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Text

Annual Emergency Exercise Scenerio for 1988
	ML20195D056
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	07/14/1988
From:	; CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	;
Shared Package
ML20195D052	List: ML20195D047; ML20195D056;
References
	NUDOCS 8811040173
	Download: ML20195D056 (133)
	v • d • e

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BREX 88

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( SS11040173 80080"2 PDR F ADOCK 05000155 PDC itIl086-00065-TP11-TP02

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k TABLE OF CONTENTS PagS 1.0 SCOPE AND OBJECTIVES 1.1 1.1 SCOPE 1.1 1.2 OBJECTIVES 1.1 2.0 EXERCISE CONDUCT 2.1 2.1 EXERCISE ORGANIZATION 2.1 2.2 CONTROLLER ORGANIZATION 2.1 2.3 EXERCISE DATA AND MISSAGES 2.2 2.4 EXERCISE GROUND RULES 2.2 2.5 CRITIQUE 2.3 2.6 EVALUATOR CHECKLISTS 2.3 3.0 APPENDICES - EXERCISE DATA APPENDIX A - SEQLINCE OF EVENTS / NARRATIVE SLTiARY APPENDIX B - MESSAGE SHEETS APPENDIX C - METEOROLOGICAL DATA APPENDIa* D - RAD MONITOR DATA APPENDIX E - ONSITE RAD DATA APPENDIX T - CTTSITE RAD DATA APPENDIX G - POST-ACCIDENT SAMPLE DATA

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1.0 SCOPE AND OBJECTIVES 1.1 SCOPE BREX 88 is designed to meet exercise requirements specified in 10 CFR 50 Appendix E.Section IV.F. It will postulate events which would require activation of major portions of the site energency plan and response by local and state government. The exercise vill be utility only. The Charlevoix County Sheriff Departeent will also participate in security aspects. The Joint Public Information Center will not be activated.

1.2 OBJECTIVES The exercise will demonstrate:

1. Assessrent and Clcssification

a. Recognition of eoergency conditiens

b. Timely classification of emergency conditions in accordance with emergency action levels

2. Cot =unication

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a. Initial notification within specified time constraints (state and local - 15 minutes NRC - I hour)

b. Subsequent notification in accordance with procedure

c. Notification and coordination with other organizations, as required (other utilities, contractors, fire or medical services)

d. Provision of accurate and timely information to support news release activity

3. Radiolorical Assessment and Control

a. Calculation of dose projection based on sample results or monitor readings

b. Performance of in-plant and offrite field surveys

c. Collection and analysis of a post-accident primary coolant saeple

d. Trending of radiological data

e. Formulation of appropriate protective action reco==endations

f. Contamination and exposure control l'

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4 Er.ercency Response Facilities

a. Activation, staffing and operation at appropriate classifications and within specified time constraints

b. Adequacy of emergency equipment and supplies

c. Adequacy of emergency com=unication systems

d. Access control

5. Emergency Management

a. Com=and and centrol with transfer of responsibilities from Control Room to Technical Support Center to Emergency Operations Facility

b. Asse=bly and accountability within approximately 20 minutes

c. Coordinatien with State of Michigan emergency organization

d. Mitigation of operational and radiological conditions

e. Mobilization of emergency teams c

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6. Reentry and Recoverv

a. Assessment ef damage and outline of reantry/ recovery plans

b. Identification of constraints, requirements and organizatien to implement the plan 7 Exercise Control

a. Provision for maximum free play

b. Accurate assessment of player performance f

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6' 2.0 EXEncISE CONDUCT 2.1 EXERCISE ORGANIZATION The exercise organization is comprised of Controllers. Evaluators.

Players and Observers. All are issued identification.

Controllers are responsible for providing eessages and data to Players.

They airo ensure that exercise activity progresses as planned. Con-trollers are authorized to codify scenario data and provide clarification to Players as judged appropriate. They must not, however, prompt Players unless the exercise or plant operation is jeopardized by inappropriate Player response. If a Player must be prompted, it must be brought to the attentien of the Lead Facility Controller er Exercise Coordinator and prior to doing so if possible.

most cases.

Controllers also serve ac Evaluators in Evaluators observe Player activity and judge effectiveness of response.

Consumers Power Company Evaluators are required to sub=it signed Evaluator Checklists to their Lead Facility Controller. NRC evaluators will be present for the exercise.

Observers may be present at any location where exercise activity occurs.

Observers are not allowed to opeak to players during the course of the g" exercise.

N Players include all personnel responding to simulated exercise conditions.

2.2 CONTROLLER ORGANIZATIOS*

The Exercise Coordinator is in charge of overall exercise conduct.

Responsibilities include conducting preexercise Controller meetings. NRC entrance meeting, joint critiques, and NRC exit critiquet approving major scenario deviations resolving exercise questions; and terminating the exercise.

A lead Facility Controller is assigned to each Emergency Re.sponse Tacility and is responsible for addressing Pltyer inquiries, conducting a post-exercise facility critique, collectint and submitting completed Evaluator Checkliste to the Exercise Coordinator.

Controllers and Evaluators vill refer all Player inquiries to the Lead racility Controller. If unable to resolve a question, the Lead Facility Controller vill refer the query to the Exercise Coordinator.

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A diagrac of the Controller organization is provided in Figure 2.1.

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EXEROSE . '

BREX 88 CONTROLLER ORGANIZATNMi COORDWATOR TOtJY KATAR5KY I I I l T5C LEAD EOF LEAD 05C LEAD D

GEORGE PETITJEAN JOE BEER JIM SRUNET DON KELLY I I I I OPERAT10ess HEALTH PHYSICS ONSITE RMT TOM ELWARD AD CLARK M EY TOM PENCE GARY STURM

- MIKE DAWSON AUXiUARY HEALTH PHYSICS EMENI OPERATOR COMMUNICATlONS OFF5 ATE RMT DAVE MdesTOSH THERESA HANCOCK LARRY KENAGA esORM mROTT CHARUE AXTELL TECHORCAL ADeNNISTRATIVE HP SUPERvtSORI PAS CONTROL ROOM 144 i DOS GAlutETT I 15C 261 1

! LEAD SECURITY

} OSC 154 MA80ffENAgeCE TEAM i

EOF 233 SKIP COOPER 1

DAVE DEfftSE l 637-7240 t COneMus#CATIOtes

STATE 532 - 6311 (EOF) i slG ROCK Pott: T 547-6537 TOM 58KAVIT5A5 ggg

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k 2.3 EXERCISE DATA AND MESSAGES Messages and data to drive Player response are contained in the following }

appendices:

Appendix A - Sequence of Events / Narrative Summary i Appendix B - Message Sheets Appendix 0 - Meteorological Data ;

Aenendix D - Rad Monitor Data j Ah andix E - Ov.ute Rad Data i Appendix F - Offsite Rad Data P

Appendix C - Powt-Accident Sample Data !

l Information not to be distributed to players is marked "Controller Use :

Only." It is ultimately each Controller's responsibility to ensure that l only appropriate information is distributed to Players.

2.4 EXERCISE GROUND RULES l'

b 1. Perform all actions to the extent possible in accordance with the emergency plan and procedures as if it were a real emergency.

Unless authorized by the Controller, you should not simulate your actions. Verbal approval from a Controller / Evaluator is required prior to simulating any action. If authorized to simulate an action, tell the Controller / Evaluator how it would be performed.

1- 2. Periodically speak out leud identifying your key actions and decisions to the Controller / Evaluators. This may seen artificial.

but it will assist in the evaluation process. If you are in doubt.

ask for clarification. The Controller / Evaluator will not prompt or coach you.

3. Know the overall Controller organization. Identify your Controller and NRC evaluators. Centro 11ers also serve as Evaluators.

4 The Centro 11er periodi: ally will issue messages or instructions designed to initiate response actions. Nessages must be accepted l immediately. They are essential to successful performance.

5. If the Controller intetvenes, obey the Controller's directions.

This is essential to the overall success of the exercise. If you j

disagree with your Controller you can ask him to reconsider. You must, however, accept his/her word as final and proceed. Respond to Centro 11er's questions.

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6. Ycu must play as if radiation levels actually are present, i.n i ,

accordance with the information you have received. This may require that you wear dosimeters and anti-Cs observe good radiation pro-tection practices, and be aware of and minimize your radiation i exposure. Identify the individuals in your emergency response 4

" organization responsible for informing you of these items. Follov l their instructions.

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7. If you are entering normal nuclear station radiation areas, observe s.11 rules and procedures. No one is exempt from normal station radiological practices and procedures.

8. Demonstrate knowledge of emergency operations and procedures.

Utilize status boards, logbooks, and message forms, as much as ,

j possible, to document and record your actions. instructions and j reports to your coplayers. I i

l 9. Do not enter into conversations unrelated to the drill with other !

] Players. You may answer questions directed to you by Federal !

! Evaluators. If the question is misdirected to you or you do not l

! know the answer refer them to the team leader or the controller. ;

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10. Keep a list of items for improvement. Provide this to your team f i

f leader. Team leaders will ensure these are considered. If neces- l j( sary they will identify them to the Controller during the critique !

vhich follows the drill / exercise. Areas for improvement or lessons !

j learred. when identified will improve overall emergency preparedness.

2.5 CRITIQUE a

, Tollowing termination of the exercise, facility critiques will be con-I ducted by Lead Tacility Controllers. f i I

A joint critique vill be conducted following facility critiquec. Lead

] Tacility Controllers vill present overall observations made at f acility j critiques. Players may attend if they wish, i Tollowing the joint critique, the NRC exit will be conducted. The NRC will present preliminary findings verbally at this time. Comments from CP Co personnel vill be fielded by the NRC.

2.6 EVALUATOR CHECKLISTS {

The checklists prov Jed in Section 2.6.1 through 2.6.9 are to be used in

, judging Player and Controller ability te meet stated exercise objectives.

1 These facility specific checklists cross-reference all applicable exer-

] cise objectives. In sun, they serve as the basis of exercise evaluation !

and documentation.

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f Each Evaluator shall submit to the Exercise Coordinator a completed, j

\. signed. and dated checklist at the conclusion of the exercise. Items j 4 t i

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marked "inadequate" shall be fully explained in the "co==ents" section.

Comments continuation sheets are provided in Section 2.6.9.

Lead Facility Controllers will cenduct critiques using these checklists l

as guides.

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2.6.1 Control Room Evaluator Checklist t'

Name: Datet Met, Not Met, Not Met.

Fully Problem Lov High Objective Met Noted* Impact

Impact

1A Recognition of emergency conditions IB Timely classification of emergency conditions , , _ _

2A Notification of state ars local governments within 15 minutes and NRC within one hour 2B Subsequent notification in accordance with procedure (state, local. NRC) 2C Notification and coordination for offsite assistance (fire, medical) 3T Contamination and exposure control 4A Notification of OSC and TSC staff to g' activate at alert classification

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4B Adequacy of equipment and supplies _____

4C Adequacy of co==unications equipment . _ _

4D Access control 5A Command and control with clear trans-fer of responsibility from Control ~~~

Room to TSC 5D Mitigation of hypothetical eperatienal problems SE Mobilitation of emergency teams _ _

6A Assessment of damage 6B Identification of reentry / recovery ,

restraints Ccnnents:

Signature

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Explain items checked in detail under comments. If not observed, mark NA (not appli. cable).

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2.6.2 Operational Support Center Evaluator Checklist 1 .

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( Name:

Date:

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' Met, Not Met, Not Met, Fully Problem Low High Objective Met Noted* Impact

Impact

3T Contamination and exposure control I

4A Activated at alert classification and staffed in accordance with SEP 4B Adequacy of equipment and supplies l 4C Adequacy of communications '

4D Access control 5A Transfer of offsite RMT control to EOF 5D Mitigation of hypothetical operational conditions 5E Mobilization of teams at appropriate '

times __

f" Comments

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Signature:

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Explain items checked in detail under comments. If not observed, mark NA I (not applicable). t 1

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2.6.3 Onsite RMT Evaluator Checklist

( Name: Date:

Met, Not Met, Not Met, Fully Problem Low .High Objective Met Noted* Impact

Impact

3B Performance of in-plant field surveys 3F Contamination and exposure control _.

4A Activation at alert classification _

4B Adequacy of equipment and supplies 4C Adequacy of communications SE Mobilized at appropriate time Comments:

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Signature:

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Explain itees checked in detail under comments. If not observed, mark NA (not applicable).

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O s 2.6.4 Offsite RMT Evaluator Checklist

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) Name: Date:

Met, Not Met. Not Met, Fully Problem Low i High Objective _ Met Noted* Impact * &__ pact

3B Performance of of fsite field surveys ,

J 3F Contamination and exposure control '

6A Activation at site area emergency classification 4B Adequacy of equipment and supplies 4C Adequacy of communications 5A Transfer of control from OSC to EOF SE Mobilized at appropriate time Comments:

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Signature:

Explain itema checked in detail under ceaments. If not observed, mark NA (not applicable).

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, 2.6.5 Security Evaluator Checklist Name: Date:

Met. Not Mut. Not Met.

Fully Preblem Lov High Objective Met Noted* Iepact* Impact * ;

3r Contamination and exposure centrsl 4B Adequacy of emergency squipment and supplies 4C Adequacy of communications ,,

4D Access centrol of site, Control Room. ~

TSC. OSC, E0T and JPIC 55 Assembly and accountability within ,,

approximately 30 minutes SE Mobilization at appropriate time _,

Comments:

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Signature:

txplain itens checked in dettil under cem=ents. If not observed. cark NA ;

(not applicable).

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e a 2.6.6 Technical Support Cente- Evaluator Checklist t Name:

Date: __

Met. Not Met. Not Met, Fully Problem Low High Objective Met Noted* Impact

Impact *_

IA Recognition of emergency co'ditions 1B Timely classification of emergency conditions _

28 Notificatien of State and NRC (sad possibly locals) at 15 minute intervals or as mutually agreed 20 Notification and coordination with other organizations as required -

(fire, medical) 2D Provision of accurate and timely information to support press release activity 3A Calculation of dose protections based on sample result. or monitor readings s 3D Trending of radiogical data 3E Formulation of appropriate protective action recommendations 3F Contamination and exposure control 4A Activation, staffing and operational within one half hour of alert declaration ,.

4B Adequacy of emergency equipment and supplies 4C Adequacy of communications AD Access control 5A Command and control with clear ~~ ~

transfer of responsibilities from fontrol Room and to ECF 5B Assembly and accountability within approximately 30 minutes l'

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Explain items checked in detail under << cents. If not observed, mark NA (not applicable).

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2.6.6 Technical Support Center Evt.luator Checklist _(Page 2)

' Met, Not Met, No t Me t ,

Fully Problem Low High Objective Met Noted* Impact

Impact *

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g s dination with State .f Michigan ancy otganization

$D' .igation of operational and radiological conditions SE Mobilization of emergency teams

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6A Accessment of damage and formulation "

of recovery plan i 6B Identification of contraints, require- ;

ments and organization to implement the recovery plan Comments:

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Signature t

Explain items checked in detail under comments. If not observed, mark NA (not appli. cable).

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i Name:

Date:

Met, Not Met, Not Met, Fully Problem Low High Objective Met Noted* Impact

Impact

1A Recognition of emergency conditions 1B Timely classification of emergency conditions 2B Notification of State and NRC at 15-minute intervals or as mutually agreed 2C Notification end coordination with other organizations as required (other utilities, contractors, fire, medical sources) 2D Provision of accurate and timely information tion to support news _

release activity 3A Calcu.3ation of dose projections based

'. on sample results or monitor readings 4

3D Trending of radiological data 3E Formulation of app;opriate protective action recommendations 3F Contamination and exposure control 4A Activated and staffed at site area emergency and operational within about ,

an hour of declaration J. 4B Adequacy of emergency equipment and supplies _ . .

4C Adequ'acy of communications systems '

4D Access control SA Command and cont *k clear trans-fer of responsibf '

= TSC and OSC

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Explain items checked in detail under comments. If not observed, mark NA (not applicable).

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I.. > 2.6.7 Emergency Operations Facility Evaluator Checklist (Contd)

Met. Not Met, Not Met, Fully Problem Low High Objective Met Noted* Impact

Impact

SC Coordination with State of Michigan _

emergency organization SD Mitigation lof operational and radiological conditions 6A Assessment of damage anj formulation of recovery plan 6B Identification of constraints, requirements ~snd organization to implement the recovery plan '

Comments:

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Explain itens checked in detail under comments. If not observed, mark NA (not applicable).

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2.6.8 Controller / Evaluator Performance Checklist

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Name: Date:

Met, Not Met , Not Met, Fully Problem Low Hir.h Objective Met Noted* Impact

Impact

7A Provision for maximum free play 75 Accurate assessment of player ,

performance Comments:

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s I' Signature: -

Explain items checked in detail under comments. If not cbserved, mark NA (not applicable).

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( 2.6.9 Evaluator Checklist Coment Continuation Sheet Area: Date:

Name: ,

Coe.ents:

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( Signature:

CExplain itecs checked in detail ~

under coc=ents. If not observed, mark NA (not applicable).

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D l APPENDIX A SEQUENCE 'T EVENTS / NARRATIVE SLMfARY

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1 ei hs BREX 88 - NARRATIVE

SUMMARY

At 0915 the previous day, the electric fire pump failed to operate during its monthly surveillanca test. At 0915 today, a Technical Specifications LCO will be met requiring initiation of plant shutdown. ,

The plant has been at steady-state power, equilibrium xenon, for 90 days. The daily reactor coclant system inventory check for July 19, 1988 has been .l performed satisfactorily.

Today at 0805, a guard making outdoor rounds hears gunshots and bullats whizzing. He immediately contacts the security building. The control room and Sheriff Department are notified. The Sheriff Department dispatches assistance to the plant. The shift supervisor classifies the situation as an unusual event, then notifies the State and locals.

Sheriff deputies arrive onsite at approximately 0820. By 0915, the security event is terminated.

At 0915, Jose of condenser vacuum causes the reactor to trip. Thirty seconds later, the turbine rupture diagram bless. Steam is seen on the turbine deck.

The turbine stop valve is open; it did not close on reactor scram. Steam drum

. ., level is dropping rapidly. Condensate and feedwater tumps trip. If the operator attempts to close the turbine stop valve, it will close. However, the l (I --

diaphragm rupture will continue to spew steam. The operator should close the main steam isolation valve and initiata the emergency condenser. The emergency condenser, however, will fail to operate as MO 7053 and MO 7063 are stuck closed. Attempts to restart a condensate pump and a feedwater pump will succeed. They will run until water in the hot well is expanded, approximately two and ene-half minutes after start. Steam drum level will increase from

-25 inches to -5 inches before the feedwater pump trips again. An alert should be declared which will result in activation of the TSC and OSC and partial r

activation of the EOF.

Both Plant and General Of fice ESF staf f will be prestaged to eliminate 4xcessive exercise time. Plant personnel vill be granted access to the EOF at 1000 General Office personnel ac 1100.

At 0923 -the steam drum relief valve lif ts, stays open for 15 to 20 seconds, them closes. Primary coolant system pressure drops from 1520 psig to 1490 psig. The relief valve cycles open for 16 to 18 seconds, then closes approximately every 80 seconds. Containment pressure rises approximately every 80 seconds. Containment pressure rises approx?mately 0.7 psi with each cycle; containment temperature increases with each.

Shortly after 0927, the steam drum relief valve cycles for the fourth time and containment pressure reaches the set point for automatic containment spray actuation. Following actuation, containment pressure oscillates between 1.8 psig and 2.5 psig. Containment temperature fluctuates between 105'T and l' 100'F.

MIO488-0091A-TP20-TP12

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t At 0930, containment sprays are operating continuously. The steam drum relief valves are cycling every 100 seconds. Both control rod drive pumps are operating. Steam drum level continues to slowly increase with two control rod drive pumps running.

Dy 1030, reactor power has reached "0." Reactor vessel water level is off-scale high. -Steam drum level is approximately +8 inches.

At 1045, containment pressure is being maintained at approximately 2.5 psig.

The steam drum safety valves are cycling to relieve excess pressure. Contain-ment sprays are operating continuoud y.

At 1115, containment pressure is approximately 2.5 psig. Steam drum level is

, approximately 17 inches above center lint.

At 1125, a steam drum relief valve opens to Jelieve pressure and sticks in the open position. Primary coolant level and pressure drop rapidly. In 30 seconds, pri.;iary coolant is 2'9" above the core which triggers actuation of the reactor depressurizaaon system following a two-minute safety delay. A site area energency should be declared.

By 1130, both core spray systems are operating normally. Containment pressure is being reduced by containment sprays after peaking v. 20 psig.

/' At 1140, steam drum level comes on scale and is increasing 6 inches per minute.

\- By 1150, steam drum level is +30 inches.

At 1230, centainment level reaches 587'. The post-incident system (recircula-tion) is put in service.

At 1245, primary coolant is being recirculated from t.'.e encloser sump to core spray, out the reactor depressurization system valves and back ta the sump. A post-accident chemistry sample may new be taken.

By 1300, recovery planning should be underway. Notifications to ':he State will be closed out at this point.

At 1315, a four-hour time jump will occur to allow formal reentry / recovery planning to occur. Approximately an hour and a half will be allowed for development of reentry and recovery outlines.

The Site Emergency Director, EOF Director, Emergency Officer and applicable support personnel will meet to outline reentry and recovery planning.

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APPEhTIX B MESSAGE SHEETS k

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M10588-0062A-TPll

. e.a SCENARIO NO BREX-88 IIME = 0800 MISSAGE NO 1 T 0000 4,

BIG ROCK POINT NUCLF#' PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSAGE FOR: Shift Supervisor / Control Room Operator SIMULATED PLANT CONDITIONS: See Data Sheet.

PESSAGES: 1. The plant has been running at steady-state power for 90 days, equilibrium xenon.

2. At 0915 yesterday, the electric fire pump failed to' operate during its monthly surveillance test.

3. The daily reactor coolant system water inventory check has been performed satisfactorily.

4. Anncunce over the plant public address that the drill is about to begin.

CONTROLLER USE ONLY

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t l 1

I NUO488-0113A-TP11-TP07

BREX 88 TIME: 0800 MEiSAGE: 1 SCENARIO TIME: 0000 CORE SPRAY 0 PSIG RCP #1 FLOW 16.4 CPM x 103 DRitt RV STATUS INSTRU AIR 95 PSIG RCP #2 FLOW 17.0 GPM x 103 WP DISCHG OPEN SHUT /

1600 PSIG TURBINE INL 1320 PSIG _l CONTROL RODS l COCO DISCLG 233 PSIC RX PRESS I335 PSIG I25 V DC BUS ENERG FDWTR TEMP 358 *F ALL IN RX WATER 22.5 FEET Y ECS #1 IDOP 95 *F ECS #2 LOOP 100 *F NOTCHES OUT 680 CONDENSER VACUIR1 COND LEVEL 45 % W FLOW 880 lb/HR 103 29 inHg CST LEVEL 75 % STEAM FLOV 875 lb/HR 10 3 DWST LEVEL 80 % DRUM LEVEL l l )

+1 VENT VLV POS 0 INCHES ({}

CONTAINMENT PRESS .05 PSIG MSIV POS 0 CONT WATER LEVEL <574 FT OFF GAS 40 UNIT 3

)

1 l

ECS WATER LVL 200 % CRD PP DSCH 1750 PSIG 138 kV AVAIL Y -

B/U CORE SPRAY 0 GPM CRD COOLING 12 GPM 46 kV AVAIL Y - I PRI CORE SPRAY 0 GPit CRD HEADER 25 GPM EDG AVAIL Y -

l B/8I CONT SPRAY 0 GPM CRD COOLING 26 PSID 2B BUS ENERG Y -

PRI CONT SPRAY 0 GPM CP.D HEADER 250 PSID -

DCWRM 96 %

START-UP CHN - CPS COMMENTS / PLANT STATUS: Generator 67 MW RDS STATUS

. FIRED RESET OTHER RX WATER LVL G COLOR DRUM LEVEL +1 INCHES FOR DRILL USE ONLY NUO483-03 TPIl-TP07 -

. w 55 ./ %d

c e SCENARIO NO BREX-88 TIME = 0805 _

, MISSALE NO 2 ,

T= 0005

{4 BIG ROCK POINT FUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MISSAGE FOR: Guard Making Rounds SIMULATED PLANT CONDITIONS:

MISSAGE: You have just heard three gunshots and bullets whizzing.

FOR CONTROLLER USE ONLY

1. Guard should notify Security.

2. Security should notify Control Room and Sheriff Department.

3. An unusual event should be declared.

fm 4. Sheriff Deputies should arrive at approximately 0820. The security event

(, should be secured by 0915.

5. The Security Controller will provide information to players for clarifi-cation as requested.

k NUO488-0113A-TP11-TP12 ,

o e

'SCENAR80 NO BREX-88 _ TIME = 0915 MESSAGE NO 3 T= 0115 BIG ROCK POINT NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM

'XESSAGE POR: Shift Supervisor / Control Room Operator SIMULATED PLANT CONDITIONS: See Data Sheet.

i l MESSAGE

l l

CONTROLLER USE ONLY

1. Condenser vacuum dropping; reactor scrams on low condenser vacuum

2. No 1 circulation water pump amps = 0 l- 3. Turbine stop valve indicates open.

4. All else normal on scrats per ONP 2.31 S. .

(

NUO488 0113A-TP11-TF12

BREX 88 TIME: 0915 MESSAGE: 3 SCENARIO TIME: 0115 CORE SPRAY 0 PSIG RCP #1 FLOW 16.5 GPM x 103 DRUM RV STATUS INSTRU AIR 95 PSIG RCP #2 FLOW 17.0 GPM x 103 OPEN SHITT /

FWP DISCHG 1600 PSIG TURBINE INL 1320 PSIG _l CONTROL RODS {_

COND DISCHC 230 PSIG RX PRESS 12006 PSIC 125 V DC BUS ENERG FIMTR TEMP 120 *F ALL IN / RX WATER 22.5 FEET Y ECS #1 LOOP 95 *F ECS #2 LOOP 100 *F i40TCHES Olfr CONDENSER VACUUM COND LEVEL 306 % IV FIDW 400 lb/HR 10 2 O inHg CST LEVEL 75 % STEAM FLOW 350 lb/IIR 103 l l DWST LEVEL 80 % DRUM LEVEL FSH INCHES (p)

VENT VLV POS C CONTAINMENT PRESS .05 PSIG MSIV POS O CONT WATER LEVEL <574 FT OFF GAS 40 UNITS ECS WATER LVL 100 % CRD PP DSCH 1600 PSIG 138 kV AVAIL Y -

B/U CORE SPRAY 0 GPM CRD COOLING

GPM 46 kV AVAIL Y -

PRI CORE SPRAY 0 GPM CRD HEADER

GPM EDG AVAIL Y B/U CONT SPRAY 0 GPM CRD COOLING

PSID 2B BUS ENERG Y -

PRI CONT SPRAY 0 GPM CRD HEADER

PSID -

DCWRM 1 %

START-UP CHN - CPS COMMENTS /PIANT STATUS: *0scilIating Annunciators: Condenser Circulating Water Pump Trip Alarm Condenser Low Vacuum Alarm Area Monitor Alarm (Condenser Area)

Condenser Low Vacuum Scram

- K-3/K-5 Tripped Alarm

- Channel 1 and Channel 2 Scram Alarm

- SDT High Water Level Alarm RDS STATUS

- Low Accumulator Pressure Alarm , FIRED RESET OTHER RX WATER LVL G COLOR DRUM LEVEL +5 INCHES FOR DRILL USE ONLY NUO488-0113 'l1-TP07

~_- i.) %.)

e a SCENARIO NO BRIX-88 TIME = 0915:30 MESSAGE NO 4 T= 0115:30 BIG ROCK POINT NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSAGE FOR: Shif t Supervisor / Control Room Operator SIMULATED PLANT CONDITIONS: See Data Sheet.

MESSAGE:

r CONTROLLER USE ONLY

1. Turbine stop valve is open. It did not close on reactor scram.

2. Steam drum level is dropping rapidly.

3. Condensate and feedwater pumps have tripped.

f,.

g, 4 Expect phone message to Control Room. See Message 4.

5. Operator response

a. Should close MSIV and initiate emergency condenser. Emergency con-denser fails to operate as MO 7053 and MO 7063 are stuck closed.

b. Attempt to restart a condensate pump and a feedwater pump. They will start.

c. Attempt to close turbine stop valve from the Control Room. It will close and the 116 OCB will open and will be annunciated. Leak will continue as diaphragm is ruptured.

t NUO488-0113A-TP11-TP12

BREX 88 TIME: 0915:30 MESSAGE: 4 SCENARIO TIME: 0 15:30 CORE SPRAY 0 PSIG kCP #1 FLOW 16.5 CPH x 103 DRUM RV STATUS INSTRU AIR 95 PSIG RCP #2 FLOW 17 GPM x 103 OPEN SHIIT J _

FWP DISCHG 0 PSIG TitRBINE INL 1000 PSIG ~l CONTROL RODS l-COND DISCHG 0 PSIG l RX PRESS 1000 PSIG 125 V DC BUS ENERG FDbTR TEMP 100 *F ALL IN J RX WATER 22.5 FEET Y ECS #1 LOOP 95 *F ECS #2 LOOP 100 *F NOTCHES OUT CONDENSER VACIRM COND LEVEL 30 % W FIDW 0 lb/HR 10 3 0 inHg 3

CST EVEL 75 % STEAM FIDW 100 lb/HR 10 l l DWST LEVEL 80 % DRUM LEVEL FSH INCHES (p)

VENT VLV POS C CONTAINMENT PRESS .05 PSIG MSIV POS 0 CONT WATER EVEL <574 FT OFF GAS - UNITS

_ a _

ECS WATER LVL 100 % CRD PP DSCH 1400 PSIG 1.58 kV AVAIL Y -

B/U CORE SPRAY 0 GPM CRD COOLING

GPM 46 kV AVAIL Y -

PRI CORE SPRAY 0 GPM CRD HEADER

GPM EDG AVAIL Y -

B/U CONT SPRAY 0 GPM CRD COOLING

PSID 28 BUS ENERG Y -

l- PRI CONT SPRAY O GPM CRD HEADER

PS -

DCWRM Sx10{D%

START-UP CHN - CPS COMMENTS /PIANT STATUS: *0 sci 11ating Annunciators: Feed Pump Trip Also see 0915 Time Sheet Feed Pump Low Suction Pressure CRD Pam.p Low Suction Pressure Condenser _"fot Well Law Level Alarm Turbine Shield Wall Area Monitor Turbine Building Cam Laundry Room Area Monitor Steam Drum 'ow Level (-4") . RDS STATUS Steam Drum Low Level Scram (-8") FIRED RESET Steam Drum Low Level (-17") OTHER Fire Pumps Start RX WATER LVL G COIDR Two-Minute Timer Start DRtM LEVEL -20 INCHES FC DHILL USE ONLY NUO688-01I? q i-Ti-07 y-

SCENARIO NO BREX-88 TIME'= 0915:45 HESSAGE No 5 T=

. 0115:45 BIG ROCK POINT NUCLEAR PlJLYT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM-MESSAGE FOR: Player on turbine deck /Shitt Supervisor SIMULATED PLANT CONDITIONS:

,. MESSAGE: This is (name) on the turbine deck. There was~a '

real loud noise out here. Now steam is leaking on the turbine deck.

CONTROLLER USE ONLY n

Controller must ;ntslall this messate in to Control Room /se. i instruct a player to de ... J. rh-G i i !- 4.

~

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4 t

i

+

4 1

l NUO488-0113A-TP11-TP12 ,

SCENARIO NO BREX-88 TIME = _ 0917

,- MISSAGE NO 6 T= 0117 4

'l BIG ROCK POINT NUCLEAR PLA!G EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSAGE FOR: Shift Supervisor / Control Room Operator SIMULATED PLANT CONDITIONS: See Data Sheet.

MESSAGE:

CONTROLLER USE ONLY

1. If started, feedwater/ condensate pumps will run until water in the hot well is gone, approximately 2-1/2 minutes from the time they are started.

Drum level will increase from -25" to -5" before the feedwater pump trips again.

2. Both control rod drive pumps remain in service and will maintain drum

/' level at about -5" as long as they are running.

5,

3. Following MSIV closure, reactor pressure will steadily increase resulting in alarms at indicated intervals. The Control Room Controller will provide this information verbally to players:

Alarms - 45 seconds - reactor pressure +25 Alarms - 1.5 minutes - reactor pressure +50 Alarms - 3 minutes - reactor pressure +100 6 minutes - reactor pressure +200

4. FW Flow - 450/900 lb/hr 103 (1 versus 2 PPS)

?

/fUO488-0113A-TP11-TP07

BREX 88 TIME: 0917 MESSAGE: 6 SCENARIO TIME: 0117 CORE SPRAY O PSIG RCP #1 FLOW 16.5 GPM x 103 DRUM RV STATUS INSTkU AIR 95 PSIG RCP #2 FLOW 17.0 GPM x 103 OPEN SHUT /

WP DISCHG 1600 PSIG TURBINE INL 0 PSIG _l CONTROL RODS l_

COND DISCHG 232 PSIG RX PRESS 1360t PSIC 125 V DC BUS ENERG FDWTR TEMP 80 *F ALL IN J RX WATER FSH FEET Y ECS #1 IDOP 95 *F -

ECS #2 IDOP 100 *F NOTCHES OUT CONDENSER VACUUM COND LEVEL 10 % W FLOW

lb/HR 10 3 0 inHg CST LEVEL 73 % STEAM FIDW 0 lb/HR 103 l l DWST LEVEL 80 % DRUM LEVEL -12 INCHES (g)

VENT VLV POS C CONTAINMENT PRESS .04 PSIL MSIV POS C CONT WATER LEVEL <574 FT OFF GAS -

UNITS ECS WATER LVL 100 % CRD PP DSGH 1760 PSIG 138 kV AVAIL Y -

B/U CORE SPRAY 0 GPM CRD COOLING 12 GPM 46 kV AVAIL Y -

PRI CORE SPRAY 0 GPM CRD HEADER 25 GPM EDG AVAIL Y -

B/U CONT SPRAY 0 GPM CRD COOLING 26 PSID 2B BUS ENERG Y -

PRI CONT SPRAY 0 GPM CRD HEADER 250 PSID -

DCWRM 10 %

START-UP CHN 80 CPS COMMENTS / PLANT STATUS:

Controller will supply data e [,.J's. #m ee rJ o RDS STATUS

, FIRED RESET OTHER Timers Running RX WATER LVL G COLOR DRUM LEVEL -12t INCHES .

FOR DRILL USE ONLY CUO488-Oll3P 1-TP07 w \uh N'

4 s'

c 0923 TIME = _

li f SCEht310 NO _ BREX-88 T= 0123 7

MESSAGE NO _ fl BIG ROCK POINT NUCLEAR PLANT.

EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Shift Supervisor / Control Room Operator

/ MESSAGE FOR:

i See Data Sheet.

t SIMULATED PLANT CONDITIONS:

e MESSAGE: ...--------..... .

CONTROLLER USE ONLY i for

' Steam drum relief valve lif ts (acoustic. alarm) and stays openPrimary coola 15-20 seconds and then closes.

' 1540 psig to 1490 psig. The valve repeatedly cycles open for 16-18

then closed for 80 seconds.and-containment temperature increases with s' - Cont Temp Other

,d Cont' Pressure

-\~ Time _

100 High temp alarm 0923 0.7 110 Cont high press 0924:30 1.4 scram / isolation 1.9 120 0926 l containment 2.3 130 0927:30 sprays initiate lly to Control Roos Controller will provide appropriate information verba players.

+

.NUO488-0113A-TP11-TP12 m

BREX 88 TIME: 0923 MESSAGE: 7 SCENARIO TIME: 0123 CORE SPRAY 0 PSIG RCP #1 FIDW 16.5 GPM x 108 DRtM RV STATUS INSTRU AIR 90 PSIG RCP #2 FLOW 17 CPM x 10 3 OPEN

SHUT WP DISCMG 0 PSIG TURBINE INL 0 PSIG _l CONTROL RODS l_

COND DISCHC 0 PSIG RX PRESS 1500 PSIG 125 V DC BUS ENERG ITNTR TEMP 80 *F ALL IN / RX WATER FSH FEE 1 Y ECS #1 IDOP % *F ,

ECS #2 IDOP 101 *F NOTCHES OUT ,

CONDENSER VACUUM COND LEVEL 15 % W FLOW 0 lb/HR 10 3 l 0 inHg 3

CST LEVEL 68 % STEAM FLOW D lb/HR 10 l l DWST LEVEL 80 % DRUM IIVEL -5 INCHES (g)

VENT VLV POS C CONTAINMENT PRESS 0.7 PSIL.

MSIV POS C CONT WATER LEVEL <574 FT OFF GAS - UNITS ECS WATER LVL 100 % CRD PP DSGH 1900 PSIG 138 kV AVAIL Y -

B/U CORE SPRAY 0 GPM CRD COOLING 12 GPM 46 kV AVAIL Y -

PRI CORE SPRAY 0 GPM CRD HEADER 26 GPM EDG AVAIL Y -

B/U CONT SPRAY 0 GPM CRD COOLING 26 PSID 2B BUS ENERG Y -

PRI CONT SPRAY 0 GPM CRD HEADER 250 PSjD DCWRM 4 x 10 %

START-UP CHN 75 CPS CotLMS/ PLANT STATUS:

Steam drum relief valve is cycling. Controller will provide inforestion.

Annunciators: Acoustic Monitor Containment High Temperature / Dew Point Reactor Building Vent System Trouble Area Monitor Alarm Sphere Cam Alarm "Drum Safety Valves Leak" Alarm -

RDS STATUS FIRED RESET OTHER Timers Timed Out RX WATER LVL G COLOR DRUM LEVEL -5 INCHES FOR DRILL USE ONLY 0U0488-0* TPil-TPG7 ..

~

v b/

o

'I6/; *

9 qc' SCENARIO NO BREX-88 IIME = 0927: 30 MESSAGE NO 8 T= 0127:30

' k[,

BIC ROCK POINT MUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MISSAGE.70R: Shift Supervisor / Control Room Operator SIMULATED Pl%'T CONDITIONS: See Data Sheet.

MESSAGE:

CONTROLLER USE ONLY

1. Steam drum tilief valve cycles for the fourth time. Containment precsure reaches the set point for automatic initiation of containment spray.

2.

Following containment spray initiation, containment pressure fluctuates between 1.8 psig and 2.5 psig. Containment temperature fluctuates between 105'F and 110'F.

i km t

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%. j NUO488-0113A-TP11-TP12 I

BREX 88 TILE: '0927:30

IESSACE: & SCENARIO TIfE: , 0127:30 4

j l CORE SPRAY 0 PSIG RCP #1 FLOW 16.5 GPft x 103 DRtRt RV STATUS -

) INSTRU AIR 95 PSIG RCP #2 FLOW 17 CPf1 x 103 OPEN

SNUT FWP DISCNC 0 PSIC PJRBINE INL 0 PSIG _l CONTROL RODS l _

COND DISCNC 0 PSIC RX PRESS 1500 PSIG 125 V DC BUS ENERG l FDWTR TEMP 60 *F ALL IN / RX WATER FSN FEET Y ECS #1 IDOP 98 *F ECS #2 LOOP 104 *F NOTCHES OUT CONDENSER VActRRt COND IIVEL 40 % W FIAW 0 Ib/HR 10 3

_ 0 iaNg.

4 CST IIVEL 64 % STEAff FLOW 0 lb/HR 103 l l

DWST IIVEL 80 % DRUtt IIVEL -4

} VENT VLV POS C INCHES ({}

CONTAllWENT PRESS 2.3 PSIG l ItSIV POS C CONT WATER IIVEL <574 kT OFF GAS - L2ilTS ECS WATER LVL 100 % CRD PP DSGH 1900 PSIC 138 kV AVAIL Y B/U CORE SPRAY 0 GPM CRD COCLING 12 CPft 46 kV AVAIL Y -

PRI CORE SPRAY 0 CPM CRD HEADER 25 GPft EDC AVAIL Y -

B/U CONT SPRAY 0 CPM CRD COOLING 26 PSID 2B BUS ENERG Y -

1 PRI CONT SPRAY 150 CPM CRD HEADER 250 PS -

} DCWRM Sx10{D%

j START-UP CHN 70 CPS i

]li C0tRENTS/PIANT STATUS: Annunciators: "Prianary Enclosure Spray Activation" "Reactor Containment Spray Flow Normal" i

Steam drum relief valve cycling, Controller will provide information.

i i

4 RDS STATUS

. FIRED RESET i OTHER RX WATER LVL C COLOR DRINI LEVEL -4 INCHES j

FOR DRILL USE cHD j .

t t

NUO4[O-O l I3' II-TP07

%) %d

1 . .

TIME = 0930 SCENARIO NO- BREX-88 T= 0130 f MESSAGE NO d BIG ROCK POINT NUCLEAR PLANT _ )

EMERGENCY PREPARELNESS EXERCISE MESSAGE FORM

. 1 Shif t Supervisor / Control Room Operator MESSAGE 'f0R:

Sec Data Sheet.

SD!ULATED PLANT CONDITIONS:

?2SSAGE:

' CONTROLLER USE ONLY 1, Containment sprays. operating continuously

2. Steam drum relief valves cycling once every 100 seconds

3. Both control rod drive pumps are operating.

4. Data sheet information - provide verbally to players.

FWP discharge O psig if off 1,800 psig if on

Cond discharge 0 psig if off 770 psig if on I

NUO488-0113A-TP11-TP12

BREX 68 TItG: 0930 ffESSAGE: 9 SCENARIO TIME: 0130 CORE SPRAY 0 PSIG RCP #1 FIDW 16.5 GPM x 108 DRUM RV STATUS INSTRU AIR 95 PSIG RCP #2 FLOW 17 GPM x 103 OPEN

SHUT FWP DISCHG ** PSIG TURBINE INL 0 PSIG _l CONTROL RODS l_

COND DISCHG ** PSIG RX PRESS 1560 PSIG 125 V DC BUS ENERG FDWTR TEMP 70 *F ALL IN J RX WATER 22.5 FEET Y ECS #1 W P 98 *F ECS #2 IDOP IK *F NOTCHES OUT CONDENSER VACUtR1 COND EVEL 50 % FW FLOW 0 lb/HR 10 8 0 inHg CST LEVEL 63 _ % STEAM FLOW 0 lb/HR 10 8 I l~

DWST LEVEL 80 % DRUM LEVEL -4 VENT VLV IOS C_ _ CONTAINMENT PRESSINCHES 2.0 PSIL(})

MSIV POS C CONT WitTER LEVEL <574 FT OFF GAS - UNITS ECS WATER LVL 100 % CRD PP DSGH 1950 PSIG 138 kV AVAIL Y -

B/U CORE SPRAY 0 GPM CRD COOLING 11 GPM 46 kV AVAIL Y -

PRI CORE SPRAY 0 GPM CRD HEADER 20 GPM EDG AVAIL Y -

B/U CONT SPRAY 0 GPM CRD COOLING 24 PSc. 2B BUS ENERG I -

PRI CONT SPRAY 150 GPM CRD HEADER 260 PS -

DCWRM 3x 10 {D%

START-UP CHN 70 CPS COMMENTS / PLANT STATUS:

Cycling, _ Controller will provide information.

- Controller will provide information verbally.

RDS STATUS

. FIRED RESET OTHER RX WATER LVL G COLOR DRtRf LEVEL -3 INCHES FOR DRILL USE CNLY NUO488-Ol l3' Il-TP07 s ,- (/ U

e e l

SCENARIO NO BR EX-88 TIME = 0945

,- MESSAGE NO 10 T= 0145 1

l BIG ROCK POINT NUCLEAR PLANT ,

EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSAGE FOR: Shif t Supervisor / Control Room Operator SIMULATED PLANT CONDITIONS: See Data Sheet, MESSAGE:

CONTROLLER USE ONLY With two control rod drive pumps running, steam drum level is slowly increasing,

, l' 1 (,

NUO488-0113A-TP11-TP12

l BREX 88 TIME: 0945 MESSAGE: 10 , SCENARIO TIME: 0145 CORE SPRAY 0 PSIG RCP #1 FLOW 16.5 GPM x 103 DRtM RV STATUS INSTRU AIR 94 PSIG RCP #2 FLOW 17 GPM x 103 OPEN

SHUT FWP DISCHC 0 PSIG TURBINE INL -

PSIG _l CONTROL RODS l_

COND DISCHG 0 PSIG RX PRESS 1550 PSIG 125 V DC BUS ENERG' FDimt TEMP 80 'F ALL IN / RX WATER FSH FEET Y ECS #1 IDOP 100 'F -

l ECS #2 IDOP 196 'F NOTCHES OUT CONDENSER VACUUM COND IIVEL 50 % FW FIDW 0 lb/HR 10 3 0 inHg CST LEVEL 63 % STEAM FLOW 0 lb/HR 10 3 l l DWST LEVEL 80 % DRIM LEVEL -2 INCHES (p) l VENT VLV POS C CONTAINMENT PRESS 2.3 PSIC MSIV 10S C CONT WATER LEVEL <574 FT OFF GAS - UNITS ECS WATER LVL 100 % CRD PP DSCH 1945 GPM 138 kV AVAIL Y -

B/U CORE SPRAY O GPM CRD COOLING 12 GPM 46 kV AVAIL Y -

PRI CORE SPRAY 0 GPM CRD HEADER 20 CPM EDG AVAIL Y -

B/U CONT SFRAY 0 GPM CRD COOLING T PSID 2B BUS ENERG Y -

PRI CONT SPRAY 150 GPM CRD HEADER 250 PS -

DCWRM 1x10{D%

START-UP CHN 65 CPS l l COMMENTS / PLANT STATUS:

-w RDS STATUS FIRED RESET OTHER RX WATER LVL G COLOR DRUM LEVEL -2 INCHES FOR DRILL USE ONLY ME88-O i l3* 'tI-TP07 l

w %d %O

SCENARIO NO BREX.88 TIME = 1000

(

i MESSAGE NO 11 T = , 0200 BIG ROCK POINT NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MISSAGE FOR: Shif t Supervisor / Control Room Operator SIMULATED PLAh"I CONDITIONS: See Data Sheet.

MESSAGE:

CONTROLLER USE ONLi If beth control rod drive pumps are left on, steam drum level vill continue to slowly increase.

t v.

NUO488-0113A-TP11-TP12

i t

! ,F'.EX 88

! TIME: 1000

( f1ESSAGE: 11 SCENARIO Tiff: 0200 I

l f CORE SPRAY 0 PSIG RCP #1 FLOW 16.5 GPft x IOS DRUff RV STATUS

! INSTRU AIR 95 PSIG RCP #2 FIAW 17 GPff x 108 OPEN

SHUT EVJ DISCHG 0 PSIG TURBINE INL 0 PSIG _l CONTROL RODS l_

i COND DISCHG 0 PSIG RX PRESS 1540 PSIC 125 V DC BUS ENERG

! FDWTR TEMP 80 *F c ALL IN _J RX WATER _FSM , FEET Y ECS #1 ILOP 102 *F ECS #2 U)0P TW 'F NOTCHES OUT CONDENSER VACUtti COND LEVEL SO W FLOW 0 lb/HR 10 3 O inHg CST LEVEL 63- 1I STEAM FM)W 0 lb/HR 10 8 .7 f DWST LEVEL 80 1 DRUrt LEVEL +1 INCHES ([)

VDiT VLV POS C CONTAINftENT PRESS 2.4 PSIG MSIV POS C CONT WATER IIVEL <574 FT OFF GAS - UNITS I -

ECS WATER LVL 100 % CRD PP DSCH 1930 PSIG 138 kV AVAIL Y -

B/U CORE SPRAY 0 CPM CRD COOLING 11 GPft 46 kV AVAIL Y -

PRI CORE SPRAY 0 CPM CRD HEADER 20- GPf1 EDG AVAIL Y -

B/U CONT SPRAY 0 CPM CRD COOLING 25 PSI 1, 28 BUS ENERG Y -

PRI COW SPRAY 150 CPM CRD HEADER 260 PFID -

DCWRM **1 x 10 %

START-UP CHN 60 CPS COMt1ENTS/ PLANT STATUS:

Cycling, Controller will provide information.

WChannel 2 DCWkt1 fails downscale.

IDS STATUS

. FIRED RESET OTHER RX WATER LVL G CC"Nt DRUtt LEVEL +1 INCHES FOR DRILL USE ONLY NUO488-Oll3 'l l-Trol

~

~~- ^ *l 'l

3

SCENARIO NO BREX-88 TIME = 1015 MESSAGE NO 12 T= 0215 BIG ROCK POINT NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSAGE FOR: Shi't Supervisor / Control Room Operator SIMULATED PLANT CONDITIONS: See Data Sheet.

MESSAGE:

CONTROLLER USE ONLY Both recirculation pumps trip.

r

\

NV0488-011'3A-TP11-TP12

3 BREX 88 TIfE: 1015 ftESSAGE: 12 SCENARIO TIIE: 0215 -

( CORE SPRAY 0 PSIG RCP #1 FLOW 0 GPft x 108 DRItt RV STATUS INSTRU AIR 93 PSIG RCP #2 FIDW 0 GPft x 103 OPEN

Sf!UT WP DISCHG O

_ PSIG TURBINE INL -

PSIG _l CONTROL ItODS l_

COND DISCMG 0 PSIG RX PRESS 1530 PSIG 125 V DC BUS ENERG FDWTR TEMP 80 *F ALL IN / RX WATER FEET Y s

j CCS #1 IAOP 105 *F I10 *F NOTCHES OUT CONDENSER VACUlti p[ECS#2th0P CotQ LEVEL 50 % W FLOW 0 Ib/NR 103 0 inHg CST 11bL 63 % STEAM FIDW 0 Ib/NR 103 l l 1AST LCVEL 80 % DRUtt LEVEL +4 tEl-T Wy POS C INCHES ({}

~ CONTAllRENT PRESS 2.4 PSIG XSU' POS C COtrT WATER IIVEL 574.5 FT OFF GAS - UNITS ECS WATER LVL 100 % CRD PP DSCH 1930 PSIG 138 kV AVAIL Y -

B/U CORE SITAY C GPf4 CRD COOLING 12 GPft 46 kV AVAII- Y -

PRI CGRE SPR$ U GPft CRD MEADER 20 GPft ' EDG AVAIL Y -

B/U CONT SPIAI O GPft CRD COOLING 25 PSID 2B BUS ENERG Y -

PRI CONT SPR*T 150 GPft CRD NEADER 260 PSID,.

~

DCWRM **3 x 10 *%

START-UP CHN **SS CPS COMMENTS / PLANT STATUS:

Cycling, ControIIer will provide information.

- Channel 1 DCWRft and Channel 6 start-up fail downscase.

RDS STATUS

. FIRED RESET OTHER RX WATER LVL G COIDC DRUM LEVEL +4 INCHES FOR DRILL USE ONLY NUO488-0113P l-TP07 '

i c W

l _ _ . _ _ _ . . _ _ . . _ . .

9 I SCENARIO NO BREX-88 TIME = 1030 MESSAGE NO 13 T= 0230 E (

BIG ROCK POINT NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSAGE FOR: Shift Supervisor / Control Room Operator SIML* LATED PLANT CONDITIONS: See Data Sheet.

MESSAGE:

CONTROLLER USE ONLY

(

r S,

J' 5

NUO488-0113A-TP11-TP12

r, _nR&s

"~

.r. .

TIfE: C30 fESSAGE: - 13 SCENARI3 TIfE: C230 e

CORE SPRAY 0 PSIG IICF fl FIA W 0 GPfl x 188 DRtM RV STATUS IIISTitU AIR 94 PSIC RCP #2 FIAW I GPM z 108 OPEN

SIRrr Pwr CISCNC 0 PSIG TURSIIIE INL 0 _ PSIG _I CONTROL 200S l_

COND DISCMG 0 PS14 RX PRESS 1500 PSIC 125 V DC BUS ESIERG ALL IN /

PDWI1t TEMP 80 *F RX WTER FSR FEET Y ECS #1 IR3P 106 *F ECS #2 IAOP 111 *F NOTCIES OLTT COIIDelSER WdtRM.

COIID LEVEL 50 % PW FiAW 0 lb/Ist 10 88 0 infig CST LEVEL 6T % STEAf FLOW 0 lb/NR 30 .l _

l DWST LEVEL 80_ % DRUll LEVEL +8 INCNES ({}

VENT VLV POS C UNITAIINEllT PRESS 2.2 PSIG IMIV POS C COIff WATER 12 VEL 575 FT OFF GAS - UNITS

- LCS WATER LVL 100 % CItD PP DSGN 1900 PSIC l138kVAVAILT -

B/U CORE SPRAY 0 GPfl CitD 000LIIIC 12 GPfl 46 kV AVAIL Y -

PRI COIRE SPIRAY 0 GPfl CitD w aara 20 GIN r.DG AVAIL Y -

B/U COIfT SPRAY 0 GPM CitD COOLING 25 PSID 2B BUS E3IERG Y -

- PRI CONT SPIRAY 150 GPfl sJtB IIEADER _260PSgD IX.1NNE 1 x 10 % !

STAltT-UP CMI 55 CPS

_I C009ENTS/PIJufT STATUS: *Cyclima, Controller will provide information.

I l

RDS STATUS FIRED RF S OTHER RK MATJ'R LYL G CCMIt DRIr LEVEL +8 INOES FOR DRILL USE DILLY IIUO488-01135-TPil-TP07

t t SCENARIO NO BREX.88 TIME = 1045

( MESSAGE NO 14 T= 0245 BIG ROCK POINT NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MISSAGE FOR: Shif t Supervisor / Control Room Operator SIMULATED PLANT CONDITIONS: See Data Sheet.

MESSAGE:

CONTROLLER USE ONLY I

(

NUO488-011.'A-TP11-TP12

BREX 88 TIFE: 1945 ftESSAGE: 14 SCENARIO TI!E: c245 CORE SPRAY 0 PSIG RCP #1 FilMi O GPtt x 103 DRLM RV STATUS INSTNU AIR 93 PSIG RCP #2 FIJW D GPfl x 10 3 OPEN

SNUT WP DISCHG 0 PSIG TJRBINE INL 0 PSIG _l CONTROL RODS l _

COND DISCMG 0 PSIG RX PRESS 1520 PSIG 125 V DC BUS ENERG FDWTR TEMP 80 *F ALL IN X RX WATER FSM FEET Y ECS #1 IAOP 107 *F ECS #2 IDOP 111 *F NOTCHES OUT CONDENSER VACUUti COND EVEL Foi FIlW D lb/NR 10 3 0 inHg -

50~ %

CST EVEL 53 % STEAM FIEW 9 lb/MR 10 3 7 f DWST EVEL 80 % DRUrl EVEL +13 INCMES({}

VENT VLV POS C CONTAINPENT PRESS 2.4 PSIG MSIV POS C CONT WATER EVEL 575.5 FT OFF GAS - UNITS ECS WATER LVL 100 % CRD PP DSGd -

PSIG 138 kV AVAIL Y -

B/U CORE SPRAY 0 GPft CRD COOLING - :';PM 46 kV AVAIL Y -

PRI CORE SPRAY O _ GPM CRD NEADER -

GPft EDG AVAIL Y -

8/U CONT SPRAY O GPft CRD COOLING - PSID 2B BUS ENERG Y -

- PRI CONT SPRAY 150 GPft CRD MEADER -

PSID ~

6 DCWRM 1.5 x 10 %

START-UP CHN **- CPS 5

CotetENTS/ PLANT STATUS: _* Cycling, Controller will provide insforisation.

- Start-up Channel 7 fails downscale.

Annunciators: Rod Drive Mi Temp CRD Pump Low Discharge Pressure l

l l RDS STATUS l , FIRED RESET OTHER RX WATER LVL G COIDR DRtM EVEL +13 INCHES i NUO488-0113I I l-TIT 7

~.s %.s/ &

6 s SCENARIO NO BREX_88 TIME e 1100 MESSAGE NO 15 T= 0300 k

BIC ROCK POINT NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSAGE FOR: Shift Supervisor / Control Room Operator SIMULATTD PLANT CONDITIONS: See Lata Sheet.

MESSAGE:

CONTROLLER USE ONLY

1. Both CRD pumps trip.

2. k'1 't no operator action, drum level vill dron slowly, 2" per 15 minutes, l'

N.

N'.'04 S S _0113 A-T Pi l-IP 12

A BRET-M 8. ..

TIfE: 1100 ESSAGE: 15 SCl3fAR13 TIME: C300

~

CORE SPRAY 0 PSIC RCP #I FLOW 0 ~ GPM x 103 DPUtt RV STATUS INSiRU AIR 96 PSIG RCF #2 FLOW D GPM x 103 OPEN

SMUT FWP CISCHG 0 PSIG IIRBINE INL 0 PSIG _l CONTROL RODS l_

COND DISCHC 0 PSIG RX PRESS 1520 PSIG 125 V DC BUS ENERG FIMIR TEMP 80 *F ALL IN ] RX WATER FFI FEET Y ECS #1 IAOP 107 *F _

ECS #2 LOOP 112 *F NOTCHES OUT CONDENSER VACUUM COND LEVEL 50 % FV F7W 0 Ib/HR 10 3 0 inHg CST LEVEL 63 % S17'./.M FLOW 0 lb/HR 10 3 l l DWST LEVEL 8_0_ % DR?d EVEL +18 INCHES ({}

VENT VLV POS C CO'4TAINVENT PRESS 2.6 PSIG ftSIV POS C_ _ CC.(T WATER EVEL 576 FT OFF GAS - UNITS ECS WATER LVL 200 % CRD PP DSCH - PSIG 138 kV AVAIL Y -

R/U CORE SPRAY 0 GPM CRD COOLING -

GPrt 46 kV AVAIL Y -

PRI CORE SPRAY 0 GPM CRD NEADER -

CIM EDG AVAIL Y -

B/U CONT SPRAY 0 GPM CRD COOLING - PSID 2B BUS ENERG Y -

PRI CONT SPRAY 150 GPft CRD MEADER -

PSgD -

DCWRM 1x 10 %

START-UP CNN - CPS C0f9ENTS/ PLANT STATUS: *Cyclieg, Controller will provide informistion.

l

. RDS STATUS FIRED RESEf OTHER RX WATER LVL G COLOR-DRUM LEVEL +18 INCHES FOR DRILL USE ONLY i

NUO488-CI138-TP~tI-TP07

, , - - - r,. -- ,er-,- - - - . , - - - - - - - - - - - - - , , -

,n---- - - - , - - - , - - . --- -~ - - ~ -

. a--- - - - - - ,s-- -- --=>-e - - - - - - - - - - - - - -. , - -

6 a SCENATIO NO BREX.88 T IMI = , 1115

( MESSAGE NO 16 _

T= 0315 BIG ROCK POINT NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MISSAGE FORh MISSAGE FOR: Shift Supervisor / Control Room Operator SIMULATED PLANT CONDITIONS: See Data Sheet.

PESSAGE:

CONTROLLER USE ONLY A'

C.

l

\.

l i

( NUO488-Oll3A-TPll-TP12

)

BREX 88 MESSAGE: 16 TIME: 1115 SCENARIO TIME: 0315 CORE SPRAY 0 PSIC RCP #: FIhW 0 GPM x 103 DRUM RV STATUS INSTRU AIR 92 PSIG RCP #2 FIDW 0 GPM x 103 OPEN

SliUT WP DISCl!G 0 PSIG TURBINE INL -

PSIG COND DISCHG 0 _ l CONTROL RODS l PSIC _

FDVTR TEMP RX PRESS 1550 PSIG I25 V DC BUS ENERG EO _ 'F ALL IN J RX WATER FSil FEET Y ECS #1 IDOP 108 *F ECS #2 LOOP 113 *F NOTCHES OUT COND LEVEL 50 CONDENSER VACUUM

% W FLOW -

Ib/HR 103 CST LEVEL 0 inIIg 63 % STEAM FIDW O O Ib/IIR 103 l l DWST LEVEL 80 1 DRUM LEVEL -f-/p INCHES ({}

VENT VLV POS C CONTAINMENT PRESS 2.5 PSIG MSIV POS C CONT WATER LEVEL 576.5 FT OFF GAS - UEITS

~

100 %

ECS WATER LVL CRD PP DSGli - PSIG I38 kV AVAIL Y -

B/U CORE SPRAY 0 GPM CRD COOLING -

GPtf 46 kV AVAIL Y -

i PRI CORE SPRAY 0 GPM CRD HEADER -

CPM EDG AVAIL Y -

B/U CONT SPRAY 0 GPM CRD COOLING - PSID 2B BUS ENERG Y -

PRI CONT SPRAY 150 GPM CRD HEADER -

PS -

DCWRM 8x 10}D%

START-UP CIIN _ _ CIS COMMENTS /PIANT STATUS:

Cycling, ControIIer will provide information. !

RDS STATUS FIRED RESET OTilER RX WATER LVL G COIBR DRUM LEVEL +I6 INCHES FOR DRILL USE ONLY CUO488-01 -TPil-TP07 k/ V

4 4 SCENARIO NO BREX.88 TIME . 1125

[ MESSAGE NO 17 T= 0325 BIG ROCK POINT NUCLEAR PLANT EMIRCENCY PREPAREDNESS EXERCISE MISSACE FORM FESSAGE FOR: St4ft Supervisor / Control Room Operator SIMULATED PLANT CONDITIONS: See Data Sheet.

MESSAGE:

CONTROLLER USE ONLY

1. A steam drum relief valve opens to relieve pressure and sticks in the open position. Primary coolant system level and pressure drop rapidly; in 30 seconds primary coolant system level is 2'9" above the core and the reactor depressurization system will actuate following the two minute timer unless it was not reset after steam drum level was restored at the e

r- onset of the transient,

2. Following the steam drum valve sticking open, conditions change rapidly.

O Steam drum relief valve sticks. -

+30 seconds Primary coolant 2'9" above core (alarm), reactor depressus-ization system actuation (Assuming timer not reset - if reset, add two minutes to all following events.)

+50 seconda Primary coolant system pressure 200 psig (alarm)

+60 seconds Core spray flow starts (alarm).

7t seconds Core spray flow 300 gpm (backup and primaty)

3. Operator should verify proper operation on reactor depressurization system and core spray.

l l

l C

NUO488-Oll3A-TPll-TP12

BREX 88 TIFE: 1125 MESSAGE: 17 SCENARIO TITE: 0325 CONE SPRAY 0 PSIG RCP #1 FLOW 0 GPM x 103 D2tM RV STATUS INSTku AIR 95 PSIC RCP #2 FIDW 0 GPM x 103 OPEN / SNUT fvP DISCHC 0 PSIC TURBINE INL - PSIG _l CONTROL RODS l_

COND DISCMG 0 PSIC RX PRESS 200 PSIG 125 V DC BUS ENERG FINrfR TEMP 80 *F ALL IN / RX WATER FSL FEET Y ECS #1 LOOP 109 *F ECS #2 IDOP 113 *F NOTCHES OUT CONDENSER VACULM COND LEVEL 50 % FW FIDW 0 Ib/MR 10 3 ,

O inNg 3

CST LEVEL 63_ % STEAM FLDW 0 lb/MR 10 l _

l DWST IIVEL 80 % DRUM LEVEL -30 INCHES (p)

VENT VLV POS C CONTAINMENT PRESS St PSIG ttSIV POS C CONT WATER LEVEL 577 FT OFF GAS UNITS ECS WATER LVL 100 % CRD PP DSCH - PSIG 138 kV AVAIL T -

B/U CORE SPRAY 0 GPt! CRD COOLING - GPfl 46 kV AVAIL Y -

PRI CORE SPRAY 0 GPM CRD HEADER -

GPM EDG AVAIL Y -

B/U CONT SPRAY 0 GPM CRD COOLING -

PSID 2B BUS ENERG Y -

l PRI CONT SPRAY 150 GPM CRD HEADER -

PSID -

DCWRM *- %

START-UP CHN - CPS l CONMENTS/ PLANT STATUS: Annunciators: Reactor Iow Water Level Scram l Core Spray Valve Open FDS Alarms JefT'ChanncIs Tripped and Valves Open

Fails downscale 67 l RDS STATUS FIRED 1 RESET OTHER RX WATER LVL R COLOR DRIM LEVEL -30 INCHES FOR DRILL USE ONLY NUO488-Oll3* it-TP01 I

~., v. & %/

e e SCENARIO NO B R EX-88 TIME . 1130 MISSAGE NO 18 T= 0330 BIG ROCK POINT NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSAGE FOR: Shift Supervisor / Control Room Operator SIMULATED PLANT CONDITIONS: See Data Sheet.

MESSAGE:

i CONTROLLER USE ONLY Both core spray systems are operating norcally. Containment pressure is being reduced by containment sprays after peaking at 25 psig.

1 i

e l

l l

l' t i

9 NUO488 0113A-TP11-TP12

l 7 l

l BREX 88 i

PsESSAGE: 18 TIfE: II30 SCENARIO TIfE: 0330

, CORE SPRAY 90 PSIC RCP #1 FIN O GPft x 103 DRLM RV STATUS l INSTRU AIR 95 PSIC RCP #2 FLOW 0 GPM x 103 WP DISCNC 0 PSIG TURBINE INL OPEN / SNUT PSIC ._l l COND DISCMG 0 PSIG CONTROL RODS l _

RX PRESS 60 PSIG 125 V DC BUS ENERG FDVIR TEMP 80 *F ALL IN /

ECS #1 IAOP 108 'F RX WATER FSL FEET Y ECS #2 Ih0P 113 *F NOTCHES OUT COND LEVEL 50 CONDENSER VACIRM

% FW FI M 0 Ib/HR IC8 I 0 inHe CST LEVEL Q_% STEAM FIN O _ lb/NR 10 3

l l DWST LEVEL 80 % DRUM LEVEL VENT VLV POS C FSL INCNES ({}

CONTAINfENT PRESS _ 224 PSIG PtSI'4 POS C CONT WATER IAVEL 578 FT OFF GAS IM fS ECS WATER LVL 100 % CRD PP DSGH PSIG 138 kV AVAIL Y -

B/U CORE SPRAY 400 GP!t CRD COOLING -

GPM 46 kV AVAIL Y PRI CORE SPRAY 380 CPM CRD MEADER -

CPM EDG AVAIL Y -

B/D CONT SPRAY 0 CPft CRD COOLING -

PSID 2B EUS F C G Y -

PRI CONT SPRAY 150 CPM CRD HEADER -

PSID -

DCWRft -

START-UP CHN - CPS COMMENTS / PLANT STATUS:

RDS STATUS FIRED / RESET OTHER RX WATER LVL G COLOR DRUM LEVEL -30t INCHES FOR DRILL USE ONLY Nuo488-Ol' FPil-TP07 s MM

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

. e SCENARIO NO BREX.88 TIME = 1140 MISSAGE NO 19 T= 0340 BIG ROCK POINT NUCLFAR PLAhi EMERGENCY PREPAREDNESS 2XERCISE MESSAGE FORM MESSAGE FOR: Shift Supervisor / Control Room Operator SIMULATED PLANT CONDITIONS: See Data Sheet.

MESSAGE:

CONTROLLER USE ONLY

1. Drum level comes on scale and is increasing 6" per minute.

2. Neutron monitoring instruments fail down scale, r

e s.

e s'

S.

NUO488-011',A-TP11-TP12

BREX 88 TIME: 1140 MESSAGE: 19 SCENARIO TIME: 0340 Coke SPRAY 90 PSIC RCP #I FLOW 0 GI'M x 103 DR121 RV STATUS INSTRO AIR 95 PSIG RCP #2 FIDW 0 GPM 7 103 FVP DISCHC 0 OPEN / SHITT PSIG TURBINE % -

PSIG _l CONTROL RODS l_

COND DISCHG 0 PSIC _

RX PRESS $8 PSIG I25 V DC BUS ENERG FDVTh TEMP 80 *F ECS #I LOOP 109 'F ALL IN / RX VATER FSH FEET Y ECS #2 LOOP 114 'F NOTCHES OUT CONDENSER VACUUM COND LEVEL So % FW FLOW 0 Ib/HR 103 CST LEVEL 63 0 infig

% STEAM FLOW 0 Ib/HR 103 l l DWST LEVEL 80 % DRUM LEVEL FSL INCHES ( )

VENT VLV POS C CONTAINMENT PRESS I8 PSI MSIV POS C CONT WATER LEVEL 578.5 FT OFF GAS - UNITS

~

ECS WATER LVL 100 % CRD PP DSCH - PSIG 138 kV AVAIL Y -

B/U CORE SPRAY 410 GPM CRD COOLING - GPM 46 kV AVAIL Y -

PRI CORE SPRAY 400 GPM CRD HEADER -

GPM EDG AVAIL Y -

B/U CONT SPRAY 0 GPM CRD COOLING - PSID 2B BUS EhT.RG Y -

PRI CONT SPRAY 150 GPM CR0 HEADER -

PSID -

DCWRM -

START-UP CHN - CPS COMt1ENTS/ PLANT STATUS:

RDS STATUS FIRED l , RESET OTIIER RX WATER LVL G COLOR DRUM LEVEL -79 INCHES FOR DRILL USE ONLY NUo488-01 TPII-TP07

%c/ \v

. e SCENARIO NO BREX.88 *IME . 1143 f

f MESSAGE NO 20 T= 0345 i

BIC ROCK POINT NUCLEAR PLAhi EMERGENCY PREPAREDNESS EXERCISE MESSAGE P0 g MESSAGE FOR: Shitt Supervisor / Control Roon Operator SIMULATED PLAh7 CONDTTIONS t See Data Sheet.

MESSAGE:

CONTROLLER USE ONLY

. t.

i 4

i NUO488-0113A-TP11-TP12

BREX 88 '

20 TIME: 1145 MESSAGE:

SCENARIO TIME: 0345 CORE SPRAY 90 PSIG RCP #I FIDW 0 GPM x 102 DRUM RV STATUS INSTRU AIR 95 PSIG RCP #2 FLOW 0 GPM x 103 WP DISCilG OPEN J SHUT 0 PSIG TURBINE INL -

PSIC COND DISCHG 0 PSIG _l CONTROL RODS (_

RX 1 6 57 PSIG 125 V DC BUS ENERG FDVTR TEMP R0 *F ALL IN J RX WATER FSH FEET Y ECS #I LOOP 110 *F ~

ECS #2 LOOP 115 *F NOTCFES OUT COND LEVEL E% W FIDW D lb/HR 103 CONDENSER VACUUM 0 inHg CST LEVEL C% STEAM FIDW 0 lb/HR 103 7_ _ f NST LEVEL 80 % DRUM LEVEL VENT VLV POS C FST, INCHES (})

CONTAINMENT PREF 3 174 PSI 6 MSIV POS C CONT WATER LEVE. 578.5 FT OFF GAS - UNITS

~

ECS WATER LVL 100 % CRD PP DSGH -

PSIG 138 kV AVAIL Y -

B/U CORE SPRAY 400 GPM CRD COOLING -

GPM 46 kV AVAIL Y -

PRi CORE SPRAY 400 GlH

~

CRD HEADER -

GPM EDG AVAIL Y -

B/U CONT E. 0 GIN CRD COOLING -

PSID 28 BUS ENERG Y -

PRI CONT SPRAY 150 GPM CRD HEADER -

PSID -

DCVRM -

START-UP CHN - CPS COMMENTS / PLANT STATUS:

RDS STATUS I FIRED _/ RESET OTilER RX WATER LVL G COLOR DRUM LEVEL +1 INCIIES FOR DRILL USE ONLY NUO688-Ol' TPil-TP07

w. % v) %d

SCENARIO NO BREX.88 71gg . 11$o MESSAGE NO 21 T= 0350 i

BIG ROCK POINT NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSAGE FOR: Shift Supervisor / Control Room Operator SIMULATED PLANT CONDITIONS: See Data Sheet.

MESSAGE:

CONTROLLER USE ONLY Drun level indicates +30. .

f

(

4 i

l I

l

!' NUO488-0113A.TP11-TP12 IG __ _ _ _ .

_BREX 88 TI!E: 1150 PtESSAGE: 21 SCENARIO TIPCt 0350 1

CORE SPRAY 90 MIC ' RCP #1 FLOW 0 GPft x 108 DRlM RV STATUS INSTRU AIR 95 P3IC RCP #2 FLOW 0 GPft x 103 OPEN / SIRTT

~

WP DISCHC 0 PSIG TURBINE INL -

PSIG COND DISCHG 0 PSIG

_l CONTROL RODS i_

RX PRESS 56 PSIG I25 V DC BUS ENERG FDVTR TEftP 80 *F ALL IN / RX WATER FSL FEET Y ECS #I IDOP 110 *F ECS #2 IDOP II5 *F NOTCHES OUT CONDENSER VACIRM COND E VEL 50 % W FLOW 0 Ib/NR 103 0 inMg CST EVEL 63 % STEAff FIDW 0 Ib/NR 10 8 l l DWST LEVEL 80 1 DRLM EVEL FSL INCHES (p)

VENT VLV POS C CONTAINMENT PRESS IS PSIG ftSIV POS C CONT WATER EVEL 578.5 FT OFF GAS - UNITS I -

ECS WATER LVL 100 % CRD PP DSGN -

PSIG 138 kV AVAIL Y -

B/U CORE SPRAY 400 GPft CRD COOLING -

GPf1 46 kV AVAIL Y -

PRI CORE SPRAY 400 GPff CRD HEADER -

CPft EDG AVAIL Y -

B/U CONT SPRAY 0 GPft CRD COOLING -

PSID 2B BUS F.NERG Y -

PRI CONT SPRAY 150 GPft CRD HEADER -

PSID -

DCWRf1 -

START-UP CHN - CPS COMffENTS/ PLANT STATUS:

RDS STATUS FIRED / RESET OTHER RX WATER LVL G COLOR DRUft EVEL +30 INCHES FOR DRILL USE ONLY NUO408-Oll' PIl-TP07 .

. ,V .

SCENARIO NO BREX-88 TIME = 1200

( MESSAGE NO 22 T= 0400 BIG ROCK POINT Nt' CLEAR PLAST EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSAGE FOR: Shif t Supervisor / Control Room Operator SIMULATED PLANT CONDITIONS: See Data Sheet.

't MESSAGE:

CONTROLLER USE ONLY s' -

k L

e ll L

NUO488-0113A-TP11-TP12

BREX 88 TIME: 1200 MESSAGE: 22 SCENARIO TIME: 0400 CORE SPRAY 90 PSIG RCP #1 FIDW 0 CPM x 103 DRUM RV STATits INSTRU AIR 92 PSIG RCP #2 FIDW 0 CPM x 103 OPEN 4 SHUT FVP DISCl!G 0 PSIG TURBINE INL -

PSIG _l CONTROL RODS l _

COND DISCHG 0 PSIC '

RI PRESS 54 PSIG 125 V DC BUS ENERG FDVTR TEMP 80 *F ALL IN J RX WATER FSL FEET Y ECS #1 IDOP - *F ECS #2 IAOP -

F NOTCHES OUT CONDENSER VACITC1 COND LEVEL 50 % FW FLOW 0 Ib/liR 10 3 0 inHg CST LEVEL 63 % STEAM FIEW 0 lb/HR 10 3 ] [

DWST LEVEL 80 % DRUM LEVEL FSL INCHES (g)

VENT VLV POS C CONTAINMENT PRESS 13 PSIL MSIV ISS C CONT WATER LEVEL 580 FT OFF GAS - UNITS ECS WATER LVL FSL % CRD PP DSCH -

PSIC 138 kV AVAIL Y -

B/U CORE SPRAY 400 GIM CRD COOLING -

GPM 46 kV AVAIL Y -

PRI CORE SPRAY 410 CPM CRD HEADER -

CPM EDG AVAIL Y -

B/U CONT SPRAY 0 CPM CRD COOLING -

PSID 2B BUS ENERG Y -

PRI CONT SPRAY 150 GIM CRD HEADER -

PSID -

DCWRM -

START-UP CHN - CIS cot 1MENTS/ PLANT STATUS:

RDS STATUS

, FITF.D / RESET OTHER RX WATER LVL G COLOR DRUM LEVEL +30 INCHES FOR DFILa,USE ONLY NUO488-O' -TPil-Trol

, . . N) y

%W

o .

(

SCENARIO NO BREX.88 TIME. = 1215 MESSAGE NO , 23 T= 0415 BIG ROCK POINT NUCLEAR PLAhi EMERGENCY PREPAREDNESS EXERCISE MISSAGE FORM

!ESSAGE FOR: Shift Supervisar/ Control Room Operator SIMULATED PLANT CONDITIONS: See Data Sheet.

MESSAGE CONTROLLER USE ONLY c

I f..

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4 9

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NUO488-0113A TP11-TP12

BREX 88 TIME: 1215 HESSAGE: 23 SCENARIO TIME: 0415 _ _ _

CORE SPRAY E0 PSIG RCP #1 FIJW -

GPM x 103 DRUM RV STATUS INSTRU AIR 94 PSIG RCP #2 FliM -

GPM x 103 FWP DISCilG 0 PSIG OPEN / SHUT TURBINE INL -

PSIG COND DISCHG 0 PSIG

'-l CONTkOL ROf6 l-RX PRESS 50 PSIG 125 V DC BUS ENERG FDWIR TEMP 80 *F ALL IN / RX WATER FSL FEET Y ECS #I LOOP - *F ECS #2 II)0P - *F NOTCHES OUT CONDENSER VACUUM COND 11 VEL 50 1 W FLOW 0 lb/HR 103 0 inHg CST LEVEL 6T % STEAM Fl/N O lb/HR 103 l [

DWST LEVEL 80 % DRUM LEVEL FSL INCHES ( )

VENT VLV POS C CONTAINMENT PRESS 10 PSI MSIV POS C CONT WATER LEVEL 583 FT OFF GAS - UNITS I

I

~

ECS WATER LVL FSL % CRD PP DSGH -

PSIG 138 kV AVAIL Y -

B/U CORE SPRAY 400 GIH CRD COOLING -

GPM 46 kV AVAIL Y -

PRI CORE SPRAY 400 GIM CRD HEADER -

GIH EDG AVAIL Y -

B/U CONT SPRAY 0 GlW CRD COOLING -

PSID 2B BUS ENERG Y -

PRI CONT SPRAY 150 GIM CRD HEADER -

PSID -

DCVRM -

START-UP CIIN - CIG COMMENTS / PLANT STATUS:

J RDS STATUS kIRED J _ RESET OTIIER RX WATER LVL G COIJ)R DRUM LEVEL +30 INCHES FOR DRILL USE ONLY CU0488-0Il' P11-TP07

.. 4d bs/

. o SCENARIO NO BREX-88 TIME = 1230 MISSAGE NO 24 T= 0430 BIG ROCK POINT NUCLEAR PLANT EMIRGENCY PREPAREDNESS EXERCISE ME3_SACE FORM KESSAGE FOR: Shif t Supervisor / Control Room Operator SIMULATED PLANT CONDITIONS: See Data Sheet.

HESSAGE:

CONTROLLER USE ONLY Operator should place containevnt sump on long-term cooling per SOP-8.

f' 4s . I i

+

.?

t NUO488-0113A-TP11-TP12

_ _ _ = _ - - - . -___ .. _ - - - . - . _ _ _ . __ - _. . <

BREX 88 Tile: 1230 MES3 AGE: 24 SCENARIO TIM: 0430 CORE SPRAY 80 PSIC RCP fl FIN -

GPft x 108 DRtNI RV STATUS INSTRU AIR 96 PSIG RCP #2 FI M -

GPM x 10 2 OPEN / SIRTT FVP DISCMG 0 PSIG TINtBINE INL -

PSIG ~l CONTROL RODS l~

COND DISCMG 0 PSIG RX PRESS 47 PSIC -Ili " DC BUS ENERG FIA/TR TEMP 80 *F ALL IN / RX WATER FSL FEET Y ECS #1 LOOP - *F ECS #2 Ih0P -

F NOTCIES Otfr COIRIENSER VACUIM COND LEVEL 50 % FW FIM 0 lb/NR 10 8 0 inIlg 8

LST LEVEL DWST LEVEL 63 80

% STEAM FIM O _ Ib/NR 10 l 7

% DittM LEVEL Q L ,INCIIES (p)

VENT VLV POS C CONTAINPENT FitESS 6 PSIG MSIV POS C CONT WATER LCVEL 587 FT OFF GAS - INIITS ECS WA1T.R LVL FS;. % CRD PP DSGil -

PSIG 138 kV AVAIL Y -

B/U CLNE SPltAY 410~ GPM CRD COOLIIIG - GPM 46 kV AVAIL Y -

j -

PRI C00tE SPRAY 410 GPM CRD NEADER -

GPM EDG AVAIL Y -

j R/U CONT SPRAY 0 GPM CRD COOLING - PSID 25 BUS ENERG Y -

J PRI CONT SPRAY ISO CPM CRD MEADER -

PSID -

i DCWRM -

i START-UP CNN - CPS CottttENTS/ PLANT STATUS:

l l

1 i

4 I RDS STATUS j

, FIRED. / RESET i GTHER l RX WATER LVL G COthdt

DRtRt LEVEL +30 INCIIES j FOR DRILL USE ONLY l -

l 1

CUO488-Oi! TPil-Tiv7 . s l

- - %) %W

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

9 O SCENARIO NO BREX-88 TIME = 1245 MESSAGE NO 25 T= 0445 BIG ROCK POINT NUCLEAR PLAhi EMERGENCY PREPAREDNESS EXERCISE MESSACE PORM l MESSAGE FOR: Shitt Supervisor / Control Room Operator i SIMULATED ?LANT CONDITIONS: See Data Sheet. !

MESSAGE:

CONTROLLER USE ONLY r Recycle established per SOP-8.

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NUO488-0113A-TP11-TP12 t-f

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

BREX 88 TIME: 1245 MESSAGE: 25 SCENARIO TIME: 0445 CORE SPRAY 90 PSIG RCP #I FLOW -

CIM x 103 DRUM RV STATUS INSTRU AIR 94 PSIC RCP #2 FLOW -

GPM x 10 2 OPEN ] SHITT FVP DIScilG _0 PSIG TURBINE INL -

PSIC COND DISCHG 0 PSIG

_l CONTROL RODS l_

RX PRESS 48 PSIG I25 V DC BUS ENERG FDVfR TEMP 80 *F ALL IN f RX WATER FSL FEET Y ECS #1 Ih0P - *F

ECS #2 LOOP -

"F NOTCHES OLTT CONDENSER VACUUM COND LEVEL 50 % FW FLOW 0 lb/HR 10 3 0 inlig CST LEVEL 63_ 1 STEAM FLOW D lb/HR 103 l l DWST LEVEL 80 % DRUM LEVEL VENT VLV POS C FSL INCHES ({}

CONTAINMENT PRESS 0 PSIG MSIV POS C CONT WATER LEVEL 589 FT OFF GAS - UNITS

~

ECS WATER LVL -

% CRD PP DSCH - PSIG 138 kV AVAIL Y -

B/U CORE SPRAY 0 CPM CRD COGLING - CIM 46 kV AVAIL Y -

PRI CORE SPRAY 350 GFM CRD HEADER -

CIM EDG AVAIL Y -

8 B/U CONT SPRAY 0 GPM CRD COOLING -

PSID 2B BUS ENERG Y -

g - PRI CONT SPRAY 0 GPM CRD HEADER -

PSID -

DCVRM -

START-UP C11N - CPS I .

COMMENTS / PLANT TATUS:

RDS STATUS I FIRED ] RESET i OTHER RX VATER LVL G COLOR DRUM LEVEL +30 INCHES FOR DRILL USE ONLY M10488-01 TPIl-TP07

\ v/ ,

O

o e SCENARIO NO BREX-88 __ TIMI = 1300

}ESSACE NC .:--

26 T= 0500 _,

,BIC ROC': POINT NUCLEAR PLAST EMERCENCY PREPAREDhTSS EXEaCISE MESSAGE FORM MESSAGE FOR: Shif t Supervisor / Control Room Operator SIMULATED PLANT CONDITIONS See Data Sheet.

MESSAGE:

C0h' TROLLER USE ONLY

1. Instruct players to close out notifications with offsite agencies at this time.

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BF.EX 88 HES3 AGE: 26 TIME: 1300 SCENARIO TI!E: 0500 CORE SPRAY 90 PSIC NCP #1 FIJN -

GIM x 103 DRLM RV STATUS INSTRU AIR 92 PSIG RCP #2 FIDW -

GPM x 103

}WP DISCHC 0 PSIG OPEN / SIRTT TUkBINE INL -

PSIC COND DISCHC 0 PSIG ~l CONTkOL RODS l~

RX PRESS 47 PSIG 125 V DC BUS ENERG FINTR TEMP 80 *F ALL IN /

ECS #1 IDOP - RX WATER FSL FEET Y

F ECS #2 LOOP - *F NOTCNES OUT COND LEVEL 50 CONDENSER VACUIM

% FV FLOW 0 lb/NR 108 'O CST LEVEL 63 1 inNg S1EAM FIDW Ib/NR 103 INST LEVEL 80 % DRIM LEVEL D

FSL_ INCHES (p)

~T _f VENT VLV POS C CONTAINMENT PRESS 0.5 PSIC j MSIV POS C CONT WATER LEVEL 589 FT OFF GAS - UNITS ECS WATER LVL -

1 CRD PP DSGM - PSIG 138 kV AVAIL T -

l -

B/U CORE SPRAY 0 Git CRD COOLING -

GIM 46 kV AVAIL Y -

PRI CORE SPRAY 3/,0_ GPM CRD HEADER -

GPM E3G AVAIL Y -

i t

B/U CONT SPRAY 0 GIM CRD COOLING -

PSID 28 BUS ENERG Y -

PRI CONT SPRAY 0 GIH CRD HEADER -

PSID -

DCWETI -

START-UP CHN - CPS COMMENTS / PLANT STATilS:

RDS STATUS FIRED J RESET OTHER RX WATER LVL G CDIDR DRUM LEVEL +30 INCNES FOR DRILL USE ONLY NUO488-01 TPIl-TP07

'%.) %d

SCENAR20 NO BREX.88 TIMI . 131$

MESSAGE NO 27 T= 0515

{

BIG ROCK POINT NUCLEAR PLAAT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSA 2 TOR: Control Room Operator /all players SIMULATED PLANT CONDITIONS: Exercise terminated except for personnel involved in reentry / recovery r MESSAGE: Announce exercise termination over plant public address.

C0hTROLLER USE OhlY

1. Instruct all players who are not participating in reentry / recovery to secure com=unications, exercise records and then conduct critique.

2. Provide Message 28 to reentry / recovery players.

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NUO488 0113A-TP11-TP12

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1715 MESSAGE NO 28 T=

\

0515

0915 BZG ROCK POINT NUCLEAR PLANT EMERCENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSAGE LOR: Reentry / recovery players SIML1ATED PLANT CONDITIONS: Tour hours have elapsed. See Data Sheet.

MESSAGE:

P CONTROLLER USE ONLY

1. Instruct players to develop reentt;/ recovery outlines.

2. Instruct players to conduct a planning coeting to close out exercise activity.

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NL'04 88-0113A-TP11-TP12

BREX 88 TIME: 1715 MESSAGE: 28 SCENARIO TIME: 0915 CORE SPRAY 90 PSIG RCP #1 FUN -

git x 103 DRiRf RV STATUS INSTRU AIR 94 PSIG RCP #2 FUN CIH x 103 WP DISCilG 0 PSIC OPCI / SHIIT TUR8INE INL -

PSIC l CONTROL RODS l COND DISC 11G 0 PSIG RX PRESS 47 PSIG 125 V DC BUS ENERG FINTR TEMP 80 *F ALL IN J RX VATER FSL FEET Y ECS #1 th0P - *F ECS #2 Ih0P - *F NOTCHES OUT CONDENSER VACUUM COND LEVEL 50 % FW FIA W 0 'b/HR 103 0 i

inHg CST LEVEL 63 % STEAM FUN O lb/HR 10 3 l l l'WST LEVEL 80 % DMUM LEVEL F VENT VLV POS C 1 INCRES (g)

CONTAINMENT PRESS O PSIL MSIV POS C CONT WATER LEVEL 589 FT OFF GAS - UNITS ECS WATER LVL -

% CRD PP DSGH - PSIG 138 kV AVAIL Y -

B/U CORE SPRAY 0 GIM CRD COOLING - GIH 46 kV AVAIL Y -

PRI CORE SPRAY 350 G"M CHD HEADER -

GIH EDG AVAIL Y -

B/U CONT SPFAY 0 GIH CRD COOLING - PSID 2B BUS ENERG Y -

PRI CONT SPRAY 0 Glw CRD HEADER -

PSID -

DCWRM -

START-UP CHN - CPS COMMENTS /PIANT STATUS:

RDS STATUS FIRED / RESET OTHER RX WATER LVL G COLOR DRUM EVEL +30 INCHES FOR DRILL USE ONLY NUO488-01l' PII-TP07

. . .. %J %d

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APPDiDIX C METEOROLOGICAL DATA

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MIO588-0062A-TP11

1 METEOROLOGICAL DATA BREX-83 07/19/S8 0800 15-Minute Averages Parameters STAB WS VD OIG Units PASQ hPH DEG DEG D 12.8 290 8.12 07/19/88 0815 15-Minute Av2 reges Parameters .cTAB WS WD SIG Units PASQ MPH DEG DEG D 9.4 272 9.40 07/19/88 0530 15-Minute Averages Parameters STAB WS WD SIG Units PASQ MPH DEO DEG E 13.0 270 6. 3.1 07/19/88 0845 15-Minute Aversees

f. Parameters STAB WS WD SIG e Units PASQ MPH DEG DEG E 17.8 281 5.62 07/19/88 0900 15-Minute Averages Parameters STAB WS WD SIG Units PASQ MPH DEG DEG D 12.8 290 8.12 07/19/88 0 'r 15 IS-Minute Averaget Parameters STAB WS VD SIG Units PASQ MPH DEG DEG D 9.4 271 9.40 07/19/88 0930 15-Minute Averages Parameters STAB WS WD SIG Units PASQ MPH DEG DEG E 13.0 270 6.33 07/19/88 0945 15-Minute Averaget Parameters STAB W3 WD SIG Units PASQ MPH DEG DEG E 17.8 281 5.62 MIC488-0268A-TP01-TP20

u 4 8 i

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!L METEOROLOGICAL DATA !

.BREX-88 {

l 07/19/88 1000 15-Minute Averages i Parameters STAB WS WD SIG- f Units PASQ. MPH DEG DEG !

a E 16.4 276 4.33 ;

M -- 07/19/88 1015 15-Minute Averages {

i Parameters STAB WS WD SIG !

!. Units PASQ MPF DEG DEG t E 15.2 278 3.95 t 07/19/88 1030 15-Minute Averages l Parameters STAB WS WD SIG !

Unitt PASQ FPH DEG DEG l E 14.9 278 4.14 l 1

07/19/88 1045 15-Minute Averages ;

Parameters STAB WS WD SIG

! /' Units PASQ MPH DEG DIG j

%e E 14.3 276 4.75 t I

j 07/19/88 1100 15-Minute Averages l Parameters STAB WS WD SIG [

Units PASQ MPH DEG DEG r E 17.0 271 4.16 I 1

t 07/19/88 1115 15-Minute Averages l

Faramettra STAB WS WD SIG ;

l Units PASQ MPH DEG DEG i

E 17.7 259 4.58 l t

07/19/33 - 1130 15-Minute Averages {

}

i- Pacaneters STAB WS WD SIG :

Units PASQ MPH DEG DEG [

i E 18.9 263 5.47 l

! l

! 07/19/88 1145 15-Minute Averages {

t Parameters STAB VS WD SIG f

! Units PASQ MPH DEG DEG !

j f F 20.7 269 3.07 l t t j i

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B.' TEX-&&

I 07/19/88 1200 15-Minute Averages 1

Parameters STAB VS WD Units $\G PAS MPH DEG DEG j E*Q 7.0. 6 271 4.31 i 07/19/88 1215 15-Minute Averages Parameters STAB WS WD SIG Units PASQ MPH DEO DEC ;

E 20.2 265 4.43 07/19/88 1230 15-Micute Averages i

t

' Parameters STAB VS WD SIG Units PASQ MPH DEG DEG !

J E 18.8 264 4.50 ;

l 3 07/19/88 1245 15-Minute Averages l Parasieters STAB WS j [ .. Units PASQ M?H WD DEC SIG DEG i

A- i F 20.4 272 2.37 l l' 07/19/88 1300 15-Minute Averages

?

! Parameters STAE WS WD SIG Units PASQ MPH DEG DEG !

E 19.3 263 4.77 !

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( BREX-88 Forecast Meteorological Data DY/HR 19/06 19/12 19/18 20/00 20/06 20/12 20/18 21/00 GMT DY/HR 19/01 19/07 19/13 19/19 20/01 20/07 20/13 20/19 EST WIND-MP 0202 C902 0804 1003 0000 0501 0503 1901 CLDS .1 0 0 0 0 0 3 3 7 HGT-TT > 7500 > 7500 > 7500 > 7500 > 7500 7050 > 7500 7500 PAS G B A C G B A C i

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1 MIo58s-0062A-trig

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{ MONITORS NUMBER LOCATION 1 Personnel Lock 2 Spent Tuel Storage 3 Condensor Access Area 4 Office Corridor 5 Air Compressor Room 6 New Tuel Storage 7 CR Drive Room 8 Condensate Demin Entrance 9 Shop Area 10 Control Room 11 Sphere EL 607 12 Sphere EL 582 13 Condensor Access Door 14 Laundry Roam 15 Exhaust Plenum 16 Locker Room 17 Turbine Shield Wall 18 Radwaste Control Entrance 20 & 21 Emerg. Cond. Vent Hon.

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R r

p MIO588-0062A-TP11

, [1 1 t

s.

d 0,FTSITE RADIOLOGICAL DATA In this scenario, there is no offsite release of radiation. The reasons are as follows:

1. Core damagn is limited to 1%; therefore, the inventory concentration of radionuclides is relatively small.

2. Containment is not breached. Release rates were calculated using actual containment leak rate and Technical Specifications containment leak rate.

In both cases, dose rates and iodine concentrations were below detectable limits using the given meteorology.

Offsite teams located at the site boun6ary at US-31 and beyond will only receive background readings for dose rates, iodine concentration and partic-ulates. Surveys on the access road will increare as the team moves toward the plant. Controllers should give readings based on onsite out-of plant maps.

i s

4 l

l l

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r RP0588-228A-TP01 I

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k 9

i MIO588-0062A-TPl l

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?

BREX-88

- - - - 19 - JUL - 88 ***************

- - - - +*****w* *********

Post-Accident Sampling Sample Collection Start Date: 19 - JUL - 88 00:00:00 Sample Collection End Date: 19 - JUL - 88 00:00:00 Sample Identification: NA Type of Saeple: NA Units: Mi*iiliters Sample Quantity: Reactor No: 1 Percent Yield: 100.00000 Operator's initials:

Efficiency File Nams: EFF .RWI 12

- - - - +******************************

Acquire Date: 19 JUL - 88 00:00:00

FVHM (1332): 1.900 Presit Time (Live): 1000 See

Sensitivity: 5.000 Elapsed Real Time: 1007 See

Shape Parameter: 10%

Elapsed Live Time: 1000 See

NBR Iterations: 10

/-

\

Detector: IGD No 1

Libra ry: LIB . LIQ Calib Date: 00 - XXX - 88 00:00:00

Energy Tolerance: 1.300 kV kev /Chal: 0.5001560

Half-Life Ratio: 8.00 Offsit: -0.2113142 kev

Abundance Limit: 75.00%

Q Coeff: -2.983 E-08 kev /C**2

a M10488-0263D-TP01

f, T ,

t I'

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BREX-88

' NUCLIDE IDENTIFICATION SYSTEM (Rev 8/81)

SUMMARY

OF NUCLIDE' ACTIVITY Total Lines in Spectrum

, Lines Not Listed in Library: 20 Identified in Summary idport J Activation Product 4

i 1-Sigma Nuclide SBHR Half-Life _ Decay UCI/ Unit Error % Error CR-51 AP 27.70D 1.003 3.3E-3 1.391E-4

' CO-60 5.51 AP. 5.27Y 1.000 9.832E-5 1 746E-5 17.75

, NA-24 AP 15.00H 1.156 2.476E-3 4.548E-f 2.71 MN-56 AP 2.58H 2.326 1.732E-3 5.224E-5 4.77 .

Halonen Fission Product 1-Sigma Nuclide SBHR Half-Life Decay UCI/ Unit Error, % Error I-133 HIP 20.80H 1.110 3.161E-7 2.637E-5 2.31

(+ I-135 2-131 HFP KTP 6.61H S.04D 1.390 1.390 1.901E+1 1.305E-4 5.09 2.441E+1 1.488E-5 17.15 7-132 HFP 2.30H 2.578 3.741E0 8.102E-5 3.01 I-134 KFP 52.60M 11.977 9.282E-2 4.067E-2 7.01 '

]. Fission Product 1-Sigma t

. Nuclide SBKR Half-Life Decay UCI/ Unit Error % Error SR-92 FP 2.71H 2.234 1.106E-3 6.980E-5 4.36 s MO-99 FP 66.00H 1.034 5.119E-3 3.091E-5 0.63 i CS-136 FP 13.00D 1.004 1.502E-2 5.22E-5 4.77 i BA-140 FP 12.800 1.003 7.940E-1 2.637E-5 2.31 :

LA-140 FP 40.23H 1.014 8.5'1E-1 J 4.067E-2 7.01 l CE 141 -FP 32.53D 1.002 8.411E-1 1.746E-5 17.76 CS-134 FP 2.90H 2.415 3.321E-2 1.305E-4 5.09 CS-137 !

FP 30.20Y 1.000 6.112E-2 8.102E-5 17.15

CS-138 FP 32.2M 1.000 1.931E-3 4.548E-5 2.71 2R-95 FP 65.50D 1.005 7.934E-1 1.391E-4 5.51 i NM 95 FP 87.00H 2.513 8.059E-1 1.488E-5 17.15 i I

t. .

MIO488-0268B-TP01 t

_ _ .___. _ _ . _ _ , _ _ _ _ _ __ _ _ . _ _ _ . _ _ . . , ~ , . _ , . _ _ _ . _ . _ _ _ _ - . . _ _ _ _ _ . _ _ -

} v CORE SPRAY ROOM (RM 427)

k. .

CORE SPRAY PUMP o .

C X 900 mR/hr CORE SPRAY PUMP SAMPLE POINT 3.5 R/hr VP-111 CORE SPRAY HEAT EXCHANGER P

(-

BREX 88 1700

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CORE SPRAY ROOM (RM 427)

[ --

CORE SPRAY PUMP C X 875 mRlhr CORE SPRAY PUMP SAMPLE POINT 3.5 R/hr

, VP-111 ,_

CORE SPRAY HEAT EXCHANGER ,

""is .

f Y CORE SPRAY ROOM (RM 427)

(

1 CORE SPRAY PUMP

( X 850 mR/hr CORE SPRAY .

PUMP SAMPLE POINT 3.4 R/hr VP-111 CORE SPRAY HEAT EXCHANGER -

1 l s' . [

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BREX E8 1730

r r CORE SPRAY ROOM (RM 427)

{

i i

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CORE SPRAY PUMP

{ X 825 mRlbr CORE SPRAY PUMP SAMPLE POINT 3.3 R/hr VP-111 CORE SPRAY __

HEAT EXCHANGER I

BREX 88 1745

f f, CORE SPRAY ROOM (RM 427)

(%

b CORE SPRAY ;

PUMP 1

ll L

X 800 mR/hr t

CORE SPRAY PUMP SAMPLE POINT 3.2 R/hr !

VP 111 ,,

j CORE SPRAY !

HEAT EXCHANGER t

BREX 88 1800 l

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