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TROJAX NUCLEAR PLANT

1990 EMERGENCY PREPAREDNESSEVALUATED EXERCISE

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PREPARED FOR:

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PORTLAND GENERAL ELECTRIC

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ENGINEERS, ENVIRONMENTAL CO N S U LT A N TS & PLANNERS

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1.0 INTRODUCTION

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EDRILAND_OEMEIMLELECTFJCTR.OJAN NUCLEAILELANI {

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Lo2RERC EVALWLTER.ENERCISE !

1.0 INTRODECT1QS

1.1 Sthedule

1.1.1 Controller Briefing

Date: To be determined

Time:

Location: Trojan North Building IE1

1.1.2 Exercise - -

Date: Unannounced

Time: Unannounced

1.1.3 Post Drill Facility Critique

Time: Following Drill termination,

Location: In facility observed

1.1.4 Annual Exercise Critique

Date: Day following the Exercise

Time: 9:00 a.m.

Location: Visitors Information Center

1.1.5 NRC Exit Meeting>

Date: To be determined

Time:

Location: Visitors infomiation Center

1.2 EanKinatipt DJganitatimu

The following organir.ations and facilhies will participate in the Annual Exercise.

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i organitatico Enility ,

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PGE Control Room (Simulator)

Operations Support Center

Technical support Center

Company Support Center

Emergency Operations Facility

Emergency Operations Center Liaisons

Joint Information Center

One Field Team

Columbia Couty Emergency Operations Center

St. llelens EWC

Cowlitz County Emergency Operations Center

Oregon Emergency Operations Center ,



Two Field Teams

Hillsboro Assistance Center

WUhington Emergency Operations Center



One Field Team

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1.3 Pummt_

li To conduct an off-hours, unannounced Annual Exercise starting sometime

in the week of November 5,1090 between the hours of 6 PM to 4 AM,

Included is the mobilitation of Licensee, State and County support

personnel and resources to adequately verify the capability to respond to an

emergency at the Trojan Nuclear Plant.

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2. To satisfy the requirements of Title 10, Code of Federal Regulations, Part

50, Appendix E, and guidance in NUREO 0654/ FEMA REP-1, Rev.1.

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3. Reveal organizational conflicts, policy differences, and resoutce gaps. )|

4. Clarify roles and responsibilities.

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5. Provide a means to instruct the emergency response personnel about

dealing with radiological hazards and familiarize them with proc edures

they would use in an actual emergency.

6. Provide an opportunity to practice skills and improve ind.vidualperfonnance un6er varying degrees of stress. |

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7. Ensure compatibility of communications and other equipment.]

8. Allow participants to network ud improve coordination of resources with

other arencies and ctganizations,

9. To provide a means to educate and involve the public, media, and key

community organizations in emergency plmning.

1.4 Q1ciallbnicipan13.cccc

This is the overall scope of play for the 1990 Trojan Exercise. It defines the extent of

Exercise play and interaction between PGE, Oregon, Columbia County, Washington State,

and Cowlitz County,

1.4.1 InitiaWatificAtien PGE will classify the event and initiate the notification

process. The counties and states will carry out their notification schemes.

l.4.2 Activa 112n - Activation of organizations and facilities will be carried out

per the emergency plaas. Participation wPI be:

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PGE- Control Room naff

Operations Support Center staff

Technical Support Center staff

Company Support Center staff

Emergency Operations Facility staff

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PGE (Cont'd) - Emergency Operations Center liaisons

Joint Information Center staff

One field team

Oregon, Columbia County, Washington, Cowlitz County non-evaluated limited

scope. May elect to control cell most activation.

1.4.3 &cid.hionitoring The field teams will:

- Communicate with the EOF by cellular phone or 2 way radio.-

Measure gamma and beta plus ganuno dose rates, and perfonn airbome

lodir'e and particulates sampling.

Report and control their exposures.-

Supply and administer KI if the decision has been made to do so.-

The EOF will demonstrate the ability to direct and control the field teams.

1.4.4 Rosclutument - The EOF representativt:s from Oregon, Washington,

and PGE will determine offsite doses based on field team and measured

releate data. They will also demonstrate the ability to coordinate protective

action recomrnendations based on doses (if necessary).

1.4.5 HanLAutument - POE and ODOE will monitor and evaluate plantconditions. They will also coordinate protective action reconunendations

based on piant conditions (if necessary).

1.4.6 Decisielthiaking - The EOC: will discuss and make consistent protective

action decisions.

l.4.7 htblic Insimclions - Columbia County, Cowlitz County, and Oregon will'

provide coordinated instructions to the public at risk starting within 15minutes of protective action decisions. Limitation: States and counties

rnay elect to control cell this function.

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1.4.8 Enblic_Infonnatiun , All organizations will develop and distribute public |

-information on their activities. Key information will be coordinated in'

advance when practical. Otherwise, key information will be shared as soon !as possible. Oregon, Washington, Columbia and Cowlitz Counties and '

PGE will handle the questions, concems, and needs of individual members

of the public, Limitation: States and counties may elect to control cell this

function..

Hsfore Joint.infonnation CentsLUIClisEtablishd:;

Public information will be developed and coordinated by PGE, theceunties, and the states. Limitation: States and counties may elect to

control cell this function. -

After the JIC isntablishd:>

PGE:will set up and manage the JIC. Oregon and Washington may send.

representatives to the JIC. Washington news releases will be developed

and issued there Oregon news releases will continue to be developed in

the Oregon EOC and re released from the JIC. Limitation: States and

counties may elect to control cell this function.

1.5 AcInnymLAbbiniations_and Definitions"

1.5.1 Astonyms ud Abbreviations

AC Assistance Center,

ALARA As Low As Reasonably Achievable

ARM- Area Radiation Monitor (s),

ATWS Anticipated Transient Without Scram~

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BIT- Boron Injection Tank :*BOP' Balance of Plant

CAS- Central Alarm Station,

CAC Containment Ait Coolers'

CCP Coolant Charging Pump

CCW. Component Coolant Water

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CD Civil Defense

CFR- Code of Federal Regulations

CS Contairunent Spray ,

CSC Company Support Center

j. CVCS Chemical and Volume Control System - 4

DOE Department of Ene*gy

DOE IRAP DOE lnteragency Radiological Assistance Plan

EAL(s) Emergency Action Level (s)

EBS - Emergency Broadcast System

EC Emergency Coordinator -

ECCS Emergency Core Cooling System

EOC Emergency Operating Center'

EOF Emergency Operations Facility

EOP E 'ergency Operating Procedures

EPA Environmental Protection Agency

EPC Emergency Planning Coordinator'EPI-- Emergency Public Information

- EPZ Emergency Planning Zone

ERF(s) Emergency Response Facility (s)

ESF Engineered Safeguards Features

EWC Emergency Worker Center

FEMA . Federal Emergency Management Agency

FLD TMS Field Teams

. FRRP Federal Radiological Response Plan

HP llealth Physicist:

HPN Health Physics Network

lilJP llold Up Tank |lIVAC Heating, Ventilation, Air Conditioning

s INPO Institute of Nuclear Power Operations

KI Potassium Iodide 5

JIC - Joint Infonnation Center'

LABS Radiation Analysis Laboratory

p LCO Limiting Condition of Operation-

LOCA Loss of Coolant Accident,

MF; Medical Facility'MPC Maximum Permissible Concentration

NAWAS National Waming System

NRC' Nuclear Regulatory Commission

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NSSS Nuclear Steam Supply System

OSC Operations Support Center

PAG (s) Protective Action Guide (s)

PASS Post Accident Sampling System

PRM(s) Process Radiation Monitor (s)

RCCA Rod Control Cluster Assembly

RCP Reactor Coolant Pump

RCS Reactor Coolant System

RIIR Residual lleat Removal

RMT Radiation Monitoring Team

SAS Secondary Alarm System

SCP Security Control Point

SI Safety injection

SJAE SteamJet Air Ejector

SPDS Safety Parameter Display System,

SRO Senior Reactor Operator -

TBilX Themial Barrier llent Exchanger

TIC Technical information Center

TSC Technical Support Center

WGDT Waste Gas Decay Tank

WGST Waste Oas Surge Tank

OIginnizations

CLA/SKA Clark /Skamania County

COL EOC Columbia County

COW Cowlitz County

DSilS - Washington Depattment of Social and llealth Services

OEMD Oregon Emergency Management Division

LEW- Lewis County

ODOE Oregon Department of Energy

ORil 0 tonllealth DivisionPAC Pacific County

WDEM Washington Division of Emergency Management

WAK- Wahkiakum County

EMWK Emergency Workers

ARC American Red Cross

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1.5.2 Rtfinitions ,

Atta Rolliation).lenitatlARMLSystem - An instrumentation system designed to

detect and indicate abnortual radiation levels in Plant areas..

AssessmcatActions Those actions taken during or ofter an accident to obtain and

process infonnation that is necessary to make decisions to implement specific

emergency measures.

Assistancc._ftntets Facilities located outside the 10-mile plume exposure ,

Emergency Planning Zone wherein evacuees can rec-tve first aid and assistance in

obtaining food and lodging. Limited housing of evacuees is provided at assistance

centers or at nearby shelter areas.

Csmpany_._SuppstL1cnicLICS.C) POE off site facility, located . at PGB

lleadquarters in Portland, Oregon, from which PGE corporate support for Trojan

emergency actions is provided.

Cone.cths. Actions a Those emergency measures taken to ameliorate or terminate

an emergency situation in order to prevent an uncontrolled release of radioactive

material or to reduce the magnitude of a release (eg, shutting down equipment, fire

fighting, repair, and damage control),

RIlli A. supervised instruction period aimed at testing, developing, andmaintaining skills in a particular operation. A drill is often a component of an

exercise.

EmcIgency - An off nonnal situation at Trojan that might have a radiological

impact upon the public health and safety. Such situations are categorized into four

classes.

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Etnergency_Actien_LeichlEAL3) - Radiological dose rates; specific levels ofairborne, waterborne, or surf ace-deposited concentrations of radioactive materials;

or specific instrument indicatior's that are used to designate a particular class of

emergency, i.e., UNUSUAL EVENT, ALF SITE AREA EMERGENCY or'

GENERAL EMERGENCY. Each class d emergency requires prescribednotification of PGE, State, and County officials and subsequent activation of

prescribed emergency facilities.

Ernetgency_Cortdinater - The PGE individual responsible for directing on site

actions during an emergency at Trojan. The Shift Supervisor initially serves in this

position until the arrival of the Plant General Manager or his alternate. TheEmergency Response Manager eventually assumes the Emergency Coordinator

duties.

Emergency _OperationsIenters.1EOfs) - Off site facilities from which State and

County emergency direction / coordination is provided.

Einergency_Opstatiuns_Eacility_LEDE) . PGE nearsite facility from which off site

communication, dose assessment, and errergency control are provided.

Emergency _M;umingleneslEMs) - Areas for which planning is done to assure

prompt and effective actions can be taken to protect the public in the event of a

radiological emergency at Trojan. A 10 mile Emergency Planning Zone and a

50-mile Emergency Planning Zone have been designated for plume exposure

pathways and ingestion exposure pathways, respectively.

Emergency._E. piker . PGE, Federal, State, County, and oti.er personnel who

execute prescribed assessment, corrective, protective, or recovery actions.

Emergency WeIket_CenteIs Off-site facilities where off-site emergency workers

can be monitored and decontaminated. as required. Also, a place where off-site

emergency worker personnel dosimetry is controlled. Such facilities are located at

the Woodland City 11all, Cowlitt County 1-lall of Justice, and PGE's office in St.

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Escinion_Atta - Area surrounding a nuclear reactor, in which the reactor licensee j

has the authority to determine all activities including exclusion or removal of I

personnel and property from the area, as defined in Title 10, Code of Federal

Regulations, Part 100.3(a).

Exetvisc - An event that tests the integrated capability and a major portion of the

basic elements of emergency preparedraess.

EcdcraLRadiologicaLMonitoring.and_AssnsmenLCentetERhiAQ - A response

center to be established by the U.S. Department of Energy. This center will be

established outside the 10 mile planning zone. It will be the location for the

perfonnance and coordination of Federal off site radiological measurement and

assessment activities.

EcdctnLResponic_CmcLIERQ - A response center to be established by the

vederal Emergency Management Agency. This center will be established outside

the 10 mile plani.ing zone. It will be the location for the various Federal Agencies

to establish an operational base in order to facilitate the coordination and exchange

of information and response efforts among the various Federal Agencies

responding to a fixed nuclear facility incident..

Implementingl1prcdures - Specific procedures which implement the associated

emergency response plan by deliner'ing the response actions to be taken in the

event of a radiological emergency at trojan.

-Ingen81thposure Patitway - The potential pathway of radioactive materials to the

public through consumption of radiologically contaminated water and food

products.

Joint Infonnation Center GIQ - A Joint Infonnation Center is a facility serving as

a central point of contact for the news media. News media representatives will be

kept informed of activities and events concerning all emergency response efforts of

the State (s) local governments, PGE, and Federal response agencies.

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This infonnation will be made available via means such as news conferences / press

briefings / technical briefings; electronic dissemination of prepared releases; and

telephone teams w ho can be responsive to questions and answers.

Lengdenn_EincIgency._Qpsniinns - A period of time beginning when the Plant

Staff is augmented by PGE Headquaners personnel and lasting until the Plant is in

a safe shutdown condition.

Loss of CnelanLAcridenLLLOCA) A postulated accident that results from a

break in the reactor coolant pressure boundary, with a subsequent loss of reactor

coolant at a rate in excess of the nonnal operating makeup capacity.

Lorfcpylation_Zunt_fjlZ) - The area within a 2.5 mile radius of Trojan andgenerally as defined in Title 10, Code of Federal Regulations, Part 100.3(b).

Non Reilticted Alea - Any area surrounding Trojan to which access is not

controlled by PGE for purposes of protecting individuals from exposure to

radiation and radioactive materials.

OprIntionaLSSpp2tLCrnittlOSO - Trojan location where personnel required for

in-Plant emergency actions can assemble.

Elan (s) - The individual documents which describe the state of preparedness of

PGE, Oregon State, Columbia County, Washington State, Cowlitz County, U.S.

Coast Guard, and medical facilities for responding to a radiological emergency at

Trojan.

l'Itune Exoosure Pathway - The potential pathway of radioactive materials to the

public through external whole body exposure and inhalation of radioactive

materials in air.

Post-AvsidenLSMnpling System (PASS.) - A sampling system consisting of a

reactor coolant sample panel located at Elevation 45 feet of the Auxiliary Building

and a Containment atmosphere sample panel located at Elevation 93 feet of the

Auxiliary Building.I

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PluctsLarid_EffhtenL_RadiatiettMenitetSystem_ffERMS) - A Trojaninst mentation system designed to detect and indicate concentrations ofradioactive materials in Plant process and effluent streams.

helectitLAttiens . Those emergency measures taken for the purpose of

preventing or minimiting radiological exposures to persons,

hotettite_ Action _fhiidel.1EAD1) - Projected or actual absorbed doses to

individuals (general public and emergency workers), and/or Trojan Plantconditions, that serve as indicators for initiating protective actions.

ReccIrty - A period of time beginning when the Plant reaches a safe shutdown

condition, and lasting until the Plant is restored to nearly as possible to its

pre emergency condition.

Site - The area controlled by PGE and within the exclusion area boundary as

defined in Title 10, Code of Federal Regulations, Part 100.3(a).

SpeciaLEcpulaien - Groups of the public within the plume exposure EPZ who, in

the event the general public is instmeted to evacuate, may requite special

transponation or protectivs provisions due to institutional confinement or tne need

to man certain industrial plants or public utilities. Examples of such groups are

members / staff of: (1) schools and day-care centers, (2) nursing homes, (3)

hospitals, (4) retirement centers, (5) paper mills, (6) chemical plants, (7) telephone

companies, (8) large dairies, and (9) Columbia River pleasure boats andconunercial vessels.

ItdulitaLSattifiqations - The limits, operating conditions, and other requirements

imposed by the NRC on Tr.)jan operation.

ItdmitaLSuppen Center (TSO - On-site Trojan facility which provides a location

for PGE technical support of the reactet conunand and control functions of the

Control Room.

UfSAll- Updated Final Safety Analysis Repon. Trojan Nuclear Plant.

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2.0 DRILL OBJECTTVES

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PORTLAND _DENEIGLELECTRIC

TROJAN NUCLEAR PLANT

1920.NRC EY,\LUATEDlXERCISE'

20 DIMECTIEES

2.1 GenenLQbjesityc3

1. Demonstrate the adequacy of the Radiological Emergency Plan and

Radiological Response Plan Implementing Procedures.

2. Dernonstrate the adequacy of communications among emergene facilities,

off site agencies and field teams.

3. Demonstrate the ability of key personnel to make timely anel effective

decisions during a radiological emergency.

4. Demonstrate the ability of emergency facility managers to effectively

utilize the resources of their facility to accomplish the goals of the'

Emergency Plan and the Emergency Procedures. This includes

inter facility conununication, comprehensive verbal briefings of staff and

requests for assistance, as required.

5. Demonstrate the timely activation of the emergency facilities, during an

off hours, unannounced exercise.

2.2 Sec.cific_Dn-Site _Qbjtsiirca

. CDIiTROL RQQML

Demonstrate that Control Room staff can:

1. Assess plant conc'itions, classify the ernergency and make appropriatei

| protective action reconunendations.

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2. Make initial notifications of the emerger.cy to appropriate individuals and

organizations. |

3. Take conective actions to control the situation and initigate the fconsequences. :

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4. Establish conununications with the Technical Support Center and ;

Operational Support Center during the process of activation of those jfacilities.

5. Tum over communication responsibility with the Nu~ lear Regulatory# c

Conunission to the Technical Support Center when it is activated ,

i Limitation: NRC Headquarters play is at their option, t

6. Coordinate operations related tasks through the Operational Support Center

after the Operational Support Center has become operational.

7. Maintain a formallog of events for the duration of the simulated emergency 4

situation. p

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8. Demonstrate that the Shift Supervisor acting as Emergency Coordinator .

maintains overall conunand and control of the _ emergency situation until ,

._selieved of this responsibility by the Duty _ Plant General Manager in the y

Technical Support Center or the Eme.gency Response Manager in the

Emergency Operations Facility.,

E TEC11NICALJUPPORT CENTER -

- Demonstrate that the Duty Plant General Manager:

1. Obtains detailed plant and emergency status briefing from the Shift - [Supervisor;

A; 2. Assumes command anct control of the emergency situation until relieved of

this responsibility by the Emergency Response Manager. ;,,

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3. Classify the emergency if the Emergency Response Manager has not

assumed Emergency Coordinator duties at the Emergency Operations

Facility.

4. Develops Protective Action Recommendations with the Technical Support

Cente - 'tf the Emergency Response Manager has not assumed the role

of Eme.ruey Coordinator) utilizing plant conditions.

Demonstrate that Technical Support Center staff can:

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5. Adequately staff and activate the Technical Support Center within 60 |

minutes of the ALERT classification.

6. Assume responsibility for Nuclear Regulatory Commission conununication

from the Control Room on activation of the Technical Support Center.

Limitation: NRC llendquarters play is at their option. {

7. Adequately monitor the three fission product barriers.

8. Support emergency functions of the Control Room and Emergency

Operations Facility. j

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9. Perfonn analyses, monitor plant conditions and anticipate problems in

carrying out the Emergency Operating Procedures to develop plans for

corrective action.

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10. Identify tasks to be perfonned by the Operational Support Center staff.

11. Provide direction to the Control Room to have plant paging system

announcements made conceming accident status, plant status, radiological

hazards, and any on-site protective actiores.,

12. Maintain a formallog of events for the duration of the simulated emergency

situation.

13, Maintain current display of plant status.

14. Maintain current display of emergency activities.

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RPERAT10NALSMPERRT_CEtHER

Demonstrate that the Operational Support Center staff can:

1. Adequately staff and activate the Operational Suppen Center within 60

minutes of the declaration of an ALERT.

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2. Communicate and coordinate task assigrunents and Operational Support

Center activities with the Control Room and Technical Suppon Center.I

3. Assemble, brief, dispatch, communicate with, and track Operational

Support Center teams to the completion of assigned tasks.

4. Track individual Operational Support Center member doses and control

Operational Support Center personnel exposure. i

5. Maintain contamination control in the Operational Support Center,including personnel, tools, and Self Contained Breathing Apparatus (if I

lnecessary). Demonstrate that Operational Support Center radiological

habitability can be monitored.

6. Demonstrate that the Operational Support Center Supervisor can keep

personnel in the Operational Support Center informed of current plant

conditions.

PDSTACCIDENT SAMElJNO SYSIEM

1. Utilizing appropriate procedures, manipulate the PASS to collect samples

of reactor coolant and containment atmosphere. Limitation: PASS Drill

will be conducted prior to the Exercise.

2. Demonstrate proper use of procedures and equipment for maintaining

radiological safeguards and transport of samples.

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3. Demonstrate proper use of procedures and equipment for analysis of

samples.

4. Provide analytical results for use in assessing core damage and containment

integrity.

2.3 Specific _O& Site #rinLObjestiYes

EMERGEliC10PIIM1]ONS FACLLLIX

Demonstrate that the Emergency Operations Facility staff can:

1. Adequately staff and activate the facility within 60 minutes of thedeclaration of an ALERT.

2. Classify :he emergency if the Emergency Response Manager has assumed

the role of Emergency Coordinator at the Emergency Operations Facility.

3. Obtain data from the Technical Support Center as required to supplement

Safety Parameter Display System output.

4. Transmit the following infonnation with updates as required to theCompany Support Center and simulate these transmissions to the Oregon

EmerEency Operations Center, Washington Emergency Operations Center,

Cowlitz County Emergency Operations Center, Columbia CountyEmergency Operations Center and Oregon llealth:

Emergency Classification-

Plant Data Summaries-

Dose Assessment Results*

Protective Action Recommendations*

5 Provide access control at the Emergency Operations Facility.

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6. hiaintain a fonnat log of events for the duration of the simulated emergency

situation.

7. hiaintain current displays of the following information for the duration of

the emergency.

Plant Status-

Emergency Status-

Off site Protective Action Reconunendations-

Emergency Operations Center Decision maker Board-

8. Demonstrate that the llealth Physics Supervisor issues thennoluminescent

dosimeters to Emergency Operations Facility personnel upon declaration of

an ALERT.

9. Demonstrate that the Public Information Representative providesinfonnation on a continuing basis to the Joint Infonnation Center.

Demonstrate that the Emergency Response bianager:

10. Obtains a detailed plant and emergency status briefing prior to assuming

the position of Emergency Coordinator.

I 1. Can develop a Protective Action Reconunendation if the EmergencyResponse Manager has become the Emergency Coordtr%o.

EhiERG ENCY_DITJMTIONSJACLII1ROSEASSESShiELE18EA

Demonstrate that the Radiological hianager can properly:

1. Manage the dose assessment activities by maintaining proper oversight of

those activities.

Demonstrate that staff can properly:

2. Project dosage to the public via plume exposure based on calculations and

field measurement.

3555/NUCL 1429 26- - _ _ _ _ _ _ _ _ - _ - _ _ - - _-_

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|3. Use dose projection results to develop any Protective A-tion j

Recommendations required by emergency conditions. l

4. Plot field team data accurately and clearly.

5. Properly process Accident Assessment / Notification Forms and maintain

control of those fonns.

6. Obtain back-up meteorological information.

7. Make Ingestion Protective Action Recommendations and dose calculations.

IlADIOLODICALEIELD_hiONITOidNG

Demonstrate that:

1. A POE Field Tearn can be prepared to begin its monitoring activities within

60 minutes of declaration of an ALERT.

2. Field Teams can communicate with the Emergency Operations Facility

using two way radios or cellular phones and provide required information

to the Emergency Operations Facility.

3. Demonstrate appropriate equipment and procedures for letennining

ambient radiation levels.

4 Demonstrate appropriate equipment and procedures for measurement of

airborne radiolodine.

5. Field Team rnembers properly report and control their exposures,

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' 3555/NUCL 1429 2-7

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._ - -______ - ___.__ _____-_ _ _ _ ________

CQh1PANY SUPPORT CEHIIR

'Demonstrate that Company Support Center staff can:

l. Document and track requests for assistance from the Technical Support

Center, Emergency Operations Facility and other emergency centers. |i1

2. Notify specified agencies and off site groups of accident conditions. i:

3. Request and coordinate assistance as necessary from off site organizations.'

i

i

4. Periodically update the Emergency Operations Facility on the status oftoff site organizations.

?

JOINTINFORMATION Celi 1ER |

1. Demonstrate the ability to set up and staff the JIC.

2. Demonstrate the ability to communicate via the Public Infonnation Phone

with other Public Information Officers. i

.

3. Demonstrate tbr ability to coordinate the development and approval of

news releases from the JIC.

4. Demonstrate the ability to conduct news media briefings at the JIC. [.

hiEDICALEhiERGENCY DRILL (To be conducted independently) -

The Medical Emergency Drill No.1 (October 29) will: ;

1. Demonstrate ' ability of the Radiation Protection Emergency Team (RPET)

to respond *n a medical emergency involving a contaminated individual. In . .:

doing so, RPET will demonstrate its ability to: f

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1

355$/NUCL-1429 2-8

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Provide first aid to injured individuals.a.

b. Conduct surveys to detennine the extent and location ofcontamination or direct radiation being emitted from the patient,

c. Decontaminate the injured person as much as possible without

interfering with first aid priorities. antrol any contamination 1

which cannot be removed.I

d. Obtain the ir. formation necessary to determine the extent of the

injured person's expecure.

Prepare the patient for ambulance transportation,c.

f. Dispatch a RPET member to accompany the patient to the hospital

to assist the ambulance and hospital staffs with radiological services,,

g. Provide complete and accurate patient status infonnation in astandardized fonnat to the receiving hospital.

2. Demonstrate the ability of Control Room Shift Supervisor to respond to a

medical emergency involving a contaminated individual. This will include:

a. Receipt and disposition of originating casualty report,

b. Activation of the Radiation Protection Emergency Team.

c. Notification of the Columbia County Communications Agency

(C-COM).

d. Notification of the Medicalliealth Physicist.

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3555/NUCL-1429 2-9

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3. Demonstrate the ability of Columbia County Emergency ServiceOrganizations to respond to a medical emergency involving a contaminated

individual at the Trojan site, including: *

Dispatch of ambulance service by C COM.a.

b. Timely arrival of the ambulance on site.

4. Demonstrate the ability of PGE security to rapidly process an ambulance

through the protected area boundary.

5. Demonstrate the ability of the ambulance crew and the RPET to transpon a

contaminated injured person to the hospital.

6. Demonstrate the adequecy of hospital facilities and procedures for

rece:ving, handling and treating contaminated injured individuals. In doing

so, the hospital will demonstrate:

a. Availability of procedures and properly trained staff for dealingwith radioactive contamination,

b. Availability of necessary supplies and equipment including survey

meters, anti contamination clothing and decontamination supplies.

c. Interaction with Medical Health Physicist and RPET member,allowing either of these individuals to take an assertive role in

preventing cross contamination.

Medical Emergency Drill No. 2 (October 30) will:

1. Demonstrate the adequacy of hospital facilities, equipment and procedures

; for handling and treating contaminated injured individuals. In doing so, the

hospital will demonstrate:

i! a. Availability of procedures and properly trained staff for dealing

with radioactive contamination.

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l3555/NUCL-1429 2-10

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meters, anti contamination clothing and decontamination supplies,

c. Interaction with Medical llealth Physicist and RPET member,

allowing either of these individuals to take an assertive role in

preventing cross contamination.

2. Demonstrate the adequacy of vehicles, equipment, procedures and'

personnel for transporting contaminated injured individuals.


1. Demonstrate the adequacy of hospital facilities, equipment and procedures

for handling and treating contaminated injured individuals. In doing so, the

hospital will demonstrate:

a. Availability of p. ;cedures and properly trained staff for dealing

with radioactive contamination.


meters, anti-contamination clothing and decontamination supplies.

2.4 speting QftSittDLitsjitts

Participation by Oregon, Columbia County, Washington State and Cowlitz County is

intended for training purposes only' as Federal Emergency Management Agency (FEMA)

evaluation will not take place for this exercise, As such, formal objectives are not included in

this section.

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3555/NUCL 1429 2-11

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3.0 DRILL GUIDELINES

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PORTLAND.OENERALELECTRIC

TROJAN NUCLEAILELANl.

IS20ERC.EYALUAIEDlXERCISE

3.0 GUIDELINES

3.1 DrnentLCtuidelines

1. The Exercise shall be conducted in real time with the following exceptions:

Counting time for samples will be reduced for Exercise timea.

compression purposes.

2. Only one Portland General Electric off site monitoring team will be used.

3. No on site or off site evacuations will be conducted.

4. The scenario will not include injured or contaminated workers on-site. This

will be demonstrated in a separate drill.

5. A Portland General Electric Master Controller will be assigned to designate

the beginning and termination of the exercise to ensure that the exercise

proceeds in the manner that achieves the above objectives.

6. Use of the siren portion of the Trojan Site Waming System will besimulated. The public address portion of the system will be used.

7. On site accountability will not be demonstrated.

3555/NUCL 1429 3-1

_

8. Objectives and on site actions will be demonstrated in as realistic a manner

as possible based on actual scenano events. All Exercise participants will

don anti-contamination clothing, use respirntory equipment, set up radiation

barriers and follow procedures as required by the scenario.

-

9. No plant systems will be manipulated.'

10. Identification of Participants, Controllers, Evaluators and Observers.

.

Ann bands will be used to identify Drill participants, controllers and

evaluators.

Arm bands will be distributed by the controllers to participant.

a. Ann band color code:

PGE participant: Red

Controller: Yeilow

Facilitator: Orange

Observer: O*een

b. Emergency Operations Facility PGE and state participants will be

issued a participant badge.

3.2 Obsen.cLGuidelines

1. The event times and scenario are crnfidential and should be kept so during

the Exercise. Do not discuss these with the participants.

2. Observers should not participate in the Exercise, nor interfue in the actions

taken by the Exercise Participants, Controllers or Evaluators.

3555/NUCL-1429 3-2

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3. Identification badges / hats /arrn bands /etc. are to be worn visibly by the

Observers. Identification devices should be returned at the end of theExercis4 or critique. Identify your self to the Exercise Controllers.

4. ' Questions snould be directed to Controllers, not Participants.

5. Observers inside the Radiologically Controlled Area (RCA) shall adhere to

all nonnal radiological control practices.

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3555/NUCL-14.'9 3-3

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3.3 E#1icipanlink' dines

- All Participants 9 it st the leaders of the Participant groups) must read andfollow the rules gn -low. This is important to the successful demonstration of

;- emergency response capabilities.

1. CONTROI.IERS serve an active role in the Exercise by providingmessages or instructions to the participants. They may also serve to prompt

or initiate certain actions to assure continuity of the events described in the

Exercise scenario. They also serve as EVALUA1DRS, noting all actions,

both good and bad.

2. EVALUATORS will be evaluating players in each facility and will note all

actions, good and bad. They will be the main source of input to the

Exercise critiques.

3. The Master Controller ensures that the overall progresaion of events occurs

as designed.

4. Identify yourself by name and function to the Exerci'e Coatrollers andEvaluators,

t

5. Play out all actions, as much as possible, in accordance with the emergency

plan and procedures as if it were a rect emergency.

6. Identify your actions te the Centroller, State whether you are going to play

them out or simulate them. It is recorrsunded that you play out youractions as much as possible to convincingly demonstrate the properemergency response.

7. If you are in doubt, ask the Controller for clarification. The Control!er will

not prompt or coach you.

8. Periodically speak out loud, identifying your key actions and decisions to

the Controllers and Evaluators. This may seem artificial, but it will assist

in the evaluation process and is to your benefit.<|

3555/NUCL-1429 3-4

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9. Any1 messages transmitted over non-dedicatcd communication lines or

: radics shall be preceded and followed by the statement that "This.ittDrill".

.

10. . You may play as if radiation levels are actually pres:nt, in accordance with -.

the infonnation 'you have received. Unless. otherwise specified, this will- require normal radiological control measures. including the wearing of .

protective clothing. .. ;.

11. Non-Participants are exempt from acting c., radiation levels specified for

the emergency Drill. However, normal radiological control practices shall j'

be followed throughout the course of the Drill.,

12. Use of the Emergency Broadcast System and Emergency Planning Zone

Sirens will be SIMULdLTER.

13. Plant and rachological parameters will be avaller le on SPDS and driven by ,

the simulator. These parameters will be available in the Control Room, the

Technical Support Center and the Emergency Operations facility.

14. Should the siraulator crash, only selected parameters and readings will be

provided. The selected infonnation will be sufficient to make decisions in j

accordance with plans and procedures. ,

*

15. mO NOT BECOME OVERLY CONCERNED WITH THE MECHANICSV OF THE REACTOR OR 'THE CAUSE OF. THE ACCIDENT - THIS

. EXERCISE IS DESIGNED TO TEST PLAf C OID PROCEDURES AND7 ,

'A IS NOT' CONCERNED WITH ES TABLISHING THE PROBABILITY,

| FEASIBILITY OR DETAILED MECHANICS- OF THE SIMULATED4

ACCIDENT,a

,

16. There will be one or more Controllers at each important location.$ Controllers will provide information and clarification on which actions are

to be cimulated or are outside the scope of this Exercise in order to keep the

Exercise progressing in accordance with the scenario. Controllers will also

observe all aspects of the Exercise to prepare an in-house evaluation of

plans, procedures and training.

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3555/NUCL-1429 ' 3-5,

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17. If, during any part of the Exercise, you are having trouble accomplishing

your required duties, confusion arises, or clarification is necessary, ask the

Controller. Controller assistance or clarification does not necessarily imply

failure on your part. The Controller will know the limitations ofinformation that may be provided to you, and will assist you only to the

extent necessary.

18. Keep a list of the items which you feel will improve your plans andprocedures. Complete the Participant Evaluation Form that will be handed

out near the end of the Exercise. Provide these to nor Lead Controller.

Remember, one of the main purposes of the Exercise is for YOU, the

participant, to assure yourself that you are adequately prepared. A.us for

improvement or lessons learned, when identified, will improve your overall

emergency planning end preparedness.

19. . Any Participants outside the plant property who encounter members of the

news media during the Exercise should avoid responding to any questions

regarding the simulated events or the success of the Exercise. All press

inquiries should be directed to the Joint Information Center,

20. Do not take actions that would result in actual alterations of valve and

switch positions in response to scenario simulations. Any event oroperation outside the scenario that results in an actual or potential danger to

plant operation or safety will take precedence over Exercise activity.

Should an actual operational requirement for action occur duiing the

Exercise, the Exercise activity will be suspended or cancelled at thediscretion of the Shift Supervisor and Master Controller.

21.- The Control Room phone number for participants' use during the Dn!! isext. 7256.

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3555/NUCL-1429 3-6

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)1%RTICIPANT EVALUATION FORM -

;NAME: DATE:

FACIL c ': -

EMERGENCY RESPONSE POSITION:

|1. Did Drill adequately test the procedures? YES _ NO _ -!(if NO, then please conunent below. Also indicate any suggested improvements).

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= 2. Were the procedures and their accompanying tasks realistictdly implementable? YESNO _. (if NO, then please comment below. Also indicate any suggested iniprovements).

,

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3. Are facilities and equipment adequate? YES ' NO (If NO, then please commentbelow. Also indicate any suggested improvements)."

.

+

4. 'Did ht e Drill provide sufficient training for you to' accomplish your task (s)?. YES rNO ._ (If NO, then please conunent below. Also indicate any suggested improvements),

n. .-,

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5. What is .your .overall evaluation of this Drill. GOOD FAIR POOR-(Please comment below regarding your evaluation and any suggestions for improvement

~

you wish to make).m.

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3555/NUCL-1429- 3-7' '

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3.4 - ExuchclitgentimutniRestan

in the event of a problem arising during the course of the Exercise which requires

the attention of Exercise participants to assure safe operation of the plant,it may be'

necessary to suspend Exercise activities. The decision to suspend Exercise

activities shall be made by the Duty Plant General Manager, in the event this

occurs, the Duty Plant General Manager should infomi the Master Controller in the

Emergency Operations Facility.

The Master Controller will then take the following action:

1. IIe. will infonn all other Contro!!ers of the suspension and direct them to

advise the players.f

2, He will monitor the situation.

3. lie will consult with the Dott Plant General Manager to detemiine if the

players should be released for the remainder of the day or to stand by to-

resume Exercise activities.

An Exercise re-start time should be established as soon a= possible by the Duty

Plant General Manage- Once a time is established, the Master Controller will

advise all Contrc'.;crs. If time pennits, key Controllers will assemble to review the

situation a..e to establish the point in the scenario where the Exercise will resume.

It may be necessary to conduct this review by telephone in which case the Master

Controller will inform the Controllers of the restart time and the point at which

play will resume.

The Controllers will be instructed to brief the players on the status of the scenario

at the time play was suspended and of the time the Exercise will remme. The.

Exercise ti will then be picked up at the appropriate point and play will-

continue.

If it is necessary to suspend L.ercise activities until the following day, Controllers

will assemble to discuss the resumption of the Exercise.

|

3555/NUCL-1429 3-8 l

PORTLAND GENERAL ELECTRIC COMPANY

TROJAN NUCLEAR POWER PLANT

EMERGENCY PREPAREDNESS DRILL AND EXERCISE PROGRAM

'1990 NRC EVALUATED EXERCISE

__ _ _ - _ _ _ _ _ _ . _________-_ - __

h

TABLE OF CONTENTS

. ...

Eage-PART1 GENERALINFORMATION

1.0 INTRODUCTION : 1-1

1.1 Schedule .1!

1.2 Participating Organizations 121.3 Purpose ' l3-1.4 Overall Partici 3 ant Scope 1-4 |

1.5 Acronyms Ab areviations and Definitions 1-7 1

~2.0 DRILL OBJECTIVES 2-1.2.I' General Objectives

.

2-1. 2.2 Spdfic On site Objectives 2.I2.3 Specific Off site / Joint Objectives 2-72.4 - Specific Off-Site Objectives 2-12

3.0 DRILL GUIDELINES - 3-13.1 General Guidelines - 3-1 -3.2 . Observer Guidelines : 33

' 3.3 - Participant Guidelines 3-43.4 - - Exercise Suspension and Restart 3-8-

4.0 CONTROLLER INFORMATION = '414.1' Controller Guidelines 4-1,

4.2 Controller Organization 4-4.4.3 Evaluation Checklists - 4;5

- ' PART II CONTROLLED INFORMATION

5.0 DRILL SCENARIO 5-15.l; Narrative Summary. 5.1-15.2 ' Sequence of Events 5.2-15,3 Scenario Controller Guide 5.3-1

6.0 . MESSAGES 6 1.

7.0 PLANT PARAMETEP" 7-!7.1 - Plant Parametei ammary 7.1-1

- 7.2 Plant Parameter Data ' ' - 7.2- 1 -7,3 SPDS Data- 7.3-1

^

.-8.0 RADIOLOGICAL DATA8.1- Radiation Monitor Summary 8.1-18.2 Radiation Monitots 8.2-1

- 8.3 Count Room Data 8.3-18.4 In Plant Radiological Data . 8.4-1 -8.5 On-Site Radiological Data'. ' 8.5- 1

8.6 Off-Site Radiological Data 8.6-1

3555/NUCL-1429 -i-

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TABLE OF CONTENTS

Page

- 9.0 METEOROLOGICAL DATA9.1 Meteorological Data Summary 9.1 19.2 Meteorological Data 9.2-1

.

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3555/NUCL-1429 -li-

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PARTI

GENERAL INFORMATiON

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a,,m_A 4.2 .- AWM 4 ,.4- b m,s.g--u,-. J- J.. ,- a, * - . A4 -44 4 .A e e__m- " pag e _ B__a.A _4h4& M 4dA-.ea. J.W.->N?-,7ung.3

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4.0 CONTROLLER INFORMATION.

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PORTLAND GENERAL ELECTRIC

1XOJARM1.!CLEAILI1AMI

.l220 NRC EVALUATED EXERCISE

4.0 COMROLLEILINEQRMATION

4.1 ContmileL9uidelines

1. All Exercise Controllers shall pre-position themselves at least thirty (30)

minutes prior to facility activation.

2. Prior to Exercise commencement, all Exercise telecomrnunications will be

tested to ensure satisfactory conununication between the Master Controller

and other participating Controllers.

3. All Controllers will comply with instructions from the Master Controller,

4. All Controllers shall synchronize their watches to ensure that messr4 and

time-related plant and radiological data are delivered on *une. The

goveming time is that shown on the clock in the Control Room.

5. Read the Participant Guidelines.

6. Each Controller will have copies of the messages controlling the process of

the Exercise scenario. All messages are noted with a number.

7. Unless otherwise instructed by the Master Controller, all messages shall be

issued at their designated times. Time-related plant parameters and

radiological data should be issued at the designated time by the appropriate

Controller. Make sure the participants understand the message.

8. Issue contingency messages only if required to keep the play on schedule

(as indicated on contingency message instruction).

3555/NUCL-1429 41

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9. Call the Master Controller immediately for advice if in doubt about what to

do.

10. Allow the Participants reasonable flexibility to do their functions anddemonstrate their skill, knowledge and initiative.

I 1. Call the Master Controller immediately for advice if the Participants depart

significantly from scenario script. If necessary, intervene with Participant

action and put piey back on track.

12. Stop play and notify the Master Controller if plant or personnel safety is

jeopardized.

13. Do not guide Participant's actions by offering suggestions, reminders or

instmetions.

14. Controllers shall not provide infomiation conceming the scenario events or

scenario data in advance of the times noted on the message or data sheets.

15. Some Participants may insist that certain ponions of the scenario areunrealistic. Lead Facility Controllers will clarify any questions that may

arise during the Exercise.

16. Each Controller will take detailed notes regarding the progress of the

Exercise and the responses of Participants. All notes should be retained for

the purpose of preparing a written critique of the Exercise. For those

purposes, Contmller Observation Sheets and Evaluation Material are

included in this Exercise scennio manual.

17. Non Participants are exempt from acting on simulated radiation levels

specified for the emergency Exercise. However, alLnennattadiological

control pra.ctitruhall be followed throughout the course of the Exercise.

555/NUCL-1429 4-2

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18; - Controllers should ensure that contact between Participants and Observers ,

(Visitors) is minhnized. This; may include the -establishment of visitor. .j..

. areas in emergency response ~ facilities. )-

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19. Following the tennination of the Exercise, each Facility Lead Controller, *

q = will- hold a critique of the Exercise activities at his assigned emergency

.esponse. facility or with the field team to which he'is assigned. ' Thiscritique should last approximately thirty (30) minutes.y

.. . tl' 21. All Controller notes, completed evaluation material and attendance sheets-

'

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should be forwarded to the Facility Lead Controller 'at the end of 'theFacility Critique. [

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4.2 ControlkLQIganitation

iController . TelephoneM ubsi; Assignment No. _HaincL._

C-1 TSC Controller_

4626 Eric SchmiemanC2 Control Room _ Controller (Simulator) 7777 Jim Connolly

~C-2a Control Room Lead Controller (Simulator) Doug Wo41ein'

C 2b Simulator Operator Training Staff- .C 3 - . Security. 4450 C.Cor.C-4 OSC Lead Controller 4218 Chris McKeownC-4 a - OSC Team Controllers (9) - John Purcell

.' C-4b Terry NicholsonC-4c : Monty HughsC-4d . . Dale Spicer.

C-4e Oreg ZielinskiC-4 f Terry MooreC-4g (TBD)C-4h P.C. MooreC-41 J.A. VanWinkleC-5 EOF Lead Controller / Master Controller 4336 Michael O' HareC-Sa EOF Dose Assessment Paul JonesC-6 Company Support Center 83-1000 Randy llansellC-7 . PGE Environmental Monitoring Team (TBD)

EvaluatorsJerry Thale (Rover)

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3555/NUCL-1429 4-4+

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: 41 ' Eyaluation Checklista - !

In addition to taking detailed notes, each Controller should complete the applicable

Evaluation Checklist (s) contained in this section of the Exercise Scenario Manual.'

i

The completed Evaluation Checklist (s) will then be utilized to document that the--i

- various Exercise objectives set forth in Section 2.0 were met -and that any _ 7

requirements for corrective actions are identified. !,.s

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' KEY TO EVALUATION CliECKLISI i

!!

.M Objective Met-

b'

N;: . Objective Not Met -:

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NO Objective Not Observed--

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ERRTLAND GENEltALELECTRIC COMfANITRO)AN NUCLEAR POWER PLANT--

'e 1990 EMERGENCY _ PREPAREDNESS DRILL AND EXERCISE PROGRAM-

CONTROL ROOhiEYALUATION.EORM

PART L

DENEllALO.BJECTIVES

Cude_One

-!"I, Demonstrate the adequacy of the Radiological Emergency M N NO NA

Plan and Radiological Response Plan Implementing Procedures.

COMMENTS:i

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: 2. Demonstrate the adequacy of communications among emergency M N' NO NAfacilities, off site agencies and field teams.

COMMENTS: -__

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3. | Demonstrate the ability of key personnel to make timely- M N' NO' NA 1

and effective decisions during a radiological emergency 1

COMMENTS:

KEY''__ _" :M Objective Met -,

N 1. -- Objective Not MetNO - Objective Not ObservedNA - Not Applicable:-

3555/NUCL-14'.9 46

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CONTRQJ ROOM EMALL%DQEffRM (ConGD

L%RIL

DENEML.ODJECTIVESCirrit.One

4. Demonstrate the ability of emergency facility managers to M N NO NA

effectively utilize the resources of their facility to

accomplish the goals of the Emergency Plan and the

Emergency Procedures. This includes interfacility

communication, comprehensive verbal briefings of staff

and requests for assistance, as required.

COMMENTS:

_.

5. Demonstrate the timely activation of emergency facilities M N NO NA

during an off-hours, unannounced Exercise.

COMMENTS:

3555/NUCL-1429 47

. . _ . _ - _ . .. . ,._. _ . , - _ . _ . _ . _ . _ - _ _ . _ . _ _ - . _ . . _ . . _ . _ . . . . - _ - . _ . .-

,';-

I

j.>

i

CONIROLRQQMI

:h3

. 1%RT_IL.'l

.

SEliGFIC ON'-SITE Ol}]ECTIVES.

Ctde_One

,d - Demonstrate that Control Room staff can: -

1. Assess plant conditions, classify the emergency and make M = N NO NA -

appropriate protective action recommendatione. j.- I

. COMMENTS: .

- :

d__

:,

' 2. ' Make initial notifications of the emergency to appropriate M N NO. ' -NA- H

individuals and organizations.-- se>

. COMMENTS:'i

.

.

.

13.- Take corrective actions to control the situation and M.N NO .NA '.

mitigate the consequences.

'?,_ _

- COMMENTS:

.i :,

!

w

J x

r

i

Ii

| ~.'i

i

.~

3555/NUCL-1429 4-8

- ~ x. . . . . = - . . . . - -.-_.- .-..--.- - -. .. . . . . - . . . - . . , . .-

- - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _

i

CONTROLROOM (Cont'd)

PNtT_IL

SPECIEIC_D&SITILQIUEC1YES

CitcitOne

4. Establish communications with the Tecimical Support Center M N NO NA

and Operational Support Center during the process of activation

of those facilities.

COMMENTS: _ _

_.

5. Tum over communication responsibility with the Nuclear M N NO NA

Regulatory Commission to the Technical Suppen Center when,

it is activated.

COMMiWIS:

-

- 6. Coordinate operations related tasks through the Operational M N NO NA- Support Center after the Operational Support Center has becom:

operational.

COMMENTS:_-

3555/NUCL-1429 4-9,

.. . . . .. . . .

--

,-

,-

' CONTROL ROOM (Cont'dt

-pgh - I

SITCIEICD&SITLOlllECTIVES-Circle One

- 7; Maintain a formal log of events for the duration of the M N NO NA :-

: simulated emergency situation.

COMMENTS: .

.

i

.

: 8. - Demonstrate that the Shift Supervisor acting as Emergency M N NO NA

. Coordinator maintains overall command and contrcl of the,,

,

: emergency situation until relieved of this responsibility'

. by the Duty Plant General Manager in the, Technical Support

Center or the Emergency Response Manager in the Emergency,

Operations Facility.

COMMENTS: 'i

,

_l $|| ~|y

- ,

1

:

EVALUATOR: DATE:'

,

3555/NUCL'-1429 4-10

,

- . - - , - - N.,-, , , - , - - , . - - , . - . , ,I.,. ,, , .,.7- , - , a,- t -+

, . . ~. , _- .. - . . . _ . . - - - . . . . - . - . . - . - . - ..- ...- ., . . . - . .

>.

9s

- PORTLAND GENERAL ELECTRIC COMPANY ;

TROJAN NUCLEAR POWER PLANT . .

1920.EMEILQENCY PREPAREDNES1 DRILL AND EXERCISE PROGRAM

TECHNICAL.SUITORT CENTEILEYALUATION FORM - :

. 1%KLL'>

. GENERAL _QIljECTIVES'

QCitdtQac

l. Demonstrate the adequacy of the Radiological Emergency M N NO .NAPlan and Radiological Response Plan Implementing Procedures

in terms of management control.of an emergency and use-

fulness of the procedures. ;

COMMENTS:

'

2. Demonstrate the adequacy of communications among emergency M N . NO NA. ,

facilities, off site agencies and field teams.

COMMENTS:

,

,,

a

3. - Demonstrate the ability of key personnel to make timely: M N 'NO NA -

. and effective decisions during a radiological emergency.

~ COMMENTS:i

;.

,

-- KEY,

M - Objective Met'

| N- Objective Not Met:-

p L NO. Objective Not Observed

| .. NA - 'Not Applicable ;L

|

3555/NUCL-1429 4-11

1

- .. _ . . _ . _ . _ . ._. _ . _ . _ . . , . _ . - , ,, ,

._.

IEC11NICAL SUPPORT CENTER EVALUKIlOREORM (cont'd)

PART1

0.BNERALS111ECTIVES

ClIde_Qat -

4. Demonstratt the abi' 'mergency facility managers to M N NO NA

effectively utilize the toources of their facility to





COMMENTS: _


during an off-hours unannounced Exercise.

COMM'iNTS:

i

|

|

3555/NUCL-1429 -4 12

.- _ _

_ - _ _ _ _ _ _ _ _ -

TECilHLCALSLTEDRT_CEtiTER

EARTIL

SPECIEIC_OES11LLOBJECILYESCirde_One

Demonstrate that the Duty Plant Oeneral Manager:

.c N NO NAl. Obtains detailed plant and emergency status briefing from'

the Shift Supervisor.

COMMENTS:

,

!

2. Assumes conunand and control of the emergency sitisation M N NO NA

until relieved of this responsibility by the Emergency

Response Manager,

COMMENTS:

_

3. Classifies the emergency if the Emergency Response Manager M N NO N'

has not assumed Emergency Coordinator duties at the

Emergency Operations Facility.

COMMENTS:

,

,** en**

_ _._.-.s.,. . . . . . _ . _ _ _ __ . . . _ . _ . _ . , . . . . . . _ . _ _ . _ _ . _ .._ _ .._ _ ..

I.

, , - 4

y --TECHNICAL' SUPPORT CENTER (Cont'd). . .'

,

l%RUL :)_H,

* - SITCIFIC Oti-SLTILQHJECllY.ES !

Clicle_Qnc~

,

:

4f Develops Protectise Action Recommendations with the M N NO. NA'+ '

Technical Support Center staf f(if the Emergency:1 -- Response ManagerSas not assumed the role of Emergency

Coordinator) utill7.mg plant conditions.-

. COMMENTS:.

f

i

-Demonstrate that Technical Support Center staff can:

Adequately staff anh activate the Technical Support M N NO NA''

5.

. Center within 60' minutes of the ALERT classification.

' COM'MENTS:.

f

,

y,t

,

[ '6. Assume responsibility for Nuclear Regulatory Commission M N .NO NA.. communication from the Control Room on activation of the|

j. | Technical Support Center.|

.

|| COMMENTS:o

|r

|J ,

n

.

. 3555/NUCL-1429 4 14.-

ii

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IMAGE EVALUATION / %+fTEST TARGET (MT-3) &

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Circle Oric --

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7, . ' Adequately 1nonitor the three fission product barriers. M N NO NA'

4

l'.>

s.

COMMENTS: ~'

>

l7 ,

. c

111

+

. |R. - Support emergency functions of the Control Room and M N NO NA'

,

1> Emergency Operatiota Facility..I

n' <

.

-

|'

- COMMENTS. ,

.|[ ... 1 ..

.|m- .m

4y j-

.' !,

.i 9. - :Perfonn an'alyses, monitor plant con 6s ns and anticipate M N NO NA {:

> : problems in carrying out the EOP's to develop plans for |'

/ corrective action.

'

COMMENTS:

!

iy, ].!L

',

1

s l' L10.. : Identify tasks to be performed by the Operational Support - M N .NO NA

Center staff / ,

m

ig' . COMMENTSi |'

.

h im ,

!

- | , g '.~

!

|

E 13555/NUCL-1429 ' 4-15

.j-. <

.. . . . - . - _ . - -.- . - . ..

r .

E - mf '.j : . 4 U-.>;,e

"TECHNICAL SUPPORT CENTER (Cont'd) |,

[ |<

m

: : EMLT IL .

g[ L APECIFIC.ON-S!TE OBJECTIVES -1

Circic_One I'

:,.-

1 l'. Provide direction to the CR to have plant paging system - M N NO NA- -

', ~ announcements made conceming accudebt status, plan status,

radiological hazards and any on site protective actions.'

>

: COMMENTS:

,-t.

_

..

- 12.: Maintain a formallog of events for the duration of the M -N NO NA;. . simulated emergency situation.

.

-

l'

COMMENTS: '.

,

, ,

_

' 13. . Maintain current display ,) plant status. M N NO NA,

t

.. COMMENTS: -_ ._.

c--

, . .r e

m

2

-14. Maintain current display of emergency activities. M N NO NA

|,

,-

- COMMENTS:,

--|.

'

3555/NUCL-14291 4-16'

~. ,. ,

,

e .- - n ,m, ~ , , , , , y

-. _ _. ___ _ _ .. ._ . . . . ._ _ _ . _ . . . . . _.-.._ _ _._ - ____.__

-

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1

e ?

EQRTLAND GENERAL ELECTRIC COMPANY j- TRQ.IAliEllCLEAR.EQEER PLANT =

192(LEMERGENCY PREPAREDNESS DRILL AND_ EXERCISE PROGRAM

OfERATIONALS.UEEORT CENTER EVALUA110N FORM

PARTI. ,

,

. GENERAL OBJECTIVES

Circle One

1. Demonstrate the adequacy of the Radiological Emergency M N NO -NA

Plan and Radiological Response Plan implementing Procedures.

COMMENTS:,

1

4

2. Demonstrate the adequacy of communications among emergency M_N NO NA

- facilities, off-site agencies and field teams.-

- COMMENTS- ;

m -

!

i<

h 3, Demonstrate the ability of key personnel to make timely M N' NO NA-

d ff ti d ii d ian e ec ve ec s ons ur ng a radiological emergency.

COMMENTS:,

_

!

,

.

KEY- 1'

_,

M- - . Objective Met'

EN , .- Objective Not Met.

'

'- ;NO ~ Objective.Not Observed-

NA -- LNot Applicablee

' 3555/NUCL-1429 4-17

=.= .- .= . .

- - - . ... . - - - - - . .

,.

..

l

OPERATIONALJ_UPPORT CENTER EVALUATION FORMLCont'd) i

EARIL1

|GENEBALRDlECTIYESCircle One

- 4. Demonstrate the ability of emergency facility managers to M N NO NA

, -effectively utilize the resources of their facility to

- accomplish the goals of the Emergency Plan and the


conununication, comprehensive verbal briefings of staff

and requests for assistance, e required.

COMMENTS:

5. - Demonstrate the timely. activation of emergency facilities M N NO NA


COMMENTS:

!-

|:

|

|~

3555/NUCL-1429 4-18

oI

_.

_ _ _ _ _ _ _ _ _ _ _ _ _ _ - _

i

QPERATION_AL SUPPORT _CENIER

PART_lL

SPECJEIC_ORSITEDalliCILYES'

CirckDne

Demonstrate that the Operational Support Center staff can:

1. Adequately staff and activate the Operational Support M N NO NA

Center within 60 minutes of the declaration of an ALERT.

COMMENTS:

2. Communicate and coordinate task assignments and Operational M N NO NA

Support Center activities with the Control Room and Technical

Support Center.

COMMENTS:

3. Assemble, brief, dispatch, communicate with, and track M N NO NA

Operational Support Center teams to the completion of

assigned tasks.

COMMENTS:

,

3555/NUCL-1429 4-19

_ _

1

1

i

OPERATIONAL SUPPORT CENTER 1ConGD

'

1%CRIL

SPEC 1EIC_Q&SIIILOBJECTD'ES

Circle One

4. Track individual Operational Support Center member doses M h O NA

and control Operational Support Center personnel exposure.

COMMENTS:

5. Maintain contamination control in the Operational Support M N NO NA

Center, including personnel, tools, and Self Contained

Breathing Apparatus (if necessary). Demonstrate that

Operational Support Center radiological habitability can be

monitored.

COMMENTS:

6. Demonstrate that the Operational Support Center Supervisor M'N NO NA

can keep personnel in the Operational Support Center infomied

of current plant conditions.

COMMENTS:

1

.

l

I

!

3555/NUCL-1429 4-20

. - . _ .

. . _ . - . - . -

PORTLAND GENERAL ELECTRIC COMPANY

TROJAN NUCLEAR.E. 3YERPLMH0L29.G.Eh1ERGENfY PREPAREDNESS _DRILLAND. EXERCISE PROGRAh!

1R"IACflDENT SAMPLING SYSTEh! EVALUATION FORM

I1RI.L

GENEIML.QBJECTIVES

Circle One

1. Demonstrate the adequacy of the Radiological Emergency M N NO NA

Plan and Radiiilogical Response Plan Implementing Procedures.

COMMENTS:

2. Demonstrate the adequacy of communications among emergency M N NO NA

facilities, off-site agencies and field teams.

COMMENTS:

3. Demonstrate the ability of key personnel to make timely M N NO NA

- and effective decisions during a radiological emergency.

COMMENTS:

KEY_M Objective Met-

! N Object;ve Not Met-

| NO Objective Not Observed-

NA - Not Applicable

L

3555/NUCL-1429 4-21

__ _ _ _ _ _ __ ___ __ _

.

POST ACCIDENT SAh1P11NG SYSTEM EVALUATION FORM (Cont'd),

PARIL :

GENERAL.DB.1ECTIVES

Cirde_Dne,




Emergency Procedures. This includes interfacility' communication, comprehensive verbal briefings of staff


COMMENTS:

L

| 5. Demonstrate the timely activation of emergency facilities M N NO NA

during an off hours, unannounced Exercise.

- COMMENTS:,

1.

-

L|

|

3555/NUCL 1429 4-22

t

_ - _ - _ _ _ _ _ - _ _ _ _

POST ACCIDENT SAMPLING SYSTEM EVALUATION FORhti.ConGD

CART _lL

SEECIELC DFESITElLQ1NT OBJECTIVESCircle _Qat

1. Utilizing appropriate procedures, manipulate the PASS to M N NO NA

collect samples of reactor coolant and containment

atmosphere.

COMMENTS: . . _ _ _ _ _

_

2. Demonstrate proper use of procedures and equipment for M N NO NA

maintaining radiological safeguards and transport of

sanmles.

COMMENTS:

3. Demonstrate proper use of procedures and equipment for M N NO NA

cualysis of samples.

COMMENTS:

_

3555/NUCL-1429 4-23

__ -________ __________ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___

- - . . . .

POST ACCIDftfLSAhiP11NQ1YSTEhtEYALUK110XEORhi1 Cont'd)

Chcle_Qne

4. Provide analytical results for use in assessing core M N NO NA

damage and containment integrity.

COMMENTS:

EVALUATOR: DATE:

;

3555/NUCL-1429 4 24

. .. ._ _._.._._. _ _ _ - . _ _ _ _ _ . . _ . . _ _ . _ _ _ . - . _ _ . _ .

Y

PORTLAND GENERAL ELECTRIC COMPANY ;

IROJAN NUCLEAR POWERflBSI1990 EMERGENCY PREPAhEDNESS DRILL AND EXERCISE PROGRAM

'

: EMERGENCY OPERATIONS _EACILITY EVALUATION FORM .>

1%KU2 -

GENERAL OBJECTIVES:Circle One

?

1; Demonstrate the adequacy of the Radiological Emergency M N NO NA


COMMENTS:..

.

2. Demonstrate the adequacy of conununications among emergency M N NO- NA


~ COMMENTS:

3. Demonstrate the ability of key personnel to make timely . M. N NO NA

- and effective decisions during a radiological emergency. .

COMMENTS:-

u

KEY: M - - Objective Met -. N? Objective Not Met ,

L NO1 ' -- Objective Not Observed |NA Not Applicable.-'

1

|

. '3555/NUCL-1429 - 4-25

ti._ .. .m.. - ._ . . ,U

.

EhiERGENCY OPERATIONS FACILITY EVALUATION FORM (Cont'd)

['NLT_L

GENERAL OBIEC11YES

Cirde One

4. Demonstrate the ability of emergency facility managers to . M N NO NA






~ COMMENTS:



COMMENTS:

.t

d

3555/NUCL-1429 4-26

_

. .--. ..- - ,.-..-..- -_. -. . -. - .. -.-.~ _ . . . . . - - . . , .

c.w

?? * i h:. . . . '

t

,

' EMERGENCY OPERATIONS FACILITY- 1,

* 9 g - .

. SEEGElc ON SITEDEJECDVES j,

Circle One]i

Demonstrate that the Emergency Operations Facility staff can: )I

1. . Adequately staff and activate the facility within M N' NO .NA

60 minutes of the declaration of an ALERT.

COMMENTS:

,

|-,

. 2.i . Classify the emergency if the Emergency Response Manager M N NO NA-'

,

; has assumed the role of Emergency Coordinator at the Emergency -

Operations Facility'. <

1-

COMMENTS: .4

!

--.

-! 3. -: "Obtain data from the Technical Support Center as required M N NO NA. -

| - to supplement Safety' Parameter Display System output..

' COMMENTS:-

, -. c ._

f

p

L,

j. - -

.

4-271

: 3555/NUCL-1429H

i

p e,

i ~. . , - _ - . . n. -- . _ .u ._ _ . - .. ._ . . . a , ~ . . _. . . . _ , - ., ,-

. - _ _ . . . .

EMERGEtiCLDEERI.TIONS. FACILITY 1Colu'd) i

l' ITILA

SEECIEIC.0&SIIE OBJECTIVES

Circle One,

l

4 .' Transmit the following information with updates as required M N NO NA

to the Company Support Center and simulate these transmis-

sions to the Oregon Emergency Operations Center, Washington |

Emergency Operations Center, Cowlitz County Emergency

Operations Center, Columbia County Emergency Operations

Center and Oregon Health:

Emergency Classification'

-

Plant Data Summaries-

Dose Assessment Results-

Protective Action Recommendations '-

COMMENTS:

4 ,

. 5. ' Provide access control at the Emergency Operations Facility. M N NO NA

COMMENTS:

.

3555/NUCL-1429 4-28

. . ,_. ._. . -- ._

EMERGENCY OPERATIONS FACILITY (Cont'd) -

PMLT.lL

SJECIEjC ON SITE _QIllECTIVES |CiIdcDae )

1

6. Maintain a fonnallog of events for the duration of the M N NO NA

simulated emergency situation.,

' COMMENTS:

__

7, Maintain current displays of the following information for M N NO NA

' the duration of the emergency.

Plant Status-

Emergency Status-

Off-site Protective Action Reconunendations*

Emergency Operations Center Decision-maker Board-

COMMENTS:

.

8. Demonstrate that the Health Physics Supervisor issues M N NO NA

thennoluminescent dosimeters to Emergency Operations Facility

= personnel upon declaration of an ALERT.

' COMMENTS:

3555/NUCL-1429 4 29

_ _ . - . _ _ . _ _ - .

EMERGEliG'_0fERAT10NS EACILDT (ConGD

PART 11.

SPECIE 1C.ON-SITE OD_1ECIly_ES

Circle One

9. Demonstrate that the Public Information Representative M N NO NA

provides information on a continuing basis to the

Joint Infonnation Center.

Demonstrate that the Emergency Response Manager:

10. . Obtains a detailed plant and emergency status briefing M N NO NA

prior to assuming the position of Emergency Coordinator.

COMMENTS:

11. Can develop a Protective Action Recommendation (if the - M N NO NA.

Emergency Response Manager has become the Emergency Coordinator).

COMMENTS:

l-

.

i

3555/NUCL-1429 4 30

|

. ..~ _ . _ _ . _ . . _ . . . . . _ . . _ _ _ _ _ . _ . . _ . . _ . . . _ . . . ..._ . . . . . _ _ ~ . . _ . . _ _ . . _ . .

,

PORTLAND GENERAL ELECTRICCOMPANY

TROJAN.liUfLEAR POWER PLANT

E90 EMERGENCY PREPARERNESS_ DRILL.AND EXERCISE PAODIMMg

EMERGENCY OPERATIONS FACILITY"

DDSXASSESSMENT AREA EYALUA110M.EQBM,

PART1.

p ,

G.ENERAL OBJECTIVES

Citcle_One i


Plan and Radiological Response Plan Implementing Proceduies.

COMMENTS::

: 2. Demonstrate the adequacy of communications among emergency MN NO 'NA'

facilities, off site agencies and field teams.

COMMENTS: 7

r

'is

: 3; Demonstrate the ability of key personnel to make timely M N- NO- NA< and effective decisions during a radiological emergency.

ICOMMENTS:

KEYy M..- - ; Objective Met

,

' .NJ : Objective Not Met-

.NO. Objective Not Observed-

.NA Not Applicable-

g

3555/NUCL-1429 4-31-

h $

'

. . - . - - . . . -- n. _-. n

. --.

.

Eh1ERGENCY OPERAIl0ES EAGLIIY

D_0SEASSESSMENT_AREARYAL1]AT10liEQIG11 Cont'd

IMRI.14

GENERAL 011JECTIVES:

CiKit_Qat





communication, comprehensive verbal briefings of staff'


- COMMENTS:

:

5. - Demonstrate the timely activation of emergency facilities M N NO NA


COMMENTS:

1-

E

3555/NUCL-1429 4-32

. .

- _ - _ - _ _ _ _ .

EMERGENCY OPERKIlONS FACILITY

. DDSE.ASSESSMEtEAREA.EY.ALMATION FORM

PART_lL

SPECIEIC_Off-SITE /10lNT.DDIECTIYESCirsle.Dnt

EMEILQENCY OPEPAT1QMS1ACIL111R.QSEASSESSMEEI. AREA

Demonstrate that the Radiological Manager can properly:

1. Manage the dose assessment activities by maintaining M N NO NA

proper oversight of those activities.

COMMENTS:

_ . -

Demonstrate that staff can properly:

. 2. Project dosage to the public via plume exposure based on M N NO NA

calculations and field measurement.

COMMENTS:

3. Use dose projection results to develop any Protective M N NO NA

Action Recommendations required by emergency conditions.

COMMENTS: __

3555/NUCL-1429 4-33

_ _ ._ __. _ _ _ _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ - _ - _ - _ _ _ _ _ -

_ _ - _ _

t

Eh1ERGENCY OPEIMTIONS FACILIIY

DOSE ASSESSMENT AREA EVALUATION FORh1(Cont'd) '

PART.ll,

.

SEECIELC_REE-SLTElJOINT OBJECTIVES

CitdcDnt

4. Plot field team data accurately and clearly. M N NO NA

COMMENTS:

__

5. Properly process Accident Assessment / Notification Fonns M N NO NA

and maintain control of thoie fonns.

COMMENTS:

- 6. Obtain back up meteorological information. M N NO NA

COMMENTS:

'7. Make Ingestion Protective Action Reconunendations and M N NO NA

dose calculations.

' COMMENTS:

3555/NUCL-1429 4-34

_ , . . . . . _ _ - . . _ _ _ . . _ _ _ . _ . . _ . . . _ , . _ _ _ . . _ _ _ . . _ _ . . . - . . _ _

'

:

PORTLAND GENERALELECTRIC C011PANY

IRQJAN NUCLEAR POWER PLANT

1920 EMERGENCY.EREEARERNESS_RRILL_AND_EXERCISEIRQGRAM

RADl0LQGICAL FIELD.hiONITORING EVALUATION FORM-

EARIl

. GENERAL OBJECTIVES

Circle _One

.

I; ' Demonstrate the adequacy of the Radiological Emergency M..N -NO- NA

- Plan and Radiological Response Plan Implementing Procedures.

1 COMMENTS:A

.i

e r

.2. Demonstrate the adequacy of conununications among emergency M N- NO NA-~


COMMENTS:it

.i

l9

3. . Demonstrate the ability of kc/ personnel to make timely M N: NO- NA~

and effective decisions during a radiological emergency.

COMMENTS:"

----

4

i

KEY-M -- -Objective Met -u

" -N. e ; Objective Not MetR JNO - . Objective Not Observed .

r

-NA Not Applicable-

7

L '3555/NUCL-1429. 4-35

o|| :i

.- - .. . . . , . . . , .-. -. -- -

. _ . . . _ . _ .

IMPl0LQDlCALEIELD MONITORINQJiVALUATION ERRhtLCont'd)

i

l' ART 1. )!

|'

GENERALQDlECTIVESCiLcitDuc |

~



accomplish the goals of the Emergency Pian and the




COMMENTS:

,

5. . Demonstrat he timely activation of emergency facilities M N NO NA-

during an off hours unannounced Exercise.

COMMENTS:,

,

l.

!

- 3555/NUCL-1429 4-36

L

. . . . . - . . .- . . . . . . ..

IMDlRLQOlCAIJJELD_h10MIOJUNG

1

1% Rill !

SEECIDfDESIIE/10MLOBlEGLVES l

Circle _One .

i

Demonstrate that:

1. The Fortland General Electric Field Team can be prepared M N NO NA

to begin its monitoring activities within 60 minutes of a

declaration of an ALERT.

,

COMMENTS:

,

2; Field Teams can communicate with the Emergency Operations M N NO- NA^ Facility using two-way radios or cellular phones and

provide required information to the Emergency Operations

Facility,

COMMENTS:

.

L

3. Demonstrate appropriate equipment and procedures for M N NO NA

| -detemlining ambient radiation levels.

COMMENTS:

1.

|.

|

3555/NUCL-1429 4-37

. ., - . .

__ _ _ _ _ _ _ _ _ _ _

RADIOLOGICALBELD MONITORING (Cont'd)

l'ARTJ.L

SI'ECIFIC OFF-SITEBOINT OBJECIL\tES

CitckDnt

4. Demonstrate appropriate equipment and procedures for M N NO NA

measurement of airbome radiciodine.

COMMENTS:

5. Field Team members properly report and control their M N NO NA

exposutes.

COMMENTS:

|

3555/NUCL-1429 4 38

.. _

y . . _ . . . . . - . _ . . ... - . __ ._ . _ . . _ . _ . . _ _ _ . . _ .- -

:,;,

*m5\ b'

,

PORTLAND GENERAL ELECTRIC COMPANY#,

TROJAN NQCLEAR POWER PLANT |p-#

.1220_ EMERGENCY PREPAREDNESS.DRILLAND_ EXERCISE PROGPsAM

g . COMPANY SUPPORT CENTER EVALUATION FORM-.

s,.

k ^

GENE'ML OBJECTIVES

Citde_Qac.


Plan and Radiological Response Plan Implementing Procedures. ,

1

COMMENTS:

c.r :-

: ,' c-

'

' 2. Demonstrate the adequacy of conununications among emergency M N NO NA-.

facilities, off site agencies and field teams,

. COMMENTS:

..

W

a-

'

: 3. . Demo'nstrate the ability of key personnel to miike timely M N: NO NA-

( and effective decisions during a radiological emergency,- 1,

. COMMENTS:-

i. i,

ow . 1c; ' KEY

'

.M= - - -Objective Met. i

LN4 - ; Objective Not Met :Objective Not Observed !'NO : -

N A -- Not Applicable ''

!

3555/NUCL-1429 4-39

._ -. - . _ . . . , ,_. ,

.. - . . . _ _ - - --

COMPANY SUP10RT_ CENTER.EYALUATLON FOfGiLCenGU

PAILT_L

GENERAL.0DJECTlYES

Circle _One


effectively utilize the resources of their facility t :

accomplish the goals of the Emergency Plan and the,




COMMENTS:


during an off hours unannounced Exercise.

COMMENTS:

|

|:

|

~

1

|

|

3555/NUCL-1429 4-40

. . . _ . ._ _ _. _ _

1

|

|

CQ. MPANY SUPPORT GUIER

I

Imitti.

SEECIEICDEE-SHEILQ1NLOBIEC11YESCircle One

Demonstrate that Company Support Center staff can:

'

1. Document and track requests for assistance from the M N NO NA

Technical Support Center, Emergency Operations Facility

and other emergency centers.

COMMENTS:

2. Notify specified agencies and off site groups of accident

conditions. M N NO NA

COMMENTS:

__

_

3. Request and coordinate assistance as necessary from off-site M N NO NA

organizations.

COMMENTS:

l

l-

f

L4. Periodically update the Emergency Operations Facility on M N NO -NA! the status of off site organizations.

COMMENTS:,

,

1

3555/NUCL-1429 4-41

_ _ . . _ , - . . _ . , _ . _ _ _ _ . _ _ _ _ . . . _ . _ _ _ _ . _ - _ . _ _ _ . _ . ~ .

x..

PORTLAND GENERAL ELECTRIC COhlfAMX

' IILQJAN NUCLEAR POWER PLANT.

,

1990 EMERGENCY PREPAREDNESSERILL AND EXERCISE PROGRAhi

JOINT INFORMATION CENTER EVALUATION FDRM -

;PA11L

'

GENERALDDJECTIVES ..

'

Citdc_Qnt+

.

1, Demonstrate the adequacy of the Radiological Emergency M N NO NA


COMMENTS:> ,

;

o,

2.' Demonstrate the adequacy of communications among emergency M N NO .NA' '

facilities, off-site agencies and field teams; j' COMMENTS:

:3; | Demonstrate the e.bility of key personnel to make timely M N- NO NA.

and effective decis~ ions during a radiological emergency.

J COMMENTS: ;

KEY-: M :- - Objective Met -N =a Objective Not Met

_ Objective Not Observed| |NO '-i- NA ' 1 Not Applicable--

L'u

!

l-

3555/NUCL 1429 4-42,

w r- - - --- - e- e y -,

.. . - - _ _ _ _ _ _ _ _ _ _

10lMI.lNE0Rh1AT101LCELUERIYALUATlotROIG11 Cento)

PARI.L'

GENERALONECI1YESCudcDat

4. Demonstrate the ability of ernergency facility managers to h1 N NO NA

effectively utilize the resources of their facility '.o

accomp;ish the goals of the Emergency Plan and the

Emesgency Procedures. This includes interfacility



COhiMENTS:

5. Demonstrate the timely activation of emergency facilities h1 N NO NA

during an off hours, unannounced Exercise.

COMMENTS:

f

3555/NUCL-1429 4-43

_ _ . - _ . _ _ - _ -___- _ _________-- _____ ____ _ ____ _ _ _ _ _ _

_- . - -.. . .. = _ - _ . _ - . .. . _ - .

,

10lNT INFOP11AIlGRCENIEILEYALLM110N FORM ICenGD

PNLT1L

Sr.ECIEIC.DthSITE.DBAGl\'ESChde.One

Demonstrate that Joint Infonnation Center staff can;

1. Demonstrate the ability to set up and staff the JIC. M N NO NA'

COMMENTS:

2. Demonstrate the ability to contmunicate via the Public M N NO NA

Infonnation Phone with other Public Information Officers.

COMMENTS:

_

_._

3. Demonstrate the ability to coordinate the development M N NO NA

and approval of news releases from the JIC.

COMMENTS:

-

-

f

. 4. Demonstrate the ability to conduct the news media M N NO NA

! briefings at the JIC.

! COMMENTS:

1

EVALUATOR: DATE:

3555/NUCL 1429 4 44

-

- ._ . . . . . . _ _ _ _ _ __

_ _ .. _ _ _ ._ _ _._._._. _ _ _ ._._ _ .._..__.. _ ._.._ _ ._ _ ._

r .;d

i

N

!-.

PORTLAND GENERAL ELECTRIC._COMPM' |,,

b- . TROJAN NUCLEAR POWERPLANT |9 19W_ EMERGENCY PREPAREDNESS _DRILLAND EXERCISE PROGIMbl

i hiEDLCALEhiEROENCY QRILLEYALUKE10B.IQEh! |

<

cAan ;;

'

GENEIMLDDJ.ECEIYES

Chcic_One ;,:

e :' l. Demonstrate the adequacy of the Radiological Emergency M -N NO NA '

Plan and Radiological Response Plan f.mplementing Procedures.

COMMENTS:. 1*

1n . _ . _ ,

,

e,

!'

e

2. Demonstrate the adequacy of communications among emergency M N NO NA

facilities, off site agencies and field teams,'

' COMMENTS:.

.

3; . Demonstrate the ability of key personnel to make timely. M N - NO -NA

and effective decisions during a radiological emergency.

. COMMENTS: __

>

'

.

_.

!

KEYa, _ _

M Objective Met-.

N: - Objective Not Met ,

NO: Objective Not Observed-

NA Not Applicable-

,

'

3555/NUCL-1429 4-45

-..~..:...__..-.._.-_-_..__..__.,.,.-,.__.,_..,,.--.. - - , - . _ - . . . , - _ . .

. .. . . _ _ - - _ . _,

k

.

MEDICALEMERGENCY_DEILL EVALUAllDN FORhi1 Cent'd)

1%RT.1

[ QEMERALDNEC11YESCkcleDne

2

4. Demonstrate the ability of ernergency facility managers to M N NO NA

effectively utuize the resources of their facility to'

accomplish the Eoals of the Emergency I'lan and the

Ernergency Procedures. This includes interfacuity'

comrnunication, comprehensive verbal briefings of staff


COMMENTS:

!-

|,

!

|;

3555/NUCL 1429 4-46

L. . . ~ . - . . . - . _ ___ __ _ . . _ .

. _ _ . _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

.

hiEDICAL EhiERGENCY DRILLIConGD :

PARIll,

SEECIEIC_Q& SITE.0BJECIlYES,

Cirde_One

The Medical Emergency Drill No.1 (October 29) will:

1. Demonstrate ability of the Radiation Protection Emergency

Team (RPET) to respond to a medical emergency inv- ving a

contaminated individual. In doing so, the RPET will demon-

strate its ability to:

a. Provide first aid to injured individuals. M N NO NA

COMMENTS:

b. Conduct surveys to determine the extent and M N NO NA

location of contamination or direct radiatinn

being emitted from the patient.'

. COMMENTS:

c. Decontaminate the injured person as much as possible, M N NO NA

without interfering with first aid priorities

Control any contamination which cannot be removed.

COMMENTS:

I -

>

3555/NUCL-1429 4-47

.. . - . - .-- - .-. . _ . . . - . - - -

.- - ,~ . .. . - - -_- - _ _ - _ . - _ . . - . _ - _ . --.

MEDICAL EMERGENC.LDRILL(cont'd)

ENELL

SFECIEICJ2& SITE OBJECTIVES

Ciale One,

d. Obtain the information necessary to determine the M N NO NA 1

extent of the injured person's exposure.

COMMENTS:

__

.

c. Prepare the patient for ambulance transportation. M N NO NA'

COMMENTS:

f. Dispatch a RPET member to accompany the patient to M N NO NA

the hospital to assist the ambulance and hospital

staffs with radiological services,

COMMENTS: _,

_

g. Provide complete and accurate patient status infor. M N NO NAmation in a standardized format to the receiving

hospital.

COMMENTS-

.

3555/NUCL-1429 4-48

. . , , . . - --_- .. . - - . _ . - . - - - .- - - - . .

__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ - _ _ _ . _ ___

l

h1EDICAL11MERGEHCDRil.LLCent'.d)

i%RTll.

|SPECIELClRL41IEDMECILVES

Cinle_One

2. Demonst ate the ability of Controf Room Supervisor to !

respond to a medical emergency involving a contaminated

individual. This will include:,

Iteceipt and disposition of originating casualty M N NO NAa.

report.

COMMENTS: _ _

b. Activation of the Itadiation Protection Emergency M N NO NA

Team.

COMMENTS: _

c. Notification of the Columbia County Communications M N NO NA

A ency (C-COM).F

COMMENTS:

..

d. Notification of the Medical llealth Physicist. M N NO NA

COMMENTS:

oi

3555/NUCL-1429 4-49

||

- - . . . . _ . , _ . . . . - _ . ._ .

. - _. .. -. __ , . . . _ - .

MERICALEMERGELY DRILLICant.'d:

EART.lL

SI'ECIEIC_O&SlIILQIllECI1YESChsle_One

'

3. Demonstrate the ability of Columbia County Emergency

Service Organizations to respond to a medical emergency

involving a contaminated individual at the Trojan site,

including:

a. Dispatch of ambulance service by C COM. M '4 NO NA

COMMENTS:

b. Timely arrival of the ambulance on site. M N NO NA

COMMENTS:

,

4. Demonstrate the chility of PGE Security to rapidly M N NO NA

process an ambulance through the protected area boundary.

- COMMENTS:

5. Demonstrate the ability of the ambulance crew and the RPET M N NO NA

to transport a contarninated injured person to the hospital,

COMMENTS:

3555/NUCL 1429 4 50

- .._ __ _ __ _ . - _ _ _ _ . . . .

. = _ -- . - - ._ . - _ _

MEDICAL EMERGENCEDRILL1 Cent'd)

PMILIL.;

SEECiflCD&SLTEDBJECTIVESCircle One

6. Demonstrate the adequacy of hospital facilities and procedures

for receiving, handling and treating contaminated injured

individuals. In doing so, the hospital will demonstrate:

a. Availability of procedures and properly trained 11 N NO NA

staff for dealing with radioactive contamination.

COMMENTS:

T'

b. Availability of necessary supplies and equipment . M N NO NA

including survey meters, anti-contammation clothing -

and decontamination supplies.

COMMENTS:

c, Interaction with Medical Health Physicist and RPET M -N NO NA

member, allowing either of these individuals to take

an assertive role in preventing cross contamination.

I COMMENTS:

;

i

(

;

|- 3555/NUCL-1429 4 51

. _ _, _ ._- _

.- - . - . - -

Il

I

MEDlCALEMEINENCY DIMLL (ConGl) )I

i w a tt l

SL'ECIE1CS&SITESD1ECILVESCircle _One


1. Demonstrate the adequacy of hospital facilities, equip-

ment and procedures for handling and treating contaminated

injured individuals. In doing so, the liospital will

demonstrate:

a. Availability of procedures and properly trained M N NO NA

staff for dealing with radioactive contarnination.

COMMENTS:

b. Availability of nece3. Jy supplies and equipment M N NO NA

including survey meters, anti-contamination clothing


COMMENTS:

;

I.c, Interaction with Medical Health Physicist and RPET M N NO NA

l member, allowing either of these individuals to take

an assertive role in preventing cross-contamination.

.

COMMENTS: .-

|

1

3555/NUCL-1429 4 52

-. - , _ _ _ . _ - , ,

. . . _ _. _. . _ . _ - - _ _ . ._- __ _-

h1ERICAL EMElWENCY_DRILLLCent'd)

1%IEIL,

SPECIE 1C_DESIBLODJEG1YESCrck_One

2. Demonstrate the adequacy of vehicles, equipment, pro- M N NO NA

cedures and personnel for transporting contaminated

injured individuals.

COMMENTS: ,

Medical Emergency Drill No. 3 (October 30) will:,

1. Demonstrate the adequacy of hospital facilities, equipment

and procedures for handling and treating contaminated

injured individuals. In doing so, the Itospital will

demonstrate:

a. Availability of procedures and properly trained M N NO NA

staff for dealing with radioactive contamination.

COMMENTS:

b. Availability of necessary supplies and equipment M N NO NA

including survey meters, anti-contamination clothing


COMMENTS: _.-

>

EVALUATOR: DATE:

3555/NUCL-1429 4 53

-. - - . _ - - - - . . . - - -- -- -

__ _ _ _ _ _ _ _ _ . - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ . __

PORTLAMILGENEIMLELECLTuC

1ROJANEUCLEAILELANT ,

.

1920_TRAINUiG.DPJLLSt

EXERCISEEITENDANfE_BECORD

DATE: _LOCATION: TIME:

N AME (l'IUNT) SIGNATURE EMERGENCY l'OSITION

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TROJAMMICLEAILIL\MT

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192DlRAINING DRILLS

CONTROLLEILOBSEILY.ATIONSHEEI

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TIME ACT1VITY OR EVENT

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... .. . . _ _ _ _ . - _ _ _ _ _ _ _ _ _ _ - _ _ ._.

.I '..

L

PART 11

CONTROLLED INFORMATION

. .. . . .

_ _ _ , .-_. _ _- _ _ _ _ _ _ _ _ _ _ _ _ _ . , _ _ _ _ _ _ _ _ _ _ . _ _ . . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . _ _ _ . _ . . - _ _ _ - _ _ _ _ - _ _ _ _ _ . _ . . _ . _ _ _ _ _ .

k

l+

SECTION 5.0 DRILL SCENARIO,

4

D

I

|.

,

1l

t

_ . _ . __ _ _ . _ _ - - .__ . _ . - _ _ _ _ . _ , . _ _ . . . - , _ _ _ , - _ _ . _ _ _ , . . - - . _ , . _ _ . - _ _ . _ _ . .

.

_ _ _ _ _

5.1 Farrative Summary

The scenario for this Exercise is based on a loss of Coolant Accident (LOCA) from aninterfacing system, resulting in a loss of RilR system recirculation capability. ReactorCoolant System makeup capacity is severely limited by the location of the leak, Corecooling capability is lost, fuel damage occurs, and a release of activity begins via theAuxiliary Building ventilation system to the environment. The basic scenario is derivedfrom probabilistic risk assessments analyzed by the Industry Degraded Core RulemakingOrganization (IDCOR) which indicate this type of event is the most likely to produce actualcore damage.

Initial conditions have the plant at 100% power,100G core flow, late in core life withmaximum decay heat. Evolutions in progress include: hiaintenance on the "A" EDGoutput breaker. "A" train ECCS is out of service while the breaker is being repaired.Estimated completion time for this repair is 2 hours. "A" Coolant charging pump has amotor winding short, and is tagged out.

A cylinder of hydrogen gas in transit to it's stowage location near the cooling tower isdropped and ruptures. The bottle explodes, and fragments from the explosion penetratethe wall of the turbine building. An ALERT is declared per module 14 step 2,(Explosionin the general area causing damage to plant structures or equipment).

The LOCA begins when RilR isolation boundary valves hiO 8701 and 8702 begin toleak by their shut seats. Low pressure RilR piping is over pressurized and fails at thedischarge side of RilR pump "A", and a leak begins into the Auxiliary Building PRhi-2 alarms. Operators declare a SITE AREA EhiERGENCY, based on either hiodule 1step 3 (Iligh Dose Rate, based on PRhi 2), or hiodule 2 step 5 (Loss of 2 Fission ProductBarriers). Operators manually trip the reactor, initiate Safety injection per El 0, thent ansition to ECA 1.2. RilR pump "A" isolation valve hiO 8700A (normally open) fails toclose when the attempt is made to isolate the leak. The power supply cable to the motoroperator grounds out and is damaged, requiring replacement.

Rising Auxiliary Building west side sump levels, and high humidity ground out "A" Safetyinjec ..m pump. Sump level continues to rise until it overflows and begins to fill theAuxiliary Building east sump.

The location of the coolant leak prevents recirculation operation of the RilR system,in addition, the reactor coolant lost begins to fill the Auxiliary Building sumps, liightemperatures, steam, poor visibility and rising radiation levels in the Auxiliary Buildingmake access for troubleshooting the LOCA repairs to, or manual operation of hiO 8700Aextremely difficult. Long term concerns of the maintenance personnelin the drill shouldinclude replenishment of the RWST without recirculation capability, and repairs to h10-8700A, to allow leak isolation. Based on concern for RWST inventory operators maysecure either "B" Si pump or "B" charging pump,in accordance with minimum ECCS flowrequirements vs. time since shutdown, per ECA 1.L

3555 5 5.12 Rev.10/09/90 i

.

- _ . - _ . - . . _ _ . . . . _ _ _ _ _ _ . , _ . . , _ _ _ _ _ _ _ _ _ , _ _ _ , _ _ _ _ _ _ _ __ , _ _ _ _,__ _

_ _ _ . _ _ _ . . _ _ _ _ _ . _ _ _ _ . _.__ _._ _ _ ___ _

i

.I

i

| ''B" Safety injectmn pump grounds out (and trips,if running), due to progressive floodingof the east sump. Reactor Vessel Level Indication System (RVLIS) indicates loweringvessel level. "B" Charging pump is operated, and should supply sufficient water to coal the

,

,

core per ECA 1.1 figure 1.4

L

1 "B" Coolant Charging Pump trips on a breaker fault. *B" SI pump is grounded andinoperative. hiinimum required ECCS flow cannot be maintained. Core thermocouples;

! indicate rising temperatures in several areas, and fuel damage occurs. Rising activity isnoted on the Auxihary Building ARhis. Operators declare a GENERAL EhiERGENCYbased either on hiodule 2 Step 6 (Loss of 2 fission product barriers with imminent loss of

,

the third), or on hiodule 1 Step 7 (iiigh dose projection: ARhis or PRhis indicate greater'

than 1 Rem /hr whole body or 5 Rem /hr thyroid at the Exclualon area boundary).,

"B" Coolant Charging Pump breaker is repaired, and makeup water is injected to coolthe core. With the replacement of the power supply cable for hiO 8700A, the valve canbe shut to isolate the LOCA. The release is terminated.

;

With the termination of the leak, operators must be concerned with stabilizing thereactor, maintaining RWST level, and cleanup and restoration of the Auxiliary Building.When a recovery path to accomplish these objectives has been identified, the Exercise willbe terminated,

i

. .

|

I

,-

|

!

i 1

,

3555 5 S.13 Rev.10/09/90

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:

i i

:

~[ Trojan Annual Exercise5.2 Exercise Timeline f

i

Approximate Time Key Event

i

0315 0000 INITIAL CONDITIONS:

The plant is at 100% power,100% core flow, late in core life with 1

; maximum decay heat. Evolutions in progress include: Maintenance on'

the "A" EDO output breaker. "A" train ECCS is out of service whilethe breaker is being repaired. Estimated completion time for thisrepair is 2 hours. "A" Coolant charging pump has a motor windingshort, and is tagged out.

0330 0015 A cylinder of hydrogen 1;as in transit to it's stowage location near thecooling tower is droppec and ruptures. The bottle explodes, andfragments penetrate the nearby outside wall of the Turbine Building,resulting in rninor structural damage to the building. Operators shouldinspect carefully and verify that no equipment has been damaged.

0345 0030- Operat_ ors declare an ALERT per module 14 step 2, (Explosion in thegeneral area causing damage to plant structures or equipment'Emergency response facilities begin activation.

0500 .0145 A Loss of Coolant Accident begins a.c RiiR isolation bounda valvesMO 8701_ and 8702 begin to leak by their shut seats. Lov t ,ure

RIlR piping is over pressurized and fails at the discharge * of RIIR- pump A", and a leak begins into the Auxiliary Build' PRM 2D"

alarms. Operators manually trip the reactor initiate .ety injectionper El 0, then transition to ECA 1.2. RHR pump "A" isolation valve

; MO 8700A (normally open) fails to close when the attempt is inade toisolate the leak. The power supply cable to the motor operator grounds i

out and is damaged, requiring replacement. -

0515 0200 Operators declare a SITE AREA EMERGENCY, based on eitherModule I step 3 (liigh Dose Rate, based on PRM 2), or Module 2 step5 (Loss of 2 Fission Product Barriers).

0530 0215 Rising Auxiliary Building west side sump levels, and high humidity !

ground out "A" Safety injection pump. "A" SI pump trips.<

3555 5 5.23 REV.10/9/90

.. - . - . - . -- - - -. . - . _ _ _ . - _ . - - --

i

1

l

Approximate Time Key Event i

0543 0230 PLANT ST/sTUS:

The location of the coolant leak prevents recirculation operation ofthe RIIR system, in addition, the reactor coolant lost begins to fill the ;

Auxiliary Building sumps. liigh temperatures, steam, poor visibility and i

rising radiation levels in the Auxiliary Building make access fortroubleshooting .he LOCA, repairs ta, or manual operation of $10-8700A extremell difficult. l.ong term concerns of the mainte1ance

_

personnel in th: drill should include replenishment of the F WST |

vithout recirculation capability, and repairs to h10 8700A, to allow leak ,

Isolation, Based on concern for RWST inventory operators may sectreeither ''B" Si pump oc "B" charging pump, in accordance with min mu nECCS How requiremeds vs. time since shutdown, per ECA 1.1.

0615 0300 Auxiliary Building west sump level continues to rise until it overflowsand begms to fill the Auxiliary Building east sump. "B" Safety injectionpump grounds out and trips (if running) due to progressive Gooding ofthe east sump. Reactor Vessel Level Indication System (RVLIS) |

indicates lowering vessel level.

0630 0315 *B" Coolant Charging Pump trips on a breaker fault. "B" SI pump isgrounded and inoperative. Minimum required ECCS flow cannot bemaintained. Core thermocouples begin to indicate rising temperaturesin several areas, and fuel damage starts.to occur.

0645 0330 Several core thermocouples indicate temperatures in the vicinity of 714degrees.

0700 0345 Operators declare a GENERAL EMERGENCY based either onModule 2 Step 6 (Loss of 2 fision product barriers with imminent lossof the third), or on Module 2 Step 4 (Loss of Core Cooling capability).

0700 0345 Rising act! by is noted on some Auxiliary Building ARMS.

0800 0445 "B" Coolan' eging Pump breaker is repaired, and makeup water isinjected to ,he core.

3555 5 5.2-4 REV.10/15/90

,

,w - , . ,m,+ ,- - - ,-, .. . . - . . . , _ . - _ - . - - - , , ,, ,m - -

- - - _- _ _ _ - _ _ _ _ _ _ _ _ _ __ _

.

Approximate Time Key Event

0830 0515 The power supply cable for MO 8700A is replaced. The valve can beshut to isolate the LOCA. The release is terminated. With thetermination of the leak, operators must be concerned with stabilizingthe reactor, maintaining RWST level, and cleanup and restoration ofthe Atuiliary Building. When a recovery path to accomplish theseobjectives has been identified, the Exercise will be terminated.

100J 0645 The Exercise is terminated

3555 5 5.2 5 REV.10/9/90

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5.3 Srnluie_ControUer Guids

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3555/NUCl 1429 5.31

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SCENARIO CONTROLLER GUIDE

TIME MSG. FROM TO EVENT SUMMARY ANTICIPATED RESPONSE CM CONTROLLER NOTESNO.

ABBREVIAT10NS USED IN TIIISGUIDE

;

AC All ControllersMSG No. Message NumberFM FromCM Contingency MessageSS Operations Shift Supervisor-C Contingency Message

(Preceded by Message Number)C- Controller Designation

(Followed by ControIIerNumber)

AP All Players :

CO Control Operator

l AO Auxiliary OperatorEC Emergency Coordinatori

IC Initial ConditionsDPGM Duty Plant General ManagerRT Repair TeamMT MaimenanceRO Radwaste OperatorSAE SITE AREA EMERGENCYGE GENERAL EMERGENCYIIP Ifealth Physics Technician i

MO Manager. Operations (TSC)ERM Emergency Response Manager

)

,

3555-0 5.3-2 Rev.10/23/90

- _ _ _ - - - _ - .-- - - - _ _ _ _ _ _ - -- --. - _ _ . _ _ - - - - _ _ - _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ - - _ _ - _ _ _ _ _ - - _ _ _ - _ _ _ _ - - _ _ - - -_ _ - _ _ _ .

1

SCENARIOCONTROLLER GUIDE!

TIME MSG. FROM TO EVENT SUMMARY ANTICIPATED RESPONSE CM COIfrROLLER NOTESNO.

.

03CO IC-1 AC AP INITIAL CONDITIONS: All personnel should be

The plant is at 100% Power.100% aware of plant conditions _flow. Late in fuel cycle (Maximum decay

' heat).

The followingevolutions are in progress: "A" ECCS scheduled for- Maintenance on the "A" EDG output completion on the day

breaker. shift.- "A" train ECCS is out of servicewhile the breaker is being repaired.Estimated completion time for this repair "A" CCP scheduled to twis 2 hours. rebuilt during the next- "A" Coolant charging pump has a outage.

motor winding short, and is tagged out.

0330 1 C-3 Sec. You noticed a bright flash and a loud Security notify the control room, and Explosion of a hydrogenGuard " boom" near the south end of the send a guard to investigate. bottle near the south ,

,

t at Turbine Building. mall of the turbine '

Access building.Cont.

0330 2 C-4 - Pass this messace to Control Room: Worker brief security when they arrive. 3-C (0345) C-2 To ensure t

Security inform control room. SS direct ALERT is declared.I just dropped the hydrogen bottle that a detailed inspection of the TB toI was carrying, and it fell on it's cap. determine damage. SS declare an C-4 deliver this messageThe bottle sounded as if it might be ALERT per Module 14 Step 2 as the worker.

3555-0 5.3-3 Rev.10/23/90

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SCENARIOCONTROLLER GUIDE

: TIME MSG. FROM TO EVENT SUMMARY AMTICIPATED RESPONSE CM CONTROLLER MOTES i,

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| 0330 leaking. ~As I was - going to call the (Explosion in ' the vicinity. causing damage Worker is unhurt. (! Contd Control ' . Room, the bottle exploded. to plant structures or equipment.) Fragmentshave penetrated t

Fragments flew all over the place. Some the turbine L-elding wall. !. appear to have . penetrated : into the No damage to equipment. !

! Turbine' Building.I.

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1 0345 3-C C-2 SS Declare an ALERT per Module 14, Step CONTROL ROOM Deliver this message only i

: 2 (Explosion in the vicinity, causing if an ALERT has not !

; damage to plant' structures or equipment.) SS declare the ALERT. Activate T5C yet been declared at the ji and OSC. Make required notifications. above time. [

:.

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: 0430 4 C-4 RT . Many sharp fragments of the hydrogen Be aware of plant conditions. |j at bottle are scattered over the roadway to |

Turb. the south. of the building. Damage to t

: Bldg. the building seems- mostly cosmetic, no jstructural frames have been found to be;

j affected. There are several relativelylarge t

holes in the south wall of the turbine I-

building,and the large garage' access door ['

is jammed shut. Further inspection for j'

2 affected components is in ' progress. No f

component damage has been found. [t

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3555-0 5.3-4 Rev.10/23/90 |

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TIME MSG. FROM TO EVENT SUIDEARY ANTICIPATED RESPONSE CM CONTROLLER NOTES*

I| NO.,

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}'

l- 0430 5-C. C-4 RT- The .*A~ EDG Breaker is tagged out for Switchecar Room: Deliver this message sf ai at"A" routine inspection and calibration. It. is RT inform - OSC. OSC' inform repair team is despatched ~ [:. EDG partially disassembled. Completion was control room. RT, prepare to re- to the "A" EDG breaker. '

| BKR. scheduled for the morning shift. assemble the breaker.~

Allow the team to

restore the breaker ifthey attempt to do so.Restoration of the

i breaker will not I

i significantly afTect the {

g scenario.:

i ,

0500 6-C C-2 SS/ ANNUNCI ATORS IN CONTROL ROOM CONTROL ROOM 8-C (0515) C-I Ensure SAE |;

Operators take action for LOCA per El- is Declared. i1- CO'

Disch Press Ili 0; Trip the reactor and initiate manual !} K- 12 "A RilR Pmpj K- 12 *B" RIIR Pmp Disch Press Ili Safety injection. Deliver this message only l

j K-01 PRM Trouble if proper indication is ff K-01 PRM-2 Radiation Alert not available from the v

| K-01 PRM-2 Radiation liigh simulator. LOCA has {! K-11 P ssurizer Control Level Low started from MO-87'll |

K-13 r Press Low litrs On and -8702 leaking by i

K-I l I CCP Auto Start their shut seats.'

hi; INDICATIONS IN CONTROL ROOM| RIIR cooler ou*Iet temp. ind. 400 F [

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i 0501 7-C C-2. SS/ ANNUNCIATORS IN CONTROL ROOM CONTROL ROOM i

! CO Operators take action to complete El-0 Deliver this message only |j. K-2I Safety injection Actuation for a manual Reactor Trip, and transition if proper indication is ;

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.3555-0 5.3-5 Rev.10/23/30

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! TIME MSG. FROM ~TO EVENT SUMMARY ANTICIPATED RESPONSE CM CONTROLLER MOTES !

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K-16 Turbine Trip, Reactor T rip to ECA-I.2. not availabic from the . . .,

j" K-21 L Rod Bottom simulator, and after [050i K-21 Rods 2 or more at Bottom operators insert manual

Contd K-21 CIS "A" Actuation reactor trip, and initiate {;

i. K-18 Feedwater Isolation Safety Injection per El-0. r

! K- 15 *A' Main Feed Pump Turb Trip i

'K-15 *B" Main Feed Pump Turb Trip

.K-21 *A* St Pump. Auto Start

i K-21 "B" SI Pump Auto Startj K-11 Pressurizer Level < 17% !

! K-12 "A" . RilR Pump Auto Start !

| K-12 *B" RIIR Pump Auto StartK-12 "A" RIIR Pump Flow Low ;

i K-12 - *B~ RIIR Pump Flow Low j;

I !f

! 0515 8-C C-I EC Declare a SITE AREA EMERGENCY by TSC Deliver this message only (j. Module 2 Step 5 (Loss of 2 Fission EC declare the SAE. Activate EOF if if a SITE AREA l

(| Product Barriers) QR by Module I, Step not already done. Make required EMERGENCY has not| 3 (Iligh Dose Rate, based on PRM-2) notifications. yet been declared. EC ji may declare SAE based i

on Module I Step 3 if

| SS is delayed more than.

(; a few minutes in the ,

; analysis and reporting of |j the RilR system LOCA |t as a LOCA outside of j

{ the containment. {t

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3555-0 S.3-6 Rev.10/23/90

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SCENARIOCONTROLLER GUIDE

ANTICIPATED RESPONSE CM CONTROLLER NOTESTIME MSG. FROM TO EVENT SUMMARY

NO.

CONTROL ROOM Deliver this message only0515 9-C C-2 CO / MO-8700Aposition indicator lights are out.

CO inform SS. SS inform TSC and if proper indication isSS not available from the

OSC. g_fler COfOSC simulatorSet up repair teams to investigate MO- attempts to shur MO-

8700A to isolate the8700A. LOCA. Indicator lights |

fail when breaker trips,

and stay out until thebreaker is reset. Valve

3fails to operate;electrically.due to failedpower supply cable onthe load side of themotor operator povrersupply breaker.

i 0530 10-C C-2 SS / ANNUNCI ATORS IN CONTROL ROOM CONTROL ROOM Deliver this message only

CO report to SS. SS report to TSC if proper indication is

K -21 "A" SI Pump Motor Overload ' and OSC. CO may attempt to restart not available from theCO

"A" SI pump. Pump will re-start and simulator. "A" Si Pump

trip within a few seconds if tried. is flooded out by highhumidity and rising

INDICATIONS IN CONTROL ROOM reactor coolant level in"A" St Pump indicates tripped the Aux Building westAux Building Sump West level high. sump.

'

I

l <Rev.10/23/90

5.3-73555-0

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0600 11 C-4 RT Conditions in the Auxiliary Building- AUX. BUILDING Deliver to RT leader atfor Temperatures are above 130 F near the RT be aware of conditions in the Aux the entrance to theMO - entrance to the building. Visibility is Building and take proper precautions. Auxiliary Building. RT8700A near zero in steam. Ilumidity is 100% should realize heat stress

and contamination areproblems of greatconcern. If they elect "

to proceed,conditionswi!!worsen to 150 F as theyapproach M O-8700 A .Obtain local arearadiation levels andcontamination levels frominplant maps.

0600 12 C-4 RT MO-8700A Power Supply Breaker indicates Switchrear Room D e Ii ye r to RTat tripped. No other abnormal indications. RT troubleshoot. When fault is troubleshooting theMO- determined. inform OSC, Control Room. breaker when they arrise.8700A Cause of trip is wornBkr. Cause of trip is worn insulation on load insulation on load side

side cabling, causing short to ground. cabling. Cable isshorted to ground. If

they replace the breakerwith a spare and attemptto operate the valveelectrically,the spare willtrip. A slight smell ofburning insulation willresult from the second

3555-0 6.3 8 Rev.10/23/90

I

SCENARIO CONTROLLER GUIDE|

!

TIME MSG. FROM TO EVENT SUMMARY ANTICIPATED RESPONSE CM CONTROLLER NOTES

NO.reser and trip. When

0600 RT remoses the breakerContd again, the power cables

on the load side arenow visibly burned, andmust be replaced. Enough ;

cable must be burned to l'

force warehouseparticipatior.,by requiringpulling of spare parts

Deliver to RT when they

0615 13 C-4 RT Conditions in the immediate vicinity of reach MO-8700 A Stayat MO-8700A, temperatures 150 to 165 F,,

time in Fe area due toMO- Visibility near zero. Valve body, piping,

heat stress is sery8700A and operator are hot (~200 F), and are limited. Operators will

operating stiffly due to high temperature feel faint after 1 Minuteand flow through the valve. of operating MO-8700A,and will collapse after anadditional minute if theydo not stop.

Rev.10/23/905.3 93555-0

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0615 14-C C-2 CO / ANNUNCIATORS IN CONTROL RCOM CONTROL ROOM Deliver this message onlySS CO may start "B" CCP if not already if proper indication is

K-21 *B' St Pump Motor Overload running to supply core cooling. If CO not available from theK-21 "B" St Pump Auto Trip attempts to re-start "B" S1 Pump, it will simulator AND if "B" SI

immediately trip. Pump is running at 0615.Pump trips on overload

INDICATIONS IN CONTROL ROOM due to progressive"B" St Pump indicates tripped flooding of the eastAux Building Sump East level high. sump by overflow from

the west su np and dueto high humidity. If

pump was not running atthis time, it will trip on

overload with the aboveindication when started.

0630 15-C C-2 SS / ANNUNCIATORS IN CONTROL ROOM CONTROL ROOM 16-C (0700) C-5 Ensure GE isCO SS notify TSC and OSC. declared.

K-Il "B" CCP Auto Trip OSC Deliver this message onlySend a RT to investigate. TSC notify if proper indication is

EOF. not available from theINDICATIONS IN CONTROL ROOM EOF simulator. Loss of ~B*

"B" CCP Pump indicates tripped. EC declare a GENERAL EMERGENCY CCP due to a fault inAux Building Sump East level high-high. based on Mod. 2 Step 6 (Loss of 2 the supply breaker.Core exit thermocouplereadings are rising. Fission Product Barriers, with imminent Loss of all charging and

loss of the third). St. If CO attempts to

restart "B" CCP, it will

not start. If "B" SIpump was not running at0615, CO may start "B"SI pump, if so, it will

3555-0 S.3-10 Rev.10/23/90

w ._ -_ _ _ _ _ _ _ _ _ _ __________ ______-_____ _ ________ ___ ______________________________ _ ______ ___ ____________ _ ____ ___________ ._. _ _ _ _ _

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- SCENARIO CONTROLLER GUIDE

[ TIME MSG. FROM TO ' EVENT SUNMARY ' ANTICIPATED _ RESPONSE .CM CONTROLLER- NOTES 4

NO. i,

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O630 trip and ' controller will~

Contd deliver me, sage 14-C.

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0645 - -- - Sewral Core Thermocouples indicate Positise indication oftemperatures in the vicinityof 714F challenge to the third .i

fission product barrier.,

0700 16-C C-5 EOF Declare a GENERAL EMERGENCY by Deliver this message only !

| / EC Module 2, Step 6 (Loss of. 2 Fission if a GENERAL'

Product Barriers, with imminent loss of EMERGENCY has notthe third.) OR_ . by Module I, Step . 7 yet been declared.. EC .;

(fligh Dose Projection: ARMS or PRMs may declare GEo based i

indicate greater than 1 R/hr WD or 5 on . Module 1 Step 7 if i'

R/hr to the thyroid at the Exclusion ARMS and PRMs show f

j Area Boundary.) sufficient increase priorto other indications offuel clad being i

endangered.:!,

,0700 17 C-4 RT "B" CCP Breaker indicates tripped.

.

Switcheear Room Deliver to RT when they -

.,

at "B" RT replace faulty CCP Breaker with a arrive at "B" CCPd4

.i CCP spare (either "A" CCP Breaker or "C" breaker. Indications are-Bkr service wIter pump breaker. Complete '"tr phase overcurrent'

-0800 relay flag is up. Pumpmotor temperature is |'

normal, motor resistance '!

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3555-0 5.3-11 Hev.10/23/90'

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SCENARIO CONTROLLER GUIDE,

, TIME MSG. FROM TO EVENT SUMMARY ' ANTICIPATED RESPONSE CM- CONTROLLER NOTESNO.

is ' greater than 5 Megohms.

Fault on "B" phase,short to' . ground, requiresbreaker . replacement . orrepair.

07G3 - - - STATUS OF TiiE PLANT:Operators should concentrate on

The plant : has suffered a '.OCA with restoration of CCP *B" by switchingfailure of all ECCS due ' to a leak in power supply breakers to provide cooling

,

'the RIIR system.. Ilumidityand flooding for the . . core, and on repairs to the

from the LOCA has disabled both SI power supply cable for MO-8700A topumps. "B" CCP tripped due to an isolate the LOCA and secure the release.internal fault on it's supply breaker "B" ;

phase, requiring breaker replacement, or |ground location and correction. ;

0800 18-C C-4 RT Spare Breaker is installed for "B" CCP, Switchgear Room Delier this messageat "B" Breaker resets normally. when RT has completedCCP. ?RT inform OSC, OSC inform SS. breaker replacement.Ukr. SS start "B" CCP to provide cooling for I

the core. Ensure C-2 inSimulator is informedprior to RT. informingOSC of repair. CETsbegin to lower on +

restoration of charging.L

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3555-0 5.3-12 Rev.10/23/90

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SCENARIO CONTROLLER ' GUIDE ...;

TIME MSG. FROM TO EVENT SUMMARY ANTICIPATED RESPONSE- CM- CONTROLLERL NOTES iNO. .

.,;

at complete.. Switcheear Room Deliser ~ this message0830 19-C C-4 RT' MO-8700A'. power cable replacement is

..RT inform OSC. OSC inform SS.. when RT- has completedMO- SS' clear . tags and shut : MO-8700A to cable repair.87004 . terminate the release. |

All Facilities {Commence recovery discussions.-

1000 20 AC AP SECURE FROM THE DRILLi

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SECTION 6.0 -MESSAGES,

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3555/NUCL-1429

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6.1 Messages

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| ' 3555-4/NUCL-1422 6.1-1|

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* THIS IS A DRILL *

Real Time: 0X!0.

Message No.: IC-1.Elapsed Time: .QQJ1

Ii

~ TROJAN NUCLEAR PLANT

EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM q

|

- Message Fort AP- - i

Message: * THIS IS A DRILL * - |,

,

'1

I

INITIAL CONDITIONS: I

- The plant is at 100% Power,100% flow, Late in fuel cycle (Maximum decay heat).'

The following evolutions"are in progress:,

-: Maintenance on the 'A' EDG output breaker. Breaker is tagged out and disassembled for. routine j

Linternal inspection. 'A" train ECCS is out of service while the breaker is being worked. Estimated ~ . i

. completion time for this work is 2 hours additional work, scheduled for completion on the day shift;

. A' Coolant charging pump has'a motor winding short, and is tagged out. Pump will be re built during*

the upcoming outage. ,

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- FOR CONTROLLER USE ONIX!

Controller Notes:_ All personnel should be aware of plant conditions,

l~ Actions Expected:L

.

- 3555 0 6.1 2 REV. 08/22/90

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*" Tills IS A DRILL "*

Real Time: 03yt

Message No. LElapsed Time: 0015

TROJAN NUCLEAR PLAST

EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM

Message Fort Steurity Guard at3ccess Control Point

Message: '" Tills IS A DRILL "*

You noticed a bright flash and a loud "txxim" near the south end of the Turbine Building.

FOR CONTROLLER USE ONLY

Controller Notes: Explosion of a hydrogen bottle near the south wall of the turbine building.

Actions Expected: Security notify the control room, and send a guard to investigate.

3555-0 6.1 3 REV. 08/22/90.

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* Tills IS A DRILL * ' 4: 1

' Real Time:,,93DO,,

'- Message No' l ;- ;

Elapsed Time:.DQ11+

I

TROJAN NUCLEAR TtANT!

]qjf ' EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM ~|

i Message For: f..i'

. uMessage: * TIIIS IS A DRILL * '

Controller pass the following report to the SS:. . . 4

I just dropped 'a hydrogen cylinder that I was carrying and it fell on it's cap.iThe bottle -.

sounded as if it-might be leaking. As I was coming over ;o the phone to notify the Control "

N, . . Room, the bottle exploded. Fragments flew all over the place. Some appear to have penetratedy, the south wall of the Turbine Building.

.

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L FOR CONTROLLER USE ONLY

Controller Notes: Worker is unhurt.L Fragments have penetrated the. turbine building wall. No damage >| to equipment. , Some of the area lig,hting around the south wall of the Turbine Building - 3

m 'has been damaged by the blast, hmdering inspection of the site,

t' Actions Expected: . C-4 inform Control Room, and brief security if they go to in'spect the scene. Security=

. inform control room.~ SS direct a detailed inspection of the TB to determine damage.';

L SS declare an ALERT per Module 14, Step 2 (Explosion in the vicinity, causing damageI to plant structures or equipment.)

IL s

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3555-0 6.1 4 REV.10/09/90.

..N- n -Y.-.-..---.--- . - - . . - . . . - . -e, 4 --e,- 4rn , , - , . .g , ,

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- * Tills IS A DRILL "* - '

? Real Time: QM1

t Message No, 2-f_ '

'iTROJAN NUCLEAR PLANT

*

EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM'

,

Message For: SS.,

' Message: * Tills IS A DRILL * -F

i

Declare an ALERT per Module 14, Step 2 (Explosion in the vicinity, causing damage to plantstructures or equipment.)

> L

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FOR CONTROLLER USE ONLY-,

l, Contrhlier' Notes:-- Deliver this message only if an ALERT has not yet been declared at the above time._ ,

.

b;'

SS declare the ALERT. Activate TSC ~and OSC. Make required notifications.. Actions Expectedt.

h

. Make the fallowing PA announcement immediately prior to passing the ALERT..

' ' '

declaration:

' Attention all personnel, We are now commencing an Emergency Drill. -Designate'd ';;. personnel should respond to all announcements as though this were a real emergency.

Unaffected personnel should remain at normal work stations. 'If an actual incident? *

occurs, an announcement will be made directing the appropriate response.

3555-0 6.15 REV.10/09/90

,

.-Ga.--,

er - - . . - .s .,, . , , ,

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'" Tills IS A DRILL *"

Real Time: OG)*

hiessage No. 4Elapsed Time: 0115 *


EhtERGENCY PREPAREDNESS EXERCISE htESSAGE FORhi

hiessage For: RT at Turbine flullding,

blessage: *" Tills IS A DRILL *"

hiany sharp fragments of the hydrogen bottle are scattered over the roadway to the south ofthe building. Damage to the building seems mostly cosmetic, no structural frames have beenseen to be affected. There are several relatively large holes in the south wall of the turbinebuilding, and the large garags access door is jammed shut. Further inspection for affectedcomponents is in progress. Na component damage has been found.


Controller Notes: * Deliver this message upon Repair Team inspection of Turbine Building damage.

Actions Expected: Be aware of plant conditions.

3555 0 6.16 REV. 08/22/90

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= 0 * T9IS IS A DRILL *

', Real Time: 0430 *'

,

Message No.X~

Elapsed Time: 0115 *,

. |

,r


EML.'IGENCY PREPAREDNESS EXERCISE MESSAGE FORM.

/

Message For: Renalr Team at 'A' EDG Breuker_ -

,

. Message: * THIS IS A DRILL *

s The "A" EDG Breaker is tagged out for routine inspection and calibration. it is partially .;disassembled.- Completion was scheduled for the morning shift. i

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FOR CONTROLLER USE ONLY j

Controller Notes: . Deliver this message if a repair team is despatched to the "A" EDG breaker. Allow . i

= the team to restore the breaker if they attempt to do so.- Restoration of the breaker,

will not significantly affect the scenario.; !

) Actions Expected:' RT inform OSC, OSC inform control room.- RT, prepare to re assemble the breaker.

I|Li

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3555 0 6.1 7 REV. 08/22/90!

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* THIS IS A DRILL *

Real Time: 0100,

Message 'No. (d'_. "Elapsed Time: QBi

TROJAN NUCLEAR PLANT ,


..

Message Fort SS/ CO

Message: * Tills IS A DRILL *

. ANNUNCIATORS IN CONTROL RO.QM

. K 12 "A" RHR Pump Discharge Pressure High (C7) ~K 12 - B" RHR Pump Discharge Pressure Hgh (C8)

"

K 01 PRM Trouble - (A1) i

K-01 PRM 2 Radiation. Alert (B1).K-01- PRM 2 Radiation High

. (BI) .

~

K 11' Pressurizer Control Level Low (B1)*

uK 13 Pressurizer Pressure Low . Heaters On (B2)'- .,

.K 11. *B" CCP Auto Start (D2) -

INDICATIONS IN CONTROL riOOM

RHR cooler outlet temperature indicates 400 F

.\

l

i

q


= Controller Notes: Deliver this message only if proper indication is not available from the simulator, t

LOCA has started from MO 8701 and' 8702 leaking by their shut seats.

= Actions Expected: Be aware of plant conditions. Operators take action for LOCA per El 0: Trip.thereactor and initiate manual Safety injection.

, 3555-0 6.1-8 REV. 08/22/90t

.

-4 +r - = .y - ,--vv e- r t

, ..- -. ,.- .- - . . . - , . . . - - . . . . . - - . _ . -..,

t t

:

h i

* Tills IS A DRILL *

Realtime: DiOL 1

, Message No,' 7 C..i.

; Elapsed Time:J)1%1

'


. EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM .|

ic Message For: SS/ CO'

Message: * THIS IS A DRILL *c

ANNUNCIATORS IN CONTROL ROOM. :

K 21 . Safety injection Actuation (A2) -K-16 Turbmc Trip, Reactor Trip . (E1)K 21 Rod Bottom J (F1)K 21 Rods 2 or more at Bottom . (A6)K 21 . CIS "A" Actuation . (A6)K 18- Feedwater Isolation (ES)K 15 ;"A" Main Feed Pump Turbine Trip (F2) :

K 15- *B" Main Feed Pump Turbine Trip (F3)>

K 21' "A" SI Pump Auto Start (C3) j'

K 21 'B' Sl Pump Auto Start (C4) '-

K 11 Pressurizer Level < 17%- (A1)K 12 . A* RHR Pump Auto Start (A7) ;"

K 12 'B" RHR Pump Auto Start (A8) -!K 12- "A" RHR Pump Flow Low -(C71K-12 fB" RilR Pump Flow Low (C8)

,,

1

FOR CONTROLLER USE ONLY..

Controller Notes: - Deliver this message or.ly if proper indication is not available from the simulator,.and I

after operators insert manual reactor trip, and initiate Safety injection per EI.0.

t

|J Actions Expected: Operators take action to complete EI 0 for a manual Reactor Trip, and transition to'

. ECA 1.2.

.!

3555 0 6.1 9 REV. 08/22/90

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o'. . _ . - . - - . .

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!, +

. . ,

|'n:

1

x

* Tills IS A DRILL * -

Real Time:_0111 ,

4 ,

*Elapsed Time:.0200.->

,-

TROJAN NUCLEAR PLANT,

-.

EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM ;

e ,

Message' Fort Emernency Coordinator'

' Message: *** Tills IS A DRILL *'

* Declare a SITE AREA EMERGENCY by Module 2, Step 5 (Loss of 2 Fission Product Barriers).QB 3

by Module 1,- Step 3 (liigh Dose Rate, based on PRM 2)

'

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,

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,;

FOR CONTROLLER USE ONLY-

Controller Notes: Deliver this message only if a SITE AREA EMERGENCY _has not yet been declared,EC may declare SAE based on Module 1 Step 3 if SS is delayed more than a few.minutes in the analysis and reporting of the RHR system LOCA as a LOCA outside,,

: ,,- of the containment.,

iiF

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,t ,

Actions Expected: EC declare the SAE. Activate EOFif not already done. Make required notifications.'

a

4

3555 0 ; 6.110 REV.10/09/90 -

_ - . ._ . _ __ _ . _ _ .- _ _ . . . _ _.. _. . - . . _ . . . _ . . .

- _ _ _ _ - _ _ _ _ _

"* Tills IS A DRILL "*

Real Time: . 0515

hiessage No. 9 C --Elapsed Time:RQQ,


EhtERGENCY PREPAREDNESS EXERCISE htESSAGE FORht

hiessage l'or:_ CO / SS

hiessage: *" Tills IS A DRILL "*

h10 8700A position indicator lights are out.


Controller Notes: Deliver this message only if proper indication is not available from the simulator,aQnCO attempts to shut h10-8700A to isolate the LOCA. Valve fails to operate electricallydue to failed power supply cable on the load side of the motor operator power supplybreaker.

Actions Expected: CO inform SS. SS inform TSC and OSC OSC set up repair teams to investigate h10-8700A.

3555-0 6.111 REV.10/23/90

_ _ ___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ - -___ _ _ _ _ _ - _ _ - _ _ _ ______-__ - _ _ _ _ _ _ ____

ma - __ _ . . _ . _ _ _ . . _ _ ... _

~~ x - .

'

'.;;

'

*** Tills IS A DRILL ***

Realtime: 053L.

Message No:- 10 CElapsed Time:_Q2,15.

TROJAN' NUCLEAR PLANT


Message Fon SS / CO

iMessage: **? Tills IS A DRILL * .I

.IANNUNCIATORS IN CONTROL ROOM

K 21 "A" S1 Pump. Motor Overload ~- (E3)'

INDICATIONS IN CONTROL ROOM i"A" St Pump indicates tripped . - |

Aux Building Sump west level high, ij

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'

- FOR CONTROLLER USE ONLY

- Controller Notes:-- Deliver this message only if proper indication is not available from the ' simulator, "A"

:i!~.

'SI Pump is flooded out by high humidity and rising reactor coolant Icvel in the Aux..

LBuilding west sump. . t

,

? Actions Expected: CO report to SS. SS report to TSC and OSC, CO may attempt to restart "A" SI pump.Pump will re start and trip within a few seconds if they do

,'

'f ,

-3555-0 6.1 12 REV. 08/22/90-

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.

6 ~ -- 6-. s .- ,w. + r e .

, , . - . 3 , - _ . . . - - .~ - -- - . .

.i-c'

,.

* THIS IS A DRILL *7c ,

~ Real Time: ora)

Message No..,_1L. -- Elapsed Time:_0241

.

TROJAN NUCLEAR PLANT,


.. Message For: RT for MO-8700A

Message:7 * THIS IS A DRILL * - >

Conditions in the' Auxiliary Building: Temperatures are above 130 F near the entrance to the building. j; Visibility is near zero in steam. : llumidity is 100% '

.i'

;

i

;,-

i

.


- Controller Notes:- Deliver to RT leader at the entrance to the Auxiliary Building. RT should realize heatj .istress and' contamination are problems 'of great concern. If they elect to proceed,1

~

'- ',

conditions will worsen to 150 F as they approach:MO 8700A. Obtain local area--'

radiation levels and contamination levels from inplant maps.._

L, '

|'

RT be aware of conditions in the Aux Building and take proper precautions.-- ' Actions Expected:-

e

?

3555 0 - 6.1-13 REV. 08/22/90

i

.. . . . ,, ,. , . _ . , . . ,. - , , - , = - - . ,. .

. ..

_____-____________ _______ .___ _

| "* Tills IS A DRILL ***

Real Time: Omo

hiessage No.1Elapsed Time: 0241

TROJAN NUCLEAR PIANT

EhiERGENCY PREPAREDNESS EXERCISE hGSSAGE FORhi

hiessage For: RT AT N10 8700A Breaker-

hiessage: "* Tills IS A DRILL "*

htO 8700A Power Supply Breaker indicates tripped. No other abnormalindications are visible.


Controller Notes: Deliver to RT trou'aleshooting the breaker when they arrive. Cause of trip is worninsulation on load * ide cabling. Cable is shorted to ground. If they replace the breakerwith a spare and attempt to operate the valve electrically, the spare will trip. A slightsmell of burniag insulation will result from the second reset and trip. When RT pullsout the breaker again, the power cables on the load side are now visibly burned, andmust be replaced. Enough cable must be burned to force warehouse participation, byrequiring pulling of spare parts

Actions Expected: RT troubleshoot. When fault is determined, inform OSC, Control Room.

3555 0 6.1 14 REV.10/09/90

_ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ____ _ _

- - - . . .- - - - - - ..-- .- -. -.

P

* THIS IS A DRILL *

Real Time: ,.0f211

- t

***"8' ""' AElapsed Time: 0300.

.



. Message For: RT at MO 8700C

Message: * THIS IS A DRILL ?**

Conditions in the immediate vicinity of MO 8700A, temperatures 150 to 165 F, Visibility nearzero. Valve body, piping, and operator are hot (~200 F), and are operating stiffly.

!

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FOR CONTROLLER USE ONLY. ;s,

Controller Notes: Deliver to RT when they reach MO-8700A Valve operates stiffly due to.high,-temperature and flow through the valve. Stay time in the area due to heat stress is .

,

. very limited. Operators will feel faint after 1 Minute of operating MO-8700A, and will|: collapse'after an additional minute if they do not stop.

,

cp Actions Expected: ' I

3555 0 6.1-15 REV. 08/22/90;

,

. - - . 6 . a-_._m __ + , _ - _m.- - -. v -m. -

. . _ . - . _.-r.___ .. _ . , _ _ __. _ ,-_ _-

.

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* THIS IS A DRILL * -r

Real Time:.M]1

Message No. 14 C '

TROJAN NUCLEAR PLANT i

EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM ,

Message Fon CO / SS.

hiessage: * Tills IS A DRILL *

ANNUNCIATORS IN CONTROL ROOMb

K 21 "B" S1 Pump Motor Overload . (E4)K 21 . B' St Pump Auto Trip (D4)-

*

INDICATIONS IN CONTROL ROOM .('B' St Pump indicates tripped .

- Aux Building Sump East level high.

i

.

4


. Controller Notes: . Deliver this message only if proper indication is not available from the simulator AtQif'B' St Pump is running at 0615. Pump trips on overload due to progressive flooding.of the east sump by overflow from the west sump, and due to high humidity, if pump _

as not running at this time,'it will trip on overload with the above indication when .wstarted. If OSC attempts to send a team into the Auxiliary building to investigate, high .

radiation levels (from in. plant maps) will be provided by controller to prevent access,

e

Actions 5'.xpected: . CO may start "B" CCP if not already running to supply core cooling. If CO attemptsto re start "B' SI Pump, it will immediately trip.- ;j

3555 0 6.116 REV. 08/31/90

. _ . .. .

i

)

!*" Tills IS A DRILL "*

Real Time: 0630 )

Message No. 15 C...Elapsed Time:0211

|



Message For: SS / CO

Message: "* Tills IS A DRILL *"

ANNUNCIATORS IN CQNTROL ROOM

K ll "B" CCP Auto Trip (E2)

INDICATIONS IN CONTROL ROOM"B" CCP Pump indicates tripped.Aux Building Sump East level high-high.

t

FO? CONTROLLER USE ONLY

Controller Notes: Deliver this message only if proper indication is not available from the simulator. Lossof"B" CCP due to a fault in the supply breaker. Loss of all charging and St. If COattempts to restart "B" CCP, it will not start, if "B" SI putap was not runrdng at 0615,CO may start "B" SI pump, if so, it will trip and controller will deliver message 14 C.

Actions Expected: SS notify TSC and OSC. OSC send a RT to investigate. TSC notify EOF, EC declarea GENERAL EMERGENCY based on Mod. 2 Step 6 (Loss of 2 Fission ProductBarr':rs, with imminent loss of the third).

3$35 0 6.1 17 REV.10/23/901

_ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _

- . --. . . . . . . ~ _ - . ._ . ._. . _ .- - , . . . . . _ . . . . . _ _ _ _ _ .

t

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.

,

hJ *** THIS IS A DRILL *** -' '

L

.Real Time: 0200. 'i

' Message No.' 16-C .

Elapsed Time:_021

-


- EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM,

Message For: EOF / ECI

Message: *** Tills IS A DRILL ***,

. . .

Declare a GENERAL EMERGENCY by Module 2, Step 6 (Loss of 2 Fission Product Barriers,. with imminent loss of the third.)

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;

* FOR CONTROLLER USE ONLY.,

!

Controller Notes: Deliver this' message bnlyif a GENERAL EMERGENCY has not yet been declared; '

EC may declare GE based on Module 1 Step 7 if ARMS and PRMs show sufficient i

increase prior to other indications of fuel clad being endangered.

m; ; Actions F.xpected:

l- '~a a}

3555 0 6.1 18 REV.10/09/90

,

< .-v - . - - - -,4 ., -- -,.--._,.-r .- .,-- e r-, . ,

. - . _ - .. -. - - . - - . . .-. . . . - . . . . - .

!.

t

*** THIS IS A DRILL *** i!

Real Time:,0100,-

hiessage No. 17~

Elapsed Time:_0.,4_1


EhtERGENCY PREPAREDNESS EXERCISE hiESSAGE FORhi,

- Message For: RT at 'H' CCP lireaker ,

-[hiessage: *** Tills IS A DRILL *** ;(

,

'B' CCP Breaker indicates tripped. "B" phase overcurrem relay flag is up.)

i

*..

4 .

_ ': \ .

!

L,!.

;

= FOR CONTROLLER USE ONLY

Deliver to RT when they arrive at *B" CCP breaker, Pump tripped due to phase to -Controller Notes: .ground fault in''B' phase internal to supply breaker. Device 150G, ground relay - 1

_ ;

overcurrent. flag is up, providing additional indication to the teams if they check._

Actions Expected: RT replace faulty CCP Breaker with a spare. Expected completion ~0800

35$5-0 - 6.1 19 REV. 09/04/90

. . . - - . . - . - . .

. -. .. .... . . . . _ - . - . . = . . ~ , - . . . - . .- .

:J

u

^, ,

~ * THIS IS A DRILL * . ,!, 1,

Real Time: 00.00!

Message No.18 CElapsed Time: Qill i

-;

TROJAN NUCLEAR PLANT -

EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM :|1 , .

- Message For: Renalr Team at "H' CCP Hreaker

Message: .* THIS IS A DRILL * ,.

-f,

,

. Spare flreaker is installed for 'IP CCP,13reaker resets normally.s

;

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!

; FOR CONTROLLER USE ONLY [,'

iController Notes: : Deliver to RT if tlky have not yet completed breaker replacement. Controller ensurethat C.2 (Simulator) is informed prior to RT infarming OSC of repair.

< Actions Expected: Core Exit thermocouples begin to lower upon restoration of %rging, .,. .

t

|

3555 0 6.1 20 ' REV. 08/22/90 -

-

-g.

I. . . . - . . .

_ _ _ _ _ _ _ _ - _ - . _.

'" Tills IS A DRILI. "*

Real Time: .py)1

Mesuge No.12;.C.Elapsed Time: f.111.


EMBRGENCY PREPAREDNESS EXERCISE MESSAGE FORM

Message fort EnudtIcam at MO 870% Itreaktt.

Message: "* Tills IS A DRILL "*

MO 8700A power cable replacement is complete.

.

FOR CONTROLt.ER USE ONLY

Controller Notes: Deliver this message when RT has completed cable repair. Controller ensurethat C 2 (Simulator) is informed prior to RT informing OSC of repair.

Actions Expected: CO shut MO.8700A, and secure the release. All facilities, commence recoverydiscussions.

3555-0 6.1 21 REY. 08/22/90

-_ _ _ . _ . _ . _ _ _ _ - __ ______ - _ _ - _ _ ___ - ____ -

.- . _ _ _ _ _ - _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ __ _ _ ____ __ . _ _ _ . ____

m Tills IS 4 DRit L "*

Real Time: 1(m

Message No. 2(LElapsed Time: (w41



Message Fon.Al'

Message: "* Tills IS A DP.ILL "*

SECURE FROM Tile DRILL

:

l'OR CONTROLLER USE ONLY

Controller Notes:

| Actions Expected: -

3555-0 6.1 22 REV. 08/22/90

. --

_- - - - . . . -_. -. . .- . _ . . - . . -- . - .... . - . . - . . -_-..

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SECTION 7,0 PLANT PARAMETERSe

.

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|-

L 3555 4/NUCL-1429

<

~us- r ~ w - - , -,-w,- r , , , - - - , -- p w , , . ,- 4 ~ - e- w - - -' ,

- _ _ _ _ _ - . _- ___ ___ _ __ - _ _ _ _ _____

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7.1 MimthtametcLSitmmary

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1

3555 4/NUCL 1429 7.1 1

!

- - _ _ _ _ . _

TROJAN PLANT PARAVETER SUMM A";Y TAILE

TIVE OF D AY 3 15 3 30 3 45 4 00 4:15 4:30

EL APSED TIME O 00 0 lb 0.30 0 45 1 00 1.ib

RCS Parametera

1. RCS Pressae (Part 2233 09 2233 06 2233 06 2233 06 2233 06 2233 06

Saturation Pre sture 1965 60 1905 60 1905 60 19(5 60 1905.00 1905.60_

2. PZR Leset (%) 61.34 61 54 61.54 61.54 61 54 61 54

Trend O O O O O O

3. PZR LIO Temp ' Steam Te mp toeg Fi 053 653 053153 053 65., 053 053 653 653 053 053

4. RVLfS SCALE OY N AMIC O Y N AMIC OYNAMIC OYN AMIC OY N AMIC OYNAMIC

5 Reactor vesseltvl(%) 120 00 120 00 120.00 120 00 120 00 120 00

6 Auct High Nuclear Pwr (%) 99 31 99 30 99 30 99 30 99 30 99 30

7. CET Ave ide9 FI 609 27 609.25 609 25 609 25 609.25 609 25

B. CET Hi toeg Fl 629 02 629 00 629 00 629 00 629 00 029 00

9. S/C Margin Ideg F) 25.74 25.76 25.76 25 70 25,76 25.76

10 LtD Rate (GPMI 77.23 77.23 77.23 77 23 77.23 77.23

L oop Parameters

1. T Hot

A 609 42 609 40 609 40 609 40 609 40 609 40

B 611.67 611 65 61105 611 65 611.05 611.05

C 600.64 600 62 600 62 600 62 608 62 608 62

0 612.56 612.54 612.54 612 54 612.54 612.54

2. T Cold

A 551.85 551.83 551.83 551.83 551.83 551.83

D 552.77 552.75 552.75 552.75 552.75 552.75

C 552.48 552.47 552.47 552.47 552 47 552 47

0 554.51 554.49 554 49 554.49 554 49 554 49

3. T Ave

A 581.87\ 581.88 581.88 581.88 581.88 581.8 F

B 583 47 583 44 583 44 583 44 583 44 583 44

C 581.81 581.79 581.79 581.79 581.79 581.79

D 564.77 584.73 584.73 584.73 584.73 584.73

Trend pA O O O O O O

B O O O O O O

C O O O O O O

D 0 0 0 0 0 0

4. RCP Statu6

A RUN RUN RUN RUN RUN RUN

B RUN RUN RUN RUN RUN RUN

C RUN RUN RUN RUN RUN RUN

D RUN RUN RUN RUN RUN RUN

FLOW (%) 100,14 100.15 100.15 100.15 100.15 100.15

6.$!G Press

A B55.70 855.75 856.13 858.57 856.59 B56.39

B B57.20 B56 BB B56.70 B57.92 856.35 856 00

C B56.70 857.37 857.63 858.09 858.61 858 95

D B55 30 854.9) 054 58 853.84 853 53 853 20

Trend . 0 +

A O + + + . +

B O + + + - I

3555 0 7.1 2 Rev 10'22:00

_ - _ _ _ _ _ - _ _ _ _ _ _ _ _ __ _ _ - - _ _ _ - _ _ _ _ - _ _ _ ____- _ _

_. _ _ _ _ _ _ . . _ _ _ __ __ _ _ _ _ - _ . . _ _ _ _ _ . - . m -_..________.._______.m _ _ _- _

l

TROJAN PLANT PARAMETER SUMM ARY T ABLE1

, TIME OF D AY 3:15 3 30 3 45 4 00 4:15 4.30J IL APSED TIME 0-00 0 16 0.30 0 45 1:00 1:15

C 0 + + +

0 0 - + . + -

6. B/G Levet (NRI

A 44.19 44 17 44.17 44.17 44.17 44.17

( B 43.36 43.34 43.34 43.34 43.34 43.34

C 44.14 44.12 44.12 44.12 44.12 44.12

0 43.79 43.78 43.78 43.78 43.78 43.78-

7. $/G Level (WR)

A 55.27 55.26 55.26 55.26 55.26 $5.26

R 55.04 55.03 55.03 55.03 55.03 55.03

C 55.25 55.25 55.25 55.25 55.25 55 3D 55.16 55.15 55.15 55.15 55.15 55.15

Trend . 0 +

A 0 0 0 0 0 0

B O O O O O O

C 0 0 0 0 0 0

D 0 0 0 0 0 0

D. Bteam Flow (1.Or6 LBMm -

A 3 65 3 65 3 65 3.65 3 65 3 65

B 3.79 3.79 3.79 3.79 3.79 3 79

C 3 65 3.65 3 65 3 65 3 65 3 65

0 3.79 3 79 3.79 3,79 3.79 3.79

9. Feed Flow (1.or6 LHIHR)

A 3.68 3.68 3.68 3.68 3.68 3.68

8 3.83 3.83 3.83 3.83 3.83 3.83

C 3.68 3 68 3.68 3.68 3.08 3.68

0 3.82 3.83 3.83 3.83 3.83 3.83

10. MSIV Status

A NT CL NT CL NT CL NT CL NT CL NT CL'

8 NT CL NT CL NT CL NT CL NT CL NT CL

C NT CL NT CL NT CL NT CL NT CL NT CL

D NT CL NT CL NT CL NT CL NT CL NT CL

91. AFW Flow (GPM) .

A 0.00 0 00 0OL 0.00 0.00 0.00

8 0.00 0.00 0.00 0.00 0.00 0.00

| C 0.00 0.00 0.00 0.00 0.00 0.00

( 0 0.00 0.00 0.00 0.00 0.00 0.00

TOTAL 0.00 0.00 0.00 0 00 0.00 0.00

12. CST Level t%) -

A | 71.07| 7166| 71.66| 71.66| 71.66| 71.66|Engineered Saf eguards Features

1. Containment

Pre ssure (PSIGl 0.21 0.21 0.21 0.21 0.21 0.21

t Humidity (%) 41.60 41.69 41.69 41.69 41.69 41.69I

Hydrogen Cone. (%) 0.00 0.00 0.00 0.00 0.00 0.00

NR Cont. Sump Lvl (IN.) 13.11 13.11 13.11 13.11 13.11 13.11

WR Cont. Lvl (IN.) 13.11 13.11 13.11 13.11 13.11 13.11

3555 0 7.1 3 Rev 10/22/90

, . - .- - . - . . . _ .. - -- .- , . . - .

TA0JAN PLANT PARAMETER SUMM ARY TABLE

VIME OF DAY 3:16 3.30 3 46 4:00 4:16 4:30

EL APSED TIME 0.00 0:16 0.30 0 46 1:00 1:15

Rad' tion tevel(Rhrl 1.00 1.00 1,00 1.00 1.00 1.00e

Contahment Spray NT ACT NT ACT NT ACT NT ACT NT ACT NT ACT

NaOH Tank Levell%) 96 40 96 40 96.40 96 40 96 40 96.40

a. RVVST Level 99.83 99.83 99.83 99.83 99.83 99.83

3. CtB NO NO NO NO NO NO

4.AFW TDAFWP OFF OFF OFF OFF OFF OFF

DAFWP OFF OFF OFF 0FF 0FF 0FF

Elec. AFWP OFF 0FF OFF OFF OFF 0FF

5. Befetylniection Actuated NOT ACT NOT ACT NOT ACT NOT ACT NOT ACT NOT ACT

(6.FWI Actuated NOT ACT NOT ACT NOT ACT NOT ACT NOT ACT NOT ACT

7. Foulpment Status

EDGi

Trah A OOS 00S 00S DOS 00S OOS

Treh B AVAll AVAll AVAIL AVAll AVAll AVAll^

EDG BKM

Train A DOS 00S 00S 005 OOS 00S'

Trah A OPEN OPEN OPEN OPEN OPEN OPEN

CCP'

Train A OOS 00S DOS 00S 00S DOS

Trah 8 0FF OFF OFF OFF OFF OFF

Flow 0.00 0.00 0.00 0.00 0.00 0.00iSI(OPM)

Tram A 0FF 0FF OFF 0FF OFF 0FF.

Trah 8 0FF OFF OFF OFF 0FF 0FF

Flow 0.00 0.00 0.00 0.00 0.00 0.00

RHR10PMI- < *i

Train A 0FF OFF 0FF OFF OFF 0FF

Trah 8 0FF OFF OFF OFF - 0FF OFF

Flow 0.00 0.00 0.00 0.00 0.00 0.00

CCW2 - -

Train A ON ON 07j ON ON ON

Trah 8 0FF OFF OFF OFF OFF OFF2SWS' W ++ --

Train A ON ON ON ON ON ON

Trah B 0FF OFF 0FF OFF OFF 0FF-

CSP -'' C-

,

Train A 0FF 0FF OFF 0FF OFF OFF

Tra h 8 0FF 0FF OFF OFF 0FF OFF

CAC VC201 ' #*

| -Trah A OFF OFF OFF OFF OFF OFF

Train B ON ON ON ON ON ON

CAC.VC202 :

Trah A 0FF 0FF OFF OFF 0FF OFF

Trah 8 ON ON ON ON ON ON

CAC.VC203 :

Train A 0FF 0FF OFF OFF OFF OFF


3555 0 7.1 4 Rev 10!22!90

|

E._ . . - - . - . _ . . . _ _ _ _ . . - . _ _ ~ . . - . _ _ _ . _ . _ . ~ . . _ . _ . . , _ . _ . ,_._ - . . . - _ . . -

.. __- .-. ._- _- . - . - . - . . . _ . - . - . . , . ~ . _ . _ . _ _ _ - . . - .- .. ~-

1

] VROJAN FtANT PAR 4.MITTR SUMM ARY T ABLE

TIME OF D AY 3:16 3:30 3 46 4:00 4:16 4.30

EL APSED TIME 0 00 0:16 0:30 0 46 1:00 1:16_

C AC VC204

Trah A ON ON ON ON ON |ON

Train B OFF OFF OFF OFF OFF |OFFMajor Ecuipment

Qeactef NT TRIP NT TRIP NT TRIP NT TRIP NT TRIP NT TRIP

Vurbbe NT TRIP NT TRIP NT TRIP NT TRIP NT TRIP NT TRIP

Generator NT TRIP NT TRIP NT TRIP NT TRIP NT TRIP NT TRIP

Electric Mant

Eraerg Busses AVAll AVAll AVAll A VAll 4.VAll A V All

Off she Power AVAll AVAll AVAll AVAll AVAll , AVAtt

isolations'

Reactor Coolant

PORV CLOSED CLOSED CLOSED CLO$tD CLOSED CLOSEO

Safeties NO FL NO FL NO FL NO FL NO FL NO FL

Letdown NT CL NT CL NT CL NT CL N1 CL NT CL

RCP Seal Retum NT CL NTCL NT CL NT CL NT CL NT CL

Main Steam

PORV NTISOL NT ISOL NTISOL NTISOL NTISOL NT ISOL

Safetle s NT AC NT AC NT AC NT AC NT AC NT AC

AFW Tutbine NT ISOL NTISOL NTISOL NTISOL NTISOL NTISOL

Fl-971 A!B O O O O O O

F1-970 A!B 0 0 0 0 0 0

CCW TR AIN C OFF OFF OFF OFF OFF OFF,

SW TR AIN C OFF OFF OFF OFF OFF OFF

I

!

I

|l

'

3555 0 7.1 5 Rev 10 2090

. . - . . . . _ . - .. - _.

_ _ _. _ ___ _. _ . _ _ . _ _ _ _ _ _ _ _ _ _ . . _ _ . _ - m_______ _ _ _ _ _ . _ _ _ _ _ . _

t

1

TQOJ AN PL ANT PARAMETEQ $UMM ARY TABLE

i TIME OF DAY 4 46 6 00 6:16 6 30 6 46 6 00

ELAPSED TIME 1:30 1 46 2 00 2 16 2:30 2 45

RCS Peremeters

1. QCS Pre at 'e (Part 2233 06 2232 93 1700.00 1700 00 1700 00 1700 00J Sa turetk,a Pre ssure 1966.60 1966 60 1226 88 1097.66 931.17 784 76

2. PZR L evel (%) 61.54 61 61 0 00 0 00 0 00 0 00

Trend O . O O O O

3. PZR LIO Temp' Steam Temp (deg Fl 663'663 663 663 666/666 647/647 629'629 602'602

4.QVLisSCALE OYNAMIC OYNAMIC FULL FULL ,F}RL FULL_

6. Qea ctor Ve ssel lvi l%) 120 00 120 00 92.03 69.12 86 21 83.30

6. Auct 6tigh_ Nuclear Pwr (%) 99 30 99 30 0 00 0.00 0 00 0 00_

7. CET Ave toeg F) 609 26 609.24 660 99 640 63 623.14 602.4F

8. UET HI(deg FI 629 00 628 99 670.98 666.68 637.71 618.46

9. BIC Margin (deo F) 26.76 26.76 .13.34 17.66 18.12 28 66

10. L'O Rete (GPMI 77.23 77.23 0.00 0 00 0.00 0 00Loop Perameters

1. T Hot

A 609 40 609 39 664.44 638.44 61602 606.26~

B 611.66 611 66 666.78 639.67 626.67 499 06'

C 608.62 608 61 663 98 638.12 619 96 624.66

D 012.64 612.63 666.10 639.80 616.77 601.21

2. T Cold

A 661.83 661.82 618.96 619.87 607.01 397.16'

B $62.76 662.74 620.42 516.92 496.49 428.99

C 662.47 662 46 619.48 620.24 468.26 401.11

0 664.49 664.48 620.12 601.20 499.67 414.47

3. T Ave

A 680.62 680.01 636.70 629.16 511.62 461.20

B 682.20 682.19 638.10 627.80 611.03 464.03

C 680.64 680.64 636.73 629.18 494.11 462.83

D $83.62 683.61 638.11 $ 20.60 608.22 467.84

Trend . 0 +

A . . . . . .

B - . . . . .

C . . . . . .

D . . + .

4. RCP Sta tus'

A RUN RUN OFF OFF OFF 'OtfB RUN RUN OFF OFF OFF OFF

C RUN RUN OFF OFF OFF 0FF

0 RUN RUN OFF OFF OFF 0FF

I FLOW (%) 100.16 100.16 4.68 4.19 3.68 0.90

6. 8tG Press

! A 867.22 867.72 1046.43 931.17 784.76 718.60

B 866.92 868.10 1097.66 931.17 866.68 666.61

C 858.62 869.38 1046.43 931.17 784.76 812.63

0 863.76 863.37 1097.66 931.17 784.76 680.86

Trend. 0 +

A . + +. +

B + + . + + .

3656 0 7.1 6 Rev 10/22'90

. , , _ ,

____ _ ____ _ _ - - - _ _ - - - - _ - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ . _ _ _ _ - - - _ - . _ _ _ _ _ _ _ .

1

1

TROJAN PLANT PARAMETER SUMMARY T ABLE

TIME OF 0 AY 4 45 5 00 Si15 5.30 6 45 6 00

EL APSED TIME 1:30 1:45 2 00 2:15 2 30 2 45

- - * + * +CO !D + + .

6. 8 /G Level (NR)

A 44.17 44.21 0 00 0.00 1.39 1 08 ,

B 43.34 43.37 0.00 0 00 0 82 1.67

C 44.12 44.17 0.00 0 00 1.34 1.92

0 43.74 4380 0.00 0 00 0.82 1.43

58/G Level (WR)I

A 55 26 55.27 52.67 59 82 65 54 0830| )

B 55.03 55.04 50.10 59.10 63 29 06 6d

C 55.25 55 26 52.55 59 82 65.37 676R

O 55.15 55.16 50 42 59.15 63.27 65.72:

' Trend. 0 4A I O + + + + +

B O + + + + +

C 0 + + + + +

0 0 + + + + +

8. Stes m Flow (1.0E6 LBMR)

A 3 65 3 65 0.00 0.00 0.00 0.00

0 3.79 3 79 0.00 0.00 0.00 0.00

C 3 65 3 65 0.00 0.00 0.00 0.00

D 3,79 3 79 0.00 0 00 0.00| 0 00

9. Feed Flow (1.0E6 L B/HRi

A 3.68 3.68 0.00 0.00 0 00 0.00

B 3.83 3 83 0 00 0.00 0.00 0.00,

C 3 68 3 69 0.00 0.00 0.00 0.00

D 3 83 3 83 0.00 0 00 0 00 0.00

10. MSIV 8tatus

A NT CL NT CL CLOSED CLOSED CLOSED CLOSED

h NT CL NT CL CLOSED CLOSED CLOSED CLOSED

C NT CL NT CL CLOSED CLOSED CLOSED CLOSED

D NT CL NT CL CLOSED CLOSED CLOSED CLOSED

11. AFW Flow (GPMl'

A 0.00 0.00 323.27 198.66 86.30 99.53

B 0.00 0.00 294.66 197.78 96.36 113.75

C 0.00 0.00 324.91 198.94 57.76 85.31

D 0.00 0.00 204.62 196.58 79.85 94.08_

TOTAL 0.00 0.00 1237.47 791.97 320.27 392.67

12. CST Level (%F

A | 71.66| 71.50| 68.63 66.54| 65.44| 64.27|Engineered Safeguaro. .*?atures -

1. Containment

Pre ssure (PSIGI 011 0.21 4.65 -0.72 0.75 0.76

Humidity {%) 41.69 41,77 55.21 51.10 49.78 49.15

Hydrogen Cone. (%) 0.00 0.00 0.00 0.00 0.00 0.00

NR Cont. Sump Lvt ilN.) 13.11 13.11 13.11 13.11 13.11 13.11

| WR Cont. Lvi {lN.1 13.11 13.11| 13.11 13.11 13.11 13.11

i

3655 0 7.1 7 Rev 10/22/90

- . -. .- - . ~ . . -- .- , -_. .-

,- I

!|

|

!- TQOJ AN PLANT PAR AMETEQ SUMM AQY T ABLE

l i

|-- - TIME OF D AY 4.46 6 03 b:16 6-30 6 46 6'00

i ELAP6ED TIME 1:30 1:46 2:00 2:16 2:30 2 461

l' - Redietion Level (Rlhri 1.00 1.00 1.00 1.00 1.00 1.00 1

Containment Spray NT ACT NT ACT NT ACT NT ACT NT ACT NT ACTI ,

NaOH ?ank tevoli%) 96 40 96.40 96 40 96.40 96.40 96.40 i

i 2. RWST Level 99.83 99.83 97,46 94.45 91.7i 89.61

| 3. CIS NO NO A A A A ,

4. # TW TDAFWP OFF OFF ON ON ON ON

h DAFWP OFF OFF ON ON ON ON

f Elec. AFWP OFF OFF ON 04 ON ON

6. Safety injection Actuated NOT ACT NOT ACT ACT ACT ACT ACT !;

] 6. FWl Actuated NOT ACT NOT ACT ACT ACT ACT ACT

7. touhment Statuad FDG

Tram A 005 OOS 00$ 00S DOS 00s"

i - Train B AVAll AVAll AVAll AVAIL AVAll AVAIL

tDG BKR ~

Train A 00S DOS DOS DOS DOS 00S

Train A OPEN OPEN OPEN OFEN OPEN OPEN

OCP- -

j

Train A OOS 00$ DOS 00S DOS DOS

Train B 0FF OFF ON ON ON ON'

I 0.00 0.00 344.35 360.35 377.45 394.90Flow

81 (OPMI,

'

Train * OFF OFF ON TRIP TRIP TRIP

Train B OrF OFF ON ON ON ON

Flow 0.00 0.00 428.94 393.86 0.00 491.84

CHR(OPM)- r -

Trah A - 0FF 0FF OFF OFF' 0FF 0FF

Train B 0FF OFF OFF 0FF OFF OFF,

| Flow 0.00 0.00 - 0.00 0.00 0.00 0.00

CCW : a4


Trah 8 0FF OFF OFF OFF OFF OFF

SWSi

Train A ON ON ON ON ON ON'

Train B 0FF OFF OFF On 0FF OFF

! C$Pi

Train A 0FF 0FF OFF OFF OFF |0FF

Train B 0FF 0FF OFF OFF OFF |0FF

CAC.VC20) '

Train A 0FF OFF OFF 0FF OFF 0FF

i -: Train B ON ON ON ON ON ON1

'OCAC.VC202 *

| Train A 0FF OFF OFF OFF 0FF OFF

Train B ON' ON ON ON ON ON

CAC.VC203 -

| Train A 0FF OFF 0FF 0FF OFF OFF


:|

3555 0 7.1 8 Rev 10/22/90 i

L _. _ . _ . . _ . , _ . . _ . _ . _ . . . . . . _ _ _ _ . _ . . _ _ - . . _ _ . _ . , . , _ _ . . _ . _ . _ _ . . . _ , , . , _ . _ , _ .- . . _ . _ . . . , , _ _ . . ,

. . - _ _ _ _ - . - -_. . . . . - . _ _ _ . . . _ _ . . . - _ _ _ . . . . - - - - - _ _ -

|1'

TQOJAN PLANT PARAMETER SUMMAQY f ABLE

TIME OF D AY 4 45 6 00 6:15 6:30 6 45 6:00

EL APSED TiVE 1:30 1:46 2:00 2:15 2:30 2.45

) CAC VC204 -

Train A ON ON ON ON ON ON j

Train B OFF OFF OFF OFF OFF OFF |M6)or Equipment

Reactor NT TRIP NT TRIP TRIP TRIP TRIP TRIP

Turbine NT TRIP NT TRIP TRIP TRIP TRIP TRIP

Generator NT TRIP NT TRIP TRIP TRIP TRIP TRIP

EOctrW: Plant

Emerg Busses AVAll AVAll AVAll AVAll AVAll AVAll

Off site Power AVAll AVAll AVAll AVAll AVAll AVAll

1&otations

Reactor Coolant,

PORV CLOSEO CLOSEO CLOSIO CLOSEO CLOSEO CLOSEO

Sa f etie s NO FL NO FL NO FL NO FL NO FL NO FL

Letdown NT CL NT CL NT CL NT CL NT CL NT CL

RCP Seal Return NT CL NT CL NT CL NT CL NT CL NT CL

Mah $ttom

PORV NTISOL NT ISOL HTISOL NT ISOL NT ISOL NTISOL

Saf etie s NT AC NT AC NT AC NT AC NT AC NT AC

AFW Turbine NTISOL NT ISOL NT ISOL NTISOL NT ISOL NT ISOL

Ft 971 AS O O O O O O

Fi 970 AS O O O O O O

CCW TR AIN C OFF OFF OFF OFF OFF OFF

fSW TRAIN C OFF OFF OFF OFF OFF OFF

|!

3555 0 7,1 9 Rev 10/22/90

- .-- . - . ., _ -. __ . . - .. . . _

TROJAN PLANT PARAMETER SUMM ARY TABLE

TIME OF DAY 6:16 6:30 6.46 7:00 7:15 7:30

ELAP$ED TIME 3 00 3:16 3.30 3:46 4:00 4:15

RCS Parameters '

1. RCS Pressure (Per) 1700.00 1700 00 1700.00 1700.00 1700.00 1700.00

Saturatinn Pressure 656.61 1431.60 3094.30 3094.30 3094.30 3094.30

2. P2R Level (%I 0.00 0.00 0.00 0.00 0 00 0.00

Trend 0 0 0 0 0 03. PZR LIO Temo/ Steam Temo ideg FI 497/497 636/536 631/F31 627/B27 529 629 452/462

4. RVLIS SCALE FULL FULL FULL FULL FULL FULL

5. Resetor Vessellvt (%) 81.36 81.36 70.68 60.00 59.78 E9.38

6. Auct High Nuclear Pwt 1%) 0.00 0.00 0.00 0.00 0.00 0.00

7. CET Ave (deg F) 477.00 463.72 469.25 460.97 458.61 449.33

8. CET Hi(deg Fi 498.32 590.75 714.00 714.00 714.00 714.00

9. S/C Margin (deg el 32.95 39.56 44.23 47.82 63.16 21.34

90 LID Rata fGPM) 0.00 0.00 0 00 0.00 0.00 0.02 !

Loop Parameters -

9. T Hot -

A 461.47 445.49 431.36 426.03 424.81 427.14;

B 464.69 446 65 432.45 427.13 426.91 428.01

C 461.04 445.13 431.00 426.66 424.46 426.76

0 460.43 447.28 430,79 427.96 426.32 428.22_.

2. T Cold L

A 424.02 407.74 393.66 392.49 391.95 390.68

8 423.72 408.18 394.07 -322.93 392.41 391.44

C 424.40 408.47 394.37 393.14 392.64 391.26

D 297.31 263 65 195.40 148.83 149.17 200.80,

3: T Ave

A= 442.74 426.61 412.61 409.26 408.38 408.91

B 444.15 427.37 413.26 410.03 4'.i9.16 409.73

C 442.72 426.80 412.69 409.40 408.56 409.01

0 378.87 3L5.47 314.60 288.39 287.74 314.51

. Trend e 0 + .

A + . . + . .

'

B + . . + . .

C + . . + - .

D . . * + .

_

4. RCP 8tatus -

A 0FF 0FF OFF 0FF OFF OFF

B 0FF OFF OFF OFF OFF 0FF

C OFF OFF OFF OFF OFF OFF

D OFF OFF 0FF OFF OFF OFF

; FLOW (%) 3.32 3.26 3 12 2.94 2.92 3.29'

5. SIG Press i t

A 466.87 405.60 343.67 329.37 308.78 329.373,

B 466.87 405.60 343.67 329.37 329.37 329.37

C 466.81 405.60 343.67 329.37 308.78 329.37

0 466.87 405.60 343.67 329.37 329.37 329.374

Trend . 0 + '' I OA 0 -. .

0 0 .a . . .

.

3555 0 7.1 10 Rev 10/22/90

-. ~ . - . _ . - .__ . . _ . . _ . _ _ _ _ _ _ _ . _ . . _ . _.._.- - , ..- . _ . ~ - , . _ . , , ~ . . _ _ . _ _ _ ,

._.___.m~_.__.__._____ .._. _._ ._ _ . - ~ - -. _._ _ _

|'

4


| TIME OF D AY 6:15 6:30 6 46 7.00 7:15 7:30

) EL APSED TIME 3'00 3 15 3:30 3 45 4:00 4:16

1 C 0 0 0 -*

0 0: D - - . .

!~

j 6. SIG Level (NRI

]. A 2.87 2.92 3.46 3.48 3.37 3.25

B 2.67 3.06 3.19 3.09 3.26 3 49 |)"

C 2.62 3 04 2.86 3.01 3.25 3.27

1 D 2.22 3.65 3.71 3.74 3.81 3.97

7. SIG Level (WR)

A 71.49 71.69 73.84 73.94 73.46 73.01 ,

B 70.66 72.25 72.76 72.34 73.04 '3.95i C 70.48 72.17 71.43 72.05 72.99 73.07

D 68.90 74.59 74.83 74.96 75.23 75.87"

Trond . 0 +

A + + * . + +

. ( B + - + + + +

C + . . + + +'

D + + - + . +,

'

8. Ste6m Flow (1.0E6 LB/HRI.--

A 0.00 0.00 0.00 0.00 0.00 0.00

B 0.00 0.00 0.00 0.00 0.00 0.00,

C 0.00 0.00 0.00 0.00 0.00 0.00

0 0.00 0.00 0.00 0.00 0.00 0.00

9. Feed Flow (1.0E6 LBtHRI'

A 0.00 0.00 0.00 0.00 0.00 0.004

B 0.00 0.00 0.00 0.00 0.00 0.00

C 0.R 0.00 0.00 0.00 0.00 0.00

D 0.00| 0.00 0.00 0.00 0.00 0.00

10. M81V Status L

A- CLOSED CLOSED ICLOSED CLOSED CLO3ED CLOSED'

B CLOSED CLOSED CLOSED CLOSED CLOSED CLOSED

C CLOSED- CLOSED CLOSED CLOSED CLOSED CLOSED'

D CLOSED CLOSED CLOSED CLOSED CLOSED CLOSED

11. AFW Flow (GPMI-: yA 131; '7 140.89 115.17 0.00 0.00 0.10

t' 15 g 161.01 92.13 0.00 0.00 0.00

C' 113 g 120.76 92.13 0.00 0.00 0.01

D 12 6. 'FL 146.51 76.42 0.00 0.00 0.0C .,

TOTAL 625.0 } 569.16 375.84 0.00 0.00 0.10 i

r 'W92. E,$T Levol t%) -

A | 63.05| 61.50| 59.89| 59.94| 59.94 60.17|'

Entineered Sefeguards Features E'

9.Contahment

Pressure (PSIG) 0.78 0.79 0.80 0.80 0.80 0.81

Humidity (%) 48.66 48.27 48.03 47.82 47.73 47.78

Hydrogen Cone. (%) 0.00 0.00 0.00 0.00 0.00 0.00

| NR Cont. Sumo Lvl (IN.) 13.11 13.11 13.11 13.11 13.11 13.11

WR Cont. Lvl (IN.I 13.11 13.11 13.11 13.12 13.12 13.12'

3555 0 711) Rev 10/22/90

! . -. _ ._ - -_-._ - _ ___. . - .

_ _ , . _ _ _ ._

$

!

TROJAN PLANT PAR AMETED $UMM ARY T ADLE

TIME OF D AY 8:16 6:30 6:46 7:00 7:ib 7:30

ELAPSED TIME 3:00 3:15 3 30 3 46 4:00 4:16

'

Radiation Level IR%el 1.00 1.00 1.00_

1.00 1.00 1.00

Containment Spray NT ACT NT ACT NT ACT NT ACT NT ACT NT ACT

NaOH Tank Level (%) 96.40 96.40 96.40 96.40 96.40 96.40,

2. RWST Levet 85.85 B2.40 79.05 76.34 73.18 71.99

3, Cl3 A A A A A A

4. AFW TDAFWP ON ON ON ON ON ON

DAFWP ON ON ON ON ON ON

Elec. AFWP ON ON ON ON ON ON!

5. Estety inhetion Actuated ACT ACT ACT ACT ACT ACT

6.FWI Actuated ACT ACT ACT ACT ACT ACT

7. Eaunprnent Stats4i200

Train A 00S COS DOS 00S 00S 00S

Trenn B AVAll AVAll AVAll AVAIL AVAIL AVAll

FDG BAR

Train A OOS 00S 00$ OOS 00S 005

Train A OPEN OPEN OPEN OPEN OPEN OPEN' ' sCCP' r

Trab A 00$ 00S DOS 00$ 00S 00$

Train B ON ON TRIP TRIP TRIP TRIP

Flow 410 47 373.96 0.00 0.00 0.00 0.00

Al10PMP

Train A TRIP TRIP TRIP TRIP TRIP TRIP

Trair J ON TRIP TRIP TRIP T RIP TRIP

Fl> .w 532.37 434.82 434.12 423.60 416 90 0.00,

nNp (GPM) '- -- *>

Train A OFF OFF OFF OFF OFF OFF

Frein B 0FF OFF OFF 0FF 0FF OFF

Flow 0.00 0.00 0.00 0.00 0.00 0.00.

-* .'.YI''- 4

Train A- ON ON ON ON ON ON

Treh B 0FF OFF OFF OFF OFF 0FF' W *

SWS --

< Train A ON ON ON ON ON ON

Train B 0FF OFF 0FF OFF OFF OFF ;

CSPJ

- Train A 0FF 0FF 0FF 0FF OFF 0FF-

Train B 0FF OFF OFF OFF OFF OFF'

CAC-VC201 ' .= *4 r

l' Train A 0FF OFF OFF OFF OFF 0FF

Train B ON ON ON- ON ON ON||

#il CAC.VC202t

I .- Train A 0FF OFF 0FF OFF OFF OFF

i- Train B ON ON ON ON ON ONl

CAC VC203- ;

Trah A 0FF 0FF OFF OFF OFF 0FF


|

3555 0 7.1 12 Rev 10/22/90'

|~

h._;........__._-._ .. _ . - . _ _ _ _ . . .. _ ._._.. _ . _ _ . _ _ . _ _ . _ , _ _ _ _ _ ___ _ ._. _ .

|

Th0JAN PLANT PARAMETER SUMM AQy 7ADLE [;

..

6:16 6:30 6 46 7.00 7:16 7.30TIME OF D AY

EL AF4ED TIM E 3 00 3.16 3.30 3 46 4.00 A:1bj'

CAC VC204


Train 8 0FF OFF OFF 0FF OFF OFF

Major [Quiprnent

Qeactor TRIP TRIP TRtP TRIP TRIP TRIP

Turbine TRIP TRIP TRIP TRIP TRIP T RIP

Generator T Rip TRIP TRIP TRIP TRIP TRIP

DDetric Plant

Emerg Busses AVAll AVAIL AVAll AVAll AVAll AVAll

; Off sha Power AVAll AVAIL AVAIL AVAtt AVAIL AVAll !

Isola tions ,

Reactor Coolant |i.

PORV CLOSED CLOSID CLOSED CLOSED Clost0 CLOSED

Sa f etie s NO FL NO FL NO FL NO FL NO FL NO FL

Letdown NT CL NT CL NT CL NT CL NT CL NT CL

RCP Seat Return NT CL fJT CL NT CL NT CL NT CL NT CL

Main Steam

PORV NTISOL IJTISOL NTISOL NT ISOL NTISOL NTISOL

Sa fetie s NT AC NT AC NT AC NT AC NT AC NT AC

AFW Turbhe NTISOL NTISOL NTISOL NTISOL NTISOL NTISOL

F1971 AS 0 0 0 0 0 0 j'

Fl 970 A2 0 0 0 0 0 0_

CCW TR AIN C OFF OFF OFF CFF OFF OFF

SW TR AIN C OFF OFF OFF 0FF OFF OFF j

3556 0 7.1 13 Rev 10:22/90

_ _ _ , _ _ . . _ . . _. __ _ _ _ . . _ _ _ _ _ _ _ . . _ . _ _ ~ __ _

4

!

]

TROJAN itANT PARAMETER $UMM ARY TABLE<

i .

1.

8 00 6:16 B:30 0.46 9 00 )TIME OF D AY 7 46

a EL AP$t D TIME 4:30 4.46 6 00 6 16 6:30 6 46i

TC$ Parameters

1. RCS Pre a sure (Prrt 1700 00 1700 00 1700.00 1700.00 1700 00 1700 00;

Saturat6on Pressure 3094 30 3094 30 2301.70 1643.20 926 79 690.87

42. P2R Level t%) 0 00 0.00 0.00 0 00 0 00 0 00

Trend 0 0 0 0 0 0

3. P2R LIO Temp' Steam Temp toeg F6 420'420 4221422 4161416 414 >414 414,414 414/414

4. RVLIS SCALE FULL FULL FULL FULL FULL FULL

'6 Reactor Vessel Lvt 1%) 69 47 69 00 64.14 69 22 74.31 77.38 .

i

G. Auct High Nuclear Pwr 1%1 0.00 0 00 0.00 0.00 0 00 0.00

j 7. CET Ave toeg 5) 426.86 3A4.63 347.73 337.22 337.22 337.22

l 0. CET Hilde0 ) 714.00 714 00 667,47 600 96 644.42 487.89F

9. S/C Mar 9h ideo F) 30.34 13.73 13.66 20.79 20.79 20.79

10. L 0 Rate (GPM) 0.00 0.00 0.00 0.00 0 00 0.00

L000 Pa3 meters1. T Hot ~

a 402.86 376 16 366.97 340.73 340.73 340.73

8 403.83 377.10 3t6.R0 341.81 341.81 341.81

C 402.66 376.96 366 64 340.38 340.30 340.38

D 404.10 377.64 364,49 342.10 342.10 342.10

2. T Cold

A 370.06 336.96 323.68 309 61 303 61 309.61

B 371.36 337.27 323.61 309 63 309 63 309.63

C 371.33 337.31 323.61 309.63 309.63 309.63

0 204.98 236.40 291.47 309.76 309.76 309.76

3. Y Ave

A 3R6.86| 366.67 339.82 326.12 326.12 326.12.

B 387.69' 367.19 340.20 326.67 326.67 326.67_

C 386 94 366.63 339 63 324 96 324.96 324.96

0 304.54 307.02 322.08 326.93 326.93 326.93

Trend . 0 4

0 0 0A + . -

0 0 0B + . .

0 0 0C + . .

. + + 0 0 00

4. RCP Status

A 0FF OFF OFF OFF OFF 0FF

B 0FF OFF 0FF OFF OFF OFF

C O!F OFF OFF OFF OFF 0FF

D OFF OFF OFF OFF OFF OFF

FLOW (%) 3.16 3.48 3.96 3.38 3.38 3.38

6.8/G Press

A 247.26 186.62 146.42 117.99 117.99 117.99

8 247.26 186.62 146 42 117.99 117.99 117.99

C 247.26 186.62 146.42 117.99 117.99 117.99-

0 247.26 186.62 134.60 117.99 117.99 117.99

-Trend.0 +0 0 0A + . .

0 0 0B 0 . .

3666 0 7.1 14 Rev 10/22/90

1_._ . _. - - . . _ . . _ - - _ . . _ _ . _ . - _ - _ _ _ . _ . . . - . _ . _ _ _ . _ _ _ , _ . _ . . _ . . . _ _ . , ,

_ _ _ _ _ _ _ . _ . . _ _ _ . _ . . . _ . _ _ - _ _ ._ _ ._____ - ~ _ _ -,

d

!

l

0 TROJAN KANT PARAMETER $UMMARY TABLE1-

TIME OF DAY 7.45 8.00 8:15 8.30 8 45 9 00'

ELAPSED TIME 4:30 4:45 5 00 5:15 5:30 5-45i

O O OC * - .

j D 0 0 0 0. .

3 6. S tG Level INRI '

i A 3.33 3.87 3.57 3.74 3.85 3.64

i B 3 67 3.64 3.37 3.51 3.77 3.97

j C 3.46 3.52 3,71 3.60 3 49 3.33I D 4.39 4.77 4.40 5.12 4.86 5.08

7. S tG lovel (WR) ;-,

j A 73.32 75.4 B 74.29 74.97 75.41 74.55 I

B 74.67 74.55 73.47 74.02 75.07 75.87

j C 73.80 74.07 74.83 74.41 73.96 73.31

D 77.57 7909 77.60 80.47 79.43 80.33'

Trend 0 WA + + = - + +

$ s e e + e +

C + + + + . -^

2 D + + . + + +

i 8. Steem Flow (1.006 LBHR1

B . 00 .

C 0.00 0.00 0.00 0.00 0.00 0.004

D 0.00 0.00 0.00 0.00 0.00 0.00

9. Feed Flow (1.056 LS/HR) -

A 0.00 0.00 0.00 0.00 0.00 0.00 '

B 0.00 0.00 0.00 0.00 0.00 0.00

C 0.00 0.00 0.00 0.00 0.00 0.00

D 0.00 0.00 0.00 0.00 0.00 0.00

10. M8lv Status ' *+

1 A CLOSED CLOSED CLOSED CLOSED CLOSED CLOSED

B CLOSED CLOSED CLOSED CLOSED CLOSED CLOSED

C CLOSED CLOSED CLOSED CLOSED CLOSED CLOSED'_

D CLOSED CLOSED CLOSED CLOSED CLOSED CLOSED'

11. AFW Flow (GPM) . *

A 0.00 175.68 107.42 110.19 110.19 110.19

[ B 46.62 186.32 117.65 103.44 103.44 103.44

| C 46.62 186.31 129.79 96.74 96.74 96.74

D 0.00 0.00 0.00 0.00 0.00 0.00

TOTAL 93.23| 548.30 354.86 310.36 310.36 310.36

12. CST Level (%) -&

-A | 60.99| 60.62| 59.75| 59.55 59.55|' 59.55|Engineered $4fe0uards Features -

;

1. Containment

Pre ssure (PSIGl 0.81 0.82 0.82 0.83 0.83 0.83

Humidity (%) 47.51 47.38 47.17 46.99 46.99 46.99

Hydrogen Cone. (%) 0.00 0.00 0.00 0.00 0.00 0.00i

l; NR Cont. Sump Lvl (IN.1 13.11 13.11 13.11 13.11 13.11 13.11

, WR Cont. Lvl (IN.I 13.12 13.12 13.12 13.12 13.12 13.12|

- 3S55 0 7.1 15 Rev 10/22/90

|'i

.~.-. _ . ~ .-.- -..- _ . - - -...._ _ _. .. _ .-- - .. ,_

'

L1.

| TROJAN PLANT PARAMETf A $UMM ARY T ABLE -

TIME OF DAY 7:45 8.00 8:15 8:30 8 45 9 00

i (LAPSED TIME 4:30 4.45 5-00 5:15 5:30 5.45

! Mediation L evel (R %rl 1.00 1.00 1.00 1.00 1.00 1.00 ,

! Containment Spray NT ACT NT ACT NT ACT NT ACT NT ACT NT ACT*

1 NaOH Tank Level (%) 96 40 96 40 96.40 96.40 96 40 96.40

2. RWST Level 71.9 D 71.98 71.98 70.16 69.26 08.36

4. TDAFWP DN ON ON ON ON ON

eMvvP ON ON ON ON ON ON {g

l Elec. AFWP ON ON ON ON ON ON,

(5. Safety iniecuon Actuated ACT ACT ACT ACT ACT ACT

6.FWl Actuated ACT ACT ACT ACT ACT ACT;

7. Eaulpment Status"

; EDO -

Train A |00S DOS 00S 00S DOS 00S

Train B | AVAll AVAll AVAll AVAll AVAll AVAll

FDG Bkm 4

Trah A 00S DOS 00S 00S 00S DOS'-

Train A OPEN OPEN OPEN OPEN OPEN OPEN;

CCP,_

Train A 00S DOS 005 OOS 00S 00S-

Trah B TRIP DN ON ON ON ON

Flow 0 00 372.16 372.39 369.10 388.80 0.00

81(OPM)-

- Train A TRIP TRIP TRIP TRIP TRIP TRIP

Train B TRIP TRIP TRIP TRIP TRIP TRIP

Flow 0.00 0.00 0.00 0 00 0.00 0.004

RHRtGPMI. >,

"

Trah A 0FF OFF OFF OFF OFF OFF,

Trah B 0FF OFF 0FF 0FF OFF OFF

Flow 0.00 0.00 0.00 0.00 0.00 0.00

CCW "- bI.

~ Train A ON ON ON ON ON ON

Train B 0FF OFF OFF OFF OFF 0FF' '$WS t

Train A ON ON ON ON ON ON,

Train B 0FF OFF 0FF OFF 0FF- 0FF.

CSPh '

Train A- 0FF OFF 0FF OFF OFF OFF'

.

Train B 0FF 0FF OFF OFF OFF 0FF..'

CA0.VC201 '

Trah A 0FF OFF !OFF 0FF OFF OFF

Train B - ON ON |0N ON ON ON*

| *AC.VC202 ~' '

Train A 0FF 0FF 0FF OFF OFF 0FF

I Tra h 8 ON ON ON ON ON ON

| CAC VC203

|~ Train A 0FF 0FF OFF 0FF OFF OFF

| Train B ON ON ON ON ON ON,

i- 3555 0 7.11.6 Rev 10/22/90

i_.._.,...__..._..._.. . _ . . _ _ _ _ ,, . ___ _ , _ _ _ _ . . _ , _ . . _ . _ , _ . , _ , , _ _ . _ . . . . . . . . . . . , , _ , . _ , _ _ _ ,

_ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ - _ _ - - _ _ _ - - _ - _ _ _ _ - - ___-_ _ _ _ _ - _ _ _ _ _ _ - _ _

TROJAN MANT PARAMETER $UMM ARY TABLE

TIME OF D AY 7:45 8 00 8:15 8.30 8 45 9 00,

EL APSED TIME 4:30 4:45 5 00 5:15 5 30 5.45

CAC-VC204

Trah A ON ON ON ON ON ON

Tra' t B OFF OFF OFF OFF OFF OFFr

Ma)or f culpment

Qeactor TRIP TRIP TR P TRIP TRIP TRIP

furthe TRIP TRIP TRIP TRIP TRIP TRIP

Oenerator TRIP TRIP TRIP TRIP TRIP TRIP

Electrk Plant

Emerg Busses AVAll AVAll AVAIL AVAll AVAll AVAIL

Off site Power AVAll AVAll AVAll AVAIL AVAll AVAIL

llolatbng

Rosetor Coolant -

PORV CLOSED CLOSED CLOstD CLOSED CLOSED CLOSED,

Safetie s NO FL NO FL NO FL NO FL NO FL NO FL

Letdown NT CL NT CL NT C'. NT CL NT CL NT CL

RCP Seal Return NT CL NT CL NT CL NT CL NT CL NT CL

Mah Steam

PORV | NT ISOL NTISOL NTISOL NTISOL NTISOL NTISOL

Saf etie s NT AC NT AC NT AC NT AC NT AC NT AC

AFW Turbhe NT ISOL NTISOL NTISOL NT ISOL NTISOL NTISOL

Fl 971 A/B O O O O O O

F1970 A/B O O O O O O

CCW TR AIN C OFF OFF OFF OFF OFF OFF

SW TR AIN C OFF OFF OFF OFF OFF OFF

:

I

3555 0 7.117 Rev 10/22/90

- . . - - . _ . . . . ~ _ _ _ _

. - - . _ . - - . -

TROJAN PLANT PARAMETIC SUMM ARY TABLE

TIME OF D AY 9:15 9.30 9 45 10:00 10:15

ELAPSFD TIME 6:00 6:15 6.30 C:45 7:00

RCS Parameters .

1. RCS Pressure (Part 1700 00 1700.00 1700.00 1700.00 1700.00

SaturatL.a Pressure 343.67 173 34 145.42 145.42 145.42

2. PZR Level 1%) 0.00 0.00 0.00 0.00 0.00

Trend 0 0 0 0 0

3. PZR LIO TemplSteam Temp Ideg Fi 414 t414 414/414 414/414 414/414 414/414

4.CVLIS SC ALE. FULL FULL FULL FULL FULL

5. Re,setor Ve ssel Lvl (%) 78.18 78.19 77.37 77.33 77.58

6. Auct High Nuclear Pwr (%) 0.00 0.00 0.00 0.00 0.00

7. CET Ave idag F) 337.22 337.22 337.22 337.22 337.22

8. CET Hildeo F) 431.37 374.84 356.02 356.02 356.02,

9. S/C Margin (deg FI 20.79 20.79 20.79 20.79 20.79

10. L/D Rate (GPM) 0.00 0.00 0.00 0.00 0.00Loop Paremeters

1. T Hot '

A 340.73 340.73 340.73 340.73 340.73

8 341.81 341.81 341.81 341.81 341.81

C 340.38 340.38 340.38 340.38 340.38

D 342.10 342.10 342.10 342.10 342.10

2. T Cold -

A 309.51 309.51 309.51 309.51 309.51

B 309.53 309.53 309.53 309.53 309.53

C 309.53 309.53 309.53 309.53 309.53

D 309.76 309.76 309.76 309.76 309.76

3. T Ave -

A 325.12 325.12 _ 325.12 325.12 325.12

B 325.67 325.67 325.67 325.67 325.67

C 324.96 324.96 324.96 324.96 324.96

D 325.93 325.93 325.93 325.93 325.93

' Trend . 0 +

A 0 ! O O O O

B O O O O O

C 0 0 0 0 0

D 0 0 0 0 0

G RCP 8tatus '<

A 0FF OFF OFF OFF OFF

R OFF 0FF OFF OFF OFF

C OFF OFF 0FF OFF 0FF

D OFF OFF OFF OFF OFF

FLOW (%) 3.38 3.38 3.38 3.38 3.38

5. 5 tG Pre ss -

A 117.99 117.99 117.99 117.99 117.99

0 117.99 117.99 117.99 117.99 117.99

C 117.99 117.99 117.99 117.99 117.99

D 117.99 117.99 117.99 117.9f | 117.99

Trend . 0 +

A O O O O O

B O O O O O

3555 0 7.1 18 Rev 10/22/90

1

1


'TIME OF D AY 9:16 9.30 9 46 10:00 10:15

EL APSED TIME 6:00 6:16 6:30 6 46 7:00

'

C 0 0 0 0 0

D 0 0 0 0 0

8.S/0 Level (NRI.

A 4.02 3.91 3 69 3 69 3.18

5 4.17 3.94 3 63 3.63 3.62

C 3.21 3.62 3.61 3.88 4.12*0 6.44 6.33 4.91 4.97 6.24

7. SIG Level (WR) ,

A 76.07| 76.64 74.76 74.36 72.71

B 76.70 76.76 74.62 74.13 74 de

C 72.83 74.48 74.03 76.63 76.49

0 81.76 81.34 79.62 79.89 80.96

- Trend 0 +

A + = = + *

8 + +. + -,

C . + . + +

D + . + + +

8. Stee m Flow (1.0f 6 L8/HR1 ;

-A 0.00 0 00 0.00 - 0.00 0.00

B 0.00 0.00 0.00 0.00 0.00

C 0.00 0.00 0.00 0.00 0.00

| D 0.00 0.00 0.00 0.00 0.00

9: Feed Flow (1.086 Lt/HR) J'

A- 0.00 0.00 0.00 0.00 0.00,

8 0.00 0.00 0.00 0.00 0.00

C 0.00 0.00 0.00 0.00 0.00

D 0.00 0.00 0.00 0.00 0.00

10. MSIV Sietus

A CLOSED CLOSED CLOSED CLOSED CLOSED ,

i B CLOSED CLOSED CLCSED CLOSED CLOSED

C CLOSED CLOSED CLOSED CLOSED CLOSED'

D CLOSED CLOSED CLOSED iCLOSED CLOSED

11. AFW Flow (GPM) .

A- 110.19 110.19 110.19 110.19 110.19

8 103.44 103.44 103.44 103.44 103 44

C 96.74 96.74 96.74 96.74 96.74

0 0.00 0.00 0.00 0.00 OgTOTAL 310.36 310.36 310.36 310.36 310.36

*92. CST Level t%) ,,

A | 69.66| - 69.66| 69.66| 69.66| 69.66||| Engineered Safeguards Features -

'

e u e( 101 0.83 0.83 0.83 0.83 0.8

Humidity (%) 46.99 46.99 - 46.99 46.99 46.99

Hydrogen Cone. (%) 0.00 - 0.00 0.00 0.00 0.00

NR Cont. Sump LvlitN.I 13.11 13.11 13.11 13.11 13.11

WR Cont. Lvt (IN.) 13.12 13.12 13.12 13.12 13.12

. 3666 0 7.1 19 Rev 10/22/90 '

2-.._ .u..__,_,._..__., . . _ . _ . _ . . _ . _ . , . - _ . _ _ - . . _ . - . . , . . - _ , , . , . , . _ . - . _ _ - . . _ , _ . - ,

-. - - ___._.m.m _ - _._. - . - _ ._ _ _. - _ . _ _ .. _ _ ._. _ . _ ,m.

!

Y

i TROJ AN PLANT PARAMETER SUMM ARY T ABLEl

i TIME OF D AY 9:15 9:30 945 10:00 10:15 I

4 ELAPSED TIME 6:00 6:ib 6:30 6:46 7:00 ji

! Radiation te vel tR hrt 1.00 1.00 1.00 1 00 1.00

] Contahment spray NT ACT NT ACT NT ACT NT ACT NT ACT

NaOH Tank t evel(%) 96.40 96 40 96.40 96.40 96.40i

2.CWST Level 67.45 66.55 65 66 64.75 64.76

i 3. CIS A A A A A

I 4.AFW TDAFWP OfJ ON ON ON ON

DAFWP ON ON ON ON ON

.fElac. AFWP ON ON ON ON ON

| 6. Saferviniection Actuated ACT ACT ACT ACT ACT'

'

6.FWl Actuated ACT ACT ACT ACI ACT;

7. Equipment Status 0.00'

EDO'

Train A 00S 00$ 00S DOS 000

Trah B AVAll AVAtt AVAll AVA.6 A VAll

EDG BKR

Train A 00S 00S 00S 00S 005

Train A OPEN OPEN OPEN OPEN OPEN

CCP' '

Trah A OOS OOS- 00S 005 OOS'

Train B Off ON ON ON OfJ

Flow 0.00 0.00 0.00 0.00 0.00

j SI (GPM) '2 Train A TRIP - TRIP TRIP TRIP TRIP

Train B TRIP TRIP TRIP TRIP - TRIP,

Flow 0.00 0.00 0.00 0.00 0.00

RHR IOPYl - s4

Trah A OFF 0FF OFF OFF OFF

Train B 0FF OFF OFF OFF ~ OFF

Flow 0.00 0.00 0.00 0.00 0.00

CCWP '

Train A ON ON ON ON ON

- Train B 0FF 0FF OFF OFF OFF

tSWSt7

;Train A ON ON ON ON ON

Train B OFF 0FF OFF OFF OFFd gps <

Train A OFF 0FF OFF 0FF OFF;

I Trah 8 0FF OFF OFF 0FF OFF

| CAC VC2011

Trah A - OFF OFF 0FF 0FF OFF

it Train s ON ON ON ON ON

| CAC.VC202 h' '

, - +

Train A 0FF 0FF 0FF OFF OFF

Train B ON- ON ON ON ON

CAC.VC2031

- Train A - 0FF OFF OFF 0FF OFF

Train 8 ON ON ON ON ON

3565 0 - 7.1 20 Rev 10/22/93

t

I.,,..... . . _ . . _ . . _ , , - ... _ _ , _ . . . . . . _ . , . . - _ . _ _ _ , . , . , , _ _ _ , , , , . _ . , . , , , . , , . _ , _ , _ _ , ,

_ . _ ._. - . _ _ _ _ . _ _ _ ,

i


TIME OF D AY 9:15 930 9 45 10 00 10:15

EL APSED TIME 6 00 6:15 6:30 6.45 7:001

CAC VC204

Tra b A ON ON ON ON ON

Trab B 0FF OFF OFF OFF OFF

Ma)or Eculpment

Qeactor TRIP TRIP TRIP TRIP TRIP

?urbbe TRIP TRIP TRIP TRIP TRIP

Generator TRIP TRIP TRIP TRIP TRIP

Electrhc Plant ,

Emerg Busses AVAll AVAfL AVAll AVAll AVAIL

Off site Power AV All AVAIL AVAll AVAll AVAll

isolations

Raaetor Coolant

FORV CLOSED CLOSED CLOSED CLOSEO CLOSED

Safeties NO FL NOFL NO FL NO FL NO FL

Letdown NT CL NT CL NT CL NT CL NT CL

RCP Seal Return NT CL NT CL NT CL NT CL NT CL

Mah Steam_

PORV NTISOL NTISOL NT ISOL NTISOL NT ISOL

Safetie s NT AC NT AC NT AC NT AC NT AC

ArW Turbbe NT ISOL N T ISOL NT: COL NTISOL NTISOL

M 971 afb O O O O O

n.970 A/B O O O O O

)CCW TRAIN C OFF OFF OFF OFF OFF

(SW TR AIN C OFF OFF OFF OFF OFF

1(

l

3555 0 7.1 21 Rev 10/22/90

I_- - - . . _ . . .

. . . . . - -.. . . .-- . . . . , . . . - , . . . - - . . , , , ,,. ' . . - . . . . . . . . . . . -

, ,3

.

7.2 ElanLEmamtitLI2.ata

3555-4/NUCL-1429 7.2 1

- __ _ - _ - - . _ _ _ _ - ___ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

i

TROJAN NUCLEAR POWER PLANT SYSTEM PARAMETERS

Rt AL TIME 3:15 ELAPSED TIME 0:00

RCS Parameters1. RCS Pressure 2233.09 PSIG

2. PZR Leve! 61.3402 % Trend O3. PZR Temp GQ' steam) 653e653 deg F

4. RVLt$ Scale. DY N AMIC %5. Reactor Vesfel Lvl 60 %

6. AuCt High Nuclear Pwr 99.3059 %

7. CET Ave 609.2696923 deg FB. CET Hi 629.023 deg F

9. SIC Margin 25.739 ceg F

10. L/0 Rate 77.2346 GPM

D i''Loop Parameters A B

_

_612.0 81. T Hot 609.441 611.672 608.6392. T Cold $51.847 552.769 552.482 554.5043. T Ave 581.874 583.468 581.812 584.766

Trend . O + 0 0 0 04, RCP Status RUN RUN kUN RUN

5. S/0 Press 855.7 857.2 856.7 855.3Trend O + 0 0 0 0

6. $!G Level INR) 44.2 44 44.2 44.1

7. S/G Level (WRI 55.2685 55.0367 55.2544 55.1561Trend . O + 0 0 0 0

8. Steam Flow (1.0E 6 LD/HR) 3 64578 3.79122 3.64796 3.793099. Feed Flow t 1.0t6 LBrHR) 3.68149 3.83128 3.67989 3.82469

' 10. MSIV Status NT CL NT CL NT CL NT CL :

11, AFW Flow (GPM) 0 0 0 0

12. CST Level (%) 71.9682

Engineered Safeguards Feature s

1. Containment'

Pressure 0.205 PSIG

Humidity 41.507 %

Hydrogen Conc. O %

N Cont. Sump Lvl 13.1083 IN.

WR Cont. Lvl 13.1089 IN.

2. RWST Levet 69.8326 %

3. CIS NO4.AFW TDAFWP OFF

DAFWP OFF

Elec. AFWP CFF

5. Safety Iniection Actuated NOT ACT

6. FWI Actuated NOT ACT7. Eouipment Status Train A Train B Train C Flow

IEDO OOS AVAIL

CCP OOS OFF 0 GPMSI OFF OFF 0 GPMRHR OFF OFF Fl.971/970 0 0

CCW ON OFF OFF

SWS ON OFF OFF

CSP OFF OFF

CAC.VC201 OFF ONCAC.VC202 OFF ONCAC VC203 OFF ONCAC VC204 ON OFF

Major Eaulement Electric Plant

Reactor NT TRIP Emerg Busses A V AIL,

l Turbine NT TRIP Offsite Power AVAIL

Generator NT TRIPi

3555 7.2 2 REV. 8/17/90

i1

.. . _ . - . - -- - -..__- _ - . - - _.=. - .-. .-._-

1

'I4

i

.

.

_

.

i

i

|!

I

i

l

7.3 Safety Pmameter Display SynenLSsterns

1

.|

.

1

L

( .',

l

1

-:

,

3555-4/NUCL-1429 7,3 1

_ _. . - _ . - _ . . . - - - _ - . _ _ _ . - _ . - . _ - . . - . _ _ _ - - . . - . . . - _ . . _ _ _ - . . _ _ _ , . . _ _ _ _ _ _ , . _ , -- _-_ _ ,, _._.

_ _ _ _ _ _ _ _ _ _ - - - _ _ _ - _ _ _ _ _ _ _ _ , _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . .. . .. .- - . - . - . . - . _ . - . .. _ _ _ - ..

!

' YROJAN PLANY PARAMETER DATA ;

;

- i

. TROJAN REAL TIME | 3:15 |

RERP 1 REACTOR PLANT STATUS OTSC Nov-90 ,

Isolation iReactor Coolant Masn Steam

Generalinformation Pber CLOSED esol Vhrs NT CL ii

*

Reactor Shutdown - NT TRIP ' * Safeties NOFL Porv NT ISOL

j Offsne Power AVAIL Letdown NT CL Safetees , ,NTdC f* Fuel Dag NOME (MANUAL ENTRY) RCP Seal Return NT CL AFW TC .I NT % ;

}

. $!

t

i Contaenment Reactor Coolant System i

2 t

i Pressure -0.2 PSIG Pumps #s B C D jRadiation 1.0 REMMR ARM-15 PdN RUN RUN RUN (,Spray Status NT ACT Flow 100.! % j

NAOH TK LEVEL .96.4 % Pressunier Poes 2233.1 PS8G f'

fTemperature (TAVGl 581.8 deg F

Emergency Core Cooieng T Hot teammumt 612.6 degF

A B C Total Flow . Incore T;C Temp 6* 629 0 deg F |<

"

Cent Charge OOS OFF O.O GPM Average 609.3 deg F<

;Safety Ini OFF OFF O.0 GPM Pressunter Lewes 61.3 %

RHR Pumps OFF OFF O.0 GPM Rn Vessel Levet 120.0 % !

Comporet CW ON OFF OFF Rm Sutxoohng Martyn 25.7 dag F fServc Wir ON- OFF OFF Saturation Pressure 1965.6 PSIG

''

'

Aun Fdwtr OFF OFF O.O GPM Leah Rate:Ident. feed G4E) GPM,

EDG Status OOS AVAll. Urudenofied (MEl GPM ,

i

. EDG Bus Bk - OOS OPEN :,

1 Steam Generators i'

I *A B C Di

! Press (PStGI 855.7 857.2 856.7 855.3

: Inoperable Equipment nu .ENTRYI Level WR (%) 55.3 5E.0 55.3 55 2 ,

1 Leve4 NR (%) 44,2 43.4 44.1 43.8 I|1~j 2 NOTE: MANUAL ENTRY (ME) ;

3 PRl/SEC Lest Rate: (MO GPM IN: (M U S/G ||1 4 J

! 5 EOF 1. REST EOF 2. REST h

! ON I ON I I |i '

!,:

3

1- !

! .

i;.

-.....m.._6 _. . . ~. . _ . . -- _ __ .- . ..~ . . . ~.

, , . - .

il I.

.

_

TROJAfd PLAtJT PARAMETER DATA

REAL TIME | 3:15]TROJAN

OTSC fJov 90RERP 2 RADIOLOGY AND METEOROLOGY

RADIATION MONITOR STATUS

PRM 1 A (PART) 1839.2 CPM PRM 2A(PART) 130.6 CPM PRM 7 (LIO) 742 6 CPM

18 (tODtNE) 7919.1 CPM 28 00 DINE) 58.4 CPM 8 (LIO) 399.0 CPM

1C IGAS-LO) 5710.6 CPM 2C (GAS-LOi 39.8 CPM 9 (LtO) 800,0 CPM

10 (GASMI) 21.3 CPM 2D (GAS-Hil 29.3 CPM 10 RIO) ,, 1309.5 CPM

13 (LIO) 29913 2 CPM

1E (GASMIMI) eDMRHR

PRM 6A (GAS-LOl 2290.8 CPM PRM 16A # GAS) 1.1 MRHR ARM 15A (CNT) 1.0 RHR

68 (GASMI) 41.0 CPM 168(GAS) 1.1 MRHR 158 (CNT) 1.0 RHR

6C (GAS HI-n) 0.0 CPM 16C (GAS) 1.1 MRHR 22 (N SIT) 0.1 MRHR

16D (GAS) 0.1 MRHR 23 IS SIT) 0.1 MRHR

-

METEOROLOGYPLANT STATUS

WIND DIRECTIONRCS PRESS (WiU 2233.1 PSIG

33 FT ELEV-FROM S DEG AT 5O MPH

iRCS TEMP (Wk 1 612.6 DEG F

200 FT ELEV-FROM 7 DEG AT 5-? MPH

PZR LEVEL (WR) 611 %500 FT ELEV-FROM 10 DEG AT 5.0 MPH

,

| PZR TEMPisq/stm 653/653 DEG F

RX VESSEL LVL 120.0 % O.O DEG33 FT ELEVATION OtRECTION STD DEV

RX SUBCOOLING 25.7 DEG F

INCORE T/C HI 629.0 DEG F : AVE 609.3 DEG FTEMPERA.TURE

STM GENERATOR A B C D

PRESS {PSIG) 855.7 857.2 856.7 855.3 33 FT ELEVATtON 23.9 DEG C 75.0 DEG F

LEVEL (%WR) 55.3 55.0 55.3 55.2 200 FT ELEVATtON 21.1 DEG C 10 0 DEG F

VERT DtFF (200-33FT) -2.8 DEG C

CONTAINMENT PRES -0.2 PStG

REACTOR SHUTDOWN NT TRfP

CONTAINMENT ISOL NO

SAFETY INJECTION NOT ACT

lI ]jI

,

|, ,3

1 ,:

3

PM L

|

0 U E9 DC RC

- MA MAvE o M T T T TMN T SN AHSI

T

_LQER

1 R 8 R 3 R6R 4 9 H6. H

9 H4 H, 7 B/1

6. B 7 B/ C3 M 3M 3M3M

7 2 7 3

5 I

7G 6G 5G5 G 5 I 5 t

5 I

8 SS S 8S 8P P P P8

R 4 R3 R 4 a. 4

N4 % A N4 % B N4 % C N4 % D|i|

ATADR

3 0M 9 0M 7 0MET 5 0M 1 R 9 R 4 R

F F F FE 1 R 2 H GH. G73 H GG 8 H G 8 /6 B - B8 B/fA 6 B/ 3 M 3ME 3M 3MAP F FF FF FT F FN M A M A M A M AALP

F F FN G G G G M M M M AA t TJ S E E E P P P P F

O N P D D D G G G G G1 3 3 2 9 7 O 2 O O OR A

T J 6 3G 3 8 0 5 7O 2 ! 2 5 6 2 7R 2 S 2T C % P

IS ST C- -

O L P RC g N

v G 3 RS a L H T

t

R1 I HS X O C L B SE P E OR L E CP g R 8R v

a O UR% W T C SWP1 3Cb 9N G9

I

SP T

C N M M Mt 1

S N T 2 A O R R RD N O 0 T M O O OT E -L M N N N N NN

N OI i

A TT AN I

DOC S Y A T R

T L S A R M E

E R T C HO R P N E TA

~ C D.

S P S C S OT A 8~ - I

S_L

P1SP2

< | ! | | |f|!fflf1||I

____ - _ _ _ . - -_ -

_ _

TROJAN PLANT PARAMETER DATA -

'TROJAan REALTIME | 3:30|3RH1 RHR OTSC nov-90

__

RWST PZR LEV 61 % CORE EXIT AVG 609 DEG F 5804A BIT

St RV LEV 120 % CLDN RATE O DEG FI_CL ABIT EXP 4% HR99.8 *A

~_ CSS RCS|31 S809A CL B e

*PSIG 70 DEG F . 69 DEG F ,,

S812 HX O

A | GPM202A

8811A 30 PSIG S716A

2069A kB8701 OGPM RCS

S703 3D8702 NOT AVAtt. SUMP

S7168

| RCS |'

HL D 20698,

2233 88118 GPM. dC-

PStG RCS

70 DEG F 70 DEG F S809B ,CL D

613 31 HX_

DEG F S7008 PSIG B

2028 31 PSIG S8048 SI

_ _ _ _ _ _ .-_

.__ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ - _ _ _ -_

-

~ TROJAN PLANT PARAMETER DATA ..

4- ,

-TROJAN REALTIME . . | 3:15 || |4RM1 RAD OTSC Nov 90

CONTAINMENT - SECONDARY-.i

AREA SG BLOWDOWN : 1309.5 CPM PRM O . F*

!

HI RANGE : 1.0 RH ARM-15A .,,

: 1.0 . ARM-158 COND AIR EJECT,

INCORE EQUIP :- 4.2 MRH ARM 4 NOBLE GAS

INCORE GUIDE : 350.6 ARM-21 . LO : 2290.8 CPM PRM-6A ' [

MANtP CRANE 132.3 AP%2O He : 41.0 CPM PRM48 !

H14tl : 0.0 MHR PRM-6C ' .

VENT EXHAUSTPARTICULATE : 1839.2 CPM PRM-1 A ,

+

IODtNE : 7919.1 PRM-1B ;

L

NOBLE GAS

LO : 5710.6 PR%1C

HI- . 21.3 PRM-1D -;-

Hi-HI : 0.0 PRM-1E

. .iSUMP DISCH : 40.0 PRu-14 - e

i

SITE BOUNDARY CCW ,

;

NORTH : O_1 ._ MRH ARM-22 LOOP A . 742.6 CPM PRM.7 [

;l

|* SOUTH : 0.1 MRH ARM-23 .LOOPB . 399.0 CPM PRM-8 I'

,

>T

, !

;' "t,

'

|

I,

b

-

__ . _ _ _ . _ _ . , . . . , - . . _ _ . . _ _ , _

____ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ , _ z_ .__

_-

TROJAta PLANT PAAfAETER DATA

REAL TIME | 3:15 |TRO.!ANth 90OTSC

4RM2 RAD

AUX BLDG,

RADWASTE

EL 5 : 0.1 MRH ARM-1 VENT COLL DISCH 2998.9 CPM PRM-5AREAS .

EL25- O.1 ARM-2 NOBLE GAS OtSCH

, ,

CPM PRMYA25.8EL 45 . O.1 ARM-3 LO

0.1 ARM 4 Hi . 29969.9 PRM 4B

EL45

.

EL 61 : 0.1 ARM-7

RADWASTE EL 77 - 0.1 MRH ARM-9 RCDTDISCH BOO,0 CPM PRM-15.

LIOutOOtSCH . 236.0 PRM-9

CONCTKPM tI

EL77 : 0.1 MRH ARM-10

MACH SHOP EL93 : 0.2 ARM-12

RADWASTE EL93 . O.2 ARM-14AUX / FUEL BLDG EXHAUST

RHR A RM EL 5 : 10.1 MRH ARM-16 PARTfCULATE 130.6 CPM PRM-2A

58.4 PRM-28

RHR 8 RM EL 5 : 9.2 ARM-17 80 DINE

VCT RM EL61 - 12.6 ARM-18 NOBLE GASLO _ 39.8 CPM PRM-2C

LTDN CHASE 29.3 FRM-2D

EL65 . 'O MRH ARM-19 HI.

CONTROL ROOM O.1 MRH ARM 11

FUEL BLOG

POOL AREA EL45 . O.1 MRH ARM-5

FUEL BLOG EL 61 : 0.1 ARM-8

NEW FUEL EL93 : 0.2 ARM-13

SPEf4T FUEL

POOL VENT- 38.3 CPM PRM-3

- ___ - -

_ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _

- TROJAfJ PLAtJT PARAMETER DATA

TROJAN REAL TIME | 3:15 |

3MT1 MET OTSC TJov-90

WIND (N = 0, 360 DEGREES) TEMPERATURE

.

33 FT ELEV-FROM 005 AT 5 MPH 33 FT ELEV 23.9 DEG C ' '

200 FT ELEV FROM 007 AT 5 MPH 75 DEG F

500 FT ELEV-FROM 010 AT 5 MPHVERT DtFF (200-33 FT) -2.8 DEG C

33 FT ELEVATION OtR STD DEV ODEG

. _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ . - . .

TROJAN PLANT PARAMETER DATA

TROJAN REALTIME |3:15 |3TC1 T/C OTSC Nov 90

RCS WR PRESS 2040 PSIG CORE Ex1T ag 475 DEG F

1 2 3 4 5 6 7 8 9 10 11 12 13 14 15

| 475 475 475| ,

A B | 475 475 475 | 11 A ,

B 475 475 475 475 B *

_,;

C 475 475 475 CD 475 475 475 475 475 475 0

E 475 475 475 475 475 E

F 475 475 475 475 475 F'

G 475 475 475 475 475 475 475 475 G

H 475 475 H

J 475 475 475 475 475 J

K 475 475 475 475 K

L 475 475 475 475 475 475 L

(4 475 475 M

N 475 475 475 475 N

P | 475 | P

R IV | 475 475 475 | Ill R

A 6 M A,W- .L >44"- e&,& AL J & aen.w-

'(

.

D

,

b

I

,1

SECTION 8.0 RADIATION DATA- t

1 ;

,

'

s-

L.p;|l

.

|

|

|

3555 4/NUCL-1429L1

- - - _. . - _ _ - _ -..--_-_ . _.

. .. .. - - - - . _ ,

-!.

,

~

.

.

.

t

|

8.1 Radiation Monitor Summary

..

. . .

'.

I :'

'

i

|

'

;i

l'

h|| ..

|!.'

i

f; 3555-4/NUCL-1429 8,1 1

..

. .. ... . . ,

|

VROJ AN NUCLE AR PLANT RAOIATION MON 1?OR SUMM ARV

3:15 3:30 3:45 4:00 4:15 4:30 |MONITOR 8: UNITS 0:00 0:15 0.30 0 45 1:00 1:15 |

'

PRM 1 A com 1839.2 1839 2 1843.1 1843.7 1843.1 1843.1

PRM 1B com 7919.1 7919.1 7919.1 7919.1 79191 7919.1

PRM 1C com - 5710 6 5710.6 5710.6' 5710.6 5710 6 5710 6 I

PRM 10 com 21.3 21.3 21.3 21.3 21.3 21.3

PRM.1 E m R 'hr 1.00E.1 100Ed 1.00E 1 1.00E 1 1.00E 1 1.00E 1

PRM 2 A com 130 6 130.6 130 9 130.9 1309 1309PRM 28 com 58.4 58.4 58.4 58.4 58.4 58 4

PRM.2C com 39 8 39.8 39 8 39.8 39 8 39 8PR M,2 D com 30 3.0 3.0 3.0 30 3.0

PRM 3 com 38.3 38.3 38.3 38.3 38.3 38.3

PRM.4 A com 25.8 25.8 25.8 25.8 25.8 25.8

PRM 4B com 29969.9 29969.9 29969.9 29969 9 29969 9 29969 9

PRM.5 com 2998.9 2998.9 2998.9 2998.8 2998.9 2998.9

PHM.6 A com 2290.8 2290.8 2290.8 2290.6 2290.8 2290.8

PRM.6B com 41.0 41.0 41.0 41.0 41.0 41.0

PRM.6C mR hr 1.00E 1 1.00E 1 1.00E 1 1.00E 1 1.00E 1 1.00E 1

PRM 7 com 742.6 742.6 742.6 742.5 742.6 742.6

PRM.8 com 399.0 399.0 399.0 399.0 399.0 3990PR M .9 com 800.0 800 0 800.0 800.0 800.0 800.0

PRM 10 com 1309.5 1309.5 1309.5 1309.5 13095 13095PRM 13 com 29913.2 29913.2 29913 4 29911.7 29913 4 29913 4

PRM 14 cpm 40.0 40.0 40.0 40.0 40 0 40.0

PRM 15 com 236.0 236.0 236.0 236.0 236.0 236.0

PRM 16 A mRlhr 1.12 E + 0 1.12E + 0 1.12 E + 0 1.12E + 0 1.12E + 0 1.12E + 0

PRM 168 mR!hr 1.12 E + 0 1.12E + 0 1.12E + 0 1.12E + 0 1.12 E + 0 1.12E + 0

PRM 16C mR!hr 1.12E + 0 1.12 E + 0 1.12E + 0 1.12 E + 0 1.12E + 0 1.12 E + 0

PRM 160 mR|hr 1.12E + 0 1.12E + 0 1.12E + 0 1.12 E + 0 1.12 E + 0 1.12E + 0

PRM 25A com 0.1 0.1 0.1 0.1 0.1 0.1

PRM 258 com 0.1 0,1 0.1 0.1 0.1 0.1

PRM 25C com 0.1 0.1 0.1 0.1 0.1 0.1

AREA MONITORSARM 1 mR/hr 9.95E 2 9.95E 2 9.95E 2 9.95E 2 9.95E 2 9.95E 2

ARM 2 mR;hr 7.25E 2 7.25E 2 7 25E 2 7.25E 2 7.2SE 2 7.25E 2

ARM 3 mRihr 1.00E + 0 1.00E + 0 1.00E + 0 1.00E + 0 1.00E + 0 1.00E + 0

ARM 4 mR!hr 9.19E 2 9.19E 2 9.19E 2 9.19E 2 9.19E 2 9.19 E .2

ARM 5 mR!hr 1.03E 1 1.03E 1 1.03E 1 1.03E 1 1.03E 1 1.03E 1

ARM.6 mR!hr 4.18E + 0 4.18E + 0 4.18E + 0 4.18E + 0 4.18E + 0 4.18E + 0

ARM 7 mR!hr 9.64E 2 9.64E 2 9.64E 2 9.64E 2 9.64E 2 9.64E 2

ARM.8 mR!ht 9.30E 2 9.30E 2 9.30E 2 9.30E 2 9.30E 2 9.30E 2

ARM 9 mR!hr 1.12E 1 1.12E 1 1.12 E a 1.12E 1 1.12E 1 1.12E 1

ARM 10 mR!hr 1.06E 1 1.06E 1 1.06E 1 1.06E 1 1.06E 1 1.06E 1

ARM 11 mR the 8.00E 2 8.00E 2 8.00E 2 8.00E 2 8.00E 2 8.00E 2

ARM 12 mRhr 1.71E 1 1.71E 1 1.71E 1 1_. 71 E 1 1.71E 1 1.71E t

ARM 13 mR /hr 1.7 7E 1 1.77E 1 1.77E 1 1. 7 7 E * 1 1.77E 1 1.7 7E 1

ARM 14 m R 'hr 165E 1 1.65E 1 1.65E 1 1.65E 1 1.65E 1 1.65E 1

ARM 15A Rihr 1.00E + 0 1.00E + 0 1.00E + 0 1.00E + 0 1.00E + 0 1.00E + 0

ARM 15B R!ht 1.00E + 0 1.00E + 0 1.00E + 0 1.00E + 0 1.00E + 0 1.00E + 0

ARM 16 mRihr 1.01 E + 1 1.01E + 1 1.01 E + 1 1.01E + 1 1.01 E + 1 1.01 E + 1

ARM 17 mR!hr 9.18E + 0 9.18E + 0 9.18E + 0 9.18E + 0 9.18E + 0 9.18E + 0

ARM 18 mR!hr 1.2 6E + 1 1.2 6E + 1 1.2 6E + 1 1.2 6E + 1 126E + 1 1.26E + 1

ARM 19 mRlhr 1.04E + 0 1.04E + 0 1.04E + 0 1.04E + 0 1.04E + 0 1.04E + 0

ARM 20 mR/hr 1.32E + 2 1.32E + 2 1.32E + 2 1.32E + 2 1.32E + 2 1.32E + 2

ARM 21 mR/hr 3.51E + 2 3.51E + 2 3.51 E + 2 3. 51 E + 2 3.51E + 2 3.51 E + 2

ARM.22 mR /hr 7.01E 2 7.01E 2 7.01E 2 7.01E 2 7.01E 2 7.01E 2

ARM 23 mR 'hr 7.11E 2 7.11E 2 7.11 E 2 7.11E 2 7.11 E 2 7.11 E 2

ARM 24 mR!ht 7.01E 2 7.01E 2 7.01E 2 7.01E 2 7.01E 2 7.01E 2

ARM 25 mRihr 1.00E + 0 1.00E + 0 1.00E + 0 1.00E + 0 1.00E + 0 1.00E + 0

3555 0 8.1 2 Rev.10'26 90

i

TQOJAN NUCLEAR PLANT RADIATION MORITOR SUMM ARY

4 45 5:00 5:15 5:30 5 45 6 00

MONITOR 0 UNITS 1:30 1:45 2:00 2:15 2:30 2:45 |

com_

1843.7 1839.2 1839.2 1839.2 1840.1 1840.1(PRM.1 APh',' 18 cpm 7919.1 7919.1 7919.1 7919.1 7919.1 7919.1

PRM 10 com 5710 6 5710.6 5710.6 5710.6 5710.6 5710.6PRM.1 D com 21.3 21.3 21.3 21.3 21.3 21.3

PRM 1E mR!hr - 1.OOE.1 1.00E .1 1.00E .1 1.00E .1 1.00E.1 1.00E.1

FQM 2A com 130.9 130.6 339796.4 ** 354303.3 '' 418522.0 ** 430341.6 '' |

PRM 2B epm 58.4 58.4 144528.8 '' 178353.3 ** 190758.7 '' 192510.1 '' |PRM 2C com 39.8 39.8 96385.4 '' 118942.1 '' 127215.7 '' 128383.7 ''PRM.2D com 3.0 3.0 3.3 4.1 4.4 44 I

PRM.3 - com 33.3 38.3 38215.2 * 41033.2 * 43720.0 * 46311.2 *PRM.4 A com 25.8 25.8 29451.5 ** 34216.5 ** 38844.4 '' 43509.1 ''PRM.48 com 29969.9 29969.9 2.85E + 7 '' 2.85E + 7 ' ' 2.85E + 7 '' 2.8 5E + 7 * ' |

!PRM.5 com 2998.8 2998.8 81871.8 ' 100652.9 * 107556.6 ' 108528.2 'PRM.6 A com 2290.6 2290.7 118.2 117.9 117.8 117.8

I PRM.6B com 41.0 41.0 41.0 41.0 41.0 41.0

PRM.6C mR!hr 1.00E.1 1.00E .1 1.00E.1 1.00E.1 1. 00E.1 1.00E .1 -l

PRM.7 com 742.6 742.6 190287.3 ** 204016.0 '' 218494.9 ** 232139.3 **PRM.8 com 099.0 399.0 101255.5 ** 110346.1 '' 119119.8 ** 128082.2 ''PRM.9 com 800.0 800.0 192028 6 ** 206572.5 ** 223727.6 ** 239380.8 ''

PRM 10 com 1309.5 1309.5 1300.0 1300.0 1300.0 1300.0

PRM 13 com 29911.7 29912.5 8748.0 8748.0 8748.0 8748.0PRM 14 com 40.0 40.0 39117.5 ** 42138.4 '' 45096.7 '' 48376.2 **

j. PRM 15 com 236.0 236.0 1M587.5 * 210691.9 * 225483.3 * 241881.1 *PRM.16 A mRihr 1.12E + 0 1.12E + 0 1. I '! E + 0 1.12E + 0 1.12E + 0 1.12E + 0

PRM.168 mR!he 1.12E + 0 1.12E + 0 1.12? + 0 1.12 E + 0 1.12E + 0 1.12E + 0

PRM 16C mRlhr 1.12 E + 0 1.12 E + 0 1.12E * 0 1.12E + 0 1.12E + 0 1.12 E + 0 i

PRM.160 mR thr 1.12E + 0 1.12 E + 0 1.12E 4 0 1.12E + 0 1.12E + 0 1.12 E + 0

(PRM 25A com 0.1 0.1 0.1 0.1 0.1 0.1 jPRM 258 com 0.1 0.1 0. 0.1 0.1 0.1 ,

PRM 25C com 0.1 0.1 0.1 0.1 0.1 0.1

AREA MONITORS

| ARM.1 mR!hr | 9.95E.2 | 9.95E 2 5.16E + 2 ' ' 6.5 2 E + 2 ' ' 6.81 E + 2 ' ' 6.89E + 2 * *

| ARM 2 mR!hr ~ Mrd % 12 2.97E + 2 ' ' 3.6 7 E + 2 ' ' 3.93E + 2 * * 3.96E + 2 ' ' i'

ARM 3 mR/hr 1.00E + 0 1.00E 4 0 1.00E + 0 1.00E + 0 1.00i + 0 1.00E + 0l - A RM .4 mRlhr 9.19E.2 9.19E.2 - 1.2 3E + 2 ' ' 1.4 7E + 2 * * 1.63E + 2 * * 1.64 E + 2 ' '

ARM 5 mRihr 1.03E.1 1.03E 1 5.5 3E + 1 * * 6.67E + 1 * * 7.31 E + 1 * * 7.36E + 1 * *

ARM.6 mRlhr ' 4.18E + 0 4.18E + 0 2.58E + 0 2.58E + 0 2.58E + 0 2.58E + 0-- ARMJ- mRlhr 9.64E.2 9.64 E.2 9.2 4E + 1 ' ' 1.0 7 E + 2 * * 1.21 E + 2 ' ' 1.2 2 E + 2 ' '

ARM 8 mR the 9.30E 2 9.30E.2 9.51 E + 1 ' ' 1.03E + 2 ' ' 1.10E + 2 * * 1.17E + 2 * *

ARM.9 mR the 1.12 E.1 1.12 E.1 1.76E + 2 ' ' 2.17E + 2 * * 2.33E + 2 * * 2.35E + 2 * *

ARM 10 mR!ht 1.06E.1 1.06E.1 9.68E + 1 * * 1.06E + 2 '' 1.15E + 2 * * 1.2 3E + 2 * * I

ARM.11 mRihr 8.00E.2 8.00E.2 1.44 E.1 1.5 9E.1 1.65 E.1 1.66 E.1

ARM.12 mR!hr - 1. 71 E .1 1.71 E.1 9.65E + 1 * * 1.05E + 2 ' ' 1.12 E + 2 * * 1.21 E + 2 ' '

ARM.13 mRihr 1. 7 7 E.1 1.7 7 E .1 9.65E + 0 * 1.00E + 2 * * 1.10E + 2 * * 1.20E + 2 * *

A R M.14 mRlbr 1.6 5 E.1 1.6 5 E.1 4.35E + 1 * * 5.10E + 1 ' ' 5.69E + 1 ' ' 5.75E + 1 * *

ARM.15A R/hr 1.00E + 0 1.00E + 0 1.00E + 0 1.00E + 0 1.00E + 0 1.00E + 0

ARM 158 R:hr 1.00E + 0 1.00E + 0 1.00E + 0 1.00E + 0 1.00E + 0 1.00E + 0

A RM.16 mR;hr 1.01E + 1 1.01 E + 1 8.45E + 2 * 1.06E + 3 ' ' 1.10E + 3 * * 1.12 E + 3 * *

ARM.17 mR;hr 9.18E + 0 9.18E + 0 4.8 5E + 2 * 6.09E + 2 * 6.38E + 2 * 6.4 5E + 2 *

ARM.18 mRthe 1.2 6E + 1 1.26E + 1 8.62E + 1 1.08E + 2 * 1.2 7E + 2 * 1.34E + 2 *

ARM.19 mRlbr 1.04E + 0 1.04E + 0 1.32E + 2 * 1.58E + 2 * 1.7 5E + 2 * 1.76E + 2 '

ARM 20 mRlhr 1.32E + 2 1.32E + 2 1.03E + 1 1.03E + 1 1.03E + 1 1.03E + 1

ARM.21 mRehr 3.51E + 2 3.51 E + 2 5.21E t o 5.21E + 0 5.21E + 0 5.21E + 0

' ARM.22 mR /hr 7.01 E.2 7.01E 2 2.5 8 E .1 2.83E.1 3.10E.1 3.18 E.1

ARM.23 mR.hr 7.1 1 E .2 7.1 1 E.2 3.10E + 0 3.50E + 0 3.93E + 0 4.06E + 0

ARM 24 mR|hr 7.01 E.2 7.01 E.2 2.58 E.1 2.8 3E.1 3.10E.1 3.18E.1

ARM <25 mR!hr 1.00E + 0 1.00E + 0 1.00E + 0 1.00E + 0 1.00E + 0 1.00E + 0

3555 0 8.1 3 Rev.10/26/90

. . - . .. ..

-. - . - - - - . - ~ - _ - - ..- - - _ _ _.~.- - - -- - ~.- -

VROJAN NUCLEAR PLANT RADIA? ION MOUT00 SUMMARY

6:15 6:30 6:45 7:00 7:15 7:30

MONITOR #: UNITS 3:00 3:15 3:30 3:45 4:00 4:15

com_

1840.1 1840.1 1840.1 1840.1 1840.1 1840.1(PRM 1 A -[PRM.1 B com 7919.1 7919.1 7919.1 7919.1 7919.1 7919.1

PRM 1C com 5710.6 5710.6 Si10 6 5710.6 5710,6 5710.6

PRM.1D com __21.3 21.3 21.3 21.3 21.3 21.3

PRM.1 E mR 'hr - * 1.00E.1 1.00E.1 1.OOE .1 1.00E .1 1.00E 1 1.00E.1

PRM.2 A com 436541.7 '* 405955.1 ** 299353 5 ** 3.92E + 8 '' 3.92E + 8 '' 4.2 3E + 8 * *

PRM 2B epm 1951530 ** 145670.1 '' 118965.3 '' 3. 5 5 E + 7 ' ' 3 SSE + 7 * * 3 8 3E + 7 * *

PRM.20 com 130146.2 '' 97146.8 '' 793'47.5 '' 1.02 E + 7 ' ' 1.2 8E + 7 ' ' 1.4 0E + 7 ' '

PRM-2D com 4.5 3.3 2.7 349.7 * 438.9 * 4.80E + 2 *

PRM.3 com 47 t15.2 * 4044 0 3 * 33201.6 * 4277626.5 ** 1.04 E + 7 ' ' 1.04 E + 7 ' '

446'5.2 '' 37341.2 ** 30518.0 '' 4081281.3 '' 1.06E + 7 ' ' 1.03E + 7 * *PRM.4 A com 4

PRM.48 com 2.85E + 7 ' ' 2.8 5E + 7 * * 2.0$E + 7 * * 2.85E + 7 '' 2.8 5E + 7 * ' 2.85E + 7 * *

PRM.5 com 109996.7 * 82521.1 * 67675.9 * 1. 7 9E + 8 * * 1. 7 9E + 8 ' ' 1. 7 9E + 8 * *

PRM 6A com 117.8 123.3 .19.3 120.6 120.6 120.6

PRM.6B com 41.0 41.0 41.0 41.0 41.0 41.0

PRM.6C mR!hr 1.00E.1 - . 00E.1 1.00E.1 1.00E.1 1.00E .1 1.00 E.1

PRM.7 epm 236518.7 '' 198612.3 **- 162487.3 '' 2.04E + 7 * * 5.40E + 7 ' ' 5.20E + 7 * *

PRM.8 com 128952.1 ** 116284.6 '' 103066.2 '' 1.96E + 7 ' ' 5.51 E + 7 ' ' 5.20E + 7 ' '

PRM.9 com 242851.3 '' 207376.6 '' 171862.9 '' 2.44E + 7 '' 5.85E + 7 * * 5.20E + 7 * *

PRM.10 com 1300.0 1300.0 1300.0 1300.0 1300.0 1300.0'

PRM 13 com E ?d 8.0 8748.0 8748.0 8748.0 8748.0 8748.0PRM 14 com 48822.9 '' 41737.3 '' 33972.6 ** 4987317.4 '' 1.15E + 7 ' ' 1.05E + 7 ' '

PRM.15 com 244114.5 ' 200686.5 * 169863.1 * 4238537.5 '' 1.08 E + 7 * * 1.05E + 7 ' '

PRM.16 A mRihr 1.12E + 0 1.12E + 0 1.12E + 0 1.12E + 0 1.12E + 0 1.12 E + 0

PRM.168 mR/hr 1.12E + 0 1.12E + 0 1.12E + 0 1.12E + 0 1.12E + 0 1.12E + 0

PRM.16C mR!ht 1.12E + 0 1.12 E + 0 1.12E + 0 1.12E + 0 1.12E + 0 1.12 E + 0

PRM.160 mRlhr - 1.12E + 0 1.12E + 0 1.12E + 0 1.12E + 0 1.12E + 0 1.12E + 0

PRM 25A com 0.1 0.1 0.1 0.1 0.1 0.1

PRM.258 com 0.1 0.1 0.1 0.1 0.1 0.1

(PRM.25C com - 0.1 0.1 0.1 0.1 0.1 0.1

- AREA MONITORSARM.1 mR/hr - 6.98E + 2 * * 5.01 E + 2 * * 4.19E + 2 * * 1. 8 B E + 6 ' * 1. 8 8 E + 6 * * 1. 8 8 E + 6 * *

ARM.2 mR/hr 4.0 2 E + 2 * ' 3.00E + 2 ' ' 2.45E + 2 * * 3.74E + 5 * * 3.7 4E + 5 ' ' 3.74E + 5 * *

ARM 3 mR/hr 1.00E + 0 1.00E + 0 1.00E + 0 3.74E + 3 * * 3.74E + 3 ' ' 3.74E + 3 ' '

ARM 4 mR /hr 1.66E + 2 ' ' 1.31 E + 2 * * 1.04E + 2 * * 4.08E + 4 * * 4.08E + 4 ' ' 4.08E + 4 ' '

ARM.5 mR/hr 7.4 7 E + 1 * * 5.79E + 1 ' ' - 4.62 E + 1 ' ' 4.36E + 4 * * 4.36E + 4 * * 4.36E + 4 * *

ARM.6 mRlhr 2.58E + 0 2.58E + 0 2.58E + 0 2.93E + 0 2.93E + 0 2.93E + 0 ,

ARM 7 mR!hr - 1.24E + 2 ' ' 1.02 E + 2 * * 7.86E + 1 * * 1.2 3E + 4 ' * 1.2 3E + 4 * * 1.2 3E + 4 * *

ARM.8 mR 'br 1.18 E + 2 * * 1.01 E + 2 * * 8.33E + 1 '' 1.18E + 4 ' ' 2.83E + 4 ' ' 6.68E + 4 ' *

ARM.9 mR:hr 2.38E + 2 * * 1. 7 9E + 2 * * 1.4 6E + 2 ' ' 3.16E + 5 * * 3.1 E E + 5 * * 3.16E + 5 * '

ARM.10 mR/hr 1.2 6E + 2 * * 1.0 7 E + 2 * * 8.4 7E + 1 * * 1.0 3E + 4 * ' 2.68E + 4 * * 7.34 E + 4 * *

ARM.11 mRihr 1.6 7 E.1 1.4 5 E.1 1.33E.1 1.44E + 0 * 1. 8 4 E + 1 ' ' 3.08 E + 1 * *

1.06E + 4 * * 2.56E + 4 ' ' 6.4 3E + 4 ' 'ARM.12 mR/hr 1. 2 2 E + 2 - * * 1.04E + 2 -' ' 8.39E + 1 ''~9.17E + 4 * * 9.17E + 4 * * 9.17E + 4 * 'ARM.13 mR1hr - 6.01 E + 1 * * 4.50E + 1 ' ' 3.6 7 E + 1 ' '

ARM.14 mRihr 5.83E + 1 * * 4.69E + 1 ' ' 3.6 7 E + 1 ' ' 3.34E + 4 * * 3.34 E + 4 ' ' 3.34E + 4 * *

ARM 15A R the 1.00E + 0 1.00E + 0 1.00E + 0 1.00E + 0 1.00E + 0 1.OOE + 0 -

ARM 158 R/hr 1.00E + 0 1.00E + 0 1.00E + 0 1.OOE + 0 1.00E + 0 1.00E + 0

ARM.16 mR the 1.13E + 3 * * 8.24E + 2 ' 6.95E + 2 * 3.26E + 6 * * 3.2 6E + 6 * * 3.2 6E + 6 ' ';_

| ARM 17 mR!hr 6.53E + 2 * 4.74E + 2 * 3.97E + 2 * 1.5 3E + 6 * * 1.5 3E + 6 ' ' 1.53E + 6 * *

! ARM.18 mR!hr - 1.65E + 2 * 1.83E + 2 * 1.76E + 2 * 2.00E + 5 * * 2.00E + 5 * * 2.00E + 5 * *- ARM 19 mRIhr 1.79E + 2 * 1.41 E + 2 * 1.11 E + 2 * 3.4 5E + 4 '' * 3.4 5E + 4 * * 3.4 5E + 4 * *

! ARM.20 mRIhr 1.03E + 1 1.03E + 1 1.03E + 1 1.10E + 1 1.10E + 1 1.10E + 1

ARM.21 mR/hr 5.21E + 0 5.21 E + 0 5.21E + 0 5.35E + 0 5.35E + 0 5.35E + 0'

ARM 22 ' mRlbr 3.2 3E.1 2.67 E.1 2.2 7E.1 2.03E.1 7.74 E.2 1.62 E .1

ARM.23 mR/hr 4.13E + 0 3.2 3E + 0 2.60E + 0 1. 7 8 E + 3 * * 1.78E + 3 * * 1. 7 8E + 3 * *

ARM.24 mR/hr 3. 2 3 E.1 2.67 E.1 2.2 7 E.1 2.03E.1 7.74E.2 1.6 2 E.1

| ARM.25 mR!ht 1.00E + 0 1.00E + 0 1.00E + 0 1.00E + 0 1.00E + 0 1.00E + 0

i

, - 3555 0 8.1 4 Rev.10/26 00

l'!

i __ _ _ . _ - . - - - . . _ _ . . , _ - . _ __m

. - . . -. - - - - . . . ~ . ~ . . - - . - - - - - . - - - - . _ . - - ~ - . . - . -

TROJAN WUCLEAR PL ANT QADI ATION MONITOR SUMM ARY

7.45 8:00 8:15 8:30 8/o 9 00MONITOR 0 UNtTS 4:30 4 45 5 00 5:15 5:30 5:45PRM.1 A com 1840.1 1840.1 1840.1 1840.1 1840.1 1840.1

PRM.18 com 79191 7919.1 7919.1 7919.1 7919.1- 7919.1

PRM .1 C com . 5710.6 5710.6 5710.6 5710 6 5710.6 5710 6PR M.1 D com 21.3 21.3 21.3 21.3 21.3 21.3PRM 1E mR.tr 1.00 E .1 1.00E.1 1.00E.1 1.00E 1 1.00E.1 1.00E.1

PRM.2 A com 4.33E + 8 * * 4.36E +8 ** 4.37E + 8 * * 4.3 7E + 8 ' * 4.37E + 8 * * 1. 4 2 E + 8 * '

PRM.2B com 3 92E + 7 * ' 3 95E + 7 ' * 3.96E + 7 ' ' 3.96E + 7 ' ' 3.96E + 7 * * 1.2 9E + 7 ' '

'PRM.2C com 1.4 5 E + 7 * * 1. 4 6E + 7 ' ' 1.4 6E + 7 ' ' 1. 4 7 E + 7 * * 6.12 E + 7 ' ' 2.16E + 6 * *PRM.2D com 4.9 7E + 2 ' 5.01 E + 2 ' 5.01 E + 2 * 5.04E + 2 * 2.10E + 3 * * 7.42E + 1

PRM.3 com 1.04 E + 7 * * 1.04 E + 7 * * 1.04 E + 7 ' ' 1.04 E + 7 * * IfE+7** 1.04E + 7 * *

PRM -4 A com 1.0 3E + 7 * * 1.03E + 7 * * 1.03E + 7 * * 1.03E + 7 ' ' 1.0 3E + 7 * * 103E + 7 ''.

PRM 4B com 2.85E + 7 '' 2.85E + 7 * * 2.85E + 7 '' 2.8 5E + 7 * * 2.I SE + 7 * * 2.85E + 7 * *

PRM.5 com 1. 7 9 E + 8 ' ' 1. 7 9E + 8 * ' 1. 7 9E + 8 ' ' 1. 7 9E + 8 * * 1. : 9E + 8 * * 1. 7 9 E + 8 * *

PRM.6A com 120.6 120.6 120.6 120.6 120.6 1 '. ).6

PRM.6B com 41.0 41.0 41.0 41.0 41.0 j1.0PRM.6C mR /hr 1.00E.1 1.00E.1 1.00E.1 1.00E .1 1 00E.1 . N E.1

PRM.7 com 5.20E + 7 * * 5.20E + 7 ' * 5.20E + 7 ' * 5.20E + 7 * * 5.2 ')E + 7 * * ' . 2 JE + 7 * *,

PRM.8 com 5.20E + 7 * * 5.20E + 7 ' ' 5.20E + 7 * * 5.20E + 7 ' ' 5.2f, E + 7 * * 5 '.0E + 7 * *

PRM.9 com 5.20E + 7 * * 5.20E + 7 * * 5.20E + 7 * * 5.20E + 7 * * 5.20E + 7 * * I20E + 7 * *

[ 1300.0PRM.10 com 1300.0 1300.0 1300.0 1300.0 1300.0PRM 13 com 8748.0 8748.0 8748 0 8748.0 8748.0 8748.0PRM.14 com 1.05E + 7 ' ' 1.05E + 7 ' * 1.0 5 E + 7 * * 1.05E + 7 ' * 1.05 E + 7 ' ' 1.05E + 7 ' *PRM.15 com 1.05E + 7 * * 1.05E + 7 * * 1.05E + 7 ' ' 1.05 E + 7 ' * 1.05 E + 7 ' * 1.05E + 7 * *PRM.16 A mR the 1.12E + 0 1.12E + 0 1.12E + 0 1.12E + 0 1.12 E + 0 1.12E + 0

PRM.168 mR hr 1.12E + 0 1.12E + 0 1.12E + 0 1.12E + 0 1.12E + 0 1.12E + 0

PRM.16C mR!ht 1.12E + 0 1.12E + 0 1.12E + 0 1.12E + 0 1.12E + 0 1.12 E + 0

PRM.160 mRlbr 1.12E + 0 1.12E + 0 1.12E + 0 1.12E + 0 1.12E + 0 1.12E + 0

PRM.25 A com 0.1 0.1 0.1 0.1 0.1 0.1

PRM 25B com 0.1 0.1 0.1 0.1 0.1 0.1

PRM.25C com 0.1 0.1 0.1 0.1 0.1 0.1

AREA MONITORSARM.1 mR!hr 1.88E + 6 * * 1.88E + 6 * * 1. 8 8 E + 6 ' ' ' 1.88E + 6 * * 1.88E + 6 * * 1. 8 8 E + 6 * *

ARM.2 mRihr 3.74E + 5 ' ' 3.74E + 5 ' ' 3.7 4 E + 5 ' ' 3. 7 4 E + 5 * * 3.74E + 5 ' ' 3.74E + 5 ' 'ARM 3 mR/hr 3. 7 4 E + 3 * * 3.74E + 3 * * 3. 7 4 E + 3 ' ' 3.74E + 3 * * 3. 7 4 E + 3 * * 3.74E + 3 * *

4.08E + 4 * * 4.08 E + 4 * * 4.08E + 4 ' 'ARM 4 mR!ht 4.08E + 4 * * 4.08E + 4 '' 4.08E + 4 *

ARM.5 mRlhr 4.36E + 4 * * 4.36E + 4 ' * 4.36E + 4 * * 4.36E + 4 * * 4.36E + 4 * * 4.36E + 4 ' *ARM.6 mRIhr 2.93F + 0 2.93E + 0 2.93E + 0 2.93E + 0 2.93E + 0 2.93E + 0

ARM.7 mR/hr 1.2 3E + 4 ' ' 1.2 3E + 4 ' ' 1. 2 3E + e . * * 1.2 3E + 4 ' ' 1.23E + 4 ' ' 1.2 3E + 4 ' '

ARM.8 - mR /hr 7.05 E + 4 ' ' 7.05 E + 4 * * 7.0 5 E + 4 ' ' 7.05E + 4 * * 7.05 E + 4 * * 6.81 E + 4 * *

ARM.9 mRIhr 3.16E + 5 ' ' 3.16E + 5 * * 3.16E + 5 * * 3.16E + 5 ' ' 3.16E + 5 ' ' < 3.16E + 5 * *

ARM.10 mR!hr 7.34E + 4 * * 7.34 E + 4 ' ' 7.34E 4 4 '' 7.34E + 4 * * 7.34 E + 4 ' ' 7.05E + 4 ' 'ARM 11 mR fhr 3.2 6E + 1 ' ' - 3.2 6E + 1 * * 3.26E .1 * * 3. 2 6 E + 1 * * 3. 2 6E + 1 * * 3.26E + 1 * *

ARM 12 mR/hr 7.12 E + 4 * * 7.12 E + 4 * * 7.12 E + 4 ' ' 7.12 E + 4 ' ' 7.12 E + 4 ' ' 6.8 PE + 4 ' '

ARM.13 mR/hr 9.17E + 4 ' ' 9.17E + 4 * * 9.17 E + 4 * * 9.17E + 4 * * 9.17E + 4 * * 9.17E + 4 * *

ARM.14 mR!ht J.24E + 4 * * 3.34 E + 4 ' ' 3.34 E + 4 ' ' 3.34 E + 4 * * 3.34 E + 4 ' ' 3.34 E + 4 ' 'ARM.15 A R;hr 1.00E + 0 1.00E + 0 1.00E + 0 1.00E + 0 1.00E + 0 1.00E + 0

ARM.158 R tr 1.00E + 0 1. ')Of + 0 1.00E + 0 1.00E + 0 1.00E + 0 1.00E + 0

ARM.16 mR thr 3.2 6E + 6 ' ' 3.26E + 6 * * 12 6E + 6 * * 3.2 6E + 6 ' ' 3.26E + 6 '' 3.26E + 6 * ';

| ARM.17 mR;hr 1. 5 3 E + 6 ' ' 1.5 3E + 6 ' ' 1.b?E + 6 * * 1.5 3E + 6 ' ' 1. 5 3 E + 6 * * 1.5 3E + 6 ' '

ARM 18 mRihr - 2.00E + 5 * * 9.00E + 5 * * 2.00E * 5 ' ' 2.00E + 5 ' ' 2.00E + 5 * * 2.00E + 5 * *

A RM.19 mRihr 3.4 5E + 4 * * 3.45E + 4 * * 3.4 5 E + t * * 3.4 5 E + 4 ' ' 3.4 5E + 4 * * 3.4 5E + 4 * *

ARM 20 mRmt 1.10E + 1 1.10E + 1 1.10E + 1 1.10E + 1 1.10E + 1 1.10E + 1

ARM 21 mR the 5.35E + 0 5.35E + 0 5.35E + 0 5.35E + 0 5.35E + 0 5.35E + 0

ARM.22 mR.tr 1.9 9E.1 2.0 3E.1 7.74E.2 1.62 E.1 1.99E.1 2.03E.1

ARM.23 mR;ht 1. 7 8 E + 3 ' ' 1.7 8 E + 3 * * 1. 7 8 E + 3 * * 1. 7 8 E + 3 * * 1.60E + 3 ' ' 1.0 7 E + 3 * *

ARM.24 mR /hr 1.99E.1 2.03E.1 7. 7 4 E .2 1.62 E.1 1.99E.1 2.0 3E.1

ARM.25 mR!ht 1.00E + 0 1.00E + 0 1.00E + 0 1.00E + 0 1.00E + 0 1.00E + 0

l 3555 0 8.1 5 Rev.10/26:90

_ _ _ _ _ _ _ _ _ _ . _ . _ _ . __ _

TQOJAN NUCLEAQ P1. ANT R ADIATON MONITOR SUMM ARY

9:15 9:30 9:45 10:00

MONITOR 8: UNITS 6:00 6:15 6:30 6:45

PRM.1 A com 1840.1 1840.1 1840.1 1840.1

PRM.18 com 7919.1 7919.1 7919.1 7919.1

PRM 10 com 5 710 = 6 3710.6 5710.6 5710.6

PRM.10 com 21.3 21.3 21.3 21.3

PRM 1E mR /hr - 1.00E.1 1.00E.1 1.00E.1 1.00E.1

PRM.2 A com 4.62E + 7 * * 1.51 E + 7 * * 4.94 E + 6 * * 4.94E + 6 ' '

PRM.28'

com 4.19E + 6 ' ' 1.3 7 E + 6 * * 4.48E + 5 ' ' 4.48E + 5 ' '

PRM.2C com 8.20E + 5 * * 2.64E + 5 ' * 1.68 E + 5 ' ' 1.68 E + 5 ' '

PRM 2D com 2.81E + 1 - 9.05E + 0 5.76E + 0 5.76E + 0

PIM.3 com 1.04E + 7 ' ' 1.04 E + 7 * * 1.04 E + 7 ' ' 1.04 E + 7 * *

EM.4 A com 1.0 3E + 7 * * 1.03E + 7 ' ' 1.03E + 7 ' ' 1.03E + 7 * *

PRM .48 com 2.85E + 7 '' 2.85E + 7 ' * 2.85E + 7 ' * 2.85E + 7 * *

PRM.5 com 1.7 9E + 8 * * 1.7 9E + 8 * * 1.7 9E + 8 * * 1.7 9E + 8 ' '

PRM.6A com 120.6 120.6 120.6 120.6

PRM.6B com 41.0 41.0 41.0 41.0

PRM.6C mRlhr 1.00E.1 1.00E 1 1.00E 1 1.00E.1

PRM.7 com 5.20E + 7 " 5.20E + 7 ' ' 5.20E + 7 * * 5.20E + 7 ' '

PRM.8 com 5 20E + 7 '' 5.20E + 7 * * 5.20E + 7 * * 5.20E + 7 * *

PRM.9 com 5.20E + 7 * * 5.20E + 7 ' * 5.20E + 7 * * 5.20E + 7 ''PMM.10 com 1300.0 1300.0 1300.0 1300.0

i

PRM.13 com 8748.0 8748.0 8748.0 8748.0

PRM.14 com 1.05E + 7 * * 1.05E + 7 ' ' 1.05E + 7 ' ' 1.05E + 7 * *,

| PRM.15 com 1.05E + 7 * * 1.05E + 7 * * 1.05E + 7 * * 1.05E + 7 * *

PIM.16 A mR!ht 1.12E + 0 1.12 E + 0 1.12E + 0 1.12 E + 0

l PRM 168 mR/hr 1.12E + 0 1.12E + 0 1.12E + 0 1.12E + 0

PRM 16C mR/hr 1.12E + 0 1.12 E + 0 1.12 E + 0 1.12E + 0

PRM.160 mR/hr 1.12 E + 0 1.12E + 0 1.12E + 0 1.12E + 0

PRM.25A com 0.1 0.1 0.1 0.1

PRM 258 com 0.1 0.1 0.1 0.1

PRM 25C com 0.1 0.1 0.1 0.1

AREA MONITORSARM * mR/hr 1.8 8E + 6 ' ' ' 1.8 8E + 6 * * 1.88E + 6 * * 1.88E + 6 ' '

l ARM.2 mR/hr 3.74E + 5 ' 3.74E + 5 '' 3.74E + 5 '' 3.74E + 5 * *

ARM 3 - mRlhr 3.74E + 3 '' 3. 7 4E + 3 * * 3.74E + 3 * * 3.74E + 3 ' 'ARM 4 mR/hr 4.08E + 4 '' 4.08E + 4 * * 4.08E + 4 '' 4.08E + 4 * *

ARM.5 mR/hr 4.36E + 4 * * 4.36E + 4 * * 4.36E + 4 * * 4.36E + 4 * *

( ARM 6 mR/hr 2.93E + 0 2.93E + 0 2.93E + 0 2.93E + 0; ARM 7 mR!ht 1.2 3E + 4 * * 1.2 3E + 4 * * 1.2 3E + 4 * * 1.2 3L ' 4 '

ARM 8 mR/hr 6.51 E + 4 ' ' 6.52E + 4 * * 6.52E + 4 * * 6.52E + 4 **

ARM 9 mRmr 3.16E + 5 * * 3.16E + 5 ' 3.16E + 5 * * 1.16E + 5 ''ARM 10 mR/hr 6.59E + 4 " 6.65E + 4 * * 6.65E + 4 * * 6.65E + 4 i

I

ARM.11 mR tr 3.26E + 1 * * 3.2 6E + 1 * * 3. 2 6E + 1 * * 3.26E + 1 *| ARM.12 mRlhr 6.56E + 4 * ' 6.5 2 E + 4 ' * 6.5 2 E + 4 ' ' 6.52 E 2

ARM.13 mR/hr 9.17E + 4 * * 9.17E + 4 ' * 9.17E + 4 * * 9.17E + 4 ' '

ARM.14 mR/hr 3.34E + 4 * * 3.34E + 4 * * 3.34E + 4 * * 3.342 + + Y '

ARM.15 A RIhr 1.00E + 0 1.00E + 0 1.00E + 0 1.00E + 0

| ARM.158 R/hr 1.00E + 0 1.00E + 0 1.00E + 0 1.00E + 0

|. ARM.16 mR/hr 3.26E + 6 " 3 26E + 6 * * 3.2 6E + 6 ' ' 3.2 6E + 6 * *

ARM 17 mR/hr 1.53E + 6 * * 1. 5 3 E + 6 ' ' 1.5 3E + 6 ' ' 1.53E + 6 ' '

ARM 18 mR!hr 2.00E + 5 * * 2.00E + 5 ' ' 2.00E + 5 * * 2.00E + 5 * *

ARM.19 mR/hr 3.4 5E + 4 ' ' 3.45E + 4 '' 3.4 5E + 4 ' ' 3.4 5 E + 4 '_

ARM.20 mR/hr 1.10E + 1 1.10E + 1 1.102 + 1 1.10E + 1

ARM.21 mR/hr 5.35E + 0 5.35E + 0 5.35E + 0 5.35E + 0 __ARM 22 mR/hr 7.74E.2 1.62 E.1 7.74E.2 7.74E.2

; ARM.23 mR/hr 5.46E + 2 * 1.78E + 1 1.78E + 1 1.78E + 1

| ARM 24 mR/hr 7.74E.2 1.62E 1 7.74 E.2 7.74E.2

ARM 25 mR/hr 1.00E + 0 1.00E + 0 1.00E + 0 1.00E + 0i

1

3055 0 8.1 6 Rev.10/26/90

__ _ _ - _ __

, + - - - - - - .u. m .u t s..n .

.

.

-

.

8.2 Radiation Monitor Data Sheets

_

$

1

g

|:

'3555 4/NUCL 1429 8.2-1- -

-.


EMERGENCY PREPAREDNESS DRILL

'

RADIATION MONITOR DATA SHEET

- REAL TIME 3:15

ELAPSED TIME 0:00.

Process Monitors Area Monitors

Monitor # Units Value Monitor # Units Value

PRM 1 A com 1.84E + 03 ARM 1 mR!hr 9.95E 02PRM 18 com 7.92 E + 03 ARM 2 mR/hr 7.25E 02

PRM 1C com 5.71 E + 03 ARM 5 m R/hr 7.90E 02

PRM 10 com 2.13E + 01 ARM 4 mR/hr 9.19E 02PRM 1E m3/hr 3.59E 07 ARM 5 mR/hr 1.03E 01

PRM 2A cp3 1. 31 E + 02 ARM 6 mR/hr 4.18E + 00

PRM 28 com 5.84E + 01 ARM 7 m R/hr 9.64E 02

PRM 2C com 3.98E + 01 ARM 8 mRlhr 9.30E 02PRM 2D com 2.93 E + 01 ARM 9 mR/hr, 1.12E 01

PRM 3 com 3.83 E + 01 ARM 10 mR/hr 1.06E 01

PRM 4A com 2.58E + 01 ARM 11 mR/hr 8.00E 02PRM 4B - com 3.00E + 04 ARM 12 mR/hr 1.71 E 01

PRM 5 com 3.00E + 03 ARM 13 mR/hr _1.77E 01PRM 6A epm _ 2.29E + 03 ARM 14 mR/hr 1.65E 01

PRM 68 con. 4.10E + 01 ARM 15A R!hr 1.00E + 00

PRM 6C mR/hr ,.?8E 0 _ ARM 15B R/hr 1.00E + 00

PRM 7 com 7.4 3E + 02 ARM 16 mR/hr 1.01 E + 01~

PRM 8 com 3.99E + 02 ARM *7 mR/hr 9.18E 4 00

PRM 9 com 8.00E + 02 ARM 18 mR/hr 1.26E + 01

PRM 10 com 1.31 E + 03 ARM 19 mR/hr 1.04E + 00

PRM 13 com 2.99E + 04 ARM 20 mR/hr 1.32E + 02

PRM 14 com 4.00E + 01 ARM 21 mR/hr 3.51 E + 02

PRM 15 com 2.36E + 02 ARM 22 mR/hr 7.01E 02PRM-16A mRlbr 1.12E + 00_ ARM 23 mR/hr 7.11E 02

PRM 168 mR/hr 1.12E + 00 ARM 24 mR/hr 0.00E + 00

PRM-16C mR/hr 1.12 E + 00 ARM 25 mR/hr 6.31E 02PRM 16D mR/hr 1.20E 01

PRM 25A cpm, 0.00E + 00 Effluent Parameters

PRM 25B com 0.00E + 00

PRM 25C com 0.00E + 00 Aux Bldg Vent (# Fans)Containment Purge& H Vent (FR 3180)(cfm)j

SJAE (FR 3100)(cfm)

' Alert Alarm (a) Local Indicators in TSC* * High Alarm Bkg = Background

3555 8.2 2

_ .____ _ _ _ __ -. -__ ___ _

_ _

.

. .,

SJ Estallunple.Rinths

and

RadiologitaLJnfomWien

,

3555-4/NUCL-1429 8.3-1

PASS RADIOLOGICAL INFORM AT60N-

1Drill Time

Before After7:15 7:15

mR ht) (mR/hr)

A. RCS PASS

Pass ARM Readings (RE5624 A & B) 10 200

Window closed, dose rate,3 feet fromsample slud.150 ml RCS sample 41uted 1000:1 <1 <1

Window closed dose rate,6 inches from150 ml RCS sample 41uted 1000:1 <1 1

Window open dose rate,6 inches from150 ml RCS sample 41uted 1000:1 1 8

Window closed, dose rate,2 feet from ;

0.6 cc off gas sample <1 <1

6. Containment Pass

Window closed, dose rate, from noble gas sample

Contact <1 <1

1 foot <1 <1

Window closed, dose rate, f rom todine sample

Contact <1 <1

Ifoot <1- <1'

Window closed, dose rate, from particulate sample

Contact <1 <1

1 foot <1 <l

1;

1

I||.

'

|- 3555 8,3 2 Rev. 9/12/90

. . . _ . _ . . . . .- .- . , _ .. -... .._... _ _ _. .. . , - . - . _ . _ _ . _ _ - . . __ _ _ . . . _

__S;_:

s''

>

tr

i

..

' REACTOR COOLANT SAMPLE SUMMARY- ._

' ACTIVITY CONCENTRATION (uCilg) AT INDICATED TIME |-'

'

.

;

'D / Sample 1- Sample 2 Sainple 3 I-

ilsotope 3:15 7:15- 7:15 10:30 After 10:30,|

Kr 85 1.5 E 01 2.6 E + 01 8.9 E + 00

. Kr 87! 6.0 E 02 ' 7.9 E + 00 2.7 E + 00 i

Kr88| : 2.0 E-01 2.9 E + 01 1.0 E + 01 I- ~ Xe 131m ' 1.1 E 01-: - 1.1 E + 00 3.9 E-01

'Xe 133m 2.2 E 01 3.7 E + 00 1.3 E + 00 -

Xe 133 ' 1.8 E + 01 - 2.3 E + 02 . 7.8 E + 01

Xe 135m .1.3 E-02 ' 2.6 E + 00 8.8 E-01 -"

- Xe 135 : 3.5 E 01 1.6 E + 01- 5.4 E + 00

~ Xe 138 - 4.4 E 02 - 8.7 E + 00 3.0 E + 00

I131 2.7 E 01 1.1 E + 02 3.8 E + 01,

'

3. - l132: 1.0 E 01 1.9 E + 01. 6.4 E + 00

l133' 3.8 E 01 ' 8.2 E + 01 2.8 E + 01 j,

1134 4,7 E 02 2.0 E + 01 6.8 E + 001

'|135= 1.9 E 01 4.3 E + 01 1. 5 E .+ 01 1--

:Te 132 ~ ~ 2.7 E 02 t 4.6 E+ 00 1.6 E + 00 .. )JCs 134' 2.5 E 02: 4.3 E + 00 1.5 E + 00 1

Cs 137 1.8 E 02 3.1 E + 00 1.1 E + 00

Ba 140 2.2 E-04 3.7 E 02 1,3 E 02 :4

'9

. 1

t

,

i

.-rj

3555; 8.3 3- Rev. 9/12/90-~;

. - . _ . _ . . - - -- .

._- . .. -. .. . _ . .- _ . - . _ . . . ~ _ . . .-__m . . . _ . _ . _ ,-

,,

' "

.

m, ' _ 9

'4,

r' 4.

-1, .

, . . . -,

.

1

P AUXILIARY BUILDING SUMP SAMPLE SUMMARYt ,

c t

: ACTIVITY CONCENTRATION (uCi/cc) AT INDICATED TIME z'

<

Sample 1 : Sample 2 Sample 3 - ;

isotope- '3:15 7:15 7:15 10:30 After 10:30' -*

-|i31 ' 2.7 E 01 1.1 E + 02 3.8 E + 01; ,

| ~ --| 132 1.0 E-01 1.9 E + 01 6.4 E + 00 f

1133 3.8 E 01 8.2 E + 01 :2,8 E + 01''

~I134 4.7 E 02 2.0 E + 01 6.8 E + 00 -

-1135- 1.9 E-01 4.3 E + 01 -1.5 E + 01 - t1>

# 'Te 132 - ,2.7 E 02 ;4.6 E + 00 - 1.6 E + 00

2.5 E 02 - 4.3 E + 00 1.5 E + 00 ' ;.Cs 134 - .

'

: Cs 137' - 1.8' E 02 - 3.1 E + 00 1.1 E + 00

-Ba 140 :2.2 E 04 3.7 E 02 .1~ 3 E 02..

. - .1

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3555 8.3 4 - Rev. 9/12/90'

l ..-- --. - - .-. . _ . -, , _. . . _ , . , , , . _ , , , , , , ,

. . - - -.

.

. - - - . - . . . , - . ~ . .. .. .~~ .,-.- .-. ..~ ,~ - - . .-.

w+,

,,

-

:

4

- A

hUXILIARY BUILDING AIR SAMPLE SUMMARY.

ACTIVIT CONCENTRATION (uCi/cc) AT INDICATED TIME l7

Sample 1 Sample 2 Sample 3 |

~ isotope :- 5:15 7:15- 7:15 10:30 After 10:30 I

JKr 85 3.2 E 04' 3.3 E 02 ~ 3.0 E 05 I

L Kr 87 -- 1.2 E 04 9.5 E 03 8.6 E 06-'

- Kr 88 - 4.1 E 04 3.6 E 02 3.3 E 05' q>

'Xe 131m. 2.3 E 04 - 1.5 E 03 1.3 E 06.Xe-133m ' : 4.7 E 04 4.8 E 03 . 4.3 E 06

'

-;Xe 133 - 3.8 E 02 - 2.9 E 01 - 2.7 E-04 -1

' Xe 135m : 2.3 E 05 2.6 E 03 2.4 E 06- -|~l

.Xe 135'- 7.4 E 04 2.0 E 02 1.8 E 05'Xe 138e 7.7 E 05 9.2 E 03 8.3 E 06-1131 1.4 E 04- 3.6 E 02 .3.3 E 05 :

1132 5'1 E 05- 5.8 E 03 ' 5.2 E-06 l.

1133 2.0 E 04 2,6 E 02: 2.4 E 05 j

1134; 2.0 E 05 - 5.8 E 03' 5.3 E 06 'j,

'# l135- 1.0 E 04 1,4 E 02 1 2 E-05 -

Te 132 9.8 E 06 1.4 E 03- 1.2 E 06Cs 134: 1.6 E 06 2.3 E 04 2.1 E 07Cs 137 8.0 E 07 1.2 E-04 1.0 E 07 q

Ba 140- 1.8 E 06. 2.7 E 04 2;5 E 07,

j,

- ,

;

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.,

,-

4

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.

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3555 8.3 5 Rev. 9/12/90

. . . = _ . _- _ _ _ _ _ _ ._ _ _ _ __ _

. . . . - . - . . . - . .- _. . -~ .- _. . . . ..

1~'

i.

I

l

..

.

-

-

8.4 In Plant RadiologicaLD21a

3555-4/NUCL 1429 8.4 1

|- . . .

, , _ , - _.ym _o.m ...,m > . . , _ _ _ . . . _ . . _ . _ _ . _ _ . _ , _ _ _ . - . . . _ _ , _ - . ~,

,

I f (- 4 , ,j

4: |

i,s

. ,

RELEASE RATES ~AND TOTAL RELEASES '*

E |

- I

]. - RELEASE RATE (Ci/secl =A

isotoon 5:15 5:30 5:45 6:00 . 6:15 6:30. 6:45 - 7:00

Kt83- 3.4 E 02 4.6 E 02 4.9 E 02- 5,1 E 02 5.1 E 02 5.1 E 02 5.1 E 02 5.1 E 02 1

Kr83m' 1.4 E 01 1.8 E41 2.0 E 01 2.1 E 01 2.1 E 01 : 2.1 E 01 21E01 . 21 F 01 |''

: Kr 85 5.2 E 03, 6.9 E 03 7.5 E 03 7.7 E 03 ~ 7.8 E 03 7 8 E 03 7.8 E 03 - 7.8 E 03 : '

Kr87' 2.1 E 03 ' 2.7 E 03 2.9 E 03 ' 2.9 E 03 2.9 E 03 2.9 E 03. 2.9 E-03 . 9 E 03 I

:Kt88: 6.9 E 03 9.1 E 03 9.8 E 03 1.0 E42 1.0 E 02 1.0 E.02 ' 1.0 E 02 - 1.0 E 02 :!Xe 131m. 3.8 E 03. 5.1 E43 ~ 5 5 E 03 5.6 E 03 5 7 E 03 5.7 E 03 5.7 E 03 - 5.7 E 03 "'i

.

: Xe 133 6.2 E 01 8.3 E 01 ' 9.0 E 01 9.2 E 01 9.3 E 01 9.3 E-01 0.3 E 01 ' 9.3 E 01

1 Xe 133m 7.6 E 03 1.0 E 02 ~ 1.1 E 02 1.1 E 02 1.1 E 02 : 1.1 E 02 1.1 E 02 11 E 02

Xe 135 " 1.2 E 02 : 1.6 E 02 1.7 E 021 18 E 02 - 1.8 E 02. 1.8 E 02 1.8 E 02 - -18 E 02

. Xe 135mi 4.5 E 04 - 5.3E44 5.4 E 04 5.4 E 04 5.4 E 04 5.4 E 04 - 5.4 E 04 ; 5.4 E 04 '1,

: Xe4138 1.5 E 03 1.8 E 03 1.8 E 03 L19 E 03 1.9 E 03 1.9 E 03 19 E 03 ' 1.9 E 03

'1 131;. 1.2 E 04 ,1.6 E 04 ' 1.7 E 04 1.7 E.04 ' 1.7 E 04 1.7 E 04 1.8 E 04 1.8 E 044 7,

h> -1132 4.3 E 05 ' 5.7 E.05 ~ 6;1 E 05 ' 6.2 E 05 6.2 E 05 6.3 E 05 6.3 E 05 6.3 E 05 .,*

1133' 1.6 E 04 2.2 E 04 ^ 2.4 E 04 2.4 E 04 2.4 E 04 ' 2.5 E 04 2.5 E 04 ' :2.5 E 04

l134 2 0 E 05 - 2.6 E 05 2.7 E 05 2.8 E 05 - 2.8 E 05 2.8 E 05 . 2.8 E 05 ~ '2.8 E 05

I135' '8.2 E 05. 1.1 E 04 1.2 E 04 - 1.2 E 04 1.2 E 04 ~ 1.2 E 04 11.2 E 04 1.2 E 04.

i ,

RELEASE RATEiCilsect ,

:s

[i Isotooe' 7:15 . 7:30 7:45- 8:00 8:15- 8:30 8:45: 9.00 4i

Kr.83 . ' 3.6 E + 00 4.7 E + 00 5.1 E + 00 5.2 E + 00 5 3 E + 00 5.3E+00 5.3 E + 00 .5.3 E A 00 ' .fKt83m " 1.4 E + 01 1.9 E +01 - 2.1 E + 01 21 E + 017 2.1 E + 01 2.1 E + 01 2.1 E + 01 21 E + 01 4,Kr85 5.4 E 01 - 7,2 E 01 - . 7 7 E 01 7.9 E 01 - 8.0 E 01 8.0 E 01 8.0 E 01 ' 8 0 E 01> , ,

Kr87: 1.6 E 01 21 E 01' 2.2 E 01 2.3 E 01'- - 23 E 01 2.3 E 01 2 3 E 01 :2.3 E 01 '

Kr88 6.0 E 01 7.9 E 01 : 8.5 E 01 ' :8.7 E 01 8.7 E 01 - 8.7 E 01 8.7 E 01 8.7 E 01.

:Xe 131m 7.8 E 03 2.6 E 02 3.2 E 02 3.4 E 02 3.5 E-02 3.5 E 02 3.5 E 02 ,3.5 E 02

sXe 133 15 E + 00 ' 5.2 E + 00 t 6.4 E + 00 6.9 [ + 00 . 7,0 E + 00 " 7.0 E + 00 ' 71 E + 00 . 7.1 E + 00~

- Xe 133m = ' 2.3 E 02 L L 8.4 E 02 11.0 E 01 1 1 E 01 - 1.1 E 01 1.1 E 01 1 1 E 01: 1.1 E 01 -'

' Xe 135 8.8 E 02 i 3.6 E 01 4.4 E 01 : 4 7 E 01 = 4.8 E 01 4.8 E 01 - 44 001 4 8 E 011 .>

Xe 135m: 1.3 E 02. 5 5 E 02 6.2 E 02 ~ 6,4 E 02 6 4 E 02 6.4 E 02 ' 6 4 E 02 S.4 E 02 -

'Xe138. 4.6 E 02 - '1.9 E 01 2.2 E 01 - - 2.2 E 01 2.2 E 01 - 2.2 E 01 2.2 E Oli 2.1 E 01'

1 131- 2.9 E 02.. 3.9 E 02 ' - 4.2 E 02 4.3 E 02 4.3 E 02 4.3 E 00 4.3 E 02 4.3 r 02 -

>l132 4.8 E 03 ' 6.3 E 03 ' 6.8 E 03 - 6.9 E 03 . 6.9 E 03 - 7.0 E-03 : 7.0 E 03 = 7.0 E 03

1133. 21 E 02 ~ 2.8 E 02 ' ' 31 F 02 3.2 E 02 3.2 E 02 . 3.2 E 02 > 3.2 E 02 - 3.2 E.32 -i 41134 5.1 E 03 ,6.5 E 03 6.9 E 03 7.0 E 03 7.0 E 03 7.0 E 03 : 7.0 E 03 7.0 E 03 :,

i1135 -1.1 E 02 1.5 E 02 - 1.6 E 02 ' 1.0 E-02 1.6 E 02 s 16 E 02_ ,1.6 E 02 1.6 E 02

s

!

, 3

9-

.

s

3555- 8.4 2 , Rev. 9/12/90s

'n- - - _ _ . _ _ _ - ._ ____. - . ,

_ - _ - - _ _ _ _ _ _ _ _ _ - _ -

|

RELEASE RATES AND TOTAL RELEASES.

- RELE ASE RATE (Ci'sec)

- T otai

isotope 6:15 9:30 9.45 10:00 10:15 10:30 ReleasetCl)

Kr83 1.8 E + 00 5.9 E 01 2.0 E 01 6.5 E 02 2.2 E 02 7.2 E 03 4.2 BE + 01

Kr83m 7.1 E + 00 2.4 E + 00 7.9 E 01 2.6 E 01 8.8 E 02 2.9 E 02 1.73E + 02

Kr SS 2 7 E 01 8.9 E 02 3.0 E 02 9.9 E 03 3.3 E 03 11 E 03 6.49E + 00

Kr87 6.7 E 02 1.9 E 02 5.6 E 03 16 E 03 4.7 E 04 1.4 E 04 1.8 7E + 00

Kr88 2.7 E 01 8.6 E 02 2.7 E 02 8.4 E 03 2.6 E 03 8.2 E 04 7.0BE + 00

xe 131m 1.2 E 02 3.9 E 03 1.3 E 03 4.3 E 04 1.4 E 04 4.8 E 05 3.03E 01

xe 133 2.3 E + 00 7.R E 01 2.6 E 01 8.6 E 02 2.9 E 02 9.5 E 03 5.87E + 01

xe 133m 3.8 E-02 13 E 02 4.2 E 03 1,4 E 03 4.6 E 04 1.5 E 04 9.23E 01

xe 135 1.6 E 01 5.2 E 02 1.7 E 02 5.5 E 03 1.8 E 03 5.9 E 04 3.66E + 00

xe 135m 1.1 E 02 1.9 E 03 3.2 E 04 5.4 E 05 9.3 E 06 1.6 E 06 4.67E 01

xe 138 4.0 E 02 7.2 E 03 1.3 E 03 2.3 E 04 4.2 E 05 7.6 E 06 1.62E + 00

1131 1.4 E 02 4.8 E 03 1.6 E 03 5.3 E 04 1.8 E 04 5.9 E 05 3.48E 01

b132 2.1 E.03 6.6604 2.0 E 04 6.3 E 05 2.0 E 05 6.0 E 06 5.62E 02

1133 1.1 E 02 3.5 E 03 1.1 E 03 3.8 E 04 1.3 E 04 4.1 E 05 2.58E 01

i134 1.9 E 03 5.2 E 04 1.4 E 04 3.9 E 05 1.1 E 05 2.9 E 06 5.65E 02

1135 5.3 E 03 1.7 E 03 5.6 E 04 1.8 E 04 5.9 E 05 1.9 E 05 1.32E 01

.

3555 8.4 3 Rev, 9/12/90

. _ _ _ _ _ _ _ _ _ ______________ - - _ - - _ _ -

_ . . . - .. . ..

CONTROL BUILDINGELEV ATION 93'

N-"

7

wmh.1- a -

!y-, ,.. . , i

l ..l l l l i f IIJN N--

j6) art we t

,

j

_ Cold Lab ,,..

YI

iC-

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Il I i ! -J; L[ i

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y 4

GENERAL1, DOSE R ATE INFORM ATION'

mRlht UNLESS NOTED NOTES

HRS A | 8 l C | D E l F.y_ TIME | '

315 As Read AS Read As Read As Read As Read As Read

515 O.t 0.1 0.1 0.1 |

j615 0.2 0.2 0.2 0.2 i

i'

700 30 32 38 38

800 30 32 38 38

000 30 32 38 38

1000 30 1 32 I 38 ) 38 ) i

2. AIRBORNE CONCENTRATIONS AND CONT AMIN ATION LEVELSCONTAMINATION(

I GENERAL

GAS l IODINE P ARTIC. ! NOTESLEVELS IN CPMTIME I

HRS UCilec uCilec uCi/ccAs Read

315 As Read AS Read As ReadAS Read

515 As Read As Read As ReadAs Read

615 AS Read As Read As ReadAs Read

700 As Read As Read As ReadAs Read i

800 As Read As Read AS ReadAs Read

900 As Read As Read As ReadAs Read

As Read j

1000 j AS Read | As Read i

[ REV.10'26:908.4 4

3555

- _

- . __ _ . . -

CONTROL BUILDING'

ELEVATION 45'.

.

N- ,-

f ot"P-J | ,I 1 ] LR P""

3

"utv

g

_ _d $

0o

^ ^ " '[ t 8C $ hop CCAWT 'O RW

-U_ L__ i I' '

.

8 AC 2.

l

4-

A nlu .u,. u

--, --

h_. y rs s',n

3 m

I=*= ,_

fg~,2 m

-

fitv 3 3

I tl C ALA41N IOC SHOP *===

' 1. DOSE RATE INFORM ATION

TIME mR/hr UNLESS NOTED GENERAL

HRS A B C 0,

E F NOTES

315 As Read As Read As Read -

515 0.2 0.2 0.2615 0.3 0.3 4.0700- 50.0 50.0 50.0800 50.0 50.0 50.0000 50.0 50.0' 50.01000 50.0 50.0 50.0

3. AIRBORNE CONCENTRATIONS AND CONTAMINATION LEVELSl' TIME G/ OlNE PARTIC. CONTAMINATION OENERAL

~

HRS uC uCi/cc LEVELS IN CPM NOTES

315- As' J- As Read As Read

515 At sad As Read As Read

L 615 A, tead As Read As Read

(; 700 1. E 08 *.2E 09 As Read! 800 1.10 1 08 4.2E 09 280

I900 1.10E O4 . 2E 08 4.2E-09 320

1000 1.10E .04 4.2E 08 4.2E 09 300

i- 3555 8.4-5 REV.10/26i90l;|

__ ____m.__ ~ , _ _ ,_

- --. . - - . - .

AUXILI ARY BUILDING . EASTELEVATION 45'

.-

HOT LAB' .

-_ g

F E El / -.r 1 A - c

# T. T1, s

'

--T W MT \' ,,

\ J -

3.

I I i 1,

-a7 "/ M T

_J

-

l I t( B-

,

'] - -- .__m

F PIPEWAYL

I

1CCW",

| r u oCl~=-

E,

SAMPLli- R M . --"_ " j

, ,

DWMT' SFP COOLING PUMPS_

-

l

-- 1. DOSE R ATE INFORM ATION

TIME mR/ht UNLESS NOTED GENERAL

HRS A B- C D E F NOTES

315 As Read ' As Read As Read As Read As Read As Read

515 150 155 190 175 1 1.5

615 278 310 375 375 1 2.5

700 5.20E + 04 5.80E + 04 6.95E + 04 6.85E + 04 3.70E + 03 7.00E + 02 Area *E* increases to this value

800 1.40E + 05 1.54E + 05 1.85E + 05 1.80E + 05 3.70E + 03 7.00E + 02 af ter 0700if PASS is on recirc.

900 1.30E + 05 1.53E + 05 1.80E + 05 1.85E + 04 3.70E + 03 7.00E + 02

1000 1.30E + 05 1.53E + 05 1.80E + 05 1.85E + 04 3.70E + 03 7.00E + O2

2. AIRBORNE CONCENTRATIONS AND CONTAMINATION LEVELS ,

TIME GAS IODINE PARTIC. CONTAMINATION GENERAL

HRS uCucc uCi/cc OCi/cc LEVELS IN CPM NOTES

315 AS Read As Read ' As Read As Read

515 2.2 E.2 2.8 E.6 2.8 E.5 - 12700

615 3.3 E.2 4.1 E.6 4.1 E.5 18600

700- 1.0 E.1 4.7 E 2 4.7 E.3 Offscale

800 3.1 E.1 6.8 E.2 6.8 E.3 Offscale

900 1.1 E.1 2.3 E.2 2.3 E 3 0ifscale

1000 1.2 E.2 2.4 E.3 2.4 E 4 Offscale

3555 8.4 6 REV.10126/ 90

- . _ -.

AUXILIARY BUILDINGELEVATION 25'

.

rur sua N Y Ah _CDT M Mp

|ME I-* ' '

gE. o . ,

__ 'la ,,

5:::-

mes mu r' C-

~m ) '

- I a

aI % pict cmnet

. -

A 8 | ,

~ | .

.

;- .

] k CCP'B' |"

, cc, y

O- -or 00 i ip o...

_wat

fat w .

- ~ A ,r

cm L L, UP9T R L t yt L-

_

==D

C-

E,,,,, _ Je,cMra warTI h- a T== suwI a

| 1 DOSE RATE INFORMATION~

l TIME mR/hr UNLESS NOTED GENERAL

HRS A B C D E F NOTESt

I 315 AS Read AS Read AS Read AS Read

515 278 310 380 350

615 520 598 715 718;

| 700 1.04E + 05 1.16E + 05 1.39E + 05 1.37E + 05| 800 2.75E + 05 3.08E + 05 3.70E + 05 3.60E + 05

900 2.75E + 05 3.08E + 05 3.70E + 05 3.60E + 05| 1000 2.74E + 05 3.062*05 3.70E + 05 3.70E + 05

2. AIRBORNE CONCENTRATIONS AND CONTAMINATION LEVELSTIME GAS IODINE PARTIC. CONTAMINATION GENERAL

HRS UC6/cc UCi/cc uCi/cc LEVELS IN CPM NOTES

315 AS Read AS Read AS Read AS Read

515 '.2.8 E 03 3.5 E 06 3.5 E 05 15750

615 2.8 E 03 3.5 E 06 3.5 E 05 15750

700 1.3 E 01 5.9202 5.9 E 03 Offscale

800 3.9 E 01 8.5 E 02 8.5 E 03 Offscale

900 1.4 E 01 2.8 E 02 2.8 E 03 Offscale

1000 1.5 E 02 3.0 E 03 3.0 E 04 Offscale

3555 8.4 7 REV.10:26 90

- _____ _-. - _ ._ _ _ __ _

|

AUXILIARY BUILDING |ELEVATION 5' !

h. ~. O,.,|4 "r =6 n u.ars a

M |

m, q, - O-_" -

Os . a-

i !

k _. ._ II|E |" " = g

- O= -.

5 h _ _ . I E.

,

.- . 1

g I l#

l

8 |AlIt m - 1 i

g'

g'p

- _

!! 1ro. ,

3 R50

"5"i i@ g 9g q.....

=...,_

----

E ~"~

=

m

.

Au nT - - c u _- _ __.2, ,

1. DOSE R ATE INFORM AYlONGENERAL.TIME mRlbr UNLE SS NOTED

, E F NOTESMRS .i B C D~

316 As Read As Read As Read As Read As Read

$15 760 H50 950 1000 100

61b 1120 1250 1400 1500 160

I ~700 2 98E * 05 3 33E + 06 3.73E + 06 3 64E + 06 1.04E + 04

800 1.01E + 06 1.13E + 06 1.2 7E + 06 1.32E + 06 2. 7EE + 03

900 9.80E + 05 1.02E + 06 1.14E + 06 1.15E + 06 1.80E + 03

[ 1000 9.40E + 06 1.02E + 06 1.14E + 06 1.15E + 06 1.80E + 03

3. AIRBORNE CONCENTR ATIONS AND COf.'* AMINATION LEVELSTIME GAS IODINE P A RTIC. CONT AMIN ATION GENERAL'

H Ft S uCuce uCecc uCece LEVELS IN CPM tJOTES,'

3$6 As Read As Read As Read Not Attainable

$1b 5 EE 03 7.0E 06 7.0E 06 Not Attainable

616 5 SE 03 7.0E 06 7 OE 06 Not Attainab!e

700 7.8E 01 1.2E 01 1.2E 02 Not Attainabic

800 7PE 01 1.7E 01 1 7 E +02 Not Attainable! 900 2.7E 01 5.6E 02 5 6E 03 Not Attainable _

j 1000 2 DE 02 6.3E 02 6 3E 03 Not Attainable

3556 8.4 8 PCv.10.26 90

|. -

ALL OYHER AREAS OF FUEL. AUXILLARY BUILDING

.-,

l

.

|

|

1

!

,

k

p

b

i-

i

I

- 1. DOSE R ATE INFORM ATION

TIME mRIhr UNLE 6S NOTED I GENERAL

HRS A B C D E F NOTE S

316 As Read-'

616 96616 110

~

700 2.60E + 04-)

800 2.60E + 04900' 2.60E + 04

-1000 2.60E + 04'

2. AIRSORNE CONCENTRATIONS AND CONTAMINATION LEVELST!ME GAS - IODINE PARTIC. CONTAMINATION GENERAL

HRS uCurc UCilec uCdec LEVELS IN CPM NOTES j

316 As Read As Read As Read As Read h

bl6 1.4E 03 1.BE 06 1.BE 05 7900

616 2.1E 03 2.6E 06 2.6E 06 11600--700 2.1 E.01 4*~.02- 4.4E 03 Offscale.

- 800 2.1 E .01 1.tm .J2 1.6E.03 '- Offscale"

-900 7.6E 02 1.6E 02 1.6E 03 - Ottscale

|- 1000- 7.40E 03 1.6E 03 1.6EG4 Offscale,

;- 3$$$ ,0.49 REV.10126/90 -

-t

--,..i*-._.._.-.._--_..._,m.......-.-._,~.m.. M <~ 4.._,,-.._..----,,.--.~,m..,.--.,,-------, . ~ , , --

---- , - - - - - - - - - - - - - ,

8.5 OndittRadielegicalRata

,

3555 4/NUCL 1429 8.5 1

_ _ _ _ . _ _ _ - - _ _

ON. SITE MON [IORING htAP INFORhtATION.

1. Dose Rates indicated in mR/hr.

2. lodine cartridge count rate assumes a sample volume of 2 cubic feet and a dettetor efficiency of0.022 cpm /dpm ,

3 Abbreviations:

a. DKO = Ilackgroundb. CPM = Counts per hiinutec. LOC = Locationd, IC = lodine Cartridgec. C/L = Centerlinef. EOP = 2dge of Plume i

g. LhiD = Less than Minimum Detectable

4. Edge of plume values are 10 percent of centerline values.

25. Smcar measurements with a RM 14/E140N 100 CM

NOTE:RADIOLOGICAL MEASUREMENTS NOT INCORPORATED

IN THIS SECTION SilOULD DE GIVEN AS READ

3555 0 S.52

(-- - . - _ . - _ . .

. . _ _ . ._ _ _ _ _ _ . _ . . _ _ _ . - _ _ _ _ _ . _ _ _ _ _ . _ _ _ . _. _ . _ _

i

| ON. SITE INSTRUMENT READINGS I! l

!

J,[ME: 3:15 5:15"

..- (|- ..

...#' ,/* '' '=.. \

. . . , . . ~ (x~ .' ._ ra r a ai N.

strucrVesc,.m ,m 7\j t ... . g ..

~ , . ,.-. m

|' | t lIIl M L_ $1 ['~""

'

), _ _ _

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< ,, ..<,; - /.'

$N09 e ntp MIENCAE ..

4 e a x.,

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Location (mRlhr) (mR/ht) (mR/hr) (mR/ht) Cartndge Paper (uCi/cc) (com)

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Location (mR/hr) ImR/ht) (mR/ht) (mR!hr) Cartridge Paper (uCi/cc) (com)

A 9.6 0.5 1.0 1.0 2250 AR 9.0 E.07 AR

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! Dose Rate 00se Rate Counts per Minute Calc. Smears


Location (mR/ht) (mR!hr) (mR/hrt (mR/ht) Cartridge Paper tuCucci (comi

A 893 892 89 89 400000 AR 1.6 E 04 AR

! B 396 178 40 18 77500 AR 3.1 E 05 AR:~

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Plume W 0. W.C , W.O. W.C. Charcoal Nter

Location (mR/hr) (mR thr) (mR/hti tmR 'hr) Cartndge Paper tuCucci (com)_

A 884 883 88 88 375000 AR 1.5 E.04 AR

B 392 177 39 18 75000 AR 3.0 F.05 AR

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Plume W.O . W .C , W.O. W.C. Charcoal Filter

Location tmR/hr) ImR!hr) (mR!ht) (mR/hr) Cartridge Paper tuCircci (com6

A 902 901 90 90 375000 AR 1.5 E 04 AR

B 400 180 40 18 75000 AR 3 0 E.05 AR

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Piume W.O . W.C. W.O . W.C. Charcoat Nter

Location (mRlhr) imR!hr) ImR!hr) (mR!hr) Cartndge Paper (uCi!cc) Icom)

A 902 901 90 90 375000 AR 1.5 E 04 AR

B 400 180 40 18 76000 AR 3 0 E.05 AR

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Plume W.O . W.C. W.O. W.C. Charcoal Filter

Location (mR!hr) tmRlbr) (mR/ht) (mR/ht) Cartridge Paper luCUcci (Com)

A 882 881 88 88 375000 AR 1.5 E.04 AR

B 391 176 39 18 72500 AR 2.9 E.05 AR

3555 0 8.5 16 REV,10/26 90

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Location imR/hr) (mR/hr) (mR/hrt (mR/ht) Cartridge Paper (vCi/cc) (com)

A 907 906 91 91 375000 AR 1.5 E C4 AR

8 402 101 40 18 75000 AR 3.0 E 05 AR

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Plume W.O . W.C. W.O . W.C. Charcoat Fdter

Location tmR/hr) (mR/hr) (mk/hr) (mR!hr) Cartndge Paper fuCi/cc) (com)

A 294 294 29 29.4 122500 AR 4.9 E 05 AR

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Oose Rate Oose Rate Counts per Minute Calc. Smears


Location imR/hr) tmR!hr) (mR/hr) (mR/hr) Cartndge Paper fuCucc) (com)

A 90 96 9.6 9.6 40000 AR 1.6 E 06 AR

8 43 19 4.3 1.9 8000 AR 3.2 E.06 AR

3555 0 8.5 19 REV.10/26t90

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Plume W.O. W .C . W.O . W.C. Charcoal Filter

Location (mR/ht) ImRlhr) (mR/hr) (mR/hr) Cartndge Paper (uCi/CC) (com)

A 31 31 3.1 3.1 12500 AR 5.0 E.06 AR

B 14 6.1 1.4 0.6 2500 AR 1.0 E.06 AR

3555 0 8.620 REV.10/26c90

_ _ . .. .. _ - _ _ _. _ _ _ .

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Plume W.0. W.C. W.O. W.C. Charcoal Filter

location imR/hr) trna /hr) (mR/hrt (mR!hr) Cartridge Paper (uCucci (com)

A 10.0 10.0 1.0 1.0 4000 AR 1.6 E.06 AR

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Centerline Edge of Ptume Air Samples lodine

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Plume W.O. W.C. W.O . W.C. Charcoal FilterjLocation (mR/hr) (mRlhr) ImRlhr) (mR/hr) Cortr49e Paper tvCucc) (comi'

A AR AR AR AR 9044 AR 3.6 E 06 AR

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3555 0 8.5 22 REV.10/26/901

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$

9.0 METEOROLOGICAL DATA

3555 4/NUCL-1429

_ _ _ _ _ _ _ - - _ _ _ _ _ _ - - - _ _ - _ _ _ _ _ _ _ _ - _ _ _ _ _-_.

-- _ _ _ - _ _ - _ _ _ _ . _ _ _

WEAT11EILEORECASI

.

LAM

12_IlcutEctenst . Today will be clear and dry with high teperatures near 50'F.

Winds will be light to moderate and from the north ranging from 2 5 mph.

12AlleuLEntenst Continued clear this evening with low temperatures nearf :

40*F. Windt will be variable and from the north-north east.

.

L

3555 4/NUCL 1429 9-1

. _ _ _ - - _ _ _ _ _ - _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

e

@

9.1 MttterelegisaltattSummary

3555 4/NUCL-1429 9.1-1

.. _

METE 0A0 LOGIC AL DAT A SUMMARY

3:15 3:30 3 45 4'00 4:15 4:30 4'45 5.00

PAR 4 METER? 0 00 0:15 0 30 0 45 1:00 1:15 1:30 1 45

Wind Speed impm ".

30 ft A 26 2.6 2.6 2.5 2.5 26 2.7 28

30 f t B 26 26 26 2.5 2.4 2.6 2.7 28

2 00 f t A 29 2.9 29 2.7 2.8 2.9 3.1 3,1

200 ft B 2.9 2.9 2.9 28 28 30 32 3.1

SOO tt A 3.1 3.1 3.1 30 30 32 34 33

500 ft B 32 3.2 32 3.1 31 J *s 34 34

Wind Direct.on (Sectori

From/TO)

30 ft A '.W /SE NWISE NWSE WNW 'E SE WNW/ESE WNW 'E SE N W /SE NW/SE

30 f t B NW/SE NW/SE NW!SE WNW/ESE WNW ESE WNW ESE NW!SE NW!SE

200 ft A f 4 WISE NW/SE NWISE WNW/ESE WNW/E SE WNW 'E S E NW!SE NW!SE

200 f t B NW/SE NWISE NW/SE WNW /E SE WNW ESE ' vNW /E SE NW/SE NWISE,

SD0 f t A NWISE NWISE N W 'S E WNW/ESE WNW/E SE .VNWiE S E NW!SE NWISE ,

500ftB N W /SE NW/SE NWISE WNW 'E SE WNW 'E SE VNW/E SE NW 's$ NW/SE

$tabihtya

Delta T (200 33 ft) A 0.30 0.30 0 30 0 30 -0.30 0 30 0.30 0.30

Delta T (200 33 til B 0.31 0.31 0.31 0.31 0.31 0.31 0.31 0.31

Sigma A/ Sigma B 6 6 6 6 6 6 6 '6

P ecetation (Yes/Not N i N N N N N N N

_ _ _ _ _ . ._.

METEOROLOGIC AL DAT A SUMM ARY

$ 15 5 30 5:45 6 00 6.15 6 30 6 45 7.00

P AR AMETE R: 2:00 2:15 2:30 2 45 3 00 3:15 3 30 3 45

Wind Speed (mph) .

30 ft A 2.9 30 30 2.9 29 2.0 30 33

30 f t B 2R 30 3.1 29 2.9 28 2.9 3.2

200 f t A 3.3 35 3.6 3.2 3.3 3.3 32 3.7

200 f t B 3.2 3.6 36 3.3 3.2 3.2 37 36

500 f t A 34 38 3.7 36 3.7 38 36 4.1

500 ft B 35 3.9 38 37 36 37 36 4.1

'

Wind Direction (Sector)(From/TO)

30 f t A NWISE NWISE NW/SE NNW/SSE NNW/SSE NNW/SSE N!S N 'S

30 f t B NW 'SE NW/SE NW/SE NNW/SSE NNW/SSE NNW.'SSE N/S N 'S

200 f t A NW!SE NW/SE NW/SE NNW/SSE NNW/SSE NNWISSE N!% N 'S

200 f t B NW/SE NW!SE NWISE NNW/SSE NNW/SSE NNW/SSE N /S N 'S

500 f t A NW/SE f4W!SE NW/SE NNW SSE NNW/SSE NNW/S$t N !S N!S

500 ft B NW!SE NW/SE NW/SE NN.' /SSE f4NW/SSE NNW/SSE N!S tJ /S

Stataty.

Deitn T (200-33 ft) A 0.32 0.32 0.32 0.32 4 32 0.32 0 35 0 35

Deita T (200 33 fti B 0.34 0.34 0.34 0.34 0.34 0.34 0.36 0.36

Sigmn A' Sigma e B 8 8 8 8 8 9 9

Precetation (Yes ttJoi N N N N N N N N

3556 9.1 3 REV. 8/2 2 /90

- - - - . _ __

_ . _ _ _ _ _ _ _

METEOROLOGICAL DATA SUMMARY

7:15 7:30 7:45 H 00 9 15 , 8;30 8 45 9 00

P A R AM[t[R: 4 00 4:15 4:30 4:45 5 00 5 15 6 30 5 45

Wind $0eed Imph) '.

30 f t A 32 32 3.3 35 35 35 36 35

30 tt B 31 3.1 ,32 3.4 35 34 35 3.3

200 f t A 36 35 3.7 4.1 4.2 4.0 4.1 4.0

200 ft B 36 36 36 4.1 4.1 4.1 4.1 39

500 ft A 40 4.1 4.2 45 46 4.6 47 4.7

500 f t B 4.1 4.2 42 44 4.5 45 45 4 . *i

Wind Direction ($ttfoN(FrorWTol

,

30 f t A N 'S N!S N !S N!S N 'S N!S NIS N 'S

30 f t B NIS N/S N!S N 'S N!S N!S NS N!S

200 f t A N<S N /S N /S N 'S NS N!S NfS N.S

203ftB NIS N!S N!S f4!S N!S N/S N!S N 'S

500 f t A N!S NIS NIS N tS N 'S NIS t4!$ N:S

500 f t B N!S NIS N/S N /S N!$ NIS N!S N$

Stability.

Delta T (200 33 90 A 0.35 0.35 0.35 0.35 0 35 0 35 0.35 0.35

Delta T (200 33 til B 0.36 0.36 0.36 0.36 0.36 0.36 0 36 0.36

Sigma A/ Sigma B 9 9 9 9 9 9 9 9

Prec#pitation (Y et|Noi N N N N N N N N

3555 9,1 4 REY. 8/22 /90

_- _ -- -__ -. - _

- - - - - - - _ - _ _ _ _ - _ _ _ _

l

METEOROLOGICAL DATA $UMMARY~

9:15 9 30 9 45 10:00 10 15 10:30 to45 $ 1:00

P AR AVETER: 6 00 6:15 6 30 6:45 7:00 7:15 7:30 _ 7:45

Wind Speed Imphi ~.

30 f t A 35 3.5 3.6 3.7 3.7 3.7 39 3.9

30 f t B 34 3.5 3.5 3.5 35 35 38 38

200 f t A 4.0 42 4.1 4.1 4.1 4.1 4.2 4.2

200 f t L 4.1 4.1 4.1 4.2 4.2 4.2 4.1 4.1

500 f t A 4.6 46 4.7 4.9 4.9 49 4.7 4.7

500 f t B 4.6 4.5 4.5 48 48 48 46 4.6

Wind Duection (Sector)(Fromffo)

30 ft A N/S N/$ N!S N 'S N 'S N 'S N !S N .'S

30 ft B NiS N t$ N 'S N /S N/S N 'S N 'S N!S

200 f t A N/S N!S N 'S N 'S N 'S N/$ N 'S N !S

200 ft B N!S N!S N!S N 'S N IS N!$ N!S NS

$00 f t A N/S N!S N!S N 'S N/S N >S N!S N 'S

IO0 f t B NrS N 'S N 'S N !S NIS N!S N /S N15

Statahty.

Delta l t200 23 f ti A 0.61 0.61 0 61 0.61 0.78 0.78 0.78 0.79

Detta T 1200 33 ft) B 0.63 0 63 0.63 0.63 0.79 0.79 0.79 0.79

S gma A/ Sigma D 11 11 11 11 15 15 15 15

Precctation lYet/Noi N N N N N N' N N

3555 9.1 5 REV. 8/22/90

-_ __ _ _ _ _ -

_

MET [0ROLOGIC AL D AT A SUMM ARY

11:15

PARAMETER: H 00

*

Wind Speed Imph) *

30 f t A 3.9

30 f t B 38

200 f t A 4.2

200 f t B 41

500 f t A 4,7

000 f t B 4.6

Wind Detection (Sector)(From/Tol

30 f t A N!S

30ftB N!S

200 ft A N!S

200 f t B N!3

$00 f t A N /S

t.00 f t 8 N/S

Stab 6hty,

Delta T (200 33 f t) A .O.78

Delta T (200 33 ft) B 0.79Sigma A/ Sigma D 15

Precipita tion (Yes /No! N

<

k

l 3555 9.16 REV. B/2 2/90

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9.2 MuertelegicaLD.ataJhtets

13555-4/NUCL-1429 9.2 1

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- - _ _ _ . _.


EMERGENCY PREPAREDNESS DRILL

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.

METEOROLOGICAL DATA

i REAL TIME 3:15

ELAPSED TIME 0:00s

Wind Speed (mph)

30 ft A 2.60

30 ft B 2.60 _200ftA 2.90

200 f t B 2.90

500 f t A 3.10

500 f t B 3.20

.

Wind Direction (Sector)

(From/To)

l 30 f t A NW/SE' 30 ft B NW/SE

! 200 ft A NW/SE,

200 f t B NW/SE

500 ft A NW/SE,

500 f t B NW/SE

Stabilityi

Delta T (200 33 ft) A 0.30

Delta T (200 33 ft) B 0.31 _Sigma A/ Sigma B 6.00Precipitation (Yes/No) N'

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3555 9.2 2 REV. 8/22/90

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