockwise) untilapproximately 1400 psigdischarge pressure wasattained.

____ ____ ____

1.4.3 IF turbine speed indication isavailable, THEN CONTROL turbinespeed ~3650 RPM.

POSITIVE CUE:SI-6602 (vibrating speed indicator behind theturbine) indicates ~3650 rpm.

NEGATIVE CUE:SI-6601A (local control cabinet)has no indication

Checked turbine speed locallyat approximately 3650 RPMusing SI-6602.

____ ____ ____

END


A1JPM-RO-EFW02P1

INITIAL CONDITIONS:

· EFW Pump Turbine K3 tripped on over speed due to a lossof electric signal to the speed controller.

· Power is unavailable to the speed controller/turbine controlcabinet.

· P-7A turbine has been reset per Exhibit A (EFW Pump P-7AOverspeed Trip Reset) Step 1.1 is complete.

INITIATING CUE:

The CRS/SM directs you to manually start EFW Pump P-7A andcontrol at approximately 1400 psig discharge pressure per1106.006 Exhibit C starting at Step 1.2.


A1JPM-RO-EFW02P1

Applicant’s Copy

INITIAL CONDITIONS:

· EFW Pump Turbine K3 tripped on over speed due to a lossof electric signal to the speed controller.

· Power is unavailable to the speed controller/turbine controlcabinet.

· P-7A turbine has been reset per Exhibit A (EFW Pump P-7AOverspeed Trip Reset) Step 1.1 is complete.

INITIATING CUE:

The CRS/SM directs you to manually start EFW Pump P-7A andcontrol at approximately 1400 psig discharge pressure per1106.006 Exhibit C starting at Step 1.2.


A1JPM-RO-EDG10P2

UNIT: 1 REV # 0 DATE: ___________________

SYSTEM/DUTY AREA: Emergency Diesel Generator

TASK: Perform DG2 Start Without DC Control Power

JTA#: ANO1-RO-EDG-OFFNORM-22





PLANT SITE:__Simulate_____________ SIMULATOR: LAB:__________



TESTING METHOD: SIMULATE:___X______ PERFORM:


REFERENCE(S): 1104.036, Emergency Diesel Generator

______________________________________________________________________


EVALUATOR'S NAME:__________________________________________________________________




___________________________________________________________________________________

___________________________________________________________________________________

___________________________________________________________________________________





A1JPM-RO-EDG10P2



JPM INITIAL TASK CONDITIONS: Station blackout is in progress. A fault in DG2 control circuit has

tripped DG2 DC Control Breaker D21-14. DG1 is out of service and not available to start.

TASK STANDARD: DG2 running, breaker A-408 closed, and ready to start HPI pump.

TASK PERFORMANCE AIDS: Copy of OP 1104.036, Section 14.0.


A1JPM-RO-EDG10P2

JPM ID: A1JPM-RO-EDG10

INITIATING CUE: CRS/SM instructs you to start DG2 without DC control power per 1104.036 and inform the control roomwhen ready to start an HPI pump.


NOTEThe following assumes no AC or DC power is available.

CAUTIONIf fault condition that caused loss of DC is not removed, a fault can still be present.

14.1 IF known THEN REMOVE fault conditionthat caused loss of DC.

POSITIVE CUE:Cause of fault is unknown.

No action, continue on withstep.

____ ____ ____

14.2 PLACE DG2 Engine Control SelectorSwitch (HS-5244) in MAINT.

POSITIVE CUE:Selected to MAINT.

Engine control switch (HS-5244) on C108 rotated toMAINT position. ____ ____ ____

EXAMINER NOTE: Do not open the cabinet doors. Show the applicant the picture of the breaker.Each picture shows the breaker in the closed position, this is the normal and expected condition how theapplicant would find the breakers. (Figure 1 – D2116A, Figure 2 – D2114A)

C

14.3 OPEN the following local breakers toprevent DG shutdown when DC power isrestored:

· DG2 Local Field Flashing Power(D2116A). Located inside ExcitationCabinet E21

· DG2 Engine Control Power (D2114A).Located inside Engine Control PanelC108

POSITIVE CUE:Breaker(s) D-2116A and D-2114A in open/offposition.

Opened cabinet door forvoltage regulator cabinet (E-21)and opened D-2116A. Openedlower cabinet door of enginecontrol cabinet (C108) andopened D-2114A.

____ ____ ____

EXAMINER NOTE: In the next step travel to the control room should be avoided. Ask the examinee whereelectrical panels RS1 and RS2 are located and then use a picture of panels RS1 and RS2 to perform the step.FYI, panels are located in the back of the control room along the south wall.


A1JPM-RO-EDG10P2


C

14.4 To prevent full ES actuation uponrestoration of power, OPEN the followingbreakers:

· ESAS Panel C86 and C87 Breaker(RS1-4)

· ESAS Panel C91 and C92 Breaker(RS2-4)

POSITIVE CUE:Breakers RS1-4 and RS2-4 open.

Opened panel door for RS1and RS2 and then openedBreakers RS1-4 and RS2-4.

____ ____ ____

TRANSITION NOTE: The applicant should proceed to the A-4 switchgear room.14.5 ENSURE open the following breakers:

· A2 Feed to A4 (A-409)· A4-A3 Crosstie (A-410)· Service Water Pump P-4C Breaker

(A-402)· Service Water Pump P-4B Breaker

(A-403)· RB Spray Pump P-35B Breaker

(A-404)· LPI Pump P-34B Breaker (A-405)· HPI Pump P-36C Breaker (A-406)· HPI Pump P-36B Breaker (A-407)

POSITIVE CUE:A-409 observes CLOSED flag, applicant depressedmechanical trip pushbutton and OPEN flag is observed.A-410 - OPEN flag is observedA-402 observes CLOSED flag, applicant depressedmechanical trip pushbutton and OPEN flag is observed.A-403, A-404, A-405, A-406, A-407 - OPEN flag isobserved

For each breaker listed, openeddoor and checkedOPEN/CLOSED flag.

For the breakers with theCLOSED flag, applicantdepressed local mechanical trippushbutton.

____ ____ ____

TRANSITION NOTE: The applicant should proceed to DG#2 room.


A1JPM-RO-EDG10P2


C

14.6 Overriding DG2 governor run solenoid:

14.6.1 LIFT red knurled knob on top ofgovernor and PUSH in the lockingpin.

14.6.2 While HOLDING IN the lockingpin, LOWER the knurled knob untilmovement is restricted.

14.6.3 RELEASE locking pin.

14.6.4 CHECK knob stays in raisedposition.

POSITIVE CUE:Governor run solenoid is overridden.

The governor run solenoid wasoverridden by:

· Lifting the red knurledknob on top of thegovernor

· Pushing in the locking pinon the red knurled knob

· Lowering the red knurledknob while holding thelocking pin in

· Releasing the pin andverifying the knob stayedin the raised position

____ ____ ____

NOTE· Service Water to DG2 Coolers (CV-3807) requires DC power to open automatically.

· Manually opening CV-3807 will allow SW flow to DG2 once SW pump starts.

C

14.7 Manually OPEN Service Water to DG2Coolers (CV-3807).

POSITIVE CUE:CV3807 indicates open.

NEGATIVE CUE:CV3807 appears just like you see it. (Closed)

Depressed clutch lever and usedmanual handwheel to open SERVWTR to DG2 CLRS (CV-3807).

____ ____ ____

CAUTION· The steps that follow the start of the DG up through closing the SW Pump breaker are

performed without delay or interruption so that cooling is established prior to engineoverheat.

· Maximum crank time for air start motors is 5 seconds.


A1JPM-RO-EDG10P2


C

14.8 START DG2 by depressing either air startsolenoid override plunger.

14.8.1 IF DG2 starts, OR crank timeexceeds 5 seconds, THENRELEASE solenoid overrideplunger.

14.8.2 IF DG2 did NOT start after 5seconds, THEN:

A. ENSURE override of DG2governor run solenoid byrepeating step 14.6.

B. REPEAT step 14.8.

POSITIVE CUE:Engine is running

NEGATIVE CUE:Engine turns over but does not start.

Located air start solenoid on sideof diesel and depressed overrideplunger until engine started andreleased the plunger.

____ ____ ____

EXAMINER NOTE: Steps 14.9 and 14.10.1 are not applicable.

CAUTIONWith loss of control power, the only functional DG protection is mechanical overspeed device.

14.10 CHECK governor maintaining thefollowing:

· Engine speed at 900 RPM

· Frequency at 60 Hz

POSITIVE CUE:Engine at 900 rpm and frequency at 60 HZ.

Moved to C108 and observedtachometer at approx. 900 rpm.Moved to voltage regulator controlpanel E-21 and verified frequencyapprox. 60 HZ.

____ ____ ____


A1JPM-RO-EDG10P2


NOTE· Loss of DC power to field flashing circuit will cause loss of automatic voltage regulator setpoint

adjustment (loss of power to motor-operated rheostat).

· Manual voltage regulation should still function.14.11 ENSURE DG2 output voltage 3800-4500

volts.

14.11.1 IF voltage falls outside 3800-4500volts, THEN:

A. At E21, PLACE DG2 ExcitationControl Selector Switch in MANUAL.

B. ADJUST manual voltage adjust dialto 3800-4500 volts.

POSITIVE CUE:Voltage is ~4160V.

NEGATIVE CUE:Engine/generator parameters are out of proper band.

At voltage regulator cabinet (E21),checked output voltage 3800-4500volts.

____ ____ ____

TRANSITION NOTE: The examinee should proceed to the A-4 switchgear room.CAUTION

The next step will cause automatic loading of the diesel if 125V DC is restored through a battery charger.Being prepared to manually adjust the diesel voltage and frequency for each load started is vital to maintainproper electrical parameters to components.EXAMINER NOTE: When the applicant checks the status of breaker A-408 the closing springs are charged,therefore the applicant should manually close A-408 with the manual push button. He may refer to this as“broom sticking” the breaker.

C

14.12 Manually CLOSE DG2 Output Breaker(A-408).

POSITIVE CUE:A-408 observe CLOSED flag

NEGATIVE CUE:A-408 observe OPEN flag

At A-408 manually close theoutput breaker.

____ ____ ____


A1JPM-RO-EDG10P2


14.13 IF DC power is restored, THEN CHECK aService Water Pump on A-4 automaticallyrestarts.

· SW Pump (P-4C)

· SW Pump (P-4B)

POSITIVE CUE:At breaker cubicle A-402 and A-403 red and greenlights both OFF.

Noted open closed lights for A-402and A-403 are off.

____ ____ ____

EXAMINER NOTE: When the applicant checks the status of the breakers, A-402 closing springs are notcharged, however the closing springs for A-403 are charged since the breaker was open prior to a loss of DCcontrol power. Therefore the applicant should choose to manually close A-403 with the manual push button. Hemay refer to this as “broom sticking” the breaker.

14.14 IF a Service Water pump does NOTautomatically start THEN manually CLOSEONE of the following breakers.

· SW Pump P-4C Breaker (A-402)

· SW Pump P-4B Breaker (A-403)

POSITIVE CUE:At breaker cubicle A-403 observe CLOSED flagand normal current.

Manually closed either A-403using the manual pushbutton ORuse 1107.001 “Breaker LocalOperation Without DC ControlPower” to manually charge thesprings and close A-402.

____ ____ ____

14.15 IF CRS/SM directs to restart an HPI pumpon A4, THEN:

POSITIVE CUE:Control room acknowledges report

Called CRS on radio or telephoneto inform diesel ready for loadingand ask if it is desired to restart anHPI Pump on A4.

____ ____ ____

END


A1JPM-RO-EDG10P2


A1JPM-RO-EDG10P2

JPM ID: A1-JPM-RO-EDG08


Station blackout is in progress.A fault has resulted in a loss of the Green Train DC.DG1 is out of service and not available to start.

INITIATING CUE:

CRS/SM instructs you to start DG2 without DC control powerper 1104.036 and inform the control room when ready to startan HPI pump.


A1JPM-RO-EDG10P2

Applicant’s Copy


Station blackout is in progress.A fault has resulted in a loss of the Green Train DC.DG1 is out of service and not available to start.

INITIATING CUE:

CRS/SM instructs you to start DG2 without DC control powerper 1104.036 and inform the control room when ready to startan HPI pump.


A1JPM-RO-LRW02P3

UNIT: 1 REV # 4 DATE: ___________________

SYSTEM/DUTY AREA: Liquid Release System

TASK: Perform Sampling TWMT (T-16A/B)

JTA#: ANO1-WCO-CZ-NORM-25





PLANT SITE:__ Simulate_____________ SIMULATOR: LAB:__________



TESTING METHOD: SIMULATE:___X______ PERFORM: ALTERNATE PATH: X


REFERENCE(S): OP-1104.020 Clean Waste System Operation

______________________________________________________________________


EVALUATOR'S NAME:__________________________________________________________________




___________________________________________________________________________________

___________________________________________________________________________________

___________________________________________________________________________________





A1JPM-RO-LRW02P3



JPM INITIAL TASK CONDITIONS: Plant is at 100% power operations. RI-4642 is OPERABLE.

T-16A level is 85% by local indication and is no longer filling.

TASK STANDARD: Applicant aligned T-16A for recirc and sampling, then secured the recirc pump

after sample was obtained.

TASK PERFORMANCE AIDS: Copy of 1104.020 Section 18.0 Sampling Treated Waste

Monitor Tank T-16A.

This is an alternate path JPM


A1JPM-RO-LRW02P3

JPM ID: A1JPM-RO-LRW02

INITIATING CUE: CRS directs you to perform “Sampling Treated Waste Monitor Tank T-16A” Section 18.0 of1104.020.

(C) PERFORMANCE CHECKLIST STANDARD SAT UNSAT

N/A

18.1. ENSURE Treated Waste Monitor T-16AInlet (CZ-47A) closed.

POSITIVE CUE:CZ-47A chain operated in the clockwisedirection and did not move. No valve stemvisible and limit switch engaged.(2nd tank and back along wall in overhead)

CZ-47A verified closed.____ ____ ____

18.1.1 Install Sample Tag on CZ-47A.

EXAMINER CUE:Tag installed through the chain operator suchthat the valve cannot be operated withoutremoving the tag.

Tag installed through the chainoperator such that the valvecannot be operated withoutremoving the tag.

____ ____ ____

18.2 ENSURE Suction Crossover on TreatedWaste Monitor Pumps (CZ-50) closed.

POSITIVE CUE:CZ-50 handwheel operated in the clockwisedirection and did not move. Valve stem is inthe “full in” position.(Right before ladder on wall)

CZ-50 Verified Closed____ ____ ____

Place Treated Waste Monitor Tank T-16A on short path recirc as follows:

18.3.1 ENSURE Treated Waste Discharge Valveto Header from P-47A (CZ-55A) closed.

POSITIVE CUE:CZ-55A handwheel operated in the clockwisedirection and did not move. Valve stem is inthe “full in” position.(Top right valve on wall)

CZ-55A Verified Closed.____ ____ ____


A1JPM-RO-LRW02P3


N/A

(C)18.3.2 OPEN Treated Waste Monitor Tank T-16A

Recirc Inlet (CZ-54A)

POSITIVE CUE:CZ-54A handwheel operated in the counterclockwise direction until it stopped. Valvestem is in the “full out” position.(Right below CZ-55A)

CZ-54A Verified Open.____ ____ ____

(C)18.3.3 START Treated Waste Monitor Pump (P-47A) using ONE of the following:

· HS-4627 on Clean Liquid RadwasteControl Panel (C112)

· HS-4637 local handswitch

POSITIVE CUE:Red light ON, Green light OFF for P-47A and40 psig discharge pressure indicated onPI-4627.

(HS-4637 and PI-4627 next to each other)

NEGATIVE CUE:Green light ON, Red light OFF for P-47A.

P-47A started

____ ____ ____

18.4 COMPLETE Request section of AttachmentB1, Treated Waste Monitor Tank T-16A LiquidRelease Permit.

EXAMINER CUE:Inform applicant that Request Section ofAttachment B1 is filled in by anotheroperator.

Applicant asks for AttachmentB1.

____ ____ ____

18.5 SUBMIT Attachment B1 to Chemistry foranalysis.

EXAMINER CUE:Chemistry reports sampling and neutralizingoperations are complete.

Applicant should state that hewould take the Attachment B1to Chemistry for analysis.

____ ____ ____


A1JPM-RO-LRW02P3


N/A

EXAMINER NOTE: ALTERNATE PATH BEGINS HERE

18.6 WHEN sampling and neutralizingoperations are complete,THEN:

No Cue given

Applicant should proceed withnext step. ____ ____ ____

EXAMINER NOTE: Applicant should attempt to stop P-47A using HS-4637 local hand switch first, which willnot work. HS-4627 on C112 will successfully stop pump. If applicant chooses to operate HS-4627 first, swapsuccess paths such that the second switch operated is the one that works.

18.6.1 Stop P-47A using ONE of the following:

· HS-4627 on Clean Liquid Radwaste ControlPanel (C112)


NEGATIVE CUE:When applicant describes stopping P-47inform him that,Red light ON, Green light OFF for P-47A and40 psig discharge pressure indicated onPI-4627.

P-47A handswitch taken to thestop position. When herealizes that the pump failed tostop proceed to the otherhandswitch.

____ ____ ____

(C)18.6.1 Stop P-47A using ONE of the following:

· HS-4627 on Clean Liquid Radwaste ControlPanel (C112)


POSITIVE CUE:Red light OFF, Green light ON for P-47A andno flow indicated on FI-4626 or 0 psigindicated on PI-4627.

P-47A handswitch taken to thestop position. ____ ____ ____

END


A1JPM-RO-LRW02P3

JPM ID: A1JPM-RO-LRW02

INITIAL CONDITIONS:

Unit 1 is at 100% power.RI-4642 is OPERABLET-16A level is 85% by local indication and is no longer filling.

INITIATING CUE:

CRS directs you to:Perform “Sampling Treated Waste Monitor Tank T-16A” Section18.0 of 1104.020.


A1JPM-RO-LRW02P3

Applicant’s Copy

INITIAL CONDITIONS:

Unit 1 is at 100% power.RI-4642 is OPERABLET-16A level is 85% by local indication and is no longer filling.

INITIATING CUE:

CRS directs you to:Perform “Sampling Treated Waste Monitor Tank T-16A” Section18.0 of 1104.020.

Appendix D Scenario 1 Outline

Page 1 of 45

Facility: ANO-1 Scenario No.: 1 R0 Op-Test No.: 2018-1

Examiners: _____DEGRADED POWER _____ Operators: __IC-219_____________________ ____________________________ _____________________________ ____________________________ _____________________________

Initial Conditions:- 99.5% Power.- EFIC Failed and will not auto-actuate- C-28A IA Compressor is out of service for

overhaul- CV-3807 SW to #2 EDG will not

automatically open- ULD will not respond to demand changes

- #1 EDG will not Auto-Start (IMFDG175)

- P-36C MU Pump in service- Run Scenario 1 Schedule File

R0- Open Event File R0- Ensure Thundersound running

Turnover:- Day shift – normal working day.- ICS in full manual for NI Calibration- Thunderstorms entering the area

- NI Calibration completed, returnICS to automatic per OP-1105.004 Section 8.0.

EventNo. Malf. No. Event

Type*Event

Description

1 N/A N-(BOP) Return ICS to automatic per OP-1105.004 Section8.0

2 DI_1413MI-(BOP)(SRO)

TS

BWST temperature controller fails, causing heatersto remain energized and BWST temperature toexceed 110oF. T.S. 3.5.4 Condition C

3 CV063

C-(ATC)C-(BOP)

C-(SRO)

Running Makeup Pump (P-36C) trips.

4

LightningDI_DG2S

IMFK01A3

CV3807 to0

C-(BOP)(SRO)

TS

Lightning strike renders #2 EDG Inoperable (#2EDG running with no cooling water).T.S. 3.8.1 Condition B

5 N/AR-(ATC)

R-(SRO)

Dispatcher directs a power reduction to 700 MW inthe next 10 minutes. (180 MW/10 min = 2% power /min)

6ULDMANOVR to

TrueI-(ATC) Unit Load Demand will not respond to demand

changes.

7 LightningED451

I-(ATC)I-(BOP)I-(SRO) Lightning causes loss of NNI-Y power supply.


Page 2 of 45


Type*Event

Description

8 LOOPED183

M(ALL)

Loss of offsite power with a / Reactor Trip / Blackout/ Degraded Power

9 DG175 C-(BOP)CT Failure of #1 EDG to automatically start

10 EFICFW621

I-(ATC)CT EFIC fails to automatically actuate.

* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor


Page 3 of 45

SCENARIO 1 OBJECTIVES

1) Evaluate individual ability to perform routine ICS Control Station Operations.

2) Evaluate individual ability to recognize when conditions require the entry intotechnical specifications conditions.

3) Evaluate individual ability to recognize and respond to the loss of a makeup pump.

4) Evaluate individual ability to recognize and respond to the false auto start ofemergency diesel generator.

5) Evaluate individual ability to recognize and respond to the failure to open of theservice water supply valve on an operating emergency diesel generator.

6) Evaluate individual ability to reduce plant power.

7) Evaluate individual ability to recognize and respond to ICS system malfunctions.

8) Evaluate individual ability to recognize and respond to the loss of power to the ‘Y’

Non-Nuclear Instrumentation system.

9) Evaluate individual ability to recognize and respond to a loss of offsite power.

10) Evaluate individual ability to recognize and respond to failure of the emergencydiesel generator to auto start.

11) Evaluate individual ability to recognize and respond to the failure of the EmergencyFeedwater Initiation and Control system to automatically actuate emergencyfeedwater.

12) Evaluate individual ability to perform the energizing of a vital bus from the AlternateAC generator. (RSOA – Risk Significant Operator Action)


Page 4 of 45

SCENARIO 1 NARRATIVE

Event One: Normal operation to return ICS to automaticThe crew will assume plant responsibility at 99.5% power. The SRO will direct returning ICSto automatic per OP-1105.004, Integrated Control System, Section 8.0, Transferring MajorICS Control Stations to AUTO. (BOP-N)

Event Two: BWST Temperature exceeds TS LimitBWST temperature controller fails, causing heaters to remain energized and BWSTtemperature to exceed 110oF. The CRS will enter the ACA 1203.012H for annunciator K09-C6 BWST TEMP HI/LO. He will direct the BOP to place the heater handswitch into OFF tosecure the heaters and enter T.S. 3.5.4 Condition C. (CRS-TS) (BOP-I)

Event Three: Failure of the running Makeup Pump (P-36C)Once the Technical Specification entries are completed, the running Makeup Pump (P-36C)will trip due to an instantaneous overcurrent condition as reported from the field operatorupon request to investigate. The CRS will enter AOP 1203.026, Loss of Reactor CoolantMakeup. Actions will be performed by both the ATC and BOP for this failure. (ATC-C)(BOP-C) (CRS-C)

Event Four: Lightning strike causes #2 EDG to start with a failure of the ServiceWater Cooling Valve for the EDG.Once the Standby Makeup Pump is running with normal Seal Injection and Makeup, andLetdown is restored, a lightning strike will cause the #2 EDG to have an erroneousautomatic start actuation. In addition to the automatic start, the cooling water valve to theEDG (CV-3807) will fail in the closed position. The crew should attempt to open the valvefrom the control room and send an operator to locally open the valve. Both attempts will fail.The CRS should direct operations per 1203.012A Annunciator K01 Corrective Actions. Thecrew should determine it is a spurious actuation. With no cooling flow available, the crewshould take the #2 EDG to lockout to prevent an automatic trip of the EDG.(BOP-C) (SRO-C)The CRS will enter TS 3.8.1. Condition B. (CRS-TS)

Event Five: Dispatcher directs power reduction due to grid instabilityThe dispatcher will call and direct U1 to reduce net generator output to 700MWe in the next10 minutes (SRO-R) (ATC-R).

Event Six: ULD fails to respond to demanded power reductionThe Unit Load Demand in ICS will not respond to the demanded change in power, the ATCwill manually control the power reduction using the SG/RX Master and will reduce power ata rate of > 2%/minute to achieve the direction of the dispatcher.


Page 5 of 45

Event Seven: Loss of NNI-Y power due to lightning strikeA second lightning strike will result in a loss of the NNI-Y power supply (ATC-I) (BOP-I)(SRO-I). The crew should recognize the loss of NNI-Y power. The CRS will enter 1203.047,Loss of NNI Power. The power supply breakers on RS-4 BKR 9 and Y01 BKR 39 will notreset. Breakers S-1 and S-2 on the NNI-Y power supply will not be tripped. Both boardoperators will have actions to place all SASS (Smart Automatic Signal Selection) switchesinto the NNI-X position.Letdown flow and pressure indication will be lost on C04. The letdown orifice bypass valvewill fail to 50% reducing letdown flow. CFT pressure instrumentation will be lost along withNaOH tank temperature. All NNI-Y inputs to PMS/PDS will be lost or fail to mid scale.

Event Eight: Loss of offsite powerA loss of offsite power will occur due to storm related grid instabilities (SRO-M) (ATC-M)(BOP-M). The reactor will trip automatically. The CRS will direct operations per 1202.001Rx Trip. After the immediate actions are complete the CRS will transition to either 1202.008Blackout or 1202.007 Degraded Power depending on when the BOP manually starts the #1EDG.

Event Nine: Failure of #1 EDG to auto startThe #1 EDG will not auto start requiring the BOP to manually start the EDG (BOP-C)(BOP-CT).CT Justification:Safety significance – Degraded emergency power capacityInitiating Cue – Loss of Offsite PowerMeasurable Performance Standard – Energize A3 within 15 minutes of LOOP. (Criteria todeclare an SAE for a station blackout)Performance Feedback – Status indicating lights, voltage, frequency and Kw loading for thediesel and A3 voltage indicated.

The Alternate AC (AAC) Generator initially will not come up to speed. Unit 2 operations willdispatch maintenance personnel to make repairs.

Event Ten: EFIC fails to actuate automaticallyThe EFIC system is failed and will not automatically actuate EFW on the Loss of OffsitePower (ATC-C) (SRO-C). The ATC should manually actuate EFW from the remote switchmatrix (ATC-CT).CT Justification:Safety significance – Failure of an automatic actuation of an ESF systemInitiating Cue – Loss of all Reactor Coolant PumpsMeasurable Performance Standard – Manually actuate EFW before the ERV opens inautomatic. (Opening the ERV is an unnecessary challenge to the RCS fission productbarrier)Performance Feedback – Status indicating lights on the Remote Switch Matrix, EFWPumps, and EFW valves.

The ATC will perform 1202.012 Repetitive Tasks RT-5 Verify proper EFW actuation andcontrol. EFW may be manually actuated before the step in the EOP that directs verifyingEFW actuated.


Page 6 of 45

Critical Task Measurable Performance Standards

(CT) The BOP should energize A3 within 15 minutes of LOOP.(CT) EFW should be manually actuated before the ERV opens in automatic.

The AAC Diesel Generator will be made available to the crew as directed by the leadexaminer and the scenario can be terminated when the AAC Generator is powering the A4vital bus.

Scenario Recapitulation

Total Malfunctions: 8Abnormal Events: 4Major Transients: 1EOPs Entered: 2EOP Contingencies: 1Malfunctions after EOP 2Critical Tasks: 2

Causing an unnecessary plant trip or ESAS actuation may constitute a CT failure. Actionstaken by the applicant(s) will be validated using the methodology for critical tasks inAppendix D to NUREG-1021.


Page 7 of 45

EventNo.

Time EventType

Description

1 T=0 N-(BOP) Return ICS to automatic per OP-1105.004 Section 8.0

2 T=8I-(BOP)I-(SRO)

TS

BWST temperature controller fails, causing heaters to remainenergized and BWST temperature to exceed 110oF. T.S.3.5.4 Condition C

3 T=18C-(ATC)C-(BOP)C-(SRO)

Running Makeup Pump (P-36C) trips.

4 T=45C-(BOP)(SRO)

TSLightning strike renders #2 EDG Inoperable (#2 EDG runningwith no cooling water). T.T. 3.8.1 Condition B

5T=50

R-(ATC)R-(SRO)

Dispatcher directs a power reduction to 700 MW in the next10 minutes. (180 MW/10 min = 2% power / min)

6 I-(ATC) Unit Load Demand will not respond to demand changes.

7 T=60I-(ATC)I-(BOP)I-(SRO)

Lightning causes loss of NNI-Y power supply.

8

T=75

M-(ALL) Loss of offsite power with a / Reactor Trip / Blackout /Degraded Power

9 C-(BOP)CT Failure of #1 EDG to automatically start

10 I-(ATC)CT EFIC fails to automatically actuate.


Page 8 of 45

Op-Test No.: 2018-1 Scenario No.: 1 Event No.: 1

Event Description:

Return ICS to automatic per OP-1105.004 Section 8.0.Time Position Applicants Actions or Behavior

T=0 CRS Direct BOP to return ICS to automatic per OP-1105.004 Section 8.0.

CAUTIONThe following section has been determined to have a Reactivity Addition Potential (RAP) andthis activity is classified as a Risk Level R2 (<5% power change).

BOP

8.1 Initial conditions:

· Diamond Panel in Manual, if applicable

· RX Demand in HAND

· Feedwater Demand Loop A in HAND

· Feedwater Demand Loop B in HAND

· Load Ratio DT-cold in HAND

· ULD Unit Master Station in HAND

· Reactivity Management Brief performed perCOPD-030 with an SRO

NOTE· With the major stations in HAND, and the plant in a stable (balanced) condition, aligning

all stations prior to returning any station to AUTO will provide a controlled, bumplessreturn to full automatic.

· Description section 3.1 of this procedure contains “Expected and normal indicationswhen transferring H/A stations to manual”.

BOP8.2 IF MEAS VAR can NOT be aligned,

THEN GO TO the appropriate section for transferringstation with misaligned MEAS VAR to AUTO.

N/A 8.3 IF SG/RX Demand in AUTO, … N/A

BOP 8.4 Verify Turbine in INTEG CONTROL, controlling TurbineHeader pressure at setpoint.

EVENT 1 CONTINUED


Page 9 of 45

Op-Test No.: 2018-1 Scenario No.: 1 Event No.: 1CONTINUED

Event Description:


CAUTIONTo ensure bumpless transfer, a transfer of H/A station from HAND to AUTO is not madewithout first minimizing error between:

· MEAS VAR and POS on controller for H/A stations other than ULD

· Current power and PMS CTP input for ULD

BOP

8.5 Check MEAS VAR on both FW Loop Demand stations onthe caret.

8.5.1 IF required,THEN drive SG/RX Demand in HAND untileither limit below is met:

· MEAS VARs for Feedwater DemandLoop A and Feedwater Demand Loop Bare at the caret.

· Indicated error is split between the twoMEAS VARs.

8.5.2 IF error between the two loops differs,THEN drive Load Ratio DT-cold H/A station inHAND to remove difference.

BOP

8.6 Check T-ave is at setpoint.

8.6.1 IF required,THEN perform one or both of the following:

· Move rods in MANUAL.

· Adjust feedwater flow to bring T-ave tosetpoint.

A. Return to step 8.5.

BOP 8.7 Check RX Demand MEAS VAR on the caret.

BOP 8.8 Check SG/RX H/A station POS and MEAS VAR areapproximately equal.

EVENT 1 CONTINUED


Page 10 of 45


Event Description:


BOP

8.9 Place stations in AUTO as follows:

8.9.1 Diamond Panel, if applicable

8.9.2 RX Demand

8.9.3 Feedwater Loop Demands:

· Loop A FW Loop Demand

· Loop B FW Loop Demand

8.9.4 Load Ratio DT-cold

8.9.5 SG/RX Demand

BOP 8.10 Check UNIT MASTER IN TRACK (K07-A1) alarm clear.

8.11 WHEN plant is stable at desired reactor powerAND desired to place ULD Unit Master Station inAUTO,THEN perform the following to place ULD Unit MasterStation in AUTO:8.11.1 Verify reactor power setpoint is within

1% of current reactor power.

8.11.2 IF a ULD setpoint adjustment isnecessary OR desired, THEN perform thefollowing:

A. Select ULD program on PMS.

B. Perform the following to program ULDsetpoint:

1. Enter desired reactor power setpoint inPMS. Do NOT save the change.

2. Obtain concurrence from second licensedoperator that setpoint is correct.

3. Save selected setpoint to PMS.


Page 11 of 45


Event Description:


8.11.3 Select AUTO on ULD Unit Master handstation.

8.11.4 Monitor NIs and PMS/PDS for stableconditions.

8.11.5 WHEN power is stable at desired powerlevel,THEN reset STAR module cumulativecorrection as follows:

A. Momentarily depress ULD Raise/LowerToggle switch in either direction.

B. Check that ULD POS is on the caret.

EVENT TERMINATION CRITERIAThis event is complete when ICS is in Automatic and UNIT MASTER IN TRACK alarm clear.

ORAs directed by the Lead Evaluator.

EXAMINER NOTES


Page 12 of 45


Event Description:

BWST temperature controller fails, causing heaters to remain energized and BWSTtemperature to exceed 110oF..

Time Position Applicant’s Actions or Behavior

8 ATC Recognize and report K09-C6, BWST TEMP HI/LO

BOP Perform 1203.012H ACA for K09-C6

BOP 1. On C14, CHECK BWST (T-3) temperature.Report that BWST temperature indicates ~120oF, with heaters energized

Booth Cue: If directed to investigate with a digital pyrometer, report that the temperature is120oF.

CRS 2. REFER TO TS 3.5.4 for BWST (T-3) requirements.

CREW 3. ATTEMPT to maintain T-3 temperature above 40°F.

N/A 4. IF temperature is low, …N/A

CRS 5. IF T-3 temperature is high, THEN:

N/A A. IF BWST Heater HS-1413 on C14 is in MAN position,…N/A

BOPB. IF BWST Heater HS-1413 is in AUTO with BWST Heater on,

THEN PLACE HS-1413 to OFF.

CRSC. IF alarm is due to BWST Heater auto TS circuit malfunction,

THEN NOTIFY I&C to investigate problem.

EVENT TERMINATION CRITERIAThis event is complete when CRS has entered T.S. 3.5.4 Condition C


EXAMINER NOTES


Page 13 of 45


Event Description:

Failure of the running Makeup Pump (P-36C)Time Position Applicant’s Actions or Behavior

18 CRS Direct operations per 1203.026 Loss of Reactor Coolant Makeup.

NOTEIndications of loss of HPI suction are all of the following:

· Erratic flow· Erratic discharge pressure· Control valves stable

N/A1. IF HPI pump has lost suction,

THEN STOP the HPI pump.

BOP

2. ISOLATE letdown by performing ONE of the following:

· CLOSE Letdown Coolers Outlet (CV-1221)

· CLOSE BOTH of the following:

- Letdown Coolers Outlet (RCS) (CV-1214)

- Letdown Coolers Outlet (RCS) (CV-1216)

NOTE· With HPI pump off, ICW cooling of RCP seals should provide adequate time to correct

HPI pump or control problems, providing no pre-condition exists, such as excessiveRCP shaft sleeve leakage. HPI can provide necessary makeup for normal operationsor plant shutdown.

· 1203.031, Reactor Coolant Pump and Motor Emergency, Attachment A may be usedas an aid to assess seal parameters.

Booth Cue: If directed to investigate, WCO will report an acrid odor in the area and P-36Cmotor hot to the touch. AO will report Instantaneous Overcurrent Relay drop flags onA-406.

BOP3. CHECK RC pump seals are being cooled by ICW.

A. IF ICW to RCP seals is NOT available, … N/A.

BOP

4. Preparing to restart an HPI pump:

A. IF BOTH OP HPI Pump and STBY HPI Pump areunavailable, … N/A

EVENT 3 CONTINUED


Page 14 of 45


Event Description:


ATC

ATC

ATC

BOP

N/A

B. PLACE the following valves in HAND:

· RC Pumps Total INJ Flow (CV-1207)

· Pressurizer Level Control (CV-1235)

C. CLOSE the following valves:

· RC Pumps Total INJ Flow (CV-1207)

· Pressurizer Level Control (CV-1235)

D. ENSURE RCP Seal Injection Block (CV-1206) closes.

E. SELECT Safety System Diagnostic Inst display on SPDS forOP HPI pump and EVALUATE suction pressure and flowstability prior to event.

F. IF loss of pump suction was indicated, … N/A

BOP

5. IF STBY HPI pump is available,THEN:

A. START Aux lube oil pump for STBY HPI pump.

B. GO TO step 8 to place STBY HPI pump into service.

BOP 8. Restoring normal makeup and seal injection:

NOTEA decision to vent HPI Pump is based on suction pressure from SPDS history as wellas leak location and lowest suction pressure achieved.

N/A A. IF decision is to vent HPI Pump, … N/A

BOP B. CHECK HPI pump suction pressure greater than 10 psig.

ATC

C. ENSURE the following valves in HAND AND closed:

· CV-1207

· CV-1235

EVENT 3 CONTINUED


Page 15 of 45


Event Description:


N/A D. IF ES HPI pump will be used, … N/A

CAUTIONSimultaneous operation of Aux Lube Oil Pump and HPI/MU Pump is minimized to limit oilleakage at pump outboard thrust bearing.

BOP

ATC

E. WHEN Aux lube oil pump has run for at least one minute,THEN START HPI pump.

F. STOP Aux lube oil pump for HPI pump.

G. IF the STBY HPI Pump was started,THEN:

1) CHECK stopped HPI pump for reverse rotation.

2) IF HPI Pump reverse rotation is indicated, … N/A

H. PLACE CV-1206 pushbutton in OVRD (OVRD light on).

I. OPEN CV-1206.

BOOTH OPERATOR CUE: If asked, report that P-36C is not rotating.

CAUTIONWith RCP seal bleed off temperature greater than 180°F rapid establishment of sealinjection, less than 30 min, will result in seal damage.

ATC

N/A

ATC

J. IF RCP Seal Bleed off temperatures are less than or equal to180°F, THEN:

1) Slowly OPEN CV-1207 until RCP Seals Total INJ Flowis 30 to 40 gpm.

2) PLACE CV-1207 in AUTO.

K. IF RCP Seal Bleed off temperatures are greater than 180°F,THEN: … N/A

L. WHEN RCP seals total injection flow is above setpoint of 22gpm (CV-1206 Flow light on), THEN RETURN CV-1206OVRD pushbutton to normal (OVRD light off).

EVENT 3 CONTINUED


Page 16 of 45


Event Description:


ATC

M. Slowly OPEN CV-1235 until makeup flow indication ison-scale.

N. ADJUST CV-1235 setpoint to desired value.

O. PLACE CV-1235 in AUTO.

BOP

ATC9. RESTORE letdown per Restore Letdown (RT-13).

EXAMINER NOTE: RT-13 guidance is on the next two pages.T.S. 3.5.2 may be referenced below but no entry is required since two trains of HPI remainOPERABLE

CRS 10. INITIATE repairs for failed HPI pumps and components.

CRS 11. REFER TO Tech Spec 3.5.2.

N/A 12. IF required, THEN PLACE plant in Mode 3, … N/A

CRS 13. INITIATE a Condition Report.

EVENT 3 CONTINUEDEXAMINER NOTES


Page 17 of 45


Event Description:


BOP

ATC9. RESTORE letdown per Restore Letdown (RT-13).

ATC 1. Verify ICW pump supplying Nuclear loop (P33C or P33B).

ATC2. Verify 3-Way Valve (CV-1248) aligned for desired flow path (BLEED

or LETDOWN).

ATC 3. Verify Orifice Bypass (CV-1223) demand adjusted to zero.

ATC

4. Verify the following:

· Makeup Filter Inlet to F3A or F3B (CV-1246 or CV-1247) open

· PURIF Demineralizer Inlet to T36A or T36B (CV-1244 orCV-1245) open

· Either or both RC to Letdown Coolers and associated ICW toLetdown Coolers open:

E29A E29B

CV-1213 RC to LetdownCoolers CV-1215

CV-2216 ICW to LetdownCoolers CV-2217

· Orifice Block (CV-1222) open

N/A 5. IF ESAS has actuated, … N/A

BOP

N/A

6. Check Nuclear ICW RB Inlet and Nuclear ICW RB Outlets open:

· CV-2214

· CV-2233

· CV-2215

A. IF Nuclear ICW RB Inlet (CV-2233) or a Nuclear ICW RBOutlet (CV-2214 or CV-2215) is closed, … N/A

EVENT 3 CONTINUED


Page 18 of 45


Event Description:


BOP

7. Verify Letdown Coolers Outlet(s) (RCS) open for available LetdownCooler(s):

· CV-1214

· CV-1216

N/A8. IF Letdown Coolers Outlet (RCS) (CV-1221) closed on high

temperature, … N/A

BOP 9. Verify Letdown Coolers Outlet (RCS) (CV-1221) open.

ATC 10. Establish desired letdown flow using Orifice Bypass (CV-1223).

EVENT TERMINATION CRITERIAThis event is complete when P-36B is running with Letdown restored.


EXAMINER NOTES


Page 19 of 45


Event Description:

Lightning strike causes #2 EDG to start with a failure of the Service Water Cooling Valve forthe EDG. (CV-3807)Time Position Applicant’s Actions or Behavior

45 CRS Direct operations per 1203.012A Annunciator K01 Corrective Actions.

EXAMINER NOTE: A lightning strike will cause an erroneous automatic start of the #2 EDG.CV-3807 will fail to open, resulting in a Critical Trouble alarm in approximately 3 minutes andthe diesel will trip in approximately 10 minutes if no operator actions are taken. Anticipatedaction would be for the BOP to attempt to open CV-3807 from the control room and the crewshould dispatch an operator to locally open CV-3807. When both attempts have failed thecrew should stop the EDG by taking it to Lockout.

K01-A3 – EDG2 AUTO START COMMAND

BOP 1. ENSURE that DG2 started.

BOP 2. CHECK bus A4 energized from bus A2 or DG2.

BOP 3. CHECK bus B6 energized.

ATCBOP 4. ENSURE SERV WTR to DG2 CLRS (CV-3807) opens.

CREW Dispatch Inside AO to Open CV-3807.

BOOTH OPERATOR CUE: Report after 2 minutes that CV-3807 handwheel spins freely andthe valve will not open.

BOP 5. ENSURE a Service Water pump powered from A4 running.

N/A 6. IF buses are de-energized, … N/A

ATC K01-C4 – EDG2 CRITICAL TROUBLE

CREW 1. DISPATCH an operator to Critical Local Alarms for DG2 (K1612)to determine cause of alarm.

BOOTH OPERATOR CUE: If asked, report that the cause for the Critical Trouble is HIGHWATER TEMPERATURE.

CRS 2. REFER TO Attachment C, EDG2 Critical Trouble Alarm Responsefor further instructions.

EVENT 4 CONTINUED


Page 20 of 45


Event Description:

Lightning strike causes #2 EDG to start with a failure of the Service Water Cooling Valve forthe EDG. (CV-3807)Time Position Applicant’s Actions or Behavior

CRS Attachment C – HIGH WATER TEMPERATURE

AlreadyKnown

1. DETERMINE cause of alarm.

2. INITIATE corrective action.

3. ENSURE Serv WTR to DG2 CLRS (CV-3807) open.

4. ENSURE Service Water Pressure Loop 2 is greater than 50 psig.

CRS5. IF cause can NOT be immediately corrected, AND DG2 NOT

required,THEN PERFORM 1104.036, Emergency DieselGenerator Operation, “DG2 Shutdown” section.

****CRITICAL TASK ****EDG taken to Lockout prior to an automatic trip of the diesel is required for satisfactoryperformance. Since the Auto Start signal is present, stopping the diesel with the stoppushbutton will only momentarily stop the diesel.

EXAMINER NOTE: The guidance in 1104.036 for “DG2 Shutdown” has several steps thatwould be performed for a normal shutdown, but probably will not be taken due to the urgencyof the situation. EN-OP-200, Plant Transient Response Rules, has the following guidancewhich is applicable. If an automatic control malfunctions, establish manual control.

CRS

BOPDirects BOP to place #2 EDG in Lockout

CRSReference and enter T.S. 3.8.1 Condition B for #2 EDG beingINOPERABLE.

EVENT TERMINATION CRITERIAThis event is complete when EDG is in Lockout or has tripped.


EXAMINER NOTES


Page 21 of 45

Op-Test No.: 2018-1 Scenario No.: 1 Event No.: 5 & 6

Event Description:

Dispatcher directs a power reduction to 700MWe in the next 10 minutes.ULD fails to respond to demand changeTime Position Applicant’s Actions or Behavior

50 BOOTHCall from Dispatcher to reduce Unit 1 Net generator output to 700 MWein the next 10 minutes due to grid instabilities. Insert Trigger 3 toprevent the ULD from functioning.

CRS Direct operations per 1203.045 Rapid Plant Shutdown. (Section 1)

EXAMINER NOTE:Power reduction will be to 700MWe net. The ULD reads out in gross MW, therefore will haveto be adjusted to ~730 MWe to achieve 700 MWe net. Expect the crew to maneuver at2-5%/minute.

NOTE· Shutdown rate is based on plant conditions and safety considerations. Rate may be

raised or lowered at any time as plant conditions necessitate.

· Recommended shutdown rates for RCS leaks inside containment with no additionalcomplications are as follows:

- Less than 50 gpm -- 0.5 to 5% per minute

- Greater than or equal to 50 gpm -- 5 to 10% per minute

· This procedure may be terminated at any point if a complete shutdown is not required.

· Net Generation can be monitored using PMS point JNETGEN.

· Steady state reactivity controls per COPD-030, ANO Reactivity Management Programare not applicable.

CRS 1. Commence a plant shutdown at 0.5 to 10% per minute.

CRS

2. During power reduction, PERFORM the following:

· IF power reduction is NOT due to automatic runback,THEN ENSURE ATC has been given a specific endpoint for the power reduction and rate of desired powerchange.

· IF power reduction is due to automatic runback, … N/A· DIRECT ATC to report power level at CRS desired

frequency.· IF power reduction is due to RCS leak or steam leak

inside RB, … N/A· IF necessary to maintain Makeup tank level, … N/A

EVENT 5 & 6 CONTINUED


Page 22 of 45

Op-Test No.: 2018-1 Scenario No.: 1 Event No.: 5 & 6CONTINUED

Event Description:

Dispatcher directs a power reduction to 700MWe in the next 10 minutes.ULD fails to respond to demand change


CRS

2. During power reduction, PERFORM the following: (Continued)

· IF power reduction is due to Dispatcher request,THEN as time allows, REFER TO 1107.001, Electrical SystemOperations, Attachment L, “Transmission Loading ReliefRequest”.

- ENSURE Unit 2 informed of Dispatcher request.

ATC

· Adjusts Rate of Change on controller ICC-0012 to directedsetpoint (reads out in 0.25 – 10%/min)

· If necessary,place ULD (ICC-0009) in manual· Lower ULD setpoint to ~730 MWe

ATCBOP 3. Monitor ICS and EHC subsystems for proper integrated response.

ATC Recognize and report that ICS / ULD is not responding to demandeddown power.

4. While monitoring ICS and EHC, PERFORM the following:· INITIATE manual control of ICS or EHC subsystems

as deemed appropriate by the operator for potentialfailures of control systems.- IF desired to restore automatic control of a subsystem,

THEN REFER TO 1105.004, Integrated Control System.· IF desired to stop down power above final ULD

setpoint, THEN PERFORM Operations ofSG/RX Demand Hand/Auto Station, Exhibit 1.

CRSATC

Direct ATC to place SG/RX in Hand and continue down power at directedrate of change.



Page 23 of 45


Event Description:

Dispatcher directs a power reduction to 700MWe in the next 10 minutes.ULD fails to respond to demand change


CRS

5. IF plant has been stabilized with the reactor critical, THEN:· DIRECT ATC to refer to "Contingency Reactivity Plans" located

in the Plant Data Book.

· USE 1102.004, Power Operation, Exhibit A, “Operationof APSR Group” to control imbalance (ref. Plant DataBook).

· ESTABLISH desired control bands with the ATC.(Recommended: power band is ± 2%.)

· DIRECT ATC to notify CRS if it becomes difficultmaintaining desired power band.

· IF power is oscillating greater than 2%, … N/A

· WHEN time permits,THEN PERFORM transient brief stressing reactivitycontrol aspects:

- Reactor status versus Contingency Reactivity Plan

- Review and maintain COLR limits

- Expected rod movement

· Expected boration / dilution

CRS

6. IF reducing power below 90%,THEN SECURE Zinc Injection per ONE of the following:

· REQUEST Chemistry secure Zinc Injection per1052.036, Unit 1 Reactor Coolant System(RCS) Zinc Control.

· PERFORM 1104.003, Chemical Addition,"Securing Zinc Injection" section.



Page 24 of 45

Op-Test No.: 2018-1 Scenario No.: 1 Event No.: 5 &6CONTINUED

Event Description:

Dispatcher directs a power reduction to 700MWe in the next 10 minutes.ULD fails to respond to demand changeTime Position Applicant’s Actions or Behavior

CRS 7. IF reducing power below Heater Drain Pump operation, … N/A

ATCStabilize plant power at < 700 MWe Net Generation. (Approx. 80%power)

EVENT TERMINATION CRITERIAThis event is complete when power is stable at ~700 MWe (Net)


EXAMINER NOTES


Page 25 of 45


Event Description:

Second lightning strike results in the loss of the NNI Y power supply.Time Position Applicant’s Actions or Behavior

60 ANY

Recognize and report the loss of NNI-Y power.May also :Recognize and report loss of letdown flow and pressure indication onC04.Recognize and report CV-1223 at 50%.Recognize and report CFT pressure indication lost.Recognize and report NaOH tank temperature indication lost.

BOPPerform OP-1203.012F, K07-A4 for ICS/AUX SYS POWER SUPPLYTROUBLE

N/A 1. IF reactor has tripped,… N/A

BOP

2. CHECK instrument Power Supply Status on C13 for loss of powersupply.

A. IF ANY NNI power supply lost, THEN GO TO 1203.047, Loss ofNNI Power.

B. IF ANY ICS power supply is lost, … N/A

CRS Direct operations per 1203.047 Loss of NNI Power.

NOTED11 breaker 25 supplies power to ICS and NNI Instrument Power Supply Status lights onC13.

CRS/ATC

1. Check ICS and NNI Instrument Power Supply Status lights on C13AND perform the following:

IF all indications are normal other than loss of all ICS and NNI InstrumentPower Supply Status lights on C13, THEN … N/A

Check all NNI X power available.

Check all NNI Y power available.- GO TO step 8.

EXAMINER NOTE: Attachment 3 is located in the back of the D-2 for reference if desired.

ATCBOP

8. IF only NNI Y power is lost, THEN perform the following:A. IF MFW pumps are on ∆P control, THEN … N/AB. Align NNI instrument handswitches per Attachment 3,

"Handswitch Alignment For Loss of NNI Y Power".Check NNIY AC power available.

C. Check NNI Y AC power available.

EVENT 7 CONTINUED


Page 26 of 45


Event Description:

Second lightning strike results in the loss of the NNI Y power supply.Time Position Applicant’s Actions or Behavior

NOTE· Orifice Bypass (CV-1223) fails to 50%.· Letdown Pressure indication is lost.

BOP

CRS

C. Perform the following:

1) Reset AND close NNI Y Cabinet C48 Normal Supplybreaker (RS4 Breaker 9) using “Reclosing TrippedIndividual Load Supply Breakers” section of ElectricalSystem Operations (1107.001).

2) Dispatch an operator to reset AND close NNI Y CabinetC48 Backup Supply breaker (Y01 breaker 39) using“Reclosing Tripped Individual Load Supply Breakers”section of Electrical System Operations (1107.001), whilecontinuing with this procedure.

EXAMINER NOTE:The BOP will go to back of control room to a picture of RS-4 to simulate resetting RS-4 Bkr 9.

EXAMINER CUE: Notify the BOP that RS-4 Breaker 9 is in mid-position.

BOP Reset AND close Normal supply breaker RS-4 Breaker 9.

EXAMINER CUE: Notify the BOP that RS-4 Breaker 9 has tripped open and will not reset.

CRS Dispatch an operator to reset AND close Alternate supply breaker Y01bkr 39, while continuing with this procedure.

BOOTH OPERATOR CUE: The AO will report that Y01 bkr 39 has tripped open and will notreset.

BOP Notifies the CRS that RS-4 Breaker 9 is tripped and will not reset.

8.D. Dispatch an operator to reset NNI Y power supply usingReactor Coolant System NNI (1105.006), “Resetting NNI PowerSupplies” section, while continuing with this procedure.

EVENT TERMINATION CRITERIAThis event is complete when instruments are verified selected to NNI-X power and power

supply breakers Y01 bkr 39 and RS-4 bkr 9 are reported as trippedOR

As directed by the Lead Evaluator.


Page 27 of 45

Op-Test No.: 2018-1 Scenario No.: 1 Event No.: 8, 9, & 10

Event Description:A Loss of Offsite Power will occur resulting in an automatic reactor trip.The #1 EDG will not auto start requiring the operators to manually start the EDG.EFIC fails to Auto-actuate.Time Position Applicant’s Actions or Behavior

75 ANY Recognize and report a loss of offsite power.

CRS Direct operations per 1202.001 Reactor Trip EOP.

ATC1. Depress Reactor Trip PB.

· Verify all rods inserted AND reactor power dropping.

BOP2. Depress Turbine Trip PB.

· Check Turbine throttle and governor valves closed.

ANY 3. Check adequate SCM.

EXAMINER NOTE: CRS should go to Blackout unless the BOP has already started #1 EDG,then he would go to Degraded Power. Below are the steps out of Blackout up to the point ofstarting an EDG.

CRSReports Immediate Actions complete, Transitioning to Blackoutprocedure.

CRS Direct operations per 1202.008 Blackout procedure.

CRS

1. Perform the following:

· Record time of Blackout: ____________

Direct Control Board Operators to monitor Floating Steps.****CRITICAL TASK ****

Manually actuating EFW prior to the ERV opening in automatic is required for satisfactoryperformance.

ATC(CT) 2. Verify proper EFW actuation and control (RT-5).

ATCRecognize and report that EFW has not actuated.Complete the actuation of EFW via the Remote Matrix for both trains ofEFW.

CRS

3. Notify Unit 2 of need for AAC Gen (2K9) AND attempt to restoreEDG using Annunciator K01 Corrective Action (1203.012A) andEmergency Diesel Generator Operation (1104.036), whilecontinuing with this procedure.A. IF AAC Gen becomes available, THEN energize a vitalbus using ES Electrical System Operation (1107.002), "PlacingAlternate AC Generator on bus A3 (A4)" section.B. IF a vital bus becomes energized by EDG or AAC Gen,THEN GO TO 1202.007, "DEGRADED POWER" procedure.

Event 8, 9, & 10 Continued


Page 28 of 45

Op-Test No.: 2018-1 Scenario No.: 1 Event No.: 8, 9, & 10CONTINUED


****CRITICAL TASK ****Manually starting #1 EDG within 15 minutes of the LOOP is required for satisfactoryperformance.

BOP

(CT)Recognize that #1 EDG will not automatically start on a Loss of Powerand manually start #1 EDG from C10 to energize A3.

CRS Direct operations per 1202.007 Degraded Power procedure.

CRS


· Record time of Degraded Power: ______

Direct Control Board Operators to monitor Floating Steps.

BOP 2. Verify proper operation of both EDGs (RT-21).

BOP

Step 2 Contingency Action:2. IF only one EDG OR only the AAC Gen (2K9) is in service,

THEN perform the following:

A. IF an EDG is operating,THEN verify proper operation of EDG (RT-21).

B. Verify 480V MCC B55 and 56 power supply is selected tooperating DG.

C. Align SW as follows:· Close ACW Isolation (CV-3643).· Close SW Crosstie associated with operating EDG to

isolate the idle SW Loop:

DG1 DG2 .CV-3640 CV-3644

· Close Service Water to ICW Coolers Supply associatedwith operating EDG:

DG1 DG2 .CV-3820 CV-3811

D. Attempt to restore non-running EDG using Annunciator K01Corrective Action (1203.012A) and Emergency Diesel GeneratorOperation (1104.036), while continuing with this procedure.



Page 29 of 45



CRS Dispatch an operator to restore EDG. (May not be performed as #2 EDGis known to be OOS.)

CRS

E. IF AAC Gen is available, THEN perform the following:1) Energize vital bus using ES Electrical System Operation

(1107.002), "Placing Alternate AC Generator on bus A3(A4)" section, while continuing with this procedure.

2) GO TO step 3.

CRS Requests U2 start AAC Generator.EXAMINER NOTE: At this time the AC Generator is not available. The diesel will be madeavailable at the direction of the lead examiner.BOOTH OPERATOR CUE: When the crew requests U2 to start the AAC Generator, reportthat “The AAC Generator will not come up to speed and maintenance has been contacted forimmediate repair efforts”.

CRS

F. IF AAC Gen is not available, THEN perform the following:1) Verify P36B Bus Select MOD Control selected to bus with

operating EDG.a) IF P36B MOD was transferred,THEN dispatch an operator to perform Attachment 3,“Makeup Pump P36B Alignment to Operating EDG”, whilecontinuing with this procedure.

2) Verify P4B Bus Select MOD Control selected to bus withoperating EDG.

3) IF SG press associated with de-energized ATM Dump ISOLis > 1040 psig,THEN as time permits, dispatch an operator with a radio tohand jack associated ATM Dump CNTRL to maintain SGpress 1000 to 1040 psig.(Refer to Alternate Shutdown (1203.002), Exhibit A).

ANY

3. Verify SERV WTR to DG1 and DG2 CLRs open to operating EDGs:

· CV-3806

· CV-3807



Page 30 of 45



BOP 4. Verify a Service Water pump running on each operating DG, after15-second time delay (P4A, P4B, P4C).

N/AStep 4 Contingency Actions4. IF both EDGs are operating AND only one Service Water pump

can be started, THEN perform the following: … N/A

****CRITICAL TASK ****Manually actuating EFW prior to the ERV opening in automatic is required for satisfactoryperformance.

ATC(CT)

5. Actuate MSLI for both SGs AND verify proper actuation andcontrol of EFW and MSLI (RT-6):

A. Check Instrument Air Header Press > 60 psig.B. Check Instrument Air to ATM Dump CNTRL valves remains

available.(ATC-CT) – EFW should be manually actuated before the

Electromatic Relief Valve (ERV) opens in automatic.EXAMINERS NOTE: EFW may have been manually actuated during the brief time that theplant was in a Blackout.

ATC 6. Check RCS press remains ³ 1700 psig AND PZR level remains ³30".

BOP

7. Isolate Letdown by closing either:· Letdown Coolers Outlet (RCS) (CV-1221)

OR

· Letdown Coolers Outlets (RCS):

- CV-1214

- CV-1216

ATC 8. Check OP and STBY HPI pumps off.

BOP

9. Place RCP Seals Bleedoff (Alternate Path to Quench Tank)controls in CLOSE:

· SV-1270

· SV-1271

· SV-1272

· SV-1273



Page 31 of 45



BOP

10. Perform the following to isolate RCP Seal Bleedoff (Normal):· Close RCP Seal Bleedoff (Normal) Return (CV-1274)

OR

· Close RCP Seal Bleedoff (Normal) from P32A/B/C/D:

- CV-1270

- CV-1271

- CV-1272

- CV-1273

ATC 11. IF PZR level is ³ 55", THEN verify Proportional ControlPressurizer Heaters operating in AUTO.

BOOTH OPERATOR CUE: Inform the control room that the AAC Generator is running andready to be loaded.EXAMINER NOTE: This cue can be given earlier if the lead examiner so desires.

Booth Call the control room and inform them that the AAC Generator isrunning, 2A-901 is closed, and AACG is ready to be loaded.

CRS Should return to the Step 2 contingency for energizing A4

BOP

D. IF AAC Gen is available, THEN perform the following:

1) Energize vital bus using ES Electrical System Operation(1107.002), "Placing Alternate AC Generator on bus A3(A4)" section, while continuing with this procedure.



Page 32 of 45



38.0 Placing Alternate AC Generator (2K9) on Bus A4

N/A 38.1 IF in Mode 1 – 4,AND Bus A3 and A4 will be crosstied,THEN ENTER TS 3.8.9 Condition A.

BOP 38.2 PLACE DG2 Output (A-408) in PULL-TO-LOCK.

BOP 38.3 ENSURE A2 Feed to A4 (A-409) open.

BOP 38.4 IF Alternate AC Generator is NOT supplying bus A3,THEN ENSURE A3-A4 Crossties (A-310 and A-410) open.

BOP 38.5 CHECK A4 L.O. RELAY TRIP (K02-B7) clear.

BOPCRS

38.6 REQUEST Unit 2 CRS/SM perform the following:

38.6.1 START Alternate AC Generator (2K9)

38.6.2 CLOSE AAC Generator to A3/A4 (2A-901).

Unit 2 CRS/SM _______________________________N/A 38.7 IF ES is actuated, … N/A

BOP38.8 PLACE A3-A4 Crossties (A-310 and A-410) Synchronize

switch to ON.

NOTE· When bus A4 is energized from Alternate AC Generator, then 4160V ES loads will not

automatically start even with ES signal present.

· If not overridden, then an ES signal will trip A3-A4 Crosstie breakers.

· Alternate AC Generator tie to bus A4 is a dead bus transfer only.

BOP 38.9 WHEN Unit 2 reports Alternate AC Generator is ready forloading, THEN CLOSE A4-A3 Crosstie (A-410).

BOP38.10 PLACE A3-A4 Crossties (A-310 and A-410) Synchronize

switch to OFF.



Page 33 of 45



BOPATC

12. Verify the following handswitches in PULL-TO-LOCK:· A1 and A2 feeder breakers:

Bus A1 Bus A2 A-111 A-211 A-112 A-212 A-113 A-213

· H1 and H2 feeder breakers:

Bus H1 Bus H2 H-13 H-23 H-14 H-24 H-15 H-25

· Condensate Pumps:

- P2A

- P2B

- P2C· ICW Pumps:

- P33A

- P33B

- P33C

EVENT TERMINATION CRITERIAThis event is complete when EFW has been manually actuated

AND#1 EDG has been manually started

ANDAAC Generator supplying A4


END OF SCENARIO


Page 34 of 45

ATTACHMENT 3Page 1 of 1

HANDSWITCH ALIGNMENT FOR LOSS OF NNI Y POWER

1.0 Place each handswitch in the NNI X position in accordance with the table below.

DESCRIPTION HANDSWITCH Select toNNI X ü

Panel C04Makeup Tank Level Transmitter HS-1255 XPressurizer TemperatureTransmitter HS-1001 X

Pressurizer Level Transmitter HS-1002 XRC Pressure (narrow range) HS-1038 X

Panel C03Neutron Flux HS-509 XLoop A RCS Flow HS-1029 XLoop B RCS Flow HS-1034 XLoop A T-Hot (narrow range) HS-1011 XLoop B T-Hot (narrow range) HS-1039 XLoop A T-Cold (narrow range) HS-1015 XLoop B T-Cold (narrow range) HS-1044 XLoop A T-Cold (wide range) HS-1016 XLoop B T-Cold (wide range) HS-1045 XSG A Pressure HS-2652 XSG B Pressure HS-2602 XSG A Startup Level HS-2664 XSG B Startup Level HS-2614 XSG A Main FW Flow HS-2628 XSG B Main FW Flow HS-2678 XSteam Header Pressure HS-2634 X

Panel C13SG A FW Temperature HS-2629 XSG B FW Temperature HS-2679 XSG A Downcomer Temperature HS-2665 XSG B Downcomer Temperature HS-2615 XSG A Operating Range Level HS-2659 XSG B Operating Range Level HS-2609 X


Page 35 of 45

RT-5 Page 1 of 4

VERIFY PROPER EFW ACTUATION AND CONTROL

1. Verify EFW actuation indicated on C09:

Train A: Train B:

· Bus 1 · Bus 1

· Bus 2 · Bus 2

NOTETable 1 contains EFW fill rate and level bands for various plant conditions.

2. Verify at least one EFW pump (P7A or P7B) running with flow to SG(s) throughapplicableEFW CNTRL valve(s).

SG A SG B

CV-2645 P7A CV-2647

CV-2646 P7B CV-2648

3. IF SCM is NOT adequate,THEN perform the following:

A. Select Reflux Boiling setpoint for the following:

· Train A

· Train B

NOTETable 2 contains examples of less than adequate/excessive EFW flow.

B. Verify EFW CNTRL valves operate to establish and maintain SG levels 370 to 410”.

(3. CONTINUED ON NEXT PAGE)


Page 36 of 45

Page 2 of 4VERIFY PROPER EFW ACTUATION AND CONTROL

3. (Continued)

NOTEA SG is considered available if it has the capability to be fed and steamed.

1) IF both SGs are available,THEN verify SG level rising until 370 to 410” is established.

a) IF EFW flow is less than adequate,THEN control EFW to applicable SG in HAND to maintain ³ 340 gpm toapplicable SG until level is 370 to 410”.

b) IF EFW flow is excessiveAND

> 340 gpm to either SG,THEN throttle EFW to applicable SG in HAND to limit SG depressurization.Do NOT throttle below 340 gpm on either SG until SG level is 370 to 410”.

2) IF only one SG is available,THEN feed available SG in HAND at ³ 570 gpm until SG level is 370 to 410”.

3) IF EFW is being controlled in HANDAND

SG press drops below 720 psig due to EFW flow induced overcooling,THEN continue feeding at required minimum rateAND perform the following:

a) Bypass MSLI by momentarily placing SG Bypass toggle switch on each EFICcabinet Initiate module in BYPASS.

· C37-3 · C37-4

· C37-1 · C37-2



Page 37 of 45


3. (Continued)

b) Place applicable EFW CNTRL valves in VECTOR OVERRIDE:

SG A SG B

CV-2645 P7A CV-2647

CV-2646 P7B CV-2648

c) Place applicable EFW ISOL valves in MANUAL.

SG A SG B

CV-2627 P7A CV-2620

CV-2670 P7B CV-2626

4. IF SCM is adequate,THEN perform the following:

CAUTIONExcessive EFW flow can result in loss of SCM due to RCS shrinkage.

NOTE· Table 2 contains examples of less than adequate/excessive EFW flow.

· CETs are expected to rise until natural circ conditions are established. If EFW flow control isin HAND, additional flow may not be necessary to prevent rising CETs until natural circ isestablished.

A. Verify EFW CNTRL valves operate to establish and maintain applicable SG level bandper Table 1.

1) IF EFW flow is less than adequateOR

EFW flow is excessive,THEN control EFW to applicable SG in HAND as necessary to ensure the following:

· Maintain sufficient EFW flow to prevent rise in CET temp.

· Maintain continuous EFW flow until applicable level band is reached.

· Maintain sufficient EFW flow to ensure SG level is either stableOR rising until applicable level band is reached.


Page 38 of 45


5. IF all RCPs are off,THEN check primary to secondary heat transfer in progress indicated by all of thefollowing:

· T-cold tracking associated SG T-sat (Fig. 2)

· T-hot tracking CET temps

· T-hot/T-cold DT stable or dropping

6. Monitor EMERGENCY FEEDWATER and EFIC alarms on K12.

Table 1

EFIC Automatic Level Control Setpoints

Condition Level Band Automatic Fill Rate

Any RCP running 20 to 40” No fill rate limit

All RCPs off and Natural Circ selected 300 to 340” 2 to 8”/min

All RCPs off and Reflux Boiling selected 370 to 410” 2 to 8”/min

Table 2

Examples of Less Than Adequate EFW Flow Indications

· SG level < 20” and no EFW flow indicated

· All RCPs off and EFIC level not trending toward applicable level band

Examples of Excessive EFW Flow Indications

· SG press drops ³ 100 psig due to EFW flow induced overcooling

· SCM approaching minimum adequate due to EFW flow induced overcooling

· EFW CNTRL valve open with associated SG level > applicable setpoint level band

ENDRT-5


Page 39 of 45

RT-6 Page 1 of 6

VERIFY PROPER MSLI AND EFW ACTUATION AND CONTROL

1. Verify MSLI actuation indicated for affected SG(s) on C09:

Train A: Train B:

· Bus 1 · Bus 1

· Bus 2 · Bus 2

2. Verify EFW actuation indicated on C09:

Train A: Train B:

· Bus 1 · Bus 1

· Bus 2 · Bus 2

3. Verify affected SG(s) MSIV, Main Feedwater Isolation, Main Feedwater Block, Low Load,and Startup valves closed:

SG A SG B

CV-2691 MSIV CV-2692

CV-2680Main

FeedwaterIsolation

CV-2630

CV-2625Main

FeedwaterBlock

CV-2675

CV-2622 Low Load CV-2672

CV-2623 Startup CV-2673

4. Verify affected SG(s) ATM Dump Control System operating to maintain SG press1000 to 1040 psig, unless SG depressurizes:

SG A SG B

CV-2676 ATM DumpISOL CV-2619

CV-2668 ATM Dump CNTRL CV-2618


Page 40 of 45

Page 2 of 6VERIFY PROPER MSLI AND EFW ACTUATION AND CONTROL

5. IF bad SG press is £ 600 psig and other SG press is > 600 psigOR

DP between SGs is > 150 psig and both SGs < 600 psig,THEN verify EFW ISOL and EFW CNTRL valves to bad SG closed:

SG A SG B

CV-2627 CV-2670 ISOL CV-2620 CV-2626

CV-2645 CV-2646 CNTRL CV-2647 CV-2648

NOTETable 1 contains EFW fill rate and level bands for various plant conditions.

6. Verify at least one EFW pump (P7A or P7B) running with flow to good SG(s)OR both SGs if both are £ 600 psig and DP is £ 150 psig through applicable EFW CNTRLvalves:

SG A SG B

CV-2645 P7A CV-2647

CV-2646 P7B CV-2648

7. IF SCM is NOT adequate,THEN perform the following:

A. Select Reflux Boiling setpoint for the following:

· Train A

· Train B


B. Verify EFW CNTRL valves operate to establish and maintain good SG level(s)370 to 410”.



Page 41 of 45


7. (Continued)


1) IF both SGs are available,THEN verify SG level rising until 370 to 410” is established.

a) IF EFW flow is less than adequate,THEN control EFW to applicable SG in HAND to maintain ³ 340 gpm toapplicable SG until level is 370 to 4t10”.

b) IF EFW flow is excessiveAND

> 340 gpm to either SG,THEN throttle EFW to applicable SG in HAND to limit SG depressurization.Do NOT throttle below 340 gpm on either SG until SG level is 370 to 410”.

2) IF only one SG is available,THEN feed available SG in HAND at ³ 570 gpm until SG level is 370 to 410”.

3) IF EFW is being controlled in HANDAND

SG press drops below 720 psig due to EFW flow induced overcooling,THEN continue feeding at required minimum rateAND perform the following:

a) Bypass MSLI by momentarily placing SG Bypass toggle switch on each EFICcabinet Initiate module in BYPASS:

· C37-3 · C37-4

· C37-1 · C37-2



Page 42 of 45


7. (Continued)

b) Place applicable EFW CNTRL valves in VECTOR OVERRIDE:

SG A SG B

CV-2645 P7A CV-2647

CV-2646 P7B CV-2648

c) Place applicable EFW ISOL valves in MANUAL:

SG A SG B

CV-2627 P7A CV-2620

CV-2670 P7B CV-2626

8. IF SCM is adequate,THEN perform the following:


NOTE· Table 2 contains examples of less than adequate/excessive EFW flow.

· CETs are expected to rise until natural circ conditions are established. If EFW flow control isin HAND, additional flow may not be necessary to prevent rising CETs until natural circconditions are established.

A. Verify EFW CNTRL valves operate to establish and maintain applicable SG level bandper Table 1.

1) IF EFW flow is less than adequateOR

EFW flow is excessive,THEN control EFW to applicable SG in HAND as necessary to ensure the following:

· Maintain sufficient EFW flow to prevent rise in CET temp.

· Maintain continuous EFW flow until applicable SG level band reached.

· Maintain sufficient EFW flow to ensure SG level is either stableOR rising until applicable level band is reached.


Page 43 of 45


9. IF a Condensate pump is running,THEN dispatch an operator to close bad SG Startup FW Control Valve Bypass whilecontinuing:

SG A SG B

FW-19 FW-20

10. IF all RCPs are off,THEN check primary to secondary heat transfer in progress indicated by all of thefollowing:




11. Monitor EMERGENCY FEEDWATER and EFIC alarms on K12.


Page 44 of 45


Table 1

EFIC Automatic Level Control Setpoints

Condition Level Band Automatic Fill Rate

Any RCP running 20 to 40” No fill rate limit

All RCPs off and Natural Circ selected 300 to 340” 2”/min to 8”/min

All RCPs off and Reflux Boiling selected 370 to 410” 2”/min to 8”/min

Table 2

Examples of Less Than Adequate EFW Flow Indications

· SG level < 20” and no EFW flow indicated

· All RCPs off and EFIC level not trending toward applicable level band





ENDRT-6


Page 45 of 45

RT-21 Page 1 of 1

CHECK EDG OPERATION

1. Verify running EDG(s) supplying associated ES bus(es) with proper voltage, frequency,and loading:

* 4100 to 4200 V

* 59.5 to 60.5 Hz

* ≤ 2750 KW

2. IF EDG(s) failed to start,THEN perform the following:

A. Notify CRS/SM of EDG status.

B. Check associated EDG alarms clear:

DG1 DG2

K01-A2 K01-A4

K01-B2 K01-B4

K02-B6 K02-B7

C. IF associated EDG alarms clear,THEN perform the following:

1) Notify CRS/SM of EDG status and intent to start EDG.

2) Attempt to start associated EDG at C10.

D. IF EDG failed to start,THEN dispatch an operator to investigate and report EDG malfunction.

ENDRT-21


Page 1 of 76


Examiners: _____OVERHEATING _________ Operators: ___IC-220 ______________

____________________________ _____________________________

____________________________ _____________________________

Initial Conditions:- 95% Power.- RPS failed – will not cause a reactor trip- MFW Crosstie valve will not automatically

open- C-5A in service- P-33B ICW Pump OOS for maintenance- P-3A, B, and D in service

- P-36C in service- Breaker A-112 will not

automatically open- C-5B Vacuum pump will not

automatically start- P-75 Aux FW Pump will trip after

start

Turnover:- Day shift – normal working day.- P-33B ICW Pump OOS for maintenance

-


Type*Event

Description

1 N/A N-(BOP) Swap Makeup Pumps, Place P-36B in service andremove P-36C from service.

2 CO_P3Ato OFF C-(BOP) P-3A, Circulating Water Pump, trips

3 TR049 to 0in 10

I-(ATC)(SRO)

TSLT-1001, Pressurizer Level Transmitter fails low.

4 MC008 to1200 in 30

R-(ATC)C-(BOP)C-(SRO)

Degraded Vacuum

5 N/A (SRO)TS

P-7B, Motor Driven EFW Pump, Inoperable due tooil leak.

6 FW074FW059

C-(ATC) P-1A, Main Feedwater Pump, trips with a failure ofthe crosstie valve (CV-2827) to open automatically.

7

CV1008 to0.15

B5534Open

C-(ATC)Pressurizer Spray Valve will not fully close followingthe MFWP trip pressure rise. The Spray isolationvalve breaker will trip open when the valve isattempted to close.

Continued on next page


Page 2 of 76


Type*Event

Description

8 ED630 C–(BOP) During transfer of auxiliaries Breaker A-112 will failto automatically open.

9 FW075 M-(ALL)CT

Loss of all feed water with a failure of RPS toautomatically trip the reactor.

10 CV6601A C-(ATC)CT

P-7A, Turbine Drive EFW Pump, trips.Transition to Overheating EOP

* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (CT)Critical Task


Page 3 of 76


1) Evaluate individual ability to perform Makeup Pump Operations.

2) Evaluate individual ability to recognize and Respond to Circulating WaterSystem Annunciators.

3) Evaluate individual ability to recognize when conditions require the entry intoTechnical Specifications conditions.

4) Evaluate individual ability to recognize and Respond to Pressurizer LevelIndication Malfunction.

5) Evaluate individual ability to recognize and Respond to Loss of CondenserVacuum.



8) Evaluate individual ability to recognize and respond to Loss of SteamGenerator Feed.

9) Evaluate individual ability to recognize and Respond to Pressurizer Spray ValveFailure.

10) Evaluate individual ability to Perform Transferring Buses from Unit Aux to SU1Transformer.

11) Evaluate individual ability to recognize and Respond to Reactor Trip.

12) Evaluate individual ability to recognize and Respond to Overheating.

13) Evaluate individual ability to Perform EOP Repetitive Tasks.


Page 4 of 76


Event One: Shift operating Makeup PumpsThe crew will assume plant responsibility at 95% power. The SRO will direct placing P-36B Makeup Pump in service and securing P-36C per OP-1104.002.(BOP-N)

Event Two: P-3A Circulating Water Pump TripThe crew will receive alarm K05-A1 for “A” Circulating Water Pump trip. Vacuum willdegrade slightly and the ATC should maintain power less than 100%. Once thedischarge valve for P-3A is fully closed the BOP will start P-3C Circulating Water Pump.(BOP-C)

Event Three: Pressurizer Level fails lowThe controlling pressurizer level transmitter will fail low causing annunciators on K09and a loss of pressurizer heater due to a low level interlock. (ATC-I) (SRO-TS) Thecrew should determine and select the good instrument and return the proportionalpressurizer heater controls to automatic. The CRS should enter T.S. 3.3.15 Condition A(PAM) for the failed pressurizer level transmitter (LT-1001).

Event Four: Operating vacuum pump failure / Loss of VacuumThe operating condenser vacuum pump (C-5A) will have a broken sight glass which willcause a loss of sealing water and subsequently a loss of condenser vacuum. Thestandby pump (C-5B) auto-start feature is failed as an initial condition. The crew willrecognize the lowering condenser vacuum trend and take action per AOP 1203.016.The AOP will require lowering plant power to stabilize vacuum. Once the ATC haslowered plant power at least 5%, the IAO will report the broken sight glass on C-5A.The BOP will be required to manually start C-5B and stop C-5A to regain condenservacuum (ATC-R) (BOP-C) (SRO-C).

Event Five: P-7B (EFW Pump) oil leakWhile condenser vacuum is recovering, the WCO will call to report a large amount of oilon the floor below P-7B EFW Pump and no oil visible in the Motor Outboard Bearingbull’s eye level indicator. The CRS should recognize that the given conditions result inmaking P-7B inoperable and enter T.S. 3.7.5.B for One EFW Train. (SRO-TS) Thecrew should either direct the field operators to rack down A-311 breaker for P-7B ORplace P-7B in Pull-To-Lock to prevent an automatic start of the pump. If one or theother is not performed, then P-7B will trip when EFW is actuated later in the scenario.

Event Six: Main Feedwater Pump tripThe “A” Main Feedwater Pump will trip with a failure of the cross-tie valve (CV2827) toautomatically open. The ATC should recognize the failure and manually open CV-2827in order to prevent a reactor trip. (ATC-C) (CRS-C) ICS will run back the plantautomatically. The CRS will direct operations per OP-1203.027 Loss of SG Feed andOP-1203.045 Rapid Plant Shutdown.


Page 5 of 76

Event Seven: Pressurizer Spray Valve failureDue to the loss of a MFWP, a pressure surge will cause the Pressurizer Spray Valve(CV-1008) to automatically open. When CV-1008 closes it will stick open ~15% and beindicating dual position, the unusually low RCS pressure along with additional heatersautomatically running should alert the crew to the condition. (ATC-C) When the ATCattempts to isolate CV-1008 by closing CV-1009, the breaker for CV-1009 (B-5534) willtrip open.

Event Eight: A-112 fails to automatically openWith the failed Spray Valve condition the CRS may choose to take the unit off line, if hedoes he will direct the BOP to transfer auxiliaries to SU1 transformer. When thetransfer takes place A-112, A1 supply from Unit Aux transformer will fail to automaticallyopen. The BOP will have to manually open A-112. (BOP-C) If the CRS contactsSenior Manager, Operations (Step 1.G in OP-1203.027 OR Step 11.B in OP-1203.027)he will recommend taking the unit off line.

Event Nine: Second Main Feedwater Pump trips with a failure of RPSThe second Main Feedwater Pump will trip, this will require a manual reactor trip by theATC due to the RPS failure. (CT)CT Justification:Safety significance – Failure of Reactor Protection System (RPS)Initiating Cue – Main Feedwater Pump Trip alarmMeasurable Performance Standard – Manually trip the reactor within 1 minute ofexceeding the RPS trip setpoint. This criterion is based on OP-1015.050, Time CriticalOperator Actions Program, which describes the following: “On failure of RPS trip andfailure of Main Reactor Trip pushbuttons. Within 1 minute, trip CRD backup tripbreakers (A-501 and B-631) from C03.” While this is not exactly the same situation, oneminute provides adequate time for the crew to recognize the condition and trip the plantas required.Performance Feedback – Reactor tripped, all rods inserted, and associated alarms

Event Ten: Turbine Driven EFW Pump, P-7A tripsDuring Reactor Trip follow-up actions, P-7B will trip if the crew did not rack down thebreaker earlier in the scenario and then P-7A will trip resulting in a loss of all feedwater.The CRS will transition to the Overheating EOP. The Auxiliary Feedwater Pump P-75will initially start, but will trip within 20 seconds. As directed by the lead examiner theWCO will be able to reset the Turbine driven EFW Pump, P-7A. The ATC will restoreEFW flow to both Steam Generators using RT-16. (CT)CT Justification:Safety significance – Failure of an ESF componentInitiating Cue – Report from the field that P-7A has been reset and is ready for serviceMeasurable Performance Standard – Restore EFW prior to loss of adequate SCM at<30oF due to CET temperature rise.Performance Feedback – P-7A in service with EFW flow indicated to both SteamGenerators


Page 6 of 76

Critical Task Measurable Performance Standards(CT) The ATC should trip the reactor within one minute of the second MFWPtripping.(CT) EFW should be restored to establish PSHT prior to loss of adequate SCM at<30oF due to CET temperature rise.

The scenario can be terminated when P-7A is feeding the steam generators per RT-16.



Causing an unnecessary plant trip or ESAS actuation may constitute a CT failure.Actions taken by the applicant(s) will be validated using the methodology for criticaltasks in Appendix D to NUREG-1021.


Page 7 of 76

Simulator Instructions for Scenario 2Recall IC 220Verify the following:- Install Caution Card and make status board entry for P-33B OOS.- Verify tags correct on HPI pumps (P36A ES, P36B STBY, P36C OP)Insert malfunction RP246Insert malfunction RP247Insert malfunction RP248Insert malfunction RP249Insert malfunction FW059Insert malfunction SW087Insert malfunction ED630Insert remote B2214 to OpenInsert Malfunction FW080Insert Remote CO_P3AInsert malfunction TR049 to 0 in 10Insert malfunction MC088 to 1200Insert malfunction MC088 to 0Insert malfunction FW074Insert malfunction CV1008 to 0.20Insert remote B5534 to OpenInsert malfunction FW075Insert remote TRPP7A to TRIPInsert remote RESP7A to RESETInsert remote CV6601A to 1.0Insert remote A311 to DOWNInsert Override DI_HS2805SP to True

Reactor Trip Relay KE1 FailsReactor Trip Relay KE2 FailsReactor Trip Relay KE3 FailsReactor Trip Relay KE4 FailsCV-2827 Main FW X-Tie Auto Open FailureC-5B Auto Start FailureA112 Unit Aux to A1 Fails ClosedB2214 P33B ICW Pump PowerAux Feedwater Pump P-75 TripCirc Water Pump P3A TripPZR LT1001 Fails to 0 inches in 10 secondsCondenser Vacuum Leak 1200 SCFMCondenser Vacuum Leak 0 SCFMMFW Pump 1A FailurePressurizer Spray Valve fails to 20% openB5534 CV1009 PZR Spray Isol Vlv PowerMFW Pump 1B FailureP7A Turbine Local TripP7A Turbine Trip ResetCV6601A P7A Trip Throttle Valve Open 100%A311 Racked Down P7B EFW PumpSTOP, EFW Pump P-7B, HS-2805

EventNo. Time Event

Type*Event

Description1 T=0 N-(BOP) Swap Makeup Pumps, Place P-36B in service and remove

P-36C from service.

2 T=10 C-(BOP) P-3A, Circulating Water Pump, trips.

3 T=25 I-(ATC)TS-(SRO) LT-1001, Pressurizer Level Transmitter fails low.

4 T=30R-(ATC)C-(BOP)C-(SRO)

Degraded Vacuum

5 T=40 TS-(SRO) P-7B, Motor Driven EFW Pump, Inoperable due to oil leak

6 T=50 C-(ATC) P-1A MFWP Trips with a failure of the crosstie valve toopen automatically.

7 T~80% C-(ATC) Pressurizer Spray Valve will not fully close following theMFWP trip pressure rise. The Spray isolation valvebreaker will trip open when the valve is attempted to close.

8 N/A C–(BOP) During transfer of auxiliaries Breaker A-112 will fail toautomatically open.

9 T=70 M-(ALL)CT

Loss of all feed water with a failure of RPS to automaticallytrip the reactor.

10 T=75 C-(ATC)CT

P-7A, Turbine Driven EFW Pump, trips.Transition to Overheating EOP

* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (CT) CriticalTask


Page 8 of 76


Event Description:

Place P-36B Makeup Pump in service and secure P-36C Makeup Pump per OP-1104.002.Time Position Applicants Actions or Behavior

T=0 CRS Direct BOP to place P-36B Makeup Pump in service and secure P-36CMakeup Pump per OP-1104.002 Step 9.6.1

Booth Cue: When asked report that the shaft is stopped on P-36B and the GREEN powersupply is selected locally at B-801

BOP

N/A

BOP

BOP

BOP

9.6.1 IF Makeup Pump (P-36C) is OP Pump and P-36A is ES STBYPump, THEN PERFORM pump rotation as desired per thefollowing:

A. CHECK P-36B shaft stopped.

1. IF shaft rotating clockwise when viewed from motor end,THEN ... N/A

2. IF shaft stopped AND P-36B Discharge Check (MU-19B)and MU Pump P-36B Minimum Recirc Isol (MU-22B)require testing (Caution Tag on pump handswitches),THEN RECORD in Station Log, MU-19B and MU-22Bclosure test is satisfactory.

a. NOTIFY IST Coordinator that check valve closure testis in Station Log.

b. ENSURE Caution Tag on pump handswitchesremoved per EN-OP-102, Protective and CautionTagging.

B. ENSURE P-36B Bus Mod selected to bus A-4.

C. CHECK P-64B Transfer Switch is selected to B65 by performingthe following:

· OBSERVE indicating lights under P-64B handswitches.

· Locally, CHECK green power supply selected asindicated by the three-spoked manual operating lever onthe left side of P-64B disconnect (B-801).

D. MAKE a plant announcement that P-36B will be started.

EVENT 1 CONTINUED


Page 9 of 76


Event Description:

Place P-36B Makeup Pump in service and secure P-36C Makeup Pump per OP-1104.002.Time Position Applicants Actions or Behavior

BOP E. START Aux Lube Oil Pump (P-64B).CAUTION

Simultaneous operation of Aux Lube Oil Pump (P-64A, B, C) and Makeup Pump (P-36A, B, C)is minimized to limit oil leakage at pump outboard thrust bearing

Booth Cue: When asked report that the shaft is stopped on P-36C.

BOP

BOP

BOP

BOP

BOP

BOP

BOP

BOP

CRS

F. WHEN P-64B has run for at least one minute, THEN STARTP-36B.

G. STOP P-64B.

H. START Aux Lube Oil Pump (P-64C).

I. STOP P-36C.

J. CHECK P-36C shaft stopped.

1. IF shaft rotating clockwise when viewed from motor end,THEN PERFORM “Reverse Rotation Corrective Actions”section of this procedure.

K. WHEN P-64C has run for at least one minute, THEN STOPP-64C.

L. UPDATE pump status tags as follows:

· OP Pump tag above P-36B handswitch (C16).

· STBY Pump tag above P-36C handswitch.

M. UPDATE status board with date and RCS boron concentrationfor P-36C.

N. ENSURE protected train flagging properly installed perOperations Maintenance Interface Standards and Expectations(COPD-013).

EVENT TERMINATION CRITERIAThis event is complete P-36A is in service and P-36C is secured

EXAMINER NOTES


Page 10 of 76


Event Description:

P-3A Circulation Water Pump trip.

Time Position Applicant’s Actions or BehaviorEXAMINER NOTE: When the Circulating Water Pump trips, the discharge valve will travel

closed. The standby pump cannot be started until the discharge valve for P-3A is fullyclosed.

ATC Reports annunciator K05-A1, CIRC WATER PUMP TRIP

BOP Reference OP-1203.012D (Page 2)

ATC

1. Reduce load as necessary to maintain condenser vacuum>26.5” Hg.A. IF Condenser vacuum is £ 26.5" Hg, THEN GO TO Loss of

Condenser Vacuum (1203.016).

BOP

2. For tripped Circ Water Pump, verify associated Circ Water PumpDischarge Valve closes:

· Circ Water Pump P-3A Discharge valve (CV-3629)

A. IF tripped Circ Water Pump Discharge Valve fails to close,THEN at supply breaker attempt to close valve using localhandswitch:· P-3A Circ Water Pump Discharge valve (CV-3629)

breaker B1342NOTE

Start of a circ water pump is prevented if any circ water pump discharge valve is noteither 100% closed or 100% open with the associated pump operating.

BOP

3. IF available, THEN start standby Circ Water Pump (any of P-3Athru P-3D). Reference Circulating Water and Water BoxVacuum System Operation (1104.008).

CAUTION· Stopping CW pump during radwaste release could result in Tech Spec violation.

· Stopping CW pump during chemical release (NT dump or biocide injection) could resultin violation of NPDES requirements.

EVENT 2 CONTINUED


Page 11 of 76


Event Description:



N/A 4. IF radioactive liquid release is in progress from either unit,THEN …N/A

N/A 5. IF condenser waterbox discharge temperature is >105°F,THEN … N/A

CRS 6. Initiate steps to determine cause of pump trip.

N/A7. Do NOT attempt to restart pump until cause of trip is known and

corrected.

BOP8. To clear alarm, either place HS for tripped pump to

NORMAL-AFTER-STOP position or restart the tripped pump.

EXAMINER NOTE: Due to the urgency of the situation, the CRS may just direct the BOP tostart a circulating water pump and follow-up with the procedure afterwards.

NOTEDuring a radioactive or chemical liquid release, the following are maintained to comply withrelease permit:

· The required number of Circ Water Pumps in operation.

· The required number of water box inlet valves open.

· At least one condenser water box discharging to the specific flume receiving theradioactive or chemical liquid release (except for low level releases when stated on therelease permit).

CAUTIONThis section has a Reactivity Addition Potential (RAP) and is classified as a Risk Level R2when performed with the unit at power.

BOP

9.1 IF operating at power, THEN ENSURE a Reactivity ManagementBrief has been conducted with an SRO per COPD-030, ANOReactivity Management Program.

EVENT 2 CONTINUED


Page 12 of 76


Event Description:



BOP

9.2 CHECK Circ Water Pump start interlocks are satisfied as follows:

· CHECK ONE of the following:

- Lube Water Flow Low lamp OFF on C12

- BOTH of the following checked locally:

¨ Cooling water flow from lube oil reservoir (more than2 gpm)

¨ Cooling/lubrication flow to pump (more than 13 gpm)

· CHECK ONE or more condenser Water Box Inlet Valves not100% closed.

· CHECK Circ Water Pump running with other three CircWater Pump discharge valves EITHER closed or 100%open and associated Circ pump running.

NOTEStarting a Circ Water Pump during a radwaste release will result in the releasecalculation being overly conservative due to the higher dilution flow rate.

EXAMINER NOTE: Steps 9.3 – 9.5 are checking for radioactive releases and are ALL notapplicable. Steps 9.6, 9.8, 9.9, and 9.11 are for starting each of the other three pumpsand are not applicable.

BOP 9.7 MAKE an announcement for starting a Circ Water Pump.

NOTE· Starting CW pump from Control Room will cause discharge control valve to begin

traveling open. After about 5-second time delay, the CW pump will start.

· CW pump will trip after two minutes if pump discharge control valve is not 100% open.

BOP

9.10 IF placing Circ Water Pump (P-3C) into service, THEN:

9.10.1 Firmly, PLACE Circ Water Pump P-3C handswitch(HS-3621) to START for one to two seconds (to allowactuation of start contacts).

9.10.2 On C12, CHECK P-3C Circ Water Pump DischargeValve (CV-3621) travel started by observing intermediateindication.

EVENT 2 CONTINUED


Page 13 of 76

EVENT 2 CONTINUED


Event Description:



BOP

9.10.3 After 5 second time delay, CHECK P-3C starts.

9.10.4 CHECK Discharge Pressure High lamp clear.

9.10.5 CHECK P-3C Circ Water Pump Discharge Valve(CV-3621) travels full open.

9.10.6 Periodically, MONITOR the following:

· CW and SW Pumps Motor Winding Temperatures(TR-2808) or PMS pump display

· Circulating and Service Water Pumps BearingTemperatures (TR-3651) or PMS pump display

BOP

9.12 For Chemistry:

· NOTIFY Chemistry that CW Pump start manipulation iscomplete.

· IF a radioactive release permit was submitted AND desiredto recalculate release, THEN … N/A

· IF P-3D was started, THEN … N/A

EXAMINER NOTE: The following are steps out of the Loss of Vacuum AOP and will only beutilized until vacuum is stabilized. Expect power to be maintained less than 100% as theonly action taken, since the source of the lowering vacuum is a loss of circulating water.

EVENT 2 CONTINUED


Page 14 of 76


Event Description:


Time Position Applicant’s Actions or BehaviorATC

N/A

1. COMMENCE reducing turbine load to stabilize vacuum.

· IF MWe is greater than 270 and vacuum is less than 24.5" HgTHEN TRIP the turbine.

· IF MWe is less than 270 and vacuum is less than 26.5" Hg,THEN TRIP the turbine.

CRS 2. REFER TO 1203.045, Rapid Plant Shutdown.

BOP

3. ENSURE proper condenser vacuum pump operation asfollows:

A. ENSURE BOTH Condenser Vacuum Pumps (C-5A andC-5B) running.

B. IF Condenser Vacuum Pump (C-5A/B) autostarts,THEN PLACE associated handswitch inNORMAL-AFTER-START.

C. ENSURE adequate Condenser Vacuum Pump (C-5A/B)Separator Tank (T-75A, T-75B) water level.

D. ENSURE Condenser Vacuum Pump Cooler (E-46A/B) ACWOutlet Temperature (TI-4020, TI-4022) is normal.

EVENT TERMINATION CRITERIAThis event is complete when P-3C is running.


EXAMINER NOTES


Page 15 of 76


Event Description:

Pressurizer level transmitter LT-1001 fails low.


T=25 ATC Reports annunciator K09-A3, PZR LEVEL LO LO

EXAMINER NOTE: CRS may proceed directly to the AOP.

BOP Reference OP-1203.012H (Page 16)

ATC 1. On C04, CHECK Pressurizer level indicators.

CRS 2. IF alarm is due to instrument failure, THEN GO TO 1203.015,Pressurizer Systems Failure.

EXAMINER NOTE: CRS will utilize Section 4, Pressurizer Level Indication Malfunction.

N/A1. IF all Pressurizer level indication is lost,

THEN GO TO "Loss of All Pressurizer Level Indication" section ofthis procedure.

CRS 2. IF one level indicator differs from the rest (indicator is assumedinvalid), THEN GO TO step 5.

ATC 5. WHEN validity of transmitters and indicators is determined,THEN SELECT valid Pressurizer level transmitter using HS-1002.

CRS

6. IF invalid instrument indication is greater than 16" from other levelindications, THEN:

A. DECLARE invalid instrument inoperable.

B. REFER TO Post Accident Monitoring (PAM) Instrumentation(TS 3.3.15).

ATC 7. ENSURE Pressurizer Heater Proportional Control (PIC-1004) inAUTO.

N/A 8. REFER TO “RCS Pressure, Temperature and Flow DNBSurveillance Limits” of the ANO1 COLR (TS 3.4.1).

EVENT TERMINATION CRITERIAThis event is complete when T.S. 3.3.15 Condition A is entered.


EXAMINER NOTES


Page 16 of 76


Event Description:

Operating vacuum pump (C-5A) failure / Loss of Vacuum


T=30 ATC Reports degrading vacuum if noticed ORReports annunciator K05-B2, CONDENSER VACUUM LO

EXAMINER NOTE: CRS may proceed directly to the AOP.

BOP Reference OP-1203.012D (Page 14)

CRS1. IF vacuum continues to degrade, THEN refer to Loss of Condenser

Vacuum (1203.016).

ATC

1. COMMENCE reducing turbine load to stabilize vacuum.

· IF MWe is greater than 270 and vacuum is less than 24.5" HgTHEN TRIP the turbine.

· IF MWe is less than 270 and vacuum is less than 26.5" Hg,THEN TRIP the turbine.

CRS 2. REFER TO 1203.045, Rapid Plant Shutdown.

EXAMINER NOTE: C-5B will not automatically start, the BOP will have to manually start thestandby vacuum pump to restore condenser vacuum.

BOP

3. ENSURE proper condenser vacuum pump operation asfollows:

A. ENSURE BOTH Condenser Vacuum Pumps (C-5A andC-5B) running.

B. IF Condenser Vacuum Pump (C-5A/B) autostarts, THENPLACE associated handswitch in NORMAL-AFTER-START.

C. ENSURE adequate Condenser Vacuum Pump (C-5A/B)Separator Tank (T-75A, T-75B) water level.

D. ENSURE Condenser Vacuum Pump Cooler (E-46A/B) ACWOutlet Temperature (TI-4020, TI-4022) is normal.

BOOTH OPERATOR CUE: Once power has been reduced by ~5%, report from the field thatC-5A has a broken sightglass and has lost sealing water pressure.

NOTEUnder ideal conditions, Condenser Vacuum Pumps can only achieve approximately26" Hg in hogging mode of operation.

CRS

E. IF Main Condenser vacuum continues to degrade below 26"Hg, THEN CONSIDER placing Condenser Vacuum PumpAUTO-HOG handswitches (HS-3636 and HS-3638) in HOGposition prior to vacuum dropping below 25" Hg.

EVENT 4 CONTINUED


Page 17 of 76


Event Description:



N/AF. IF outside ambient temperature is below freezing,

THEN: … N/A

NOTEThe following step automatically sets the CONDENSER VACUUM LO (K05-B2) alarmsetpoints to 24.7” or 26.7" Hg, depending upon MWe output to PMS.

BOP4. From PMS Alarm menu, SET the Transient Low Vacuum Alarm:

"Y", Enter, F3 (save).

EXAMINER NOTE: The remainder of the Loss of Condenser Vacuum AOP is looking forpossible causes of the lowering vacuum, since the problem has been identified, proceedon to the next event as desired by Lead Examiner.

BOP

5. ENSURE all available Condenser Waterbox Inlets open:

· Main Condenser E-11A South Waterbox (CV-3630)

· Main Condenser E-11A North Waterbox (CV-3626)

· Main Condenser E-11B South Waterbox (CV-3622)

· Main Condenser E-11B North Waterbox (CV-3618)

BOP

6. ENSURE available Circ Water Pumps (P-3A thru P-3D)running on C12.

A. IF Circ Water Pump(s) tripped,THEN: … N/A

EXAMINER NOTE: The next pages contain the information in Rapid Plant Shutdown.

EVENT 4 CONTINUED


Page 18 of 76


Event Description:


Time Position Applicant’s Actions or BehaviorNOTE

· Shutdown rate is based on plant conditions and safety considerations. Rate may beraised or lowered at any time as plant conditions necessitate.







ATC 1. COMMENCE power reduction at 0.5 to 10% per minute.

CRS


· IF power reduction is NOT due to automatic runback,THEN ENSURE ATC has been given a specific endpoint for the power reduction and rate of desiredpower change.

· IF power reduction is due to automatic runback, THEN … N/A

· DIRECT ATC to report power level at CRS desired frequency.

· IF power reduction is due to RCS leak or steam leak insideRB, THEN … N/A

· IF necessary to maintain Makeup tank level, THEN:

- OPEN BWST T3 Outlet to operating HPI Pump (CV-1407or CV-1408).

- MINIMIZE or ISOLATE Letdown.· IF power reduction is due to Dispatcher request,

THEN … N/A

EVENT 4 CONTINUED


Page 19 of 76


Event Description:



3. MONITOR ICS and EHC subsystems for proper integratedresponse.

4. While monitoring ICS and EHC, PERFORM the following:

· INITIATE manual control of ICS or EHCsubsystems as deemed appropriate by theoperator for potential failures of control systems.

- IF desired to restore automatic control of a subsystem,THEN REFER TO 1105.004, Integrated Control System.

· IF desired to stop downpower above final ULDsetpoint, THEN PERFORM Operations ofSG/RX Demand Hand/Auto Station, Exhibit 1.

5. IF plant has been stabilized with the reactor critical, THEN:

· DIRECT ATC to refer to "Contingency Reactivity Plans"located in the Plant Data Book.

· USE 1102.004, Power Operation, Exhibit A,“Operation of APSR Group” to control imbalance (ref.Plant Data Book).



· IF power is oscillating greater than 2%,THEN CONSIDER placing ICS Hand/ Auto Station(s) in HANDto stabilize plant power.

· WHEN time permits,THEN PERFORM transient brief stressing reactivitycontrol aspects:

- Reactor status versus Contingency ReactivityPlan

- Review and maintain COLR limits- Expected rod movement- Expected boration / dilution

EVENT 4 CONTINUED


Page 20 of 76


Event Description:


Time Position Applicant’s Actions or Behavior6. IF reducing power below 90%,

THEN SECURE Zinc Injection per ONE of the following:


PERFORM 1104.003, Chemical Addition, "Securing Zinc Injection"section.

EVENT TERMINATION CRITERIAThis event is complete when power is stabilized and vacuum is recovering.


EXAMINER NOTES


Page 21 of 76


Event Description:

P-7B (EFW Pump) oil leak

Time Position Applicant’s Actions or BehaviorBOOTH OPERATOR CUE: Call into the control room as the WCO and report that:.“There is a large amount of oil on the floor below P-7B EFW Pump and there is no oil visiblein the, Motor Outboard Bearing, bull’s eye level indicator.”

T=40 WCO Reports condition found at P-7B EFW Pump

EXAMINER NOTE: CRS may reference the oil level exhibit for EFW or immediately declareP-7B INOPERABLE and reference Technical Specifications.

Exhibit L is located at the end of this section which provides guidance.

CRS Reference OP-1107.001 Exhibit L

CRS Determine that P-7B is INOPERABLE

CRS Enter T.S. 3.7.5 Condition B

Crew Direct IAO or Work Management to rack down breaker A-311 (P-7B).

EXAMINER NOTE: If A-311 is not racked down or P-7B handswitch placed inPull-To-Lock, P-7B will trip when automatically started later in the scenario.

EVENT TERMINATION CRITERIAThis event is complete when T.S. 3.7.5 Condition B is entered.


EXAMINER NOTES


Page 22 of 76

1107.001 EXHIBIT L REVISED9/7/2016

PAGE 2 OF 2

EFW PUMP AND MOTOR P-7B LUBE OIL CHECK AND ADD

P-7B Motor Lube Oil Check1. CHECK level at bull’s-eye sightglass midpoint, with slightly higher or lower level within the

sightglass acceptable. (For Operability, oil level must be visible in bull’s-eye.)

P-7B Motor Lube Oil Addition1. OBTAIN proper oil.

(Ref. On-line ANO Lubrication Manual at All Programs\ANO Apps\Lube Oil Manual)

2. At the bearing needing oil, ENSURE grit and debris is cleaned away from the plug.

3. REMOVE the plug using a 3/4” square drive.

4. While the fill port is open, STAY at the motor. (Do NOT leave the opening unattended.)

5. ADD oil until oil level is at bull’s-eye sightglass midpoint, with slightly higher or lower level withinthe sightglass acceptable. (For Operability, oil level must be visible in bull’s-eye.)

6. Using a 3/4” square drive, RE-INSTALL the plug.

7. INITIATE action to ensure entries are made before end of shift in the following:

· Lube Oil Add Tracking database (ANO Apps)

· Station Log with component and oil volume added

REFERENCES

· Emergency Feedwater Pump Operation (1106.006) · CR-ANO-C-2004-00526-CA-26

· Tech Manual TDI075 0230, section 4 ·CR-ANO-2-2010-00120-CA-11

Oil is added at plugopposite the slinger

ring sightglass.


Page 23 of 76


Event Description:

“A” Main Feedwater Pump trip


T=50 ATC Reports annunciator K07-A7, A MFP TURBINE TRIP

EXAMINER NOTE: CRS may go directly to Loss of Steam Generator Feed

BOP Reference ACA for K07-A7

BOP1. IF Main Feedwater Pump "A" was supplying feedwater,

THEN GO TO 1203.027, Loss of Steam Generator Feed.

N/A

1. IF EITHER of the following conditions apply:

· SG level is less than 15" with no indication of recovery

· Feedwater flow is lost to EITHER SG with no indication ofrecovery with Reactor power above 7%.

THEN: … N/A

N/A2. IF both MFWPs are running

AND ONE MFWP has failed without tripping,THEN manually TRIP the failed MFWP.

EXAMINER NOTE: CV-2627 will not automatically open, in order to prevent a reactor trip,the ATC will open CV-2627 manually.

ATC 3. IF ONE MFWP is operating, THEN ENSURE that FeedwaterPumps Disch Crosstie (CV-2827) is open.

ATC 4. ENSURE power is reduced to within capacity of availablefeedwater.

CRS 5. PERFORM 1203.045, Rapid Plant Shutdown in conjunction withthis procedure.

ATC 6. OPEN Pressurizer Spray (CV-1008) in MAN as needed tomaintain RCS pressure.

ATC 7. WHEN RCS pressure is lowering, THEN ENSURE PressurizerSpray Control Mode switch in AUTO.

ATC

8. ENSURE CV-1008 closes at ONE of the following setpoints:

· Normal operation: Closes - 2155 psig

· Power >80% AND MFWP trip: Closes - 2030 psig

EVENT 6 CONTINUED


Page 24 of 76


Event Description:

“A” Main Feedwater Pump trip

Time Position Applicant’s Actions or BehaviorEXAMINER NOTE: Pressurizer Spray Valve will not close fully. The ATC should recognize

this by lower than normal RCS pressure with the spray valve indicating dual position.When the isolation valve (CV-1009) is attempted to close the breaker (B-5534) will tripopen.

ATC 9. IF CV-1008 has failed to close,THEN CLOSE Spray Isolation (CV-1009).

CRS 10. IF possible, THEN DETERMINE and CORRECT cause of loss offeed.

NOTEA feedwater line rupture in Reactor Building can be indicated by rising RBtemperature, pressure or sump level.

CRS

11. IF feedwater flow to BOTH SGs is restoredAND flow is sufficient for present power level,THEN:

A. STABILIZE plant power level.

B. CONTINUE plant operations as directed by Senior Manager,Operations.

BOOTH OPERATOR CUE: If the CRS contacts Senior Manager, Operations, he willrecommend taking the Unit off line.

N/A 12. IF feedwater flow to BOTH SGs can NOT be restored,THEN … N/A

EVENT TERMINATION CRITERIAThis event is complete power is < 40%.


EXAMINER NOTES


Page 25 of 76


Event Description:

Pressurizer Spray Valve failure


EXAMINER NOTE: Portions of Step 1 where completed during the Main Feedwater Pumptrip AOP. The following steps are from Pressurizer System Failures, Section 6

T~80%

ATC

1. IF Pressurizer Spray Valve (CV-1008) is failed open, THEN:

A. PLACE Pressurizer Spray Control Mode switch (HS-1003) inMAN.

B. ATTEMPT to close CV-1008 (modulating valve).

C. IF CV-1008 will NOT close, THEN:

1) CLOSE Pressurizer Spray Isolation Valve (CV-1009).

2) IF CRS/SM desires,THEN HOLD the handswitch in the desired position tooverride CV-1009 torque switch.

3) IF CV-1009 will NOT close AND time permits, THEN:

a. DISPATCH an operator to Pressurizer Spray BlockCV-1009 (B5534).

b. ATTEMPT to close CV-1009 using localhandswitch on breaker.

D. ENSURE Pressurizer heaters return RCS pressure tonormal.

CAUTIONTRM 3.4.3 states (in part) that the temperature difference between pressurizer and sprayfluid shall be less than or equal to 430°F.

N/A

E. IF necessary to control RCS pressure andspray line temperature, THEN CYCLEPressurizer Spray Isolation Valve (CV-1009)open and closed.

EVENT 7 CONTINUED


Page 26 of 76


Event Description:



ATCATC

BOP

F. IF both CV-1008 and CV-1009 fail to close AND RCSpressure is dropping, THEN:

1) ENSURE all PZR heaters ON.2) BEGIN reducing load to 40% at 10%/min per 1203.045,

Rapid Plant Shutdown.3) IF 4 RCPs are running

AND BOTH of the following conditions are met:

· Load is reduced to less than or equal to 675 MWe(less than or equal to 75% load)

· Reactor power is less than or equal to 75%,

THEN:

a) START one of the following:

· "C" RCP HP Oil Lift Pump (P-63C)· “C” Emergency HP Oil Lift Pump (P-80C)

b) PLACE the pump not started in Pull-to-Lock:

· "C" RCP HP Oil Lift Pump (P-63C)· “C” Emergency HP Oil Lift Pump (P-80C)

c) START both of the following:

· "C" RCP Backstop Lube Oil Pump (P-81C)· “C” Backup Backstop Lube Oil Pump

(P-82C)d) STOP "C" RCP (P-32C).

e) WHEN zero speed is indicated,THEN ENSURE the following pumps inPULL-TO-LOCK:

· P-63C· P-80C· P-81C· P-82C

EVENT 7 CONTINUED


Page 27 of 76


Event Description:



N/A

4) IF 3 RCPs runningAND all of the following conditions are met:

· Load is reduced to less than or equal to 360 MWe(less than or equal to 40% load)

· Reactor power is less than or equal to 55%,· "C" and "D" RCPs in-service

THEN: … N/A

N/A 2. IF Pressurizer Spray Valve (CV-1008) is failed closed,THEN: … N/A

N/A 3. IF an RCS pressure transmitter which is selected for control hasfailed or is failing, THEN … N/A

N/A 4. REFER TO “RCS Pressure, Temperature and Flow DNBSurveillance Limits” of the ANO1 COLR (TS 3.4.1).

EVENT TERMINATION CRITERIAAs directed by the Lead Evaluator.

EXAMINER NOTES


Page 28 of 76


Event Description:

A-112 Fails to automatically open


EXAMINER NOTE: Due to the Main Feedwater Pump trip and the failed Pressurizer Sprayvalve, the CRS will continue in the Rapid Plant Shutdown AOP. He will pick up at Step 6.

CRS

6. IF reducing power below 90%,THEN SECURE Zinc Injection per ONE of the following:· REQUEST Chemistry secure Zinc Injection per

1052.036, Unit 1 Reactor Coolant System(RCS) Zinc Control.


CRS

7. IF reducing power below Heater Drain Pump operation,THEN as time permits, PERFORM 1106.031, MSR DrainDemineralizer Operation, "Removing MSR DI From Service"section.

CREW 8. IF RCP trip or shutdown caused downpower,THEN: … N/A

NOTE· Heater Drain Pumps (P8A/B) will automatically trip if the associated T-40 pressure

drops below 75 psig or associated T-40 level drops below 42 inches. Plant historyindicates Heater Drain Pumps can be maintained in operation down to approximately50% power.

· Stopping Heater Drain Pumps (P8A and P8B) helps reduce sodium buildup insecondary chemistry.

EVENT 8 CONTINUED


Page 29 of 76


Event Description:



BOP

9. IF desired to trip Heater Drain Pumps (P8A and P8B)AND power is less than or equal to 65%, THEN:

A. TRIP Heater Drain Pumps:

· P8A· P8B

B. DISPATCH an operator to perform 1203.012E, AnnunciatorK06 Corrective Action, Exhibits A and B “Local Actions forHeater Drain Tank T-40A/T-40B Level Control on High LevelDump”.

C. On C02, ENSURE Low Level Condenser Sprays (HS-2907)open.

D. IF Polisher Bypass Valve (CS-27) is throttled open/open,THEN DIRECT Auxiliary Operators to throttle CS-27 per1102.016, Power Reduction and Plant Shutdown.

EVENT 8 CONTINUED


Page 30 of 76


Event Description:



ATC

10. WHEN MFW Block Valve Closure setpoint is approached (~45%FW Loop Demand), THEN:

· MONITOR the following ICS feedwater PDS points(as a minimum):

- FW23, MFW VLV CONTROL OUT LPA- FW27, MFW VLV CONTROL OUT LPB- FW19, LIMITED MFW FLW ERR LPA (MFW flow

error Loop A)- FW20, LIMITED MFW FLW ERR LPB (MFW flow

error Loop B)

· Upon closure of each MFW Block, CHECK ICS feedwater PDSpoints respond as expected:

- FW23 and FW 27 track together and lower withpower reduction

- FW19 and FW20 remain near zero

· IF PDS points indicate feedwater control problems are presentwith MFW Block closed,THEN:

A. ENTER Tech Spec 3.7.3, Conditions C, Dand E.B. PLACE BOTH associated Startup and LowLoad Control Valves in HAND.C. CONTROL Startup and Low Load Control Valves in

HAND to stabilize RCS parameters.

CRSATC

11. IF runback to 40% power (360 MW) has occurred,THEN CONSIDER lowering ULD in Manual to ~330 MW to stopTRIP ON LOSS OF TURB BYPASSED (K08-F3) alarm fromrecurring.

EVENT 8 CONTINUED


Page 31 of 76


Event Description:



EXAMINER CUE: Inform CRS that Ops Management recommends taking the unit off linedue to the issues with the Pressurizer Spray and the Main Feedwater Pump.

EXAMINER NOTE: During the transfer of A-1 to S/U 1, A-112 will fail to automatically open,the BOP will recognize this and take manual action to open A-112. The following pagescontain the directions from OP-1107.001.

CRS

12. IF main turbine will be taken off-lineAND power is less than or equal to 50%, THEN:

A. IF SU1 is available, THEN TRANSFER plant auxiliaries toSU1 per 1107.001, Electrical System Operations.

B. IF SU1 is unavailable, THEN: … N/A

13. WHEN Main Generator output less than or equal to 350 MW,AND main turbine will be shutdown, THEN:

A. SET Lo-Load Limit at minimum.

B. On C02, OPEN Turbine Bypass Condenser Sprays(HS-2858).

C. On C02, ENSURE HP Turbine Drains (HS-6627) open.

14. Before lowering power below 270 MWe (30%):

A. ENSURE condenser vacuum is above 26.5" Hg.

1) IF vacuum is less than 26.5" Hg,THEN PERFORM ONE of the following:

· DELAY power reduction until vacuum can berestored.

· TRIP main turbine and PERFORM 1203.018,Turbine Trip Below 43% Power.

B. ENSURE CONDENSER VACUUM LO (K05-B2) alarmsetpoints near but below current vacuum reading using PlantComputer points Y2850 and Y2851.

EVENT 8 CONTINUED


Page 32 of 76


Event Description:



EXAMINER NOTE: BOP will transfer auxiliary power to S/U 1 as follows.

8.0 Transferring Buses from Unit Aux to SU1

NOTESupplying ANO-1 from an off-site source (SU#1 or SU#2) raises the risk of a grid-initiated disturbance causing the offsite source feeder undervoltage relay to actuatewhich will trip the offsite feeder breaker(s) to A and H buses and initiate auto-transferof these buses to the selected offsite source. (Refer to CR-ANO-2-2014-0707).

BOP

N/A

8.1 CHECK SU1 Transformer is considered operable.

8.2 IF time permits, THEN ESTABLISH flash protection boundary ataffected breakers.

CAUTION· High circulating currents can trip bus lockout relay if both feeder breakers remain

closed.

· Delaying steps which open a feeder breaker when both feeder breakers are closedallows high circulating currents to develop.

BOP

8.3 IF desired to transfer A1 from Unit Aux to SU1,THEN:

8.3.1 CHECK Startup Xfmr #1 Feed to A1 (A-113) NOT inLocal.

8.3.2 PLACE A-113 Synchronize switch to ON.

8.3.3 CHECK synchroscope between 11 and 1 o'clock.

8.3.4 CLOSE A-113 and allow control switch to return toNORMAL-AFTER-CLOSE position.

8.3.5 PLACE A-113 Synchronize switch to OFF.

8.3.6 CHECK Unit Auxiliary Xfmr Feed to A1 (A-112) open.

CRITICAL STEP{4.2.3}

A. IF A-112 is NOT open, THEN TRIP A-112.

1. IF A-112 will NOT trip, THEN TRIP A-113.

2. INITIATE Condition Report.8.3.7 IF A-112 opened automatically, THEN PLACE A-112

control switch in NORMAL-AFTER-TRIP.

EVENT 8 CONTINUED


Page 33 of 76


Event Description:


Time Position Applicant’s Actions or BehaviorEXAMINER NOTE: Once A1 is powered from SU1, it is acceptable to proceed to the next

event at the discretion of the Lead Examiner. The rest of the transfers are very similarand if no issues are noted, little discriminatory value remains for the additional transfers.

BOP

8.4 IF desired to transfer A2 from Unit Aux to SU1, THEN:

8.4.1 CHECK Startup Xfmr #1 Feed to A2 (A-213) NOT inLocal.

8.4.2 PLACE A-213 Synchronize switch to ON.


8.4.4 CLOSE A-213 and allow control switch to return toNORMAL-AFTER-CLOSE position.

8.4.5 PLACE A-213 Synchronize switch to OFF.

8.4.6 CHECK Unit Auxiliary Xfmr Feed to A2 (A-212) open.


A. IF A-212 is NOT open, THEN TRIP A-212.

1. IF A-212 will NOT trip, THEN TRIP A-213.

2. INITIATE Condition Report.

8.4.7 IF A-212 opened automatically,THEN PLACE A-212control switch in NORMAL-AFTER-TRIP.

EVENT 8 CONTINUED


Page 34 of 76


Event Description:



BOP

8.5 IF desired to transfer H1 from Unit Aux to SU1, THEN:

8.5.1 CHECK Startup Xfmr #1 Feed to H1 (H-15) NOT in Local.

8.5.2 PLACE H-15 Synchronize switch to ON.


8.5.4 CLOSE H-15 and allow control switch to return toNORMAL-AFTER-CLOSE position.

8.5.5 PLACE H-15 Synchronize switch to OFF.

8.5.6 CHECK Unit Auxiliary Xfmr Feed to H1 (H-14) open.


A. IF H-14 is NOT open, THEN TRIP H-14.

1. IF H-14 will NOT trip, THEN TRIP H-15.


8.5.7 IF H-14 opened automatically,THEN PLACE H-14 controlswitch in NORMAL-AFTER-TRIP.

EVENT 8 CONTINUED


Page 35 of 76


Event Description:



BOP

8.6 IF desired to transfer H2 from Unit Aux to SU1, THEN:

8.6.1 CHECK Startup Xfmr #1 Feed to H2 (H-25) NOT in Local.

8.6.2 PLACE H-25 Synchronize switch to ON.


8.6.4 CLOSE H-25 and allow control switch to return toNORMAL-AFTER-CLOSE position.

8.6.5 PLACE H-25 Synchronize switch to OFF.

8.6.6 CHECK Unit Auxiliary Xfmr Feed to H2 (H-24) open.


A. IF H-24 is NOT open, THEN TRIP H-24.

1. IF H-24 will NOT trip, THEN TRIP H-25.


8.6.7 IF H-24 opened automatically,THEN PLACE H-24 controlswitch in NORMAL-AFTER-TRIP.

EVENT 8 CONTINUED


Page 36 of 76


Event Description:



BOP

8.7 CHECK the following bus voltages:

· 4160V buses greater than 3640V (C10)

· 6900V buses greater than 6010V (C10)

· 480V buses between 460V and 500V (SPDS E1B5/E1B6)

8.7.1 IF ANY of the above voltages require adjustment,THEN ADJUST per "Startup Transformer VoltageRegulator Operation" section of this procedure.

EVENT TERMINATION CRITERIAThis event is complete when A1, A2, H1, H2 are powered from S/U#1.


EXAMINER NOTES


Page 37 of 76

Op-Test No.: 2018-1 Scenario No.: 2 Event No.: 9 & 10

Event Description:

Second Main Feedwater Pump trips with a failure of RPSP-7A EFW Pump trips


70 ATC Reports annunciator K07-A8, B MFWP TURBINE TRIP

CRS Directs tripping the reactor and carrying out immediate actions

EXAMINER NOTE: CRITICAL TASK – crew must trip the reactor within 1 minute of thetrip of the second MFWP.

BOOTH OPERATOR CUE: Ensure P-7B tripped if breaker A-311 was not racked down.

ATC

1. Depress Reactor Trip PB.

A. Verify all rods insertedAND

reactor power dropping.

BOP 2. Depress Turbine trip PB.

A. Check Turbine throttle and governor valves closed.

BOP 3. Check adequate SCM.

CRS


· Advise Shift Manager to implement Emergency ActionLevel Classification (1903.010).

· Direct Control Board Operators to monitor floating steps


BOP6. Open BWST T3 Outlet (CV-1407 or CV-1408) to operating HPI

pump.

ATC 7. IF Emergency Boration is not in progress,THEN adjust Pressurizer Level Control setpoint to 100".

ATC 8. Control RCS press within limits of Figure 3 (RT-14).



Page 38 of 76


Event Description:

Second Main Feedwater Pump trips with a failure of RPSP-7A EFW Pump trips


EXAMINER NOTE: Electrical response is normal, the rest of Step 10 is not applicable.

BOP 9. Check for proper electrical response (RT-19).

BOOTH OPERATOR CUE: Trip P-7A EFW Pump Turbine at Lead Examiners direction.

ATC 10. Check OP HPI pump supplying normal Makeup and SealInjection.

ATC 11. Check both SG levels remain £ 410".

ATC 12. Check Instrument Air Header Press> 75 psig.

EXAMINER NOTE: NNI and ICS power is available, the rest of Step 13 is not applicable.

ATC 13. Check NNI and ICS power available (RT-20).

ATC 14. Check both SG pressures ³ 900 psig.

ATC 15. Check MSSV OPEN (K07-C5) alarm clear.

ATC

16. Check both MSIVs open:

· CV-2691

· CV-2692EXAMINER NOTE: When P-7A is tripped the CRS will transition to Overheating EOP. The

crew should direct the WCO to investigate cause of P-7A EFW Pump trip.BOOTH NOTE: When contacted as the WCO to investigate cause of trip of P-7A, start a

timer. In 10 minutes the pump will be made available to the crew.



Page 39 of 76


Event Description:

Second Main Feedwater Pump trips with a failure of RPSP-7A EFW Pump tripsTransition to Overheating EOP


CRS

1. IF any of the following criteria is met before overheating iscorrected:

· ERV opens in AUTO

· RCS press ³ 2450 psig

· RCS press approaches NDTT Limit (Figure 3)

· Overheating causes SCM to become inadequate

THEN GO TO step 5.

ATC

CRS


· Verify proper EFW actuation and control (RT-5).

· Direct Control Board Operators to monitor Floating Steps.

BOP

3. IF EFW cannot be placed in service, THEN perform the following:

A. IF Main or Aux Feedwater Pump is available,THEN refill SG using RT-16.

EXAMINER NOTE: The Auxiliary Feedwater Pump will initially start but will subsequentlytrip. This will require Step 3 Contingency Action.

ATC

A. Close Main Feedwater Isolation valves:

· CV-2630

· CV-2680

ATC

3. (Continued)B. Restore EFW using Annunciator K12 Corrective Action

(1203.012K), while continuing with this procedure.C. Place EFW CNTRL valves in HAND

AND close:

SGA SGBCV-2645CV-2646

CV-2647CV-2648



Page 40 of 76


Event Description:



ATC

3. (Continued)D. Place EFW Pump P7B in PULL-TO-LOCK.

E. Verify EFW Pump Turbine K3 Steam Admission Valves inMANUAL AND closed:

· CV-2613

· CV-2663NOTE

Leaving P-32A and P-32C running if available provides enhanced PZR spray and oneRCP running per loop.

BOP

4. Reduce running RCPs to one per loop.

A. IF SG Tube-to-Shell DT reaches 60°F (tubes hotter)AND SCM is adequate, THEN trip running RCP(s).

1) Do not restart an RCP until SG Tube-to-Shell DT is £ 50°F(tubes hotter).

EXAMINER NOTE: Overheating is not corrected, therefore Contingency Actions for Step 5will be taken. Also Step 5 would have been transitioned to if the ERV had opened inautomatic prior to reaching this point. RT-4 is located at the end of this guide. Oncethe ERV has been manually cycled a couple of times AND the Lead Examinerconcurs, inform the Control Room that P-7A is repaired.

N/A 5. IF overheating has been corrected, THEN GO TO 1202.001,"REACTOR TRIP" procedure.

BOP

5. IF any of the following criteria is met:

· ERV opens· RCS press ³ 2450 psig· RCS press approaches NDTT Limit (Figure 3)· Secondary feed not expected to become available· Overheating causes SCM to become inadequate

THEN while continuing attempts to restore secondary feed, performthe following:

A. Initiate HPI cooling (RT-4).

1) Record time full HPI flow initiated for reference in step 11:



Page 41 of 76


Event Description:



EXAMINER NOTE: The following steps are still part of Step 5 Contingency Actions.

BOP

B. IF no HPI pumps are available, … N/A

C. IF ERV cannot be opened, … N/A

D. IF SG Tube-to-Shell DT reaches 60°F (tubes hotter)AND SCM is adequate, THEN trip the running RCP(s).

1) Do not restart an RCP until SG Tube-to-Shell DT is£ 50°F (tubes hotter).

E. Continue efforts to restore feedwater AND continue with thisprocedure.

6. Check ESAS ACTUATION alarms clear on K11.

7. Check adequate SCM.

8. IF Makeup Tank level drops below 18",THEN close Makeup Tank Outlet (CV-1275).

9. Check Letdown in service.

10. Control RCS press within limits of Figure 3 (RT-14).

11. Check CET temps stable or dropping.

EXAMINER NOTE: Overheating will not be corrected, therefore Contingency Actions forStep 11 will be taken, steps contained on next page.



Page 42 of 76


Event Description:



BOP


A. IF HPI flow is < full flow from one HPI pump, … N/A

B. Hold at this point until one of the following conditions ismet:

· IF EFW becomes available,THEN GO TO step 14.

· IF Main or Aux Feedwater Pump becomes available,THEN GO TO step 13.

· IF CET temps begin to drop,THEN GO TO step 12.

· IF ≥ 120 minutes on HPI cooling elapseAND

CET temps are still rising,THEN GO TO step 19.

· IF CET temps are superheated AND moving away fromthe saturation line,THEN GO TO 1202.005, "INADEQUATE CORECOOLING" procedure.

BOOTH OPERATOR CUE: 10 minutes after being sent to check on the tripped P-7A,contact the Control Room as the WCO and report that P-7A is repaired and you are about toreset the trip condition.

14. IF EFW becomes available,THEN refill available SG(s) using RT-16.

EXAMINER NOTE: The following pages contain the actions for the different Repetitive Tasksthat will be performed during this scenario.



Page 43 of 76


Event Description:

Second Main Feedwater Pump trips with a failure of RPSP-7A EFW Pump tripsTransition to Overheating EOPRT-4 – Initiate HPI Cooling – Actions


BOP1. IF RCP Seal Injection is in service,

THEN place RCP Seal INJ Block (CV-1206) in OVRD.OTHERWISE verify RCP Seal INJ Block (CV-1206) closed.

BOP

2. Open both BWST T3 Outlets:

· CV-1407

· CV-1408

ATC 3. Verify Electromatic Relief ERV Isolation (CV-1000) open.

BOP

4. IF OP or STBY HPI pump is running,AND associated BWST Outlet is open,THEN fully open all associated HPI Block valves:

P36A/B P36B/C

CV-1219CV-1220CV-1278CV-1279

CV-1227CV-1228CV-1284CV-1285

BOP

5. Prevent dead heading HPI pumps by verifying one of thefollowing:

· Both HPI Pump RECIRC Blocks open:

- CV-1300

- CV-1301

OR

· Open HPI Block valve(s) as follows:

- Fully open one HPI Block valve associated with ES HPIpump (CV-1220 or CV-1285).

- IF OP and STBY HPI pumps are both off,THEN fully open one HPI Block valve associated with OPor STBY HPI pump (CV-1220 or CV-1285).



Page 44 of 76


Event Description:



BOP

6. Place ES HPI pump in service as follows:

A. Start AUX Lube Oil pump for ES HPI pump.

B. WHEN associated BWST T3 Outlet is open,THEN start ES HPI pump.

C. Stop AUX Lube Oil pump.

D. Fully open all associated HPI Block valves:

P36A P36C

CV-1219CV-1220CV-1278CV-1279

CV-1227CV-1228CV-1284CV-1285

E. IF ERV opens in auto,THEN perform step 11 while continuing.

N/A 7. IF OP and STBY HPI pumps are both off, … N/A

N/A 8. IF no HPI pumps are available, … N/A

BOP 9. Close HPI Pump RECIRC Block (CV-1300 or CV-1301).

N/A 10. IF only one train of HPI is available … N/A



Page 45 of 76


Event Description:



BOP

11. Perform the following to manually cycle ERV AND continue withthis procedure:

A. Open ERV.

B. WHEN either of the following criteria is met,THEN place ERV in AUTO:

· RCS press drops to 1650 psig if ES is armed

· SCM approaches minimum adequateCAUTION

Electromatic Relief ERV Isolation (CV-1000) is left open until HPI cooling is no longerrequired to maximize HPI cooling flow.

BOP

1) IF ERV fails open, THEN do NOT close ElectromaticRelief ERV Isolation (CV-1000).

C. WHEN RCS press reaches 2400 psigOR

approaches NDTT Limit on Figure 3,THEN repeat step 11 until ERV can remain open with thefollowing criteria met:

· RCS press > 1650 psig if ES is armed

· SCM adequate

D. IF ERV is closedAND

CET temp rise causes adequate SCM to be lost, without adrop in RCS press,THEN open ERVAND leave open to maximize cooling.

ATC 12. Turn off all Pressurizer Heaters.

BOP 13. Trip all but one RCP.



Page 46 of 76


Event Description:



BOP

14. Maximize RB cooling as follows:

A. Verify all four RB Cooling Fans running:

· VSF1A · VSF1C

· VSF1B · VSF1D

B. Open RB Cooling Coils Service Water Inlet/Outlet valves:

· CV-3812/CV-3814

· CV-3813/CV-3815

C. Unlatch key-locked Chiller Bypass Dampers:

· SV-7410 · SV-7412

· SV-7411 · SV-7413

BOP

15. Isolate possible RB leak paths as follows:

A. IF RB Sump draining is in progress,THEN close RB Sump to AUX Sump valves:

· CV-4400

· CV-4446

B. On C25, depress STOP for RB Leak Detector RX-7460Sample Pump Control (PB-7462).

C. On C26, close RB Leak Detector Isolations (SV-7454 andSV-7456) by placing HS-7454 in CLOSE BOTH.



Page 47 of 76


Event Description:

Second Main Feedwater Pump trips with a failure of RPSP-7A EFW Pump tripsTransition to Overheating EOPRT-16 – Feeding Intact SG – Actions


ATC

1. IF feed source is EFW, THEN perform the following:

A. Place affected SG(s) EFW CNTRL valves in HAND:

SG A SG B

CV-2645 P7A CV-2647

CV-2646 P7B CV-2648

1) Verify affected SG(s) EFW CNTRL valves demandedclosed.

B. IF EFW Pump (P7A and/or P7B) NOT runningTHEN perform the following:

1) IF EFW Pump P7A is available,THEN open either EFW Pump Turbine K3 SteamAdmission valve (CV-2613 or CV-2663).

2) IF EFW Pump P7B is available,THEN perform the following:

a) Verify EFW Pump P7B handswitch removed fromPULL-TO-LOCK.

b) Start EFW Pump P7B.

C. Place affected SG(s) EFW CNTRL valves in VECTOROVERRIDE:

SG A SG B

CV-2645 P7A CV-2647

CV-2646 P7B CV-2648



Page 48 of 76


Event Description:



ATC

D. Place affected SG(s) EFW ISOL valves in MANUAL ANDverify open (modulating valves):

SG A SG B

CV-2627 P7A CV-2620

CV-2670 P7B CV-2626

CAUTIONExcessive EFW flow can result in loss of RCS pressure control due to RCS shrinkage.


N/A E. IF SCM is NOT adequate, ... N/A


ATC

2) IF both SGs are available,THEN slowly adjust EFW CNTRL valve(s) in HAND toestablish ³ 340 gpm per SG until level is 370 to 410".

SG A SG B

CV-2645 P7A CV-2647

CV-2646 P7B CV-2648

a) IF EFW flow is excessiveAND

> 340 gpm to either SG,THEN throttle EFW to applicable SG in HAND tolimit SG depressurization.Do not throttle below 340 gpm on either SG untilSG level is 370 to 410”.



Page 49 of 76


Event Description:



ATC

1. (Continued)

3) IF only one SG is available, … N/A

4) IF any good SG press drops below 720 psig due toEFW flow induced overcooling,THEN continue feeding at required minimum rateAND perform the following:

a) Bypass MSLI by momentarily placing SG Bypasstoggle switch on each EFIC cabinet Initiatemodule in BYPASS.

· C37-3 · C37-4

· C37-1 · C37-2

b) Verify associated SG(s) EFW ISOL valves inMANUAL:

SG A SG B

CV-2627 P7A CV-2620

CV-2670 P7B CV-2626

c) Verify associated SG(s) EFW CNTRL valves inVECTOR OVERRIDE:

SG A SG B

CV-2645 P7A CV-2647

CV-2646 P7B CV-2648



Page 50 of 76


Event Description:



ATC

1. (Continued)

5) IF SCM becomes adequate prior to establishing SGlevel of 370 to 410”,THEN GO TO step 1.F.

6) WHEN SG level is 370 to 410",THEN place associated EFW CNTRL valves in AUTO:

SG A SG B

CV-2645 P7A CV-2647

CV-2646 P7B CV-2648

a) Verify SG level maintained 370 to 410".

b) Place associated EFW ISOL valves in AUTO:

SG A SG B

CV-2627 P7A CV-2620

CV-2670 P7B CV-2626



Page 51 of 76


Event Description:



ATC

1. (Continued)7) Check primary to secondary heat transfer in progress

indicated by all of the following:

· T-cold tracking associated SG T-sat (Fig. 2)T-hot tracking CET tempsT-hot/T-cold DT stable or dropping

a) IF primary to secondary heat transfer is NOT inprogress,THEN raise primary to secondary DT to40 to 60°F as follows:

(1) IF SG press drops below 720 psig duringthe following steps, THEN bypass MSLI asfollows:

(a) On Initiate module in each EFICcabinet, place each SG Bypass toggleswitch in BYPASS and release:

· C37-3 · C37-4

· C37-1 · C37-2

(b) Verify SG(s) EFW ISOL valves inMANUAL:

SG A SG B

CV-2627 P7A CV-2620

CV-2670 P7B CV-2626

(2) Adjust TURB BYP or ATM Dump ControlSystem to establish SG press within limits ofFigure 5 “SG Pressure to Establish 40 to 60°FPrimary to Secondary ΔT”.

b) Re-check primary to secondary heat transfer inprogress per step 7) above.



Page 52 of 76


Event Description:



ATC

1. (Continued)

c) IF primary to secondary heat transfer isestablished, THEN adjust TURB BYP or ATMDump Control System to stabilize RCS temp.

d) IF primary to secondary heat transfer is NOT inprogress, THEN raise primary to secondary DT to90 to 110°F as follows:

(1) Adjust TURB BYP or ATM Dump ControlSystem to establish SG press within limits ofFigure 6 “SG Pressure to Establish90 to 110°F Primary to Secondary ΔT”.

(2) IF primary to secondary heat transfer isestablished,THEN adjust TURB BYP or ATM DumpControl System to stabilize RCS temp.

8) WHEN primary to secondary heat transfer isestablished, THEN adjust associated EFW CNTRLvalve as necessary to maintain the following:

SG A SG B

CV-2645 P7A CV-2647

CV-2646 P7B CV-2648

· Adequate SCM

· £ 100°F Tube-to-Shell DT (tubes colder)

· £ 60°F Tube-to-Shell DT (tubes hotter)

· Desired cooldown rate



Page 53 of 76


Event Description:



ATC

Table 1

Examples of Excessive EFW Flow Indications· SG press drop > 100 psig due to EFW flow induced overcooling· SCM approaching minimum adequate due to EFW flow induced

overcooling· EFW CNTRL valve open with associated SG level > applicable

setpoint level bandCAUTION

Excessive EFW flow can result in loss of SCM due to RCS shrinkage.

ATC

F. IF SCM is adequate, THEN adjust affected SG(s) EFWCNTRL valve(s) in HAND as necessary to maintain thefollowing:

SG A SG B

CV-2645 P7A CV-2647

CV-2646 P7B CV-2648

· EFW flow within the following limits,until primary to secondary heat transfer is restored:

Condition Flow

Any RCP running £ 450 gpm

All RCPs off £ 200 gpm

· Adequate SCM· £ 100°F Tube-to-Shell DT (tubes colder)· £ 60°F Tube-to-Shell DT (tubes hotter)

1) IF RCPs are off,THEN check primary to secondary heat transfer inprogress indicated by all of the following:· T-cold tracking associated SG T-sat (Fig. 2)· T-hot tracking CET temps· T-hot/T-cold DT stable or dropping



Page 54 of 76


Event Description:



ATC

1. (Continued)

2) WHEN primary to secondary heat transfer isestablished, THEN adjust affected SG(s) EFW CNTRLvalve as necessary to maintain the following:

SG A SG B

CV-2645 P7A CV-2647

CV-2646 P7B CV-2648

· Adequate SCM· £ 100°F Tube-to-Shell DT (tubes colder)· £ 60°F Tube-to-Shell DT (tubes hotter)· Desired cooldown rate

G. IF TURB BYP Valves are NOT available, THEN operate ATMDump Control System to establish desired SG press:

SG A SG B


CV-2668 ATM DumpCNTRL CV-2618

H. IF associated MSIV is open and TURB BYP Valves areavailable, THEN operate TURB BYP Valves to establishdesired SG press:

SG A SG B


CV-6689CV-6690

TURB BYPValves

CV-6687CV-6688



Page 55 of 76


Event Description:



ATC

1. (Continued)

I. WHEN associated SG level is in applicable level band(preferably near midpoint),THEN place associated EFW CNTRL valve(s) in AUTO:

SG A SG B

CV-2645 P7A CV-2647

CV-2646 P7B CV-2648

1) Verify SG level maintained within applicable band:

Condition Level Band

Any RCP running 20 to 40”All RCPs off

ANDNatural Circ selected

300 to 340”

2) Place associated EFW ISOL valves in AUTO.

SG A SG B

CV-2627 P7A CV-2620

CV-2670 P7B CV-2626

J. Monitor EMERGENCY FEEDWATER and EFIC alarms onK-12.

N/A2. IF feed source is MFW or AFW, THEN perform the following:

… N/A

EVENT TERMINATION CRITERIAThis scenario is complete when EFW flow is established per RT-16.


END OF SCENARIO


Page 56 of 76

EXAMINER NOTES


Page 57 of 76

RT-4 Page 1 of 4INITIATE HPI COOLING

1. IF RCP Seal Injection is in service,THEN place RCP Seal INJ Block (CV-1206) in OVRD.OTHERWISE verify RCP Seal INJ Block (CV-1206) closed.

2. Open both BWST T3 Outlets:

· CV-1407

· CV-1408

3. Verify Electromatic Relief ERV Isolation (CV-1000) open.

4. IF OP or STBY HPI pump is running,AND associated BWST Outlet is open,THEN fully open all associated HPI Block valves:

P36A/B P36B/C

CV-1219CV-1220CV-1278CV-1279

CV-1227CV-1228CV-1284CV-1285

5. Prevent dead heading HPI pumps by verifying one of the following:


- CV-1300

- CV-1301

OR

· Open HPI Block valve(s) as follows:

- Fully open one HPI Block valve associated with ES HPI pump(CV-1220 or CV-1285).

- IF OP and STBY HPI pumps are both off,THEN fully open one HPI Block valve associated with OP or STBY HPI pump(CV-1220 or CV-1285).


Page 58 of 76

Page 2 of 4INITIATE HPI COOLING

6. Place ES HPI pump in service as follows:

A. Start AUX Lube Oil pump for ES HPI pump.

B. WHEN associated BWST T3 Outlet is open,THEN start ES HPI pump.

C. Stop AUX Lube Oil pump.

D. Fully open all associated HPI Block valves:

P36A P36C

CV-1219CV-1220CV-1278CV-1279

CV-1227CV-1228CV-1284CV-1285

E. IF ERV opens in auto,THEN perform step 11 while continuing.

7. IF OP and STBY HPI pumps are both off,THEN place OP or STBY HPI pump in service as follows:

A. IF HPI Pump (P36B) will be used,THEN verify the following selected to energized bus:

· P36B/P64B Bus Select MOD Control

· P64B Transfer Switch

B. Start AUX Lube Oil pump for OP or STBY HPI pump.

C. WHEN associated BWST T3 Outlet is open,THEN start OP or STBY HPI pump.

D. Stop AUX Lube Oil pump.

E. Fully open all associated HPI Block valves:

P36A/B P36B/C

CV-1219CV-1220CV-1278CV-1279

CV-1227CV-1228CV-1284CV-1285


Page 59 of 76


8. IF no HPI pumps are available,THEN notify CRS to perform Contingency Actions for no HPI pumps availableAND GO TO step 12.

9. Close HPI Pump RECIRC Block (CV-1300 or CV-1301).

10. IF only one train of HPI is availableAND

RCS press is > 600 psig,THEN throttle HPI Block valve with the highest flow to within 20 gpm of the nexthighest flow.

11. Perform the following to manually cycle ERV AND continue with this procedure:

A. Open ERV.

B. WHEN either of the following criteria is met,THEN place ERV in AUTO:

· RCS press drops to 1650 psig if ES is armed

· SCM approaches minimum adequate

CAUTIONElectromatic Relief ERV Isolation (CV-1000) is left open until HPI cooling is no longer required to maximizeHPI cooling flow.

1) IF ERV fails open,THEN do NOT close Electromatic Relief ERV Isolation (CV-1000).

C. WHEN RCS press reaches 2400 psigOR

approaches NDTT Limit on Figure 3,THEN repeat step 11 until ERV can remain open with the following criteria met:

· RCS press > 1650 psig if ES is armed

· SCM adequate

D. IF ERV is closedAND

CET temp rise causes adequate SCM to be lost, without a drop in RCS press,THEN open ERVAND leave open to maximize cooling.


Page 60 of 76


12. Turn off all Pressurizer Heaters.

13. Trip all but one RCP.

14. Maximize RB cooling as follows:


· VSF1A · VSF1C

· VSF1B · VSF1D


· CV-3812/CV-3814

· CV-3813/CV-3815


· SV-7410 · SV-7412

· SV-7411 · SV-7413

15. Isolate possible RB leak paths as follows:

A. IF RB Sump draining is in progress,THEN close RB Sump to AUX Sump valves:

· CV-4400

· CV-4446

B. On C25, depress STOP for RB Leak Detector RX-7460 Sample Pump Control(PB-7462).

C. On C26, close RB Leak Detector Isolations (SV-7454 and SV-7456) by placingHS-7454 in CLOSE BOTH.

END


Page 61 of 76

RT-16 Page 1 of 16FEEDING INTACT SG

1. IF feed source is EFW,THEN perform the following:

A. Place affected SG(s) EFW CNTRL valves in HAND:

SG A SG B

CV-2645 P7A CV-2647

CV-2646 P7B CV-2648

1) Verify affected SG(s) EFW CNTRL valves demanded closed.

B. IF EFW Pump (P7A and/or P7B) NOT runningTHEN perform the following:

1) IF EFW Pump P7A is available,THEN open either EFW Pump Turbine K3 Steam Admission valve(CV-2613 or CV-2663).

2) IF EFW Pump P7B is available,THEN perform the following:

a) Verify EFW Pump P7B handswitch removed from PULL-TO-LOCK.

b) Start EFW Pump P7B.

C. Place affected SG(s) EFW CNTRL valves in VECTOR OVERRIDE:

SG A SG B

CV-2645 P7A CV-2647

CV-2646 P7B CV-2648

D. Place affected SG(s) EFW ISOL valves in MANUAL AND verify open (modulatingvalves):

SG A SG B

CV-2627 P7A CV-2620

CV-2670 P7B CV-2626



Page 62 of 76

Page 2 of 16FEEDING INTACT SG

1. (Continued)

CAUTIONExcessive EFW flow can result in loss of RCS pressure control due to RCS shrinkage.


E. IF SCM is NOT adequate,THEN perform the following:

1) Select Reflux Boiling setpoint for the following:

· Train A

· Train B


2) IF both SGs are available,THEN slowly adjust EFW CNTRL valve(s) in HAND to establish ³ 340 gpm perSG until level is 370 to 410".

SG A SG B

CV-2645 P7A CV-2647

CV-2646 P7B CV-2648

a) IF EFW flow is excessiveAND

> 340 gpm to either SG,THEN throttle EFW to applicable SG in HAND to limit SGdepressurization.Do not throttle below 340 gpm on either SG until SG level is 370 to 410”.



Page 63 of 76


1. (Continued)

3) IF only one SG is available,THEN slowly adjust associated SG EFW CNTRL valve(s) in HAND to establish³ 570 gpm. Do not throttle below 570 gpm until SG level is 370 to 410”.

SG A SG B

CV-2645 P7A CV-2647

CV-2646 P7B CV-2648

4) IF any good SG press drops below 720 psig due to EFW flow inducedovercooling,THEN continue feeding at required minimum rateAND perform the following:

a) Bypass MSLI by momentarily placing SG Bypass toggle switch on eachEFIC cabinet Initiate module in BYPASS.

· C37-3 · C37-4

· C37-1 · C37-2

b) Verify associated SG(s) EFW ISOL valves in MANUAL:

SG A SG B

CV-2627 P7A CV-2620

CV-2670 P7B CV-2626

c) Verify associated SG(s) EFW CNTRL valves in VECTOR OVERRIDE:

SG A SG B

CV-2645 P7A CV-2647

CV-2646 P7B CV-2648



Page 64 of 76


1. (Continued)

5) IF SCM becomes adequate prior to establishing SG level of 370 to 410”,THEN GO TO step 1.F.

6) WHEN SG level is 370 to 410",THEN place associated EFW CNTRL valves in AUTO:

SG A SG B

CV-2645 P7A CV-2647

CV-2646 P7B CV-2648

a) Verify SG level maintained 370 to 410".

b) Place associated EFW ISOL valves in AUTO:

SG A SG B

CV-2627 P7A CV-2620

CV-2670 P7B CV-2626



Page 65 of 76


1. (Continued)

7) Check primary to secondary heat transfer in progress indicated by all of thefollowing:




a) IF primary to secondary heat transfer is NOT in progress,THEN raise primary to secondary DT to 40 to 60°F as follows:

(1) IF SG press drops below 720 psig during the following steps,THEN bypass MSLI as follows:

(a) On Initiate module in each EFIC cabinet, place each SGBypass toggle switch in BYPASS and release:

· C37-3 · C37-4

· C37-1 · C37-2

(b) Verify SG(s) EFW ISOL valves in MANUAL:

SG A SG B

CV-2627 P7A CV-2620

CV-2670 P7B CV-2626

(2) Adjust TURB BYP or ATM Dump Control System to establish SGpress within limits of Figure 5 “SG Pressure to Establish 40 to 60°FPrimary to Secondary ΔT”.

b) Re-check primary to secondary heat transfer in progress per step 7)above.



Page 66 of 76


1. (Continued)

c) IF primary to secondary heat transfer is established,THEN adjust TURB BYP or ATM Dump Control System to stabilize RCStemp.

d) IF primary to secondary heat transfer is NOT in progress,THEN raise primary to secondary DT to 90 to 110°F as follows:


(2) IF primary to secondary heat transfer is established,THEN adjust TURB BYP or ATM Dump Control System to stabilizeRCS temp.

8) WHEN primary to secondary heat transfer is established,THEN adjust associated EFW CNTRL valve as necessary to maintain thefollowing:

SG A SG B

CV-2645 P7A CV-2647

CV-2646 P7B CV-2648

· Adequate SCM




Table 1







Page 67 of 76


1. (Continued)


F. IF SCM is adequate,THEN adjust affected SG(s) EFW CNTRL valve(s) in HAND as necessary tomaintain the following:

SG A SG B

CV-2645 P7A CV-2647

CV-2646 P7B CV-2648

· EFW flow within the following limits,until primary to secondary heat transfer is restored:

Condition Flow

Any RCP running £ 450 gpm

All RCPs off £ 200 gpm

· Adequate SCM



1) IF RCPs are off,THEN check primary to secondary heat transfer in progress indicated by all ofthe following:






Page 68 of 76


1. (Continued)

2) WHEN primary to secondary heat transfer is established,THEN adjust affected SG(s) EFW CNTRL valve as necessary to maintain thefollowing:

SG A SG B

CV-2645 P7A CV-2647

CV-2646 P7B CV-2648

· Adequate SCM




G. IF TURB BYP Valves are NOT available,THEN operate ATM Dump Control System to establish desired SG press:

SG A SG B



H. IF associated MSIV is open and TURB BYP Valves are available,THEN operate TURB BYP Valves to establish desired SG press:

SG A SG B


CV-6689CV-6690

TURB BYPValves

CV-6687CV-6688



Page 69 of 76


1. (Continued)

I. WHEN associated SG level is in applicable level band (preferably near midpoint),THEN place associated EFW CNTRL valve(s) in AUTO:

SG A SG B

CV-2645 P7A CV-2647

CV-2646 P7B CV-2648

1) Verify SG level maintained within applicable band:

Condition Level Band

Any RCP running 20 to 40”All RCPs off

ANDNatural Circ selected

300 to 340”

2) Place associated EFW ISOL valves in AUTO.

SG A SG B

CV-2627 P7A CV-2620

CV-2670 P7B CV-2626

J. Monitor EMERGENCY FEEDWATER and EFIC alarms on K-12.

Table 1






Page 70 of 76


2. IF feed source is MFW or AFW,THEN perform the following:

A. Verify affected SG(s) Main and Low Load Feedwater Block closed:

SG A SG B

CV-2625Main

FeedwaterBlock

CV-2675

CV-2624Low LoadFeedwater

BlockCV-2674

B. Place affected SG(s) Startup valve in HAND AND close:

SG A SG B


C. CHECK at least one Condensate pump running.

1) IF a Condensate pump is NOT running,THEN PERFORM Condensate Pump Emergency Start per RT-23

D. Verify affected SG(s) Main Feedwater Isolation open:

SG A SG B

CV-2680Main

FeedwaterIsolation

CV-2630

E. Verify Feedwater Pumps DISCH Crosstie (CV-2827) open.



Page 71 of 76


2. (Continued)

F. IF AUX Feedwater Pump (P75) is available,THEN perform the following:

1) Dispatch an operator to verify AUX FW Pump RECIRC to E-11A Isolation(FW-1) open.

2) WHEN FW-1 open,THEN verify Aux Feedwater Pump (P75) running.

3) GO TO step 2.H.

G. IF MFW pump is available,THEN verify MFW pump running.

1) Place RFR Override handswitch in OVERRIDE.

H. IF SCM is NOT adequate,THEN establish AND maintain SG levels 370 to 410" within 25 minutes of SCM lossusing Startup valve H/A stations in HAND.

1) IF SCM becomes adequate prior to establishing 370 to 410",THEN GO TO step 2.I.

2) IF any good SG press drops below 720 psig,THEN perform the following:

a) Bypass MSLI by momentarily placing SG Bypass toggle switch on eachEFIC cabinet Initiate module in BYPASS.

· C37-3 · C37-4

· C37-1 · C37-2



Page 72 of 76


2. (Continued)

3) WHEN SG level is 370 to 410”THEN check primary to secondary heat transfer in progress indicated by all ofthe following:




a) IF primary to secondary heat transfer is NOT in progress,THEN raise primary to secondary DT to 40 to 60°F as follows:

(1) IF SG press drops below 720 psig during the following steps,THEN on Initiate module in each EFIC cabinet, place each SGBypass toggle switch in BYPASS and release:

· C37-3 · C37-4

· C37-1 · C37-2


b) Re-check primary to secondary heat transfer in progress per step 3)above.



Page 73 of 76


2. (Continued)

c) IF primary to secondary heat transfer is established,THEN adjust TURB BYP or ATM Dump Control System to stabilize RCStemp.

d) IF primary to secondary heat transfer is not in progress,THEN raise primary to secondary DT to 90 to 110°F as follows:


(2) IF primary to secondary heat transfer is established,THEN adjust TURB BYP or ATM Dump Control System to stabilizeRCS temp.

4) WHEN primary to secondary heat transfer is established,THEN adjust affected SG(s) Startup valve(s) to maintain the following:

SG A SG B


· Adequate SCM






Page 74 of 76


2. (Continued)

CAUTIONExcessive FW flow can result in loss of SCM due to RCS shrinkage.

I. IF SCM is adequate,THEN adjust associated Startup valve(s) as necessary to maintain the following:

SG A SG B


· MFW Loop flow £ 0.2x10 6 lbm/hr

· Adequate SCM



1) IF RCPs are off,THEN check primary to secondary heat transfer in progress indicated by all ofthe following:






Page 75 of 76


2. (Continued)

2) WHEN primary to secondary heat transfer is established,THEN adjust associated Startup valve(s) to maintain the following:

SG A SG B


· Adequate SCM




3) IF TURB BYP Valves are NOT available,THEN operate ATM Dump Control System to establish desired SG press:

SG A SG B



4) IF associated MSIV is open and TURB BYP Valves are available,THEN operate TURB BYP Valves to establish desired SG press:

SG A SG B


CV-6689CV-6690

TURB BYPValves

CV-6687CV-6688



Page 76 of 76


2. (Continued)

5) WHEN SG level is ³ 20",THEN perform the following:

a) IF any RCP is running,THEN perform the following:

(1) WHEN SG level is near midpoint for 20 to 40",THEN place associated Startup valve(s) in AUTO:

SG A SG B


(2) Verify SG level maintained 20 to 40".

b) IF no RCPs are running,THEN continue to raise SG level as necessary to establish and maintain300 to 340", while maintaining the following:

· MFW Loop flow £ 0.2x10 6 lbm/hr until primary to secondary heattransfer is established

· Adequate SCM




END


Page 1 of 52


Examiners: _____OVERCOOLING _________ Operators: ___IC-221____________________ ____________________________ _____________________________ ____________________________ _____________________________

Initial Conditions:- 95% Power.- P-40B in service

- P-36C in service- P-4B aligned to A3- B55/56 aligned to B6

Turnover:- Day shift – normal working day.- Y-41 in service (normal power source)- Align B55/56 to B5

- VUC-9 secured due to highbearing vibrations


Type*Event

Description1 N/A N-(BOP) Align B55/56 to B5.

2 N/A (SRO)TS

Inside AO reports low electrolyte level on D06battery bank, Cell 30. T.S. 3.8.6 Condition C

3 TR449 to620 in 30

I-(ATC)I-(BOP)

Loop B (TT-1048, NNI-Y) Tcold instrument failshigh.

4 CO_P4AC-(BOP)C-(SRO)

TS

P-4A Service Water Pump trips, momentaryinoperability on Loop I Service Water. T.S. 3.7.7Condition A

5 Several R-(ATC) P-32A, Reactor Coolant Pump, high vibrations andbearing temperatures.

6 RX150 C-(BOP)C-(ATC)

Turbine will stop responding during power reductionat ~85% power.

7 RC031 C-(ATC)C-(BOP) P-32A, RCP Sheared Shaft

8 MS131 to0.3 in 180 M-(ALL) Steam line break inside containment on “A” SG.

9 ES263CV6203 to

1.00

I-(ATC)C-(BOP)

CT

ESAS Channel 5 fails to automatically actuate onhigh Reactor Building Pressure.

10 RB Isolation Valve for Chilled Water CV-6203(Channel 6) fails to isolate.

11

CV2627 to1.00

DI_HIC2645Oto TRUE

C-(ATC)CT

Vector fails to isolate EFW Flow through FlowControl Valve CV-2645 and Flow Isolation ValveCV-2627.

* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor


Page 2 of 52


1) Evaluate individual ability to perform MCC B55 & B56 operation.


3) Evaluate individual ability to perform SASS operation with failed input.

4) Evaluate individual ability to respond to ICS Annunciators on K-07.

5) Evaluate individual ability to respond to a loss of Service Water flow.


7) Evaluate individual ability to respond to RCP motor / bearing trouble.


9) Evaluate individual ability to respond to an RCP sheared shaft.

10) Evaluate individual ability to respond to Reactor Trip.

11) Evaluate individual ability to respond to Overcooling.

12) Evaluate individual ability to perform EOP Repetitive Tasks.


Page 3 of 52


Event One: Align B55/56 to B5The crew will assume plant responsibility at 95% power. The SRO will direct aligningB55/56 to B5 per OP-1107.002, in preparations for #2 EDG maintenance later this shift.(BOP-N)

Event Two: D06 Battery Cell leakingA report from the Inside Auxiliary Operator (IAO) indicates that the electrolyte on D06Cell 30 is below the top of the plates. There is no indication of leakage. CRS will enterT.S. 3.8.6 Condition C for the low electrolyte level. (CRS-TS)

Event Three: Loop B Tcold input to ICS fails highLoop B Tcold instrument (TT-1048) fails high requiring the ATC to take ICS stations tohand per AOP 1203.001 and stabilize the plant. After determining and selecting a goodinstrument the BOP will return ICS to automatic. (ATC-I) (BOP-I)

Event Four: P-4A Service Water Pump tripsP-4A Service Water Pump will trip, resulting in a momentary loss of Loop I ServiceWater until the BOP manually starts P-4B Service Water Pump. CRS will enter T.S.3.7.7 Condition A for the duration of the loss of Loop I SW. (BOP-C) (CRS-TS)

Event Five: P-32A RCP develops high vibrations and temperaturesP-32A Reactor Coolant Pump will develop a high motor bearing and shaft vibrations andhigh motor bearing temperatures, requiring the ATC to lower power to 60 – 65% powerin preparation for stopping P-32A. (ATC-R)

Event Six: Turbine stops responding during power reductionAt ~ 85% power the Turbine EHC System will stop responding during the powerreduction. Once identified the ATC should take the SG/Rx Master station to hand toprevent ICS from raising power due to the resultant header pressure error built in duringthe turbine control issue. Once the BOP returns header pressure back to setpoint, theATC will return SG.RX Master to automatic and the BOP should continue the powerreduction with the Turbine in Operator Auto at the rate directed by the CRS. (ATC-C)(BOP-C)

Event Seven: P-32A RCP Sheared ShaftAs cued by the lead examiner or after the Heater Drain Pump is stopped, P-32A willexperience a sheared shaft. This will require the ATC to trip the reactor and the BOPwill trip the affected RCP (P-32A). (ATC-C) (BOP-C)


Page 4 of 52

Event Eight: Steam Leak in containmentPost trip a steam leak on the “A” Steam Generator will develop inside the ReactorBuilding. The leak will cause Reactor Building pressure to exceed the ESAS setpointfor building pressure resulting in a transition into the Overcooling EOP. (ALL-M)

Event Nine and Ten: Containment IsolationThe building pressure should result in ESAS Channels 1-6 actuating, however ESASChannel 5 will fail to actuate and CV-6203 (RB Isolation Valve for Chilled Water) willalso fail to close from the ESAS Channel 6 actuation signal. The critical task ofestablishing containment closure can be met by either manually actuating ESASChannel 5 and/or manually closing CV-6203. (CT)CT justification:Safety Significance – Degradation of any fission product barrierInitiating Cue – ESAS actuation and alarmsMeasurable Performance Standard – Manually actuate Channel 6 or close CV-6203prior to the BOP reporting that RT-10, Verify Proper ESAS Actuation, is completed.Performing this action prior to announcement of RT-10 complete provides reasonabletime for the crew to utilize procedural guidance to determine that the channel is failedand to implement actions to correct.Performance Feedback – Status light indication of proper containment isolation

Event Eleven: EFW Flow Control Valves / Vector IsolationThe ESAS actuation will result in an EFW actuation. Two valves in series to the faultedSteam Generator will not receive the Vector Isolation signal (CV-2645 and CV-2627)requiring the ATC to either take manual control and close CV-2645 or stop the EFWpump, P-7A, providing flow to them in order to stop the Overcooling condition. (CT)CT justification:Safety Significance – Failed ESF components resulting in exceeding cool down limitsInitiating Cue – EFIC actuation and indicated flow rateMeasurable Performance Standard – Isolating faulted flow path prior to T-cold reaching465 oF ensures excessive overcooling does not occur before corrective actions aretaken. Additional actions are required due to concerns with hydraulic lifting of fuelassemblies at temperatures below 465 oF.Performance Feedback – EFW flow, SG level, and RCS temperature

Critical Task Measurable Performance Standards(CT) Actuate ESAS Channel 5 or close CV-6203 prior to completing RT-10(CT) Take manual control of CV-2645 and isolate flow to the faulted SG or stopP-7A EFW pump providing flow through the failed flow path to the faulted SGprior to T-cold reaching 465 oF.

The scenario can be terminated when overcooling is terminated and the crew hascontrol of RCS temperature.


Page 5 of 52



Causing an unnecessary plant trip or ESAS actuation may constitute a CT failure.Actions taken by the applicant(s) will be validated using the methodology for criticaltasks in Appendix D to NUREG-1021.


Page 6 of 52

Simulator Instructions for Scenario 3Recall IC 221 – 95% PowerVerify the following:- Verify B55/56 aligned to B5- P-4A/C running and P-4B aligned to A3- P-40B in service- Scenario 3 Event File R0 open

Insert malfunction ES263Insert malfunction CV6203 to 1.00000Insert malfunction CV2627 to 1.00000Insert malfunction TR449 to 620.00000 in 30Insert remote CO_P4A to OFFInsert override AO_TR6500A to 215.39999 in 360Insert override AO_TR6500B to 192.50000 in 600Insert override AO_TR6500C to 195.60001 in 360Insert malfunction RC511 to 18.60000 in 300Insert malfunction RC512 to 15.60000 in 360Insert malfunction RC515 to 22.20000 in 360Insert malfunction RC516 to 19.20000 in 300Insert malfunction RC031Insert malfunction MS131 to 0.84780 in 180

Delete malfunction CV6203 to 1.00000Insert malfunction CV2645 to 0.30000Delete malfunction RC511 to 18.60000Delete malfunction RC515 to 22.20000Delete malfunction RC516 to 19.20000Delete override AO_TR6500A to 215.39999Delete override AO_TR6500B to 192.50000Delete override AO_TR6500C to 195.60001Insert malfunction K08A8 to NORMALInsert malfunction K08A8 to ON

ESAS CHANNEL 5 FAILS TO ACTUATECH WS RB OUTLET ISOEFW P-7A to SG A ISOLLOOP B TC (TT1048) {NNIY} 520-620 DEG FCO_P4A SERVICE WATER PUMP P4ARC P32A MTR BRG THRUST,PT 1RC P32A MTR BRG 1,PT 2RC P32A MTR BRG 2,PT 3VE6500AX P-32A UPPER MOTOR X VIBVE6500AY P-32A UPPER MOTOR Y VIBVBE6500X P-32A PUMP SHAFT X VIBVBE6500Y P-32A PUMP SHAFT Y VIBRCP SHEARED SHAFT P32AA MAIN STEAM LINE RUPTURE INSIDE REACTORBUILDING 0-3.14 SQ. FT.CH WS RB OUTLET ISOEFW P-7A to SG A CNTRLVE6500AX P-32A UPPER MOTOR X VIBVBE6500X P-32A PUMP SHAFT X VIBVBE6500Y P-32A PUMP SHAFT Y VIBRC P32A MTR BRG THRUST,PT 1RC P32A MTR BRG 1,PT 2RC P32A MTR BRG 2,PT 3K08 RCP MOTOR BRG TEMP HIK08 RCP MOTOR BRG TEMP HI

EventNo. Time Event Type Event Description

1 T=0 N-(ATC) Align B55/56 to B5.

2 T=10 C-(SRO)TS

Inside AO reports low electrolyte level on D06 battery bank,Cell 30. T.S. 3.8.6 Condition C

3 T=15 I-(ATC)I-(BOP) Loop B (TT-1048, NNI-Y) Tcold instrument fails high.

4 T=55 C-(BOP)TS

P-4A Service Water Pump trips, momentary inoperability onLoop I Service Water. T.S. 3.7.7 Condition A

5 T=60 R-(ATC) P-32A, Reactor Coolant Pump, high vibrations and bearingtemperatures.

6 85% C-(BOP)C-(ATC)

Turbine will stop responding during power reduction at ~85%power.

7 T=70 C-(ATC)C-(BOP) P-32A, RCP Sheared Shaft

8 T=85 M-(ALL) Steam line break inside containment on “A” SG.

9N/A

I-(ATC)C-(BOP)

CT

ESAS Channel 5 fails to automatically actuate on highReactor Building Pressure.

10 RB Isolation Valve for Chilled Water CV-6203 (Channel 6)fails to isolate.

11 N/A C-(ATC)CT

Vector fails to isolate EFW Flow through Flow Control ValveCV-2645 and Flow Isolation Valve CV-2627.


Page 7 of 52


Event Description:Align B55/56 to B5

Time Position Applicants Actions or BehaviorNOTE

· The following conditions require MCC B55 and B56 to be powered from bus B5:

- Power is lost to B6

- DG2 becomes inoperable for greater than 1 hour

- Control Room Emergency Cooler (2VUC-27A/B and 2VE-1 A/B) is powered fromMCC B64

· Power is momentarily lost during the B55/56 transfer, resulting in the following:

- MCC B55/56 LOSS OF VOLTAGE (K02-B8)

- Control Room lighting powered from B56 is interrupted during the transfer.

- If Inverter Y41 is on alternate source, then Plant Computer will be lost.

· If Control Room Emergency Ventilation Control Cabinets (C141/C141B) are selected toALTERNATE power, then transferring B55 and B56 will result in Control Room Isolationdue to loss of power.

CAUTION· The alignment of B55/56 to the opposite electrical train from Service Water Pump (P-4B)

creates additional risk when P-4A or P-4C is out of service. This is due to B55/56supplying power to ACW Loop Isolation Valve (CV-3643). Therefore it is desirable toalign P-4B and B55/56 to the same electrical train when both EDGs are operable.CR-ANO-1-02-0074-2

· When B55/56 are not aligned to the same power supply as P-4B, a single failure during aDesign Basis Accident (DBA) of a loss of the opposite train ES power could result in theremaining Service Water Pump potentially driven to a runout condition supplying all its looploads and Auxiliary Cooling Water. CR-ANO-1-2013-2671

T=0 BOP

15.1 PERFORM the following to transfer MCC B55/56 to B5:

15.1.1 ENSURE the following are secured:

· Spent Fuel Pool Circ Pump (P-40B)

· Turb Gen Turning Gear (K-6)

· Turb Gen HP Lift Oil Pump (P-76)

· Turb Gen Bearing Oil Pump (P-20)

· Control Room Emerg A/C Unit Assembly (VUC-9)

EVENT 1 CONTINUED


Page 8 of 52


Event Description:Align B55/56 to B5


BOP 15.1.2 CHECK Control Rm Air Emergency Recirc (VSF-9) secured.

BOP 15.1.3 CHECK Boric Acid Pump (P-39A or P-39B) secured.

BOP

15.1.3 PERFORM ONE of the following:

· At C10, momentarily SELECT B5 with the 480V AC MCC B55& 56 POWER SUPPLY SELECTOR switch.

· At MCC B56, DEPRESS B5 pushbutton.

BOP 15.1.4 CHECK transfer to B5 by observing indicator lights on C10or MCC B56.

BOP

15.1.5 IF any of the following was secured for B55/56 transfer,THEN RESTART as needed:

· Spent Fuel Pool Circ Pump (P-40B)

· Turb Gen Turning Gear (K-6)

· Turb Gen HP Lift Oil Pump (P-76)

· Turb Gen Bearing Oil Pump (P-20)

· Control Room Emerg A/C Unit Assembly (VUC-9)EVENT TERMINATION CRITERIA

This event is complete when B55/56 are powered from B5OR


EXAMINER NOTES


Page 9 of 52


Event Description:Inside AO Reports low electrolyte level on D06 Battery Bank, Cell 30


EXAMINER NOTE: D06 is the 125 VDC Station Battery Bank to Bus D02.

BOOTH OPERATOR CUE: Call the control room as the IAO and report the following:“The electrolyte on D06 Cell 30 is below the top of the plates”. If asked, there are no signs ofleakage from the battery cell.

T=10 CRS Acknowledge communication from the Inside AO pertaining to D06.

CRS Reference OP-1107.002, Battery and 125 VDC Distribution procedure.

CRS Reference Technical Specifications

CRS Enter T.S. 3.8.6. Condition C – Required Actions C.1, C.2, AND C.3

CRS Update Crew on status of Green Train Battery and T.S. entry.

EVENT TERMINATION CRITERIAThis event is complete when SRO updates crew on T.S. entry.


EXAMINER NOTES


Page 10 of 52


Event Description:Loop B Tcold instrument fails high (TT-1043, NNI-Y)


T=15 ATC Acknowledge and report Annunciator K07B4 SASS MISMATCH.

ATC Recognize and report Loop B Tcold instrument failing high.

ATC

1. PLACE BOTH MFW Pump H/A Stations in HAND:

· MFW Pump A H/A

· MFW Pump B H/A

ATC 2. PLACE Diamond Panel in MANUAL.

ATC 3. CHECK Turbine Header pressure is stable between 880 and 920psig.

EXAMINER NOTE: Steps 4, 5 and 7 are not applicable for the given conditions.

ATC

6. ADJUST the following as necessary to stabilize RCS temp andmaintain power below 100%:

· Diamond Panel

· MFW Pump A H/A

· MFW Pump B H/A

CRS 8. GO TO the appropriate section of this procedure for the associatedequipment failure. (Section 4)

EXAMINER NOTE: The following steps are from Section 4.

ATC

1. PLACE the following in HAND:

· Feedwater Loop A Demand H/A

· Feedwater Loop B Demand H/A

ATC

2. PERFORM the following:

· ENSURE Diamond Panel in MANUAL.

· PLACE RX Demand H/A in HAND.

EVENT 3 CONTINUED


Page 11 of 52




ATC 3. Using applicable MFW Pump Loop H/A, LOWER the highest FWFlow to maintain DTc less than 5°F.

ATC

4. SELECT the good RCS T-cold instrument for indication:

· Loop A T-Cold:

- TT-1015

- TT-1018

· Loop B T-Cold:

- TT-1044

- TT-1048

Crew 5. PROCEED as directed by CRS/SM.

EXAMINER NOTE: Once Feedwater flow is adjusted to restore RCS Tave and power isstabilized, the crew should return ICS to automatic per OP-1105.004 Section 8.0.Unlike Scenario 1, this will require some manipulations be made in order to complete thetransfer to automatic.

8.0 Transferring Major ICS Control Stations to AUTO

CAUTIONThe following section has been determined to have a Reactivity Addition Potential (RAP)and this activity is classified as a Risk Level R2 (<5% power change).

8.1 Initial conditions:· Diamond Panel in Manual, if applicable

· RX Demand in HAND

· Feedwater Demand Loop A in HAND

· Feedwater Demand Loop B in HAND

· Load Ratio DT-cold in HAND

· ULD Unit Master Station in HAND

· Reactivity Management Brief performed per COPD-030 with anSRO

EVENT 3 CONTINUED


Page 12 of 52




NOTE· With the major stations in HAND, and the plant in a stable (balanced) condition, aligning

all stations prior to returning any station to AUTO will provide a controlled, bumplessreturn to full automatic.

· Description section 3.1 of this procedure contains “Expected and normal indicationswhen transferring H/A stations to manual”.

BOP8.2 IF MEAS VAR can NOT be aligned,

THEN GO TO the appropriate section for transferringstation with misaligned MEAS VAR to AUTO.

N/A 8.3 IF SG/RX Demand in AUTO, … N/A

BOP 8.4 Verify Turbine in INTEG CONTROL, controlling TurbineHeader pressure at setpoint.

CAUTIONTo ensure bumpless transfer, a transfer of H/A station from HAND to AUTO is not madewithout first minimizing error between:

· MEAS VAR and POS on controller for H/A stations other than ULD

· Current power and PMS CTP input for ULD

BOP

8.5 Check MEAS VAR on both FW Loop Demand stations onthe caret.

8.5.1 IF required,THEN drive SG/RX Demand in HAND untileither limit below is met:

· MEAS VARs for Feedwater DemandLoop A and Feedwater Demand Loop Bare at the caret.

· Indicated error is split between the twoMEAS VARs.

8.5.2 IF error between the two loops differs,THEN drive Load Ratio DT-cold H/A station inHAND to remove difference.

EVENT 3 CONTINUED


Page 13 of 52




BOP

8.6 Check T-ave is at setpoint.

8.6.1 IF required,THEN perform one or both of the following:

· Move rods in MANUAL.

· Adjust feedwater flow to bring T-ave tosetpoint.

A. Return to step 8.5.

BOP 8.7 Check RX Demand MEAS VAR on the caret.

BOP 8.8 Check SG/RX H/A station POS and MEAS VAR areapproximately equal.

BOP

8.9 Place stations in AUTO as follows:

8.9.1 Diamond Panel, if applicable

8.9.2 RX Demand

8.9.3 Feedwater Loop Demands:

· Loop A FW Loop Demand

· Loop B FW Loop Demand

8.9.4 Load Ratio DT-cold

8.9.5 SG/RX Demand

BOP 8.10 Check UNIT MASTER IN TRACK (K07-A1) alarm clear.

EVENT TERMINATION CRITERIAThis event is complete when ICS is in Automatic and UNIT MASTER IN TRACK alarm clear.


EXAMINER NOTES


Page 14 of 52


Event Description:P-4A Service Water Pump Trip


EXAMINER NOTE:Service Water Pump Trip can be addressed by either the Annunciator Corrective Actions orthe AOP guidance, the following is the guidance contained in the ACA

T=55 ATC Acknowledge and report Annunciator K10-A3 SERV WATER PUMPTRIP.

CAUTION· Failure of traveling screens can result in clogging of SW pump discharge

strainers.

· SW pump operation with bay level <332' can damage pump.

· Attempting to reclose breaker with protective relay tripped can damage motorand circuit components.

N/A1. IF SW is lost to in-service DH Cooler (E-35A or E-35B), THEN refer

to Loss of Service Water (1203.030) before starting standby SWPump (any of P-4A thru P-4C).

N/A 2. IF trip was caused by bus undervoltage, THEN …N/A

CRS

3. IF operating SW pump strainers are NOT clogged AND SW Baylevels are >332', THEN perform the following:

A. Perform the appropriate sub-section to start the standbySW pump (P4A, B or C).

B. IF the operating SW pump trips, THEN check protective relays.

· Refer to "Closing Tripped Individual Load Supply Breakers"section of Electrical System Operations (1107.001).

EVENT 4 CONTINUED


Page 15 of 52

Op-Test No.: 2018-1 Scenario No.: 3 Event No.: 4Continued

Event Description:P-4A Service Water Pump Trip


BOP

4. IF P-4A tripped due to unknown cause AND P-4B is the standbypump, THEN perform the following to start P-4B:

A. Verify P-4B Bus Select MOD Control switch is selected toBus A3.

B. Verify P-4B MOD closed on bus A3.

C. Check P-4A to P-4B Crossties (CV-3644 and CV-3646) areopen.

1) IF P-4A to P-4B Crossties (CV-3644 and CV-3646) closed,THEN … N/A

D. Attempt to start P-4B from C18.

E. IF only 1 SW pump is operating AND a second SW pump canNOT be quickly restored, THEN GO TO Loss of Service Water(1203.030).

EXAMINER NOTE: Technical Specification 3.7.7 Condition A should be entered during thetime that only one Service Water Pump is running. At this point it is no longer an issue, ifthe applicant does not enter the LCO, then follow up with the applicant after the scenario.

CRS 9. Refer to TS 3.7.7 for operability requirements.

BOP

10. To clear alarm, perform one of the following:

A. Place the tripped pump HS to NORMAL-AFTER-STOP orPULL-TO-LOCK.

B. Reclose tripped breaker per "Reclosing Tripped Individual LoadSupply Breakers" section of Electrical System Operations(1107.001).

EXAMINER NOTE: Technical Specification 3.7.7 Condition A - A.1 would have you look atentering LCO 3.8.1 for #1 EDG and OP-1104.029 provides guidance for handling anInoperable SW Loop, which can be discussed following the scenario.

EVENT TERMINATION CRITERIAThis event is complete when P-4B SW Pump is in service and the CRS has momentarily

entered T.S. 3.7.7 Condition AOR



Page 16 of 52


Event Description:

P-4A Service Water Pump Trip


EXAMINER NOTE:Service Water Pump Trip can be addressed by either the Annunciator Corrective Actions orthe AOP guidance, the following is the guidance contained in the AOP.

T=55 ATC Acknowledge and report Annunciator K10-A3 SERV WATER PUMPTRIP.

CRS Enter P-1203.030, Loss of Service Water AOP

CRS

1. IF Service Water Pump trips for unknown causesAND no Bay Level or Pump Strainer problems exist,THEN PERFORM Attachment B, Placing Standby Service WaterPump Into Service.

EXAMINER NOTE: The following is from Attachment B, which does not prompt the CRS toreference T.S. 3.7.7.

BOP

1. IF P-4A tripped due to unknown cause AND P-4B is the standbypump, THEN START P-4B as follows:

A. ENSURE P-4B Bus Select MOD Control switch is selected toBUS A3.

B. ENSURE P-4B MOD closed on bus A3.

C. ENSURE P-4A to P-4B Crossties (CV-3644 and CV-3646)are open.

D. START P-4B from C18.

EXAMINER NOTE: T.S. 3.7.7 Condition A should be entered during the time that only oneService Water Pump is running. At this point it is no longer an issue, if the applicant doesnot enter the LCO, then follow up with the applicant after the scenario.

Technical Specification 3.7.7 Condition A - A.1 would have you look at entering LCO 3.8.1 for#1 EDG and OP-1104.029 provides guidance for handling an Inoperable SW Loop, whichcan be discussed following the scenario.

EVENT TERMINATION CRITERIAThis event is complete when P-4B SW Pump is in service and the CRS has momentarily

entered T.S. 3.7.7 Condition AOR

As directed by the Lead Evaluator.EXAMINER NOTES


Page 17 of 52


Event Description:P-32A RCP develops high vibration and temperature.Tim

e Position Applicant’s Actions or Behavior

T=60

ATC Acknowledge and report Annunciator K08-B6 RCP VIBRATION HI

ATCLook at C13 status lights for RCP Vibration and determine that P-32A isin alarm

EXAMINER NOTE: C15 is not modeled in the simulator. Vibration information is available onPDS. Inform the applicant to utilize PDS in place of C15, Step 3 below cannot beperformed

BOP1. At C15, DETERMINE which pump and parameter is in alarm by

observing Reflash Unit (VBAY-6503).NOTE

· This alarm indicates a monitor has exceeded the ALERT or DANGER setpoint foreither motor vibration or shaft vibration. Shaft axial position modules may also beconfigured to actuate this alarm.

· Analysis of vibration data by Predictive Maintenance should be able to detect pumpshaft crack propagation and allow pump shutdown before pump failure. Pump shaftphase angle trends (used for determining pump shaft crack issues) are available onPlant Data Server.

CRS 2. NOTIFY Predictive Maintenance to collect and analyze data.

BOOTH OPERATOR CUE: Inform the CRS that the indication is valid and data analysis is inprogress.

NotModeled

insimulator

3. Observing value of alarming parameter:

A. At RCP Vib Mon PC Display (VBPC-6501), DETERMINE theaffected RCP.

B. ENSURE Bargraph Display for the affected RCP is displayed.

C. APPLY the meter scale that corresponds to parameter being readto read the parameter value below bar on display.

D. READ setpoint for alarming parameter under POINT ACTIVITIESdrop-down menu and selecting “Adjust Setpoints”.

CRS4. REFER TO 1203.031, Reactor Coolant Pump and Motor Emergencies.

EVENT 5 CONTINUED


Page 18 of 52


Event Description:P-32A RCP develops high vibration and temperature.Time Position Applicant’s Actions or Behavior

Crew 1. ATTEMPT to determine the cause of motor/bearing trouble.

N/A

2. IF RCP motor bearing temperature exceeds any of the following:

· P-32A Upper Thrust Bearing 230°F

· P-32B motor bearing 167°F

· Any other P-32A, P-32C, P-32D motor bearing 190°F

AND associated RCP oil reservoir is low, THEN:

A. INITIATE reactor building entry to add oil to reservoir.

B. ATTEMPT to determine whether fire is present in reactorbuilding.

NOTEVibration probes can exhibit intermittent spikes.Spikes due to instrument anomalies do not require pump tripping.

CRS 3. IF RCP vibration is abnormal, THEN NOTIFY PredictiveMaintenance to collect and analyze RCP vibration data.

BOOTH OPERATOR CUE: Inform the CRS that the indication is valid and data analysis is inprogress.

CRS4. PROVIDE Attachment A, RCP Parameters, to a Control Board

Operator to aid in monitoring seal parameters.

CRS

5. IF bearing temperature exceeds any of the following:




THEN CONTACT System Engineering.

BOOTH OPERATOR CUE: Inform the CRS that the indication is valid and that yourecommend taking action to secure P-32A.

ATC

6. IF bearing temperature(s) continue to rise AND tripping the affectedRCP(s) will permit continued operation, THEN REDUCE reactorpower to within capacity of unaffected RCP combination using1203.045, Rapid Plant Shutdown.

EVENT 5 CONTINUED


Page 19 of 52



BOP

7. DETERMINE if any of the following conditions are met:

· Motor current exceeds 800 amps

· Winding temperature exceeds 300°F

· P-32A Upper Thrust Bearing temperature exceeds 245°F

· P-32B bearing temperature exceeds 176°F

· Any other P-32A, P-32C, P-32D bearing exceeds 225°F

· RCP MOTOR vibration; more than one channel greater than 20mils after startup stabilizationand corresponding changes in RCP motor or seal parametersOTHER than vibration exist

· RC PUMP SHAFT vibration; greater than or equal to 29 mils,after startup stabilization and corresponding changes in RCPmotor or seal parameters OTHER than vibration exist

NOTE· Flux/DFlux/Flow reactor trip setpoints are shown on COLR Figure 10.

· High power/pumps reactor trip setpoints are:

- One pump per loop greater than or equal to 55%

- Zero pumps in one loop greater than or equal to 0%

· Tripping 1 RCP with reactor power greater than 92% may result in reactor trip on highpower/imbalance/flow.

N/A 8. IF any of the above conditions exist, THEN:

EVENT 5 CONTINUED


Page 20 of 52



ATC

BOP

ATC

CRS

N/A

9. IF Reactor Coolant PUMP SHAFT vibration greater than or equal to25 and less than 29 milsAND corresponding changes in RCP motor or seal parametersOTHER than vibration exist,THEN:

A. REDUCE reactor power to within capacity of available pumpsusing 1203.045, Rapid Plant Shutdown.

B. TRIP affected RCP(s).

C. ENSURE proper ICS response for the following:

· FW Re-ratio

· Plant runback

D. REFER TO 1203.022, Reactor Coolant Pump Trip.

E. IF only one RCP is in operation per loop,THEN ENTER Tech Spec 3.4.4 Condition A.

EVENT TERMINATION CRITERIAThis event is complete the CRS should reference OP-1203.045 for the down power.

EXAMINER NOTES


Page 21 of 52


Event Description:Turbine stops responding during power reduction.Time Position Applicant’s Actions or Behavior

NOTE· Shutdown rate is based on plant conditions and safety considerations. Rate may be

raised or lowered at any time as plant conditions necessitate.







~85%Power ATC 1. COMMENCE power reduction at 0.5 to 10% per minute.

CRS


· IF power reduction is NOT due to automatic runback,THEN ENSURE ATC has been given a specific endpoint for the power reduction and rate of desired powerchange.

· IF power reduction is due to automatic runback, THEN …N/A

· DIRECT ATC to report power level at CRS desired frequency.

· IF power reduction is due to RCS leak or steam leak inside RB,THEN …N/A

· IF necessary to maintain Makeup tank level, THEN:

- OPEN BWST T3 Outlet to operating HPI Pump (CV-1407 orCV-1408).

- MINIMIZE or ISOLATE Letdown.

· IF power reduction is due to Dispatcher request, THEN …N/A

BOOTH OPERATOR CUE: Insert malfunction for Turbine EHC at 85% or at the direction ofthe Lead Examiner.

ATCBOP 3. MONITOR ICS and EHC subsystems for proper integrated response.

Event 6 Continued


Page 22 of 52



EXAMINER NOTE: The following step will be applicable when the Turbine stops respondingduring the power reduction.

ATCBOP

4. While monitoring ICS and EHC, PERFORM the following:

· INITIATE manual control of ICS or EHCsubsystems as deemed appropriate by theoperator for potential failures of control systems.

- IF desired to restore automatic control of a subsystem,THEN REFER TO 1105.004, Integrated Control System.

· IF desired to stop downpower above final ULDsetpoint, THEN PERFORM Operations ofSG/RX Demand Hand/Auto Station, Exhibit 1.

CRS

5. IF plant has been stabilized with the reactor critical, THEN:

· DIRECT ATC to refer to "Contingency Reactivity Plans"located in the Plant Data Book.

· USE 1102.004, Power Operation, Exhibit A,“Operation of APSR Group” to control imbalance (ref.Plant Data Book).



· IF power is oscillating greater than 2%, THEN … N/A

· WHEN time permits, THEN PERFORM transient briefstressing reactivity control aspects:

- Reactor status versus Contingency ReactivityPlan

- Review and maintain COLR limits

- Expected rod movement

- Expected boration / dilution

Event 6 Continued


Page 23 of 52



CRS

6. IF reducing power below 90%, THEN SECURE Zinc Injection perONE of the following:



BOP7. IF reducing power below Heater Drain Pump operation, THEN as time

permits, PERFORM 1106.031, MSR Drain Demineralizer Operation,"Removing MSR DI From Service" section.

BOP

8. IF RCP trip or shutdown caused downpower, THEN:

· CONTINUE power reduction to 60 to 65%.

· TRIP Heater Drain Pump (P8A/B) associated with thetripped RCP:

P8A P8B

P32CP32D

P32AP32B

BOOTH OPERATOR CUE: Insert malfunction for sheared shaft.

EVENT TERMINATION CRITERIAThis event is complete the CRS should reference OP-1203.031 for the sheared shaft.

EXAMINER NOTES


Page 24 of 52


Event Description:P-32A Sheared ShaftTime Position Applicant’s Actions or Behavior

T=70 ATC 1. TRIP the Reactor.ATCBOP 2. PERFORM immediate actions of 1202.001, Reactor Trip.

NOTE· RCP vibration monitoring system and motor current indicators are useful in determining

affected RCP.

· Motor current is indicated locally at the breakers and at the following SPDS points:A1RCPA, A1RCPB, A1RCPC and A1RCPD.

BOP 3. TRIP affected RCP.

CRS 4. PERFORM 1202.001 in conjunction with this procedure.

CREW

5. COMMENCE RCS cooldown per 1102.010, Plant Shutdown andCooldown, "Normal Cooldown and Depressurization Sequence"sections.

CRS6. NOTIFY Predictive Maintenance to collect and analyze RCP

vibration data.

NOTERCP vibration monitor and Vibration & Loose Parts Monitoring system are useful indetermining whether affected RCP impeller is rotating in pump casing.

N/A 7. IF impeller rotation in pump casing is indicated for affected RCP,THEN … N/A

8. MONITOR affected RCP seal performance.

EVENT TERMINATION CRITERIAThis event is complete the CRS should reference OP-1202.001, Reactor Trip.

EXAMINER NOTES


Page 25 of 52


Event Description:Reactor Trip as a result of the sheared shaftMain Steam Line Break following reactor tripTime Position Applicant’s Actions or Behavior

ATC

1. Depress Reactor Trip PB.

A. Verify all rods insertedAND

reactor power dropping.

BOP 2. Depress Turbine trip PB.A. Check Turbine throttle and governor valves closed.

ATC/BOP 3. Check adequate SCM.

CRS


· Advise Shift Manager to implement Emergency ActionLevel Classification (1903.010).



BOP 6. Open BWST T3 Outlet (CV-1407 or CV-1408) to operating HPIpump.

ATC 7. IF Emergency Boration is not in progress,THEN adjust Pressurizer Level Control setpoint to 100".

ATC 8. Control RCS press within limits of Figure 3 (RT-14).

BOP 9. Check for proper electrical response (RT-19).

ATC 10. Check OP HPI pump supplying normal Makeup and Seal Injection.

BOOTH OPERATOR CUE: Insert malfunction for Main Steam Line Break.

ATC 11. Check both SG levels remain £ 410".

ATC 12. Check Instrument Air Header Press> 75 psig.

ATC 13. Check NNI and ICS power available (RT-20).

EVENT 8 CONTINUED


Page 26 of 52

Op-Test No.: 2018-1 Scenario No.: 3 Event No.: 8, 9, 10 & 11CONTINUED

Event Description:Reactor Trip as a result of the sheared shaftMain Steam Line Break following reactor tripESAS Channel 5 fails to actuate and CV-6203 fails to isolateVector fails to isolate bad SGTime Position Applicant’s Actions or Behavior

ATC 14. Check both SG pressures ³ 900 psig.

T=85 CRS 14. GO TO 1202.003, "OVERCOOLING" procedure.

EXAMINER NOTE: The following step are contained in the OVERCOOLING EOP, transitionshould occur when ESAS actuates on RB Building Pressure alone or on low steamgenerator pressure which was checked in Step 14 above.

ATC

CRS


· Check adequate SCM


BOP 2. Open BWST T3 Outlet to OP HPI pump (CV-1407 or CV-1408).

ATC 3. Check Pressurizer Level Control valve (CV-1235) maintains PZRlevel ³ 55”.

ATCBOP 4. Check RCS press remains ³ 1700 psig.

ATC 5. Check RCS T-cold ³ 465°F.ATC 6. Control RCS press within limits of Figure 3 (RT-14).ATC 7. Check ESAS ACTUATION alarms clear on K11.

EVENT 8, 9, 10 & 11 CONTINUED


Page 27 of 52



BOP

7. Perform the following:A. Perform the following to throttle HPI:

1) IF OP or STBY HPI pump is in service,THEN override AND open HPI RECIRC Blocks:

· CV-1300

· CV-1301

2) IF ES HPI pump is only HPI pump in serviceOR HPI pump recirc flow path to Makeup Tank isunavailable,THEN maintain HPI pump flow ³ 90 gpm.

3) Override AND throttle HPI Block valves to maintain RCSpress within limits of Figure 3 (RT-14):· CV-1219

· CV-1220

· CV-1278

· CV-1279

· CV-1227

· CV-1228

· CV-1284

· CV-1285EXAMINER NOTE: ***CRITICAL TASK***The ATC and BOP should recognize the failure of

Channel 5 and / or CV-6203 and take actions per RT-10. Manually actuate Channel 5 ormanually close CV-6203 prior to completing RT-10,

BOP

B. Verify proper ESAS actuation (RT-10).

C. IF RB Spray has actuated, THEN …N/A

ATC 8. Check MSSV OPEN (K07-C5) alarm clear.

ATC 9. Check RB press < 17 psia and stable.



Page 28 of 52


Event Description:Reactor Trip as a result of the sheared shaftMain Steam Line Break following reactor tripESAS Channel 5 fails to actuate and CV-6203 fails to isolateVector fails to isolate bad SGEXAMINER NOTE: ***CRITICAL TASK***The ATC should identify that the bad SG is being

fed by CV-2645 and CV-2627. CV-2627 is failed open and cannot be closed, howeverCV-2645 can be closed or P-7A can be secured to stop flow. This is to be completedbefore T-cold reaches 465oF.

ATC

ATC

ATC

BOP

ATC

CRS

N/A

9. Perform the following for bad SG:

A. Place bad SG EFW ISOL valves in MANUAL AND verifyclosed(modulating valves):

SG A SG B CV-2627 CV-2620 CV-2670 CV-2626

B. Actuate EFW.

C. Actuate MSLI for bad SG AND verify proper actuation and control(RT-6).

D. Maximize RB cooling (RT-9).

E. IF EFW is in service, THEN trip both MFW pumps:· Main Feed Pump A

· Main Feed Pump B

NOTE Overcooling could continue until SG boils dry

F. IF overcooling is terminated,THEN GO TO step 25.

G. IF overcooling is still in progress after SG boils dry,THEN GO TO step 35.



Page 29 of 52



ATC

10. Check SG press > 600 psig ANDMSLI alarms clear on K12:

· MSLI OTSG A (K12-A7)

· MSLI OTSG B (K12-A8)

ATC

ATC

CRS


A. Verify proper MSLI actuation and control (RT-6).

B. IF EFW is in service, THEN trip both MFW pumps:

· Main Feed Pump A

· Main Feed Pump B

C. IF overcooling is terminated,THEN GO TO step 25.

D. IF overcooling is still in progress,THEN GO TO step 35.

EXAMINER NOTE: CRS should transition to Step 25



Page 30 of 52



ATC

25. WHEN overcooling is terminated,THEN perform the following for each SG:

A. IF MSIV is open AND TURB BYP Valves are available,THEN operate TURB BYP Valves as necessary to preventRCS heatup.

ATC

A. Perform the following:

1) Operate ATM Dump Control System as necessary toprevent RCS heatup:

SG A SG B


CV-2676 ATM DUMP ISOL CV-2619

CV-2668 ATM DUMP CONTRL CV2618

a) Place TURB BYP Valves for SG(s) with closed MSIV inHAND AND close to prevent loss of condenser vacuum.

EVENT TERMINATION CRITERIAThis scenario is complete when Overcooling is terminated and the crew has control of RCS

TemperatureOR


END OF SCENARIO


Page 31 of 52

1203.031 REACTOR COOLANT PUMP AND MOTOR EMERGENCYPAGE: 31 of 52CHANGE: 027

ATTACHMENT APAGE 1 OF 2

RCP PARAMETERS

NOTE· RCP Seal chart recorders on C13 show actual cavity pressures.

· Seal DP is available on RCP mimic displays on PDS/PMS.

· RCP seal stage DP can be determined as follows:

- 1st stage DP = system pressure - lower seal cavity press.

- 2nd stage DP = lower seal cavity pressure - upper seal cavity press.

- 3rd stage DP = upper seal cavity pressure - RB atmospheric press.

· Third stage seal leakage by design is 0 to 0.08 gpm. Third stage leakage in excess ofdesign will affect upper seal cavity pressure and seal bleed off flow.

Seal Degradation ¾ any of the following requires securing the affected RCP:

· RCP seal cavity pressure oscillations exceed 800 psi peak-to-peak

· DP across any stage exceeds 2/3 of system pressure on a running RCP or exceeds 80% ofsystem pressure on an idle RCP.

· Greater than or equal to 2.5 gpm total seal outflow, including seal bleedoff (excluding shaftsleeve leakage) and a loss of seal injection

· RCP seal bleed off or seal stage temp reaches 180°F and no interruption of seal injection orICW flow.

Seal Failure ¾ any of the following requires tripping the affected RCP:

· Greater than or equal to 10 gpm rise in RCS leak and a change in seal cavity pressurebehavior.

· RCP seal bleed off or seal stage temp reaches 200°F and no change in seal injection orICW flow.

· DP across a single stage equal to RCS press with seal bleed off flow established.


Page 32 of 52

ATTACHMENT APAGE 2 OF 2

Loss of Cooling Water to RCP Motors or Motor/Bearing Trouble

1. IF Motor Bearing Temperature exceeds any of the following:




AND continues to rise,THEN SECURE the affected RCP per section 4 and/or section 5 of this procedure.

2. IF Reactor Coolant PUMP SHAFT vibration; more than one channel greater than orequal to 25 mils, after startup stabilizationAND corresponding changes in RCP motor or seal parameters OTHER thanvibration exist,THEN SECURE the affected RCP per section 5 of this procedure.

3. ANY of the following is criteria to TRIP the affected RCP per section 4 and/orsection 5 of this procedure:

· Motor current exceeds 800 amps

· Winding temperature exceeds 300°F

· P-32A Upper Thrust Bearing temperature exceeds 245°F

· P-32B bearing temperature exceeds 176°F

· Any other P-32A, P-32C, P-32D bearing temperature exceeds 225°F

· RCP MOTOR vibration; more than one channel greater than 20 mils after startupstabilizationand corresponding changes in RCP motor or seal parameters OTHER than vibrationexist

· ANY RC PUMP SHAFT vibration greater than or equal to 29 mils after startupstabilizationand corresponding changes in RCP motor or seal parameters OTHER than vibrationexist


Page 33 of 52

RT-19

CHECK PROPER ELECTRICAL RESPONSE

1. Check 125 V DC Bus D01 energized:

· Turbine Trip Solenoid Power Available light lit

· Breaker position indications available on left side of C10

A. IF 125 V DC Bus D01 is de-energized,THEN inform CRS to perform “Loss of D01” section of Loss of 125 V DC (1203.036)in conjunction with Reactor Trip procedure, while continuing.

2. Check Main Generator and Exciter Field breakers open.

· 5114

· 5118

· Exciter Field breaker

A. IF Main Generator and Exciter Field breakers are closed,THEN perform the following:

1) IF 125 V DC Bus D01 is energized,THEN perform the following:

a) Inform the CRS.

b) Manually trip Main Generator breakers:

· 5114

· 5118

c) Manually trip Exciter Field breaker.

2) IF 125 V DC Bus D01 is de-energized,THEN leave Main Generator and Exciter Field breakers closed.


Page 34 of 52

Page 2 of 2CHECK PROPER ELECTRICAL RESPONSE

3. Check DGs off:

· DG1

· DG2

A. IF DG is running,THEN perform the following:

· Verify associated SERV WTR to DG CLRs open:

DG1 DG2

CV-3806 CV-3807

· Inform CRS that DG is running

4. Check vital 4160 V buses energized:

· A3

· A4

A. IF either 4160 V bus A3 or A4 is de-energized,THEN inform CRS.

5. Check non-vital 4160 V buses energized:

· A1

· A2

A. IF either 4160 V bus A1 or A2 is de-energized,THEN inform CRS.

ENDRT-19


Page 35 of 52

RT-20

CHECK NNI AND ICS POWER AVAILABLE

1. Check all NNI power available:

* Instrument Power Supply Status lights on C13 lit

* ICS/AUX SYS POWER SUPPLY TROUBLE (K07-A4) alarm clear

* NNI Indicator/Recorder AC power available indicators lit

* NNIs indicate other than mid-scale

A. IF any NNI AC or DC Instrument Power Supply is lost,THEN inform CRS.

2. Check all ICS power available:

* Instrument Power Supply Status lights on C13 lit

* HAND or AUTO lights on ICS H/A Stations lit

A. IF any ICS AC or DC Instrument Power Supply is lost,THEN inform CRS.

ENDRT-20


Page 36 of 52

RT-2Page 1 of 6

INITIATE HPI

1. IF HPI initiation is for any reason other than Emergency Boration (RT-12),THEN isolate Letdown by closing either:

· Letdown Coolers Outlet (RCS) (CV-1221)

OR

· Letdown Coolers Outlets (RCS):

- CV-1214

- CV-1216

2. IF OP or STBY HPI pump is running,THEN perform the following:

A. Verify BWST T3 Outlet to OP or STBY HPI pump (CV-1407 or CV-1408) open.

B. IF RCP Seal Injection is in service,THEN place RCP Seal INJ Block (CV-1206) in OVRD.

C. WHEN associated BWST T3 Outlet is open,THEN open HPI Block valve associated with OP or STBY HPI pump(CV-1220 or CV-1285) to maintain PZR level and RCS press.

D. IF initiating HPI for Emergency Boration only,THEN GO TO RT-12 step 2.B.

E. IF PZR level or RCS press continues to drop,THEN open additional HPI Block valves associated with OP or STBY HPI pump:

P36A/B P36B/C

CV-1219CV-1278CV-1279

CV-1227CV-1228CV-1284


Page 37 of 52

Page 2 of 6INITIATE HPI

3. IF either OP or STBY HPI pumps are availableAND both pumps are off,THEN place OP or STBY HPI pump in service as follows:

A. Verify BWST T3 Outlet to OP and STBY HPI pump (CV-1407 or CV-1408) open.

B. Verify RCP Seal INJ Block (CV-1206) closed.

C. Close RCS Makeup Block (CV-1233 or CV-1234).

D. Prevent dead heading pump by verifying one of the following:


- CV-1300

- CV-1301

OR

· One HPI Block valve associated with OP HPI pump (CV-1220 or CV-1285) fullyopen.

E. IF HPI Pump (P-36B) will be used,THEN verify the following selected to energized bus:

· P36B/P64B Bus Select MOD Control

· P64B Transfer Switch

F. Start AUX Lube Oil pump for OP or STBY HPI pump.

G. Start OP or STBY HPI pump.

H. Stop AUX Lube Oil pump.



Page 38 of 52


3. (Continued)

I. WHEN associated BWST T3 Outlet is open,THEN open HPI Block valve associated with OP or STBY HPI pump(CV-1220 or CV-1285) to maintain PZR level and RCS press.

1) IF PZR level or RCS press continues to drop,THEN open additional HPI Block valves associated with OP or STBY HPIpump:

P36A/B P36B/C

CV-1219CV-1278CV-1279

CV-1227CV-1228CV-1284

2) Monitor Makeup Tank level and control per step 10 as necessary.

J. IF initiating HPI for Emergency Boration only,THEN GO TO RT-12 step 2.B.

4. IF PZR level or RCS press continues to drop,THEN place ES HPI pump in service as follows:

A. Open BWST T3 Outlet to ES HPI pump (CV-1407 or CV-1408).

B. Prevent dead heading pump by verifying one of the following:


- CV-1300

- CV-1301

OR

· One HPI Block valve associated with ES HPI pump (CV-1220 or CV-1285) fullyopen.

C. Start AUX Lube Oil pump for ES HPI pump.

D. IF OP and STBY pumps are both off,THEN verify RCP Seal INJ Block (CV-1206) closed.



Page 39 of 52


4. (Continued)

E. WHEN associated BWST T3 Outlet is open,THEN start ES HPI pump.

F. Stop AUX Lube Oil pump.

G. Open HPI Block valve associated with ES HPI pump (CV-1220 or CV-1285) tomaintain PZR level and RCS press.

1) IF initiating HPI for Emergency Boration only,THEN GO TO RT-12 step 2.B.

2) IF PZR level or RCS press continues to drop,THEN open additional HPI Block valves associated with ES HPI pump:

P36A P36C

CV-1219CV-1278CV-1279

CV-1227CV-1228CV-1284

3) Monitor Makeup Tank level and control per step 10 as necessary.

5. IF all HPI Block valves are fully openAND

additional HPI flow is required,THEN close HPI Pump RECIRC Block (CV-1300 or CV-1301).

6. IF only one train of HPI is availableAND



Page 40 of 52


7. IF leakage into the RB is indicated,THEN maximize RB cooling as follows:


· VSF1A · VSF1C

· VSF1B · VSF1D


· CV-3812/CV-3814

· CV-3813/CV-3815


· SV-7410 · SV-7412

· SV-7411 · SV-7413

8. Verify the following sample valves closed on C26:

· Pressurizer Steam Space Sample Valve (CV-1814)

· Pressurizer Water Space Sample Valve (CV-1816)

· Hot Leg Sample (SV-1840)

9. Verify the following High Point Vents closed,except when another procedure directs otherwise:

A Loop B Loop ReactorVessel Pressurizer

· SV-1081

· SV-1082

· SV-1083

· SV-1084

· SV-1091

· SV-1092

· SV-1093

· SV-1094

· SV-1071

· SV-1072

· SV-1073

· SV-1074

· SV-1077

· SV-1079


Page 41 of 52


10. IF Makeup Tank level is risingAND

it is necessary to control Makeup Tank level,THEN perform one or more of the following:

· Verify all running HPI pump flow(s) ³ 90 gpm/pumpAND

close HPI Pump RECIRC Block (CV-1300 or CV-1301).

1) Maintain running HPI pump flow ³ 90 gpm/pump.

· IF OP and STBY HPI pumps are both off,THEN start OP or STBY pump per step 3.

· IF OP or STBY HPI pump is running,THEN perform the following:

1) Verify HPI Pump RECIRC Blocks open:

· CV-1300

· CV-1301

2) Transfer HPI flow from ES pump to OP or STBY pump as necessary to controlMakeup Tank level.

3) IF total HPI flow is within capacity of OP or STBY HPI pump,THEN perform the following:

a) Transfer remaining HPI flow to OP or STBY HPI pump.

b) Start AUX Lube Oil pump for ES HPI pump.

c) Stop ES HPI pump.

d) Stop AUX Lube Oil pump.

ENDRT-2


Page 42 of 52

RT-14Page 1 of 4

CONTROL RCS PRESS

NOTE· PTS limits apply if any of the following has occurred:

- HPI on with all RCPs off

- RCS C/D rate > 100°F/hr with Tcold < 355°F

- RCS C/D rate > 50°F/hr with Tcold < 300°F

· Once invoked, PTS limits apply until an evaluation is performed to allow normal presscontrol.

· When PTS limits are invoked OR SGTR is in progress, PZR cooldown rate limits do notapply.

· PZR cooldown rate <100°F/hr.

1. IF PTS limits apply or RCS leak exists,THEN maintain RCS press low within limits of Figure 3.

2. IF RCS press is controlled AND will be reduced below 1650 psig,THEN bypass ESAS as RCS press drops below 1700 psig.

3. IF PZR steam space leak exists,THEN limit RCS press as PZR goes solid by one or more of the following:

A. Throttle makeup flow.

B. IF SCM is adequate,THEN throttle HPI flow by performing the following:

1) Verify both HPI Recirc Blocks open:

· CV-1300

· CV-1301

2) Throttle HPI.

C. Raise Letdown flow.

1) IF ESAS has actuated,THEN unless fuel damage or RCS to ICW leak is suspected, restore Letdownper RT-13.

D. Verify Electromatic Relief ERV Isolation open (CV-1000)AND cycle Electromatic Relief ERV (PSV-1000).


Page 43 of 52

Page 2 of 4CONTROL RCS PRESS

4. IF RCS press is high,THEN limit press using one or more of the following:

A. Throttle makeup flow.

B. Throttle HPI flow by performing the following:

1) Check adequate SCM AND any of the following conditions met:

· HPI Cooling (RT-4) NOT in progress

· CET temps dropping

· RCS press rising with Electromatic Relief ERV (PSV-1000) open

2) Verify both HPI Recirc Blocks open:

· CV-1300

· CV-1301

3) Throttle HPI.

C. IF RCP is running,THEN operate Pressurizer Spray Control (CV-1008) in HAND.

D. IF PZR AUX Spray is in service,THEN throttle Pressurizer AUX Spray (CV-1416) open.

E. Place Pressurizer Heaters in OFF.

F. Raise Letdown flow.

1) IF ESAS has actuated,THEN unless fuel damage or RCS to ICW leak is suspected restore Letdownper RT-13.

G. Verify Electromatic Relief ERV Isolation open (CV-1000)AND cycle Electromatic Relief ERV (PSV-1000).



Page 44 of 52


4. (Continued)

H. IF desired to secure HPI pump(s),THEN perform the following:

1) Start AUX Lube Oil pumps for associated HPI pump(s):

P36A P36B P36C

P64A P64B P64C

2) Stop desired HPI pump(s):

· P36A · P36B · P36C

3) Close all associated HPI Block valves:

P36A/B P36B/C

· CV-1219

· CV-1220

· CV-1278

· CV-1279

· CV-1227

· CV-1228

· CV-1284

· CV-1285

5. IF RCS press is low,THEN raise press using one or more of the following:

A. Raise makeup flow.

B. Raise HPI flow or initiate HPI per RT-2.

C. IF RCP is running,THEN verify Pressurizer Spray Control (CV-1008) closed.

D. Reduce Letdown flow.

E. Place Pressurizer Heaters in MANUAL.



Page 45 of 52


5. (CONTINUED)

CAUTIONIf HPI cooling is in progress, Electromatic Relief ERV Isolation (CV-1000) is left open until HPIcooling is no longer required.

F. Verify Electromatic Relief ERV (PSV-1000) or Electromatic Relief ERV Isolation(CV-1000) closed.

CAUTION

With RCS solid, 1°F temp change can cause 100 psig press change.

6. IF PZR is solid,THEN RCS press may also be controlled by varying RCS temperature.

· Raise RCS temp to raise RCS press

· Lower RCS temp to lower RCS press

NOTEAdjusting Pressurizer Level Control setpoint and HPI as necessary to maintain normal makeupflow on-scale will allow CV-1235 to automatically compensate for small changes in RCS leakrate and cooldown rate.

7. IF normal makeup is in service ANDHPI is in service,THEN adjust Pressurizer Level Control setpoint and HPI as necessary to maintainnormal makeup flow on-scale.

ENDRT-14


Page 46 of 52

RT-10Page 1 of 7

VERIFY PROPER ESAS ACTUATION

1. Verify BWST T3 Outlets open:

· CV-1407

· CV-1408

A. IF BWST T3 Outlet (CV-1407 or CV-1408) fails to open,THEN obtain Shift Manager/CRS permission to override ES.

B. Override AND stop associated HPI, LPI, and RB Spray pumps until failed valve isopened:

CV-1407 CV-1408

P34A P34B

P36A/B P36C/B

P35A P35B

2. Verify SERV WTR to DG1 and DG2 CLRs open:

· CV-3806

· CV-3807


Page 47 of 52

Page 2 of 7VERIFY PROPER ESAS ACTUATION

3. IF any RCP is running,THEN perform the following:

A. IF ES Channel 5 or 6 has actuated,THEN perform the following:

1) IF SCM is adequate,THEN trip all running RCPs due to loss of ICW:

· P32A · P32C

· P32B · P32D

2) IF SCM is NOT adequate,THEN check elapsed time since loss of adequate SCMAND perform the following:

a) IF £ 2 minutes have elapsed,THEN trip all RCPs:

· P32A · P32C

· P32B · P32D

b) IF > 2 minutes have elapsed,THEN perform the following:

(1) Leave currently running RCPs on.

(2) IF RCS press > 150 psig,THEN notify CRS to GO TO 1202.002, “LOSS OF SUBCOOLINGMARGIN” procedure.

(3) Restore RCP services per RT-8 while continuing.

B. IF neither ES channel 5 nor 6 has actuated,THEN dispatch an operator to perform Service Water And Auxiliary CoolingSystem (1104.029) Exhibit B, "Restoring SW to ICW Following ES Actuation"while continuing.

1) WHEN ICW Cooler SW Outlets and Bypasses are aligned per 1104.029,Exhibit B,THEN perform the following:

a) Obtain Shift Manager/CRS permission to override ES.

b) Override AND open one Service Water to ICW Coolers Supply(CV-3811 or CV-3820).


Page 48 of 52


4. Verify proper ESAS Channels tripped:

Condition Channels Actuated

RCS press ≤ 1550 psig 1,2,3,4

RB press ≥ 18.7 psia 1,2,3,4,5,6

RB press ≥ 44.7 psia 7,8,9,10


A. Verify each component properly actuated on C16 and C18, except those overriddenin previous steps.

B. Verify proper ES system flow rates.

NOTE· During ESAS actuation, low LPI flow is expected until RCS depressurizes below LPI pump shutoff head.

· During large break LOCAs, high LPI flow can be experienced. Flow is throttled to ensure ECCS flowsare maintained within assumptions of calculations.

1) IF any of the following conditions exist:

· A HPI FLOW HI/LO (K11-A4)

· B HPI FLOW HI/LO (K11-A5)

· A LPI FLOW HI/LO (K11-B4)

· B LPI FLOW HI/LO (K11-B5)

· A RB SPRAY FLOW HI (K11-C4)

· B RB SPRAY FLOW HI (K11-C5)

THEN use Annunciator K11 Corrective Action (1203.012J) to clear unexpectedalarms.

C. IF only one train of HPI is availableAND



Page 49 of 52


6. On C10, perform the following:

· Verify DGs operating within normal limits:

- DG 1 - DG 2

- 4100 to 4200 V - 4100 to 4200 V

- 59.5 to 60.5 Hz - 59.5 to 60.5 Hz

- £ 2750 KW - £ 2750 KW

· Verify the following breakers open:

· A3-A4 Crossties:

- A-310 - A-410

· B5-B6 Crossties:

- B-513 - B-613

· Unit AUX feeds to A1 and A2:

- A-112 - A-212

· Verify the following breakers closed:

· A3 Feeds to B5:

- A-301 - B-512

· A4 Feeds to B6:

- A-401 - B-612


A. Check AUX Cooling Water header depressurized.

B. IF proper EFW actuation and control has NOT already been verified,THEN verify proper EFW actuation and control (RT-5).


Page 50 of 52



A. Verify LPI (Decay Heat) Room Cooler running in each Decay Heat Room:

P34A Room P34B Room

VUC1A or B VUC1C or D

B. IF RB Spray has actuated,THEN verify SW to RB Spray P35A and P35B LO CLRs open:

· CV-3804

· CV-3805

9. IF all RCPs are offAND

RCP Seal INJ Block (CV-1206) is closed,THEN place RCP Seal Bleedoff (Alternate Path to Quench Tank) controls in CLOSE:

· SV-1271 · SV-1273

· SV-1270 · SV-1272

10. IF leakage into the RB is indicated,THEN verify RB cooling maximized:


· VSF1A · VSF1C

· VSF1B · VSF1D

B. Verify RB Cooling Coils Service Water Inlet/Outlet valves open:

· CV-3812/CV-3814

· CV-3813/CV-3815

C. Verify key-locked Chiller Bypass Dampers unlatched:

· SV-7410 · SV-7412

· SV-7411 · SV-7413


Page 51 of 52


11. Initiate RB H2 sampling using Containment Hydrogen Control (1104.031), Exhibit A.

12. Verify each component properly actuated on C26.

13. Verify the following sample valves closed on C26:

· Pressurizer Steam Space Sample Valve (CV-1814)

· Pressurizer Water Space Sample Valve (CV-1816)

· Hot Leg Sample (SV-1840)

14. Verify the following High Point Vents closed:

A Loop B Loop ReactorVessel Pressurizer

· SV-1081

· SV-1082

· SV-1083

· SV-1084

· SV-1091

· SV-1092

· SV-1093

· SV-1094

· SV-1071

· SV-1072

· SV-1073

· SV-1074

· SV-1077

· SV-1079

15. IF AUX Lube Oil pump for running HPI pump fails to stop after 20 second time delay,THEN within one hour of ESAS actuation dispatch an operator to stop AUX Lube Oilpump locally at breaker while continuing:

P64A P64B P64C

B5721 B5722/B6515 B6514

16. Place running Low Pressure Injection (Decay Heat) Pump (P34A/P34B) handswitches in NORMAL-AFTER-START to enable DECAY HEAT PUMP TRIP (K09-A7)alarm:

· P34A

· P34B

17. Monitor ENGINEERED SAFEGUARDS ACTUATION SYSTEM alarms on K11.


Page 52 of 52


18. IF any of the following components/systems are in service:

· Condensate Pumps

· Condenser Vacuum Pumps

· Waterbox Vacuum Pumps

· Seal Oil System

· Control Room Chillers

THEN coordinate with CRS/SM to secure components and/or systems, as timepermits.

19. Coordinate with CRS/SM to re-verify component actuation with another operator.

ENDRT-10

· administrative job performance measure a1jpm-ro-pms1 page 1 of 7 a1 unit: 1 rev # 4 date:...

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