2k2 lout exam materials simulator exam si~mo1 examination · 2012. 11. 18. · id number: 2k2...
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2K2 LOUTEXAM MATERIALS
SIMULATOR EXAM
SI~MO1
EXAMINATION
08112102 - 08115/02
MILLSTONE POWER STATION A
NRC SIMULATOR EXAM GUIDE APPROVAL SHEET
IExam Title:
Revision:
ATWS with Faulted SIG
0
ID Number: 2K2 NRC-001
This document is the property of Millstone Power Station, which controls its
distribution. Further transfer, copying, and modification of this document are
strictly prohibited without the written consent of Millstone Power Station.
H - /I
Submitted by:
Validated by:
Approved by:
Approved by:
Technvcloper
Technical Reviewer
2/13/02Date
6//7/ot
Date
Date
DaeC
,Operation Manager (Optional)
Training Supervisor
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SECTION 2
SIMULATOR EXAM GUIDE
TABLE OF CONTENTS
SECTIONS LISTED IN ORDER
1. Cover Page
2. Table of Contents
3. Exam Overview
4. Evaluation Guide
5. Scenario Initial Conditions Sheet
6. Scenario Validation Checklists
7. Reference and Task Tracking
8. Scenario Attributes Checklist
Attachments
- NUTIMS Module Report
-ST OP .T - iZ AC, X, VITo , Y
SECTION 3
EXAM OVERVIEW
Title: ATWS with Faulted S/G
ID Number: 2K2 NRC-001 Revision: 0
Exam Brief:
1. The plant is at 50% power, EOL steady state operations with all control systems inautomatic. The "A" PORV is out of service due to an electrical short in the control circuitry.The crew is directed to hold power at 50% and to Pump the Containment Drains TransferTank in accordance with OP 3335A, Reactor Plant Gaseous Drains, section 4.4.
After the CDTT has been pumped a partial Loss of RCP B Cooling Water Supply willoccur. The following alarms will actuate as their setpoints are reached: RCP B THERMALBARRIER FLOW LOW (MB4B, 3-4A), RCP B COOLER SPLY PRES LOW (MB4B, 3-4B).The crew will primarily use MB4B, 3-4B to respond to this condition. Thrust bearingtemperatures will remain <1950 so a rapid downpower and reactor trip will not be
implemented.After the partial Loss of RCP B Cooling Water has been addressed, a Loss of
Instrument Bus VIAC-3 will occur. The crew will respond using AOP 3564, Loss of OneProtective System Channel. Once the US has referred to Tech Specs (step 6), the nextevent will occur.
The A Main Feed Regulating valve will fail closed over 1 minute. The BOPoperator should attempt to take manual control of the valve but that will be ineffective.Once the crew realizes that S/G lo-lo is inevitable they should decide to trip the reactorin anticipation.
The reactor trip will not occur automatically, MB4 nor MB7 trip switches will work, and32N will not be able to be de-energized. The crew will enter FR-S.1, Response to NuclearPower Generation/ATWS. When attempting to align a boration flowpath the normal chargingflow control valve will not open requiring the use of the safety grade boration. At step 6 thePEO will successfully open the reactor breakers locally. When E-0 steps 1-14 are checked,the RO will discover that the SIH (HPSI) components did not actuate and will have to bemanually started or aligned [Critical Task]. During the initial ATWS transient a Main SteamLine D Rupture Inside CTMT occurs. MSI Fails to Auto Actuate and will have to be manuallyactuated by the crew at least by step 13 of FR-S.1 path [Critical Task].
The crew will proceed through FR-S. 1 to completion and then transition to E-0 step 15(SI verification done within FR-S.1) and then to E-2, Faulted Steam Generator Isolation, at E-0 [Critical Task], step 24. Conditions may require performing FR-Z.1.
The scenario will end when the crew decides to make the transition to E-1.
2. The SM should classify this event as a Site Area Emergency- Charlie Two due to FR-S.1 beingentered directly from E-0 (ES1).
3. Plant/Simulator differences that may affect the scenario are: NONE
4. Duration of Exam: 60 minutes
SECTION 4
EVALUATION GUIDE
ATWS with Faulted S/GTitle:
ID Number: 2K2 NRC-001 Revision: 0
All Control Room Conduct, Operations and Communications shall be in accordance with
MP-14-MMM.
"Review the Simulator Operating Limits(design limits of plant) and the SimulatorModeling Limitations and Anomalous Response List prior to performing this examscenario on the simulator. The evaluators should be aware if any of these limitationsmay be exceeded." (NSEM 6.02)
Section 4Page 1 of 61
SIMULATOR PROBLEMS DURING EXAMS
It is the responsibility of the Instructors in the simulator to insure that exam interruptions have aminimum negative impact on the Crew and the examinations we provide.
Be aware that at all times the Operators should treat the simulator as if it were the plant andyou too should treat it as much like the plant as possible when they are in the simulator.
As soon as the Instructors are aware of a simulator problem that will adversely affect the examin progress (computer fault, etc.) the Instructor should:
1. Place the simulator in FREEZE if possible.
2. Announce to the Crew that there is a simulator problem.
3. Request that the Crew leave the simulator control room. (The Crew should leavethe simulator for problems which involve major switch alignments).
4. Deal with the problem (reboot, call STSB, etc.)
5. After the Instructors believe the simulator is restored to service, the Crew should betold how the exam will continue. If it is possible and felt to be acceptable to theevaluators, the examination can begin where it left off with an update on plantparameters and each Crew member is prepared to restart. If the examination willnot begin where it left off, the crew should be told how and where the exam willbegin again.
6. Once the Crew has been told how and where the exam will begin, have the crewconduct a brief so that the Instructor and evaluators can insure that the crew has allthe necessary information to continue with the scenario.
7. Once all Crew members, Instructors and evaluators are satisfied that they have thenecessary information to continue the scenario, place the simulator in RUN andannounce to the Crew that you have continued the evaluation session.
Section 4Page 2 of 61
SECTiuN 4
Lesson Title: ATWS with Faulted S/G
ID Number: 2K2 NRC-001 Revision: 0Task
Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard
Simulator Setup Instructions:
1. HANG Exam Placards on the simulator doors.
2. START the Sun Workstation.
a. IF the Sun Workstation is running THEN go to SIM ACTIVE.
3. PLACE Recorder Power to ON.
4. VERIFY that the current approved training load is loaded.
5. REMOVE the step counter OVERRIDE and allow the counters to step out during the IC reset.
6. RESET to IC 89: TEMP IC 2K2NRC-LOUT-001 (based on IC 22)
7. ADJUST the various pot settings to the valued specified by the chart in the simulator booth or Notepad for the selected IC.
8. PLACE Simulator to RUN.
9. RESET the Plant Calorimetric at the Instructor Station PPC by Pressing "SHIFT LEFT" and "F6" simultaneously.
10. ENSURE Simulator fidelity items cleared.
a. CHECK the STEP COUNTERS at correct position for plant conditions.
b. PLACE 5 tiles under the DEMINS IN SERVICE lamacord label on MB6.
c. PLACE the Main Turbine on the LOAD LIMITER and ENSURE Standby Load Set MATCHED if conditions require.
d. PLACE the Westronic (5) and Gammametrics (2) recorders in active/run by depressing up or down arrow for each.
e. CLEAR DCS alarms on MB7 and BOP console.
f. VERIFY annunciator, "COMPUTER FAILURE" (MB4C, 1-1 1), is NOT LIT.
Section 4Page 3 of 61
(SECTiuN 4
Lesson Title: ATWS with Faulted S/G
ID Number: 2K2 NRC-001 Revision: 0Task
Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard
g. ENSURE NSSS Picture 1, MODES 1, 2, 3, 4; Burnup and Cb match lesson plan AND Cb sample date < 3 days old.
1. See laminated directions on clipboard in Sim booth.
2. RESET Computer Terminals to At Power displays if 100% power IC.
a. MB2, (AY6), CVCS Data Trend, 1 minute update, CHS-F132 (40-120), CHS-L112 (40-80), CHS-F121 (40-80), RCS-L461 (40-80)
b. MB4, (AY1), At Power Data Trend, 15 second update, CVQRPI, (3391-3428), CVQRPHRUN (3409-3413), CVQRP (3409-3413), RCL-
T412*, (585-588)
c. MB4, (AY4), NSSS Picture 1, MODES 1, 2, 3, 4
d. BOP Console (AY5A), BOP Picture 26, Circ Water
e. STA Console, (AY3), NSSS Picture 15, RCP Seals
13. RESET Rad Monitor Screen to Status Grid.
14. OVERRIDE the annunciators that will be lit longterm in the CR, (as listed in the "Lit CRP Annunciators" section of the MP3 daily Status Report
hanging near instructor booth door).
15. IF placing equipment OOS, THEN perform the necessary switch manipulations and hang appropriate tags, as required, listed under "Equipment
OOS."
16. LOCK the Simulator Room front door.
17. HANG a Caution Tag on 3RCS*MV8000A stating, "Caution Tag 3RCS*MV8000A Closed and de-energized lAW Tech Spec 3.4.4, action b"
18. With SIM in RUN momentarily push 3DGS*CTV24 open/auto
19. ENSURE 3RCS*8000A in CLOSE position
Section 4Page 4 of 61
(SECTION 4
(
Lesson Title: ATWS with Faulted S/G
Revision: 0ID Number: 2K2 NRC-001Task
AnnianTr:- lr/A Iftflf lnc~itr-ufnr InfnrmntinnlAr-livitv Expected Action StandardI 1111W I Lfrl M43 I I . - .
PLACE THE FOLLOWING EQUIPMENT OOS: STANDARD 2K2NRC EXAM EQUIPMENT
Ensure CDTT Level Raised (-1000 gallons) to allow pumping during NORMAL Evolution
Initial Malfunctions
1/01/01/01/01/0
(RC)(RC)(RC)(RC)(RC)
3RCS*PCV455A3RCS*PCV455A3RCS*PCV455A3RCS*MV8000A3RCS*MV8000A
A PORVA PORVA PORVA PORVA PORV
OPEN - OFFGREEN - OFFRED - OFFGREEN - FALSERED - FALSE
Block ValveBlock Valve
I/O (ED)I/O (ED)
1 -3NJSACB-BF1-3NNSACB-BF
TRIP - OFFTRIP - OFF
32N Fails to Trip32N High Side Fails to Trip
MALFMALFMALFMALFMALF
MALF
MALFMALF
RP09ARP09BRP10ARP1OBRP11E
CV18
RP08ARP08B
Reactor Fails to Manually Trip from MB4Reactor Fails to Manually Trip from MB7'A' Train Reactor Fails to Auto Trip'B' Train Reactor Fails to Auto TripAuto Actuation Failure: HPSI
Charging Flow Control Failure
MSI Train A Fails to Auto ActuateMSI Train B Fails to Auto Actuate
0% BT1 3
MALF MS01D Main Steam Line D Rupture Inside CTMT 20% 60 second ramp BT1
Section 4Page 5 of 61
(SECTION 4
Lesson Title: ATWS with Faulted
ID Number: 2K2 NRC-001
Time IDA/MalfTask
Assian
Revision: 0
StandardI nctriuctr I nformatinn/Artivitv Expected Action-
Event
MALF
MALF
MALF
Malfunctions
CC03B
ED08C
FW08A
Loss of RCP B Cooling water Supply
Loss of Instrument Bus VIAC-3
A S/G FRV Failure
40% ramp 30 seconds
ramp 60 seconds
RSCU 1
RSCU 2
RSCU 30%
Lead Examiner: Refer to the "Briefing Script for the Operational Exam" and brief the crew.
Section 4Page 6 of 61
SECTiON 4
Lesson Title: ATWS with Faulted S/G
Revision: 0ID Number: 2K2 NRC-001Task
AssianTime- InAIMInf Inctritetnr InfnrmatinnIArtivitv Expjected Action StandardI1W Iu vnlwa# I..~vs....-....... ,. a___
T+1 EVENT 1: Pump the ContainmentDrains Transfer Tank
OP3335A Reactor Plant GaseousDrains, Rev. 7
[Normal Evolution]
REMOTE When directed as PEO use Remote toopen 3DGS-V949. Delay 3 minutes
WOROI before reporting back.
RO IF CDTT is being pumped to the boronrecovery tanks, UNLOCK and OPEN3DGS-V949, gaseous drains to boronrecovery isolation.
OPEN the following:
* 3GSN*CTV105, "N2 TO PRT"
OP 3335AStep 4.4.1
RO OP 3335AStep 4.4.2
* 3GSN*CV8033, "N2 TO PRT"
RO IF CDTT is being pumped to theradioactive gaseous waste degasifier,PEFORM the following:
OP 3335AStep 4.4.3
a. SELECT "DRAINS DEGAS" on thedegasifier function selector switch(MB3).
b. Go To step 4.4.4.
Section 4Page 7 of 61
SECTIuN 4(,
Lesson Title: ATWS with Faulted S/G
Revision: 0ID Number: 2K2 NRC-001Task
AssianTrn-- IfA M~UIf Incfriirtnr Infnrmntinn/Activitv ExDected Action StandardI mimic *s.,,-# ,w,~54, . - . - -
RO START one containment drainstransfer pump (MB1)
* 3DGS-P1A, "CTMT DRAINSPPS`""A"
* 3DGS-P1B, "CTMT DRAINSPPS'"B"
OP 3335AStep 4.4.4
RO IF the low pressure N2 regulator isbypassed, CYCLE one of the followingas necessary to maintain pressurebetween 16 and 21 psia, as read onDGS-PI29 (MB1).
* 3GSN*CTV105, "N2 TO PRT"
* 3GSN*CV8033, "N2 TO PRT"
OP 3335AStep 4.4.5
RO WHEN CDTT level is less than 300gallons, STOP the containment drainstransfer pump (MB1)
* 3DGS-P1A, "CTMT DRAINSPPS""A"
* 3DGS-Pl B, "CTMT DRAINSPPS""B"
OP 3335AStep 4.4.6
Section 4Page 8 of 61
!SECTION 4
(,
Lesson Title: ATWS with Faulted S/G
Revision: 0ID Number:
Tinsa
2K2 NRC-001Task
AssianIItAIRA M If Inftrir-tnr Infnrmqatinn/Activitv Expected Action StandardI 1111V 1LOPlllve"l -ltO L ll ElE lV-A l X ____ ___
RO IF CDTT was being pumped to theradioactive waste degasifier, SELECT"LETDOWN DEGAS" on the degasifierfunction selector switch (MB3).
OP 3335AStep 4.4.7
RO
RO
CLOSE 3GSN*CTV105 and3GSN*CV8033, "N2 TO PRT".
IF CDTT was being pumped to theboron recovery tanks, CLOSE andLOCK 3DGS-V949, gaseous drains toboron recovery isolation.
OP 3335AStep 4.4.8
OP 3335AStep 4.4.9
.
T= normalevolution inprogress
MALFCC03B4Al0 /n
EVENT 2: Partial Loss of RCP BCooling Water Supply
_ .- i
ram 30 NOTE: Modify MALF to about 55%ramp after annunciator received and asseconds necessary to maintain RCP bearing
RSCU1 temperatures less than 1950 F.
ARP OP3353.MB4B, 3-4B Rev. 004RCP B COOLER SUPPLY PRES LO
US IF a loss of RPCCW has occured, GoTo AOP 3561, "Loss of Reactor PlantComponent Cooling Water"
OP3353.MB4B, 3-4B
Step 1
Section 4Page 9 of 61
(SECTION 4
(
Lesson Title: ATWS with Faulted S/G
ID Number: 2K2 NRC-001 Revision: 0Task
AssianTi ma InAIMnif Instrrftnr Infnrmation/Activitv Expected Action Standardla 1111 an eA _A..... ;
RO CHECK the following parameters(MB1):
* 3CCP-FI1 5B, RPCCW containmentsupply flow, 600 to 1000 gpm
* 3CCP*MOV45B, Train B RPCCWsupply containment isolation, open
* 3CCP*AOV179A, Train A RPCCWheader division valve, closed
* 3CCP*AOV179B, Train B RPCCWheader division valve, closed
* 3CCP*AOV1 80A, Train A RPCCWheader division valve, closed
* 3CCP*AOV180B, Train B RPCCWheader division valve, closed
OP3353.MB4B, 3-4B
Step 2
Section 4Page 10 of 61
(.SECTiON 4
Lesson Title: ATWS with Faulted
ID Number: 2K2 NRC-001
Time IDA/MalfTask
AssianIncfriirftnr Infnrmatinn1Antivitvt vv..w- . ... ,
RO
F
Expected Action
MONITOR the following RCP B thrustbearing and radial bearing temperaturecomputer points ("RCP Status," NSSS,picture 15)
* RCS-T480A, RCP B upper thrustbearing
* RCS-T484A, RCP B upper radialbearing
* RCS-T480B, RCP B lower thrustbearing
* RCS-T484B, RCP B lower radialbearing
Revision: 0
Standard
OP3353.MB4B, 3-4B
Step 3
Section 4Page 11 of 61
SEC1 ioN 4f
Lesson Title: ATWS with Faulted S/G
Revision: 0ID Number: 2K2 NRC-001Task
AssianThea- I A IRAM.If Inatrm-tr InfnrmatinnlActivitv Expected Action StandardI 1IIW ELAMIWIGAIN . … J_ *_--_T
T= Step 4 MODIFYMALFCC03B
to 55%
RSCU 1
Modify, asnecessaryto keep
thrustbearingtempsless than1950F
NOTE: To Instructor, for thismalfunction, as "valve" increasesseverity of malfunction decreases.
USE NSSS picture 15 to monitor RCPseal temperatures and
USE Real-Time trend RCS-T480A tomonitor RCP bearing temperatures
RO IF at any time any RCP B thrustbearing or radial bearing temperaturecomputer point is greater than 195 0F,PERFORM the following:
OP3353.MB4B, 3-4B
Step 4
IF reactor power is greater than P-8(37%) PERFORM the following:
1. TRIP the reactor
2. STOP RCP B
3. Go To E-0, "Reactor Trip or SafetyInjection"
Refer to AOP 3554, "RCP Trip orStopping an RCP at Power", andREMOVE RCP B from service.
NOTE: When the US calls either thesystem engineer, the OPS manager orthe Duty Officer RECOMMEND thatthey reduce power per AOP 3575,Rapid Downpower, at 1 %/min toremove the RCP from service.
Refer to Technical Specifications, andDETERMINE Limiting Condition forOperation
OP3353.MB4B, 3-4B
Step 5
Section 4Page 12 of 61
alSECTION 4
I'
Lesson Title: ATWS with Faulted S/G
Revision: 0ID Number: 2K2 NRC-001Task
AssianTim^ InAM1nIf Inctrniltnr Infnrmatinn1Artivitv Exoected Action StandardI vII lC 5|51*5fl -, - -- _
EVENT 2a: Rapid Downpower toRemove RCP
[Reactivity Manipulation]
AOP 3575, Rapid Downpower,
Rev. 7
* A CONVEX requested emergencygeneration reduction should becompleted within 15 minutes ofnotification.
AOP 3575Step 1NOTE
* If a unit shutdown is required, thetarget power level should bebetween 20% and 25% reactorpower.
* If at any time ROD CONTROLBANKS LIMIT LO - LO (MB4C 4 - 9) annunciator is received, DO NOTgo to AOP 3566, ImmediateBoration. Immediately perform step9.
CREW Determine Power Reduction Rate(%/min).
US Check desired power reduction rate -LESS THAN OR EQUAL TO 5%/min.
RO/ Perform the following for an immediateBOP turbine unloading:
AOP 3575Step 1
AOP 3575Step 1.a
AOP 3575Step 1.aRNO
Section 4Page 13 of 61
fI (SECTION 4
Lesson Title: ATWS with Faulted S/G
ID Number: 2K2 NRC-001 Revision: 0Task
AssianTim&% I nA/Mlf Instriirtnr Infnrmation/Activitv ExDected Action StandardI. .._. ...1..-----. ...... ..- _-_… -n- _
RO
BOP
Us
US
US
1) Place rod control SEL switch inAUTO.
2) Rotate LOAD LIMIT SET to reduceturbine load the desired amount upto a 480 MWe reduction.
3) Proceed to Step 5
Check power reduction - CONVEXREQUESTED
Perform load reduction at 5%/min andProceed to Step 1.d.
AOP 3575Step 1.b
AOP 3575Step 1.bRNO
CREW Perform load reduction at 5% min andProceed to step 2.
AOP 3575Step 1.c
AOP 3575Step 1.d
CREW Determine power reduction rateusing Table.
Total Power Change (A%)I- -,I I
10% 20% 30% 40% 50% 60% 70% 80%Il t . I I
315F 1 3 3 5 5 5
30 0.5 1 1 3 3 3 3 3
45 0.5 0.5 1 1 3 3 3 3
Section 4Page 14 of 61
I
SECTIUN 4
Lesson Title: ATWS with Faulted S/G
ID Number: 2K2 NRC-001 Revision: 0Task
AssiqnTime InA/Malf Instructor Information/Activitv Expected Action Standard
60 i 0.5 0.5 1 1 1 3 3
Time to 75 0.5 0.5 1 1 1 _1 ;_
Reduce 90 0.5 0.5 0.5 1 1 1 1
Power 105 0.5 0.5 0.5 0.5 1 1 1
(min) 120 0.5 0.5 0.5 0.5 1 1
135 0.5 0.5 0.5 0.5 1 1
150 0.5 0.5 0.5 0.5 0.5 1
160 _ _ 0.5 0.5 0.5 0.5 0.5 0.5
US
RO
RO
CREW
Check Rod Control In AUTO.
Place rod control SEL switch inAUTO and Proceed to NOTE prior toStep 3.
IF automatic rod control NOTavailable, THEN Move rods in MANas necessary to maintain Tavg within
+50F of Tref.
Align EHC Panel
AOP 3575Step 2
AOP 3575Step 2 RNO
AOP 3575Step 3
Section 4Page 15 of 61
(SECTiuN 4
I:
Lesson Title: ATWS with Faulted S/G
Revision: 0ID Number: 2K2 NRC-001Task
AssianTiara InA/Minlf nctrmletor Wnfrmatinn/Artivitv Expected Action StandardI I IIt IEOF5i"Iu -v -. . .
US
US
US
BOP
BOP
BOP
BOP
Check turbine OPERATING MODE -MANUAL
Proceed to step 4.
Check LOAD LIMIT LIMITING light -LIT
Proceed to step 3.e.
Intermittently Press DECREASELOAD pushbutton until LOAD LIMITLIMITING light - NOT LIT
Rotate LOAD LIMIT SET adjust knobat least one full turn in raise direction
Select DECREASE LOADING RATEto ON
Select LOAD RATE LIMIT % MIN torequired power reduction rate (%min)
If at any time the power reductionrate or target power level must bechanged, Return to step 1.
AOP 3575Step 3.a
AOP 3575Step 3.aRNO
AOP 3575Step 3.b
AOP 3575Step 3.bRNO
AOP 3575Step 3.c
AOP 3575Step 3.d
AOP 3575Step 3.e
AOP 3575Step 3.f
AOP 3575Step 4NOTE
Section 4Page 16 of 61
(SECTION 4
Lesson Title: ATWS with Faulted
ID Number: 2K2 NRC-001
Time IDA/Malf Instructor Information/ActivityTask
Assign
US/RO
RO
F
Expected Action
Verify Power Reduction Rate
Check power reduction rate 5% MIN
Perform the applicable action:
Revision: 0
Standard
AOP 3575Step 4
AOP 3575Step 4.a
AOP 3575Step 4.aRNO
* IF power reduction rate is 3%min,
THEN
Proceed to step 5.
* IF power reduction rate is LESSTHAN 3% min,
THEN
Proceed to NOTE prior step 6.
Check power reduction - REQUIREDTO STABILIZE PLANT
Proceed to step 5.
Proceed to NOTE prior step 7.
RO
RO
AOP 3575Step 4.b
AOP 3575Step 4.bRNO
AOP 3575Step 4.c
Section 4Page 17 of 61
I'
SECTION 4
Lesson Title: ATWS with Faulted S/G
Revision: 0ID Number: 2K2 NRC-001Task
AssianTime^ InAIMinIf I nctriuetor I nformatinn/Artivitv Expected Action StandardI IS ._
RO Initiate Rapid Boration
Verify RCS makeup system in -AUTO
Perform the following:
AOP 3575Step 5
AOP 3575Step 5.a
AOP 3575Step 5.aRNO
1. Select AUTO on the reactorcoolant makeup select switch.
2. Select START on the reactorcoolant makeup start switch.
START one boric acid transfer pump. AOP 3575Step 5.b
Proceed to step 5.d.
OPEN emergency boration valve(3CHS*MV8104).
Verify direct boric acid flow (3CHS-FI183A) - INDICATED.
Perform the following to initiategravity boration:
RO
AOP 3575Step 5.bRNO
AOP 3575Step 5.c
AOP 3575Step 5.d
AOP 3575Step 5.dRNO
Section 4Page 18 of 61
SECTIUN 4
Lesson Title: ATWS with Faulted S/G
ID Number: 2K2 NRC-001 Revision: 0Task
Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard
1. Place the charging line flowcontrol valve in MAN.
2. OPEN at least one gravity feedboration valve.
3. CLOSE at least one VCT outletisolation valve.
4. Limit net charging flow to the RCSto LESS THAN 75 gpm (charging +seal injection - RCP seal return).
5. Adjust charging line flow controlvalve as required.
IF gravity boration flow can NOT beestablished,
THEN
TRIP the reactor and Go to E - 0,Reactor Trip or Safety Injection.
6. Proceed to step 5.f.
OPEN charging line flow control AOP 3575valve, to match boric acid flow Step 5.e(3CHS-FI 183A)
RO Record time boration started AOP 3575
Time Step 5.f
Section 4Page 19 of 61
(. SEC1I oN 4
Lesson Title: ATWS with Faulted S/G
Revision: 0ID Number: 2K2 NRC-001Task
AssianTombs IMAIMAlf Inctrniftnr Infnrmatinn/Activitv Expected Action StandardI1m IU*115t*1fl
Energize all PZR heaters.
Determine required boric acidaddition by multiplying total powerchange (A%) by 15 (gal/%) =gal.
Determine required time to borate bydividing required gallons of boric acidby the direct boric acid flowrate (net
charging flow rate if using gravityboration) _ min.
Check turbine load decrease - INPROGRESS OR COMPLETED.
Proceed to NOTE prior to Step 7.
Proceed to NOTE prior to Step 8.
AOP 3575Step 5.g
AOP 3575Step 5.h
AOP 3575Step 5.i
AOP 3575Step 5.j
AOP 3575Step 5.jRNO
AOP 3575Step 5.k
US
US
US
Section 4Page 20 of 61
(SECTION 4
Lesson Title: ATWS with Faulted S/G
ID Number: 2K2 NRC-001 Revision: 0Task
AssianTime I nf IM2nIf Inctri.ttnr Infnrmation/Activitv ExDected Action StandardIII , ; iWtA, ..- . *5- - - - ._
CREW
US
US/RO
RO
Boric acid total volume addition andflow rates are based onapproximations. Adjustments shouldbe made to these values asnecessary to ensure the reactorreaches the desired end state of:
* Tavg on program
* Rods above the Rod InsertionLimit
* AFD on or above the target value
Align RCS Makeup System ForBoration.
Determine required boric acidaddition by multiplying total powerchange (A%) by 15(gal/%) =gal.
Set the boric acid batch counter tototal gallons of boric acid required.
Check power reduction rate- AT0.5%/min.
Adjust boric acid blend flow controllerpot setting to 3.75 (15 gpm) andProceed to Step 6.e.
AOP 3575Step 6
AOP 3575Step 6.a
AOP 3575Step 6.b
AOP 3575Step 6NOTE
US
RO
AOP 3575Step 6.c
AOP 3575Step 6.cRNO
Section 4Page 21 of 61
( (SECTION 4
Lesson Title: ATWS with Faulted S/G
ID Number: 2K2 NRC-001 Revision: 0Task
AssianTima MAIMnIf Instruictnr Information/Activitv ExDected Action Standard- -- - -- --
RO Adjust boric acid blend flow controllerpot setting to 1.9 (7.5 gpm).
RO Select BORATE on the reactorcoolant makeup select switch.
RO Select START on the reactor coolantmakeup start switch.
RO Verify boric acid flow - INDICATED
US Return to step 5.
RO Energize all PZR heaters.
RO If a unit shutdown is beingperformed, the final MWe loadshould be approximately 230 MWe.
US/BOP Initiate Load Reduction.
BOP Check turbine OPERATING MODE -MANUAL
BOP Unload turbine at required rate usingthe STANDBY LOAD SET pot andProceed to step 7.e.
AOP 3575Step 6.d
AOP 3575Step 6.e
AOP 3575Step 6.f
AOP 3575Step 6.g
AOP 3575Step 6.gRNO
AOP 3575Step 6.h
AOP 3575Step 7NOTE
AOP 3575Step 7
AOP 3575Step 7.a
AOP 3575Step 7.aRNO
Section 4Page 22 of 61
( (SECTIUN 4
Lesson Title: ATWS with Faulted S/G
Revision: 0ID Number: 2K2 NRC-001Task
AssianThea MI Qftfilf Inatriu-tnr Infnrmatinn/Artivitv Expected Action StandardI me11W ILI W1 IWEICINI - -- - _
BOP
BOP
BOP
BOP
BOP
BOP
US
BOP
US/RO
Check rapid or gravity boration - INPROGRESS
Proceed to step 7.d.
Check LOAD RATE LIMIT % MIN setat - 3% OR 5%.LIMITING light - LIT.
Select LOAD RATE LIMIT % MIN to3% or 5%.
Utilizing DECREASE LOADpushbutton, Adjust LOAD SET todesired final MWe (target powerlevel)
Check power reduction - CONVEXREQUESTED.
Inform CONVEX of load reductionrate (MWe/min) and final MWe level.
Maintain initial MVAR loading duringpower reduction, unless directedotherwise.
Check boration - IN PROGRESS
AOP 3575Step 7.b
AOP 3575Step 7.bRNO
AOP 3575Step 7.c
AOP 3575Step 7.cRNO
AOP 3575Step 7.d
AOP 3575Step 7.e
AOP 3575Step 7.eRNO
AOP 3575Step 7.f
AOP 3575Step 7.g
Section 4Page 23 of 61
( ISECTiuN 4
(
Lesson Title: ATWS with Faulted S/G
ID Number: 2K2 NRC-001 Revision: 0Task
AqsianTown rlA IRAIf Inoerm ujtr Infnrmntinn/At-tivitv Exoected Action StandardI 1111W 1L.IrWaviall 111�1.
T= AFTERRCPdownpowerandExaminerConcurs
MALFED08C
EVENT 3: Loss of Instrument BusVIAC-3
RSCU 2
AOP 3564, Loss of One ProtectiveSystem Channel, Rev. 8
US Loss of VIAC-1 (2) results in dieselgenerator sequencer A(B) being de-energized. If an ESF actuation takesplace during this condition, thefollowing items will not occurautomatically.
AOP 3564Step 1CAUTION
RO Determine Plant Status AOP 3564Step 1
Check reactor status - TRIPPED AOP 3564Step la
Proceed to Step 2 AOP 3564Step laRNO
CREW Check the Following ControlSystems:
AOP 3564Step 2
* Verify rod control - OPERATINGNORMALLY IN AUTO
Section 4Page 24 of 61
(f (.
SECTION 4
Lesson Title: ATWS with Faulted S/G
ID Number: 2K2 NRC-001 Revision: 0Task
As-innY;.- IlAIMlkIf Inftriirntr Infnrmatinn/Atctivitv ExDected Action StandardI III IV IuIwc sLoPuvmv 1111se sr-| -II.. .
* Verify SG level - OPERATINGNORMALLY IN AUTO
* Verify PZR level - OPERATINGNORMALLY IN AUTO
* Verify PZR pressure - OPERATINGNORMALLY IN AUTO
Perform the following: AOP 3564Step 2RNO
a. Place the affected controller inMANUAL.
b. Stabilize plant parameters.
c. Defeat the failed channel input.
d. Return the affected controller toAUTO.
Verify Normal Letdown - IN SERVICE
Verify Cold Overpressure ProtectionSystem - BLOCKED
Block the affected Train of ColdOverpressure Protection System
RO
RO
AOP 3564Step 3
AOP 3564Step 4
AOP 3564Step 4RNO
Section 4Page 25 of 61
SECTION 4
Lesson Title: ATWS with Faulted S/G
Revision: 0ID Number: 2K2 NRC-001Task
AeminnT:� *IA IRAl-L1 Incr.rtr nfrormntio~n1Aritifxtv Exoected Action StandardI ime *I.,UMuV~i IEI 1.1LI'%,LA1 I..,
RO Verify VCT Level (3CHS*LTI12)Using Computer Point 3CHS-L 112 -CONTROLLING NORMALLY
AOP 3564Step 5
[Tech Specs] US Refer to the Following TechnicalSpecifications for ApplicableActions:
AOP 3564Step 6
* If in Mode 2 and LESS THAN 1 0-'IR amps, 3.3.1 Reactor Trip SystemInstrumentation:
Action 4 (FU 6-a)Action 8 (FU 17.a)
* 3.3.1 Reactor Trip SystemInstrumentation Action 8 (FU 17.b)
3.3.2 Action 17, the operable channelis placed in the bypass condition
* 3.3.2 ESF Actuation SystemInstrumentation:
Action 16 (FU 7.d)Action 17 (FU 2.c & 3.b.3)Action 18 (FU 7.e)Action 20 (FU 8.a & 8.b)**entry into T/S 3.0.3 required
* If in Mode 5 or 6, 3.3.2 ESFActuation System InstrumentationAction 26 (FU 3.c)
Section 4Page 26 of 61
!,SECT IUN 4
l'
Lesson Title: ATWS with Faulted S/G
ID Number:
Time
2K2 NRC-001 Revision: 0Task
AssianInA/Malf Instructor Information/Activitv Expected Action Standard
* If in Modes 4, 5 or 6, 3.4.9.3Overpressure Protection Systems
* 3.8.3.1 and 3.8.3.2, Onsite PowerDistribution
3.8.3.1.e Action b, re-energize the ACvital bus within 2 hours or be in HOTSTANDBY within the next 6 hours andin COLD SHUTDOWN within thefollowing 30 hours.
NOTE: If PEO and/or Maintenance aredispatched to investigate VIAC they willfind it de-energized and Maintenancewill find the 150A input fuse blown.Report that they will begin procurementand replacement procedures. (Foundon EE-1BA)
RO Check All Vital 120 VAC InstrumentBuses - ENERGIZED
AOP 3564Step 6
T= VIAC MALF EVENT 4: Feed Reg Valve Failure
Tech Specs FWO08A NOTE: Loss of control at the Feedaddressed 0% 60 sec Station will require an anticipatory
ramp reactor trip
RSCU 3
T= AOP3571, Aft. Bstep 4
MALFI/Os 32NRP09A/BRP10A/B
EVENT 5: ATWS; 32N Fails toDe-energize
Section 4Page 27 of 61
(SECt iuN 4
Lesson Title: ATWS with Faulted S/G
Revision: 0ID Number: 2K2 NRC-001Task
AssianTi m InAiMnif Inc~triutnr Infnrmatinn/Activitv Expected Action Standard3 1111� .--- - -- j
FR-S.1, Response to NuclearPower Generation/ATWS, Rev. 16
US * If RHR is in service, all referencesto AFW are NOT applicable.
* Immediate Boration (step 4, 5 and6) may be performed in parallelwith steps 1*, 2*, or 3, provided thatefforts to initiate ImmediateBoration do not preclude or delaycompletion of steps 1*, 2*, or 3.
Verify Reactor Trip
EOP 35FR-S.1Step 1NOTE
EOP 35FR-S. 1Step 1*
RO
* Check reactor trip and bypassbreakers - OPEN
* Check rod bottom lights - LIT
* Check neutron flux - DECREASING
RO TRIP the reactor. EOP 35FR-S.1Step 1*RNO
IF the reactor will NOT trip,
THEN
Drive rods in (AUTO or MANUAL).
Section 4Page 28 of 61
I'SECTION 4
(.
Lesson Title: ATWS with Faulted S/G
ID Number:
Time
2K2 NRC-001 Revision: 0Task
AssiqnIDA/Malf Instructor Information/Activitv Expected Action Standard
BOP Verify Turbine Trip
Check all turbine stop valves -CLOSED
Verify AFW Pumps Running
EOP 35FR-S.1Step 2*
EOP 35FR-S.1Step 2.a
EOP 35FR-S.1Step 3
BOP
* Check MD pumps - RUNNING
* Check TD pump - RUNNING, IFNECESSARY
reactor tripMALFCV1 8
EVENT 6: Charging Flow ControlFailure
RO Initiate Immediate Boration of RCS EOP 35 FR-S.1 Step 4
Check SI - NOT ACTUATED
Check one charging pump - RUNNING
START one charging pump.
EOP 35FR-S.1Step 4.a
EOP 35FR-S. 1Step 4.b
EOP 35FR-S.1Step 4.bRNO
Section 4Page 29 of 61
( aSECI-ON 4
Lesson Title: ATWS with Faulted S/G
ID Number:
Timg%
2K2 NRC-001 Revision: 0Task
AssicinIDAIMnif Inqtrictor Information/Activitv Expected Action StandardI . -1 .1 . .-. .
Align boration path:
1) START at least one boric acidtransfer pump
2) OPEN emergency boration valve(3CHS*MV81 04)
Check normal charging flow pathaligned:
1. Charging flow control valve - OPENOR THROTTLED
AND
CAPABLE OF BEINGTHROTTLED
EOP 35FR-S. 1Step 4.c
EOP 35FR-S.1Step 4.d
2) Charging header loop isolationvalve (3CHS*AV8146 or3CHS*AV8147) - OPEN
3. Charging header isolation valves -OPEN
* 3CHS*MV8106
* 3CHS*MV8105
Section 4Page 30 of 61
!i'
SEC ION 4
Lesson Title: ATWS with Faulted S/G
Revision: 0ID Number: 2K2 NRC-001Task
Assiane.--d InA/Mmif Inctriuctr Infnrmation/Activitv Expected Action StandardI IIIU *L1I**1V *..tA.. .. -. .
Position valves as required. EOP 35FR-S.1Step 4.dRNO
NOTE: Proceed To step 5 IF a controllable normal charging flowpath can NOT be established, THENProceed to step 5.
RO Align Safety Grade Boration Path
Check busses 34C and 34D - BOTHENERGIZED
OPEN charging header flow controlvalve (3CHS*HCV190A)
open CHARGING HEADER BYPASSISOLATION (3CHS*MV8116)
CLOSE charging flow control outletisolation (3CHS*MV8106)
EOP 35FR-S. 1Step 5
EOP 35FR-S.1Step 5.a
EOP 35FR-S.1Step 5.b
EOP 35FR-S.1Step 5.c
EOP 35FR-S.1Step 5.d
Section 4Page 31 of 61
(SEC;, ION 4
f
Lesson Title: ATWS with Faulted S/G
Revision: 0ID Number: 2K2 NRC-001
Task
Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard
T= FR-S.1 REMOVE NOTE: Call back as PEO as report Proceed to step 6 EOP 35
step 5 RP09A/B reactor trip breakers open. FR-S.1
complete RP10A/B Step 5.e
NOTE: RP02A/B may not beINSERT necessaryRP02A/B
T= FR-S.1 MALF EVENT 7: Main Steam Line D RO Verify Boration Flow EOP 35
step 6 MS01D, Rupture Inside CTMT FR-S. 1
20%, 60 Step 6
secondramp
T= Initial MALFRP08
EVENT 8: MSI Fails to AutoActuate
Check PZR pressure - LESS THAN2350 psia
Check normal charging flow path -ALIGNED
EOP 35FR-S.1Step 6.a
EOP 35FR-S.1Step 6.b
Section 4Page 32 of 61
1i:
SEC riON 4
Lesson Title: ATWS with Faulted S/G
Revision: 0ID Number: 2K2 NRC-001Task
AssianTime- IfA/Mnlf Inc~triirtnr Infnrmation/Activitv Expected Action StandardI 11111W .. -.. ---- - -- j
Perform the applicable action:
* IF Si actuated, THEN Proceedto step 7.
* IF a safety grade boration flowpath is established, THEN
1. Using GA-14, Establish reactorvessel head vent letdown to thePRT.
2. Proceed to step 7.
Check the Following Has Occurred
Verify reactor trip breakers - OPEN
Verify turbine trip
Check If Si Is Actuated
EOP 35FR-S.1Step 6.bRNO
US EOP 35FR-S.1Step 7
EOP 35FR-S.1Step 7.a
EOP 35FR-S.1Step 7.b
RO EOP 35FR-S.1Step 8
EOP 35FR-S.1Step 8.a.
Verify SAFETY INJECTIONACTUATION annunciator (MB4D 1-6or MB2B 5-9) - LIT
Section 4Page 33 of 61
¢ ¢SEC s ION 4
Lesson Title: ATWS with Faulted S/G
ID Number: 2K2 NRC-001 Revision: 0Task
AssianTim. IFIA/Mnlf Instrirtnr Infnrmatinn/Activitv Expected Action StandardI 1111�- ---- - -- J -- - -
[Critical Task]
Establish flow from at least one SIpump before completion of the checkof E-0, steps 3-14 in FR-S.1.
Manually actuate MSI or close MSIV'sbefore completion of FR-S.1 step 13.
NOTE: Crew should notice MSI isrequired and actuate when reviewingStep 10 of E-0.
Verify steps 3-14 of E-0, Reactor Tripand Safety Injection
EOP 35FR-S.1Step 8.b.
BOP Check AFW Suction Source
Check DWST level - LESS THAN80,000 gal
Proceed to step 10 and,
IF DWST level decreases to LESSTHAN 80,000 gal,
EOP 35FR-S.1Step 9
EOP 35FR-S.1Step 9.a
EOP 35FR-S. 1Step 9.a,RNO
THEN Perform step 9.b
BOP Check SG Levels EOP 35FR-S.1Step 10
Section 4Page 34 of 61
SEC, ION 4
Lesson Title: ATWS with Faulted S/G
ID Number: 2K2 NRC-001 Revision: 0Task
Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard
Verify NR level in at least one SG - EOP 35GREATER THAN 8% (42% ADVERSE FR-S.1CTMT) Step 10.a
Perform the following: EOP 35
1. Verify total feed flow is GREATER Step 10.aTHAN 1150gpm RNO
IF the flow is LESS THAN 1150gpm THEN
START pumps and Align valves asnecessary.
2. Maintain total feed flow GREATERTHAN 1150 gpm until NR level isGREATER THAN 8% (42%ADVERSE CTMT) in at least oneSG.
Control feed flow to maintain NR level EOP 35between 8% and 50% (42% and 50% FR-S.1ADVERSE CTMT) Step 10.b
High Radiation Area Key and Locked EOP 35Valve Key are required for FR-S.1performance of some local actions in Step 11the following step. NOTE
Section 4Page 35 of 61
(SECTION 4
Lesson Title: ATWS with Faulted S/G
ID Number:
Timn
2K2 NRC-001 Revision: 0Task
AssianInAIMnif Instrurctnr Information/Activitv Expected Action StandardI to I I- .. .- _. - - __ . .. - - - - - - ___ __ - - __ - - - __ - - -1 . -
RO/US/PEO
Verify All Dilution Paths Isolated
* Check primary makeup water toblender (3CHS*FCV1 1 1A) -CLOSED
EOP 35FR-S.1Step 11
NOTE: As US request wait 3 minutesand report chemical mix tank outletisolation valve (3CHS*V317) -CLOSED and manual dilution valve(3CHS*V305) - CLOSED
* Locally check chemical mix tankoutlet isolation valve (3CHS*V317)- CLOSED
* Locally check manual dilution valve(3CHS*V305) - CLOSED
* Check BTRS - OFF ANDBYPASSED
CREW Check for Reactivity Insertion FromUncontrolled RCS Cooldown.
* RCS temperature - DECREASINGIN AN UNCONTROLLED MANNER
OR
* Any SG pressure - DECREASINGIN AN UNCONTROLLED MANNER
EOP 35FR-S.1Step 12
Section 4Page 36 of 61
( lSECTION 4
Lesson Title: ATWS with Faulted S/G
ID Number: 2K2 NRC-001 Revision: 0Task
AssiqnTima IMAIM2af Instructor Information/Activitv Expected Action Standard
[Critical Task] Manually actuate MSIor close MSIV's before completion ofFR-S.1 step 13.
BOP Check MSIVs and MSIV BypassValves - CLOSED
EOP 35FR-S. 1Step 13
EOP 35FR-S. 1Step 13RNO
CLOSE valves.
BOP Identify Faulted SGs EOP 35FR-S.1Step 14
Check pressures in all SGs:
* ANY SG PRESSUREDECREASING IN ANUNCONTROLLED MANNER
OR
* ANY SG COMPLETELYDEPRESSURIZED
EOP 35FR-S.1Step 14.a
US * At least one SG must bemaintained available for RCScooldown.
EOP 35FR-S.1Step 15CAUTION
Section 4Page 37 of 61
(SEC ION 4
Lesson Title: ATWS with Faulted S/G
ID Number: 2K2 NRC-001 Revision: 0Task
Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard
* If all SGs are faulted, at least 100gpm feed flow should bemaintained to each SG.
* If the TD AFW pump is the onlyavailable source for feed flow, asteam supply to the TD AFW pumpmust be maintained from at leastone SG.
BOP Isolate Each Faulted SG EOP 35FR-S.1Step 15
* Isolate main feedline
* Isolate AFW flow
* CLOSE steam supply isolationvalve to TD AFW pump
* Verify SG atmospheric dump valve- CLOSED
* Verify SG atmospheric dumpbypass valve - CLOSED
* Verify SG blowdown isolation valve-CLOSED
* Verify SG chemical feed isolationvalve - CLOSED
Section 4Page 38 of 61
SEC; & ON 4
Lesson Title: ATWS with Faulted S/G
Revision: 0ID Number: 2K2 NRC-001Task
AssianTinan InA1iMnIf InctrUidtr Infnrmatinn/Activitv Expected Action StandardI ,,,,*: *5luW.- . .. ...... U. ... . ---. .. ., _ ..........---.--- ,
US/RO Check Core Exit TCs - LESS THAN12000F
EOP 35FR-S.1Step 16
EOP 35FR-S.1Step 17
RO Verify Reactor Subcritical
* Check power range channels -LESS THAN 5%
* Check intermediate range channels- NEGATIVE STARTUP RATE
US Verify No Fuel Damage
Request Chemistry obtain RCSsamples
Request the ADTS obtain samplesusing any means possible.
Using MP-26-EPI-FAP06,"Classification and PARs," Evaluate forincident classification
EOP 35FR-S. 1Step 18
EOP 35FR-S.1Step 18.a
EOP 35FR-S. 1Step 18.aRNO
EOP 35FR-S.1Step 18.b
Section 4Page 39 of 61
fSEC-I ION 4
!
Lesson Title: ATVVS with Faulted S/G
Revision: 0ID Number: 2K2 NRC-001Task
AnsianT.:_ IMA /RM-14 Inctriu,4 ,r InfnrmntinnIAftivitv Expected Action StandardI 1111t: Rimilviall 1111-0t.1%A�1%W. .
US Verify Security Has Checked SLCRSDoors - CLOSED
Request status of SLCRS doors fromSecurity.
EOP 35FR-S.1Step 19
EOP 35FR-S.1Step 19RNO
EOP 35FR-S. 1Step 20CAUTION
EOP 35FR-S.1Step 20
US Boration shall continue duringsubsequent actions until adequateshutdown margin is obtained.
Go to Procedure and Step in Effectand Initiate Monitoring of the CSFStatus Trees
NOTE: Depending on the pace of thecrew the transition may be to FR-Z.1,Response to High CTMT Pressure,page 56 of this Sim Guide
US
E-0, Reactor Trip or SafetyInjection, Rev. 21
RO Determine If ADVERSE CTMTConditions Exist
E-0, Step 15
* Ctmt temperature GREATERTHAN 180 0F
OR
* Ctmt radiation GREATER THANO0 R/hr
Section 4Page 40 of 61
SECTIION 4
Lesson Title: ATWS with Faulted S/G
Revision: 0ID Number: 2K2 NRC-001
TaskAnqianT:�_ IrA IRA-IS 1nfrrm!nfinn1ArfiVifV ExDected Action Standard
I Ime II.I.M11VICIII It 117 1.1 " %, %.W I I... .....
CREW DO NOT use ADVERSE CTMTparameters.
E-0,Step 15,RNO
RO Verify ECCS Flow E-0, Step 16
RO
RO
US
Check charging pumps -
FLOW INDICATED
START pumps and Align valves.
Check RCS pressure - GREATERTHAN 1650 psia (1950 psiaADVERSE CTMT)
Proceed to Step 16.d
Proceed to step 17.
Check SI pumps - FLOW INDICATED
START pumps and Align valves.
Check RCS pressure - LESS THAN300 psia (500 psia ADVERSE CTMT)
E-0,Step 16.a
E-0,Step 16.a,RNO
E-0,Step 16.b
E-0,Step 16.b,RNO
E-0,Step 16.c
E-0,Step 16.d
E-0, Step16.d RNO
E-0,Step 16.e
Section 4Page 41 of 61
(.
SEC | ION 4
Lesson Title: ATWS with Faulted S/G
Revision: 0ID Number: 2K2 NRC-001
TaskAssinnI narsurtr nfnrrmnfirn1Art-iviftr Expected Action Standard
_ h IErA IRA -1Z
lime IUIAIIVIdUII IIEZLIU%.,LJE A__. ro d
Proceed to step 17.
Check RHR pumps - FLOWINDICATED.
START pumps and Align valves.
E-0,Step 16.eRNO
E-0,Step 16.f
E-0,Step 16.fRNO
CREW should perform a short briefand come out of "Master Silence" atthe completion of Step 16.
BOP Verify Adequate Heat Sink E-0, Step 17
Check NR level in at least one SG -GREATER THAN 8% (42% ADVERSECTMT)
Proceed to Step 17.d.
E-0,Step 17.a
Us
BOP
US
BOP
E-0,Step 17.a,RNO
Control feed flow to maintain NR level- BETWEEN 8% and 50% (42% and50% ADVERSE CTMT)
E-0,Step 17.b
Proceed to Step 18. E-0,Step 17.c
Verify Total AFW Flow - GREATERTHAN 530 gpm
E-0,Step 17.d
Section 4Page 42 of 61
i: SEC i iON 4
Lesson Title: ATWS with Faulted S/G
Revision: 0ID Number: 2K2 NRC-001
TaskAqqinnleer~rarIn-Frnnrmirtnn/A9-fivit Expected Action Standard
_ D II5 A SREX1;I ime *LILU.IVU.aLV IIIEtJE v s.. _ --
BOP
us
BOP
START pumps and Align valves asnecessary.
E-0,Step 17.d,RNO
IF AFW Flow GREATER THAN 530gpm can NOT be established,
THEN
Initiate monitoring of CSF StatusTrees and Go to FR-H.1, Response toLoss of Secondary Heat Sink.
Verify AFW Valve Alignment -PROPER EMERGENCY ALIGNMENT
E-0, Step 18
Align valves E-0,Step 18,RNO
RO Verify ECCS Valve Alignment -PROPER EMERGENCY ALIGNMENT
E-0, Step 19
Align valves E-0,Step 19,RNO
US Check Plant Status E-0, Step 20
BOOTHINST
NOTE When asked, REPORT that "allSLCRS doors indicate closed."
Verify SLCRS doors - CLOSED E-0,Step 20.a
Section 4Page 43 of 61
SECTION 4(
Lesson Title: ATWS with Faulted S/G
Revision: 0ID Number: 2K2 NRC-001Task
AssianT.;- If~lAIMif Ina-triiitnr Informntinn/Artivitv Expected Action StandardI IIIU - -- -
US
RO
RO
RO
RO
Request Security Close all SLCRSdoors.
Check CONTROL BUILDINGISOLATION annunciator (MB4D 3-6) -LIT
Check if CBI is required
* Ctmt pressure GREATER THAN18 psia
OR
* Control Building radiation monitorin alarm
OR
E-0,Step 20.a,RNO
E-0,Step 20.b
E-0,Step 20.b,RNO
RO
* Si manually actuated
IF CBI required,
THEN
Initiate CBI.
Section 4Page 44 of 61
SECTION 4
Lesson Title: ATWS with Faulted S/G
ID Number: 2K2 NRC-001 Revision: 0Task
AnnianTo; MnA IRA-lf In&4vctr ipre Infnrmntinn/Artivitv Expected Action StandardI meIIW ILJIPIIVIOII , u imLI -.... ... _..- _
US
RO
RO
BOP
BOP
IF CBI is NOT required,
THEN
Proceed to Step 21.
Verify ESF Group 2 CBI lights - LIT
Align HVAC components as necessaryfor minimum safety function.
Verify control building purge supplyfan and purge exhaust fan - NOTRUNNING
Perform the following:
E-0,Step 20.c
E-0,Step 20.c,RNO
E-0,Step 20.d
E-0,Step 20.d,RNO
* Stop purge supply fan.
* Stop purge exhaust fan.
* Locally Close instrument airisolations
* 31AS-V725 (CB 47' IRRstairwell)
* 31AS-V726 (CB 47' IRRstairwell)
Section 4Page 45 of 61
(SEC i ION 4
Lesson Title: ATWS with Faulted S/G
ID Number: 2K2 NRC-001 Revision: 0Task
AssianTima MAIn^Mnif Instructor Information/Activitv Expected Action StandardI We I11Uc ..... ........ _.._.. __-. ... - .--
* 31AS-V644 (CB 66' west wall)
* Locally Close instrument airisolation valve for 3HVC-AOD134
Control building air bank isolationvalves - OPEN (after 60 seconds)
OPEN valves
BOP
BOP
BOP
E-0,Step 20.e
E-0,Step 20.e,RNO
IF at least one air bank isolation valvecan NOT be opened,
THEN
Locally throttle Open at least onepair of air bank isolation bypassvalves to maintain 0.125 incheswater at Control Building APindicator on VP1.
* 3HVC*V750 and 3HVC*V751
* 3HVC*V758 and 3HVC*V759
BOP STOP kitchen exhaust fan E-0,Step 20.f
Section 4Page 46 of 61
f.SEC i iON 4
(
Lesson Title: ATWS with Faulted S/G
ID Number: 2K2 NRC-001 Revision: 0
TaskAssicnTi me InAlnM2if Instructnr Information/Activitv Expected Action StandardI 1111�
BOOTHINST
NOTE When called, WAIT 3 - 5 min, ThenREPORT "All Control Buildingpressure boundary doors are Closedand Dogged."
PEO Close and Dog (as applicable) ControlBuilding pressure boundary doors.
E-0,Step 20.g
RO Check RCS Temperature E-0, Step 21
Verify RCS cold leg WR temperature -BETWEEN 5500F and 5600 F
US Perform the applicable action:
E-0,Step 21.a
E-0,Step 21.a,RNO
US
* IF temperature is GREATERTHAN 550 0F AND 560 0F, THEN
1) Dump steam to the condenser,if available OR Dump steam toatmosphere.
2) Proceed to Step 22.
* IF the temperature is LESS THAN5500
THEN
Proceed to Step 21c.
Section 4Page 47 of 61
(l (SECTION 4
Lesson Title: ATWS with Faulted S/G
ID Number: 2K2 NRC-001 Revision: 0Task
AssicnTime InlAiMaif Instruictor Information/Activitv Expected Action Standard
US
BOP
BOP
BOP
Proceed to Step 22
Maintain total feed flow BETWEEN530 and 600 gpm until NR level isGREATER THAN 8% (42% ADVERSECTMT) in at least one SG
CLOSE SG atmospheric dump anddump bypass valves
Check the following valves - CLOSED
* MSIVs
* MSIV bypass valves
Perform the following:
1. Place both condenser steam dumpinterlock selector switches to OFF.
2. IF unexpected cooldowncontinues, THEN
E-0,Step 21.b
E-0,Step 21.c
E-0,Step 21.d
E-0,Step 21.e
US
BOP
BOP
E-0,Step 21.e,RNO
CLOSE the MSIVs and MSIVbypass valves.
RO Check PZR Valves E-0, Step 22
Section 4Page 48 of 61
(ISECTION 4
Lesson Title: ATWS with Faulted S/G
ID Number: 2K2 NRC-001 Revision: 0Task
AsifinT;^- nA 1M1fi Intrni.tnr Infnrmftinn/Aectivitv ExDected Action StandardI HIM MV-MI ldll 1 II> u-vA ss||s4, rw- *s... .. ______
Verify PORVs - CLOSED
RO
RO
RO
RO
RO
RO
RO
IF PZR pressure LESS THAN 2350psia, THEN CLOSE PORVs.
IF any PORV can NOT be closed,THEN CLOSE its block valve.
IF block valve can NOT be closed,THEN Initiate monitoring of CSFStatus Trees and Go to E-1, Loss ofReactor or Secondary Coolant.
Verify normal PZR spray valves -CLOSED
IF PZR pressure LESS THAN 2270psia THEN CLOSE valves.
IF valves can NOT be closed, THENSTOP RCPs 1 and 2
E-0,Step 22.a
E-0,Step 22.a,RNO
E-0,Step 22.b
E-0,Step22.b,RNO
Verify PZR safety valves - CLOSED E-0,Step 22.c
Section 4Page 49 of 61
(SEC i ION 4
(
Lesson Title: ATWS with Faulted S/G
Revision: 0ID Number: 2K2 NRC-001
TaskAQsinn Exoected Action StandardT: Ad IM A 1MIf
I ime IUtIjIVIdII I5IlLI1U%.LJUI I * . -ore
US IF PZR pressure decreasing in anuncontrolled manner, THEN initiatemonitoring of CSF Status Trees andGo to E-1, Loss of Reactor orSecondary Coolant
Check PORV block valves - OPEN
OPEN energized block valves.
To prevent damage to the RCPseal(s), seal injection flow should bemaintained to all RCPs.
E-0,Step 22.c,RNO
E-0,Step 22.d
E-0,Step 22.d,RNO
E-0,Step 23,CAUTION
CREW
RO Check If RCPs Should Be Stopped E-0, Step 23
Verify RCPs - ANY RUNNING
Proceed to step 24.
E-0,Step 23.a
E-0,Step 23.a,RNO.
RO Verify RCS pressure - LESS THAN1500 psia (1800 psia ADVERSECTMT)
EOP 35 E-0, Step 23.b
Section 4Page 50 of 61
A
SEC; ION 4(.
Lesson Title: ATWS with Faulted S/G
ID Number: 2K2 NRC-001 Revision: 0
TaskArminnT i_ A nrA IRU19 In~rss^t.r nfnrmftfiron1Adrfixvfx Exnected Action Standard
I ime I~iUIMMai IEIZ1U ULJE IEI'I IE-II*- - - -- --
US
RO
US
RO
Proceed to Step 24
Verify charging or Si pumps - ATLEAST ONE RUNNING
Proceed to Step 24
STOP all RCPs
E-0,Step 23.b,RNO
E-0,Step 23.c
E-0,Step 23.cRNO
E-0,Step 23.d
BOP/RO Check If SG Secondary BoundariesAre Intact
Check pressure in all SGs
E-0, Step 24
E-0,Step 24.a
* NO SG PRESSUREDECREASING IN ANUNCONTROLLED MANNER
* NO SG COMPLETELYDEPRESSURIZED
US Initiate monitoring of CSF StatusTrees and Go to E-2, Faulted SteamGenerator Isolation.
E-0,Step 24.aRNO
Section 4Page 51 of 61
(SECTION 4
(
Lesson Title: ATWS with Faulted S/G
Revision: 0ID Number: 2K2 NRC-001
TaskAQqinnl~etffrnr nform-wnfirn1A&-*ivit Expected Action Standard_ _ I1.A IRA 15
I rne W/AltIU'.,L'E - --.. -5-
E-2, Faulted Steam GeneratorIsolation, Rev. 9
US At least one SG must be maintainedavailable for RCS cooldown.
E-2 CAUTION
US
US
Any faulted SG or secondary breakshould remain isolated duringsubsequent recovery actions unlessneeded for RCS cooldown or sampling isrequired.
If RWST level decreases to LESS THAN520,000 gal, Go to ES-1.3, Transfer toCold Leg Recirculation, to align theECCS system.
BOP Check Main Steam Isolation And
US Bypass Valves - CLOSED
US Check at least one SG boundaryintact.
RO/ BOP Check pressures in all SGs - AT LEASTONE STABLE OR INCREASING
US Identify Faulted SGS
RO/ BOP Check pressure in all SGs
ANY SG PRESS DECREASING IN ANUNCONTROLLED MANNER
OR
E-2, Step 1
E-2, step 2
E-2, step 2.a
E-2, Step 3
E-2, Step 3.a
Section 4Page 52 of 61
(SECTION 4
(
Lesson Title: ATWS with Faulted S/G
ID Number: 2K2 NRC-001
Timem InAiMnif
Revision: 0
TaskAssicnInstnrutor Information/Activitv Expected Action Standard
2, Step 4s - vrzl .- .. I
[Critical Task] Isolate the faultedS/G before transition out of E-2
RO/BOP
RO/BOP
ANY SG COMPLETELYDEPRESSURIZED
If the TD AFW pump is the only availablesource of feed flow, a steam supply tothe TD AFW pump must be maintainedfrom at least one steam generator
Isolate each faulted SG.
* Isolate main feed line
* TRIP TD FW pumps
* Place MD FW pump in PULL-TO-LOCK
* Isolate AFW flow path
* CLOSE steam supply isolation valveto TD AFW pump
* Verify SG atmospheric dump andbypass valves - CLOSED
* Verify SG blowdown isolation valve -CLOSED
* Verify SG blowdown sampleisolation valve - CLOSED
* Verify SG chemical feed isolationvalve - CLOSED
E-2, Step 4CAUTION
E-2, step 4
Section 4Page 53 of 61
(
SEC;i ION 4
Lesson Title: ATWS with Faulted S/G
Revision: 0ID Number: 2K2 NRC-001Task
AssianTima^ InAIMnif Incfnier-Mr Infnrmatinn/Activitv Expected Action StandardI * * I I1U *9 f u t . .a . . . .#. -
* Using table, Verify main steam linedrains upstream of MSIVs and TDAFW pump - CLOSED
SG A SG B SG C SG D
3DTM*AOV29A 3DTM*AOV29B 3DTM*AOV29C 3DTM*AOV29D
3DTM*AOV61A 3DTM*AOV61B 3DTM*AOV61C 3DTM*AOV61D
3DTM*AOV63A 3DTM*AOV63B 3DTM*AOV63D
3DTM*AOV64A 3DTM*AOV64B 3DTM*AOV64D
RO/ BOP/US
Close valve(s) or isolation valve(s).
IF flow path(s) can NOT be isolated,THEN Dispatch an operator to locallyClose valve(s) using Attachment A forguidance
E-2 Step 4RNO
NOTE: IF crew performs S/G isolationin E-2 TERMINATE the exam aftercompletion of step 4 of E-2 AND FR-Z.1 (if conditions require)
Section 4Page 54 of 61
!SEC;, iON 4
(.
Lesson Title: ATWS with Faulted S/G
Revision: 0ID Number: 2K2 NRC-001
TaskAqqinnInerrtgr nfnrrmntirn1A#-tiAit Exoected Action Standard_ _ InrA IRXl-1
I Ime IlUA/Wl4l IIlbI UY.LIW IIIIEaJI * ' - -
FR-Z.1, Response to CTMT HighPressure, Rev. 11
NOTE: If the crew anticipates highCTMT pressure they may not bedirected to perform FR-Z.1
US/RO Check if CDA Required
RO Check CTMT pressure GREATERTHAN 23 psia
US
RO
US
RO
RO
RO
Verify Annunciator "CTMT DEPRESACTUATION" (MB2B 5-5)-LIT
Verify CIB
Check ESF Group 2 columns 2Through 10 - LIT
Verify CIB
Check RPCCW Ctmt supply and returnheader isolation valves - CLOSED
Check RPCCW pumps - STOPPED
STOP all RCPs
If ECA-1.1, Loss of EmergencyCoolant Recirculation, is in progress,Ctmt spray should be operated asdirected in ECA-1.1 rather than steps3, 4, and 7
FR-Z.1,Step 1
FR-Z.1,Step 1.a
FR-Z.1,Step 1.b
FR-Z.1,Step 2
FR-Z.1,Step 2.a
FR-Z.1,Step 3
FR-Z.1,Step 3.a
FR-Z.1,Step 3.b
FR-Z.1,Step 3.c
FR-Z.1,Step 4CAUTION
Section 4Page 55 of 61
(SEC I-ION 4
(
Lesson Title: ATWS with Faulted
ID Number: 2K2 NRC-001
Time IDA/Malf
TaskAssinn1--4-tn^r#r I nferrMntirsn/Ae-fivifV
111Q ,L Mu L J ,I,,v, v *
US
RO
RO
RO[Critical Task]
Expected Action
Verify Quench Spray SystemOperation
Check annunciator RWST EMPTYQSS PP OFF (69,331 gal)(MB2A 5-2)not lit)
Verify quench spray pumps -RUNNING
START pumps.
Verify quench spray pump dischargevalves (3QSS*MOV34A and3QSS*MOV34B) - OPEN
OPEN valves.
STOP All Main Circulating WaterPumps
Check Containment Ventilation
* Verify CAR fans - STOPPED
* Verify CRDM fans - STOPPED
Revision: 0
Standard
FR-Z.1,Step 4
FR-Z.1,Step 4.a
FR-Z. 1,Step 4.b
FR-Z.1,Step4.b,RNO
FR-Z.1,Step 4.c
FR-Z. 1,Step 4.c,RNO
FR-Z.1,Step 5
FR-Z.1,Step 6
RO
[Critical Task] RO
BOP
BOP
Section 4Page 56 of 61
EVALUATION GUIDE
Title: ATWS with Faulted S/G
ID Number: 2K2 NRC-001 Revision: 0Task
Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard
US Verify Recirculation Spray System FR-Z.1,Operation Step 7
RO Check annunciator CTMT RECIRC FR-Z.1,PUMP AUTO START SIGNAL on Step 7.a(MB2B 1-8) - LIT
US Proceed to step 9 and, WHEN 11 FR-Z.1,minutes have elapsed since CDA Step 7.a,initiation, THEN Perform steps 7b RNOthrough 7e.
RO Check recirculation spray pumps - FR-Z.1,RUNNING Step 7.b
RO Proceed to step 7.d FR-Z.1,Step 7.bRNO
RO Proceed to step 7.f FR-Z.1,Step 7.c
RO Check Ctmt WR sump level is FR-Z.1,GREATER THAN 1.5 feet Step7.d
RO START recirculation spray pumps FR-Z. 1,Step 7.e
RO Check recirculation spray pump suction FR-Z.1,isolation valves - OPEN Step 7.f
RO Verify recirculation spray pump FR-Z.1,discharge isolation valves - OPEN Step 7.g
Section 4Page 57 of 61
(EVALUNI iON GUIDE
(
Title:
ID Number:
Time
ATWS with Faulted S/G
2K2 NRC-001
IDA/Malf InstrTask
uctor Information/Activity-
Assign Expected Actions
RO Check recirculation spray - FLOWINDICATED IN AT LEAST ONE TRAIN
RO Proceed to step 9
RO Verify ESF Group 4 Lights - LIT
CREW Operate components as necessary forminimum safety function.
US/ BOP Verify Main Steam Line Isolation
* Check MSIVs and MSIV bypassvalves - CLOSED
* Check ESF Status Group 3 lights -LIT
BOP Initiate MSI.
Revision: 0
Standard
FR-Z. 1,Step 7.h
FR-Z.1,Step 7.1
FR-Z.1,Step 9
FR-Z.1,Step 9,RNO
FR-Z.1,Step 10
FR-Z.1,Step 10,RNO
FR-Z. 1,Step 1 1
BOP/RO Verify Main Feedwater Isolation
* Verify MD AND TD FW pumps -TRIPPED
* Verify FW isolation trip valves -CLOSED
Section 4Page 58 of 61
EVALUA I iON GUIDE
/
Title:
ID Number:
Time
ATWS with Faulted S/G
2K2 NRC-001
IDA/Malf InstrTask
Assian
Revision: 0
Standardi inftor 1nfnrmnfinn/Act.ivitv,~L -s-s, ,,,v, cvs.,\k .}.._U
US
US
US
BOP/RO
US
Expected Actions
* Verify SG feed regulating valves -CLOSED
* Verify SG feed regulating bypassvalves - CLOSED
At least one SG must be maintainedavailable for RCS cooldown.
If all SGs are faulted, at least 100 gpmfeed flow should be maintained to eachSG.
Check If Auxiliary Feedwater FlowShould Continue To All SGs
Check pressure in all SGs
* NO SG PRESSUREDECREASING IN ANUNCONTROLLED MANNER
* NO SG COMPLETELYDEPRESSURIZED
Go to Procedure and Step In Effect
FR-Z.1,Step 12,CAUTION
FR-Z.1,Step 12,CAUTION
FR-Z.1,Step 12
FR-Z.1,Step 12.a
FR-Z.1,Step 13
TERMINATE UPON Completion of FR-Z.1 AND Isolation of SIG (either in E-0, E-2, or FR-Z.1).
Section 4Page 59 of 61
SECTION 4
ID Number: 2K2 NRC-001 Revision: 0
EVALUATION GUIDE
I. SUMMARY
The following Critical Tasks are covered in this exam:
TASK DESCRIPTION TASK # K/A >I= 3.0 BASIS FOR SELECTION
Establish flow from at leastone Si pump beforecompletion of the check ofE-0, steps 1-14 in FR-S.1.
Manually actuate MSI orclose MSIV's beforecompletion of FR-S.1 step13.
Isolate the faulted S/Gbefore transition out of E-2
E-0-J 007 EA2.024.3/4.6
E-0-P 040 AA2.044.5/4.7
E-2-A 040 AA1.044.34.3
Failure to manually start atleast one intermediate -head ECCS pump underthe postulated conditionsconstitutes "mis-operationor incorrect crewperformance which leads todegraded ECCS capacity."
Failure to close the MSIVschallenges the CSFsbeyond those irreparablyintroduced by thepostulated conditions andconstitutes a"demonstrated inability bythe crew to recognize afailure of the auto actuationof an ESF system."
Failure to isolate a faultedSG that can be isolatedcauses challenges to CSFsbeyond those irreparablyintroduced by thepostulated conditions.
Note: ri Used to designate critical tasks. Should alsobe incorporated into column 3 or 4 ofInstructor Guide.
Section 4Page 60 of 61
SECTION 4
Title: ATWS with Faulted SIG
ID Number: 2K2 NRC-001 Revision: 0EVALUATION GUIDE
Section 4Page 61 of 61
SECTION 5
SCENARIO INITIAL CONDITIONS
ID Number: 2K2 NRC-001 Revision: 0
Reactor Power: 50%, steady state Xenon
Operating History: 450 days on line
RCS Boron: 300 ppm
Core Burnup: 18,600 MWD/MTU
Condensate Demins:
Evolutions in Progress:
Major Equipment OOS:
5 demins in service
NONE
"A" PORV is inoperable due to an electrical short in thecontrol circuitry. It has been out of service for 8 hours.Electrical maintenance estimates that the valve will bereturned to service within 24 hours.
The following Tech Specs are applicable:Tech Spec 3.4.4, action b3TRM 7.4.1 action a.1 and a.3 for both the A PORV andthe block valve 3RCS*MV8000A
Crew Instructions:
The unit downpowered in response to a severe weather threat. The next shift will beginthe power increase. Maintain the plant at 50% power. Intake conditions are now Green.
The crew is directed to Pump the Containment Drains Transfer Tank in accordance withOP 3335A, Reactor Plant Gaseous Drains, section 4.4.
Plant/Simulator Differences:
* Real Time and Simulator Rad Monitor historical data not valid prior to the beginning ofthis exercise.
* Auto-log terminals need to be refreshed after entry is made.
* If not using the speed dial option on the phone system, the operator must dial either #3333or #3334 to reach the person/department they desire.
* The following PPC programs do not function on the simulator:
* Samarium Follow* Xenon Follow* Sequence of Events
Section 7Page 1 of 1
SECTION 6
VALIDATION CHECKLIST
ATWS with Faulted S/GTitle:
ID Number: 2K2 NRC-001 Revision: 0
Remote functions:
All remote functions contained in the guide are certified.
Malfunctions:
All malfunctions contained in the guide are certified.
Initial Conditions:
The initial condition(s) contained in the guide are certified or have been developed from certified
IC's in accordance with NSEM-4.02.
Simulator Operating Limits:
The simulator guide has been evaluated for operating limits and/or anomalous response.
Test Run:
The scenario contained in the guide has been test run and validated (validation sheet
completed, next page)on the simulator. Simulator response is reasonable and as expected.
Examination Scenario Review
The dynamic examination review checklist is complete. (This is not required unless the exam
will be used as an Annual Exam, then NUREG 1021 requirements apply.)
11/20/2001
Technical Reviewer Date
Section 7Page 1 of 1
SECTION 7
REFERENCE AND TASK TRACKING
ATWS with Faulted SIGTitle:
ID Number: 2K2 NRC-001 Revision: 0
I. References:
OP3335A
ARP MB4B, 3-4B
AOP*3575
AOP*3564
EOP*E-0
EOP*E-2
EOP*FR-S. 1
EOP*ERGEXE
EOP* Step DOC
EOP*ERGHP
FAP06*01
NUREG*1021 rev 8
Reactor Plant Gaseous Drains
RCP B Cooler Supply Pressure Low
Rapid Downpower
Loss of One Protective System Channel
Reactor Trip or Safety Injection
Faulted Steam Generator Isolation
Response to Nuclear Power Generation I ATWS
Westinghouse Owners Group Executive Document
MP3 step deviation Document
Westinghouse Owners Group Background Document
Event Assessment, Classification and Reportability
Examiners Standards
I
Section 7Page 1 of 1
Initial Dynamic Simulator Scenario
NUREG-1021, Appendix D, Attachment 1
ATWS with Faulted S/GTitle:
ID Number: 2K2 NRC-001 Revision: 0
I. Summary:
Facility: Millstone 3 PWR:_ Scenario No: 2K2NRC-001 Op-Test No: 2K2
Examiners:_ Operators:
Initial Conditions: IC-22; 50% power, end of life
The "A" PORV is out of service due to an electrical short in the control circuitry
Event Malf. Event Event DescriptionNo: No. Type *
I N(US) Pump the Containment Drains Transfer Tank
2 CC03B C(RO) Partial Loss of RCP B Cooling water Supply
2a R(ALL) Rapid Downpower to Remove RCP
3 ED08C C(ALL) Loss of Instrument Bus VIAC-3
4 FW08A I(BOP) A S/G Feed Reg Valve Failure5 I/Os 32N M(ALL) AT\NS; 32N Fails to De-energize
RP09A/BRP10A/B
6 CV18 C(RO) Charging Flow Control Failure
7 RP11 E C(RO) SIH Fails to Align on SIS
8 MS01 D M(ALL) Main Steam Line D Rupture Inside CTMT
9 RP08 I(US/ MSI Fails to Auto ActuateBOP)
*( N ) ormal ( R ) eactivity ( I ) nstrument ( C ) omponent ( M ) ajor
Section 7Page 1 of 1
SECTION 8MILLSTONE UNIT 3
SIMULATOR SCENARIO ATTRIBUTES CHECKLISTFORM ES-301-4
Exam Title: ATWS with Faulted S/G
ID Number: 2K2 NRC-001 Revision: 0
Assessor: Steve Jackson
QUALITATIVE ATTRIBUTES
_Y_1. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of
service, but it does not cue the crew into expected events.
_Y_2. The scenario consists mostly of related events.
_Y_3. Each event description consists of:
- the point in the scenario when it is to be initiated- the malfunctions(s) that are entered to initiate the event
- the symptoms/cues that will be visible to the crew- the expected operator actions (by shift position)- the event termination point (if applicable)
_Y_4. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario
without a credible preceding incident such as a seismic event.
_Y_5. The events are valid with regard to physics and thermodynamics.
_Y_6. Sequencing/timing of events is reasonable, and allows for the examination team to obtain
complete evaluation results commensurate with the scenario objectives.
_N/A_7. If time compression techniques are used, scenario summary clearly so indicates. Operators have
sufficient time to carry out expected activities without undue time constraints. Cues are given.
_Y_8. The simulator modeling is not altered.
_Y__9. The scenario has been validated. Any open simulator performance deficiencies have been
evaluated to ensure functional fidelity is maintained while running the scenario.
Y__10. Every operator will be evaluated using at least one new or significantly modified scenario. All other
scenarios have been altered IAW Section D.4 of ES301
Y_11. All individual operator competencies can be evaluated, as verified using form ES-301-6.
Y_12. Each operator will be significantly involved in the minimum number of transients and events
specified on Form ES-301-5. (Form submitted with simulator scenarios).
Y__13. Level of difficulty is appropriate to support licensing decisions for each crew position.
Section 8Page 1 of 2
SECTION 8MILLSTONE UNIT 3
SIMULATOR SCENARIO ATTRIBUTES CHECKLISTFORM ES-301-4
Lesson Title: ATWS
ID Number: 2K2 NRC-001 Revision: 0
Note: Following criteria list scenario traits that are numerical (QUANTITATIVE) in nature.
01. Total Malfunctions (TM) - Include EM's- 5 to 8 requiredLoss of RCP B Cooling water Supply, Charging Flow Control Failure, MSI Fails to
Auto Actuate, Main Steam Line D Rupture Inside CTMT, Loss of Instrument Bus VIAC-3, A
SIG Feed Reg Valve Failure, SIH Fails to Align on SIS
02. Malf s after EOP entry (EM's)- 1 to 2 required
SIH Fails to Align on SIS, MSI Fails to Auto Actuate,
03. Abnormal Events (AE)-2 to 4 required
Loss of RCP B Cooling water Supply, Loss of Instrument Bus VIAC-3, A S/G Feed Reg
Valve Failure
04. Major Transients (MT)-1 to 2 required
ATWS/32N Fails to De-energize, Main Steam Line D Rupture Inside CTMT
05. EOP's (EU) entered/requiring substantive actions 1 to 2 required
E-O, E-2
06. EOP Contingencies requiring substantive actions [ECAs/FRs](EC) 0 to2 required
FR-S.1, FR-Z.1
07. Critical Task (CT) - 2 to 3 required
E-0-J: Establish flow from at least one Si pump before completion of thecheck of E-0, steps 1-14 in FR-S. 1.
E-0-P: Manually actuate MSI or close MSIV's before completion of FR-S. 1step 10.
E-2-A: Isolate the faulted S/G before transition out of E-2
08. Approximate Scenario Run Time: 45 to 60 min. (One scenario mayapproach 90 minutes)
Total: 7
Total: 2
Total: 3
Total: 2
Total: 2
Total: 2
Total: 3
Total: 70 min
09. EOP run time: Total: 40 min
10. Technical Specifications are exercised during the scenario. (Y/N)_Y_
NOTES: Reactivity Manipulation: Rapid Downpower to Remove RCP
Section 8Page 2 of 2
2K2 LOUTEXAM MATERIALS
SIMULATOR EXAM
SIM-002
EXAMINATION
08/12/02 - 08/15102
MILLSTONE POWER STATION ANRC SIMULATOR EXAM GUIDE APPROVAL SHEET
Exam Title:
Revision:
SGTR WITHOUT PZR PRESSURE CONTROL
0
ID Number: 2K2 NRC-002
This document is the property of Millstone Power Station, which controls itsdistribution. Further transfer, copying, and modification of this document are
strictly prohibited without the written consent of Millstone Power Station.
e I4SK S.1'�z�- 4 1--610'04"s " , 'I.� . VqQ-."
OR -PII'l-fiWiP ! EF'."'g 0 iI-wp� I
SECTION 2
SIMULATOR EXAM GUIDE
TABLE OF CONTENTS
SECTIONS LISTED IN ORDER
1. Cover Page
2. Table of Contents
3. Exam Overview
4. Evaluation Guide
5. Scenario Initial Conditions Sheet
6. Scenario Validation Checklists
7. Reference and Task Tracking
8. Scenario Attributes Checklist
Attachments
- NUTIMS Module Report
~TO ACe. .R ........... !
SECTION 3
EXAM OVERVIEW
Title: SGTR WITHOUT PZR PRESSURE CONTROL
ID Number: 2K2 NRC-002 Revision: 0
Exam Brief:
1. The plant is at 100% power, EOL steady state operations with all control systems in
automatic. The "A" PORV is out of service due to an electrical short in the control circuitry.
The crew is initially directed to reduce CTMT pressure to 13.80 psia using OP 3313E,
Containment Vacuum, section 4.2. After the evolution has commenced, the Digital Rod
Position Indication system will experience a Data A failure on rod D12. AOP 3552,
Malfunction of the Rod Drive System with Attachment C will direct the crew's actions. Tech
Specs should be reviewed for this malfunction.After Tech Specs have been reviewed, a tube leak will occur on the "C" S/G. A small
increase in charging flow and radiation alarms on ARC21, Air Ejector Rad Monitor, and N-16
alarms will indicate the problem to the crew. The crew may use the guidance in AOP 3573,
Radiation Monitor Response, or may go directly to AOP 3555, Reactor Coolant System Leak.
AOP 3555 and the N-16 ARP will direct the crew to AOP 3576, Steam Generator Tube Leak.
Conditions are present to require a power reduction to be in MODE 3 within 6 hours (AOP
3576 step 9.j).When the power reduction is underway a Rod Bank CB-D Continuous Rod Insertion
will occur. The crew should place the control rod bank SEL switch in MAN and when this
does not stop rod motion, trip the reactor and go to E-0, Reactor Trip or Safety Injection. At
the time of the reactor trip the SIG leak will worsen into a SGTR [Critical Task -2: Isolate
Steam and Isolate Feed] and a loss of Offsite power will occur. The EDGs will both start
and provide power to the emergency buses but offsite power will not return during the
scenario. The C Service Water pump will trip at the reactor trip and the A SWP will not
automatically start. Manual action will be required to start the A Service Water pump [Critical
Task]. The crew should proceed through E-0 and transition to E-3, Steam Generator Tube
Rupture. At step 3.i of E-3 the "C" MSIV will not close and the RNO will be implemented.
Time compression techniques are used to complete Attachment A referenced in the step 3.1.
At step 18 of E-3 the crew will be unable to depressurize the RCS due to one PORV out of
service (initial condition), one PORV failing to open, and auxiliary spray unavailable due to the
CTMT Instrument Header isolation valve, 31AS*MV72, failing to open. This will require the
crew to transition to ECA-3.3, SGTR Without Pressure Control.The scenario will end when the crew has completed step 8 of ECA-3.3.
2. The SM should classify this event as a Alert - Charlie One due to Loss of RCS Barrier
(RCB4).
3. Plant/Simulator differences that may affect the scenario are: NONE
4. Duration of Exam: 60 minutes
SECTION 4
EVALUATION GUIDE
SGTR WITHOUT PZR PRESSURE CONTROLTitle:
ID Number: 2K2 NRC-002 Revision: 0
All Control Room Conduct, Operations and Communications shall be in accordance withMP-14-MMM.
"Review the Simulator Operating Limits(design limits of plant) and the SimulatorModeling Limitations and Anomalous Response List prior to performing this examscenario on the simulator. The evaluators should be aware if any of these limitationsmay be exceeded." (NSEM 6.02)
Section 4Page 1 of 71
SIMULATOR PROBLEMS DURING EXAMS
It is the responsibility of the Instructors in the simulator to insure that exam interruptions have a
minimum negative impact on the Crew and the examinations we provide.
Be aware that at all times the Operators should treat the simulator as if it were the plant and
you too should treat it as much like the plant as possible when they are in the simulator.
As soon as the Instructors are aware of a simulator problem that will adversely affect the exam
in progress (computer fault, etc.) the Instructor should:
1. Place the simulator in FREEZE if possible.
2. Announce to the Crew that there is a simulator problem.
3. Request that the Crew leave the simulator control room. (The Crew should leave
the simulator for problems which involve major switch alignments).
4. Deal with the problem (reboot, call STSB, etc.)
5. After the Instructors believe the simulator is restored to service, the Crew should
be told how the exam will continue. If it is possible and felt to be acceptable to
the evaluators, the examination can begin where it left off with an update on
plant parameters and each Crew member is prepared to restart. If theexamination will not begin where it left off, the crew should be told how andwhere the exam will begin again.
6. Once the Crew has been told how and where the exam will begin, have the crewconduct a brief so that the Instructor and evaluators can insure that the crew hasall the necessary information to continue with the scenario.
7. Once all Crew members, Instructors and evaluators are satisfied that they havethe necessary information to continue the scenario, place the simulator in RUN
and announce to the Crew that you have continued the evaluation session.
Section 4Page 2 of 71
( (#(SECTION 4
Title: SGTR WITHOUT PZR PRESSURE CONTROL
ID Number: 2K2 NRC-002 Revision: 0
TaskTime IDA/Malf Instructor Information/Activity Assign Expected Action Standard
Simulator Setup Instructions:
1. HANG Exam Placards on the simulator doors.
2. START the Sun Workstation.
a. IF the Sun Workstation is running THEN go to SIM ACTIVE.
3. PLACE Recorder Power to ON.
4. VERIFY that the current approved training load is loaded.
5. REMOVE the step counter OVERRIDE and allow the counters to step out during the IC reset.
6. RESET to IC 90: TEMP IC 2K2NRC-LOUT-002 (based on IC 21)
7. ADJUST the various pot settings to the valued specified by the chart in the simulator booth or Notepad for the selected IC.
8. PLACE Simulator to RUN.
9. ADJUST MWt using Turbine Load Set to 3411, (+)O, (-)3 IF using 100% power IC.
10. RESET the Plant Calorimetric at the Instructor Station PPC by Pressing "SHIFT LEFT" and "F6" simultaneously.
11. ENSURE Simulator fidelity items cleared.
a. CHECK the STEP COUNTERS at correct position for plant conditions.
b. PLACE 7 tiles under the DEMINS IN SERVICE lamacord label on MB6.
c. PLACE the Main Turbine on the LOAD LIMITER and ENSURE Standby Load Set MATCHED if conditions require.
d. PLACE the Westronic (5) and Gammametrics (2) recorders in active/run by depressing up or down arrow for each.
e. CLEAR DCS alarms on MB7 and BOP console.
Section 4Page 3 of 71
,X
SECI iUN 4
Title: SGTR WITHOUT PZR PRESSURE CONTROL
ID Number: 2K2 NRC-002 Revision: 0
Task
Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard
f. VERIFY annunciator, "COMPUTER FAILURE" (MB4C, 1-11), is NOT LIT.
g. ENSURE NSSS Picture 1, MODES 1, 2, 3, 4; Burnup and Cb match lesson plan AND Cb sample date < 3 days old.
1) See laminated directions on clipboard in Sim booth.
12. RESET Computer Terminals to At Power displays if 100% power IC.
a. MB2, (AY6), CVCS Data Trend, 1 minute update, CHS-F132 (40-120), CHS-L112 (40-80), CHS-F121 (40-80), RCS-L461 (40-80)
b. MB4, (AY1), At Power Data Trend, 15 second update, CVQRPI, (3391-3428), CVQRPHRUN (3409-3413), CVQRP (3409-3413), RCL-
T412*, (585-588)
c. MB4, (AY4), NSSS Picture 1, MODES 1, 2, 3, 4
d. BOP Console (AY5A), BOP Picture 26, Circ Water
e. STA Console, (AY3), NSSS Picture 15, RCP Seals
13. RESET Rad Monitor Screen to Status Grid.
14. OVERRIDE the annunciators that will be lit longterm in the CR, (as listed in the "Lit CRP Annunciators" section of the MP3 daily Status Report
hanging near instructor booth door).
15. IF placing equipment OOS, THEN perform the necessary switch manipulations and hang appropriate tags, as required, listed under
"Equipment OOS."
16. LOCK the Simulator Room front door.
17. HANG a Caution Tag on 3RCS*MV8000A stating, "Caution Tag 3RCS*MV8000A Closed and de-energized IAW Tech Spec 3.4.4. action b"
18. HANG DRPI Console picture/diagram (A+B switch position) on Main Board Door directly behind MB4.
Section 4Page 4 of 71
fSECTiUN 4
Title:
ID Number:
Time
SGTR WITHOUT PZR PRESSURE CONTROL
2K2 NRC-002
IDA/Malf Instructor Information/Actii
Revision: 0
TaskAccinnliti, Exnected Action Standard
- -
Section 4Page 5 of 71
(SECTION 4
SGTR WITHOUT PZR PRESSURE CONTROL
(
Title:
ID Number: 2K2 NRC-002 Revision: 0
TaskAssianTime InA/Malf Instructor Information/Activitv Expected Action Standard
-1
PLACE THE FOLLOWING EQUIPMENT OOS: STANDARD 2K2NRC EXAM EQUIPMENT
Initial Malfunctions
1/01/01/01/01/01/0
(RC)(RC)(RC)(RC)(RC)(RC)
3RCS*PCV455A3RCS*PCV455A3RCS*PCV455A3RCS*PCV4563RCS*MV80003RCS*MV8000
A PORVA PORVA PORVB PORVA PORV Block ValveA PORV Block Valve
OPEN - FALSEGREEN - FALSERED- FALSEOPEN - FALSEGREEN - FALSERED- FALSE
MALF
MALF
SG01C
ED01
Steam Generator "C" Tube Rupture
Loss of Offsite Power
50% 30 second ramp BT1
BT1
I/O (IA) 31AS*MOV72 IAS CTMT Isolation OPEN - FALSE BT1
MALF
MALFMALF
MS12C
SW01CSW02A
MSIV "C" Stuck Open
Service Water Pump C TripsService Water Pump A Fails to Auto Start
BT1
Section 4Page 6 of 71
SECTION 4
Title: SGTR WITHOUT PZR PRESSURE CONTROL
ID Number: 2K2 NRC-002
(.
Revision: 0
TaskAssianTima IMAIM2If Instructor Information/Activitv Expected Action Standard
Event Malfunctions
MALF
MALF
MALF
RD1 0-59
SG03C
RD021 (eye)
Control Rod Position Failure Data A - Rod D12
Steam Generator "C" Tube Leak 100% (46 gpm)
Rod Bank CB-D Continuous Rod Insertion
60 second ramp
RSCU 1
RSCU 2
RSCU 3
Lead Examiner: Refer to the "Briefing Script for the Operational Exam" and brief the crew.
Section 4Page 7 of 71
(SECTION 4
SGTR WITHOUT PZR PRESSURE CONTROLTitle:
ID Number: 2K2 NRC-002 Revision: 0
TaskAssiqnTime IDA/Malf Instructor Information/Activity Expected Action Standard
T+1 EVENT 1: Reduce CTMT Pressure
OP3313E CTMT Vacuum, Rev. 8
US
US
RO
Do not reduce containment pressure below13.75 psia if a CTMT entry is anticipated
One CTMT vacuum pump is operatedperiodically to maintain 3LMS*PI24A and3LMS*PI24B containment pressure 13.7 to13.9 psia, (MB2)
IF using 3CVS-PlA, containment vacuumpump A, PERFORM the following:
OP331 3EStep 4.2.1CAUTION
OP331 3EStep 4.2.1NOTE
OP331 3EStep 4.2.1
RO
RO
RO
OPEN 3CVS*CTV20A, "CTMT VAC PP"(MB1)
OPEN 3CVS*CTV21A, "CTMT VAC PP"(MB1)
START 3CVS*P1A, "CTMT VAC PP'S""1A" (MB2)
OP331 3EStep 4.2.1.a
OP331 3EStep 4.2.1.b
OP331 3EStep 4.2.1.c
T= normalevolutioncommenced
MALFRD1 0-59
EVENT 2: Control Rod PositionFailure Data A - Rod D12
RO
Section 4Page 8 of 71
(SECT iON 4
Title: SGTR WITHOUT PZR PRESSURE CONTROL
ID Number: 2K2 NRC-002
Time IDA/Malf
RSCU #1
.
Instructor Information/Activity
AOP 3552 Rev. 3MALFUNCTION OF THE RODDRIVE SYSTEM
TaskAssign
CREW
RO
RO
CREW
US
US
US
US
RO
Expected Action
Stabilize Plant Conditions
Place control rod bank SEL switch in MAN
Verify - NO RODS MOVING
Stop any power increase or decreaseevolutions in progress.
Verify Tavg - Tref deviation - LESS THAN
OR EQUAL TO 1.50F
Verify TURB LOAD REJECTION ARM C-7(MB4D 6-6) annunciator - NOT LIT
Borate or Dilute as necessary to maintainTavg within 1.50F of Tref
Check No Rod Dropped
Verify RPI URGENT FAILURE (MB4C 4-10) annunciator - NOT LIT
Check rod bottom lights - NONE LIT
Revision: 0
Standard
AOP 3552Step 1
AOP 3552Step 1.a
AOP 3552Step 1.b
AOP 3552Step 1.c
AOP 3552Step 1.d
AOP 3552Step 1.e
AOP 3552Step 1.f
AOP 3552Step 2
AOP 3552Step 2.a
AOP 3552Step 2.b
Section 4Page 9 of 71
I.SECTION 4
Title: SGTR WITHOUT PZR PRESSURE CONTROL
(
ID Number: 2K2 NRC-002 Revision: 0
TaskAssianTimu IMAIMnif Instrumtnr Infnrmation/Activitv ExDected Action Standard9 llE VIll>l | .-. .... __.._.. .-- .. _., __,___ _
us Check No Rod Position IndicationMalfunctions
AOP 3552Step 3
Verify DRPI power available
* Any DRPI display light lit
Verify status of following annunciators:
AOP 3552Step 3.a
AOP 3552Step 3.b
NOTE: Annunciator IS LIT RPI NON URGENT FAILURE(MB4C 3-10) annunciator - NOTLIT
* RPI URGENT FAILURE (MB4C 4-10) annunciator - NOT LIT
Determine rod position indicationmalfunction using Attachment C.
NOTE: US will most likelytransition to the Attachment at thisstep
US AOP 3552Step 3, RNO
Verify status of DRPI display alarms: AOP 3552Step 3.c
* URGENT ALARM - NOTFLASHING
NOTE: DATA A IS Flashing DATA A FAILURE - NOTFLASHING
Section 4Page 10 of 71
SECTION 4
Title: SGTR WITHOUT PZR PRESSURE CONTROL
I
Revision: 0ID Number: 2K2 NRC-002
TaskAssianTime InAiM2nIf Instrutiror Infnrmation/Activitv Expected Action Standard
I 11111U ---. - -- j
* DATA B FAILURE - NOTFLASHING
* Rod GW- NONE FLASHING
* CENTRAL CONTROL FAILURElights - NONE LIT
Determine rod position indicationmalfunction using Attachment C.
Check DRPI Power Supply
US AOP 3552Step 3, RNO
AOP 3552, ATTACHMENT C
RO
US
RO
Verify DRPI display lights - NONE LIT
AOP 3552 AttC Step 1
AOP 3552 AttC Step 1.a
AOP 3552 AttC Step 1.a,RNO
Proceed to Step 2.
A DRPI URGENT ALARM indicates one ofthe following:
AOP 3552Attachment CStep 2, Note
* Error in both data A AND data Bfrom detector/encoder cards.
* Codes from data A and data Bdiffer by GREATER THAN 1 bit
Section 4Page 11 of 71
l'I (
SECTiuN 4
Title: SGTR WITHOUT PZR PRESSURE CONTROL
Revision: 0ID Number: 2K2 NRC-002
TaskAssianTr.," IlAiMinIf Inctriu-tor Infnrmation/Activitv Expected Action Standard
I11111 vIll~ Lf.| ...... i....#.. ,.__,,_,
* The binary sum of data A and dataB data exceeds 38.
RO
US
US
US
US
RO
RO
Check For DRPI Urgent Alarm
Verify DRPI display URGENT ALARMlights - FLASHING
Proceed to NOTE prior to Step 3
* Loss of Data A will result in DRPIhalf-accuracy of +10 and -4 stepsfor affected rods.
* Loss of Data B will result in DRPIhalf-accuracy of +4 and -10 stepsfor affected rods.
Check For DRPI Non-Urgent Alarm
Verify RPI NON URGENT FAILURE(MB4C 3-10) annunciator - LIT
Verify DRPI Display DATA A FAILURE ORDATA B FAILURE lights - FLASHING
AOP 3552 AttC Step 2
AOP 3552 AttC Step 2.a
AOP 3552AttCStep 2.a,RNO
AOP 3552 AttC Step 3,Note
AOP 3552 AttC Step 3,Note
AOP 3552 AttC Step 3
AOP 3552 AftC Step 3.a
AOP 3552 AttC Step 3.b
Section 4Page 12 of 71
SEC! 1UN 4
SGTR WITHOUT PZR PRESSURE CONTROLTitle:
Revision: 0ID Number: 2K2 NRC-002
TaskAssianTima- InflMnif Inctrmietnr InfnrmationlActivitv Expected Action Standard
I11111U vllz a-......- %,w ........a_.<
NOTE: If asked or if boardoperator is sent to DRPI cabinet,"ACCURACY MODE switch is inA+13"
RO Verify ACCURACY MODE selector switch(back of DRPI cabinet) - A + B POSITION
AOP 3552 AttC Step 3.c
RO Identify affected rod(s) as follows:
* General Warning (GM) lightflashing
Verify affected rod(s) indicates within ± 12steps of associated group Step counterdemand height
AOP 3552 AttC Step 3.d
AOP 3552 AttC Step 3.e
RO
NOTE: When requestedacknowledge direction and after 1minute REPORT that theACCURACY MODE switch is in BONLY position
RO Perform the applicable action: AOP 3552 AttC Step 3.e,RNO* IF DRPI display DATA A FAILURE
lights flashing, THEN
1) Place ACCURACY MODE selectorswitch (back of DRPI cabinet) in B ONLYposition.
2) Proceed to Step 3.g
Verify affected rod(s) indicated within ± 12steps of associated group Step counterdemand height
RO AOP 3552 AttC Step 3.g
Section 4Page 13 of 71
Title:
SECTION 4
SGTR WITHOUT PZR PRESSURE CONTROL
(
ID Number: 2K2 NRC-002 Revision: 0
TaskAssianTime- InAIMlif Inttrunrfnr Infnrmation/Activitv ExDected Action Standard
I loil vsnz,,,,,,,.,..Z,_ ,_ _
NOTE: After notified as l&C informthe US that it is okay to return therods to Automatic. Once the rodsare in auto then...
Notify I & C AOP 3552 AttC Step 3.h
Proceed to Event 3
US
US
RO
US
US
US
A Central Control Card failure does notimpair system operation since the threecards are redundant, handling both data Aand data B.
Check For Central Control Card Failure
Verify DRPI display any CENTRALCONTROL FAILURE 1 2 3 light - LIT
Proceed to NOTE prior to Step 5.
In "half accuracy" operation, the affectedrod position will be indicated by every otherLED as the rod is raised or lowered.
Perform Follow-up actions
AOP 3552 AttC Step 4,Note
AOP 3552 AttC Step 4
AOP 3552 AttC Step 4.a
AOP 3552 AttC Step 4.a,RNO
AOP 3552 AttC Step 5,Note
AOP 3552 AttC Step 5
Section 4Page 14 of 71
( (SECTION 4
SGTR WITHOUT PZR PRESSURE CONTROLTitle:
ID Number: 2K2 NRC-002 Revision: 0
TaskAssiqnTime IDA/Malf Instructor Information/Activitv Expected Action Standard
T=completestep 3 ofAOP3552, Aft.C androds inauto
MALFSG03C
100%
EVENT 3: Steam Generator "C"Tube Leak
NOTE: Crew can enter AOP 3573,AOP 3555 (pg. 15), or AOP 3576(pg. 16) based on MALFindications.
AOP 3573, Radiation MonitorAlarm Response, Rev. 12
US If alarms are actuated on both area andprocess monitors, the applicable steps inthis procedure for each alarm may beperformed concurrently.
Check Initiating Monitor - AN AREAMONITOR
AOP 3573,Step 1,NOTE
AOP 3573,Step 1
RO
US
US
RO
RO
Proceed to step 3. AOP 3573,Step 1 RNO
Identify Affected Process UsingAttachment A
Check initiating process monitor - INALARM
Verify automatic actuations stated inAttachment A - OCCURRED
AOP 3573,Step 3
AOP 3573,Step 3.a
AOP 3573,Step 3.b
Section 4Page 15 of 71
Title:
SECTIUN 4
SGTR WITHOUT PZR PRESSURE CONTROL
ID Number: 2K2 NRC-002 Revision: 0
TaskAsctinnAt: i_ IFrA IRN-1I l~etrtnr Ifnrr"mftin1A*tivitv Exoected Action Standard
l ime IlUA/IElldI EHOI MLL'JtU I **** ~ ac i * ..y r , -ads -
Monitor Sample Stream/Possible Automatic/SubsequentActions
ARC21-1 Condenser air ejector discharge to Monitorradioactive gaseous waste. radiation
monitorsPossible indication of primary to MSS75 -
secondary leakage. MSS79 and
SSR08 forpossible 1°to 20 leak.
Takeappropriateaction usingAOP 3555,ReactorCoolantLeak.
AOP 3555, Reactor CoolantSystem Leak, Rev. 14
RO Check PZR Level - DECREASING AOP 3555Step 1
Proceed to NOTE prior to step 7
CREW Steps 7 through 17 may be performed inany order.
AOP 3555Step 1 RNO
AOP 3555Step 7,NOTE
Section 4Page 16 of 71
(SECTiuN 4
SGTR WITHOUT PZR PRESSURE CONTROLTitle:
ID Number: 2K2 NRC-002 Revision: 0
TaskAssignTime IDA/Malf Instructor Information/Activity Expected Action Standard
US
US
US
RO
Determine Leak Rate Using One OrMore Of the Following:
* Computer program 3J3
* Inventory balance
* VCT level trend
Check If SG Tubes Are Intact
Verify trend history and alarm status ofradiation monitors:
* Main steamline - NORMAL
* Condenser air ejector - NORMAL
* SG blowdown - NORMAL
Go to AOP 3576, Steam Generator TubeLeak.
Foldout Page must be open.
Verify PZR Level
Check PZR Level - DECREASING
AOP 3555Step 7
AOP 3555Step 8
AOP 3555Step 8.a
AOP 3555Step 8 RNO
3576 Step 1NOTE
3576 Step 1
3576Step 1.a
AOP 3576: Steam GeneratorTube Leak, Rev. 001
US
RO
Section 4Page 17 of 71
( (SECTION 4
SGTR WITHOUT PZR PRESSURE CONTROLTitle:
ID Number: 2K2 NRC-002 Revision: 0
TaskAssignTime IDA/Malf Instructor Information/Activity Expected Action Standard
Proceed to step 2. 3576Step 1.aRNO
US
US
Notify Chemistry 3576 Step 2
Request Chemistry perform SP 3861,"Primary to Secondary Leak RateDetermination," to:
3576Step 2.a
NOTE: Time and call back in 30minutes: Confirm "C" leak -20gpm
1. Determine the presence of primary tosecondary leakage.
2. Determine the leak rate.
3. Identify the leaking SG.
Note: There are 2/5 conditionswhich satisfies the step action.Crew should proceed
US
US/RO
SG tube leakage can be interpreted as"verified" when any two of the bulletedsubsteps of step 3 are satisfied.
Verify Primary To Secondary Leakage
* Check trend history and alarm status ofcondenser air ejector radiation monitor- NOT NORMAL
3576 Step 3NOTE
3576 Step 3
3576 Step 3Note: This condition exists
* Check trend history and alarm status ofsteam generator blowdown radiationmonitor - NOT NORMAL
Section 4Page 18 of 71
(SECTION 4
Title: SGTR WITHOUT PZR PRESSURE CONTROL
ID Number: 2K2 NRC-002
Time IDA/Malf Instructor Information/Acti
Revision: 0
vityTask
Assign
Note: This condition exists
Note: This condition exists
Expected Action
* Check trend history and alarm status ofmain steam line radiation monitors -NOT NORMAL
* Check Chemistry grab sample -INDICATESPRESENCE OF PRIMARYTO SECONDARY LEAKAGE
* Check trend history and alarm status ofN16 monitors - NOT NORMAL
Perfom Monitoring of N16 MonitorTrends
Initiate monitoring of N16 monitor trends
Verify SG Blowdown Status
Check if blowdown should be isolated
Condenser air ejector radiation monitor -IN ALERT OR ALARM
Standard
RO
RO
3576 Step 4
3576Step 4.a
3576 Step 4
3576Step 5.a
OR
Steam generator blowdown radiationmonitor - IN ALARM
OR
Section 4Page 19of71
( (SECTIUN 4
SGTR WITHOUT PZR PRESSURE CONTROLTitle:
Revision: 0ID Number: 2K2 NRC-002
TaskAssianYTim InAIMnlf I nstriuetMr I nfrmatinn/Activitv Expected Action Standard
I .,,,IU -... ...... .. , - - -,
Chemistry grab sample indicates primaryto secondary leakage - GREATER THANOR EQUAL TO 75 gpd
OR
N16 monitor in ALERT or HIGH
RO Check SG blowdown isolation valves -CLOSED
* 3BDG-CTV22A
* 3BDG-CTV22B
* 3BDG-CTV22C
* 3BDG-CTV22D
CLOSE valves.
Proceed to step 6.
3576Step 5.b
RO
US
3576Step 5.bRNO
3576Step 5.c
US
BOP
Limit Effects Of SecondaryContamination
Check auxiliary steam - SUPPLIED FROMMAIN STEAM
3576 Step 5
3576Step 6.a
Section 4Page 20 of 71
Title:
SECTIUN 4
SGTR WITHOUT PZR PRESSURE CONTROL
C
ID Number: 2K2 NRC-002 Revision: 0
TaskAssignTime IDA/Malf Instructor Information/Activity Expected Action Standard
REMOTE NOTE: When directed as PEO,MSR01 use REMOTE MSR01 To start
Aux Boiler.
US/PEO Using OP 3331A, "Auxiliary Boiler, Steamand Condensate" Perform the following:
3576Step 6.b
1. Startup of auxiliary boiler A (B)
2. Shift auxiliary steam from main steamto auxiliary boiler system.
US/PEO Locally Close the condenser level controlvalve outlet isolation (3CNS-V12)
3576Step 6.c
3576Step 6.d
US Request HP determine if personnel shouldbe evacuated from affected areas
* Turbine Bldg (north end)
* Secondary sample sink
* CPE
* MS Valve Bldg
Evacuate personnel from affected areas 3576Step 6.e
NOTE: Not desired to implementC OP 200.11. INFORM US thatSTA will perform and notify US ofany required actions.
US Refer to C OP 200.11, "Operation of aCross Contaminated System," andPerform any required actions
3576Step 6.f
Section 4Page 21 of 71
(i (SECTION 4
SGTR WITHOUT PZR PRESSURE CONTROLTitle:
Revision: 0ID Number: 2K2 NRC-002
TaskAssian* *mu InAIMnlf Intruirtnr Infnrmation/Activitv Expected Action Standard
I 1lult vii ~ v| . |} _.<
US Check If Unit Shutdown Should BeInitiated
3576 Step 7
Check any of the following: 3576Step 7.a
Note: This condition exists RO * Condenser air ejector radiation monitor- IN ALERT OR ALARM
OR
* Chemistry grab sample indicatesprimary to secondary leakage in anySG - GREATER THAN OR EQUAL TO75 gpd
OR
* Condenser air ejector radiation monitorcorrelation to leak rate (gpd) indicatesprimary to secondary leakage -GREATER THAN OR EQUAL TO 75gpd
OR
* N16 monitor in ALARM
NOTE: Inform US that the SM willperform this task.
US Evaluate event using MP-26-EPI-FAP06-003, Unit 3 Emergency Action Levels(Barrier Failure)
3576Step 7.b
Section 4Page 22 of 71
(IISECTION 4
Title: SGTR WITHOUT PZR PRESSURE CONTROL
(
ID Number: 2K2 NRC-002 Revision: 0
TaskAssignT~rim MAIM2If Instructnr Information/Activitv Expected Action Standard
I 1819a .... q.. .......... .. .. __w ....
US
US
Check plant status - MODE 1 OR 2
Proceed to step 9.
3576Step 7.c
3576Step 7.d
3576 Step 9NOTE
US * The shutdown times provided are EPRIrecommendations and should not beachieved at the cost of plant stability orintentional reactor trip.
* If a unit shutdown is initiated based ona condenser air ejector or N16 monitorALERT or ALARM condition andsubsequent Chemistry calculationsindicate actual leakage does not meetor exceed a shutdown criterion, thenthe shutdown may be suspended.
* The rate of increase limit does notapply to leak rate spikes followed bydecreasing leak rates.
* Plant shutdown may be accomplishedusing AOP 3575, "Rapid Downpower,"or appropriate General OperatingProcedures as determined necessary.
Section 4Page 23 of 71
( (SECtIuN 4
SGTR WITHOUT PZR PRESSURE CONTROLTitle:
ID Number: 2K2 NRC-002 Revision: 0
TaskAssignTime IDA/Malf Instructor Information/Activitv Expected Action Standard
[Tech Specs]
NOTE TO EVALUATOR: IF TechSpecs are not reviewed at thispoint, follow-up with US at end ofscenario (procedure does notspecifically direct Tech Specreview).
LCO 3.4.6.2.b & c, action b
US Perform Unit Shutdown 3576 Step 9
Verify a leakage rate of increase limit met: 3576Step 9.a
NOTE: The leak is about 40 gpm.This should be obvious to the
crew and they should answer yesat this step and continue to step9.b..IF they pause at this stepREPORT as Chemistry that initialindications are that the leak is > 20gpm.
* Check leakage increased in any SG by- GREATER THAN OR EQUAL TO 15gpd IN A 30 min PERIOD
OR
* Check condenser air ejector radiationmonitor RATE OF CHANGE ALARM -IN ALARM FOR 30 min
OR
Section 4Page 24 of 71
SECTIuN 4
Title: SGTR WITHOUT PZR PRESSURE CONTROL
ID Number: 2K2 NRC-002 Revision: 0
TaskTime IDA/Malf Instructor Information/Activity Assign Expected Action Standard
* Check N16 S/G Leak Detection Status(PPC) HIGH RATE (75 GPD & 15 GPDRISE IN 30 MIN) - IN ALARM
Proceed to step 9.d 3576Step 9.b
RO Check power level - GREATER THAN 357650% Step 9.d
US Initiate power reduction to be LESS THAN 357650% within 1 hour (downpower rate of Step 9.e3%/6/min or 5%/6/min recommended)
T= When EVENT 3a: Rapid Downpowerdirected due to S/G Tube Leak (AOPby AOP 3576)3576 [Reactivity Manipulation]
* A CONVEX requested emergency AOP 3575generation reduction should be Step 1completed within 15 minutes of NOTEnotification.
* If a unit shutdown is required, thetarget power level should be between20% and 25% reactor power.
* If at any time ROD CONTROL BANKSLIMIT LO - LO (MB4C 4 - 9)
Section 4Page 25 of 71
( (SECTION 4
SGTR WITHOUT PZR PRESSURE CONTROLTitle:
ID Number: 2K2 NRC-002 Revision: 0
TaskAssignTime IDA/Malf Instructor Information/Activitv Expected Action Standard
annunciator is received, DO NOT go toAOP 3566, Immediate Boration.Immediately perform step 9.
AOP 3575 Rev. 7 CREW
US
US
Determine Power Reduction Rate(%/min).
Check desired power reduction rate -LESS THAN OR EQUAL TO 5%/min.
Check power reduction - CONVEXREQUESTED
AOP 3575Step 1
AOP 3575Step 1.a
AOP 3575Step 1.b
US Proceed to Step 1.d. AOP 3575Step 1.bRNO
CREW Determine power reduction rateusing Table.
AOP 3575Step 1.d
Total Power Change (A%)
10% 20% 30% 40% 50% 60% 70% 80%70% 80%____________ L .1. I .L. 4 4 4
115 3 3 3 5 5 5
30 0.5 1 1 3 3 3 3 3
45 0.5 0.5 1 1 3 3 3 3
Section 4Page 26 of 71
(SECTION 4
SGTR WITHOUT PZR PRESSURE CONTROLTitle:
ID Number: 2K2 NRC-002 Revision: 0
TaskAssignTime IDA/Malf Instructor Information/Activity Expected Action Standard
Time to
Reduce
Power
(min)
60 0.5 0.5 1 1 1 3 3
75 0.5 0.5 1 1 1 1 3
90 0.5 0.5 0.5 1 1 1 1
105 0.5 0.5 0.5 0.5 1 1 1
120 0.5 0.5 0.5 0.5 1 1
135 0.5 0.5 0.5 0.5 1 1
150 _ 0.5 0.5 0.5 0.5 0.5 1
160 I 0.5 1 0.5 1 0.5 0.5 10.5 0.5
US
CREW
US
US
Check Rod Control In AUTO.
Align EHC Panel
Check turbine OPERATING MODE -MANUAL
Check LOAD LIMIT LIMITING light - LIT
AOP 3575Step 2
AOP 3575Step 3
AOP 3575Step 3.a
AOP 3575Step 3.b
Section 4Page 27 of 71
(SECT1UN 4
SGTR WITHOUT PZR PRESSURE CONTROL
!
Title:
ID Number: 2K2 NRC-002 Revision: 0
TaskAssignTime IDA/Malf Instructor Information/Activity Expected Action Standard
BOP
BOP
BOP
BOP
US/RO
RO
Proceed to step 3.e. AOP 3575Step 3.bRNO
Intermittently Press DECREASE LOADpushbutton until LOAD LIMIT LIMITINGlight - NOT LIT
Rotate LOAD LIMIT SET adjust knob atleast one full turn in raise direction
Select DECREASE LOADING RATE toON
Select LOAD RATE LIMIT % MIN torequired power reduction rate (% min)
If at any time the power reduction rate ortarget power level must be changed,Return to step 1.
Verify Power Reduction Rate
Check power reduction rate 5% MIN
Perform the applicable action:
AOP 3575Step 3.c
AOP 3575Step 3.d
AOP 3575Step 3.e
AOP 3575Step 3.f
AOP 3575Step 4NOTE
AOP 3575Step 4
AOP 3575Step 4.a
AOP 3575Step 4.aRNO
Section 4Page 28 of 71
Title:
ID Number:
Time
EVALUAI iON GUIDESGTR WITHOUT PZR PRESSURE CONTROL
2K2 NRC-002 Revision: 0Task
IDA/Malf Instructor Information/Activity Assign
RO
RO
RO
RO
Expected Actions
* IF power reduction rate is 3% min,
THEN
Proceed to step 5.
Proceed to step 5.
Proceed to NOTE prior step 7.
Initiate Rapid Boration
Verify RCS makeup system in - AUTO
START one boric acid transfer pump.
OPEN emergency boration valve(3CHS*MV8104).
Verify direct boric acid flow (3CHS-FI183A) - INDICATED.
OPEN charging line flow control valve, tomatch boric acid flow (3CHS-FI 183A)
Record time boration started
Time
(
AOP 3575Step 4.bRNO
AOP 3575Step 4.c
AOP 3575Step 5
AOP 3575Step 5.a
AOP 3575Step 5.b
AOP 3575Step 5.c
AOP 3575Step 5.d
AOP 3575Step 5.e
AOP 3575Step 5.f
Standard
Section 4Page 29 of 71
alEVALUATION GUIDE
Title: SGTR WITHOUT PZR PRESSURE CONTROL
ID Number: 2K2 NRC-002 Revision: 0Task
AssiqnTime IDA/Malf Instructor Information/Activity Expected Actions Standard
Energize all PZR heaters. AOP 3575Step 5.g
Determine required boric acid addition bymultiplying total power change (A%) by 15(gal/%) = _ gal.
Determine required time to borate bydividing required gallons of boric acid bythe direct boric acid flowrate (net chargingflow rate if using gravity boration) -
min.
Check turbine load decrease - INPROGRESS OR COMPLETED.
Proceed to NOTE prior to Step 7.
Proceed to NOTE prior to Step 8.
US
US
US
AOP 3575Step 5.h
AOP 3575Step 5.i
AOP 3575Step 5.j
AOP 3575Step 5.jRNO
AOP 3575Step 5.k
Section 4Page 30 of 71
Title:
(EVALUATION GUIDE
SGTR WITHOUT PZR PRESSURE CONTROL
i.
ID Number: 2K2 NRC-002 Revision: 0Task
AssianTimn IflAIRM If I nstri irctr I nfnrmation/Activitv Expected Actions StandardaIt I 1lIv -v1ll .svvv zw bev - .. Oa - - ....- . .r.--- 1-----
CREW Boric acid total volume addition and flowrates are based on approximations.Adjustments should be made to thesevalues as necessary to ensure the reactorreaches the desired end state of:
AOP 3575Step 6NOTE
US
US/RO
RO
US
RO
RO
RO
* Tavg on program
* Rods above the Rod Insertion Limit
* AFD on or above the target value
Align RCS Makeup System ForBoration.
Determine required boric acid addition bymultiplying total power change (A%) by15(gal/%) = _ _gal.
Set the boric acid batch counter to totalgallons of boric acid required.
Check power reduction rate- AT 0.5%/min.
Adjust boric acid blend flow controller potsetting to 3.75 (15 gpm) and Proceed toStep 6.e.
Adjust boric acid blend flow controller potsetting to 1.9 (7.5 gpm).
Select BORATE on the reactor coolantmakeup select switch.
AOP 3575Step 6.b
AOP 3575Step 6.c
AOP 3575Step 6.cRNO
AOP 3575Step 6.d
AOP 3575Step 6.e
Section 4Page 31 of 71
AOP 3575Step 6
AOP 3575Step 6.a
(EVALUAI ION GUIDE
SGTR WITHOUT PZR PRESSURE CONTROL
i
Title:
ID Number: 2K2 NRC-002 Revision: 0Task
AssiqnTime InA/MIMlf Instructor Information/Activity Expected Actions Standard,,,,, ,a, . m., .. . ___._ ............... _ ..... ... ......... .. .. ,
RO
RO
US
RO
RO
Select START on the reactor coolantmakeup start switch.
Verify boric acid flow - INDICATED
Return to step 5.
Energize all PZR heaters.
If a unit shutdown is being performed, thefinal MWe load should be approximately230 MWe.
Initiate Load Reduction.
Check turbine OPERATING MODE -MANUAL
Check rapid or gravity boration - INPROGRESS
Proceed to step 7.d.
Check LOAD RATE LIMIT % MIN set at -3% OR 5%.LIMITING light - LIT.
US/BOP
AOP 3575Step 6.f
AOP 3575Step 6.g
AOP 3575Step 6.gRNO
AOP 3575Step 6.h
AOP 3575Step 7NOTE
AOP 3575Step 7
AOP 3575Step 7.a
AOP 3575Step 7.b
AOP 3575Step 7.bRNO
AOP 3575Step 7.c
Section 4Page 32 of 71
BOP
BOP
BOP
BOP
(EVALUA! iON GUIDE
SGTR WITHOUT PZR PRESSURE CONTROL
(,
Title:
ID Number: 2K2 NRC-002 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Expected Actions Standard
BOP
BOP
BOP
US
BOP
US/RO
US
Select LOAD RATE LIMIT % MIN to 3% or5%.
Utilizing DECREASE LOAD pushbutton,Adjust LOAD SET to desired final MWe(target power level)
Check power reduction - CONVEXREQUESTED.
Inform CONVEX of load reduction rate(MWe/min) and final MWe level.
Maintain initial MVAR loading during powerreduction, unless directed otherwise.
Check boration - IN PROGRESS
Return to step 5.
AOP 3575Step 7.cRNO
AOP 3575Step 7.d
AOP 3575Step 7.e
AOP 3575Step 7.eRNO
AOP 3575Step 7.f
AOP 3575Step 7.g
AOP 3575Step 7.gRNO
T= powerreductioninprogress
MALFRD021
EVENT 4: Rod Bank CB-DContinuous Rod Insertion
RSCU3
Section 4Page 33 of 71
( (:EVALUATION GUIDE
SGTR WITHOUT PZR PRESSURE CONTROLTitle:
ID Number:
Time
2K2 NRC-002 Revision: 0Task
AssignIDA/Malf Instructor Information/Activity Expected Actions Standard
AOP 3552 MALFUNCTION OFTHE ROD DRIVE SYSTEM, Rev.3
CREW Stabilize Plant Conditions AOP 3552Step 1
RO
RO
CREW
Place control rod bank SEL switch in MAN
Verify - NO RODS MOVING
TRIP the reactor and Go to E-Q, ReactorTrip or Safety Injection.
AOP 3552Step 1.a
AOP 3552Step 1.b
AOP 3552Step 1.bRNO
MALFSG01C50%ED01
EVENT 5: SGTR with Loss ofOffsite Power
E-O, Reactor Trip or SafetyInjection, Rev. 21
Crew Go to E-0, Reactor Trip or Safety Injection.
* Foldout page must be open E-0, Step 1,NOTE
* ADVERSE CTMT defined asGREATER THAN 180 0F or GREATERTHAN 105 R/hr in containment.
* The reactor can be interpreted as"tripped" when any two of threebulleted substeps of Step 1.* aresatisfied.
Section 4Page 34 of 71
(aEVALUATION GUIDE
SGTR WITHOUT PZR PRESSURE CONTROL
1
Title:
ID Number: 2K2 NRC-002 Revision: 0Task
AssiqnTime IDA/Malf Instructor Information/Activity Expected Actions Standard
RO
BOP
BOP
BOP
US
RO
US
Verify Reactor Trip
* Check reactor trip and bypassbreakers - OPEN
* Check rod bottom lights - LIT
* Check neutron flux - DECREASING
Verify Turbine Trip
Check all turbine stop valves - CLOSED
Verify Power to AC Emergency Busses
Check busses 34C and 34D -
BOTH ENERGIZED
Check If Si Is Actuated
Verify SAFETY INJECTION ACTUATIONannunciator - (MB4D 1-6 or MB2B 5-9) -LIT
Check if Si is required
E-0, Step 1
E-0, Step 2
E-0,Step 2.a
E-0, Step 3
E-0,Step 3.a
E-0, Step 4
EOP 35 E-0,Step 4.a
E-0, Step 47RNO
* CTMT pressure GREATER THAN 18psia
OR
* RCS pressure LESS THAN 1890 psia
Section 4Page 35 of 71
(EVALUAI ION GUIDE
SGTR WITHOUT PZR PRESSURE CONTROLTitle:
ID Number: 2K2 NRC-002 Revision: 0Task
AssianTime IDA/Malf Instructor Information/Activity Expected Actions Standard. | . .. ..... % .. _ _. _. ... ... ...... _ .. ... .. .... ... ,I,
OR
* PZR level LESS THAN 16%
OR
* RCS subcooling LESS THAN 320F
OR
* SG pressure LESS THAN 660 psig
IF Si is required, THEN initiate Si andProceed to step 5
MALFSW01ASW02C
EVENT 6: Service WaterPumps Fail to Auto Start
[Critical Task] Manually start theB Train Service Water Pumpbefore transitioning from E-0.
NOTE: If the A SWP does not starton the first time REPORT as PEOor Maintenance, if requested, andrecommend a second attempt.
RO
RO
RO
Verify Service Water Pumps - AT LEASTONE PER TRAIN RUNNING
E-0, Step 5
START pumps E-0, Step 5RNO
Verify Two RPCCW Pumps - ONE PERTRAIN RUNNING
E-0, Step 6
RO Verify ECCS Pumps Running
* Check SI pumps - RUNNING
* Check RHR pumps - RUNNING
E-0, Step 7
Section 4Page 36 of 71
(EVALUAi iON GUIDE
SGTR WITHOUT PZR PRESSURE CONTROL
(
Title:
ID Number: 2K2 NRC-002 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Expected Actions Standard
* Check two charging pumps -RUNNING
NOTE: Crew may identify rupturedS/G early and take critical taskaction in advance of proceduraldirection.
BOP Verify AFW Pumps Running E-0, Step 8
[Critical Task] Identify rupturedS/G and Isolate AFW beforenarrow range level reaches 29%.
Check MD pumps - RUNNING
Check turbine - driven pump - RUNNING,IF NECESSARY
E-0,Step 8.a
E-0,Step 8.b
BOP Verify FW Isolation
* Check SG feed regulating valves -CLOSED
* Check SG feed regulating bypassvalves - CLOSED
* Check FW isolation trip valves -CLOSED
* Check MD FW pump - STOPPED
* Check TD FW pumps - TRIPPED
E-0, Step 9
Section 4Page 37 of 71
(.EVALUATION GUIDE
SGTR WITHOUT PZR PRESSURE CONTROL
(
Title:
ID Number:
Time
2K2 NRC-002
IDA/Malf
Revision: 0Task
AssignInstructor Information/Activity Expected Actions Standard
BOP
* Check SG blowdown isolation valves -CLOSED
* Check SG blowdown sample isolationvalves - CLOSED
* Check SG chemical feed isolationvalves - CLOSED
Check If Main Steam Lines Should BeIsolated
Check Ctmt pressure GREATER THAN 18psia
OR
Any SG pressure LESS THAN 660 psig
Proceed to Step 11
Check if CDA Required
Check Ctmt pressure is GREATER THAN23 psia
E-0, Step 10
E-0,Step 10.a
E-0,Step 10.a,RNO
E-0, Step 11
E-0,Step 1 1.a
RO
OR
Ctmt spray is initiated
Section 4Page 38 of 71
EVALUATION GUIDESGTR WITHOUT PZR PRESSURE CONTROL
f
Title:
ID Number: 2K2 NRC-002 Revision: 0Task
AssionTime- IrlA /AnIf tri nftrnr Infnrmftieon/Activitv Expected Actions StandardI 1111V IL-Ii-VIVIG111
US Proceed to Step 12. E-0,Stepl 1,a,RNO
BOP
BOP
Verify CAR Fans Operating InEmergency Mode
E-0, Step 12
Check CAR fan status: E-0,Step 12.a
BOP
RO
RO
* CAR fans A and B - RUNNING
* CAR fan C - STOPPED
START/STOP CAR fans as necessary.
Verify RPCCW Ctmt supply and returnheader isolations - OPEN
Verify Train A and B RPCCW supply andreturn to chill water valves - OPEN
E-0,Step 12.a,RNO
E-0,Step 12.b
E-0,Step 12.c
E-0, Step 13
E-0,Step 13.a
RO
RO
Verify CIA
Check ESF Group 2 status columns 2through 10 - LIT
Verify Proper ESF Status PanelIndication
RO E-0, Step 14
* Verify ESF Group 1 lights - OFF
Section 4Page 39 of 71
Title:EVALUAI iON GUIDE
SGTR WITHOUT PZR PRESSURE CONTROL
ID Number: 2K2 NRC-002 Revision: 0Task
AssianTimn~ I AIM K f Inctri ictnr Inform~ation/Activitv Expected Actions Standard111110 *-lUI-A,
* Verify ESF Group 2 lights - LIT
RO/BOP Align component(s) as necessary forminimum safety function.
E-0,Step 14,RNO
RO Determine If ADVERSE CTMTConditions Exist
E-0, Step 15
* Ctmt temperature GREATER THAN1800F
OR
* Ctmt radiation GREATER THAN 105R/hr
DO NOT use ADVERSE CTMTparameters.
CREW E-0,Step 15,RNO
RO Verify ECCS Flow E-0, Step 16
Check charging pumps -
FLOW INDICATED
E-0,Step 16.a
E-0,Step 16.b
RO
US
Check RCS pressure - GREATER THAN1650 psia (1950 psia ADVERSE CTMT)
Proceed to Step 16.d E-0,Step 16.b,RNO
Section 4Page 40 of 71
( (EVALUM iON GUIDE
SGTR WITHOUT PZR PRESSURE CONTROLTitle:
ID Number: 2K2 NRC-002 Revision: 0Task
A--ionTiff- I rA /hAn If I nctri jit-r I nfnrmntinn/Artivitv ExDected Actions StandardI 111lU 1I1Vt\/V1G1l --- 1;>t ---vi allvEcvApzv- U -
Proceed to step 17.
Check Si pumps - FLOW INDICATED
START pumps and Align valves.
Check RCS pressure - LESS THAN 300psia (500 psia ADVERSE CTMT)
Check RHR pumps - FLOW INDICATED.
E-0,Step 16.c
E-0,Step 16.d
E-0, Step16.d RNO
E-0,Step 16.e
E-0,Step 16.f
BOP Verify Adequate Heat Sink E-0, Step 17
Check NR level in at least one SG -GREATER THAN 8% (42% ADVERSECTMT)
E-0,Step 17.a
US
BOP
US
BOP
Proceed to Step 17.d. E-0,Step 17.a,RNO
Control feed flow to maintain NR level -BETWEEN 8% and 50% (42% and 50%ADVERSE CTMT)
E-0,Step 17.b
Proceed to Step 18. E-0,Step 17.c
Verify Total AFW Flow - GREATER THAN530 gpm
E-0,Step 17.d
Section 4Page 41 of 71
Title:EVALUATION GUIDE
SGTR WITHOUT PZR PRESSURE CONTROL
(
ID Number:
Tim-
2K2 NRC-002 Revision: 0Task
AssianInA/Mnlf Instructor Information/Activitv Expected Actions Standard
BOP
RO
US
Verify AFW Valve Alignment - PROPEREMERGENCY ALIGNMENT
Verify ECCS Valve Alignment - PROPEREMERGENCY ALIGNMENT
Check Plant Status
E-0, Step 18
E-0, Step 19
E-0, Step 20
BOOTHINST
NOTE When asked, REPORT that "allSLCRS doors indicate closed."
Verify SLCRS doors - CLOSED E-0,Step 20.a
RO
RO
RO
Check CONTROL BUILDING ISOLATIONannunciator (MB4D 3-6) - LIT
Check if CBI is required
* Ctmt pressure GREATER THAN 18psia
OR
* Control Building radiation monitor inalarm
E-0,Step 20.b
E-0,Step 20.b,RNO
RO
OR
RO
US
* Si manually actuated
IF CBI required, THEN initiate CBI.
IF CBI is NOT required, THEN proceed toStep 21.
Section 4Page 42 of 71
(EVALUATION GUIDE
SGTR WITHOUT PZR PRESSURE CONTROLTitle:
ID Number:
Time
2K2 NRC-002 Revision: 0Task
AssignIDA/Malf Instructor Information/Activity Expected Actions Standard
RO
RO
BOP
BOP
BOP
Verify ESF Group 2 CBI lights - LIT
Align HVAC components as necessaryfor minimum safety function.
Verify control building purge supply fanand purge exhaust fan - NOT RUNNING
Control building air bank isolation valves- OPEN (after 60 seconds)
STOP kitchen exhaust fan
E-0,Step 20.c
E-0,Step 20.c,RNO
E-0,Step 20.d
E-0,Step 20.e
E-0,Step 20.f
BOOTHINST
NOTE When called, WAIT 3 - 5 min,Then REPORT "All ControlBuilding pressure boundary doorsare Closed and Dogged."
PEO Close and Dog (as applicable) ControlBuilding pressure boundary doors.
E-0,Step 20.g
RO Check RCS Temperature E-0, Step 21
Verify RCS cold leg WR temperature -BETWEEN 5500F and 5600F
E-0,Step 21.a
E-0,Step 21.a,RNO
US Perform the applicable action:
* IF temperature is GREATER THAN550 0F AND 5600F, THEN
Section 4Page 43 of 71
(.
EVALUAl ION GUIDESGTR WITHOUT PZR PRESSURE CONTROLTitle:
ID Number: 2K2 NRC-002 Revision: 0Task
AssianTime IDA/Malf Instructor I nformation/Activitv Expected Actions Standard
1) Dump steam to the condenser, ifavailable OR Dump steam toatmosphere.
2) Proceed to Step 22.
* IF the temperature is LESS THAN550°, THEN proceed to Step 21 c.
US
US
BOP
BOP
BOP
Proceed to Step 22 E-0,Step 21.b
Maintain total feed flow BETWEEN 530and 600 gpm until NR level is GREATERTHAN 8% (42% ADVERSE CTMT) in atleast one SG
CLOSE SG atmospheric dump and dumpbypass valves
Check the following valves - CLOSED
E-0,Step 21.c
E-0,Step 21.d
E-0,Step 21.e
* 5s
* MSIV bypass valves
US Perform the following: E-0,Step 21.e,RNO
BOP Place both condenser steam dumpinterlock selector switches to OFF.
E-0,Step 21.e.1,RNO
Section 4Page 44 of 71
Title:
ID Number:
Time
EVALUi ION GUIDESGTR WITHOUT PZR PRESSURE CONTROL
2K2 NRC-002 Revision: 0Task
IDA/Malf Instructor Information/Activity Assign
BOP
RO
RO
RO
RO
CREW
RO
Expected Actions
IF unexpected cooldown continues, THENCLOSE the MSIVs and MSIV bypassvalves.
Check PZR Valves
Verify PORVs - CLOSED
Verify normal PZR spray valves - CLOSED
Verify PZR safety valves - CLOSED
Check PORV block valves - OPEN
To prevent damage to the RCP seal(s),seal injection flow should be maintained toall RCPs.
Check If RCPs Should Be Stopped
Verify RCPs - ANY RUNNING
Proceed to step 24.
Standard
E-0,Step 21.e.2,RNO
E-0, Step 22
E-0,Step 22.a
E-0,Step 22.b
E-0,Step 22.c
E-0,Step 22.d
E-0,Step 23,CAUTION
E-0, Step 23
E-0,Step 23.a
E-0,Step 23.a,RNO.
(
Section 4Page 45 of 71
Title:EVALUATION GUIDE
SGTR WITHOUT PZR PRESSURE CONTROL
l
ID Number: 2K2 NRC-002 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Expected Actions StandardVerify RCS pressure - LESS THAN 1500
RO
US
RO
US
RO
Verify RCS pressure - LESS THAN 1500psia (1800 psia ADVERSE CTMT)
Proceed to Step 24
Verify charging or SI pumps - AT LEASTONE RUNNING
Proceed to Step 24
STOP all RCPs
E-0,Step 23.b
E-0,Step 23.b,RNO.
E-0,Step 23.c
E-0,Step 23.c,RNO
E-0,Step 23.d
E-0, Step 24BOP/RO Check If SG Secondary Boundaries AreIntact
Check pressure in all SGs
* NO SG PRESSURE DECREASING INAN UNCONTROLLED MANNER
* NO SG COMPLETELYDEPRESSURIZED
Check If SG Tubes Are Intact
E-0,Step 24.a
BOP E-0, Step 25
Section 4Page 46 of 71
( (EVALUATION GUIDE
Title: SGTR WITHOUT PZR PRESSURE CONTROL
ID Number: 2K2 NRC-002 Revision: 0Task
Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard
RO Sample all SGs for activity E-0,Step 25.a
1. RESET SG blowdown sampleisolation
2. OPEN SG blowdown sample isolationvalve(s)
3. Request Chemistry obtain activitysamples using HP coverage
BOP Check steam generator levels - NO SG E-0,LEVEL INCREASING IN AN Step 25.bUNCONTROLLED MANNER
US Initiate monitoring of CSF Status Trees E-0,and Go to E-3, Steam Generator Tube Step 25.b,Rupture. RNO
Verify trend history and alarm status of E-0,radiation monitors Step 25.c
* Main steam line - NORMAL
* Condenser air ejector - NORMAL
* SG blowdown - NORMAL
Initiate monitoring of CSF Status Trees E-0,and Go to E-3, Steam Generator Tube Step 25.cRupture RNO
Section 4Page 47 of 71
KEVALUA-I ION GUIDE
SGTR WITHOUT PZR PRESSURE CONTROLTitle:
ID Number: 2K2 NRC-002 Revision: 0Task
AssianTime InA/Mnlf Instructor Information/Activity Expected Actions Standard. I.- --- -1
RO Verify trend history and alarm status ofradiation monitors
MALFSG01C
E-3: Steam Generator TubeRupture, Rev. 17
US To prevent damage to the RCP seal(s),seal injection flow should bemaintained to all RCPs.
E-3 Step 1CAUTION
US * Foldout page must be open
* The RCP trip criteria is onlyapplicable until a controlledcooldown is initiated in step 6.
Check If RCPs Should Be Stopped
E-3, Step 1,NOTE
E-3, Step 1RO
Check RCPs - ANY RUNNING E-3,Step 1.a
Proceed to step 2. E-3,Step 1.a,RNO
Verify RCS pressure - LESS THAN 1500psia (1800 psia ADVERSE CTMT)
Proceed to step 2.
E-3,Step 1.b
E-3,Step 1.b,RNO
Verify charging or safety injection pumps -AT LEAST ONE RUNNING
E-3,Step 1.c
STOP all RCPs E-3,Step 1.d
Section 4Page 48 of 71
Title:EVALUA) iON GUIDE
SGTR WITHOUT PZR PRESSURE CONTROL
f
ID Number: 2K2 NRC-002 Revision: 0Task
A--ionT;:_ IMA IfA-1F I rLtri irtnr Infnrmnfinn/Ac--tixvitv Expected Actions StandardI IIII IlUAIVIdII 1l 11QL k IU LW. 11I * 11t*SS-,*'-r
[Critical Task] Identify rupturedS/G and Isolate AFW beforenarrow range level reaches 29%.
BOP Identify Ruptured SGs
* Unexpected increase in any SG level
E-3, Step 2
OR
* High radiation from any SG steam lineas indicated by the trend history oralarm status
OR
* High radiation from any SG sample
* If the TD AFW pump is the onlyavailable source for feed flow,steam supply to the TD AFW pumpmust be maintained from at leastone SG.
US E-3, Step 3,CAUTION
* At least one SG must be maintainedavailable for RCS cooldown.
BOP Isolate Flow From Each Ruptured SG E-3, Step 3
Verify each ruptured SG atmosphericdump valve controller - IN AUTO AT 1125psig
Check each ruptured SG atmosphericdump valve - CLOSED
E-3, Step3.a
E-3,Step 3.b
RO
Section 4Page 49 of 71
EVALUATION GUIDESGTR WITHOUT PZR PRESSURE CONTROL
i'
Title:
ID Number: 2K2 NRC-002 Revision: 0Task
AssianTima InA/Malf Instructor Information/Activitv Expected Actions Standard| dvvc f-- OBw-- -I
Check each ruptured SG atmosphericdump bypass valve - CLOSED.
CLOSE each ruptured SG steam supplyisolation valve to TD AFW pump.
E-3,Step 3.c
E-3, Step3.d
* 3MSS*MOV17A
* 3MSS*MOV17B
* 3MSS*MOV17D
Verify each ruptured SG blowdownisolation valve - CLOSED
CLOSE valves.
Verify each ruptured SG blowdown sampleisolation valve - CLOSED
CLOSE valves
Verify each ruptured SG chemical feedisolation valve - CLOSED
CLOSE valves
E-3,Step 3.e
E-3,Step 3.e,RNO
E-3, Step3.f
E-3,Step 3.f,RNO
E-3,Step 3.g
E-3,Step 3.g,RNO
Section 4Page 50 of 71
(.
EVALUATION GUIDESGTR WITHOUT PZR PRESSURE CONTROLTitle:
ID Number: 2K2 NRC-002 Revision: 0Task
AssianTime IDA/Malf Instructor I nformation/Activitv Expected Actions StandardI
Using table, CLOSE the main steam linedrains upstream of MSIVs and TD AFWpump for the ruptured SG(s)
E-3,Step 3.h
SG A SG B I SG C SG D
3DTM*AOV29A
3DTM*AOV61A
3DTM*AOV63A
3DTM*AOV64A
3DTM*AOV29B
3DTM*AOV61 B
3DTM*AOV63B
3DTM*AOV64B
3DTM*AOV29C
3DTM*AOV61 C
3DTM*AOV29D
3DTM*AOV61 D
3DTM*AOV63D
3DTM*AOV64D, _
_ _
EVENT 7: MSIV on Ruptured S/GFails to Close
BOP CLOSE each ruptured SG MSIV and MSIVbypass valve.
E-3,Step 3.i
Perform the following: E-3, Step3.i RNO[Critical Task] Isolate steam flow from
ruptured S/G before a transition to ECA-3.1 occurs at step 3 of E-3 (MSIV failed).
NOTE: Perform this step when directedas PEO and Report when the crewreaches Step 5 Caution. (This is a TimeCompression technique to supportprocedure flow).
1. CLOSE all remaining SG MSIVs andMSIV bypass valves.
2. Close all valves listed on AttachmentA.
3. Use the intact SG atmospheric dumpvalves to dump steam, for RCStemperature control or cooldown.
IF any ruptured SG can NOT beisolated from at least one intact SG,THEN Go to ECA-3.1, SGTR with Lossof Reactor Coolant - SubcooledRecovery Desired.
Section 4Page 51 of 71
Title:EVALUAI ION GUIDE
SGTR WITHOUT PZR PRESSURE CONTROL
(
ID Number: 2K2 NRC-002 Revision: 0Task
AssionTime- r) A /tAn If I nctni I-tnr I nfnrmntinn/Artivitv ExDected Actions StandardI III I; .... 1, .L. . -- r
-US
BOP
If any ruptured SG is faulted, feed flowto that SG should remain isolatedduring subsequent recovery actionsunless the SG is needed for RCScooldown.
Check Ruptured SG Level
Verify one of the following is satisfied:
* Ruptured SG WR level - GREATERTHAN 67% (95% ADVERSE CTMT)
OR
* Ruptured SG NR level - GREATERTHAN 8% (42% ADVERSE CTMT)
Isolate feed flow to ruptured SGs.
E-3, Step 4,CAUTION
E-3, step 4
E-3,Step 4.a
E-3,Step 4.b
NOTE: When the Crew reaches this stepreport as the PEO that the step iscomplete (This is a Time Compressiontechnique to support procedure flow).
Steps 3.d and 3.i for isolating the rupturedSG must be completed prior to continuingto step 5.
E-3, Step 5,CAUTION
BOP Check Ruptured SGs Pressure -GREATER THAN 530 psig
E-3, step 5
Section 4Page 52 of 71
Title:EVALUM iON GUIDE
SGTR WITHOUT PZR PRESSURE CONTROL
(
ID Number: 2K2 NRC-002 Revision: 0Task
AssianTime IDA/Malf Instructor Information/Activity Expected Actions StandardI
US
US
If RCPs are NOT running, the followingsteps may cause a false entry into theINTEGRITY Status Tree for the affectedloop. Disregard the affected loop Tcindication until after performance of step27.
* To allow steam dump operation tocontinue during a controlled cooldown,ensure the Low-Low Tavg interlock isbypassed at 5530F.
E-3, Step 6CAUTION
E-3, Step 6NOTE
* Ensure Low Steam Line Pressure Si isblocked when pressurizer pressure isLESS THAN 2000 psia.
* After the Low Steam Line Pressure SIsignal is blocked, MSI will occur if thehigh steam pressure rate setpoint isexceeded.
US/RO/PEO
Initiate RCS Cooldown E-3, Step 6
Check RCPs -ANY RUNNING E-3, Step6.a
Proceed to step 6.c. E-3,Step 6.a,RNO
Section 4Page 53 of 71
Title:EVALUATION GUIDE
SGTR WITHOUT PZR PRESSURE CONTROL
(S
ID Number: 2K2 NRC-002 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Expected Actions Standard
Locally, Place the eight RCP overcurrenttrip switches (43PP and 43PB) in theCOLD position using CO key Locker Key#7
E-3,Step 6.b
Determine required core exit temperaturewithout interpolatina (use lower pressure)
E-3,Step 6.c
NOTE: If the Plant ProcessComputer has been lost use one ofthe following to report CETCs andsubcooling values as requested:
* IDT Pages
* "Max Fuel Temp" on InstructorConsole
* Steam Tables (for subcooling)
Lowest Ruptured SG Core Exit TemperaturePressure (psig) (OF)
NORMAL ADVERSE
1285 537 513
1185 526 502
1085 515 489
985 502 475
885 488 459
785 474 443
685 457 423
585 449 426
530 435 410
Dump steam to condenser from intact SGs atmaximum rate
E-3, Step 6.d
Section 4Page 54 of 71
( ( (fEVALUATION GUIDE
Title: SGTR WITHOUT PZR PRESSURE CONTROL
ID Number: 2K2 NRC-002 Revision: 0Task
Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard
1. Verify the following:
* Intact SG MSIVs - OPEN
* Annunciator "CONDENSER AVAILFOR STM DUMP C-9" (MB4D 5-6) -LIT
2. Adjust steam pressure controller toobtain zero output in MANUAL
3. Transfer condenser steam dumpsto Steam Pressure Mode
4. Place both condenser steam dumpinterlock selectors - ON
5. Adjust steam pressure controller todump steam to condenser
Dump steam to atmosphere from intact E-3,SGs at maximum rate using SG Step 6.datmospheric dump valves. RNO
Verify core exit TCs - LESS THAN E-3,REQUIRED TEMPERATURE Step 6.e
Section 4Page 55 of 71
( {l:EVALUAM ION GUIDE
SGTR WITHOUT PZR PRESSURE CONTROLTitle:
ID Number: 2K2 NRC-002 Revision: 0Task
AssianTime InA/Mqlf Instructor Information/Activitv Expected Actions Standard
Proceed to NOTE prior to step 7 and,
WHEN
Core exit TCs less than requiredtemperature,
THEN
E-3,Step 6.eRNO
Perform steps 6.f and 6.g
Stop RCS cooldown E-3, Step 6.f
Maintain core exit TCs - LESS THANREQUIRED TEMPERATURE
E-3,Step 6.g
E-3, Step 7,NOTE
To aid in identifying previously undetectedsteam generator tube failures, the widerange SG level indication should be usedif the narrow range level is off scale.
BOP Check Intact SG Levels E-3, step 7
Verify NR level - GREATER THAN 8%(42% ADVERSE CTMT)
Maintain total feed flow GREATER THAN530 gpm until NR level is GREATERTHAN 8% (42% ADVERSE CTMT) in atleast one SG.
Control feed flow to maintain NR levelbetween 8% and 50% (42% and 50%ADVERSE CTMT)
E-3,Step 7.a
E-3,Step 7.a,RNO
E-3,Step 7.b
Section 4Page 56 of 71
(EVALUA X ION GUIDE
SGTR WITHOUT PZR PRESSURE CONTROL
(,Title:
ID Number: 2K2 NRC-002 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Expected Actions Standard
US
RO
If any PZR PORV opens because of highPZR pressure, step 8.a should berepeated when pressure decreases toLESS THAN 2350 psia.
Check PZR PORVs And Block Valves
E-3, Step 8,CAUTION
E-3, Step 8
Verify PORVs - CLOSED
Verify PORV block valves - AT LEASTONE OPEN
E-3,Step 8.a
E-3,Step 8.b
E-3, Step 9CAUTION
RO
* If offsite power is lost after SI reset,manual action to restart safeguardsequipment may be required.
* DO NOT reset CDA if recirculationspray pumps are required and havenot automatically started.
RESET ESF Actuation Signals IfRequired
* SI
* CDA
* CIA
* CIB
. LOP
E-3, Step 9
Section 4Page 57 of 71
Title:EVALUATION GUIDE
SGTR WITHOUT PZR PRESSURE CONTROL
(
ID Number: 2K2 NRC-002 Revision: 0Task
A--ionTimo- II-A hAnIf Inctri irfnr Infnrmntinn/Artivitv Expected Actions StandardI 1111:V I LJ'VIVIUII --- - -..
NOTE: If crew calls anymaintenance department,IAS*MOV72 is mechanically stuckshut.
RO Establish Instrument Air to Ctmt E-3, Step 10
Check instrument air compressors - ATLEAST ONE RUNNING
START one instrument air compressor
E-3,Step 10.a
E-3,Step 10.a,RNO
NOTE: RO will be unable tocomplete this step
OPEN instrument air Ctmt isolation valves E-3,Step 10.b
US/PEO RESTORE MCC 32-3T E-3, Step 11
Check Emergency Bus 34C ENERGIZED
Proceed to the caution prior to step 12and,
WHEN
Power restored to emergency bus 34CTHEN
perform step 1 b
E-3,Step 1 la
E-3,Step I laRNO
T+ 5minutes ofrequest
EDR18
EDR44
Resets 32-3T and Using GA-1, Energize MCC32-3T E-3,Step 1l.b
clears inverter 6 alarms
Section 4Page 58 of 71
(EVALUATION GUIDE
SGTR WITHOUT PZR PRESSURE CONTROL
(
Title:
ID Number: 2K2 NRC-002 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Expected Actions Standard
US
RO
To provide adequate ECCS flow, RCSpressure should be monitored toensure that the RHR pumps aremanually restarted if pressuredecreases to LESS THAN 300 psia (500psia ADVERSE CTMT).
Check If RHR Pumps Should BeStopped
Verify RCS pressure - GREATER THAN300 psia (500 psia ADVERSE CTMT)
Proceed to CAUTION prior to step 13.
STOP RHR pumps and Place in AUTO
E-3,Step 12,CAUTION
E-3, Step 12
E-3,Step 12.a
E-3,Step 12.a,RNO
E-3,Step 12.b
US Check If Cooldown Should Be Stopped E-3, Step 13
Check Cooldown - IN PROGRESS E-3,Step 13.a
Proceed to step 1 3.d E-3,Step 13.a,RNO
Maintain core exit TCs - LESS THANREQUIRED TEMPERATURE
E-3,Step 13.d
Section 4Page 59 of 71
( (EVALUAMI iON GUIDE
SGTR WITHOUT PZR PRESSURE CONTROLTitle:
ID Number: 2K2 NRC-002 Revision: 0Task
Aq-cini--.4-. ,,-r Infe4rmnfinn/A e%4fiit Expected Actions StandardT:_ I rARA 1-^19li me Mit-vIVlalT i11LbUt.,LU Iiaillatily{zl- t
BOP
US/RO
RO
Check Ruptured SGs Pressure -STABLE OR INCREASING
Check RCS Subcooling Based on CoreExit TCs - GREATER THAN 520F (1350FADVERSE CTMT)
Depressurize RCS To Minimize BreakFlow and Refill PZR
E-3, Step 14
E-3, Step 15
E-3, Step 16
Verify normal PZR spray - AVAILABLE
Proceed to CAUTION prior to step 17.
E-3,Step 16.a
E-3,Step 16.aRNO
E-3,Step 17,CAUTION
US * The PRT may rupture if a PZR PORVis used to depressurize the RCSresulting in abnormal containmentconditions.
* Cycling of the PZR PORVs should beminimized.
US If RCPs are NOT running, the upper headregion may void during RCSdepressurization resulting in a rapidlyincreasing PZR level.
E-3,Step 17,NOTE
Section 4Page 60 of 71
Title:
ID Number:
Time
EVALUAi ION GUIDESGTR WITHOUT PZR PRESSURE CONTROL
2K2 NRC-002 Revision: 0Task
IDA/Malf Instructor Information/Activity Assign
1/0 EVENT 8: Inability to De- RO3RCS* pressurize RCSPCV456
OPEN -FALSE
Expected Actions
Depressurize RCS Using PZR PORV toMinimize Break Flow And Refill PZR
.
=Standard
E-3, Step 17
Check PZR PORVs - AT LEAST ONEAVAILABLE
Proceed to step 17.e.
Establish auxiliary spray:
1. Verify at least one Si pump - RUNNING
2. Verify at least one charging pump -RUNNING
3. CLOSE charging header loop isolationvalves (3CHS*AV8146 and3CHS*AV8147)
4. Fully OPEN charging line flow controlvalve
5. OPEN charging header isolation valves(3CHS*MV8106 and 3CHS*MV8105)
E-3,Step 17.a
E-3,Step 17.a,RNO
E-3,Step 17.e
E-3,Step 17.e.1
E-3,Step 17.e.2
E-3,Step 17.e.3
E-3,Step 17.e.4
E-3,Step 17.e.5
Section 4Page 61 of 71
(:EVALUATION GUIDE
SGTR WITHOUT PZR PRESSURE CONTROLTitle:
ID Number:
Time
2K2 NRC-002
IDA/Malf
Revision: 0Task
AssignInstructor Information/Activity Expected Actions Standard
6. Unlock and OPEN auxiliary spray valve(3RCS*AV81 45)
7. CLOSE both charging pump cold leginjection valves
8. Verify Auxiliary Spray - ESTABLISHED
* Charging header flow
* PZR Pressure - DECREASING
Perform the following:
E-3,Step 17.e.6
E-3,Step 17.e.7
E-3,Step 17.e.8
E-3,Step 17.e.8RNO
a) OPEN both charging pump cold leginjection valves.
b) CLOSE auxiliary spray valve.
c) CLOSE charging header isolationvalves.
d) Go to ECA - 3.3, SGTR WithoutPressurizer Pressure Control.
Foldout page must be open.ECA-3.3: SGTR WITHOUTPRESSURE CONTROL, Rev. 12
US EOP 35ECA-3.3Step 1, Note
Section 4Page 62 of 71
(EVALUATION GUIDE
SGTR WITHOUT PZR PRESSURE CONTROLTitle:
ID Number: 2K2 NRC-002 Revision: 0Task
AssianTime IDA/Mnlf Instructor Information/Activitv Expected Actions Standard-- -- ---1 - - -
RO Check Ruptured SG(s) Level
Check Ruptured SGs Narrow Range Level -LESS THAN 80% (54% ADVERSE CTMT)
EOP 35ECA-3.3Step 1
EOP 35ECA-3.3Step 1.a
US RCPs should be operated in the followingorder of priority to ensure optimum PZRspray flow:
EOP 35ECA-3.3Step 2, Note
First: RCP 2
Second: RCP 1 and one other RCP
RO Try To Establish Normal PZR Spray
Check RCP status - AT LEAST ONERUNNING IN EITHER LOOP 1 OR LOOP 2
Using GA-6, START the preferred RCP(s)
IF the preferred RCP(s) can NOT be started,
THEN
EOP 35ECA-3.3Step 2
EOP 35ECA-3.3Step 2.a
EOP 35ECA-3.3Step 2.a,RNO
Proceed to step 3.
Section 4Page 63 of 71
(IEVALUAI ION GUIDE
SGTR WITHOUT PZR PRESSURE CONTROL
i,
Title:
ID Number:
Time
2K2 NRC-002
IDA/Malf
Revision: 0Task
AssignInstructor Information/Activity Expected Actions Standard
RO Try To Restore PZR PORV
Establish conditions for opening a PZRPORV:
Check PZR PORV power available
Check PZR PORV block valve open
Check PZR PORV - AT LEAST ONEAVAILABLE
Proceed to step 4.
EOP 35ECA-3.3Step 3
EOP 35ECA-3.3Step 3.a
EOP 35ECA-3.3Step 3.a.1
EOP 35ECA-3.3Step 3.a.2
EOP 35ECA-3.3Step 3.a.3
EOP 35ECA-3.3Step 3.a,RNO
RO Try To Establish Auxiliary Spray
Verify SI pumps - BOTH RUNNING
EOP 35ECA-3.3Step 4
EOP 35ECA-3.3Step 4.a
Section 4Page 64 of 71
( (EVALUA-i ION GUIDE
SGTR WITHOUT PZR PRESSURE CONTROLTitle:
ID Number: 2K2 NRC-002 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Expected Actions Standard
Verify charging pumps - AT LEAST ONERUNNING
EOP 35ECA-3.3Step 4.b
EOP 35ECA-3.3Step 4.c
NOTE: These steps wereattempted in E-3. It is expectedthat the crew will not attempt themagain without a change inconditions.
Establish auxiliary spray:
Proceed to step 5. EOP 35ECA-3.3Step 4.c,RNO
CLOSE charging header loop isolation valves(3CHS*AV8146 and 3CHS*AV8147)
CLOSE charging line flow control valve
OPEN charging header isolation valves(3CHS*MV8106 and 3CHS*MV8105)
Unlock and OPEN auxiliary spray valve(3RCS*AV8145)
EOP 35ECA-3.3Step 4.cl
EOP 35ECA-3.3Step 4.c.2
EOP 35ECA-3.3Step 4.c.3
EOP 35ECA-3.3Step 4.c.4
Section 4Page 65 of 71
EVALUA I ION GUIDETitle: SGTR WITHOUT PZR PRESSURE CONTROL
ID Number: 2K2 NRC-002 Revision: 0Task
Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard
Slowly Open charging line flow control valve EOP 35to establish auxiliary spray flow ECA-3.3
Step 4.c.5
CLOSE both charging pump cold leg injection EOP 35valves ECA-3.3
Step 4.c6
Go to E-3, Steam Generator Tube Rupture, EOP 35step 17.b ECA-3.3
Step 4.d
BOP Check Intact SG Levels EOP 35ECA-3.3Step 5
Verify NR level - GREATER THAN 8% (42% EOP 35ADVERSE CTMT) ECA-3.3
Step 5.a
Maintain total feed flow GREATER THAN EOP 35530 gpm until NR level is GREATER THAN ECA-3.38% (42% ADVERSE CTMT) in at least one Step 5.a,SG. RNO
Control feed flow to maintain NR level - EOP 35BETWEEN 8% and 50% (42% and 50% ECA-3.3ADVERSE CTMT) Step 5.b
IF NR level in any intact SG continues to EOP 35increase in an uncontrolled manner, THEN ECA-3.3Go to E-3, Steam Generator Tube Rupture. Step 5.b,
RNO
Section 4Page 66 of 71
( (/EVALUAI ION GUIDE
Title: SGTR WITHOUT PZR PRESSURE CONTROL
ID Number: 2K2 NRC-002 Revision: 0Task
Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard
RO Check PZR Level - GREATER THAN 16% EOP 35(50% ADVERSE CTMT) ECA-3.3
Step 6
US/RO Check If ECCS Flow Can Be Terminated EOP 35ECA-3.3Step 7
Verify RCS subcooling based on core exit EOP 35TCs - GREATER THAN 320F (1 150F ECA-3.3ADVERSE CTMT) Step 7.a
Verify secondary heat sink EOP 35ECA-3.3Step 7.b
* Total feed flow to SGs - GREATER THAN530 gpm AVAILABLE
OR
* NR level in at least one intact SG -GREATER THAN 8% (42% ADVERSECTMT)
Check RVLMS plenum level - GREATER EOP 35THAN OR EQUAL TO 19% ECA-3.3
Step 7.c
Check ruptured SGs NR level - EOP 35
INCREASING IN AN UNCONTROLLED Step73d3MANNER
Section 4Page 67 of 71
(EVALUATION GUIDE
SGTR WITHOUT PZR PRESSURE CONTROL
A'Title:
ID Number:
Time
2K2 NRC-002 Revision: 0Task
AssignIDA/Malf Instructor Information/Activity Expected Actions Standard
OR
OFF-SCALE HIGH
RO Stop ECCS Pumps EOP 35ECA-3.3Step 8
* STOP SI pumps and Place in AUTO
* STOP all but one charging pump andPlace in AUTO
TERMINATE UPON COMPLETION OF STEP 8 OF ECA-3.3. Verify ECCS Flow Not Required.
Section 4Page 68 of 71
SECTION 4
ID Number: 2K2 NRC-002 Revision: 0
EVALUATION GUIDE
I. SUMMARY
The following Critical Tasks are covered in this exam:
TASK DESCRIPTION TASK# K/A >1= 3.0 BASIS FOR SELECTION
Isolate steam flow fromruptured S/G before atransition to ECA-3. 1 occursat step 3 of E-3 (MSIVfailed).
Identify ruptured SIG andIsolate AFW before narrowrange level reaches 29%.
E-3-A 038 EA1.324.6/4.7
Failure to isolate theruptured SG causes a lossof differential pressurebetween the ruptured SGand the intact SGs and thecrew must transition to acontingency procedure that"...necessitates the crewtaking compensating actionwhich complicates theevent mitigationstrategy...."
Failure to stop reactorcoolant leakage into aruptured SG bydepressurizing the RCSneedlessly complicatesmitigation of the event andconstitutes a "significantreduction of safety marginbeyond that irreparablyintroduced by thescenario."
E-3-C(1)
038 EA1.014.514.4
Section 4Page 69 of 71
TASK DESCRIPTION TASK # K/A >I= 3.0 BASIS FOR SELECTION
Manually start the A TrainService Water Pump beforetransitioning from E-0.
ECA-0.0--F
Failure to manually startthe SW pump under thepostulated plant conditionsmeans that the EDG isrunning without SW coolingleading to ahigh-temperature conditionthat can result in EDGfailure due to damagecaused by engineoverheating. Under thepostulated plant conditions,the running EDG is the onlyoperable EDG. Thus,failure to perform thecritical task constitutes"mis-operation or incorrectcrew performance thatleads to degradedemergency powercapacity."
Note: [*] Used to designate critical tasks. Should alsobe incorporated into column 3 or 4 ofInstructor Guide.
Section 4Page 70 of 71
SECTION 4
Title: SGTR WITHOUT PZR PRESSURE CONTROL
ID Number: 2K2 NRC-002EVALUATION GUIDE
Revision: 0
Section 4Page 71 of 71
SECTION 5
SCENP
ID Number: 2K2 NRC-002
Reactor Power:
Operating History:
RCS Boron:
Core Burnup:
Condensate Demins:
Evolutions in Progress:
Major Equipment OOS:
kRIO INITIAL CONDITIONS
REwvision: 0
100%
450 days on line
50 ppm
18,600 MWD/MTU
7 demins in service
NONE, A Train Protected, Intake Condition: GREEN
"A" PORV is inoperable due to an electrical short in thecontrol circuitry. It has been out of service for 8 hours.Electrical maintenance estimates that the valve will bereturned to service within 24 hours.
The following Tech Specs are applicable:
Tech Spec 3.4.4, action b3TRM 7.4.1 action a.1 and a.3 for both the A PORV andthe block valve 3RCS*MV8000A
Crew Instructions:
The crew is initially directed to reduce CTMT pressure to 13.80 psia by starting CTMTvacuum pump 3CVS-P1A using OP 3313E, Containment Vacuum, section 4.2.
Plant/Simulator Differences:
* Real Time and Simulator Rad Monitor historical data not valid prior to the beginning ofthis exercise.
* Auto-log terminals need to be refreshed after entry is made.
* If not using the speed dial option on the phone system, the operator must dial either #3333or #3334 to reach the person/department they desire.
* The following PPC programs do not function on the simulator:
* Samarium Follow* Xenon Follow* Sequence of Events
Section 7Page 1 of 1
SECTION 6
VALIDATION CHECKLIST
SGTR WITHOUT PZR PRESSURE CONTROLTitle:
ID Number: 2K2 NRC-002 Revision: 0
Remote functions:
All remote functions contained in the guide are certified.
Malfunctions:
All malfunctions contained in the guide are certified.
Initial Conditions:
The initial condition(s) contained in the guide are certified or have been developed from certifiedIC's in accordance with NSEM-4.02.
Simulator Operating Limits:
The simulator guide has been evaluated for operating limits and/or anomalous response.
Test Run:
The scenario contained in the guide has been test run and validated (validation sheetcompleted, next page)on the simulator. Simulator response is reasonable and as expected.
Examination Scenario Review
The dynamic examination review checklist is complete. (This is not required unless the examwill be used as an Annual Exam, then NUREG 1021 requirements apply.)
11/20/2001Technical Reviewer Date
Section 7Page 1 of 1
SECTION 7
REFERENCE AND TASK TRACKING
SGTR WITHOUT PZR PRESSURE CONTROLTitle:
ID Number: 2K2 NRC-002 Revision: 0
I. References:
OP3313E
AOP 3552
AOP*3555
AOP*3575
AOP*3576
EOP*E-0
EOP*E-3
EOP*ECA-3.3
EOP*ERGEXE
EOP* Step DOC
EOP*ERGHP
FAP06*01
NUREG*1021 rev 8
Containment Vacuum
Malfunction of the Rod Control System
Reactor Coolant System Leak
Rapid Downpower
Steam Generator Tube Leak
Reactor Trip or Safety Injection
Steam Generator Tube Rupture
SGTR Without Pressure Control
Westinghouse Owners Group Executive Document
MP3 step deviation Document
Westinghouse Owners Group Background Document
Event Assessment, Classification and Reportability
Examiners Standards
Section 7Page 1 of 1
Initial Dynamic Simulator Scenario
NUREG-1021, Appendix D, Attachment 1
SGTR WITHOUT PZR PRESSURE CONTROLTitle:
ID Number: 2K2 NRC-002 Revision: 0
I. Summary:
Facility: Millstone 3 PWR:________ Scenario No: 2K2NRC-002 Op-Test No: 2K2Facility: Millstone 3 PWR:- Scenario No: 2K2NRC-002 Op-Test No: 21<2
Examiners:_ Operators:.
Initial Conditions: IC-21; 100% power, end of life
The "A" PORV is out of service due to an electrical short in the control circuitry
Event Malf. Event Event DescriptionNo: No. Type *1 N(ALL) Reduce CTMT Pressure2 RD10- C(RO) Control Rod Position Data A Failure
593 SG03C C(ALL) Steam Generator "C" Tube Leak
3a R(ALL) Rapid Downpower due to S/G Tube Leak (AOP 3576)4 RD021 C(RO) Rod Bank CB-D Continuous Rod Insertion5 SG01C M(ALL) Steam Generator "C" Tube Rupture
ED01 Loss of Offsite Power6 SW01A C(RO) A SWP Trips
SW02C C SWP Fails to Auto Start7 MS12C C(BOP) MSIV on Ruptured S/G Fails to Close
8 I/Os: M(ALL) Inability to De-pressurize RCSPCV455PCV456IAS*V72
*( N ) ormal ( R ) eactivity ( I ) nstrument ( C ) omponent ( M ) ajor
Section 7Page 1 of 1
SECTION 8MILLSTONE UNIT 3
SIMULATOR SCENARIO ATTRIBUTES CHECKLISTFORM ES-301-4
Exam Title: SGTR WITHOUT PZR PRESSURE CONTROL
ID Number: 2K2 NRC-002 Revision: 0
Assessor: Steve Jackson
QUALITATIVE ATTRIBUTES
Y 1. The initial conditions are realistic, in that some equipment and/or instrumentation may be out ofservice, but it does not cue the crew into expected events.
Y__2. The scenario consists mostly of related events.
Y__3. Each event description consists of:
- the point in the scenario when it is to be initiated- the malfunctions(s) that are entered to initiate the event- the symptoms/cues that will be visible to the crew- the expected operator actions (by shift position)- the event termination point (if applicable)
_Y_4. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenariowithout a credible preceding incident such as a seismic event.
_Y_5. The events are valid with regard to physics and thermodynamics.
_Y_6. Sequencing/timing of events is reasonable, and allows for the examination team to obtaincomplete evaluation results commensurate with the scenario objectives.
_Y_7. If time compression techniques are used, scenario summary clearly so indicates. Operators havesufficient time to carry out expected activities without undue time constraints. Cues are given.
_Y_8. The simulator modeling is not altered.
_Y_9. The scenario has been validated. Any open simulator performance deficiencies have beenevaluated to ensure functional fidelity is maintained while running the scenario.
_Y_10. Every operator will be evaluated using at least one new or significantly modified scenario. All otherscenarios have been altered lAW Section D.4 of ES301
_Y_11. All individual operator competencies can be evaluated, as verified using form ES-301-6.
_Y_12. Each operator will be significantly involved in the minimum number of transients and eventsspecified on Form ES-301-5. (Form submitted with simulator scenarios).
_Y_13. Level of difficulty is appropriate to support licensing decisions for each crew position.
Section 8Page 1 of 2
SECTION 8MILLSTONE UNIT 3
SIMULATOR SCENARIO ATTRIBUTES CHECKLISTFORM ES-301-4
Lesson Title: SGTR WITHOUT PZR PRESSURE CONTROL
ID Number: 2K2 NRC-002 Revision: 0
Note: Following criteria list scenario traits that are numerical (QUANTITATIVE) in nature.
01. Total Malfunctions (TM) - Include EM's- 5 to 8 required Total: 8PORV failed closed, CTMT IAS valve will not open, S/G Tube Leak / Rupture, DPRIData A Failure, Continuous Rod Insertion, Service Water Pumps Fail to Auto Start,Loss of Offsite Power, MSIV Fails Closed
02. Malf s after EOP entry (EM's)- 1 to 2 required Total: 2PORV failed closed, MSIV Fails Closed
03. Abnormal Events (AE)-2 to 4 required Total: 4Service Water Pumps Fail to Auto Start, S/G Tube Leak, DPRI Data A Failure,Continuous Rod Insertion
04. Major Transients (MT)-1 to 2 required Total: 2SIG Tube Rupture / Loss of Offsite Power
05. EOP's (EU) entered/requiring substantive actions 1 to 2 required Total: 2E-0, E-3
06. EOP Contingencies requiring substantive actions [ECAs/FRs](EC) 0 to Total: 12 required
ECA-3.3
07. Critical Task (CT) - 2 to 3 required
E-3-A: Isolate feedwater flow to and steam flow from ruptured S/G beforea transition to ECA-3.1 occurs at step 3 of E-3. (MSIV fails)
E-3-C: Identify and Isolate ruptured S/G before narrow range levelreaches 29%.
ECA-O.O--F: Manually start the A Train Service Water Pump before transitioningfrom E-0.
08. Approximate Scenario Run Time: 45 to 60 min. (One scenario mayapproach 90 minutes)
09. EOP run time:
Total: 3
Total: 60 min
Total: 30 min
10. Technical Specifications are exercised during the scenario. (Y/N)_Y_
NOTES: Reactivity Manipulation: Rapid Downpower due to S/G Tube Leak
Section 8Page 2 of 2
2K2 LOUTEXAM MATERIALS
SIMULATOR EXAM
SIM-004
EXA:MINATION
08112/02 - 08/15/02
- - - - =
I
MILLSTONE NUCLEAR POWER STATION
LOIT NRC SIMULATOR EXAM GUIDE APPROVAL SHEET
Exam Title:
Revision:
ID Number:
INTER-SYSTEM LOCA
0
2K2NRC-004 (SPARE)
This document is the property of Millstone Power Station, which controls itsdistribution. Further transfer, copying, and modification of this document are
strictly prohibited without the written consent of Millstone Power Station.
-F r *VXZ
SECTION 2
SIMULATOR EXAM GUIDE
TABLE OF CONTENTS
SECTIONS LISTED IN ORDER
1. Cover Page
2. Table of Contents
3. Exam Overview
4. Evaluation Guide
5. Scenario Initial Conditions Sheet
6. Scenario Validation Checklists
7. Reference and Task Tracking
8. Scenario Attributes Checklist
Attachments
- NUTIMS Module Report
aAWLKt , a
SECTION 3
EXAM OVERVIEWTitle: INTER-SYSTEM LOCA
ID Number: 2K2NRC-004 Revision: 0
Exam Brief:
1. The plant is at 100% power, EOL steady state operations with all control systems inautomatic. The "A" PORV is out of service due to an electrical short in the control circuitry.After turnover the crew will shift running Charging Pumps as directed by the turnover per OP3304A, Charging and Letdown, Section 4.4.
After the normal evolution is complete, Power Range Nuclear Instrument (NI) Channel42 Lower Detector will fail high. Inward rod motion will occur and the appropriateannunciators will alarm. Rod Control should be placed in manual and the crew shouldrespond using AOP 3571, Instrument Failure Response. Once the failed channel has beendefeated Tave will be restored by moving the rods if necessary before they are returned toautomatic control.
Once Tech Specs have been address for the failed NI channel, a leak will develop inthe 6B Low Pressure Feedwater Heater. Feedwater Heater annunciators will alarm directingthe crew to AOP 3567, Operation with one Feedwater Heater String Isolated. The B HeaterDrain Pump will trip and the heater string will automatically isolate. The AOP responseincludes a plant downpower to 95% and verification of isolation of the heater string from theControl Room.
Once the crew has confirmed isolation of the affected LP heater, a leak (tube failure)of Reactor Plant Component Cooling Water (CCP) into the Upper Oil Reservoir of the "B"RCP will occur. CCP Surge Tank level, though slight, will discernibly decrease and, after afew minutes of leakage, an Oil Reservoir high level alarm will sound. The crew should takeaction per the ARP and AOP 3554, RCP Trip or Stopping a RCP at Power to attempt toreduce reactor power and take the affected RCP out of service. The crew may judge thatthey cannot take the plant offline quickly enough to prevent RCP damage and elect to trip theplant.
At the time of the trip, an Inter-System LOCA will occur. The crew should transitionthrough E-0 to step 27 and then to ECA-1.2, LOCA Outside CTMT. At some point in the EOPnetwork, depending on the speed of the crew, RCP trip criteria may be reached and shouldbe implemented [Critical Task]. SI will actuate or be actuated normally except that ESFBuilding Ventilation (RHR area ACUs) will fail to start. When the SI cold leg injection valve(3SIH*MV8835) is closed, the break will be isolated [Critical Task].
The scenario will be terminated upon transition to E-1, Loss of Reactor or SecondaryCoolant.
2. The SM should classify this event as a Site Area Emergency - Charlie Two due to a failureof two barriers (RCS & CTMT).
3. Plant/Simulator differences that may affect the scenario are: NONE
4. Duration of Exam: 60 minutes
SECTION 4
EVALUATION GUIDE
INTER-SYSTEM LOCATitle:
ID Number: 2K2NRC-004 Revision: 0
All Control Room Conduct, Operations and Communications shall be in accordance withMP-14-MMM.
"Review the Simulator Operating Limits(design limits of plant) and the SimulatorModeling Limitations and Anomalous Response List prior to performing this examscenario on the simulator. The evaluators should be aware if any of these limitationsmay be exceeded." (NSEM 6.02)
Section 4Page 1 of 55
SIMULATOR PROBLEMS DURING EXAMS
It is the responsibility of the Instructors in the simulator to insure that exam interruptions have aminimum negative impact on the Crew and the examinations we provide.
Be aware that at all times the Operators should treat the simulator as if it were the plant andyou too should treat it as much like the plant as possible when they are in the simulator.
As soon as the Instructors are aware of a simulator problem that will adversely affect the examin progress (computer fault, etc.) the Instructor should:
1. Place the simulator in FREEZE if possible.
2. Announce to the Crew that there is a simulator problem.
3. Request that the Crew leave the simulator control room. (The Crew should leavethe simulator for problems which involve major switch alignments).
4. Deal with the problem (reboot, call STSB, etc.)
5. After the Instructors believe the simulator is restored to service, the Crew shouldbe told how the exam will continue. If it is possible and felt to be acceptable tothe evaluators, the examination can begin where it left off with an update onplant parameters and each Crew member is prepared to restart. If theexamination will not begin where it left off, the crew should be told how andwhere the exam will begin again.
6. Once the Crew has been told how and where the exam will begin, have the crewconduct a brief so that the Instructor and evaluators can insure that the crew hasall the necessary information to continue with the scenario.
7. Once all Crew members, Instructors and evaluators are satisfied that they havethe necessary information to continue the scenario, place the simulator in RUNand announce to the Crew that you have continued the evaluation session.
Section 4Page 2 of 55
SECTIuN 4
Lesson Title: INTER-SYSTEM LOCA
ID Number: 2K2NRC-004 Revision: 0Task
Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard
Simulator Setup Instructions:
1. HANG Exam Placards on the simulator doors.
2. START the Sun Workstation.
a. IF the Sun Workstation is running THEN go to SIM ACTIVE.
3. PLACE Recorder Power to ON.
4. VERIFY that the current approved training load is loaded.
5. REMOVE the step counter OVERRIDE and allow the counters to step out during the IC reset.
6. RESET to IC-92: TEMP IC 2K2NRC-LOUT-004 (based on IC-21)
7. ADJUST the various pot settings to the valued specified by the chart in the simulator booth or Notepad for the selected IC.
8. PLACE Simulator to RUN.
9. ADJUST MWt using Turbine Load Set to 3411, (+)0, (-)3 IF using 100% power IC.
10. RESET the Plant Calorimetric at the Instructor Station PPC by Pressing "SHIFT LEFT" and "F6" simultaneously.
11. ENSURE Simulator fidelity items cleared.
a. CHECK the STEP COUNTERS at correct position for plant conditions.
b. PLACE 7 tiles under the DEMINS IN SERVICE lamacord label on MB6.
c. PLACE the Main Turbine on the LOAD LIMITER and ENSURE Standby Load Set MATCHED if conditions require.
d. PLACE the Westronic (5) and Gammametrics (2) recorders in active/run by depressing up or down arrow for each.
e. CLEAR DCS alarms on MB7 and BOP console.
Section 4Page 3 of 55
(S ( (SECTION 4
Lesson Title: INTER-SYSTEM LOCA
ID Number: 2K2NRC-004 Revision: 0Task
Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard
f. VERIFY annunciator, "COMPUTER FAILURE" (MB4C, 1-1 1), is NOT LIT.
g. ENSURE NSSS Picture 1, MODES 1, 2, 3, 4; Burnup and Cb match lesson plan AND Cb sample date < 3 days old.
1) See laminated directions on clipboard in Sim booth.
12. RESET Computer Terminals to At Power displays if 100% power IC.
a. MB2, (AY6), CVCS Data Trend, 1 minute update, CHS-F1 32 (40-120), CHS-L1 12 (40-80), CHS-F1 21 (40-80), RCS-L461 (40-80)
b. MB4, (AY1), At Power Data Trend, 15 second update, CVQRPI, (3391-3428), CVQRPHRUN (3409-3413), CVQRP (3409-3413), RCL-T412*, (585-588)
c. MB4, (AY4), NSSS Picture 1, MODES 1, 2, 3, 4
d. BOP Console (AY5A), BOP Picture 26, Circ Water
e. STA Console, (AY3), NSSS Picture 15, RCP Seals
13. RESET Rad Monitor Screen to Status Grid.
14. OVERRIDE the annunciators that will be lit longterm in the CR, (as listed in the "Lit CRP Annunciators" section of the MP3 daily Status Reporthanging near instructor booth door).
15. IF placing equipment OOS, THEN perform the necessary switch manipulations and hang appropriate tags, as required, listed under"Equipment OOS."
16. LOCK the Simulator Room front door.
17. HANG a Caution Tag on 3RCS*MV8000A stating, " 3RCS*MV8000A Closed and de-energized IAW Tech Spec 3.4.4, Action b"
Section 4Page 4 of 55
(SECTION 4
(
Lesson Title: INTER-SYSTE
ID Number: 2K2NRC-004
Time IDA/Malf
0
:M LOCA
RevieTask
Instructor Information/Activity Assign Expected Action
PLACE THE FOLLOWING EQUIPMENT OOS: STANDARD 2K2 NRC EXAM EQUIPMENT
;ion: 0
Standard
1/01/01/01/01/0
MPMa
Ma
Ma
Ma
Ma
Initial Malfunctions
(RC) 3RCS*PCV455A A PORV OPEN - FALSE(RC) 3RCS*PCV455A A PORV GREEN - FALSE(RC) 3RCS*PCV455A A PORV RED - FALSE(RC) 3RCS*MV8000A A PORV Block Valve GREEN - FALSE(RC) 3RCS*MV8000A A PORV Block Valve RED - FALSE
kLF S106A RCS to Inter-System LOCA 1kLF S106B RCS to Inter-System LOCA (isolable) 1
LLF RP11 D Failure of Automatic Actuation of ESF Bldg. Ventilation
Event Malfunctions
1LF N109B Power Range NI Channel 42 Lower Detector Fails High
IF FW13N Low Pressure Feedwater Heater E6B Leak
1LF RC14B RCP B Upper Oil Reservoir Cooling Water Leak
00%00%
BT1BT1
I 100%
100%
100%
15 second ramp
15 second ramp
No ramp
RSCU #1
RSCU #2
RSCU #3. .
Lead Examiner: Refer to the "Briefing Script for the Operational Exam" and brief the crew.
Section 4Page 5 of 55
(SECTiON 4
(
Lesson Title: INTER-SYSTEM LOCA
ID Number: 2K2NRC-004 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Expected Action Standard
T = 0 EVENT 1: Shifting ChargingPumps
OP 3304A, Charging and Letdown,Rev. 28-01
Starting/Shifting Charging Pumps OP 3304A,Step 4.4
This Section Contains EOP RelatedMaterial
[Normal Evolution] Us
US
A computer display, showing all datarelevant to the operation of the pumpbeing started, should be used.
IF the associated alternate minimumflow relief valves (3CHS*RV851OA or3CHS*RV851 OB) lift, REQUEST IST toperform required testing andinspections. (* Ref. 6.4.6)
OP 3304A,Step 4.4.1NOTE
OP 3304A,Step 4.4.1
US/ RO/ IF starting or shifting to 3CHS*P3A,PEO charging pump A, PERFORM the
following:
a) Refer To OP 3330D, "ChargingPump Cooling," and VERIFYcharging pump cooling water is inoperation for 3CHS*P3A, chargingpump A.
OP 3304A,Step 4.4.4
Section 4Page 6 of 55
(SECTIUN 4
(
Lesson Title: INTER-SYSTEM LOCA
ID Number: 2K2NRC-004 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Expected Action Standard
NOTE: Throughout this procedure,when asked for local indications, allindications are normal as perprocedure.
PEO b) For 3CHS*P3A, charging pump A,CHECK lube oil reservoir level isbetween 1/3 and 2/3 full using3CHS*LG1A, A lube oil reservoirsite glass on pump (local).
PEO
RO
RO
RO
RO
c) PLACE 3CHS*P6A, charging pumpA auxiliary lube oil pump in "AUTO,"(local).
d) To align charging pump minimumflow recirculation valves for3CHS*P3A, charging pump A,OPEN the following (MB3):
* 3CHS*MV811 1A, "RECIRC DIS"
* 3CHS*MV8110, "RECIRC HDRISOL"
e) VERIFY a flow path from one of thefollowing sources to the chargingpumps:
* VCT
* RWST
* Boric acid tanks
f) START 3CHS*P3A, "CHG PP A,"(MB3).
Section 4Page 7 of 55
( (a (SECTION 4
Lesson Title: INTER-SYSTEM LOCA
ID Number: 2K2NRC-004 Revision: 0Task
Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard
RO g) VERIFY minimum recirculation flowof 60 gpm as indicated on 3CHS-F75 (computer) or SHUTDOWNpump.
US/ RO h) IF any of the following conditionsoccur during the operation of thepump, SHUTDOWN the chargingpump:
* Pump operation changes fromsmooth to rough
* Oil temperature leaving the thrustbearing exceeds 1 550 F (local)
* Discharge pressure drops suddenlyas indicated on 3CHS*PI 117 (local)
* Auxiliary lube oil pressure dropsless than 15 psi (local)
* Pump running current exceeds88 amps (MB3)
US/ PEO i) CHECK the following parameters(locally):
Section 4Page 8 of 55
( CSECTION 4
Lesson Title: INTER-SYSTEM LOCA
ID Number: 2K2NRC-004 Revision: 0Task
Time IDA/Malf Instructor Information/Activity Assign Expected Action Standard
1) WHEN oil discharge pressure isgreater than 8 psig as indicated on3CHS*PI 1023A, VERIFYappropriate auxiliary lube oil pumpautomatically stops.
2) CHECK 3CHS-TI 1021A, auxiliarylube oil bearing outlettemperatures, are less than 1 550F(local).
3) CHECK 3CHS-PI 1023A, auxiliarylube oil filter outlet pressure,between 15 psig and 18 psig.
4) CHECK differential pressurebetween 3CHS-PI 1024A, auxiliarylube oil filter (3CHS*FLT1 1A) inlet,and 3CHS-PI 1023A, auxiliary lubeoil filter (3CHS*FLT1 1A) outlet,pressure indicators between 3 psidand 10 psid.
RO k) CHECK the following annunciators,not lit:
* MB3A 2-7, "CHARG PP A MOTORTEMP HI"
* MB3A 3-7, "CHARG PP A LUBEOIL PRESSURE LO"
Section 4Page 9 of 55
(SECTIUN 4
(
Lesson Title: INTER-SYSTEM LOCA
ID Number: 2K2NRC-004 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Expected Action Standard
* MB3A 5-9, "CHARG PP AUTOTRIP/OVERCURRENT"
* MB3B 3-1, "CHARG PP A OILCOOLER FLOW LO"
* MB3B 4-1, "CHARG PP A OILCOOLER TEMP Hi"
I) VERIFY the following chargingpump cubicle dampers positionedas required (VP1):
BOP
The ventilation supply lines to thecharging pump cubicles are isolated inwinter mode; no supply flow will occurwhen the inlet MODs are open.
* 3HVR*MOD5OA, ventilation supply,opened
* 3HVR*MOD49A, ventilationexhaust, opened
m) IF the charging pump was startedfor the purpose of shifting chargingpumps, PERFORM the following:
2) STOP the desired charging pump.
3) PLACE the applicable controlswitch to "AUTO."
OP 3304A,Step 4.4.4.1NOTE
RO
RO
RO
Section 4Page 10 of 55
(I/I.
SECTIuN 4
Lesson Title: INTER-SYSTEM LOCA
ID Number: 2K2NRC-004 Revision: 0Task
AssignTime IDA/Malf Instructor InformationlActivity Expected Action Standard
RO
BOP
4) Refer To SP 3601 F.3," RCSLeakage-Controlled Leakage toRCP Seals," and PERFORMleakage determination.
n) WHEN the applicable pump isstopped, VERIFY the followingapplicable charging pump cubicledampers positioned as required(VP1):
Us
BOP
The ventilation supply lines to thecharging pump cubicles are isolated,therefore no supply flow will occurwhen the inlet MODs are open.
1) IF charging pump 3CHS*P3B wasstopped, VERIFY the followingclosed:
* 3HVR*MOD50B, ventilation supply
* 3HVR*MOD49B, ventilation exhaust
OP 3304A,Step 4.4.4.nNOTE
US/ PEO o) For the charging pump stopped,VERIFY the appropriate auxiliarylube oil pump automatically started:
CHS PUMP LUBE OIL PUMP INDICATOR3CHS*P36 3CHS*P6B 3CHS*PI 1023B
Section 4Page 11 of 55
(SECTION 4
(
Lesson Title: INTER-SYSTEM LOCA
ID Number: 2K2NRC-004 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Expected Action Standard
T=CHSpump shiftcomplete
MALFN109B100%15secramp
RSCU #1
EVENT 2: PR N1 42 UPPERDETECTOR FAILS HIGH
AOP 3571, Instrument FailureResponse, Rev.7
US Do not leave the rod selector switch inAUTO while diagnosing a relatedinstrument failure unless the reason forrod movement is a runback.
AOP 3571Step 1CAUTION
[Reactivity Manipulation - potential] US If a reactor trip occurs, immediately go toE-0, Reactor Trip or Safety Injection.
AOP 3571Step 1 NOTE
or
[instrument Malfunction - potential] RO Determine the initiating parameterand place the affected controller inMANUAL.
AOP 3571Step 1
CREW Stabilize the plant parameters. AOP 3571Step 2
Section 4Page 12 of 55
(SECTION 4
I.
Lesson Title: INTER-SYSTEM LOCA
ID Number: 2K2NRC-004 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Expected Action Standard
Us
US
It is desired that l&C personnel trip thebistables specified in this procedure. If,during off-hours, I&C personnel are notable to trip the necessary bistables withinthe time limitations required by theTechnical Specifications, OperationsDepartment personnel may trip thebistables using the guidance providedwithin this procedure.
Perform corrective actions usingappropriate attachment.
Instrument Failure
Power Range Nuclear InstrumentChannel Failure
AOP 3571Step 3 NOTE
AOP 3571Step 3
Attachment
D
AOP 3571 Rev. 7 Attachment D US Power Range Nuclear InstrumentChannel Failure
The following annunciators aresymptoms of a PZR pressure instrumentfailure:
PRESSURIZER PRESSURE Hi
PRESSURIZER PORV CHANNELPRESSURE Hi
MB4A 3-4
M B4A 4-3
Section 4Page 13 of 55
(SECTIUN 4
(
Lesson Title: INTER-SYSTEM LOCA
ID Number: 2K2NRC-004 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Expected Action Standard
PRESSURIZER PRESSUREDEVIATION
PRESSURIZER PRESSURE LO
PZR RELIEF VALVE DIS TEMP HI
PRESSURIZER SI CHANNELPRESSURE LO
PZR REL TK TEMP HI
PZR REL TK LEVEL HI-HI/HI1/LO
PZR REL TK PRESSURE HI
PZR PRES LO
PZR PRES HI
MB4A 4-4
MB4A 5-4
MB4A 3-5
MB4A 5-3
MB4A 2-2
MB4A 2-3
MB4A 2-4
MB4F 1,2,3,4-3
MB4F 1,2,3,4-4
LOOP 1,2,3,4 OVR TEMP AT
LOOP 1,2,3,4 OVR TEMP AT
PZR PORV PRES HI
PZR PRES LO
MB4F 1,2,3,4-5
MB4F 1,2,3,4-7
MB4F 1,2,3,4-13
MB2D1,2,3,4-5
Section 4Page 14 of 55
(:SECTIUN 4
(
Lesson Title: INTER-SYSTEM LOCA
ID Number: 2K2NRC-004 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Expected Action Standard
PZR PRES HI MB2D 1,2,3-6
Failure of two or more channels of PRinstrumentation may prevent P-1 0 fromresetting when power is reduced below10%. If P-10 fails to reset, the followingautomatic reactor trip signals are lost:
1. SR HIGH FLUX TRIP (1 05 CPS)
2. IR HIGH FLUX TRIP (25%)
3. PR HIGH FLUX LOW STPT TRIP(25%)
* The reactor operator must remainalert to any power increases whichwould necessitate a manual reactortrip.
* The Gamma Metrics NuclearInstrumentation System shall beused during the reactor shutdownin lieu of the source rangechannels.
AOP 3571Attachment DStep 1CAUTION
RO Defeat the failed channel input. AOP 3571Attachment DStep 1
Section 4Page 15 of 55
SECTION 4(
Lesson Title: INTER-SYSTEM LOCA
ID Number: 2K2NRC-004 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Expected Action StandardStandard
At the detector current comparatordrawer, Turn the following switches tothe failed channel:
AOP 3571Attachment DStep 1 a
Rod Stop BypassUpper SectionLower SectionPower Mismatch Bypass.
At the comparator and rate drawer, Turnthe following switch to the failed channel:
Comparator Channel Defeat.
RO Restore TAVE - TREF error to within 10Fand Place rod control in automatic.
CREW When conditions have stabilized,observe MB board annunciators andparameters and immediately reportany unexpected or unexplainedconditions to the Shift Manager.
US Determine which Reactor ProtectionSystem bistable (s) requires tripping:
Place a check mark in the box above theappropriate channel that requires trippingon the last page of this Attachment.
AOP 3571Attachment DStep l b
AOP 3571Attachment DStep 2
AOP 3571Attachment DStep 3
AOP 3571Attachment DStep 4
AOP 3571Attachment DStep 4a
Section 4Page 16 of 55
(SECTION 4
Lesson Title: INTER-SYSTEM LOCA
ID Number:
Time
2K2NRC-004 Revision: 0Task
AssignIDA/Malf Instructor Information/Activity Expected Action Standard
[Tech Specs]
LCO 3.3.1 (FU2)
Refer to Technical Specification 3.3.1and 4.2.4.2 and 4.2.1.1.1.b.
AOP 3571Attachment DStep 4b
SURV 4.2.4.2
NOTE: 4.2.1.1.1.b. not required if thecrew removes the affected channelfrom the AFD computer per AOP3571, Att. D, steps 6 & 7
Check the existing bistable status toensure a reactor trip will not occur whenthe failed channel is tripped.
Remove the appropriate control powerfuses for the affected channel.
AOP 3571Attachment DStep 4c
AOP 3571Attachment DStep 4d
REMOTESSeecolumn 3
NOTE: When requested act as l&CTechnician and trip bistables.
REMOTES
Request the l&C Department trip theappropriate bistables using AttachmentD and Attachment S.
AOP 3571Attachment DStep 4e
RXR107
RXR35
RXR06
RXR107
Door Open
OTDT 421 C
OTDT 421 D
Door Closed
Section 4Page 17 of 55
(SECTIuN 4
!
Lesson Title: INTER-SYSTEM LOCA
ID Number: 2K2NRC-004 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Expected Action Standard
Verify the appropriate bistable statuslights are lit.
AOP 3571Attachment DStep 4f
NOTE: If at any time during theperformance of this procedure, ifasked, as Reactor Engineering or UnitManagement, advice that NI powershould be used to determine reactorpower.
US Within one hour, Determine byobservation of the associatedpermissive annunciator window (s)that the following interlocks are intheir required state for the existingplant condition (Tech, Spec. 3.3.1,Action 8):
AOP 3571Attachment DStep 5
* Rx or turbine not at power P-7(MB4D 5-3)
* Three loop permissive P-8(MB4D 3-3)
* NIS power range P-9 permissive(MB4D 6-1)
* Reactor at power P-10(MB4D 4-3).
US / Perform the following to remove theCREW affected power range input to the AFD
computer (Program 3R5):
On the plant process computer, Selectthe NSSS menu, page 2.
AOP 3571Attachment DStep 6
AOP 3571Attachment DStep 6a
Section 4Page 18 of 55
(SECTIUN 4
(
Lesson Title: INTER-SYSTEM LOCA
ID Number:
Time
2K2NRC-004 Revision: 0Task
AssignIDA/Malf Instructor Information/Activity Expected Action Standard
At the NSSS menu, Select "TiltingFactors" (F9).
Press the key (F5 through F8) thatcorresponds to the channel to beremoved.
Within one hour, if step 6 has notbeen performed, Refer to T/SSurveillance Requirement 4.2.1.1.1.b.
Request l&C Department performcorrective maintenance on failedinstrument.
AOP 3571Attachment DStep 6b
AOP 3571Attachment DStep 6c
AOP 3571Attachment DStep 7
AOP 3571Attachment DStep 8
US
US
T=NI failurecomplete andreactivitymanipulationcomplete.
MALFFW13N
EVENT #3: LP Feedwater Heater 6BLeak
RSCU #2
AOP 3567, Operation With OneFeedwater Heater String Isolated, Rev4
[Reactivity Manipulation]
CREW When removing a feedwater heaterfrom service during turbine operation,closely monitor turbine vibration,differential expansion, nuclear power,and feedwater heater temperaturesand pressures.
CREW Decrease Reactor Power To EQUALTO OR LESS THAN 95%
AOP3567Step 1CAUTION
AOP3567Step 1
Section 4Page 19 of 55
(lSECTION 4
Lesson Title: INTER-SYSTEM LOCA
ID Number: 2K2NRC-004 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Expected Action Standard
NOTE: The leak is in LP FeedwaterHeater E6B (6th Point, B Train)
CREW Identify Faulted Feedwater HeaterString
AOP3567Step 2
* Check feedwater heater levels -HIGH (with proper LCV operation)
NOTE: If PEO dispatched, reportabnormal noise and vibration
* Check feedwater heater - NOISEAND VIBRATION
* Check feedwater heaterperformance - DEGRADED
BOP OPEN Feedwater Heater BypassValve For The Affected FeedwaterHeaters
AOP3567Step 3
NOTE: This valve will be open
NOTE: This valve will be closed
For the low pressure heaters(3CNM-MOV88)
For the 1 st point heaters(3FWS-MOV17)
BOP Check 1st Point Feedwater HeaterBypass Valve (3FWS-MOV17) -OPEN
AOP3567Step 4
US
BOP
Proceed to step 7. AOP3567Step 4 RNO
Check LP Feedwater Heater BypassValve (3CNM-MOV88) - OPEN
AOP3567Step 7
Section 4Page 20 of 55
(SECTION 4
(Lesson Title: INTER-SYSTEM LOCA
ID Number: 2K2NRC-004Task
Assign
Revision: 0
StandardTime IDA/Malf Instructor Information/Activity Expected Action
US
BOP
Isolate Steam Supply and Drains ForLP Feedwater Heaters
Check affected low pressure feedwaterheater string extraction steam supplyvalves - CLOSED
AOP3567Step 8
AOP3567Step 8.a
For String A For String B For String C
3ESS-MOV29A (E2A) 3ESS-MOV29B (E2B) 3ESS-MOV29C (E2C)
3ESS-MOV38A (E3A) 3ESS-MOV38B (E3B) 3ESS-MOV38C (E3C)
3ESS-MOV47A (E4A) 3ESS-MOV47B (E4B) 3ESS-MOV47C (E4C)
BOP CLOSE valves.
BOP Check affected low pressure feedwaterheater string extraction steam drainvalves - OPEN
For String A For String B For String C 13DTM-AOV46A (E2A) 3DTM-AOV46B (E2B) 3DTM-AOV46C (E2C)
AOP3567Step 8.aRNO
AOP3567Step 8.b
3DTM-AOV47A (E3A) 3DTM-AOV47B (E3B) 3DTM-AOV47C (E3C)
Section 4Page 21 of 55
(SECTION 4
('
Lesson Title: INTER-SYSTEM LOCA
ID Number: 2K2NRC-004 Revision: 0Task
AssianTime IDA/Malf Instructor Information/Activitv Expected Action Standard
3DTM-AOV49A (E4A) 3DTM-AOV49B (E4B) 3DTM-AOV49C (E4C)
BOP
BOP
OPEN valves.
IF the low pressure feedwater heaterstring extraction steam drain valves willNOT open, THEN Open affected lowpressure feedwater heater stringextraction steam drain bypass valvesusing Attachment C.
Verify Affected SG Blowdown FlashTank Vent - CLOSED
For heater E4A3BDG-MOV21A
For heater E4B3BDG-MOV21 B
For heater E4C3BDG-MOV21 C
AOP3567Step 8.bRNO
AOP3567Step 9
BOP CLOSE valves. AOP3567Step 9 RNO
Section 4Page 22 of 55
(SECTION 4
(
Exam Title: INTER-SYSTEM LOCA
ID Number: 2K2NRC-004 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Expected Action Standard
BOP If a heater drain tank pump is stoppedwith the Main Feed System inoperation, closely monitor the mainfeed pump suction pressure, dischargepressure, and flow rate forabnormalities.
AOP3567Step 10NOTE
NOTE: See attached ARP MB6A, 5-7,to direct PEO actions on Heater DrainPump trip.
BOP Verify Affected 4th Point HeaterDrain Pump - TRIPPED
AOP3567Step 10
BOP STOP pump. AOP3567Step 10RNO
CREW Complete Isolation Of FeedwaterHeater String
AOP3567Step 11
AOP3567Step 11.a
BOP Check affected heater outlet isolationvalve - CLOSED
For string A3CNM-MOV70A
BOP
BOP
CLOSE valves. AOP3567Step 11.aRNO
Check affected heater inlet isolationvalve - CLOSED
AOP3567Step 11.b
Section 4Page 23 of 55
(SSECTION 4
(
Exam Title: INTER-SYSTEM LOCA
ID Number: 2K2NRC-004 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Expected Action Standard
For string A3CNM-MOV49A
CLOSE valves.BOP AOP3567Step 11.bRNO
NOTE: Objective of the procedure met.Consult with Lead Examiner and
proceed ahead to Event 4.
CREW Perform Local Isolation of AffectedLP Feedwater
AOP3567Step 12
US
Us
Dispatch an operator to Perform thelocal actions to isolate the affectedfeedwater heater string usingAttachment B
WHEN the local actions specified inAttachment B are complete, THENProceed to step 13
Following the performance of theproceeding steps, the affectedfeedwater heater string is sufficientlyisolated for continued power operation.
AOP3567Step 12.a
AOP3567Step 12.b
AOP3567Step 13NOTE
CREW Verify MB Annunciators AndParameters - AS EXPECTED
Immediately notify the Shift Manager ofany unexplained or unexpectedconditions.
AOP3567Step 13
AOP3567Step 13RNO
Section 4Page 24 of 55
I
SECT1UN 4(
Exam Title: INTER-SYSTEM LOCA
ID Number: 2K2NRC-004 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Expected Action Standard
CREW
CREW
US
CREW
Perform Follow-up Actions:
If desired, increase reactor power to100%
Repair affected feedwater heater string
Restore the affected 1st pointfeedwater heater to service byperforming the following:
AOP3567Step 14
AOP3567Step 14.a
AOP3567Step 14.b
AOP3567Step 14.c
Using OP 3321, "Main Feedwater,"Place the tube side of the affected HPfeedwater heater in service
Using OP 3320, "Feedwater HeaterDrains and Vents," Place the shell sideof the affected HP feedwater heater inservice
AOP3567Step 14.c 1)
AOP3567Step 14.c 2)
US Notify Plant Engineering (ISI Group)that the LP feedwater heater bypassline or the HP feedwater heater bypassline (MP3 Erosion/Corrosion Programlow usage lines) has been placed inservice
AOP3567Step 14.d
Section 4Page 25 of 55
( (SECTiuN 4
(
Exam Title: INTER-SYSTEM LOCA
ID Number: 2K2NRC-004 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Expected Action Standard
T= AOP 3567substantiallycompleteANDExaminer'sCue.
MALFRC14B100%
EVENT 4: RPCCW Leak into RCPB Upper Oil Reservoir
RSCU #3
NOTE: The reservoir high level alarmwill sound after the malfunction hasbeen in about 4 minutes.
RO Check RCS-L477A, RCP C upper oilreservoir level computer point, to confirmalarm.
OP 3353.MB4BStep 1
CREW MONITOR the following RCP Ccomputer points:
OP 3353.MB4BStep 2
* RCS-T481A, RCP C upper thrustbearing temperature
* RCS-T481 B, RCP C upper thrustbearing temperature
* RCS-T485A, RCP C upper thrustbearing temperature
RO IF at any time RCP C thrust bearing orradial bearing temperature computerpoint is greater than 1950 F PERFORMthe following:
OP 3353.MB4BStep 3
* TRIP reactor
* STOP RCP C
Section 4Page 26 of 55
(SECTION 4
(
Exam Title: INTER-SYSTEM LOCA
ID Number: 2K2NRC-004 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Expected Action Standard
* Go To E-0
US CHECK 3CCP-LI20B, RPCCW surgetank level, for indication of RPCCWleakage.
US The following steps requirescontainment entry.
CREW IF directed by the SM/US CHECK forRPCCW to RCP C lube oil leak.
US Refer to Tech Specs and DETERMINELCOs
OP 3353.MB4BStep 4
OP 3353.MB3BALARA Step 5
OP 3353.MB3BStep 5
OP 3353.MB3BStep 6
AOP 3554, Stopping an RCP atPower, Rev. 6
RO Check RCP Status - ALL PUMPSRUNNING.
AOP 3554Step 1
RO Check Reactor Power.
Verify THREE LOOP PERMISSIVE P-8annunciator (MB4D 3-3) - LIT.
AOP 3554Step 2
AOP 3554Step 2.a
NOTE: The rate at which temperatureis increasing should inspire the crewto use the Rapid Downpower
Go to one of the following to reducepower:
|e AOP 3575, "Rapid Downpower I
AOP 3554Step 2.aRNO
* OP 3204, "At Power Operation"
Section 4Page 27 of 55
(SECTION 4
(
Exam Title: INTER-SYSTEM LOCA
ID Number: 2K2NRC-004 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Expected Action Standard
AOP 3575, Rapid Downpower, Rev.7 * A CONVEX requestedemergency generation reductionshould be completed within 15minutes of notification.
AOP 3575Step 1NOTE
[Reactivity Manipulation] * If a unit shutdown is required, thetarget power level should bebetween 20% and 25% reactorpower.
* If at any time ROD CONTROLBANKS LIMIT LO - LO (MB4C 4- 9 ) annunciator is received, DONOT go to AOP 3566, ImmediateBoration. Immediately performstep 9.
CREW
US
US
US
Determine Power Reduction Rate(%/min).
Check desired power reduction rate -LESS THAN OR EQUAL TO5%/min.
Check power reduction CONVEXREQUESTED
Proceed to Step 1.d.
AOP 3575Step 1
AOP 3575Step 1.a
AOP 3575Step 1.b
AOP 3575Step 1.bRNO
Section 4Page 28 of 55
(SECTIoN 4
(.
Exam Title: INTER-SYSTEM LOCA
ID Number: 2K2NRC-004 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Expected Action Standard
CREW Determine power reduction rateusing Table.
AOP 3575Step 1.d
Total Power Change (A%)
10% 20% 30% 40% 50% 60% 70% =
15 1 3 3 3 5 5 5
30 0.5 1 1 3 3 3 3
45 0.5 0.5 1 1 3 3 3
60 0.5 0.5 1 1 1 3
Time to 75 0.5 0.5 1 1 1 1
Reduce 90 0.5 0.5 0.5 1 1 1 =
Power 105 0.5 0.5 0.5 0.5 1 1
(min) 120 0.5 0.5 0.5 0.5 1
135 0.5 0.5 0.5 0.5 1
150 0.5 0.5 0.5 0.5 0.5 =
160 0.5 0.5 0.5 0.5 0.5
US Check Rod Control In AUTO. AOP 3575Step 2
Section 4Page 29 of 55
SECTIuN 4(.
Exam Title: INTER-SYSTEM LOCA
ID Number: 2K2NRC-004 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Expected Action Standard
CREW
us
US
BOP
BOP
BOP
Align EHC Panel
Check turbine OPERATING MODE -MANUAL
Check LOAD LIMIT LIMITING light -LIT
Intermittently Press DECREASELOAD pushbutton until LOAD LIMITLIMITING light - NOT LIT
Rotate LOAD LIMIT SET adjust knobat least one full turn in raise direction
Select DECREASE LOADING RATEto ON
Select LOAD RATE LIMIT % MIN torequired power reduction rate (%min)
AOP 3575Step 3
AOP 3575Step 3.a
AOP 3575Step 3.b
AOP 3575Step 3.c
AOP 3575Step 3.d
AOP 3575Step 3.e
AOP 3575Step 3.f
If at any time the power reductionrate or target power level must bechanged, Return to step 1.
Verify Power Reduction Rate
Check power reduction rate 5% MIN
US/RO
RO
AOP 3575Step 4NOTE
AOP 3575Step 4
AOP 3575Step 4.a
Section 4Page 30 of 55
Title:
ID Number:
Time
EVALUATION GUIDE(
INTER-SYSTEM LOCA
2K2 NRC-004
IDA/Malf Instr
F
:uctor Information/ActivityTask
Assign
RO
RO
RO
RO
Expected Actions
Check power reduction - REQUIREDTO STABILIZE PLANT
Proceed to step 5.
Initiate Rapid Boration
Verify RCS makeup system in -AUTO
START one boric acid transfer pump.
OPEN emergency boration valve(3CHS*MV8104).
Verify direct boric acid flow (3CHS-FI183A) - INDICATED.
OPEN charging line flow controlvalve, to match boric acid flow(3CHS-FI 183A)
Record time boration started
Time
Energize all PZR heaters.
Revision: 0
Standard
AOP 3575Step 4.b
AOP 3575Step 4.bRNO
AOP 3575Step 5
AOP 3575Step 5.a
AOP 3575Step 5.b
AOP 3575Step 5.c
AOP 3575Step 5.d
AOP 3575Step 5.e
AOP 3575Step 5.f
AOP 3575Step 5.g
Section 4Page 31 of 55
(EVALUATION GUIDE
(..Title: INTER-SYSTEM LOCA
ID Number: 2K2 NRC-004 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Expected Actions Standard
Determine required boric acidaddition by multiplying total powerchange (A%) by 15 (gal/%) =gal.
AOP 3575Step 5.h
Us
US
BOP
Determine required time to borate bydividing required gallons of boric acidby the direct boric acid flowrate (netcharging flow rate if using gravityboration) _ min.
Check turbine load decrease - INPROGRESS OR COMPLETED.
Proceed to NOTE prior to Step 8.
The following step places one TDFW pump in manual while allowingthe other TD FW pump toautomatically unload during thedownpower.
AOP 3575Step 5.i
AOP 3575Step 5.j
AOP 3575Step 5.k
AOP 3575Step 8NOTE
NOTE: The degrading oil reservoircondition will eventually either impell theCrew to manually trip the Reactor ORthe RCP will seize and the Reactor willtrip on RCP Low Speed. It is notexpected that the crew will get muchfurther than Step 8 of AOP 3575 beforeone of these conditions occurs.
US/BOP Align One Feedwater Pump ForAutomatic Unloading
AOP 3575Step 8
Section 4Page 32 of 55
Title:EVALU~i ION GUIDE
(INTER-SYSTEM LOCA
ID Number: 2K2 NRC-004 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Expected Actions Standard
BOP Verify removing a feedwater pump AOP 3575from service during the downpower - Step 8.aDESIRED
T= MALF EVENT 4: RPCCW Leak into RCPDownpower RC14B C Upper Oil Reservoir - Ongoingunderway ongoingand reactivitymanipulationcomplete ifdone hereplusExaminer'sCue
EVENT 5: Inter-System LOCA
NOTE: US should go to "MasterSilence" before orderingreactor trip .
E-O, Reactor Trip or SafetyInjection, Rev. 21
RO
Crew
TRIP the reactor
Go to E-0, Reactor Trip or SafetyInjection.
* Foldout page must be open E-0, Step 1,NOTE
* ADVERSE CTMT defined asGREATER THAN 180 0F orGREATER THAN 105R/hr incontainment.
Section 4Page 33 of 55
Title:EVALUA) iON GUIDE
INTER-SYSTEM LOCA
ID Number: 2K2 NRC-004 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Expected Actions Standard
* The reactor can be interpreted as"tripped" when any two of threebulleted substeps of Step 1.* aresatisfied.
T= 3 minsof eventclassifiable
Floorinstructor
Prompt the SM to contact the backroom for the Shift Tech.
RO Verify Reactor Trip E-0, Step 1
* Check reactor trip and bypassbreakers - OPEN
* Check rod bottom lights - LIT
* Check neutron flux -DECREASING
Verify Turbine Trip E-0, Step 2
Check all turbine stop valves -CLOSED
E-0,Step 2.a
BOP
BOP
US
Verify Power to AC EmergencyBusses
Check busses 34C and 34D -
BOTH ENERGIZED
Check If Si Is Actuated
E-0, Step 3
E-0,Step 3.a
E-0, Step 4
RO Verify SAFETY INJECTIONACTUATION annunciator - (MB4D 1-6or MB2B 5-9) - LIT
EOP 35 E-0, Step 4.a
Section 4Page 34 of 55
(EVALUATION GUIDE
(Title: INTER-SYSTEM LOCA
ID Number: 2K2 NRC-004 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Exoected Actions StandardStandard
US Check if SI is required E-0,Step 4.a,RNO
* CTMT pressure GREATER THAN18 psia
OR
* PZR pressure LESS THAN 1890psia
OR
* PZR level LESS THAN 16%
OR
* RCS subcooling LESS THAN 32 0F
OR
* SG pressure LESS THAN 660psig
IF SI is required,
THEN
Initiate SI and Proceed to step 5.
Section 4Page 35 of 55
(EVALUATION GUIDE
(Title: INTER-SYSTEM LOCA
ID Number: 2K2 NRC-004 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Expected Actions Standard
IF Si is NOT required,
THEN
Initiate monitoring of CSF StatusTrees and Go to ES-0.1, ReactorTrip Response.
By observation of ESF Group 2 StatusPanel lights, Verify both trains of Si -ACTUATED
Manually Initiate SI.
RO
RO
RO
BOP
Verify Service Water Pumps - ATLEAST ONE PER TRAIN RUNNING
Verify Two RPCCW Pumps - ONEPER TRAIN RUNNING
Verify ECCS Pumps Running
* Check Si pumps - RUNNING
* Check RHR pumps - RUNNING
* Check two charging pumps -RUNNING
Verify AFW Pumps Running
E-0,Step 4.b
E-0,Step 4.b,RNO
E-0, Step 5
E-0, Step 6
E-0, Step 7
E-0, Step 8
Section 4Page 36 of 55
EVALUAl iON GUIDEa,
Title: INTER-SYSTEM LOCA
ID Number: 2K2 NRC-004 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Expected Actions Standard
Check MD pumps - RUNNING
BOP
BOP
Check turbine - driven pump -RUNNING, IF NECESSARY
Verify FW Isolation
* Check SG feed regulating valves -CLOSED
* Check SG feed regulating bypassvalves - CLOSED
* Check FW isolation trip valves -CLOSED
* Check TD FW pump - TRIPPED
* Check MD FW pumps - STOPPED
* Check SG blowdown isolationvalves - CLOSED
* Check SG blowdown sampleisolation valves - CLOSED
* Check SG chemical feed isolationvalves - CLOSED
Check If Main Steam Lines ShouldBe Isolated
E-0,Step 8.a
E-0,Step 8.b
E-0, Step 9
E-0, Step 10
Section 4Page 37 of 55
Title:
ID Number:
Time
EVALUAl iON GUIDEINTER-SYSTEM LOCA
2K2 NRC-004
IDA/Malf InstrTask
Assiqnuctor Information/Activity------ ZL��
Expected Actions
Check Ctmt pressure GREATERTHAN 18 psia
OR
Any SG pressure LESS THAN 660psig
Verify MSIVs and MSIV bypass valves-CLOSED
Check ESF Group 3 lights - LIT.
Check if CDA Required
Check Ctmt pressure is GREATERTHAN 23 psia
OR
Ctmt spray - INITIATED
Proceed to Step 12.
Verify CAR Fans Operating InEmergency Mode
Check CAR fan status:
* CAR fans A and B - RUNNING
Revision: 0
Standard
E-0,Step 10.a
E-0,Step 10.b
E-0,Step 10.c
E-0, Step 11
E-0,Step 11.a
E-0,Stepl 1 ,a,RNO
E-0, Step 12
E-0,Step 12.a
RO
US
BOP
BOP
Section 4Page 38 of 55
( (S (EVALUATION GUIDE
Title: INTER-SYSTEM LOCA
ID Number: 2K2 NRC-004 Revision: 0Task
Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard
* CAR fan C - STOPPED
BOP START/STOP CAR fans as E-0,necessary. Step 12.a,
RNO
RO Verify RPCCW Ctmt supply and return E-0,header isolations - OPEN Step 12.b
RO Verify Train A and B RPCCW supply E-0,and return to chill water valves - Step 12.cOPEN
RO Verify CIA E-0, Step 13
RO Check ESF Group 2 status columns 2 E-0,through 10 - LIT Step 13.a
RO Initiate CIA. E-0,
IF ESF Group 2, columns 2 Step 13.a,through 10 are NOT lit, THEN
Using Attachment A Reposition valvesas necessary for minimum safetyfunction
RO Verify Proper ESF Status Panel E-0, Step 14Indication
* Verify ESF Group 1 lights - OFF
* Verify ESF Group 2 lights - LIT
Section 4Page 39 of 55
(EVALUATION GUIDE
(Title: INTER-SYSTEM LOCA
ID Number: 2K2 NRC-004 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Expected Actions Standard
T= InitialMALF
MALFRP11D
EVENT 6: ESF Building VentilationFails to Auto Actuate
Align components for minimum safetyfunction.
E-0, Step 14RNO
RO Determine If ADVERSE CTMTConditions Exist
E-0, Step 15
* Ctmt temperature GREATERTHAN 1800 F
OR
* Ctmt radiation GREATER THAN1 05 R/hr
CREW DO NOT use ADVERSE CTMTparameters.
E-0,Step 15,RNO
RO Verify ECCS Flow E-0, Step 16
RO
RO
Check charging pumps -
FLOW INDICATED
START pumps and Align valves.
Check RCS pressure - GREATERTHAN 1650 psia (1950 psiaADVERSE CTMT)
E-0,Step 16.a
E-0,Step 16.a,RNO
E-0,Step 16.b
Section 4Page 40 of 55
(EVALUAI iON GUIDE
(Title: INTER-SYSTEM LOCA
ID Number: 2K2 NRC-004 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Expected Actions Standard
US Proceed to Step 16.d
Proceed to step 17.
E-0,Step 16.b,RNO
CREW should perform a short briefand come out of "Master Silence" atthe completion of Step 16.
E-0,Step 16.c
Check Si pumps - FLOW INDICATED
START pumps and Align valves.
Check RCS pressure - LESS THAN300 psia (500 psia ADVERSE CTMT)
Proceed to step 17.
Check RHR pumps - FLOWINDICATED.
START pumps and Align valves.
E-0,Step 16.d
E-0, Step16.d RNO
E-0,Step 16.e
E-0,Step 16.eRNO
E-0,Step 16.f
E-0,Step 16.fRNO
BOP Verify Adequate Heat Sink
Check NR level in at least one SG -GREATER THAN 8% (42% ADVERSECTMT)
E-0, Step 17
E-0,Step 17.a
Section 4Page 41 of 55
(EVALUA i ION GUIDE
Title: INTER-SYSTEM LOCA
ID Number: 2K2 NRC-004 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Expected Actions Standard
Us
BOP
US
BOP
BOP
US
BOP
Proceed to Step 17.d. E-0,Step 17.a,RNO
Control feed flow to maintain NR level- BETWEEN 8% and 50% (42% and50% ADVERSE CTMT)
E-0,Step 17.b
Proceed to Step 18. E-0,Step 17.c
Verify Total AFW Flow - GREATERTHAN 530 gpm
START pumps and Align valves asnecessary.
E-0,Step 17.d
E-0,Step 17.d,RNO
IF AFW Flow GREATER THAN 530gpm can NOT be established,
THEN
Initiate monitoring of CSF StatusTrees and Go to FR-H.1, Response toLoss of Secondary Heat Sink.
Verify AFW Valve Alignment -PROPER EMERGENCY ALIGNMENT
E-0, Step 18
Align valves E-0,Step 18,RNO
Section 4Page 42 of 55
EVALUATION GUIDEI,
Title: INTER-SYSTEM LOCA
ID Number: 2K2 NRC-004 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Expected Actions Standard
RO Verify ECCS Valve Alignment -PROPER EMERGENCY ALIGNMENT
E-0, Step 19
Align valves E-0,Step 19,RNO
US Check Plant Status E-0, Step 20
NOTE: When asked, REPORT that"all SLCRS doors indicate closed."
Verify SLCRS doors - CLOSED
Request Security Close all SLCRSdoors.
US
E-0,Step 20.a
E-0,Step 20.a,RNO
RO
RO
RO
RO
Check CONTROL BUILDINGISOLATION annunciator (MB4D 3-6) -LIT
Check if CBI is required
E-0,Step 20.b
E-0,Step 20.b,RNO
* Ctmt pressure GREATER THAN18 psia
OR
* Control Building radiation monitorin alarm
OR
Section 4Page 43 of 55
(EVALUATION GUIDE
(Title: INTER-SYSTEM LOCA
ID Number: 2K2 NRC-004 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Expected Actions Standard
RO
US
* SI manually actuated
IF CBI required,
THEN
Initiate CBI.
IF CBI is NOT required,
THEN
Proceed to Step 21.
Verify ESF Group 2 CBI lights - LIT
Align HVAC components as necessaryfor minimum safety function.
Verify control building purge supplyfan and purge exhaust fan - NOTRUNNING
Perform the following:
RO
RO
BOP
BOP
E-0,Step 20.c
E-0,Step 20.c,RNO
E-0,Step 20.d
E-0,Step 20.d,RNO
* Stop purge supply fan.
* Stop purge exhaust fan.
* Locally Close instrument airisolations
Section 4Page 44 of 55
( ~((EVALUAliON GUIDE
Title: INTER-SYSTEM LOCA
ID Number: 2K2 NRC-004 Revision: 0Task
Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard
* 31AS-V725 (CB 47' IRRstairwell)
* 3IAS-V726 (CB47' IRRstairwell)
* 31AS-V644 (CB 66' west wall)
Locally Close instrument airisolation valve for 3HVC-AOD134
BOP Control building air bank isolation E-0,valves - OPEN (after 60 seconds) Step 20.e
BOP OPEN valves E-0,Step 20.e,RNO
BOP IF at least one air bank isolation valvecan NOT be opened,
THEN
Locally throttle Open at least onepair of air bank isolation bypassvalves to maintain 0.125 incheswater at Control Building APindicator on VP1.
* 3HVC*V750 and 3HVC*V751
* 3HVC*V758 and 3HVC*V759
Section 4Page 45 of 55
(EVALUAI iON GUIDE
(Title: INTER-SYSTEM LOCA
ID Number: 2K2 NRC-004 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Expected Actions Standard
BOP STOP kitchen exhaust fan E-0,Step 20.f
E-0,Step 20.g
NOTE: When called, WAIT 3 - 5 min,Then REPORT "All Control Buildingpressure boundary doors are Closedand Dogged."
PEO Close and Dog (as applicable) ControlBuilding pressure boundary doors.
RO Check RCS Temperature E-0, Step 21
Verify RCS cold leg WR temperature -BETWEEN 5501F and 5601F
Proceed to Step 22
E-0,Step 21.a
US E-0,Step 21.b
RO Check PZR Valves E-0, Step 22
RO
RO
RO
Verify PORVs - CLOSED
iF PZR pressure LESS THAN 2350psia, THEN CLOSE PORVs.
Verify normal PZR spray valves -CLOSED
Verify PZR safety valves - CLOSED
E-0,Step 22.a
E-0,Step 22.a,RNO
E-0,Step 22.b
E-0,Step 22.c
Section 4Page 46 of 55
(EVALUATION GUIDE
(,Title: INTER-SYSTEM LOCA
ID Number: 2K2 NRC-004 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Expected Actions Standard
CREW To prevent damage to the RCPseal(s), seal injection flow should bemaintained to all RCPs.
E-0,Step 23,CAUTION
[Critical Task] RO Check If RCPs Should Be Stopped E-0, Step 23
NOTE: Depending on the pace of thecrew through the EOP network thisstep may be performed here or lateras a continuous action.
Verify RCPs - ANY RUNNING E-0,Step 23.a
BOP/RO Check If SG Secondary BoundariesAre Intact
Check pressure in all SGs
E-0, Step 24
E-0,Step 24.a
* NO SG PRESSUREDECREASING IN ANUNCONTROLLED MANNER
* NO SG COMPLETELYDEPRESSURIZED
Ensure crew request activity sampleswith HP coverage
BOP Check If SG Tubes Are Intact E-0, Step 25
RO Sample all SGs for activity E-0,Step 25.a
Section 4Page 47 of 55
( ~((EVALUATION GUIDE
Title: INTER-SYSTEM LOCA
ID Number: 2K2 NRC-004 Revision: 0Task
Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard
1. RESET SG blowdown sampleisolation
2. OPEN SG blowdown sampleisolation valve(s)
3. Request Chemistry obtain activitysamples using HP coverage
BOP Check steam generator levels - NO E-0,SG LEVEL INCREASING IN AN Step 25.bUNCONTROLLED MANNER
US Initiate monitoring of CSF Status E-0,Trees and Go to E-3, Steam Step 25.b,Generator Tube Rupture. RNO
Verify trend history and alarm status of E-0,radiation monitors Step 25.c
* Main steam line - NORMAL
* Condenser air ejector - NORMAL
* SG blowdown - NORMAL
Initiate monitoring of CSF Status E-0,Trees and Go to E-3, Steam Step 25.cGenerator Tube Rupture RNO
RO Check If RCS Is Intact E-0, Step 26
Section 4Page 48 of 55
(EVALUAI ION GUIDE
(,Title: INTER-SYSTEM LOCA
ID Number: 2K2 NRC-004 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Expected Actions Standard
* Verify Ctmt radiation using3CMS*RE22 (pre-trip) - NORMAL
* Verify Ctmt radiation usingradiation monitoring grouphistogram (CTMT) - NORMAL
* Verify Ctmt pressure - NORMAL
* Verify Ctmt recirculation sumplevel - NORMAL
RO Check for RCS Leakage OutsideCTMT
E-0, Step 27
Check Auxiliary Building and ESFBuilding radiation (radiation monitoringgroup histograms)
Verify Auxiliary Building (AUX) -NORMAL
Verify ESF Building (ESF) - NORMAL
Verify SLCRS Building (SLCRS) -NORMAL
E-0,Step 27.a
Section 4Page 49 of 55
EVALUAl iON GUIDETitle: INTER-SYSTEM LOCA
ID Number: 2K2 NRC-004 Revision: 0Task
Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard
Check for Auxiliary Building or ESF E-0,Building flooding Step 27.b
1) Verify SUMP LEVEL HI lights(MB1) - NOT LIT
* ESF PIPE TNL
* ECCS PIPE CUB
* ESF RHR CUB
* ESF RSS CUB
2) Verify Annunciator SAFEGUARDSAREA FLOODING (MB1C 2-8) -NOT LIT
IF the cause is a loss of RCS E-0,inventory outside containment, THEN Step 27.b
RNOInitiate monitoring of CSF Status Tressand Go to ECA-1.2, LOCA OutsideContainment
ECA-1.2, LOCA Outside CTMT, US Determine Procedure Entry Point ECA 1.2,Rev. 7 And Perform The Applicable Action Step 1
US * IF the LOCA is in the AuxiliaryBuilding, THEN Proceed to Step 2.
US * IF the LOCA is in the ESFBuilding, THEN Proceed toCAUTION prior to Step 3.
Section 4Page 50 of 55
( (1 (EVALUATION GUIDE
Title: INTER-SYSTEM LOCA
ID Number: 2K2 NRC-004 Revision: 0Task
Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard
US Consult with the ADTS prior to ECA 1.2,dispatching personnel to locally Step 3operate RHR System valves. CAUTION
US/RO Verify Proper Valve Alignment In ECA 1.2,ESF Building Step 3
CLOSE valves. ECA 1.2,
IF the valves can NOT be closed, Step 3 RNOTHEN Locally Close valves forminimum safety function.Verify RHR suction isolation valves - ECA 3 a
CLOSED.Step 3.a
3RHS*MV8701A
3RHS*MV8701 B
3RHS*MV8701 C
3RHS*MV8702A
3RHS*MV8702B
3RHS*MV8702C
Verify RHR hot leg injection valve ECA 1.2,(3SIL*MV8840) - CLOSED. Step 3.b
Verify Si pump hot leg injection valves ECA 1.2,(3SIH*MV8802A and 3SIH*MV8802B) Step 3.c-CLOSED.
Section 4Page 51 of 55
(EVALUATION GUIDE
(Title: INTER-SYSTEM LOCA
ID Number: 2K2 NRC-004 Revision: 0Task
AssignTime IDA/Malf Instructor Information/Activity Expected Actions Standard
US Try To Identify And Isolate Break
Turn the power lockout switch to ONfor the following valves (MB2R):
* RHR pump A cold leg injectionvalve (3SIL*MV8809A).
* RHR pump B cold leg injectionvalve (3SIL*MV8809B).
* Si cold leg injection valve(3SIH*MV8835).
CLOSE one of the following:
* RHR pump A cold leginjection valve(3SI L*MV8809A)
* RHR pump B cold leginjection valve(3SI L*MV8809B)
* SI cold leg injection valve(3SIH*MV8835)
Check RCS pressure - INCREASING
ECA 1.2,Step 4
ECA 1.2,Step 4.a
ECA 1.2,Step 4.b
T= Begins toclose 3SIH*MV8835
DELETEMALF
[Critical Task]
S106A
ECA 1.2,Step 4.c
Section 4Page 52 of 55
EVALUAI iON GUIDETitle: INTER-SYSTEM LOCA
ID Number: 2K2 NRC-004 Revision: 0Task
Time IDA/Malf Instructor Information/Activity Assign Expected Actions Standard
Perform the following: ECA 1.2,Step 4.cRNO
1. OPEN valve closed in step 4.b
2. IF all lines have been checked,THEN Proceed to step 4.d
3. Return to step 4.b
Turn the power lockout switch to OFF ECA 1.2,for the following valves (MB2R): Step 4.d
* RHR pump A(3S[L*MV8809A)
* RHR pump B(3SIL*MV88809B)
* SI injection (3SIH*MV8835)
Check If Break Is Isolated ECA 1.2,Step 5
Check RCS pressure - INCREASING. ECA 1.2,Step 5.a
Go to E-1, Loss of Reactor or ECA 1.2,Secondary Coolant. Step 5.b
TERMINATE UPON TRANSITION TO E-1, Loss of Reactor or Secondary Coolant.
Section 4Page 53 of 55
SECTION 4
ID Number: 2K2NRC-004 Revision: 0
EVALUATION GUIDE
I. SUMMARY
The following Critical Tasks are covered in this exam:
TASK DESCRIPTION
Trip all RCPs so that anOrange Path on Core Coolingbased on core exit
thermocouples (718 F) doesnot occur when forcedcirculation in the RCS stops(Small Break LOCA).
NOTE: Critical task IFconditions occur which wouldrequire the tripping of theRCPs.
TASK#
E-1 -- C
K/A >1= 3.0
002.K5.143.814.2
BASIS FOR SELECTIONFailure to trip the RCPs under thepostulated plant conditions leads tocore uncovery and to fuel claddingtemperatures in excess of 22000F,which is the limit specified in theECCS acceptance criteria. Thus,failure to perform the taskrepresents "mis-operation orincorrect crew performance whichleads to degradation of.. .{the fuelcladding} ...barrier to fission productrelease" and to "violation of thefacility license condition."Failure to isolate a LOCA outsidecontainment (that can be isolated)degrades containment integritybeyond the level of degradationirreparably introduced by thepostulated conditions. It alsoconstitutes "mis-operation orincorrect crew performance whichleads to degradation of a barrier tofission product release" andeventually "to degradedECCS.. .capacity."
Isolate the LOCA outside
containment before transition
out of ECA-1.2
ECA-1 .2-- A
E04.EA1 .33.814.0
Note: r] Used to designate critical tasks. Should alsobe incorporated into column 3 or 4 ofInstructor Guide.
Section 4Page 54 of 55
SECTION 4
Title: INTER-SYSTEM LOCA
ID Number: 2K2NRC-004 Revision: 0EVALUATION GUIDE
Section 4Page 55 of 55
SECTION 5
SCENARIO INITIAL CONDITIONS
ID Number: 2K2NRC-004 RE
Reactor Power: 100%
Operating History: 450 day on line
RCS Boron: 50 ppm
Core Burnup: 18,600 MWD/MTU
Condensate Demins: 7 demins in service
Evolutions in Progress: NONE, A Train Protected, Intaki
Major Equipment OOS: "A" PORV is inoperable due to acontrol circuitry. It has been outElectrical maintenance estimatereturned to service within 24 hot
The following Tech Specs are ai
Tech Spec 3.4.4, action b3TRM 7.4.1 action a.1 and a.3 fithe block valve 3RCS*MV8000A
wvision: 0
a Condition: GREEN
in electrical short in theI of service for 8 hours.s that the valve will beirs.
pplicable:
or both the A PORV and
Crew Instructions:
Shift running Charging Pumps to the "A" CHS pump running per OP 3304A, Chargingand Letdown, Section 4.4.
Plant/Simulator Differences:
* Real Time and Simulator Rad Monitor historical data not valid prior to the beginning ofthis exercise.
* Auto-log terminals need to be refreshed after entry is made.
° If not using the speed dial option on the phone system, the operator must dial either#3333 or #3334 to reach the person/department they desire.
° The following PPC programs do not function on the simulator:
* Samarium Follow* Xenon Follow* Sequence of Events
Section 7Page 1 of 1
SECTION 6
VALIDATION CHECKLIST
INTER-SYSTEM LOCATitle:
ID Number: 2K2NRC-004 Revision: 0
Remote functions:
All remote functions contained in the guide are certified.
Malfunctions:
All malfunctions contained in the guide are certified.
Initial Conditions:
The initial condition(s) contained in the guide are certified or have been developed from certifiedIC's in accordance with NSEM-4.02.
Simulator Operating Limits:
The simulator guide has been evaluated for operating limits and/or anomalous response.
Test Run:
The scenario contained in the guide has been test run and validated (validation sheetcompleted, next page)on the simulator. Simulator response is reasonable and as expected.
Examination Scenario Review
The dynamic examination review checklist is complete. (This is not required unless the examwill be used as an Annual Exam, then NUREG 1021 requirements apply.)
Technical Reviewer Date
Section 7Page 1 of 1
SECTION 7
REFERENCE AND TASK TRACKING
INTER-SYSTEM LOCATitle:
ID Number: 2K2NRC-004 Revision: 0
I. References:
AOP*3571
AOP*3567
AOP*3575
AOP*3554
EOP*E-0
EOP*ECA-1.2
EOP*ERGEXE
EOP* Step DOC
EOP*ERGHP
EPIP*EPIP 4400
NUREG*1021 rev 8
Instrument Failure Response
Operation with One Feedwater Heater String Isolated
Rapid Downpower
RCP Trip or Stopping an RCP at Power
Reactor Trip or Safety Injection
LOCA Outside CTMT
Westinghouse Owners Group Executive Document
MP3 step deviation Document
Westinghouse Owners Group Background Document
Event Assessment, Classification and Reportability
Examiners Standards
Section 7Page 1 of 1
Initial Dynamic Simulator Scenario
NUREG-1021, Appendix D, Attachment 1
INTER-SYSTEM LOCA
2K2NRC-004 Revision: 0
Title:
ID Number:
I. Summary:
Facility: Millstone 3 PWR: Scenario No: 2K2NRC-004 Op-Test No: 2K2
Examiners: Operators:
Initial Conditions: IC-21; 100% power, end of life
Event Malf. Event Event DescriptionNo: No. Type *1 None N(RO) Shift running CHS pumps using OP 3204A, Charging
and Letdown, Section 4.42 N109B I(RO) or Power Range NI Channel 42 Lower Detector Fails High
R(RO)3 FW1 3N C(ROI LP Feedwater 6B Heater Leak
BOP)R(ALL)
4 RC14B C(RO) RPCCW Leak into RCP B Upper Oil ReservoirR(ALL) Rapid Downpower per AOP 3575
5 S106A M(ALL) RCS to Si Inter-System LOCAS106B
6 RP11 D C(ALL) ESF Bldg Ventilation Fails to Automatically Actuate
*( N ) ormal ( R ) eactivity ( I ) nstrument ( C ) omponent ( M ) ajor
Section 7Page 1 of 1
SECTION 8MILLSTONE UNIT 3
SIMULATOR SCENARIO ATTRIBUTES CHECKLISTFORM ES-301-4
Exam Title: INTER-SYSTEM LOCA
ID Number: 2K2NRC-004 Revision: 0
Assessor: Steve Jackson
QUALITATIVE ATTRIBUTES
_Y_1. The initial conditions are realistic, in that some equipment and/or instrumentation may be out ofservice, but it does not cue the crew into expected events.
_Y_2. The scenario consists mostly of related events.
_Y_3. Each event description consists of:
- the point in the scenario when it is to be initiated- the malfunctions(s) that are entered to initiate the event- the symptoms/cues that will be visible to the crew- the expected operator actions (by shift position)- the event termination point (if applicable)
_Y_4. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenariowithout a credible preceding incident such as a seismic event.
_Y_5. The events are valid with regard to physics and thermodynamics.
_Y_6. Sequencing/timing of events is reasonable, and allows for the examination team to obtaincomplete evaluation results commensurate with the scenario objectives.
_N/A_7. If time compression techniques are used, scenario summary clearly so indicates. Operators havesufficient time to carry out expected activities without undue time constraints. Cues are given.
_Y_8. The simulator modeling is not altered.
_Y_9. The scenario has been validated. Any open simulator performance deficiencies have beenevaluated to ensure functional fidelity is maintained while running the scenario.
_Y__10. Every operator will be evaluated using at least one new or significantly modified scenario. All otherscenarios have been altered lAW Section D.4 of ES301
_Y__11. All individual operator competencies can be evaluated, as verified using form ES-301-6.
_Y__12. Each operator will be significantly involved in the minimum number of transients and eventsspecified on Form ES-301-5. (Form submitted with simulator scenarios).
_Y__13. Level of difficulty is appropriate to support licensing decisions for each crew position.
Section 8Page 1 of 2
SECTION 8MILLSTONE UNIT 3
SIMULATOR SCENARIO ATTRIBUTES CHECKLISTFORM ES-301-4
Lesson Title: INTER-SYSTEM LOCA
ID Number: 2K2NRC-004 Revision: 0
Note: Following criteria list scenario traits that are numerical (QUANTITATIVE) in nature.
01. Total Malfunctions (TM) - Include EM's- 5 to 8 required
Power Range NI Fails High, Leak in LP Feedwater Heater, RCP Hi Motor Temp (CCPLeak to Oil Reservoir), Inter-System LOCA,, ESF Auto Actuation Failure (ESF BldgVentilation)
02. Malf's after EOP entry (EM's)- 1 to 2 required
ESF Auto Actuation Failure (ESF Bldg Ventilation), Inter-System LOCA
03. Abnormal Events (AE)-2 to 4 required
Power Range NI Fails High, Operation with One Feedwater String Isolated, RCP HiMotor Temp (CCP Leak to Oil Reservoir), ESF Auto Actuation Failure (ESF BldgVentilation)
04. Major Transients (MT)-1 to 2 required
Rapid Downpower/Plant Trip, Inter-system LOCA
05. EOP's (EU) entered/requiring substantive actions 1 to 2 required
E-O
06. EOP Contingencies requiring substantive actions [ECAs/FRs](EC) 0 to2 required
ECA-1.2, LOCA Outside CTMT
07. Critical Task (CT) - 2 to 3 required
ECA-1.2 -- A Isolate the LOCA outside containment before transition out ofECA-2.1
E.1-C Trip all RCPs before Orange Path
08. Approximate Scenario Run Time: 45 to 60 min. (One scenario mayapproach 90 minutes)
Total: 5
Total: 2
Total: 4
Total: 2
Total: 1
Total: 1
Total: 2
Total: 60 min
09. EOP run time: Total: 30 min
10. Technical Specifications are exercised during the scenario. (Y/N)_Y_
NOTES: Reactivity Manipulation: Power Range High Failure/RCP High Temp
Section 8Page 2 of 2