ML20070C161

1994 Palisades Emergency Exercise Scenario

ML20070C161
Person / Time
Site:	Palisades
Issue date:	05/06/1994
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18059B079	List: ML20070C161
References
NUDOCS 9407050051
Download: ML20070C161 (376)

Text

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y-4 SCOPE AND OBJECTIVF3 EXERCISE CONDUCT EXERCISE ORGANIZATION CONTROLLER ORGANIZATION EXERCISE DATA AND MESSAGES CRITIQUES EVALUATOR CHECKLISTS EXERCISE DATA SEQUENCE OF EVENTS NARRATIVE

SUMMARY

MESSAGE SHEETS i CFMS OPERATIONS DATA CFMS RADIATION DATA RAD MONITOR DATA INPLANT RADIATION DATA ONSITE RAD DATA OFFSITE RAD DATA CFMS METEOROLOGICAL DATA WSIFORECAST WSI HOURLY METEOROLOGICAL DATA -

ONSITE MET TOWER

• 1. 188u 74888!ss F PDR

O SCOPE AND OBJECTIVES l

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PALEX-94 SCOPE AND OBJECTIVES i

.O SCOPE PALEX-94 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 Emergency Plan and response by State and local governments. The j exercise will include participation by Allegan County, Berrien County, Van Buren County i and the State of Michigan. The State of Michigan will demonstrate ingestion pathway

, planning for the Federal Emergency Management Agency. The Joint Public Information Center will be activated during the exercise.

OBJECTIVES The following objectives will be demonstrated as dictated by the exercise scenario.

! 1. Assessment and Classification

a. Assess conditions which warrant classification within fifteen minutes of being

provided those conditions.

b. Classify posed conditions in accordance with Emergency Action Levels within fifteen minutes of determination that conditions warrant classification.

O 2. Communications

. a. Upon making an emergency classification, complete initial notifications within fifteen minutes to the State and locals and within one hour to the NRC using the Notification form, i

b. Complete subsequent notifications to the State, locals, and NRC on a routine fifteen minme basis or as mutually agreed.

. c. Contact other organizations such as contractors, utilities, fire or medical support l within one hour of recognizing that conditions exist that warrant their assistance.

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d. Provide accurate press release information on plant conditions within one hour after occurrence.

c. Provide updates between appropriate Emergency Response Facilities at least every 30 minutes.

4 l 3. , Radiological Assessment and Control m

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c etiect. ixze. aece m e t 8 1reeo r oieie8 icei ervex 8 ate.

a. Collect, analyze, document and trend radiological survey data.

b. Analyze plant radiological conditions and implement protective actions for site personnel in accordance with procedures.

c. Prepare and brief personnel for activities required in high radiation areas.

d. Monitor, track and document radiation exposure to maintenance, operations, and monitoring team personnel.

e. Calculate dose projections based on sample results or monitor readings.

, f. Identify appropriate protective action recommendations.

g. Perform environmental monitoring in accordance with procedures and as directed by the Controller.

4. Emergency Response Facilities

a. Staff and activate onsite Emergency Response Facilities within approximately 30 minutes of an Alert classi5 cation.

b. Staff and activate the Emergency Operations Facility within about an hour of the Site Area Emergency declaration,

c. Update status boards at least every 30 minutes.

d. Document field team activities in logs and on appropriate status boards.

e. Track and prioritize status of key in plant jobs.

5. Direction and Control

a. Command and control all Emergency Response Facilities in accordance with assigned functions.

b. Coordinate maintenance activities,

c. Take appropriate measures to secure emergency equipment, supplies, and support.

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d. Dispatch field teams in accordance with procedures. l l

e. Direct and monitor field team actions.

f. Transfer Command and control in accordance with the Site Emergency Plan.

p g. Perform accountability within approximately 30 minutes of the Alert tg classification.

h. Control site access and site evacuation as directed.

i. Brief Emergency Response Facility staffs approximately every 30 minutes on changes in plant status, emergency classification, field team progress, and offsite actions as appropriate.

j. Effectively coordinate with State and local governments as appropriate.

k. Demonstrate reentry and recovery in accordance with procedures.

6. Exercise Control

a. Allow adequate free play for players to demonstrate their capabilities.

b. Accurately assess performance of exercise players and controllers.

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EXERCISE CONDUCT O

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2.0 EXERCISE CONDUCT

! 2.1 EXERCISE ORGANIZATION The exercise organization is comprised of Controller / Evaluators, Players and Observers.

Controller / Evaluator; observe player activities and judge the effectiveness of Player actions based on Evaluator Checklists in section 2.6. Each CPCo Controller / Evaluator must submit a completed, signed Evaluator Checklist at the conclusion of the exercise. NRC evaluators will also be present for the exercise.

Selected Controller / Evaluators provide messages and exercise data to players and ensure that the exercise proceeds in accordance with the Sequence of Events.

Controller / Evaluators are authorized to modify scenario data as judged appropriate. However, every attempt must be made to contact a Lead Controller or the Exercise Coordinator before doing so. If data is modified without approval, the Controller / Evaluator involved is required to notify his/her Lead Controller as soon as possible. ,

Controller / Evaluators are authorized to prompt players, but again should make every effort to discuss the situation with the Lead Controller before doing so. If a 3

player must be prompted, it must be noted during the critique following the exercise.

, Observers may be present at any location where exercise activities may occur.

Observers are not allowed to converse with exercise players unless approved by the Controller / Evaluator in charge.

Players include all personnel responding to simulated emergency conditions.

2.2 CONTROLLER ORGANIZATION The Exercise Coordinator is in charge of overall exercise conduct.

Responsibilities include conducting preexercise Controller / Evaluator training sessions, the NRC Entrance, joint critiques, and the NRC Exit; approving major scenario deviations; resolving exercise questions; and terminating the exercise.

A Lead Controller is assigned to each Emergency Response Facility and is responsible for addressing Player inquiries, conducting a post exercise critique, and collecting completed Evaluator Checklists following the exercise.

Controller / Evaluators will refer all Player inquiries to the Lead Controller if possible. If the Lead Controller is not able to answer the question, it should be referred to the Exercise Coordinator.

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2.3 EXERCISE DATA AND MESSAGES Messages and data to drive Player actions are contained in Section 3, Exercise 4

Data. Refer to the Table of Contents for headings.

It is each Controller / Evaluator's responsibility to be fully familiar with the scenario package and ensure that only appropriate information is provided to Players.12ading questions and hints are not allowed at any time. If con 5dential scenario information must be provided to a Player, it must be formally noted in the critique that the Player -

was prompted.

2.4 EXERCISE GROUND RULES

1. Perform all actions without simulation to the maximum extent possible. This includes acting as if radiation is actually present, donning anti-C's, and minimizing radiation exposure. Simulation is not allowed unless your Controller / Evaluator has authorized simulating a specific action. If authorized to simulate, you should explain to the Controller / Evaluator how the task would be accomplished.

! 2. Although it may seem ardficial, speak out loud to identify your actions and decisions tr Controller / Evaluators. This will assist in the evaluation process.

3. Be aware of CPCo Controller / Evaluators and NRC Evaluators in your area.

4. Whenever a Controller / Evaluator provides a message or data, accept it for

face value. If you do not understand a message or any Controller / Evaluator j provided information, ask for clarification. Exercise data is intended to be clear and straight forward. Scenario developers will never provide data that

intentionally misleads Players.

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! 5. If your Controller / Evaluator asks you a question or provides directions, you -

l should answer or comply as appropriate. If you think he/she is in error, feel free to discuss your concerns. _You must, however, accept his/her word as i final with respe:t to scenario related matters.

l 6. Observe all rules and procedures when entering radiation areas. No one is

! exempt from normal station radiological practices and procedures.

) 7. Demonstrate your knowledge of emergency operations and procedures. Use status boards, logs, and message forms to document your actions and instructions from other Players. This will assist in event reconstruction.

8. Keep your focus on the exercise. Unrelated conversations detract from your performance.

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9. If an NRC Evaluator asks you a question, you should answer to the best of your knowledge or refer the question to your Team leader.

10. At the conclusion of the exercise there will be a critique. Team Leaders will be asked for suggestions and comments. Make sure that your comments are known to your Team Leader.

2.5 CRITIQUES Following the conclusion of the exercise, each Lead Controller will conduct a critique in the Emergency Response Facility where he/she is assigned. Each Team Leader, Director, and Controller / Evaluator shall be asked for comments during the critique. NRC evaluators are expected to attend.

1 Following Facility Critiques, a Joint Critique will be conducted with each lead Controller presenting findings. Players and NRC evaluators are welcome to attend.

Following the Joint Critique, the NRC will conduct an Exit Meeting. The NRC will verbally present its preliminary findings at this time. This is the only opportunity to comment on NRC observations before the formal exercise report is 2

published. If anyone has a question, this is the time to ask.

l 2.6 EVALUATOR CHECKLISTS The checklists provided in the following section are used in gauging effectiveness of Player response. Checklists are cross referenced to exercise objectives to ensure that Player and Controller / Evaluator actions have accomplished exercise objectives.

Each Controller / Evaluator shall submit a completed, signed, and dated checklist at the conclusion of the exercise. Problems shall be fully explained on the completed checklist.

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CONTROL ROOM EVALUATOR CHECKLIST

1. ASSESSMENT AND CIASSIFICATION OVERALL- MET NOT MET

a. Assess conditions which warrant classification within fifteen minutes of being provided those conditions.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

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b. Classify posed conditions in accordance with Emergency Action Imvels within fif teen minutes of determination that conditions warrant i

i O classification, MET MET / PROBLEM NOT MET N/A EXPIANATION:

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2. ColotUNICATIONS OVERALL: MET NOT MET

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O a. Upoa making an emergency classification, complete initial no ifications within fifteen minutes to the State and Locals and w! thin one hour to the NRC using the Notification Form.

1 Mn MET / PROBLEM NOT MET N/A CCPLANATION:

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b. Complete subsequent notifications to the State, locals, and NRC on a routine fifteen minute basis or as mutually agreed.

MET MET / PROBLEM NOT MET N/A EXPLANATION:

c. Contact other organizations such as contractors, utilities, fire or medical support within one hour of recognizing that conditions exist that warrant their assistance.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

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d. Provids updates betvsan appropriate Emargancy Rospsnse Fccilition at least every 30 minutes.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

3. RADIOLOGICAL ASSESSMENT AND CONTROL OVERALL: MET NOT MET

c. Prepare and brief personnel for activities required in high radiation areas.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

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4. EMERGENCY RESPONSE FACILITIES OVERALL: MET NOT MET

a. Staff and activate onsite Emergency Response Facilities within approximately 30 minutes of an Alert classification.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

i b. Staff and activate the Emergency Operations Facility within about an hour and a half of the Site Area Emergency declaration.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

e. Track and prioritize status of key inplant jobs.

MET MET / PROBLEM NOT MET N/A i

EXPIANATION:

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5. DIRECTION AND CONTROL OVERALL: MET NOT MET

a. Command and control of Emergency Response Facilities in accordance with assigned functions.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

b. Coordinate maintenance activities.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

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c. Take appropriate measures to secure emergency equipment, supplies, and support.

MET MET / PROBLEM NOT MET N/A i

EKPIRIATION-9 l.

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f. Transfer Conusand and Control in cecordancs with tha Sits Easrgsney Plan.

MET MET /PROBIIM NOT MET N/A EXPIANATION:

h. Brief Emergency Response Facility staffs approximately every 30 minutes on changes in plant status, emergency classification, field team progress, and offsite actions as appropriate.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

i. Effectively coordinate with state or local governments as appropriate.

MET MET / PROBLEM NOT MET N/A EXPLANATION:

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6. EXERCISE CONTROL ,

I OVERALL: MET NOT MET

a. Allow adequate free play for players to demonstrate their capabilities.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

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b. Accurately assess performance of exercise players and controllers. (

l MET MET / PROBLEM NOT MET N/A EXPIANATION:

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c. Adequacy of scenario data.  !

MET MET / PROBLEM NOT MET N/A EXPIANATION:

Name: Date:

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TSC EVALUATOR CHECKLIST

1. ASSESSIGNT AND CIASSIFICATION OVERALL: MET NOT MIT

a. Assess conditions which warrant classification within fifteen minutes of being provided those conditions.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

O b. Classify posed conditions in accordance with Emergency Action Levels within fifteen minutes of determination that conditions warrant classification.

MET MET / PROBLEM NOT MET N/A EXPLANATION!

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2. COMMUNICATIONS l

OVERALL: MET NOT MET j

O a. Upon making an emergency classification, complete initial  !

notifications within fifteen minutes to the State and Locals within one hour to the NRC using the Notification Form. ,

l NOT MET MET MET / PROBLEM N/A EXP!ANATION t

b. Complete subsequent notifications to the State, locals, and NRC on a routine fif teen minute basis or as mutually agreed.

MET MET / PROBLEM NOT MET N/A EXPLANATION:

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c. Contact other organizations such as contractors, utilities, fire or medical support within one hour of recognizin5 that conditions exist that warrant their assistance.

MET MET / PROBLEM NOT MET N/A EXPLANATION:

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d. Previda updatas batvasn apprcpricts Emargsncy Rstpensa Facilitisa et least every 30 minutes.

(g KET MET / PROBLEM NOT MET N/A EXPIANATION:

3. RADIOLOGICAL ASSESSMENT AND CONTROL OVERALL: MET NOT MET

a. Collect, analyze, document and trend radiological survey data.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

b. Analyze plant radiological conditions and implement protective actions for site personnel in accordance with procedures.

MET MET / PROBLEM NOT MET N/A EXPLANATION:

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e. Calculate dose projections bcsad on sample results or tonitor readings. ]

1 MET MET / PROBLEM NOT MET N/A EXPIANATION - I l

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f. Identify appropriate protective action reconnnendations.

MET MET / PROBLEM NOT MET N/A p EXPIANATION:

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4. EMERCENCY RESPONSE FACILITIES OVERALL: MET NOT MET f^s

a. Staff and activate onsite Emergency Response Facilities within approximately 30 minutes of an Alert classification.

MET MET / PROBLEM NOT MET N/A EXPLANATION:

e. Update status boards at least every 30 minutes.

MET MET / PROBLEM NOT MET N/A FXPIANATION:

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e. Track and prioritize status of key inplant jobs.

MET MET / PROBLEM NOT MET N/A EXPLANATION:

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5. DIRECTION AND CONTROL OVERALL: MET NOT MET

a. Command and control of Emergency Response Facilities in accordance with assigned functions.

MET MET / PROBLEM NOT MET N/A EXPLANATION:

j c. Take appropriate measures to secure emergency equipment, supplies, and

] support.

MET MET / PROBLEM NOT MET N/A i

j EXPLANATION:

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d. Dispatch field teams in accordance with procedures.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

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e. Direct and monitor field team actions.

MET MET / PROBLEM NOT MET N/A .

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f. Trensfer Command and control in accordance with tha Sits Emargsney Plan.

MET MET / PROBLEM NOT MET N/A O EXPIANATION:

g. Perform accountability within approximately 30 minutes of the Alert classification.

MET MET / PROBLEM NOT MET N/A

< EXPLANATION:

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h. Brief Emergency Response Facility staffs approximately every 30 minutes on chan5es in plant status, emergency classification, field O team progress, and offsite actions as appropriate.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

1. Effectively coordinate with state and local governments as appropriate.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

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6. EIERCISE CONTROL OVERALL: MET NOT MET

a. Allow adequate free play for players to demonstrate their

capabilities.

MET MET / PROBLEM NOT MET- N/A EXPIANATION:

b. Accurately assess performance of exercise players and controllers MET MET / PROBLEM NOT MET N/A.

EXPIANATION:

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, c. Adequacy of scenario data.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

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OSC EVALUATOR CHECKLIST j

2. COMMUNICATIONS OVERAll: MET NOT MET

d. Provide updates between appropriate Emergency Response Facilities at least every 30 minutes.

MIT MET / PROBLEM NOT MET N/A EXPLANATION:

1

3. RADIOLOGICAL ASSESSMENT AND CONTROL

, OVERALL: KET NOT MET

a. Collect, analyze, document and trend radiological survey data.

MET MET / PROBLEM NOT MET N/A EXPLANATION:

c. Prepare and brief personnel for activities required in high radiation areas.

MET MET / PROBLEM NOT MEY N/A EXPLANATION:

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d. Monitor, track and documsnt r:diaticn exposure to maintenanco, operations, and monitoring team personnel.

MET MET / PROBLEM NOT MET N/A f"

EXPIANATION:

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4. EMERGENCY RESPONSE FACILITIES

OVERALL

MET NOT MET

a. Staff and activate onsite Emergency Response Facilities within approximately 30 minutes of an Alert classification.

MET MET / PROBLEM NOT MET N/A J

J EXPLANATION:

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c. Update status boards at least every 30 minutes MET MET / PROBLEM NOT MET N/A EXPLANATION:

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d. Decument field team cetivitics in leg.s and en cpprcprints status boards. l 1

MET MET / PROBLEM NOT MET N/A EXPIANATION: i 1

.I j e. Track and prioritize status of key inplant jobs, i

MET MET / PROBLEM NOT MET N/A i -

EXPLANATION!

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5. DIRECTION AND CONTROL OVERALL: MET NOT MET

a. Command and control all Emergency Response Facilities in accordance with assigned functions.

MET MET / PROBLEM NOT MET N/A EXPLANATION:

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b. Ccordinate caintenance activities.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

e. Take appropriate measures to secure emergency equipment, supplies, and support.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

d. Dispatch field teams .in e:.cordance with procedures.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

e. Direct and monitor field team actions.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

g. Perform accountability within approximately 30 minutes of the Alert classification.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

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h. Brief Emsrgency Response Facility staffs approximately avary 30 minutes on changes in plant status, emergency classification, field team progress, and offsite actions as appropriate.

r 1 MET MET / PROBLEM NOT MET N/A EXPLANATION:

6. EXERCISE CONTROL OVERALL- MET NOT MET

a. Allow adequate free play for players to demonstrate their capabilities.

MET MET / PROBLEM NOT MET N/A EXPLANATION:

O b. Accurately assess performance of exercise players and controllers.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

c. Adequacy of scenario data.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

Name: Date:

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RMT EVALUATOR CHECKLIST

2. COMMUNICATIONS OVERALL: MET NOT MET i

d. Provide updates between appropriate Emergency Response Facilities at least every 30 minutes.

MET MET / PROBLEM NOT MET N/A EXPLANATION:

3. RADIOLOGICAL ASSESSMENT AND CONTROL t OVERALL' MET NOT MET -

a. Collect radiological survey data.

MET MET / PROBLEM NOT MET N/A EXPLANATION:

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d. Monitor, track and docunant radiatien exposura to monitoring team

. personnel.

MET MET / PROBLEM NOT MET N/A O

i EXPIANATION:

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g. Perform environmental monitoring in accordance with procedures.

4 MET MET / PROBLEM NOT MET N/A EXPIANATION:

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5. DIRECTION AND CONTROL OVERALL: MET NOT MET i

h. Brief Emergency Response Facility staffs approximately every 30 minutes on changes inplant status, emergency classification, field team progress, and offsite actions as appropriate.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

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6. EXERCISE CONTROL OVERALL: MET NOT MET i

a. Allow adequate free play for players to demonstrate their capabilities.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

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b. Accurately assess performance of exercise players and controllers.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

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c. Adequacy of scenario data.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

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PAGE 3 0F 3 C/ ' Name: Date:

EOF EVALUATOR CHECKLIST O 1. ASSESSMENT AND CIASSIFICATION V NOT MET 0_VERALL- MET

a. Assess conditions which warrant classification within fifteen minutes of being provided those conditions.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

b. Classify posed conditions in accordance with Emergency Action Levels within fifteen minutes of determination that conditions warrant classification.

MET MET / PROBLEM NOT MET N/A O EXPIANATION:

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2. C010fDNICATIONS OVERALL: MET NOT MET

a. Upon making an emergency classification, complete initial notifications within fifteen minutes to the State and Locals and within one hour to the NRC using the Notification Form.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

PACE 1 0F 8

_ __ _ . . _ _ . . . . . . . . . . _ . . _ = . . . _ ~ _ , . _ . _ . .

b. Ccaplete subsequant notifications to the Stats, locals, and NRC on a

. routine fifteen minute basis or as mutually agreed.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

c. Contact other organizations such as contractors, utilities, fire or medical support within one hour of recognizing that conditions exist that warrant their assistance.

. MET MET / PROBLEM NOT MET N/A EXPLANATION

d. Provide' accurate press release information on plant conditions within i one hour after occurrence.

MET MET / PROB 12M NOT MET N/A EXPIANATION:

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e. Provide updates between appropriate Emergency Response Facilities at j least every 30 minutes.

MET MET / PROBLEM NOT MET N/A EXPIANATI0f_;.

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3. RADIOIDGICAL ASSESSMENT AND CONTROL OVERALL: MET NOT MET O a. Collect, analyze, document and trend radiological survey data.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

d. Monitor, track and document radiation exposure to monitoring team personnel.

MET MET / PROBLEM NOT MET N/A a

EXPIANATION: ,

e. Calculate dose projections based on sample results or monitor readings.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

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i l f. Idsntify appropriate protective action recommendations.

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j- MET MET / PROBLEM NOT MET N/A 1

EXPIANATION:

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g. Perform environmental-monitoring in accordance with procedures.

MET MET / PROBLEM NOT MET N/A.

f EXPIANATION:

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4 EMERGENCT RESPONSE FACILITIES OVERALL: MET NOT MET O b. Staff and activate the Emergency Operatio'ns Facility within about an hour and a half of the Site Area Emergency declaration.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

a

c. Update status boards at least every 30 minutes.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

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d. Document field team activities in logs and on appropriate status boards.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

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f S. DIRECTION AND CONTROL OVERALL: MET NOT MET

a. Command and control all Emergency Response Facilities in accordance with assigned functions.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

c. Take appropriate measures to secure emergency equipment, supplies, and support.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

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e. Direct and monitor field team actions.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

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PAGE 6 0F 8

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f. Transfer Command and control in accordance with tha Sita Emirgsney Plan.

4 MET MET / PROBLEM NOT MET N/A EXPIANATION:

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, h. Brief Emergency Response Facility staffs approximstely every 30

minutes on changes in plant status, emergency classification, field team progress, and offsite actions as appropriate.

MET MET / PROBLEM NOT MET N/A

, EXPLANATION:

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1. Effectively coordinate with state and local governments as

-appropriate.

MET MET / PROBLEM NOT MET N/A 4

EKPIANATION:

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PAGE 7 OF 8'

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6. EIERCISE CONTROL OVERALL' MET NOT MET O a. Allow adequate free play for players to demonstrate their.

capabilities.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

b. Accurately assess performance of exercise players and controllers.

MET MET / PROBLEM NOT MET N/A EXPLANATION:

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c. Adequacy of scenario data.

MET MET / PROBLEM NOT MET N/A l

EXPLANATION:

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PAGE 8 of 8 I

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

A JPIC EVALUATOR CHECKLIST

2. COMMUNICATIONS OVERALL- MET NOT MET

d. Provide accurate press release information on plant conditions within one hour after occurrence.

MET MET / PROBLEM NOT MET N/A EXPIANATION:

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e. Provide updates between appropriate Emergency Response Facilities at least every 30 minutes.

MET MET / PROBLEM NOT MET N/A EXPLANATION:

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5. DIRECTION AND CONTROL OVERALL: MET NOT MET

1. Effectively coordinate with state and local governments.as appropriate.

l NET MET / PROBLEM NOT MET N/A

. EXPLANATION:

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6. -EXERCISE CONTROL OVERALL: MET NOT MET E

a. Allow adequate free play for players to demonstrate their 1 capabilities.

MET MET / PROBLEM NOT MET N/A

] EXPLANATION:

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b. Accurately assess performance of exercise players and controllers.

MET MET / PROBLEM NOT MET N/A EXPIANATION i

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c. Adequacy of scenario data.

1 MET MET / PROBLEM NOT MET N/A EXPIANATION:

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i Name: Date:

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PAGE 2 of 2 l

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O SEQUENCE OF EVENTS l

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1 SCENARIO

SUMMARY

PALEX-94 involves a prolonged loss of Shutdown Cooling, substantial fuel damage, and breach of Containment. A release to the environment occurs.

The Control Room simulator will be used and run in real time mode. Backup plant conditions have been prepared and will be used if needed.

SEQUENCE OF EVENTS:

-0030/0800 Initial conditions are provided to players:

The plant is in Cold Shutdown at the end of core life. The Reactor head is removed and Reactor cavity seal installed.

Nozzle dams are installed in both Steam Generators with primary side manways removed. Several Containment openings exist.

Equipment degraded /out of service:  ;

Primary Coolant System Containment Spray Pump P-54A Component Cooling Water Heat Exchanger E-54A Charging system Switchyard ABB 27R8 Diesel Fire Pump P-98 1

Normal shutdown alarms are annunciated.

0000/0830 The exercia begins when 2400VAC Breaker 152-105 supplying i Bus IC from Safeguards Transformer 1-1 developes a phase-to- j O phase short and explodes. All 2400 VAC vital power is lost, resulting in a loss of Shutdown Cooling. An " ALERT" should be i

decl ared.

0015/0845 Steam Generator "A" hot and cold leg nozzle dams fail.

0020/0850 2400 VAC Bus ID is repowered from 1-2 Diesel Generator.

0100/0930 Boiling begins in the Reactor Vessel; expanding coolant is lost to the Containment Sump via S/G "A" primary manways. Site Emergency Plan activation should be complete by this time.

0130/1000 Containment temperature and humidity rise as PCS boils off and escapes via any open penetrations. Site Emergency Plan classification should be upgraded to " SITE AREA EMERGENCY" g hiaher.

0215/1045 Fuel uncovery begins and fuel damage commences. Sito Emergency Plan classification upgraded to " GENERAL EMERGENCY" if not performed prior.

0315/1145 Severe core degradation has occurred; a large amount of hydrogen gas has been generated. A hydrogen " burn" in containent pressurizes the building and expells any water seal existing in the Fuel Transfer Tube. Fuel Handling Building l filter banks saturate, and a continuous plume release commences O

I from the plant stack.

0415+/1245+ Time jump to new plant conditions, recovery planning begins.

Players not involved in recovery planning begin critiques.

0630/1500 Recovery planning .is completed; the exercise is terminated.

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--+u- - - - - - -

O NARRATIVE

SUMMARY

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NARRATIVE

SUMMARY

1 0800 (-0030)

O A. The plant is in Cold Shutdown at the end of core life. The Reactor has (v) been shutdown for 11 days; the Reactor head is removed and the Reactor cavity seal is installed and tested. Preparations are in progress to install the Upper Guide Structure lift rig and perform incore detector removal prior to a full core offload for Reactor Vessel beltline weld inspections. Operators are currently performing shift turnover and conducting pre-job briefings.

B. The Equipment Hatch is open with several temporary service lines running through it to Containment; the Personnel Airlock door interlock is defeated and both doors are open. The Fuel Transfer tube is open; the isolation valve on the Spent Fuel Pool side of the Fuel Transfer Tube has been broken for many years and is not capable of closure. Hot and cold leg nozzle dams are installed in both Steam Generators, and the secondary side of each S/G is dry; primary side S/G manways are open. Containment purge is in progress for worker comfort, although no personnel are presently in Containment due to the changing shift schedule.

C. Contractors are at work in the Spent Fuel Pool Heat Exchanger Room, Component Cooling Water Pump Room, both Diesel Generator Rooms and the Screenhouse installing temporary hoses, inserts and valve manifolds in preparation to remove Service Water, Component Cooling Water and Engineered Safeguards Systems from service simultaneously as soon as core offload is complete for valve replacement and repairs.

D. Equipment in a degraded mode:

1. The primary Coolant System is tagged for refueling. nuditionally, Containment Spray Pump P-54A has its motor removed for refurbishment.

2. Component Cooling Water Heat Exchanger E-54A has Service Water valved out and tagged.

3. All Charging Pumps are valved out and tagged for repairs to SIRWT Suction Valve M0-2160, which is disassembled with ster and packing removed. The required boric acid and inventory addition pathways are being provided by both High Pressure Safety Injection Pumps, which are available for service although presently valved out by power operated valves (all manual valves in the flowpaths are open).

4. 345 KV Switchyard ABB 27R8 is out of service and tagged for overhaul by Region.

5. Diesel Fire Pump P-9B is out of service and tagged for protection of divers at work in the Service Water Bay.

6. I&C personnel are presently troubleshooting a DC ground which has been isolated to alarm scheme EK-05 on panel C-11.

E. Many normal shutdown alarms are annunciated.

V F. See the following pages for Shutdown Safety Equipment Availability.

T AVAILAMMrY PALISADES SHUTDOWN SAFETY EQUF w m e - aa,,uPsi Effective Through . U '

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/ppaanaus m er Date T SpecialInstructions:

KEEP sDC RE111RN TEMPERATURES COMFORTABLY ABOVE 70*F, WrrH THE REACroR HEAD REMOVED Tm3 IS NO t.ONGER A IlMrr B11TWREN WE CETINTO REFUELING TT AGAIN BECOMES A LIMTTFOR hDNIMUM RX CAVTTYTEMPERATURE BOTTITRAINS OF sDC ARE OPERABE, THE SKrs ARE NOT AVAILABGTO MEET GOP 14 REQIHREMEN13.

Shinly s/O level venfication u not reemred to be logaed in sHO 1 to mea OOP-14 regaremaus.

PCS Over pressure Protecdon is being provided by the removed Reactor Vessel Head W Decay HeatRemovalrequirements: parmdio vuetain Shutdown Cooiing Train 'A' dermedin OOP-14 Atuch.S SU12) m OPERABLE LPSI P-67A CCW PUMP P 52B SWS PUMP P 7A CCW HX E 54B SDC HX E-60A LPSIINI MO 3012 / H-0311 A MO 3014 /R4313A EK-1161/1162 LPSIPanni Pas sai trni Alanns Shutdown Cooling Train 'B' dermed in OOP 14 Atuch.S (D,01-1) OPERABLE LPSI P-67B CCW PUMP P-52A SWS PUMP P 7B CCW HX E-54B SDCHX E-60B LPSIINJ MO-3008/n-0307A MO 3010 / H-0309A EK-1161/1162 LPsiPunni Pas and trip Alanns PCS Loop 1 ('A' S/G and P-50B ) _ NOTOPERABLE PCS Loop 2 ('B'S/G and P-50C) NOTOPERABLE T CVCS Boric Acid Tech Spec 3.2 and GOP-14 Inventory Addition Pathways ( Both required ):

1. SIRWT with level 250% and IB121720 ptxn; CV-3057 (sawr) to P-66A HPSIpump and digterge through REDUNDANT HPSI header through MO 3064

2. SIRWTwith level 250% and IB121720 ppm, CV-3031 sawr) to P-66B HPSIpump and discharge through NORMAL HPSI header througn MO 30(Tl (Path available within 30minmes) mamani T PCS normalmakeupInventory Addition Pathway: SIRWT, MO-2160 "q["", nonnalcharging .

g t,,,g 624*6' T PCS Level Band during Reactor Head removal: 623' 0" to 624'3" Mi. t,,,i 623 e-7 PCS Level Indication Requirements: LIA-0105 AND LIA-0106 when PCS <628'6" EK ons Rx u,tvi mios m->

Man Tensp. 1epar T PCS Temperature Band: 80 F to 100'F ui,7, wr .

No CET's available T PCS Temperature Indication Requirements: TR-0351 Reactor Headis removed T Electric PowerRequirements: Diesel 1-2 Diesel 1-1 R,s",dC$,y Cand D Buseson SAFEGUARDS AND STARTUP poweravailable T SFP Exhaust Fan / Charcoal Filter: V-8B AND VF 66 OPERABLE (em need wu EW Had Closed)

T Containment Closure Time Frame: 42 MINUTES U ."." u "innoam pI Msr 62!Y Basedon 11 daysaherreactorshutdown -

T Equipment Hatch Closure Responsibility: MECHANICAL MAINTENANCE Notify: SEE DUTY LIST Phone Ext. # 181 ,

NOTE: Adherence to all of the ec uipment conditions mpecht will ensme that the risk ofjwpma.iug the safe thntdnwn condition of the plantis minimW Adduianal egmpment may also be avminhie. these flow paths meet the reqmrements and support the schedule. This equipment should not be degraded without Op.rmiess Shiing approval

nILM V I LUMi> f*M i na I inv2nannuac waunaan Ju sanatatates #

, Suctigo ReactorSump through CV-3029 Eggt1 Panp HPSI P A TRAIN 2 REDUNDANTHPSI l

Discharge REDUNDANTHPSIthmugh MO3064 iO Suction ReactorSump through CV-3029 and MO-3198 falh.2 Pump LPSI P-67 A Discharge NonnalSDC through MO-3012 and MO-3014 Suction ReactorSump thmugh CV- 3029 4

fadL3 Pmnp HPSI P-66 A Discharge REDUNDANTHPSI Hot 12gInjectionthrough MO-3082 l Suction LPSI through MO 3015 and MO 3016 i

falkf Pump LPSI P-67-A Discharge NonnalSDC, bothHeath- ;- , MO-3012 and MO 3014  ;

INOPERABLE CONTAINMENT PENETRATIONS ,

For planned maintmance REMEMBER THAT OPERATIONS PENETRA110NS MU5T ALSO BE CONDtOUJiD BY THE SHIFT SUPERVISOR

MZ-42 PMWTO QUENCH 1X MAY BE OPEN TO SUPPLY PMW 10 THE CONTAINMENT.

CY4155 CANBECLOSEDTUISOLATEIFNEEDED.

MZ 10 SERVICE AIR MAY BE OPEN 10 SUPPLY Ant 10115! CONrAINMENT AS REQUESTED, MV- CA-122 CAN BE CLOSED TO ISOLATE IF NEEDED.

m MZ 50 EQUIPMENTHATCH MAYBE OPEN A CONTADGGINT CIDSURE11ME it 40 MINUIE G ALIDW3 OPERATORS 10 MINUDIS TO RECOGNIZE A IRSS OF SDC, 10 MennE5 io NonPY MAINT. AND Q.ZAR TEMPORARY UNES, AND 20 b6NUTE510 CD5E1BEBATUL MZ.19 PERSONNEL AIR LOCK WE HAVE ALLOWED 1EEDWD 1311MEFRAME1D EXPIRE,1HE DOOR IN11!RIDCK B DEPEATED TO AUDW Bo!H DOORS 1D BE OPEN TO ESTABLISH REPUEUNO VENIEA110NLINE UP. AT AU., TIMES ATLEAST I THE INNER DOOR SHOULD BE CAPABU! OF BEING r'r twm NO l TEMPORARY UNES SHOULD BE RUNTHROUGH THE DOORS.  !

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i MZ-18/lRA FUELTRANSFER THIS IS OPEN WITH THE CAVITY SEALINFTALLED AND '!ESTED. THE SFP SIDE BOLATION VALVE B NOT CAPABLE OF CIRSURE. THE PENETRATION CAN BE SEAU!D BY PIDODIN011IE SOUTH TILT PIT WI1H SDtWT WATER AND MAINTAINING A WATER 3EAL ABOVE THE1RANSPER 1UBE.

CONTAINMENTPURGE CONTAINMENT PURGE CARD HAS BEENISSUED, CDNTAINMENT PURGE l MAY BE PERf0RMED AS NEEDED. IF1BE PURGEIS STOPPED CONTACT

, RADPRO PRIOR 10 RESTAR11N01HE PURGE.

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! Note: The we- hy side of the Steam Generators are venedin the JJmy building by the MSIV and bypass work. l l steam trap work etc. ski == my side in the .. ...... -.. must remain closed to provide -. . . .... -.. closure.

NOTE With the PCS level above 623' 0" we are technically out of" reduced inventory".

We will be keeping both trains of SDC, both D/G's, and controuing the schedule as if we were still in reduced inventory operation until we start to Good the Reactor Cavity.

l OPERATIONS SUPERINTENDENT WAIVERS OF GOP-14 REQUIREMENTS l

} NOME - NO WAIVERS ALLOWED IN j ORNEAR REDUCEDINVENTURY l

OPS 311FERlLNTENDENT

-. z. _ _ .

Any "N# ansmr to the quesoons willhave - -.... ..ces *nnhi on me Slundown Safety Fm Avadshary Sheas. Havmg sever- )

condaicuts not santneri is expected. A nmew atf the no ansmrs, ranwnenti. -f- -- !-5 to the and stams ahmets willh alevelof  !

curnnt risk level. A copy of this will be anscheri to the SS and the Outage Manager's Cbpy of the Avadability Sheets.

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, , m-commmer o.m

( F2 Xu COREIIEAT REMOVAL <

- V PCS Tm.uu is less than 120'F?

- V Two Shutdown Cooling pmnps are Operable?

- V Two Shutdown Cooling trains are Operable?

_V SDCFlowis 23.000 gallonsperminute?

Reaciar He.d med, no CETs avahhie I Two Corn Exit Ttc roWes are Operable 7 V Bom SFP Cooling Pumps am available?

V PCS makeup is anilable > " Boil Off rate *? P.66A HPS! Pump is pitm&ng the makeup pse.

V SDCInstr=naa'* is Operable?

All Fire Protsction systems are Operable? P-9B Fue Pump om of semce for 4ver mspecnon.

1. 2 Instrument Air my.- are Operable?

REACTIVITY CONTROL At least two Pmnped Borir: Acid flow paths

- V (dieselimekadep) to the PCS are Operable?

V PCS [B] is > 3.5% CSD g Rs.fnehng baron concentranon? PCS 2 REFUELING [B)of1.720 PPM V 2 Source Range NuclearInstranents are Operable?

- V No com ahcranons are in progress?

1 No Fuelmovesin SFP ar:inprogress?

V No Control Pod Drive testing is in progress?

V Prunary Makeup Water to PCS is cannen tagged closed? MV.cyc.7162 etomf.

ELECTRICAL AVAILABILITY I Atleastone Diesci Generatoris operaMe? Boe Operable for Ruhuwt Invemory Oceranens V At least 2 Off-Site power somees am operabic?

b' -

V At least 3 Preferred AC bcscs are operable?

V Both IC and ID buses are energxzed?

I No Electrual special sesong is planned? l 1 SwuchyardPomesupplyisstable7 Maxmmm ef one Switchyard Breaker out of service at a time, l I AllDCBasesareoperable?

PCSINVENTORY '

v.'

I PCS full and intact g is elevation oflowest openmg idennfied?

.I _ PCS levelis above 62r S* 7

- .I.,

V PCS levelis above 623' 0* (reducnd mventary)?

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PCS level above is 61r 0* (2.5*< hot / cold leg censratme)? l

![ 2 0:=i== Sump level '.~. .... -.. am available?  !

V Two PCS levelinstnanents are operable? l I

1 Allflowpa&sforheavyload. p.oa areavadable?

I Elevation oflowest PCS openmg is idennSed7 Remser Hand deamsomed cr iemoved (624* 6") l V OOP 14 PCS Vendng m ts arc tantht?

CONTAINMENTINTEGRITY 42 Ininute cantarameln Cosure Tune for loss ef SDC I

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__ V cam -m,stImagnty is act g comrolled IAW GOP-147 V N- -

-" is open with ability to close within specified time?

V l-10 penetrances are open which can be ciceed within tbne limits'

-.!I Contammear Closure perw=neJ arewnnfied and available?

No penetranons open which can not be closed within time limits?

I SFP Otarcoal Filters me available? At less one door dossi (Eamo Had. Hatch Covers. Roll-g Door)

Y Air locks are closed g e of being closed?

v IF PCSISINREDUCEDINVENTORY

• Y Time spentin reduced mvenmry M V Only w-herinnert testing and manwenanre in progress?

V No Electncal Power supply changes planner 47 I

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

l Urn 2Vwuna umu.am v , .. ~- -- .. - _ _ .

Pt.zasssavizw1mEaccurnarrsTAlussumEssausrrs.YArm3B AwAREoFCEANGB0oFLA frCoperrmHL PUIAsE i l

SEAaB ANY cmmeris oR CDMGENs wfTE STETE. CoNTEM. BOOM AND e EAVETER oNLY ofFICsAL CIFIEE.

l 1HE DA1Es1D THE UET oF1EE DmtY tErCTTHEI.ATErr CHA)GE101EB ASsor3A1ED ENTRY.

a Fillmg out Outage Conque - sheets as r=nar== warmot and whm they me insh in your med is the canest and most effecuve way to effect change in the funne. The SE's am ==i==6=ag a book of en===we All Operations personnel are encouraged to summat and review the cannssets firegnandy. ,

= Keep lodme snoval fants in semce as RadPm requesta. Keep at lean one VHX-2 and 4 fan on to reene Cont air.

m Work Orderhas disabled SIS on PCS Low Pressme SIS wiH still actzar on High Cent Pressme and mannd w PCS makeup should be from the SIRWT to HPSL AH chargmg is out of service. We will resmee Qiarsmg to Operable before the SIRWTlevel drops below 50%. Until furthernonce MO 2160 can only be ,- - si by the manual operamr. Paa MO 2160 or MV-CVC-3242 closed whm not bemg used to prevent gravny feed to PCS.

= IAChasthenhaart the RAS cucun, thisisin rn-.-s of Dami'a- the cayny.

l ;i toprevent back flow

) = Ensme the Comalled Bleed-off Plow Connet Valves are closed with the PCS -h--

1 froen the VCTinto the PCP seals.

= we closed and cannon tagged PMW makeup so the PCS MV CVC-2162 when conhng down before gang on SDC. 'Ihis ensues unwamed elilant= on SDC does not occur. Mantam this closed.

! w After the PCS drain through Leedown was cr==pimi and befose stanag dein with Cold 123 drums we closed the

! -"iawnisolaten at the PCS Cold Leg MV-CVC-106. This is to limit a pah for unp3=n==8 PCS drains.

j = PCS Cold Leg drams on loop 1A and IB have had theirspectacle fisages swapped to the open pannon.

i e Nozzie dans am m both SA3's and venfied. W. has natale dem ==anang .4"y. They can be stached at i ext 0769 in their under. Nozzle dams are oninsmanent air and mannrumr- t.offMCC-9 i

w AllPCS drums should go e T-64'B' CWRT. We willtop off SRWT one more time fme the SPP whus we are pamn, the incons for the thst time. We need the SIRWT fhn to compime the cavity flood.

! w While on SDC muntan SDC flow >2810 GPM. Below this Tech Spee 3.10.1c and SOP 3 applies. We now only need me Qargmg or HPSI ca== eienently ennnamd for PCS makeup paths as the =aai=8 rue is <40 gpm ,

w Do not vent any of the STI's but the peamme can decay away, keep stleast500 in each boule. RI-15C was ;- '--- =1 l which mains the level indieminn wrong natil we backfD1 =4a==== less at end af the antage, swkches win sein work.

= When the Eqmpment batch is open ehbarthe anck ausy haches or the sou up doornmst be closed

! = We have cannon tagged the Cont Samp drain vatves so aDow the levet so zine from decon and drain weer to at least 25% on LT 0358. *ihis is weR above the stanns and we should frequently checklevel to emmre no sensual mends are 3

occumng =="ny when we ase changmg PCS level. This 255 is about 8.000 gallons or over 2.5 fhu Diny Wase

' tanks so close coordinanon~is needed when we eventuaHy drain this -a

= CV-1212 Service Alrisolanon is Temp Mod blacied open to annuman loss of benadung airin theenmman=nr.

Bra =hia! Airis bemg =a=&'i fmm the Service Airheaderin thecr===runant w When the F- Hachis open we shonid establish and mannum the GOP 14 Vana1=nr= hneup. This l

has snown to be the least er=r==inaring air flow padt so the SPP men.

m The Prensamer Massy is removed, These is a daue:gn amenal bemernutailed winch has been venfled not to .

limit the veet tieth. We are using the removed Reecer Vesel Head this for PCS C- Proachen. _

w If T-2 levul c.'er drops please keep T-2 Cond Storage Tanklevellow, work towards a p ' .4 =50% level, we will need this invei to be low imer this month to disin beah SKTs to it for =e=4=y side b= , andsludge t.a,.;ay w After the Reactor Head was off the flange we placed HPSI in service for (B] injecnon flow path. We lined up '

l l P-66A ad did a est an, after this we wiH bc ===* ming its sucnon and discharge power aa===4 valves ]

closed. AH mannal vielves in the padt win be open. Since this is not a nnannan flow puh ensme you myiew the anrh forthisinjecaxmpuh.

w We will be domg ====== ara on the Oumr Door of the Paar===i Air Lock. Theinner docrmust renam einenhie Nannal ventilanaalineup for sfueling win be whh both doors open. If a doorneeds to be closed for

,, , ... .. .. . orvenniennn gamasit nRay be na aa'i - 3 _--- y ItaW- J ateess.

er The Shift Manager win run the 0815 mesangs dung the outage, a shift contactis needed and win pade Ops i status and report enar- back to the shiftL ar An 1830 outage managanant meeting is held in the Tech Support Cener daily, please have an M nr OSS anend j

i O each mght ShiftManagerwS1runthemeeting e our safety duececr needs to be nemami neannent. VikkiJanes Beeper brs)about or injury on site which requaes off site

, j 1

@ MarkHolbeurs rV--- , fcrany a_---+ LLRT. or ----w-F== ornmir I

- @ ne.YE WAWRO'S PHONE BEE 6 ENTER 0225 WHEN#IS REQUESTED 1

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l G. Meterological conditions are as follows: l

1. Clear weather and high barowtric pressure have been prevelant for I several days; moderate to stiong winds are from the southwest. No d inclement weather is predicted, i l

a. Wind speed: 7 mph l

b. Wind direction: 347'

c. Stabilty: B

d. Ambient temperature: 57'F H. Primary chemistry conditions:

1. pH: 4.77

2. Boron: 2035 ppm

3. Total beta gamma activity: 0.187pci/ml

4. Iodine dose equivilent: 7.74pci/ml 0830-0845 (0000-0015)

A. The exercise begins when 2400VAC Breaker 152-105 supplying Bus 1C from Safeguards Transformer 1-1 developes a phase-to-phase short due to the unintended intrusion of construction debris (cable scraps)

(

inside the breaker cubicle. The breaker explodes, deenergizing Bus 1C and damaging bus and feeder cable connections and adjacent breaker cubicles; smoke, but no fire results. No personnel are in the breaker area at the time. The breaker explosion is heard in the Control Room and throughout the Turbine Building. The inservice Shutdown Cooling Pump, P-67B, loses power and stops.

B. Safeguards Transformer 1-1 Feeder Breaker 152-401 trips on differential voltage, deenergizing 2400VAC Busses ID and IE in addition to Bus IC. Both Diesel Generators start; D/G 1-1 output breaker closes and then trips due to the fault on Bus IC, tripping the diesel engine as well. D/G 1-2 output breaker does not close and Bus ID incoming breaker 152-203 does not trip due to lack of control power; a contractor has opened breaker 72-402 inside DC Panel D21A, thinking that it was a light switch, in the D/G 1-2 Room in a futile search for additional room lighting during temporary cooling system installation work and neglected to reclose it.

C. Expected actions:

1. Operators will respond to the loss of Shutdown Cooling by invoking 0NP-17, " Loss of Shutdown Cooling".

2. The plant Fire Brigade will be called out and dispatched to the Bus 1C area; vital area door keys will be required due to the N failure of all AC power (the actual Fire Brigade will be used (d if plant conditions at the time of the exercise are stable enough to permit the utilization of plant operators for a fire drill. If not, this action will be simulated.)

3. The Shift Supervisor will assume the Site Emergency Director (SED) position and:

- a. An Alert will be declared under " Engineered Safety (s' ') Features - Complete loss of any functions needed for plant cold shutdown" or " Plant Power Electrical - Loss of offsite and onsite power for less than 15 minutes"; either catagory is appropriate.

b. Directs a public address annoucement on the situation ordering the evacuation of any personnel who might be in the Containment Building and the sounding of the emergency siren.

c. Delegates actions and notifications identified in EI-l and marked on El-2.1 Attachment 1, including emergency staff augmentation; personnel accountability; activation of the Operational Support Center (0SC) and Technical Support Center (TSC); dose assessment; and activation of the Emergency Response Data System (ERDS).

d. Directs completing the emergency notification forms of El-3 and N0D Form 3160.

e. Commence 15 minute notifications per El-3.

0845-0900 (0015-0030)

A. The Reactor core, deprived of cooling, begins to heat up rapidly. The increasing PCS temperature cannot be seen by (G) operators and TSC personnel since the only available temperature indicator with the Reactor Vessel head removed is Shutdown Cooling Temperature Recorder TR-0351, which is presently deenergized due to loss of Y01 and, even if powered, is effectively disabled when there is no flow through the Shutdown Cooling System.

B. Inside The "A" Steam Generator, the dams installed in the hot and cold legs have been installed improperly; rather than being locked in place, they are instead being held in place only by the inflated seals around each dam. The inflated seals have also been operating with backup nitrogen supplies inadvertantly valved out and backuo battery power supplies non-functional. When AC power is lost, the seals deflate as instrument air pressure decays away; soon, several thousand gallons of Primary Coolant are pouring out of the primary manways to the Containment Sump. Reactor Vessel water level falls to 618'2.5", and the uncooled Reactor heats up even faster.

C. Expected actions:

1. Operators will deduce that lack of control power is the most likely cause of the failure of D/G l-2 output breaker to close and an Auxiliary Operator will find breaker 72-402 out of position; control power will be restored, Bus ID incoming breaker 152-203 will trip and D/G 1-2 will reenergize Bus 10.

(V,-). They will then attempt to restore Shutdown Cooling flow by starting alternate Shutdown Cooling Pump P-67A, but the pump will cavitate heavily and will either trip or be secured. The pump impeller will be damaged, rendering P-67A unusable.

Notifications previously made to offsite agencies will be updated as appropriate.

2. Personnel will be dispatched to clear service lines from the Equipment Hatch in anticipation of closing the hatch.

3. The status of inoperable Containment penetrations will be evaluated and measures to close the penetrations identified, including the necessity to water seal the Fuel Transfer Tube to provide Containment closure.

4. Attempts will begin to determine the scope of electrical system malfunctions.

5. As normal refueling damper control is unavailable due to the loss of MCC-1, maintenance efforts will begin to manually align ventillation in the Fuel Handling Building to exhaust via charcoal filters.

0900-0930 (0030-0100)

A. The Reactor continues to heat up, achieving 210'F by 0930. The Primary Coolant covering the fuel begins to boil. Expanding coolant continues to find its way to the Containment Sump via the "A" S/G primary manways.

B. Expected actions:

1. Complete staffing of the Operations Support Center and Technical Support Center and turn over responsibilty.

2. Complete site accountability and commence search and rescue for any missing personnel.

3. If operators attempt to use the P-66A High Pressure Safety Injection Pump to make up to the PCS, the pump will immediately go to runout when started and trip its power supply breaker 152-207. Maintenance efforts will then shift to reassembly of M0-2160 and the normal charging path if not initiated previously.

4. Operators will conmence flooding tne south Tilt Pit of the Spent Fuel Pool with SIRWT water to attempt to establish a water seal above the Fuel Transfer Tube to eliminate the leakage path out of Containment. This will require flooding the south tilt pit, fuel transfer tube and reactor side tilt machine pit to at least the 619'0" elevation; no more than 5 1/2 feet of water can be added above this elevation before the additional water spills out on to the refueling deck, i.e.

the maximum Containment pressure capable of being contained by this method is approximately 2.4 psi.

5. All available Containment Air Coolers will be operated at maximum capacity to minimize Containment temperature rise.

O 6. Available instrumentation will be placed in service to monitor d Containment conditions. Whichever channel of Containment Hydrogen Monitoring is placed in service first will fail upscale high (the purpose of this failure is to exercise I&C personnel who, by the very nature of SEP exercise scenarios,

tend to be less involved than other disciplines, and at the same time ensure that TSC attention is focused on potentially degrading Containment conditions).

p\ 0930-1000 (0100-0130)

A. The water covering the fuel in the Reactor is now boiling vigorously, and fuel temperature increases dramatically. The water level covering the core decreases as heavy plumes of steam are driven into the Containment atmosphere; Containnent temperature and humidity rapidly increase. All Containment area monitors and high range gamma monitors are in alarm.

B. Warm, humid air and some airborne contamination escapes the Containment via the Fuel Transfer Tube until operators water seal the leak path.

C. Expected actions:

1. The emergency classification will be upgraded to a minimum of Site Area Emergency based on " Fission Product Barriers / Fuel Damage - Degraded core with possible loss of coolable geometry". A high probability exists that players will conservatively elect to declare a General Emergency at this point in the exercise due to the potential for core damage and loss of Containment.

2. Appropriate respiratory and dose minimization requirements will p be applied for personnel exposed to escaping noble gasses and Q airborne contamination.

1000-1045 (0130-0215)

A. Reactor Vessel water volume continues to boil off to Containment; the fuel is uncovered by 1045. The cladding of several fuel rods has already failed due to high internal gas pressures; fission gasses are being released directly to the Containment atmosphere.

Superheated steam is the only remaining cooling medium for the fuel.

B. Expected actions:

1. The Emergency Classification will be upgraded to General Emergency, if not performed earlier, and appropriate protective ;

action recommendations made.

2. Maintenance efforts will be directed at effecting repairs to a means of injecting borated cooling water to recover the core; Bus 1C will not be permitted to be recovered for the duration of the exercise. Controllers will permit recovery of whichever success path (powered from Bus 10) is most dilligently pursued, but not before core geometry has degraded to the point where  :

effective cooling is no longer possible (for scenario purposes, this will occur at 1045). A great deal of inventory is also contained in the Safety Injection Tanks, should players e' lect i O to inject them; this will delay the onset of fuel damage but l

,C not prevent it (i.e. briefly reflood the Reactor Vessel to I 618'2.5 with the excess spilling to the Containment Sump).

i

4. Water sealing of the Fuel Transfer Tube, if previously initiated, will be completed.

1045-1145 (0215-0315)

O V A. As the Reactor core uncovers, fuel temperatures exceed 4000*F in the upper portions of the core. The zirconium cladding of the fuel rods is actively reacting with steam, generating large amounts of hydrogen gas and converting the cladding to relatively weak zirconium oxide. The oxidation and embrittlement of the cladding causes several feet of the upper part of the core to slump inward, blocking flow passages and inhibiting steam cooling; fuel temperatures in these regions of the core begin to ~ . ach the melting point of the uranium oxide fuel. Signifig . ants of fission fragments now join the hundreds of thousands u. euries of noble gasses in the Containment atmosphere.

C. Expected actions:

1. A source of borated PCS makeup (most likely throttled High Pressure Safety Injection or normal Charging following reassemby of M0-2160) will be placed in service to flood t ..

Reactor cavity and recover the core. That portion of this makeup which does not boil off to the Containment atmosphere will be lost to the Containment Sump via the failed S/G "A" nozzle dam when a PCS elevation of 618'2.5" is achieved. Due to its degraded geometry, some regions of the core can no longer be effectively cooled.

c 2. If Hydrogen Recombiner M-69A is placed in service, it wi' it

(,' effectively function due to being surrounded by outage ma ial and will instead serve only as an ignition source for the hydrogen-laden Containment atmosphere when explosive proportions are attained.

1145-1245 (0315-0415)

A. As the Containment pressurizes, an ignition source inside Containment causes a hydrogen exposion, felt throughout the plant as a sharp, quick concussion. The water seal above the Fuel Transfer Tube, if successfully established, is expelled into the Fuel Handling Building. The Containment atmosphere now freely vents to the plant stack via the Fuel Handling Building Ventillation System.

Exposed to high humidity and heavy radioisotope concentrations, the filter banks quickly saturate and lose their efficiency, resulting in a continuous plume release from the stack.

B. Overflights of the site by members of the media and curious onlookers have begun; several pass downwind through the release plume.

C. Expected 'a.(lons:

1. Protm cive action recommendations will be upgraded as appropriatu external assistance will be requested to prevent any unnecessary exposure to onlookers.

2. The remaining contents of the SIRWT will be added to the PCS/ Containment Sump and suction of the in-use injection path shifted to the sump for long term recirculation cooling;

additional boric acid addition flowpaths will be restored to operation as maintenance resources become available.

. 1

3. Maintenance and engineering efforts will commence to focus on O necessary actions to seal the Containment breach via the Fuel Transfer Tube.

i 1245+ (0415+)

A. Time jump to new plant conditions.

. B. Several days have passed since the accident. Bus 1C has been repaired; Shutdown Cooling Pump P-67B is recirculating Primary Coolant from the Containment Sump through the Shutdown Cooling Heat Exchangers. Portions of the Reactor core remain uneffectively cooled, and PCS temperature has stabilized at approximately 200*F.

Radiation levels in Containment remain very high; no attempts at 1

Containment entry have yet been made.

C. The south tilt pit has been sealed with a pressure-tight enclosure and the Fuel Handling building is being ventillated using truck-mounted high efficiency filters; no further release is occurring, although detectable ground deposits in the former direction of the

. plume exist for many miles.

D. Most plant personnel are at or near their yearly exposure limits.

Maintenance efforts are presently focused on maximizing the reliability of Shutdown Cooling, radiation levels permitting (both

-Safeguards Rooms have extremely high general area dose rates).

E. Expected actions:

1. Strategies will be put in place for the entry into and evaluation of damage in the Containment and Auxiliary Buildings and the retrieval and disposal of over one million-gallons of radioactive water, signifigant emounts of radioactive gasses and the destroyed Reactor core.

2. - The extent and nature of environmental cleanup will be determined, including necessary evacuation of any additional population centers.

3. The exercise will be terminated when recovery objectives have been met.

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, s --- -- - - --

O MESSAGE SHEETS O

O

Scenario: PALEX-94 Time: 0800 Message No: 1 s Scenario Time: -0030 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: All Plant Personnel Simulated Plant Conditions:

See attached Initial Conditions and Data Sheets Message:

The Control Room has announced the following message: " Attention all personnel. The emergency exercise will commence shortly. All announcements related to the drill will be preceeded by and followed by the statement 'This is a drill'."

FOR CONTROLLER USE ONLY Controller Notes:

l. All controllers will provide Initial Conditions, Alarm and Data Sheets to the players they are responsible for upon activation of the Emergency Plan.

2. Control Room Controller will act as off-going SS and give turnover to

players.

3. Answer questions as appropriate.

4. Control Room Data Sheets / Alarm Sheets are not to be provided to Control Room players unless a simulator malfunction occurs which jeopardizes the scenario time line.

Action expected:

Players should familiarize themselves with data provided.

INITIAL CONDITIONS 0800 (-0030)

A. The plant is in Cold Shutdown at the end of core life. The Reactor has been shutdown for 11 days; the Reactor head is removed and the Reactor cavity seal is installed and tested. Preparations are in progress to install the Upper Guide Structure lift rig and perform incore detector removal prior to a full core offload for Reactor Vessel beltline weld inspections. Operators are currently performing shift turnover and conducting pre-job briefings.

B. The Equipment Hatch is open with several temporary service lines running through it to Containment; the Personnel Airlock door interlock is defeated and both doors are open. The Fuel Transfer tube is open; the isolation valve on the Spent Fuel Pool side of the Fuel Transfer Tube has

, been broken for many years and is not capable of closure. Hot and cold leg nozzle dams are installed in both Steam Generators, and the secondary

! side of each S/G is dry; primary side S/G manways are open. Containment purge is in progress for worker comfort, although no personnel are j presently in Containment due to the changing shift schedule.

C. Contractors are at work in the Spent Fuel Pool Heat Exchanger Room, Component Cooling Water Pump Room, both Diesel Generator Rooms and the

! Screenhouse installing temporary hoses, inserts and valve manifolds in l preparation to remove Service Water, Component Cooling Water and Engineered Safeguards Systems from service simultaneously as soon as core offload is complete for valve replacement and repairs.

7 D. Equipment in a degraded mode:

3 1. The primary Coolant System is tagged for refueling. Additionally, l Containment Spray Pump P-54A has its motor removed for i

refurbishment.

2. Component Cooling' Water Heat Exchanger E-54A has Service Water valved out and tagged.

I

3. All Charging Pumps are valved out and tagged for repairs to SIRWT

] Suction Valve M0-2160, which is disassembled with stem and packing

! removed. The required boric acid and inventory addition pathways are being provided by both High Pressure Safety Injection Pumps, l which are available for service although presently valved out by -

power operated valves (all manual valves in the flowpaths are open).

4. 345 KV Switchyard ABB 27R8 is out of. service and tagged for overhaul by Region.

5. Diesel Fire Pump P-98 is out of service and tagged for protection of divers at work in the Service Water Bay.

6 I&C personnel are presently troubleshooting a DC ground which has been isolated to alarm scheme EK-05 on panel C-11.

E. Many normal shutdown alarms are annunciated.

F. See the following pages for Shutdown Safety Equipment Availability.

PA1JNADES SHUTDOWN SAFETY EQUIP T AY AILA151LITY wm6. M .a.srsi -

l FEccrive T11 rough k' ' '

p . - n. - Date i

7 SpecialInstructions:

KEEP sDC RETURN TEMPERATtJREs COMFORTABLY ABOVE 70"F. WTTH Tile reactor HEAD REMOVED Tm3 IS No ,

l LONGER A LIMir BtTrWHEN WE GETINTO REFUEL.ING IT AGAIN BECOMES A 11MITFOR MINIMUM RX CAVTTYTEMPERATUPE BOTH TRAINS OFsDC ARE OPERABLE. THE sKrs ARE NOT AVAD ABLE TO MEET GOP 14 REQUIREMEPrI1L Shiftly SK) level ven&arion is not rannrad to be logged in sHO 1 to meet GOP 14 seguranents.

PCS Over-pressure Protection is being provided by the removed Reactor Vessel Head 2

T Decay Heat Removalrequirements: ,,,d.,,d i, n ,,.

Shutdown Cooling Train 'A' ds5andinOOP-14 Anach.5 (DK]12) OPERABLE LPSI P-67A CCWPUMP P 52B SWS PUMP P 7A CCW HX E-54B SDC HX E40A l LPSIINJ MO 3012/FI-03t1A MO 3014 /FI4313A EK-1161/1162 tpst pm., Pnss and wi, Al==s Shutdown Cooling Train 'B' win-iinOOP 14 Anach.5 (DK]11) OPERABLE LPSI P 67B CCW PUMP P 52A SWS PUMP P 7B CCW HX E-54B SDCHX E 608 LPSIINJ MO 3008/FI-0307A MO-3010 / FI-0309A EK-1161/1162 trstPomo Pass and as Alems PCS Loop 1 ('A' S/G and P-50B ) NOTOPERABLE

,- PCS Loop 2 ('B'S/G and P-50C) NOTOPERABLE T CVCS Boric Acid Tech Spec 3.2 and GOP-14 Inventory Addition Pathways ( Both required ):

1. SIRWTwithlevel2$0% and[B121720 xan; CV-3057 sawn to P-66A HPSI===a and 4=*nrge Ituough REDUNDANT HPSI mader tinough MO 3064 1

! 2. SIRWTwithlevel250% and fB121720ptzn, CW3031 anwn to P46B HPSI===a and

) **1w e sthrough NORMAL HPSI header stuough MO 30(Tl (Pat avaGabis wkhin 30 mannes) '

e 7 PCS nonnalmakeupInventory Addition Pathway: SIRWT, MO 2160'FlllR", nonnald=w .

u. t.,,i ascr T PCS Level Band during Reactor Head removal: 623' 0" to 624' 3" ui.w arr o-T PCS LevelIndication Requiremnte LIA 0105 AND LIA 0106 when PCS <628' 6" sg.aug myi,,d taoio3 %, ,

T PCS Temperature Band:

80 F to 100*F ui,.r -

No CET's available T PCS Temperature Indication Requirements: TR-0351 Reanor Headis removed W Electric PowerRequirements: Diesel 12 Diesel 1-1 a.Is'EO y C and D Buseson SAFEGUARDS AND STAR 7UP poweravailable 7 SFP Exhaust Fan / Charcoal Filter: V4B ANDVF46 OPERABLE (emmedwkhSemi,HanC3.sc ,

j-T Containment Closure Time Frame:

Based on 1Ldays afterreactor shutdown 42 MINUTES U'n"uY"C8I:.p Wsor a2rE -~ *

- T Equipment Hatch Closure Responsibility: MECHANICAL MAINTENANCE l Nodfy: SEE DUIY LIST Phone Ext.# 181 ,

NOTE: Adherence to all of the 5 :; = mrweitum ew will ensme that the risk ofbdL.Lig the safe shutdon i condition of the plantis d '= Additional eqmpment may also be avalable, these flow paths meet the requuements l and support the schedule. ' Ibis equipment should not be de,aded without Opernicos W' Hag approval.

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. . _ . .m ._ _

HILM V I 1AJM111 M 1 na t savananunc w tLian11 Jts f allI1LALES 7

, ,,,Suaign ReacorSump thttmgh CV-3029 gggjtj, Pump HPSI P-66. A 'IRAIN 2 REDUNDANTHPSI

- Discharge REDUNDANTHPSIthrough MO3064 O f,athl Suct1m Pump Reac o, Sum. throu8h Cv-3029 a.d MO2198 LPSI P 67. A Discharge NormalSDC through MO 3012 and MO 3014

Suctim .ReactorSump through CV.3029 Ealh) Pump HPSI P-66 A Discharge REDUNDANTHPSI HotLeginiectimthrough MO-3082 I Suctim LPSI through MO.3015 and MO3016 l fath.,4 Pump LPSI P-67-A Ducharge NcrmalSDC bothHeat N=-- - MO 3012 and MO-3014 INOPERABLE CONTAINMENT PENETRATIONS i Forplanned maintenwe REMEMBER THAT OPERAMONS PENETRAMONS MUST A1JO BE CONTROM,PD BY THE SHIFT SUPERVISOR MZ-42 PMWTO QUENCHTK MAY BE OPEN1D SUPPLY P'4#10 THE CONTAINMENr.

i CV 01S$ CAN BE CIDSED E ISO! ATE IF NEEDED.

MZ 10 SERVICE AIR MAY BE OPEN TO SUPPf.Y AIR 1D THE (DNTAINMENT AS REQUESTED.

MV. CA 122 CAN BE CDSED 1D 13OLATE IF NEEDED.

MZ 50 EQUIPMENTHATCH MAYBE OPEN A Cuf fTADEEENT CLOSURE EME 240 MINUTE O AUDWS OPERATORS 1 J MINU!ES TO RECOGNIZE A IDSS OF SDC 10 MINUTES 10 NUTIFY HAINT. AND QEAR TEMPORARY LINES. AND 20 MINUTES 10 CDSEGE HATT.H.

MZ 19 PERSONNEL AIR LOCK WE HAVE AUDWED DIE DWD.13 MME FRAME 10 EXPDtE. THE DOOR INIERIDCI:IS DEPEATED TO AUDW BOTH DOORS TO BE OPEN1D ESTABUSH REPUEIJNG VENTRATIONIJNE UP. AT A1.LTIMES ATLEAST THE INNER DOOR SHOU 1D BE CAPAB12 OF BEING et nun. NO

, TEMPORARY LINES SHOULD BE RUN THROUGH THE DOORS.

~

MZ-18/18A FUELTRANSFER THIS IS OPEN WrrH THE CAVITY SEALINSTAU.ED AND 1ESTED. THE SFP SIDE ISOLAMON VALVE IS NOT CAPABLE OF CLOSURE. THE PENETRA11DN CAN BE SEALED BY PLOODING THE SOUTH TILT PIT WITH SIRWT WATER AND MAINTANING A WATER SEAL ABOYE THE TRANSPER 7t?".

CONTAINMENTPURGE CONTAINMENT PURGE CARD HAS BEEN ISSUED. CDNTAINMENT PURGE MAY BE PERIORMED AS NEEDED. IFTHE PURGEIS STOPPED CONTACT RADPRO PRIOR 10 RESTARTING THE PURGE.

Note: The w- hy side of the Steam Genermors are vened in the auxiliary building by the MSIV and bypass work.

steam trap work etc. ski ==*ry side in the ennemhnnnr mun remam closed to provide - '..~. -. closure.

i NOTE - With the PCS level above 623' 0" We are technically out of" reduced inventory".

We Will be keeping both trains of SDC, both D/G'S, and controuing the Schedule a5 If We Were  :

Still in reduced inventory operation until We Start to flood the Reactor Cavity. l O orzaiTrous surza1*rzwussr wA1vras or oor 14 ==ourazuzurs NONE - NO WAIVERS ALLOWED IN l ORNEAR REDUCEDINVENTURY l cps suPERIN7ENDENT i

, ' Any "No* answers to the gusanoes will have cue ===- Aamin=d on the Shandsen Saissy Equqases Availshikey Shassa. Navag severr j M- not aman 6md is aq= read A review cf the no answers. ca====*= and assess absess will levelof aderstanding to the current risklevel. A copy of this will be anached to tbs SS and the Ousage Manager's Copy of the t Av=lalahiy Shases.

lA Qm M-N2 121 CORE HEATREMOVAL /e Commems

! V PCS Taroperanse isless than 120*P7 l - ![ TwoShadownCoolagpuenpsareOperable?

- tl Two Shadown Cooing trams am Operable?

_ V SDCPlowis 23.000 gaDonsperminme?

! V Two Core Exit Thermocouples are Operable?

Ramsar Head amoved, so CETs avalabic l V Both SPP Cooling Pumps are available?

V PCS makeup is available > " Boil Off rase *7 P46A HPS! Pump is piovuksg the asksup pah, l

V SDCInstr=====aaa is Operable?

l 1 AD Phe Protecnout symams as Operable? P 9B Fire Puump osa af servics for everinspessen.

V 2 Inserement Air compisamors are Operabic?

REACTIVITY CONTROL At least two Penped Boric Acid Dow paths 1 (dismal bankakp) to the PCE are Operable?

,, V PCS[B]is>3.5%CSDgReisshag boson - . -  ? PCS 2REFUEUNG [B)of1.720 PPM -

, - tf 2SomosRanseNaciserInsmansamareOperable?

I NoCasesharamensasinprogress?

Jf No Pust movesin SPP mein progress?

I No Connel Red Drive semang is in progress?

- f Prunary Makamp Waaer to PCS is cannon tagged closed? MV-cyc-2162 clammt 4

ELECTRICAL AVAILABILITY j

V At lasst ens Dissal Osmaraseris operahis? Both Operabis for Reduced Inventory Operances V At issut 2 Off Sias power sauces are operabis?

V At least3 Preferred ACbuses me operabis?

V Bodt IC and ID bases are smagised?

I NoEnsemmalspecialassangisplumed?

V Swuchymd Po.orapply is sabis? Ma- or ons Swiachvad Besaker as of servies at a time I AllDCBasesareoperabis?

i PCSINVENTORY e,

1. PCS fall and heet a ls ensvanen of bwest opams id afi-r7 td _ PCS levelis above 625' 5* 7 .

1 PCS level is above 623' 0" (reduced urvasary)?

- tf PCS level above is 61s' 0"(2.5"< hot / cold leg caserhus)? -

_ 1 2 r====== Samp levelinsmmasas am availabis?

V Two PCs level innruments se operabis?

- lf AB Dowpashsforheavyloadreqessenenesmeavailabis?

1 Elevamos oflowest PCS opsang is idannfled? Rommer Hand desumamed er nummd (624' 6")

- OOP-14 PCS Vaning sequuumans are sans6sd7 V set conneumi WOOP 147 42 mirmm GClosure Tinn forloss ofSDC

_ 1 - is . . bh ab y . . . bh , _ ~ ,

- td 1-10peasmenomsmeoputwhichsombeclosedwithinthneliants' Pa*====ar Closure personnel are idannnad and availabis?

No passmenons open which can not be cloemd within thns hauss?

V SPP Qiannel Rhars are availabist At Issa oss door stosed Giosip Hasen. HsudiCovent rob-e Door)

Air locks are closed a capabis of being closed?

IFPCSISIN REDUCEDINVENTORY -

I Tkne spost in nahmoed invenery =i=====rr

• I. Only schahdad assing and massessmos in progress?

1 No Ensemcal Power supply changes pimmed?

~ . . . - -- . . - - -

Urr:Atmt.m o ur m.auu.,

i PLEAssasvizwTusanorrumerrrATUIamEI5aMFH.Y Alm SE AWAREoF CRANG50GPEANTCONDT CoffTEM. Boom AND B EAVEYBE oNLY OFFICIAL CorEN.

l SEAaB ANY t'nuumers 03 CoNCaENs WFIE NTEVE.

nE DATIs1D THE UFr oF 1EE EmT DEMCTTHE LATENT CHANtE To TEB ASsoCATED ENTRY.

m Filhng out Outage e nnrpe enmment sheces as mmhname wamus ad when they am fresh in your mindis the l canest atxi mca effecuve way to effner change in the futme. The SE's are ==irena=g a book of trun=,nts

O l

All Oper=* personnai are en&===d to sunnait and review the esaments thquantly.

w Kaan lodme removal fan /s in semce as RadPm requests. Keep at lean one VHX-2 and 4 fan on to recue Coni air,

~

i a Work Orderhas disabled SIS on PCS Low Pressme SIS will still occur on High Cont Pressme and m-- l.

w PCS makeup should be fman the SIRW'r to HPSL All chargmg is out of servtce. We will resmre CM to j Operable before the SIRWT level drops below 50%. Until funbernonce MO.2160 can only be opermed by the i

====1 operunr. Keep MO.2160 or MV-CVC.3242 closed when not bemg used to prevent gnmry feed to PCS.

w IAC has disabled the RAS cucuit, this is in pp is of flar-Ha! the cavity.

I w Ensme the Ccenolled Bleed-off Plow Contrti Valves are closed with the PCS ? 3 -- -- d tor . E hackflow l from the VCTinto the PCP seals.

j w we closed and caman tagged PMW makeup to the PCS MV-CVC.2162 when wuusg down befose gamg en 1 SDC. This ensnes unwanted diinnte on SDC does not occur. Mamtam this closed.

! w After the PC5 drain sinaugh Leadown was (---f M and before namng disin with Cold Leg drums we closed the Letdown iscianon a the PCS Cold Leg MV-CVC 106. This is m iimit a path for unpl===d PCS drans.

I a PCS Coldlag drans on loop 1A and IB have had their 3="- flanges awapped to the open posman,

" Pry. They canbe reached ac i w Nozzie dans ass in both SKrs and venfind .E hasnosatedent=rumannny. r- fMCC-9 l ext 0769 in their traik:r. Noezie dams are oninananent air and mananesm /.of

. e AH PCS drams should go ao T-6411' CWRT. We win top off SIRWT one most time inun the SPP while we are aallia* the inceres for the first time. We need the SIRWT fur to complete the cavny flood.

w While on SDC massan SDC flow >2310 GPM. Below this Tech Spec 3.10.1c and SOP 3.nu We nowonly need one Nr=ne or HPSI pump enemiemlly emnened for PCS makeup pahs as the required ran is <40 gpm

'- ==d

m Do not vent any of the STrs but the preanne can decay away, keep aleestSO# in each houle. RI-15C was which mains the levelinrhemrirm wrong until we backfHi reference less at emiof the catage, switches will din w

• When the Frpnpnent haeh is open enher the track alley haches or the mB-up dooruma be closed a We have cannon tagged the Cent Sump drain vaives to allow the level to rise inzn decen and drain weer to at least 25% on LT-0353.1 bis is well above the slanns and we shonid fregnantiy checklevel to ensee no aansnal trends are occumng =a-i.ny when we are changmg PCS level 1his 25% is about 3,000 gallons or over 2.5 fun Dirty Wase tanks so close coorriinannn 'is needed when we evenmally drain this =

i j = CV-1212 Semce Airinninnnn is Temp Mod blocked open to nuonnize loss of breatinns airin the ennemnment Breathmg Airis haian ===M from the Service Airheaderin the c anemament i

j = When the E r-- = Hach is open we shonid esabbsh and maatam the GOP-14 Vannimann U.- r 1 bis

has shown to be the lean enemminering air flow path to the SPP men, m The Pr=nnverMamray is removed. There is a foreign mannat bemermstalled winch has been venfied not to -

limit the van 4 We are usar the removed Reactor Vessel Head this for PCS Cm.-. Proaction. ,,,

m ifT-21cveleverdropspleasekeepT-2CondStorageTantlevellow, worktowardsa r.L.e =50% kr,.i. we will need this level to be low later this month to dran both SKrs to it for =----i y side ingwenan and sludge ,

J 1-w m a After the Reactor Head was off the Gange we pla.ed HPSIin service for (B] injecxion flow puh. We lined up

• P.66A and did a test run, after this we will be matemenmg its socnon and discharge power ==~ad valves closed. Au manual vatves in the path win be open. Since this is nota er===an flow pub ensme you review the

' parh fot thisinjecum a='h j

w We will be domg in=nn n=nem cm the Outer Door of the Personnel Airimck. The inner doormust retnan

einenhie Nnnnal vani1= ann lineup for sfuehng win be with both doors open, if a door needs to be closed for

< ,, ..,~,. ,, . orveniinnem reasonsit may be aaaaad - --dy forner=naaai acesss.

j sr 1he Shif1 Manger wiu nun the 0815 meenngs danng the outage, a shift enntactis needed and win 94(4 Ops stams and repon rmr== backto the shifta.

a er An 1830 outage ==neranent meetmg is heldin the Tech Suppott Center daily, please have an SE.SSar OSS an eachnight ShiftManagerwin runthe meenng .

hrs)about injury on site which requues offshe l @ Oursafety duecentneedsto be nnri treannent. VikkiJanes Beeper or 1

@ MarkHolbem's r'-= , for any %=. f f RT. or - ;- _-%- -- or -*

4 j -@ nmdE WAWRO'S PHONE Bm6 ENTER 0225 WHEN #IS REQUESTED

G. Meterological conditions are as follows:

1. Clear weather and high barometric pressure have been prevelant for several days; moderate to strong winds are from the southwest. No s inclement weather is predicted.

i. . Wind speed: 7 mph

b. Wind direction: 347=

c. Stabilty: B

d. Ambient temperature: 57aF H. Primary chemistry conditions:

1. pH: 4.77

2. Boron: 2035 ppm

3. Total beta gamma activity: 0.187 ci/ml

4. Iodine dose equivilent: 7.74pci/ml O

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l

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

PALEX 94 Date M*y 17, 1994 Hessage # 1 (Page 1) Timeg800 Scenario Time 0030 Time Juep Scenario Time Jupp SW Sumps P 7A SIBJ P 78 QN P 7C QN, SW Critical Hdr Press AM 8 97, peig CCW Puups P-52A ON P 528 Sf8Y P 52C ON FPC Pumps 'P 51A gu Fire Puips P-9A 0FF P 98 0FF P 41 0FF P-518 0,g Contairenent Cooler Rectre Fans V1A DE V2A ON v3A OFF V4A ON V18 gg V2B ON V38 OFF V48 ON L21 CCW Cooler Outlet Teep Containment Spray Puups A E F 8 (Q F P 54A 0FF P 548 0FF P 54C 0FF HPSI Pumps P 66A 0FF P-668 0FF LPS! Pumps P 67A OJL P 678 g,l safety Inleetion suction Supply Train A Train 8 CV 3057 (SIRW) CLOSED CV 3029 (SIRW) CLOSED CV 3031 (SIRW) CLOSED CV 3030 (Susp) CLOSED I.d$

CVCS Letdown Charging Intermediate Press Letdown Teep J04_ F Flow Q gpm Letdown Line fesp 104 F Line iemp 89 F Letdown Flow g gpm Puups P-55A 0FF P 558 0FF P 55C OFF Volune Centrol innk Tenp 69, F Pressure U psi Level }4 % PCP Control Bleedoff Pressure y psig Shutdown Cooling System SOCS from PCS (R) 190 F SOCS to PCS (R) E F f Quench Tank Temp 101 F Pressure O pslo Level Q %

Primary Coolant System Pressurizer Pressure (R) 13 pela PCS Tave (R) Loop 1 (TR 0111) M Loop 2 (TR 0121) 96, Pressurizer Level (R) LRC 0101A 2  % LRC 01018 0_,  % LIA 0102A d %

P2r Mtr Asps LCC 15 9 LCC 16 !

PORY PRV 10428 CLOSED PRV 10438 ClosE0 nlock Valve MOV 1042A OPCM MOV 1043A QLtN, PCPs P 50A 0FF P 508 0FF P 50C OFF P 500 gFf Reactor Power Level NI 01 JQg+0] Ml*02 .20E+02 NI 03 98E-08 NI 04 96E 08 NI 05 .12t -07 NI-06 12E 07 NI 07 12E 07 NI 08 12E-07 E 91 AFW System AFW Punp P 8A 0FF P 88 0FF P-8C OFF AFW Puup Amps P 8A 0 P-8C 9 AFW Puip P 88 Steam Pressure 0, psig AFW Disch Press P 8A & P 88 I8 P 8C 18 pel .

Secondary System MSIV Sypass MOV-0$C1 CLOSED MOV-0510 CLOSED MSiv's CV 0501 CLOSED CV-0510 CLOSED MfP Suction Prensure M psig MFP Discharge Pressure A 15 8 15 pst '

Moisture Separator Drain Tank Level 26 % Condenser Notwell Level Z1 %

Atmospheric Duip Valves CLOSED Condenser Vacuun in Ng.

9 Heater Drain Puup Status P 10AJO L P 100 g g Gland Seal Condenser Vactam 14.2 in No.

Condensate Puup Status P 2A 0FF P 28 0FF I.E (Demand Log + Constant, Rod, or Flux / Temp)

Gross MW Q Net W -] Core Exit Thermocouple Temperature 0 F Control Rod Position GP1 g GP2 Q GP3 9 GP4 9 GP5(P) 1 GP6(A) 0 GP7(8) 0 i

Stuck Rods M #9

. ., .. n__ . - . . + . . ~ . . _._ - ___ .. - . .. _ _ . . - ...

.- LA,M l l'

D:ts Fay 17. 1994 Messagt#1 (Pagt 2) Timeg890 Scenario Time 0030 Time Jump Scenario Time Junp

- Sill T 81 Level 90 % 7 939 Level 95 % Condensate Storage Tank Level T 2 ~

86 %

instrument AU Pressure @ psig

Contalement Sullding Pressure g psig Dome Tesperature 103 0 F Humidity [g %

t S/G A Compartment Temperature 8.0 F Humidity L6 1 '

S/G B Compartment Temperature g5, F Hunidity {6 %

! SIRW Tank Lewt J 8  %

WR Contalruent Pressure (R) 14 pela

' Contalruent Susp Level 181 % contalruent Water Level (R) g  %

4

$1 Tank Level (X) A 41 8 41 C 4 0 41 S1 Tank Pressure (psig) A M6 8 756 C L.1 36 0 232 l l

PANEL K 13

$!AS Alare @ Containment High Pressure Alarm $ Contalruent High Radiation Alarm . @

Concentrated Boric Acid Tank Levels T53A 199 % T538 100 % )

Reactor vessel DP 8J pald PORV Discharge Temperature 111 F Par Safety Valve Discharge Temp (F) RV 1039 125 RV 1040 140 RV 1041 175 PCP Current (Asps) P 50A Q P 508 9 P-50C. 9 P 500 g PCS Flow Q  % Pressure Level (cold) W%

Loop Thot (F) Loop 1 101 Loop 2 100 Loop Teold (F) Loop 1 B Loop 2 H l Tcold Wide range Loop 1 J 9 Loop 2 H j Subccoling Temp j04 F Press 12 psi PCS Prssure WR JJ, NR 13 pela Steam Generator A Steam Generator B Level (WR) Q  % (NR) Q  % (WR) Q  % (WR) Q  %

Press 1 psia 14 psia

= Flow Steam j PPH Feed Q PPM Steam [ PPH Feed 0' PPH Note Steam and Feed Flow X 1000000 E'11 AFW Flow to A S/G From P 8A&8 0 From P-8C 0 AFV Flow to B S/G From P 8AAB d From P 8C l Condenser vacuan (R) g PCP Saal Leakoff Flow P 50A g PPH P 508 Q PPM P 50C 9 PPH P 500 Q PPH SJ94. .

Diesel Cenerator Frequency 11 9 12 Q 1 C auS voltage 2431 Amps3 1 0 aus voltage 24n Asps 149 l l C 11 Back C 11A a Containment Area Monitors (R/Hr) RIA 1805 J21 RIA-1806 J11 RIA 1807 .02 RIA 1808 .015 4 High Range Containment Monitors (R/Hr) RIA 2321 3+01 RIA 2322 3 01 Containment Hydrogen Concentration (1) Al 2401R 9 Al 2401L 9 Main Steam Line Gasses (cpa) - RIA 2324 .23E+02 RIA*2323 .25E+02 Stack Monitors RIA 2325 309 cpn RIA 2326 .6E+02 cpn RIA 2327 J . ar/hr 1 i O l l l

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l l Scenario: PALEX-94 Time: 0831  : l Message No: 2 Scenario Time: 0001 l PALISADES NUCLEAR PLANT l i EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Control Room personnel Simulated Plant Conditions: Loss of all 2400 VAC power Message: A muffled explosion is heard in the Control Room. Busses IC and ID show 0 volts; all other busses are powered. 1-2 D/G is running, but there is no position indication for its output breaker or the other feeder breakers to bus ID. 1-1 D/G started but tripped along with its output breaker when the output breaker attempted to close. Safeguards power breaker 152-401 indicates open. O FOR CONTROLLER USE ONLY Controller Notes: Action expected: Implement ONP 17, " Loss of Shutdown Cooling". O

   -,    -,e--      ~   -

Scenario: PALEX-94 Time: 0832 Message No: 2A Scenario Time: 0002 PALISADES NUCLEAR PLANI EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Control Room Personnel Simulated Plant Conditions: Loss of all 2400 VAC power Message: The Bus 1C area is full of smoke. O FOR CONTROLLER USE ONLY Controller Notes: Message should be phoned in by simulator console operator. Action expected: Call out the plant Fire Brigade (may be simulated). O

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

Scenario: PALEX-94 Time: 0835 Message No: 3 Scenario Time: 0005 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Control Room Personnel Simulated Plant conditions: Loss of all 2400 VAC power Message: See alarm and data sheets.

O FOR CONTROLLER USE ONLY Controller Notes:

Action expected: O

                  .- .,  -           w - - . . - - .         n ,     e

_ _ _ _ _ mm_ _ __ _ . __ - -_ _ _ _ _ _. . 7 s ta v. Date M*y 17. 1994 Messtg30} (Page 1) 3 Time 9835 ScenarioTime9995 Time Jtap scenario Time Jump ESS SV Simps P 7A 0FF P 78 0FF P-7C 0FF SW Critical Hde Press A0 80 psig CCW Ptaps P-52A 0FF P 528 0FF P-52C OFF FPC Ptaps P 51A 02 Fire Purps P 9A 0FF P-98 0FF P 41 0FF 'P*518 g Contairvnent Cooler Rectre Fans VIA gg V2A 0FF V3A 0FF V4A 0FF V18 0FF V28 0FF V38 0FF V48 0FF L91 CCW Cooler outlet feno A 69 F 8 82 F Contairment Spray Ptmps P 54A 0FF P 548 0FF P 54C 0FF HPS! Purps P 66A OFF P 668 0FF LPSI Ptmps P 67A 0FF P 678 0FF Safety injection Suction Stooly Train A Train 8 CV 3057 (SIRW) CLOSED CV 3029 (SIRW) CLOSED CV 3031 (SIRW) Ct0 SED CV 3030 (Sump) CLOSED E*S$

                                                                                             -CVCS Letdown                                                                                            Charging Intermediate Press Letdown Temp             104 F                                                       Flow            0'    spn Letdown Line Tenp                           1M, F                                                       Line Temp       M F Letdown Flow                                Q       gpn                                                 Ptsps P-55A 0FF P 358 0FF P-55C OFF Volune Control Tank

T eap 69 F Pressure 21 psi Level 54 % PCP Control Bleedoff Pressure 13 psig Shutdown Coolino System SOCS from PCS (R) 79 F SOCS to PCS (R) g5 F n Quench tank

[ Teap 101 F Pressure 0 psig Level {} % Primary Coolant System Pressurizer Pressure (R) 1] psia PCS fave (R) Loop 1 (TR 0111) M Loop 2 (TR 0121) 95 Pressurizer Level (R) LRC 0101A 0  % LRC 01018 0 _% LIA 0102A 3 % Pzr Mtr Amps LCC 15 g LCC 16 9 PORY PRV 10428 CLOSED PRV 10438 CLOSED Block Valve MOV 1042A OPEN MOV 1043A OPEN PCPs P 50A 0FF P 508 0FF~ P 50C 0FF P 500 0FF Reactor Power Level N1-01 70E+02 WI 02 720E+02 NI 03 798E-08 NI 04 796E 08 NI 05 .12E 07 NI 06 .12E-07 NI 07 12E 07 N1-08 .12E 07 CE1 AFW System AFW Punp P 8A 0FF P 88 0FF P-SC 0FF AFW Ptsp Amps P-8A 9 P-8C 9 AFW Ptap P 33 Steam Pressure Q psig AFV Disch Press P 8A & P 88 19 P 8C 18 psi Secondary System MSly Bypass MOV 0501 CLOSED MOV 0510 CLOSED MSlV's CV 0501 CLOSED CV 0510 CtOSED MFP Suction Pressure H psig MFP Discharge Pressure A 15 8 15 psi Moisture Separator Drain Tank Level 26 % Condenser Notwell Level 9  %. Atmospheric Dtap Valves CJOSJ0,0 Condenser Vacuun g in Ng. Heater Drain Ptap Status P 10A 0FF P 108 0FF Gland Seal Condenser Vacuun M in Ng. Condensate Puup Status P 2A 0FF P 28 0FF E1*. (Deaund Log + Constant, Rod, or Flux / Temp) , Gross MW g Net MW 0 Core E.xit Thermoco@te Temperature 0 F 1 Control Rod Position GP1g GP2 0 GP3g GP4g CP5(P) 1 GP6(A) 0 GP7(8)g Stuck Rods M #9 a

       .        _                               . _ _ ~ - _ _        ..       _ _ _ _ . . ,__ . ,                                    . _ _ - .           __             _ >           m_ ,   _ _ _ _ .

D ts May 17. 1994 Missage # } (Paga 2) Timeg83.1 ScenarioTime9001 Time Jwp Scenario Time Jw p , d T 81 Levet 90 % T 939 Level M% Condensate Storage Tank Level T 2 g % InstrumentAIrPressure M psig g Contairment Building Pressure 9 pelg Dome Temperature 10} . F Ntaldity M % S/G A Coopertment Tenperature 83 F Hunidity M 1 S/G B Co gartment Temperature M F Hueldity M % SIRW Tank Level J 8  % W Contairment Pressure (R) 15 psia contairment Sg Level El % Contairveent Water Level (R) g  %

         $1 Tank Level (%)                                    AM                                   B 41                           C 41                         0M St Tank Pressure (paig)                              A M                                  B G                            C 236                        0 231 PANEt, K*13
         $1AS Alare M                         Contairinent High Pressure Alarm $                                                   Contairment High Radiation Alarm . M E*1$

concentrated Boric Acid Tank Levels T53A 109 % T538 100 % Reactor Vessel DP 8j psid PORY Discharge Temperature 13 F Par Safety Valve Olscharge Tenp (F) Rv 1039 36 Rv 1040 j 4_1, Av.1041 E6 PCP Current (Amps) P 50A 2 P-508 0 P-50C g P 500 g PCS Flow g  % Pressure Level (cold) M% Loop Thot (F) Loop 1 log Loop 2 102 Loop Teold (F) Loop 1 J 9 Loop 2 9j Teotd Wide range Loop 1 9 J Loop 2 91 S4 cooling Temp 105 F Press H psi PCS Prssure WR 7 NR 13 psia Steam Generator A Steam Generator B Level (WR) 2  % (NR) g  % (WR) 9  %. (NR) Q  % Press 1 psia 11 psia Flow Steam 0

                                                                ~

PPM Feed 0 PPH Steam 0 PPM F*ed 0

                                                                                                                                                                  ~

PPH Note Steam and Feed Flow X I000000 E*U AFV Flow to A S/G From P 8A&8 g From P 8C g AFW Flow to 8 S/G From P 8AA8 0 From P-8C ~0 Condenser VectAm (R) PCP Seal Leakoff Flow P 50A g PPH P 508 g PPH P 50C Q PPH P 500 g PPH E:Pi Diesel Generator Fregaency 1-1 0 12 60 1 C sus Voltage 9 Amps 9 1 0 sus Voltage g Anps g C-11 Back C-11A Contairment Area Monitors (R/Hr) RIA 1805 025 RIA-1804 .015 RIA 1807 .0 RIA 1808 E Nigh Range Contalrunent Monitors (R/Hr) RIA 2321 1E+01 RIA 2322 3 01 Contairment Hydrogen Concentration (%) Al*2401R 9 Al 2401L 9 Main Steam Line Gamme (cpm) RIA 2324 .23E+02 RIA 2323 .25E+02 Stack Monitors RIA 2325 390, cps RIA 2326 .6E+02 eps RIA 2327 d ar/hr s i n , . , - . - _ . . _ ,

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s Scenario: PRACTEX-94 Time: 0835 Message No: 3a Scenario Time: 0005 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: CAS Supervisor Message: Power has been lost to all security systems. The battery power to alarm panel has automatically energized itself. All CCTV and primary system zones are out of service. FOR CONTROLLER USE ONLY Controller Notes:

1. Provide CAS supervisor with information that the cardreader system is out of service.

2. The CAS supervisor will have to ask a responding officer to verify this.

[3 3. No CCTV assessment will be available for zone /CCTV alarms. V 4. Secondary system is available. Action expected: Player should obtain and follow the correct contingency procedure for situation. 1 i ! I v , l l i

Scenario: PRACTEX-94 Time: 0835 ()

  %,,/   Message No:          3b                              Scenario Time: 0005 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For:          Search Area Security Personnel Message:                                                    including  the Power has         been   lost to all    security systems explosive, X-Ray and metal detectors.

FOR CONTROLLER USE ONLY Controller Notes:

1. The search area security personnel should do pat searches on drill players only due to lack of search equipment. that

2. Search area security personnel should acknowledge entrance to the PA would be through door 507 with loss of entering turnstiles. They should not actually take people through door 507.

O 3. Security personnel should not silence the portal monitors and direct exiting personnel to go through them without stopping unless directed to do so by Rad Pro personnel. Action expected: See Controller Notes i 1 1 1 I 1 I ~ l

Scenario: PALEX-94 Time: 0844 Message No: 4 Scenario Time: 0014 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Control Room Personnel Simulated Plant Conditions: Loss of all 2400 VAC power Message: Smoke is clearing out of the Bus 1C area; there is no fire. Safeguards / station power feeder breaker 152-105 is destroyed and adjacent breakers are damaged. O FOR CONTROLLER USE ONLY Controller Notes: Message should be phoned in by the simulator console operator if the plant Fire Brigade has been simulated. Action expected: 4 I I O l

m Scenario: PALEX-94 Time: 0845 Message No: 5 s Scenario Time: 0015 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Control Room Personnel Simulated Plant Conditions: Loss of all 2400 VAC power Message: See alarm and data sheets O FOR CONTROLLER USE ONLY Controller Notes: Action expected: , 1. Dispatch operators to clear service lines from the Equipment Hatch and commence water-sealing the Fuel Transfer Tube.

2. Alert Maintenance to the need to close the Equipment Hatch.

O V

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W.Lt A yde Date May 17. 1994 Message # 5 (Page 1) Time 0845 Scenario Time 0015 Time Juup Scenario Time Junp E90 p SW Sumps P 7A 0FF P 78 0FF P-7C 0FF SW Critical sde Press A5 85 psiS , t CCW Pumps P 52A 0FF P 52B OFF P 52C OFF FPC Pumps P 51A DE

   \             Fire Puups       P 9A 0FF               P 98 0FF              P 41 ON                                                       'P 518 0FF Contairvnent Cooler Rectre Fans
 .                     VIA OE      V2A of            V3A 0FF        V4A 0FF                                                      V18 0FF           V2B 0FF          V38 0FF     V48 0FF 1

L91 CCW Cooler outlet Tenp A 68 F S 81 F Contairvnent Spray Puups P 54A 0FF P-548 0FF P-54C 0FF HPSI Purps P 66A 0FF P-668 0FF LPSI Puips P 67A 03 P-678 03 Safety Inleetion Suction Stcoly i Train A Train B i CV-3057 (SIRW) CLOSED CV 3029 (SIRW) CLOSED CV 3031 (SIRW) CLOSED CV 3030 (Susp) CLOSED i 0 g ,0,,3 C_vli letdown Charolm Intermediate Press Letdown Teep 104 F Flow 0 ppm Letdown Line Temp 104_ F Line Temp 96 F Letdown Flow Q gun Puups P 55A 0FF P 558 0FF P-55C OE volune Control tank Temp 69 7 Pressure 21 psi Level 54 4  % PCP Control 8teedoff Pressure 13, psig Shutdown Cooling System SOCS f rom PCS (R) [0 F SDCS to PCS (R) H F Quench Tank

             .                                            Temp 101 F                 Pressure O                psig                         Level 63 %

Primary Coolant System Pressurizer Pressure (R) 13 psia PCS Tave (R) Loop 1 (TR 0111) 95,, Loop 2 (TR-0121) 95 Pressurizer Level (R) LRC-0101A 9  % LRC 01018 0  % LIA 0102A' d % Ptr Mtr Asps LCC 15 9 LCC 16 g PORV PRV 10428 CLOSED oRV 10438 CLOSED Block Valve MOV 1042A OPEN MOV 1043A QP_EN PCPs P-50A 0FF P 508 0FF P 50C OFF P-50D OFF Reactor Power Level NI 01 .20E+02 NI 02 .20E+02 N!-03 98E 08 N! 04 .96E 08 NI-05 .12E 07 NI 06 EEgCZ NI 07 .12E 07 NI 08 .12E 07 C.:.91 AFV system AFW Puip P 8A 0FF P 88 0FF P 8C OFF AFW Puup Amps P 8A g P 8C 9 AFW Puip P 88 Steam Pressure g psig AFW Olsch Press P 8A & P 88 18 P 8C 18 psi secondary System MSIV Sypass MOV 0501 CLOSED Mov-0510 CLOSED MSIV's CV 0501 CLOSED CV 0510 CLOSED MFP Suction Pressure 15, psig MFP Discharge Pressure A 15 8 15 psi Moisture Separator Drain Tank Level 14 % Condenser Hotwell Level 9  % Atmospheric Duip Valves CLOSED Condenser Vacuun g in Hg. Heater Drain Puup Status P 10A 0FF P-100 0FF Gland Seal Condenser Vacuun 14.2 in Hg. Condensate Puup Status P 2A DE P28pff, f.LP, (Demand Log + Constant, Rod, or Flux /lenp) Gross MW g Net MW 9 Core Exit Thermocotple Tenperature 2 F GP7(8)g Control Rod Position CP1g GP2 g GP3 9 GP4 0,, GP5(P) 1 GP6(A) 0 Stuck Rods N,9Ng #0  ! i l I

Data May 17. 1994 Messigt#1 (Pega 2) Time 0845 Scenario Time 0015 iime Jurp Scenario Time Jug

         $~.11 T-81 Level 90 %        T 939 Level       9,6    %                     condensate Storage Tank Level T 2        !! %

(ph Instrument AU Pressure g psig

 \j Contairusent Building Pressure                g      psig                  Dane Temperature 1,02 F       Hunidity {8 %

S/G A compartment. Temperature g6 F Hunidity 43 % S/G B Ccupartment Tesperature ] 8 F Hunidi ty 41 % SIRW Tank Levet 31, % WR Contelnment Pressure (R) H psia Containment Sump Level 59) % containment Water Level (R) g  % SI Tank Level (%) A 41 8 41 C 41 D 41 St Tank Pressure (psig) A gj! 8 238 C 238 0 233 PANEL Kal) S!AS Alarm M Containment High Pressure Alarm g Containment High Radiation Alarm g M Concentrated Boric Acid Tank Levels T53A 100 % T538 100 % Reactor Vessel DP 8J psid PORY Discharge Temperature M2 F Pzr Safety Valve Discharge Teno (F) Rv 1039 Hg Rv 1040 141 Rv 1041 176 PCP Current (Amps) P-50A g P-508 g P-50C 9 P-500 g PCS Flow 0  % Pressure Level (cold) "~

                                                                                                  -2.9 %

Loop Thot (F) Loop 1 109 Loop 2 199 Loop Teold (F) Loop 1 9,1 Loop 2 9 J Teold Wide range Loop 1 ,91 Loop 2 9 J

         $@ cooling                   Tenp       106 F           Press     L2 pst PCS Prssure                  WR         M               NR        L3      psia steam Generator A                                 Steam Generator B Level                        (WR)       9      %        (NR)      9     %      (WR)      g    %      (NR)     9       %

Press 1 psia 14, psia Flow Steam Q PPH Feed g PPH Steam 9 PPM Feed 2 PPH Note Steam and Feed Flow X 1000000 C.3 AFW Flow to A S/G From P 8A&B g From P 8C 9 AFW Flow to 8 S/G From P-8A&8 9 from P 8C 0, Condenser Vactam (R) 9 PCP Seal Leakoff Flow P 50A g PPH P 508 9 PPH P-50C g PPH P 500 g PPM S2.96 I Diesel Generator Frequer.cy 1-1 0 12 60 1 C BUS Voltage 9 Asps 9 1 D BUS Voltage g Asps 9 C-11 Back C 11A Containment Area Monitors (R/Hr) RfA 1805 .025 RIA 1806 JM RIA 1807 g RIA 1808 g j High Range Containment Monitors (R/Mr) RIA 2321 .1E+01 RIA 2322 .1E+01 Containment Hydrogen Concentration (%) Al 2401R 9 Al 2401L g Main Steam Line Gamma (cpn) RIA 2324 ,23E+02 RIA 2323 .25E+02 I Stack Monitors RIA 2325 309 cpn RIA 2326 .6E+02 epm RIA 2327 J mr/hr C (.

                .           __    ~.                   . - - .                                       . . . . -     -                   - - .                                -..             .

1 1 PALEX-94 TIME b #88A * -~ SCENARIO TIME bOl5 ANNUNCIATOR DISPLAYS K-01

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i Scenario: PALEX-94 Time: 0846 i Message No: SX (Contingency) Scenario Time: 0016 4 PALISADES NUCLEAR PLAMI EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Shift Supervisor Simulated Plant Conditions: Loss of all 2400 VAC power Message: Declare an ALERT based on " Engineered Safety Features - Complete loss of any functions needed for plant cold shutdown" or " Plant Power Electrical - Loss of offsite and onsite power for less than 15 minutes." Either category is appropriate. 'f 8 O FOR CONTROLLER USE ONLY Controller Notes: This message may be delayed for as long as 5 minutes if declaration appears imminent. 4 J Action expected: O

Scenario: PALEX-94 Time: 0850 Message No: 6 p) g Scenario Time: 0020 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Control Room Personnel Simulated Plant conditions: Loss of all 2400 VAC power Message: Breaker 72-402 has been found open on DC Panel D21A in the 1-2 D/G Room. O FOR CONTROLLER USE ONLY Controller Notes:

1. Message must be phoned in by an A0 at this time regardless of whether ONP 20 troubleshooting actions have been invoked by ONP 17 to prevent needing to escalate to SAE classification.

2. If either P-67A LPSI or P-66A HPSI is started after Bus 10 is repowered, it must trip immediately.

Action expected: Close 72-402, which will permit 0/G l-2 output breaker to close to repower Bus ID. O

Scenario: PALEX-94 Time: 0053 Message No: 7 Scenario Time: 0023

    . ,O PALISADES NUCLEAR PLANT

. EMERGENCY PREPAREDNESS EXERCISE FORM 1 Message For: Control Room Personnel i Simulated Plant Conditions: Restoration of Bus 10 4 , Message: l Bus 10 has been repowered by 1-2 D/G. See attached alarm and data sheets. k O FOR CONTROLLER USE ONLY controller Notes: l Action expected:

1. Attempt to restore Shutdown Cooling by starting P-67A LPSI Pump; the pump will cavitate heavily due to the low PCS level and trip.

2. Alert maintenance to the inability to align Fuel Handling Building

. Venti 11ation to exhaust via charcoal filters. O 1

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ruta v. Date Mty 17, 1994 Mess 19e#Z (Page 1) Time 0853 ScenarioTime20_23 fine Jug Scenario flee Jump E*98 SV Surps P 7A ON P 7B 0FF P 7C ON SW Critical Nde Press A 97 89Z psig CCW Ptsps P-52A OE P-528 ON P 52C OFF FPC Pumps P 51A Og

    %              Fire Puips     P 9A 0FF                P 98 0FF                P*41 ON                                                                       'P-518 Og Contairunent Cooler Recire Fans V1A ON      V2A ON             V3A ON         V4A 0FF                                                                        V1B 0FF                 V28 0FF                                     V3B 0FF              v4e OFF d

CCW Cooler Outlet Teny A 39 F B 40 F Contairveent Spray Flaps P 54A 0FF P 548 0FF P 54C OE J HPSI Ptsps P-66A 0FF P 668 0FF LPSI Pumps P-67A 0FF P 67B 0FF Safety injection Suction Supply .! Train A Train B CV 3057 (SIRW) Closed CV-3029 ($1RW) CLOSED CV 3031 (SIRW) CLOSED CV-3030 (Susp) CLOSED E*S2 CVCS Letdown Charging Internediate Press Letdown Temp 104 F Flow 0 spo Letdown Line fewp 1% F Line Tenp J F 9 Letdown Flow 0 gpm Ptaps P 55A 0FF P 558 0FF P-55C OFF Volune Control Tank Tenp 69 F Pressure 21 psi Level 54,  % PCP Control Bleedoff Pressure 13, psig , Shutdown Cooling System SOCS from PCS (R) ,100 F SDCS to PCS (R) 91 F Quench Tank Temp 101 F Pressure O psig Level Q % Primary Coolant System Pressurizer Pressure (R) 13 psia PCS Tave (R) Loop 1 (TR 0111) $ Loop 2 (TR 0121) 95 Pressuriger Level (R) LRC 0101A 9  % LRC-0101B 9  % LIA-0102A 13 % Par Mtr Anps LCC 15 0 LCC 16 0 PORY PRV 10428 CLOSED PRV 10438 CLOSED Block Valve MOV 1042A gpEi! MOV 1043A gP1N PCPs P 50A gH P 508 0FF P 50C OFF P 500 0FF Reactor Power Level N!-01 .20E+02 NI*02 .20F+02 N! 03 .98E 08 NI 04 96E 08 NI 05 12E-07 NI 06 .12E 07 NI 07 .12E 07 NI 06 .12E 07 Edl AFW System AFW Pwp P 8A OE P 88 0FF P 8C OFF AFW Punp Asaps P 8A 9 P 8C 0 AFW Puip P*B8 Steam Pressure g psig AFW Disch Press P 8A & P-88 18 P 8C 18 pal Secondary System MSIV Bypass MOV 0501 CLOSED MOV 0510 CLOSED MS!V's CV 0501 CLOSED CV 0510 CLOSED MFP Suction Pressure 15 psig MFP Discharge Pressure A 15 B 15 pel Moisture separator Drain Tank Level ,14, % Cordenser Hotwell Level 81 % Atmospheric Dump Valves CLOSED Condenser Vacuun Q in Hg. Heater Drain Pusp Status P 10A 0FF P-108 0FF Glard Seal Condenser Vacuun 14.2 in Hg. Condensate Pump Status P 2A 0FF P 28 0FF P,1, (Demand Log + Constant, Rod, or Flux / Temp) Gross MW p Net MW D Core Exit Thermocouple Temperature 0 F Control Rod Position GP1g CP2 0 GP3 0 GP4 0 GP5(P) 1 GP6(A)2 GP7(B) O Stuck Rods NONE #0

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

                                                                  .                          .      . _u-           ..      .           .-                .           -               _                  - . . _ .

Date May 17, 1994 Mirssage # Z (Paga 2) Time 0@5,1 Scersrlo Time 9011

• Time Jump Scenario Time Junp E*11 T 81 Level 90 % T 939 Level 96 % condensate Storage Tank Level T 2 as %

b InstrumentAIrPressure 5 psig Q Contalruent Sullding Pressure S/G A coupertment g psig Dome Temperature 10,} F tesperature g} F Htmldity 28 % Htnidity 19 % S/G 8 Compartment Temperature g, F Humidity },2  % SIRW Tank Level J 8  % WR Containment Pressure (R) 15 psia contairment Sump Level 5ag % Contairment Water Level (R) 9  %

        $1 Tank Level (%)                                                     A 41        ~                      8 41                         C 41                               D 41 St Tank Pressure (psig)                                              A          l3Z3                     8 13Z                        C 13Z                              D $

PANEL K 13 SIAS Alarm jfg Contalmnent High Pressure Alarm Ng Containnent High Radiation Alarm N_Q U1$ concentrated Boric Acid Tank Levels T53A 109 % T538 100 % Reactor Vessel DP 8, psid PORY Discharge Temperature @1 F P2r Safety Valve Olscharge Tenp (F) RV-1039 126 Rv 1040 141 RV 1041 IZs PCP Current (Asps) P 50A g P 508 g P 50C 9 P 500 g PCS Flow Q  % Pressure Level (cold) -j  % Loop Thot (F) Loop 1 100_ Loop 2 100 Loop Teold (F) Loop 1 91 Loop 2 9.1 Teold Wide range Loop 1 91 Loop 2 _91,

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Press 1 psia 14 psia Flow Steam 0

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Scenario: PRACTEX-94 Time: 0853 O ' Message No: 7a PALISADES NUCLEAR PLANT Scenario Time: 0023 EMERGENCY PREPAREDNESS EXERCISE FORM Message For: CAS Supervisor Message: Power has been restored to all security systems. All systems, including RS-40 and cardreaders are working. r FOR CONTROLLER USE ONLY l Controller Notes: l The lead controller in the control Room should contact hte s Security Controller to ler them know when power is restored. Action expected:

1. Notify proper personnel that cardreader system power has been restored according to procedures.

O 2. Ensure that cardreader system is tested procedures (may_ be simulated but CAS/SAS supervisor must state according to proper procedure to follow.) i a e t 0

Scenario: PRACTEX-94 Time: 0853 O Message No: 7b Scenario Time: 0023 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM J Message For: Search Area Security Personnel Message: Power has been restored to all security systems including the explosive, X-Ray and metal detectors. 1 FOR CONTROLLER USE ONLY t Controller Notes:

1. The search area security personnel should no longer do pat searches on drill players.

2. PA access should return to entering turnstiles for drill players.

l Action expected: . See Controller Notes 4 i

O

Scenario: PALEX-94 Time: 0855 Message No: 8 p Scenario Time: 0025 PALISADES NUCLEAR P_LAE EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Control Room Personnel Simulated Plant Conditions: Message: " Reactor Water Level Low" alarm (EK-07 #48) has just been received. LIA-0105 (wide range) indicates 10%, and LIA-0106 indicates 50%. O V FOR C0KTROLLER USE ONLY Controller Notes: Action expected: Operators will attempt to start P-66A HPSI Pump, which will go to runout and trip. Maintenance efforts will then be focused on restoring the Charging System lineup and reassembling M0-2160. O

Scenario: PALEX-94 Time: 0900 Message No: 9 Scenario Time: 0030 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Control Room Personnel Simulated Plant Conditions: Message: See alarm and data sheets. FOR CONTROLLER USE ONLY Controller Notes: PCS temperature is now approximately 155 degrees F, although the operators have no way of measuring PCS temperature. As the PCS expands it leaks from the S/G 'A' primary manways, resulting in a constant RV level of 618'2.5". Action expected: O

FF.LR A Yee Date M*y 17. 1994 Messaga # 9 (Ptga 1) Time 2 00 ScenarioTime0039 3 Time Jtap Scenario Time Ju g SW Surps P 7A ON P 78 0FF P 7C ON SW Critical Hdr Press A 97 8 97 psig CCW Ptsps P 52A og P-528 ON P 52C OFF FPC Ptmps P 51A 03 Fire Pumps P-9A 0 3 P-98 0FF P 41 ON 'P 518 pf,1 . Contairvnent Cooler Rectre Fans VIA ON V2A Om V3A ON V4A 0FF V1B 02 V2B 0FF V38 0FF V48 0FF S .0.1 CCW Cooler thatlet Terup A 39 F 8 40 F Contalrinent Spray Pugs P 54A 0FF P-548 0FF P 54C OFF HPS! Purps P-66A 0FF P 668 0FF LPSI Ptaps P-67A 0FF P 67B 0FF Safety injection Suction Supply Train A Train 8 CV 3057 ($1RW) CLOSED CV 3029 (S!RW) CLO!!D CV 3031 ($1RW) CLOSED CV-3030 (Sump) CLOSED C,, ,9,{ ESS Letdown Charoina Intermediate Press Letdown Temp 104 F Flow 0 gpn Letdown Line Teep 104 F Line Temp H F Letdown Flow 0 gpm Purps P-SSA 0FF P-558 0FF P 55C 9F,f, Volune Control Tank Temp 69 F Pressure 21 psi Level M % PCP Control Bleedoff Pressure 13 psig Shutdown Cooling System SDCS from PCS (R) 109 F SDCS to PCS (R) H F p Quench Tank Temp 101 F Pressure o psig Level M % Primary Coo l ant System Pressurizer Pressure (R) 13, psia PCS Tave (R) Loop 1 (TR-0111) 95_ Loop 2 (TR 0121) M Pressurizer Level (R) LRC-0101A Q  % LRC 01018 9  % LIA-0102A -33  % Pzr Htr Asps LCC 15 g LCC 16 0 PORY PRV 10428 CLOSED PRV-10438 CLOSED Block Valve MOV-1042A OPEN MOV 1043A OPEN PCPs P-50A 0FF P 508 0FF P 50C OFF P-50D OFF Reactor Power Level NI 01 .20E+02 NI 02 .20E+02 NI 03 .98E 08 N! 04 796E-08 NI 05 .12E-07 WI-06 .12E -07 NI 07 .12E-07 NI 08 .12E 07 C-01

     ~

AFW System ' AFW Ptsp P 8A 0FF P 88 0FF P 8C OFF AFW Ptap Amps P 8A 9 P 8C g AFW Ptsp P-88 Steam Pressure 2 psig AFW Disch Press P-8A & P 88 18 P-8C 18 psi Secondary System MSIV Bypass MOV-0501 CLOSED MOV 0510 CLOSED MSIV's CV 0501 CLOSED CV 0510 CLOSED MFP Suction Pressure 15 psig MFP Discharge Pressure A 15 8 15 psi Moisture separator Drain Tant Level 14 % Condenser Hotwell Level 81,  % Atmospheric Dtmp Valves CLOSED Condenser Vacuun Q in Ng. Heater Drain Pump Status P 10A 0FF P 108 0FF Gland Seal Condenser Vacuun M in Hg. Condensate Ptmp Status P 2A 0FF P 28 0FF E.LP (Demand Log + Constant, Rod, or Flux /Tenp) Gross NW Q Net MW 9 Core Exit ThermocoLple Temperature. O, F Control Rod Position GP1g top 0 GP3p GP4 Q GP5(P)1 GP6(A)p GP7(8)g Stuck Rods - Ji,9N,iE, #9

D:ta May 17. 1994 Messtge # 9 (Pass 2) Time 0900 ScenarioTime2039 Time Juip Scenario Time Junp

        . tll T 81 Level 3 %           T 939 Level        94 %                              Cordensate Storage Tank Level T 2                 Ds %

f Instrument Air Pressure g4 psig

, t N      Contalrument Buildirg Pressure              9      psig                       Dome Temperature 10} F                  Humidity (( %

S/G A Caspartment Temperature g} F Humidity }p % S/G B Compartment Teaperature g6 F Hunidity }g % SIRW Tank Level  !! % WR Contairument Pressure (R) 15 psia contairement Simp Level 131 % Omsliennt Water Levet (R) g  % St Tonk Levet (%) A 41 B 41 C 41 0 41~ St Tank Pressure (psig) A 2}Z B gj3? C JJ3.? D 2]3 PANEL K 13 SIAS Alarm N9 Contalrsnent High Pressure Alann g Contairment High Radiation Alarm NQ E'll Concentrated Boric Acid Tank Levels T53A 100 % T533 100 % Reactor Vessel DP J 8 psid PORV Olscharge Temperature 111 F P2r Safety Valve Discharge Tenp (F) RV-1039 126 Rv 1040 141 RV-1041 176 PCP Current (Asps) P-50A Q P-506 S P 50C 9 P 500 g PCS Flow g  % Pressure Level (cold) d  % ' Loop Thot (F) Loop 1 10,0 Locp 2 102 Loop Tcold (F) Loop 1 91 Loop 2 91 Teotd Wide range Loop 1 9J Loop 2 91 SthcooLing iesp 106 F Press 12 psi PCS Prasure WR jj, NR j)3 psia Stean Generator A Steam Generator B Level (WR) 9  % (NR) Q  % (WR) 0,  % (NR) Q  % Press 1 psia 14 psia Flow Steara O

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PPH Feed 0 PPH Steam 0 PPH Feed 0

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PPM Note: Steam and Feed Flow X I000000

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i I PALEZ-94 TIME: _O9 O MESSAGE Not , SCENARIO TIME: oOAo O M[NUNCIATOR DISPLAYS l K-01 l i

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Scenario: PALEX-94 Time: 0915 Message No: 10 Scenario Time: 0045 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Control Room personnel I Simulated Plant Conditions: 4 Message: See data sheets. Alarm status is unchanged. 4 O FOR CONTROLLER USE ONLY Controller Notes: PCS temperature is now approximately 183 degrees F. Action expected: . Operate all available Containment Air Coolers and place Containment Hydrogen Monitoring in service. O

PAL.t A W Date F:ey 17, 1994 nessagt#19 (Page 1) Time 99J5, scenario Time 0045, Time Jusp , Scenario Time Juup i*90 SW Susps P 7A ON P 78 0FF P*7C ON SW Critical Hdr Press A 97 8 97 psig CCW Pumps P 52A 0FF P 528 ON P 52C 03 FPC Ptsps P 51A 0ff Fire Putps P-9A O ff,, P 98 off, P 41 ON P 518 0FF Contairvnent Cooler Rectre Fans V1A ON V2A ON V3A ON V4A 0FF V1B 0FF V2B 0FF V38 0FF V4B 0FF

                  $$3 CCV Cooler Outlet Teep                           A        39 F        B        40 F Contairment spray Ptsps                          P 54A 0FF            P 148 OFF                      P 54C OFF HPSI Pumps                                       P 66A 0FF            P 668 0FF                      LPSI Ptsps                                             P 67A 0FF                                                P 678 0FF Safety Inlection Suction S a ty Train A                                                                                                                                    Train 8 CV 3057 (SIRW) CLOSED CV 3029 (SIRW) CLOSED                                                                                                       CV 3031 ($1RW) CLOSED CV 3030 (Sump) CLOSED C
                  ~

02 CVCS

                                                                                                                 ~

Letdown Charging Intermediate Press Letdown Tesp 104 F Flow a gpa Letdown Line Tesp 104, F Line Tesp $ F Letdown Flow Q gpn Purps P 55A 0FF P 558 0FF P 55C OFF Volune Control Tank Teno 69 F Pressure 21, psi Level g4 1 PCP Control Bleedoff Pressure jJ3, pelg Shutdown Cooling System SDCS from PCS (R) j00 F SOCS to PCS (R) $ F Ouench Tank Teap 101 F Pressure 0 peig Level Q % Primary Coolant System Pressurizer Pressure (R) j] psia PCS Teve (R) Loop 1 (TR 0111) M Loop 2 (TR*0121) M Pressurizer Level (R) LRC 0101A 0  % LRC 01018 9  % LIA 010.2A d % Pzr Mtr Aaps LCC 15 g LCC 16 9 PORV PRV 10426 CLOSED PRV 10438 CLOSED Block Valve MOV 1042A og MOV 1043A gPEj! PCPs P 50A 0FF P 506 0FF P 50C OFF P 500 0*F ' Reactor Power Level NI 01 20E+02 NI 02 .20E+02 NI 03 % 03 NI 04 "WE 08 NI 05 12E 07 NI 06 12E 07 N1 07 .12E-07 NI 08 12E 07 Edl AFW System AFW Punp P 8A 0FF P 88 0FF P 8C OFF AFW Puup Asps P 8A 0, P-8C 9 AFW Pump P 8B Steam Pressure g psig AFW Disch Press P 8A 4 P 88 j,8 P-8C 18, pal Secondary System MSiv typass MOV 0501 CLOSED MOV 0510 Ct0 SED MSIV's CV 0501 CLOSED CV-0510 CLOSto MFP Suction Pressure M psig MFP Discharge Pressure A 15 B 15 pal Moisture Separator Drain Tank Level 14,  % Condenser Hotwell Level 91 % Atmospheric Dump Valves CLOSED Condenser Vacuun g in Hg.- Heater Drain Puup Status P 10A 0FF P 108 0FF Gland Seal Condenser Vacuun jM, in Ng. Condensate Puup Status P-2A 0FF P 28 0FF IE (Demand Log + Constant, Rod, or Flux / Temp) Gross W 9 Net W g Core Exit Thermocotple fer.perature g F Control Rod Position GP1 g GP29 GP3 0 GP4g GP5(P)j, GP6(A) 0 GP7(B) g a O

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_.__- --. . .. _ . - _ _ - . . - - . - - - . . . -_ . ..- - ~_-. _ - _ - - - . " . 0:te May it 19o4 Message #ja (Pcgs 2) Time Eli scenarioTime9045 Time Jurp Scenarlo Time Jwp S211 T 81 Level 90 % T 939 Level 96 % Condensate Storage Tank Level T 2 gg % fratrument Air Pressure M psig Containment Sullding Pressure g psig Dome Te.perature _10J F Hunidity {g % S/G A Compartment Teeperature gf F Husidity 50 % l S/G B Compartment Temperature g4 F Hunidity @ % SIRW Tank Levet J 8  % WR Contairuumt Pressure (R) 15 Contalrunent Swp Levet @ psia% centairment Water Levet (R) 9  % , St Tank Levet (%) A 41 8 41 C 41, . D 4J St Tank Pressure (psig) A jE lt jE CM D L33 PANEL E-13 SIAS Alarm $ Contairunent High PrestJre Alarm $ Contairment High Radiation Alarm g S:ll Concentrated Boric Acid Tank Levels 153A 1Q9 % T538 100 % Reactor Vessel DP M paid PORY Discharge Temperature fj{ F Par Safety Valve Discharge Temp (F) RV 1039 126 RV 1040 1st Rv 1041 17.g

        - PCP Current (Asps)           P 50A     9                    P 508          9                        P 50C       Q                   P 500        9 PCS Flow                               .Q     %             Pressure Level (cold)                               ;}      %

i Loop Thot (F) Loop 1 1QQ Loop 2 j.0.2 . Loop Teotd (F) Loop 1 9,1 Loop 2 9_1 Teotd Wide range Loop 1 91 Loop 2 9) Subcooling Temp 106 F Press 12 psi PCS Prssure WR [ NR j33 psia Steam Generator A Steam Generator 8 Level (WR) 0  % (NR) g  % (WR) Q  % (NR) 9  % Press } psia j4, psia Flow Steam 9 PPM Feed g PPH Steam 0 PPM Feed Q PPH Note: Steam and Feed Flow X I000000

          $*11 AFW Flow to A S/G        Fran P 8A&8 9                   From P 8C 9 AFW Flow to 8 S/G        From P 8A&8 0                   From P 8C ~       0 Condenser vacuus (R)                   y PCP Seal Leakoff Flow        P 50A     9      PPH           P 508          g        PPM             P 50C       9    PPH           P+500        9    PPH S:54 Olesel Generator Frequency        11 0                           12 6_0 1 C SUS                      Voltage !                         Amps 9 1 0 SUS                      Voltage ZL32                      Amps g C 11 Sack C 11A Containment Area Monitors (R/Hr)                           RIA 1805 J21                              RIA 1806 A15 alA 1807 fg                               RIA 1808 J1}

High Range Contalraent Monitors (R/Mr) RIA 2321 .1E+01 RIA 2322 dg+,01 0 Containment Hydrogen Concentration (%) Al 2401R 9 Al 2401L g Main Steam Line Gasume (cpe) RIA 2324 .23t+02 RIA 2323 .25E+02 Stack Monitors RIA 2325 igo, cpn RIA 2326 .6E+02 cpm RIA 2327 d ar/hr I

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

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Scenario: PALEX-94 Time: 0925 Message No: 11 Scenario Time: 0055 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Control Room Personnel Simulated Plant Conditions: Message:

      " Cont. H2 Mont. C-161 (or C-162) High" (EK-02 #3 or #4) alarm has been received; left/right channel of Containment Hydrogen Monitoring (whichever was placed in service) AI-240ll (or R) is full scale high.

FOR CONTROLLER USE ONLY Controller Notes: Defer message until a channel of hydrogen monitoring is placed in service. Action expected: 1 Place other channel in service to confirm alarm; it will indicate 0%. l 1 l

                                                                                                              )

1 O

Scenario: PALEX-94 Time: 0930 Message No: 12 Scenario Time: 0100 PAllSADES NUCLEAR PLANT EHERGENCY PREPARE 0 NESS EXERCISE FORM Hessage For: Control Room personnel Simulated Plant Conditions: Hessage: See alarm and data sheets, O V FOR CONTROLLER USE ONLY controller Notes: The PCS is now approximately 210 degrees F and has begun to boil. Action expected: Classification should be upgraded to a minimum of SAE by this time. The decision to do so will have to be based on factors other than actual PCS temperature measurement, as this is unavailable. If players decide to classify the event as General Emergency in less than 60 minutes from the declaration of the ALERT, the Lead controller in the facility that has command and control must intervene and prevent General Emergency declaration to preserve the integrity of the offsite scenario. Players should be given credit for the classification and instructed to provide the information via notification form at the appropriate time.

]                                                                    .

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WLtA V4 Oste M*y 17. 1994 Messigt # 12 (P gt 1) Time 99.Jg scercrioflee9100 Time Jum $cenario item Junp kS$

    $W lwpe        P 7A ON           P 78 0FF          P 7C ON             SW Critical Hde Press            A 94                      8 94 psig g    CCW Ptros      P 52A 03          P 528 @           P 52C Of            FPC Puvs                    P 51A 02
 \   Fire Purps    P 9A 0FF          P 90 0FF          P 41 ON                                        ~P 518 02 Contairment Cooler Recire Fani VIA ON     V2A ON       V3A DN       V4A 02                                        V18 ON       V28 ON        V38 ON      V48 0FF C.M CCV Cooler Outlet Temp         A      40 F        8      42 F Contairment Spray Ptsps        P 54A 0FF          0 hs O'T             P 54C OFF HPSI Purps                     P 66A 0"           P 668 0FF            LPS! Punps                P 67A 0FF                P 678 0FF
                                                        $afety injection Suetion $twty train A                                                                                 Train 8 CV 3057 (slRV) ClosE0 CV 3029 (SIRW) Closed                                            CV 3031 (SIRV) CLOSED CV 3030 (Stap) CLOSED dl C

gvCS, letdown Charging Intermediate Press Letdown Teap 104 F Flow 0 gpm Letdown Line Tenp MF Line Temp 98 F Letdown Flow g gpn Punps P 55A 0FF P 558 0FF P 55C OFF Volune Control tank Tenp 60 F Pressure 21 psi Level M % PCP Control Bleedoff Pressure 3 1,3 psig Shutdown Cooling System SDCS from PCS (R) 102 0 7 SOCS to PCS (R) 090 F p Quench Tank tenp 101 F Pressure 0 psig Level 63 % Prinury Coolant System Pressurlier Pressure (R) 1} psia PCS Teve (R) Loop 1 (TR 0111) M Loop 2 (TR 0121) 91 Pressurlier Level (R) LRC 0101A g  % LRC 01018 0  % LIA 0102A 3 % Par Mtr Anps LCC 15 g LCC 16 9 PORV PRV 10428 CLOSED PRV 10438 Closed Block Valve mV 1042A OPEN MOV 1043A OPEN PCPs P 50A 077 P 500 0FF P 50C OFF P 500 0FF Reactor Power Level NI 01 3E+02 Ni-02 3E+02 NI 03 28E 08 N! 04 96E-08 Wl 05 21 ]J, 0,] NI 06 .12E 07 NI 07 .s12L91 NI 08 .12E 07 C2 AFV System AFW Puip P 8A 0FF P 88 0FF P 8C OFF AFW Purp Asps P 8A Q P 8C Q AFW Pump P 88 Steam Pressure O psig AFW Disch Press P 8A & P 88 18 P 8C 18 psi secondary System MSiv Sypass MOV 0501 Closed MOV 0510 ClosE0 Ms!V's CV 0501 CLOSED CV 0510 ClosE0 MFP Suction Pressure 15, psig MFP Oischarge Pressure A 15 8 15 psi Moisture Seoarator Drain Tank Level 3 % Condenser Hotwell Level 81 % AtmosMeric Otmp Valves CLOSED Condenser Vacuun Q in Hg. Heater Drain Ptep Status P 10A 0FF P 108 0FF Gland Seal Condenser Vacuun 1M in Ng. Condensate Ptnp Status P 2A 0FF P 28 0FF M (Demand Los + Constant, Rod, or Flux / Teep) Gross MW g Net NW p Core Exit Thermoco@ le Tenperature 0 F q Control Rod Position GP1g GP2 0 GP3g GP4 0 GP5(P)1 GP6(A) 0 GP7(8){ l #0 O Stuck Rods NONE

       . .        . .-. _1-    _ -             _ _ _ _ _ _ _           m   - _- . . . = _                        ,   _ . . - - _ _ _    . _ _ . _ - . _ _                   . . _ . _ . _ _ . _ _ _ _ _ . _ - - _ _

D2te May 17.1994 Misstgi#j,{ (Page 2) Time 99 Q J scenarioTime0j,gg Time Juip scenarlo Time Jupp 8

                  $'.ll T 81 Levet 90 %         T 939 Level              9,.s     X                                  condensate storage Tank Level T*2                                    Os %

fristrument air Pressure 9J psig Contalrunent Building Pressure g pulg Dome Teeperature WO F Hualdity 27 %

                  $/G A Compartment                                                                            Teeperature                  8.1 F               Hunidity 6%
                  $/G B Ccepartment                                                                            Tenperature                  M F                        Hueldity 14 %

SIRW Tank Level 81 % W Contalresent Pressure (R) ;j: pela Contalrunent susp Levet jg % Contairment Water Level (R) Q  %

                  $1 Tank Level (%)                             A 4J                              8 41                                  C 41                                  D 41 St Tank Pressure (psig)                       A Q                                8 h                                  C g)3s                                D 2J3,{

PANEL K 13

                  $lAS Alarm M                    Contairmeent High Pressure Alarm M                                                     Contalroent High Radiation Alarm NO
                  $ *.l.$

Concentrated Boric Acid Tank Levels 153A 199 % 1538 100 % Reactor Vessel DP 83 paid 2 PORY Discharge Teseperature 1,1_2 F P2r Safety Valve Discharge Temp (F) RV 1039 126 Rv 1040 141 Rv 1041 176 PCP Current (Amps) P+50A 9 P-508 [~ P 50C 9 P 500 g PCS Flow Q  % Pressure Level (cold) J  % Loop Thot (F) Loop 1 199 Loop 2 ,1_og Loop Tcold (F) Loop 1 91 Loop 2 91 Tcold Wide range Loop 1 6 Loop 2 9_I St.bcoollruj Temp 106 F Press 12 pst PCS Pr$sure WR IT~ NR Il psia steam Generator A Steam Generator 8 Level (W) Q  % (NR) Q  % (WR) Q  % (NR) Q  % Press 1 pela J1 psia Flow Stears g PPH Feed Q PPH Steam 0 PPH Feed 0

                                                                                                                                                                                   ~

PPM Note steam and Feed Flow X I000000

                 $.*.l.1 AFW Flow to A $/G            From P 8AAB Q                          From P 8C Q AFW Flow to 8 S/G            From P SA&8 0                          From P 8C 9 Cmdenser Vacuus (R)                             {0                    P 508            g                 P 50C                                        P 500      g               PPM

' PCP Seat Leakoff Flow P 50A PPH PPH Q PPH 9.*E4 Olesel Generator Frequency 11 g 12 60 1 C SU$ Voltage Q Asps [

1 D Sus voltage g)3,39 Anps 2 C 11 Sack C 11A Contairment Area Monitors (R/Hr) RIA 1805 w 025 RIA 1806 .015 RIA 1807 dj RIA*1808 E High Range Contalrusent Monitors (R/Hr) RIA 2321 .1E+01 RIA 2322 .1E+01 Contairment Hydrogen Concentration (%) AI 2401R Q Al 2401L Q Main Steam Line Canne (cpe) RIA 2324 .23E+02 RIA-2323 .25E+0{

                   $ tack Monitors        RIA 2325 309                  cpra          RIA 2326 .9E+02 cpm RIA 2327 il                                           mr/hr J

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Scenario: PALEX-94 Time: 0945 Message No: 13 Scenario Time: 0115 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Control Room Personnel Simulated Plant conditions: Message: Containment temperature and humidity indicators are all trending upward. See alarm and data sheets. FOR CONTROLLER USE ONLY controller Notes: Action expected: 4

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PALtA v4 Date May 17. 1994 Mssssgs8j), (Page 1) Time 9945 ScenarioTime21,1,5 l Time Jump _ Scenario Time Juup . k90 83 psig SV Susps P 7A Oei P 7B QF F, P 7C Og SW Critical Hdr Press A 94

    '[ --          CCW Pumps       P-52A 0FF             P 528 ON             P 52C OE                          FPC Puips                                        P-51A DE Fire Puups      P 9A 0FF              P 98 OFF             P-41 ON                                                                           'P 518 OFF Contairstent Cooler Recire Fans
'                       VIA ON      V2A ON           V3A ON           V4A OE                                                                       V18 QN           V28 ON           V38 ON         V48 0FF 2 91 CCW Cooter Outlet Temp              A       40 F           8         42 F Contairment Spray Puips             P 54A 0FF              P 548 0FF                        P-54C OE MPSI Puups                          P 66A 0FF              P 666 0FF                        LPSI Pumps                                      P 67A gF1                       P 678 gFf Safety injection Suetion S a ly Train A                                                                                                                             Train 8 CV 3057 (SIRW) Closed CV 3029 (SIRW) CLOSED                                                                                   CV 3031 (SIRW) CLOSED CV 3030 (Susp) CLOSED C 02 CVCS Letdown                                                                                                                            Charging Interniediate Press Letdown Tenp               j04 F                                                                             Flow                p       gpm Letdown Line Tenp                              104, F                                                                            Line Temp           98 F Letdown Flow                                    g      gpm                                                                        Puips P-55A OFF P-558 0FF P 55C OFF Volume Control tank Temp 69 F                          Pressure il psi                          Level 54,              %                              PCP Control Bleedoff Pressure                      j)3 pelg Shutdown Cooling System SDCS from PCS (R) j02 F                                                                                    SOCS to PCS (R) 90,             F Quench Tank
' k                                                       Temp 101 F                Pressure 0                       psig                                       Level g 1 Primary Coolant System Pressurizer Pressure (R)                         13      psia PCS Tave (R)         Loop 1 (tR 0111) H                  Loop 2 (TR 0121) M LRC-01018 0                                                             LIA-0102A -3          %

j Pressurizer Level (R) LRC 0101A 0  %  % Par Htr Aaps LCC 15 9 LCC 16 9 PORV PRV 10428 Cl0 SED PRV 10438 CLOGED Block Valve MOV 1042A QPJN MOV 1043A gPE.8! PCPs P 50A 0FF P-508 0FF P 50C ~OFF P 500 0FF N!-04 N 08 Reactor Power Level NI 01 .20E+02 'N1-02 .20E+02 NI 03 98E 08 l NI 05 .12E 07 NI 06 .12E 07 N! 07 12E-07 N! 06 .12E 07 l C 01 AFW System l AFW Pump P 8A 0FF P 88 0FF P-8C OE AFV Pump Asps P 8A 9 P-8C 9 ) AFW Puup P 88 Steam Pressure 9 psig AFW Disch Press P-8A & P 88 18 P 8C j8 pai  ; l Secondary System i MS!v Bypass MOV 0501 CLOSED MOV 0510 CLOSED MSIV's CV 0501 CLOSED CV 0510 CLOSED  ! MFP Suction Pressure 15, psig MFP Discharge Pressure A 15 8 15 psi  ! Moisture separator Drain Tank Level 14,  % Condenser Hotwell Level 81 % l Atmospheric Duup Valves CLOSED Conderser Vacuan p in Ng. i Heater Drain Pump Status P 10A OFF P 108 0FF Gland Seal Condenser vacuus 14.2 in Ng. Condensate Puup Status P 2A 0FF P 28 0FF I P.L. (Demand Log + Constant, Rod, or Flux / Temp) Gross MW Net MW p Core Exit Thermocouple Temperature - 0 F Q Control Rod Position GP1g GP2g GP3 0, GP4 0 GP5(P)1 GP6(A) 0, GP7(8) 0 Stuck Rods E # 0,, l 1

                                                                                                                                                                                                                       ,J

. Dits May 17, 1994- Mtssige # j3 (Pigs 2) Time 994,5 ScenarioTime0,HS, Time JLap Scenario Time Jump tlk T 81 Level 90 % T 939 Level  %% cordensate Storage Tank Level T 2 86 %

                                                                                                                                        ~

InstrumentAIrPressure 5 psig

 \               Contalrwent Building Pressure           9    psig                     Dome Tenperature        2 J2Q  F      Hunidity H %
             -   $/G A Compertment                                                     Tenperature            90 F        Humidity D %

S/G 8 Compartment Temperature _ 91 F Hunidity Zg % SIRW Tank Level J % 8 WR Contairment Pressure (R) 15 psia contairment Susp Level M% Contairment Water Level (R) Q  % St Tank Level (%) A 41 8 41 C 41 0 41 St Tank Pressure (psig) A 236 8 236 C 33s D 2J32 PANEL K 13 SIAS Alarm NQ Containment High Pressure Alarm N,9 Contairment High Radiation Alarm Ng M Concentrated Boric Acid Tank Levels T53A j,09 % T538 100 % Reactor Vessel DP J 8 psid PORY Discharge Temperature 112 F Pze safety Valve Discharge Teep (F) Rv-1039 126 Rv 1040 '141 RV-1041 1[g PCP Current (Amps) P 50A Q P-508 9 P 50C 9 P-500 'g PCS Flow 0  % Pressure Level (cold) -

                                                                                                              -3     %

Loop Thot (F) Loop 1 109 Loop 2 log Loop Tcold (F) Loop 1 91 Loop 2 91 Teold Wide range Loop 1 6 Loop 2 91 St& cooling Temp 106 F Press 12 psi PCS Prssure WR 3~ NR jJ3 psia Steam Generator A Steam Generator 8 Level (WR) Q  % (NR) Q  % (WR) Q  % (NR) Q  % Press 1 psia 14 psia Flow Steam 0

                                                         ~

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                                                                                                                                       ~

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                   # SUS                      Voltage !                 Amps Q O. B ls                    Voltage 3J3JO             Anps g C U Sack C IIA Contairment Area Monitors (R/Hr)                    RIA 1805 .025                  RIA 1806 .015 RIA 1807 g                     RIA 1808 3 High Range Contairment Monitors (R/Nr)              RIA 2321       .1E*01          RIA 2322      1E+01 Contairment Hydrogen Concentration (%)              At 2401R 9                     Al 2401L g Main Steam Line Canne (cpa)                         RIA 2324 .23E+02               RIA 2323 .25F+02 Stack Monitors       RIA 2325 }59       cpm      RIA-2326 .12E+03 cpm RIA 2327 d                    er/hr s

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Scenario: PALEX-94 Time: 1000 Message No: 14 Scenario Time: 0130 PALISADES NUCLEAR PLANT EMERGENCY PREPAPEDNESS EXERCISE F0Jjt Message For: Control Room Personr.el Simulated Plant Conditions: Message: " Containment Hi Radiation" alarm (EK-13 #63) has been received; RIAs 1805 thru 1808 are high up scale. Containment pressure indicators are trending upscale. See alarm and data sheets. l t O I FOR CONTROLLER USE ONLY l Controller Notes: Action expected: t t _ . , . , ,, ,~. . . . _ _ -

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

FAttA W Dats May 17, 1994 Message # 14 (Paga 1) TimeJ000 ScenarioTime$139 7ime Jtap Scenario Time Jtmp

                $*S$

SW Surps P 7A ON P 78 0FF P 7C ON SW Critical Ndr Press A 94 8 94 psig ( N CCW Punps Fire Puups P 52A OFF P 9A 0FF P 528 ON P 99 OFF P 52C OFF P-41 ON FPC Ptaps P 51A O_FfF

                                                                                                                                                             'P 518 0FF Contaironent Cooler Reetre Fans VIA ON         V2A ON         V3A ON             V4A 0FF                                                             V1B ON              V28 ON         V38 ON        V4B 0FF
                $* 01 CCW Cooler Outlet Temp                  A           40 F              G                39 F Contairunent spray Punps                P $4A 0FF                     P 548 0FF                       P 54C OFF HPS! Puips                              P 66A 0FF                     P 668 0FF                       LPSI Punps                            P 67A 0FF                  P 67B 0FF 5

Safety iniection Suction Supply Train A Train B CV 3057 ($1RW) CLOSED CV 3029 (SIRW) CLOSED CV 3031 (SIRW) CLOSED CV 3030 (Stmp) CLOSED

                $.*.0.1
                                                                                                              .CVCS
                                                                                                                ~

Letdown Charging Intermediate Press Letdown Tenp 104, F Flow g gpm Letdown Line Tewp 104 F Line Tenp 10_{ F Letdown Flow g gpn Puups P 55A 08F P-$5B 0FF P-55C OFF Volune Control Tank Tenp 69 F Pressure il psi Level 54 % PCP Control Bleedoff Pressure j 3, psig shutdown Cooting System SOCS from PCS (R) 102 F SOCS to PCS (R) 91 F Cuench Tank Tenp 101 F Pressure 0 psig Level B % Primary Coolant System Pressurizer Pressure (R) 1} psia PCS Tave (R) Loop 1 (TR 0111) M Loop 2 (TR-0121) 96 Pressuriter Level (R) LRC 0101A 0  % LRC 01018 9  % LIA 0102A ,,3  % PZr Htr Aaps LCC 15 g LCC 16 9 PORV PRV-1042B CLOSED PRV 10438 CLOSED Block Valve MOV 1042A OPEN Mov 1043A OPEN PCPs P 50A 0FF P 506 0FF P 50C OFF P 500 0FF i Reactor Power Levet N!*01 3E+03 NI 02 3 E+03 NI 03 .13E 06 NI 04 _.12E 06 NI 05 .14E 06 Wl 06 .14E 06 NI 07 .14E 06 NI 08 .15E 06 G'91 AFW System AFW Ptop P 8A 0FF P 88 0FF P 8C OFF AFW Puip Amps P BA 9 P-8C 0_ i AFW Puip P-88 Steant Pressure O psig AFW Disch Press P 8A & P 88 18, P 8C j,88 pal Secondary System Msly Bypass MOV 0501 CLOSED MOV 0510 Ct0 SED MS!v's CV 0501 CLOSED CV-0510 CLOSED MFP Suction Pressure 15,, psig MFP Discharge Pressure A 15 B 15 psi Moisture Separator Drain Tank Level 14 % Condenser Hotwell Level E % in Hg. i

Atmospheric DLap Valves CLOSED Condenser Vacuum 9 Heater Orain Puup Status P 10A 0FF P-108 0FF Gland Seal Condenser vacuun M in Ng.

Condensate Pump Status P 2A Off,F, P 28 QFf, l l P,2 (Demand Log + Constant, Rod, or Flux /Teap) Gross MW 0 Net MW 0 Core Exit Thermocouple Tenperature Q f i Control Rod Position GP1 Q GP29 GP3Q GP49 GP$(P)1 GP6(A) 0 GP7(B)g l Stuck Rods NONE #Q i w + =e, --% - .----p-. p , -a m, , - . --. - .-e -- _ - , ,g-s q p ,, r

D:t3 May 17, 1994 Messigt # M (Pega 2) Time 1000 Scenario Time 0130 Time Jep Scenario Time Junp Sill T 81 Level 90 % T 939 Level 97 % Condensate Storage Tank Level T 2 86 % [mT Instrunent air Pressure 104, psig ij contalement Building Pressure DJ psig Dome Teeperature 209 F Hunidity 109 % S/G A Ca partment Temperature 1$ F Hunidi ty 0 1_09 % S/G 8 Cenpartment Temperature 199 F Munidity 109 % SIRW Tank Level 8.1 WR Containment Pressure (R) j5 psia Containment Sunp Level M% Contairunent Water Level (R) M%

        $! Tank Level (%)                   A 41                               8 41                   C 41                   0 41 St Tank Pressure (psig)             A 13{                              B 232                  C 232                  0 228 PANEL K 13
        $1AS Alarm NQ                Contairrent High Pressure Alarm N_g                               Contairunent High Radiation Alarm IEj  E Q1E Corx:entrated Boric Acid Tank Levels                         T53A          109 %        T538     100 %

Reactor Vessel DP J 8 psid PORV Discharge Teniperature j_1.3 F Par Safety Valve Discharge Terp (F) RV-1039 127 Rv 1040 142 RV 1041 j_77 PCP Current (Ant 3) P 50A 9 P 508 g P 50C 9 P-500 g PCS Flow 9  % Pressure Level (cold) ;3  % Loop Thot (F) Loop 1 90 Loop 2 199 Loop Tcold (F) Loop 1 9 J Loop 2 9 J Teold Wide range Loop 1 9.] Loop 2 9J Sdrooling Tenp .106 F Press 12 psi PCS Prasure WR 13 NR 13 psia Steam Generator A Steam Generator 8 Level (WR) 9  % (NR) Q  % (WR) 9  % (NR) 9  % Press 1 psia M psia Flow Steam 0

                                              ~

PPH Feed 0

                                                                                  ~

PPH Steam 0 PPH Feed 0 PPH fg Note: St am and Feed Flow X I000000

                                                                                                                               ~

N.) y AFW Flow to A S/G From P 8A&B g From P 8C Q f AFW Flow to B S/G From P 8A&B 0 Fran P-8C ~0 t Condoreser Vacuun (R) Q l PCP Seal Leakoff Flow P 50A 0 PPH P 508 0 PPH P 50C 0 PPH P 500 0 PPM i i t9h Diesel Generator Frequency 11 0 12 60 1 C BUS Voltage 2 Anps 9 , 1 0 SUS Voltage 2319 Amps 9 { C 11 Back C 114 ( Contalrisent Area Monitors (R/Hr) RIA 1805 ??? RIA 1806 ??? RIA 1807 121 RIA 1808 221 Nigh Range Contatriment Monitors (R/Mr) RIA 2321 .1E+01 RIA 2322 .1E+01 Contalrvnent Hydrogen Concentration (%) Al 2401R Q Al 2401L g Main Steam Line Gamma (cpa) RIA 2324 .23E+02 RIA 2323 .25E+02 1 Stack Monitors RIA 2325 .38E+03 cpn RIA 2326 .15E+03 cpn RIA 2327 J mr/hr

                                                                                                                                                       \

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Scenario: PALEX-94 Time: 1015 Message No: 15 Scenario Time: 0145 O PALISADES NUCLEAR PLAMI EMERGENCY PREPAREDNESS EXERCISE FORM i Message For: Control Room personnel Simulated Plant Conditions: Message: " Containment Pressure Off Normal" alarm (EK-13 #62) has just been received. Reactor Vessel level indicators LIA-0105 and LIA-0106 are off scale i low. See data sheets. All other alarm conditions are the same as at scenario time 0130. l O FOR CONTROLLER USE ONLY controller Notes: Action expected: Players may elect to upgrade to G.E. at.this point due to the potential for < core damage and loss of containment. O

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FAttA Vie Date May 17, 1994 Masstge0}} (Page 1) Time 1015 ScenarioTime0141 Time Jw p scenario Time Jtap 4 O

                      $W Steps                           P 7A ON                       P 78 0FF                      P 7C QN                       $W Critical Ndr Press           A 94_                              B 94 psig CCW Pwps                           P 52A 0FF                     P 528 ON                      P 52C E                       FPC Ptaps                   P 51A QFf i                    Fire Pups                          P 9A 0FF                      P 98 0FF                      P 41 ON                                                  'P 518 OE Contairment Cooler tect re Fans i                          VIA ON                         Y2A ON          V3A ON                 V4A 0FF                                                           V18 ON       V28 ON          V38 ON          V48 0FF M91 CCW Cooler Outlet Teep                                       A            40 F                  B       39 F Contairnent Spray Ptaps                                      P 54A 087                          P 548 0FF                     P 54C of MPSI Ptaps                                                   P 66A 0FF                          P 668 0FF                     LPSI Pups                P 67A 0FF                       P 678 0FF Safety injection Suction Stoply Train A                                                                                                                    Train B CV-3057(siRW)ggsE CV 3029 ($1RW) Closed                                                                                                      CV 3031 (SIRW) CLOSED CV 3030 (Simp) CLOSED i

J C Ev.El letdown Charging intermediate Press Letdown Tenp 104,, . F Flow g gpm 2 Letdown Line Temp 1h F Line Temp 102 F Letdown Flow g gpn Ptsps P 55A 0FF P 558 0FF P 55C OFF Volume Control Tank Teno 6,,9 F Pressure il psi Level F3 % PCP Control Bleedoff Pressure 11 psig Shutdown Cootino System SOCS from PCS (R) 1,02 0 F SOCS to PCS (R) 91 F Quench Tank

     \                                                                                    Temp 101 F                       Pressure 0                psig                    Level B %

Primary Coolant System Pressurizer Pressure (R) 13 psia PCS Tave (R) Loop 1 (fR*0111) 5 Loop 2 (TR 0121) M Pressurlier Level (R) LRC*0101A 9  % LRC 01018 9  % LIA 0102A

• 3,,,

, Par Mtr Anps LCC 15 9 LCC 16 g PORV PRV 10428 CLOSED PRV 10438 CLOSED Block Valve MOV 1042A QPE ' MOV 1043A QPE '- . PCPs P-50A QFJ P 508 0FF P 50C OFF P 500 0FF ~ Reactor Power Level N1 01 ,14E+03 NI 02 3E+03 N!*03 M E 06 NI 04 12E 06 Ni+05 .16E % NI 06 .14E 06 NI 07 .14E 06 N!*08 .15E 06 S'.91 AFW System AFW Pump P 8A 972 P 88 p H P 8C OE AFW Ptap Amps P 8A 9 P 8C 9 AFW Pump P 88 Steam Pressure g pelg AFW Disch Press P*8A & P 88 18 P 8C 18 pel Secondary System M$lv Bypass MOV 0501 ClosFO MOV 0510 ClosEO MS1V's CV 0501 CLOSED CV 0510 MFP suction Pressure 15 psig MFP Discharge Pressure Ah B U, ,g2SEpel Moisture $eparator Drain f ar* Level 14, Atmospheric Duip Valves

                                                                                                       %                                          Condenser Notwell Level            la % in Ng.

CLOSED Condenser Vacuun Q 4 Heater Drain Ptsp Status P 10A 0FF P 108 077 Gland seal Condenser vacuus 14.J in Ng. ! Condensate Pump Status P-2A 0FF P 2s OFF . ele I (Demand Log + Constant, Rod, or Flux / Temp) Gross MW D Net MW 0 Core Exit Therwacosple Temperature Q F Control Rod Position GP1g GP22 GP3Q GP4 9 GP5(P)1 GP6(A)Q GP7(B) g Stuck Rods NON,{ #0 1

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nts niv 17, 1994 '4essige # 11 (P&ge 2) Timejojtj o Scenario Time M 45 Time Jump Scenario Time Jump E*).1 g T 81 Level 90 % T 939 Level H% Condensate Storage Tank Level T 2 M% Instrument air Pressure 194 psig Containment Building Pressure M psig Dome Temperature 209 F Hunidi ty j09 % S/G A Campartment Temperature 199 F Hunidity 199 % S/G B Compartment Tepperature ,L99 F Hunidity j,0,9 0 %

                               $1RW Tank Level                                8],    %

WR contairment Pressure (R) jf psia Contairment Sump Level 59,1, % contairment Water Level (R) 55 % Si Tank Level (%) A 41 8 41 C 41 D 41

                               $1 Tank Pressure (psig)                  A 132                                 8 232                         C 232                        0 228 PANEL K 13 SIAS Alarm N9                     Containment High Pressure Alarm JJJ                                            Contairinent High Radiation Alarm IES E*1E Concentrated Boric Acid Tank Levels                                      T53A      J,00     %        T538         100 %

Reactor Vessel DP J 8 psid PORV Discharge Temperature jl3 F Pzr Safety Valve Discharge Temp (F) RV-1039 J21 RV 1040 14J Rv 1041 L77 PCP Current (Asps) P 50A 0 P-506 9 P 50C 9 P-500 9 PCS Flow 9  % Pressure Level (cold) 3  % Loop Thot (F) Loop 1 9_9 Loop 2 100 Loop Teold (F) Loop 1 H Loop 2 J 9 Tcold Wide range Loop 1 H Loop 2 9J

                               $ @ ooling                        Temp         106 F                     Press     12 psi PCS Prssure                       WR           13                        NR        13       psia Steam Generator A                                                  Steam Generator 8 Level                             (WR)        0       %                  (NR)      9      %          (WR)         0      %.        (NR)      9     %

Press j, psia 14 psia Flow Steam 9 PPH Feed 9 PPH Steam 9 PPH Feed 9 PPM i O: E 11 AFW Flow to A S/G From P 8A&8 9 Wotes Steam and Feed Flow x 1000000 From P 8C 9 AFW Flow to B S/G From P 8A&8 9 From P 8C 9 Condenser Vacuun (R) 9 PCP Seal Leakoff Flow P 50A 9 PPH P 508 9 PPH P 50C 9 PPH P-500 9 PPH 4 Diesel Generator Frequency 11 0 12 60 1 C BUS Voltage 9 Amp 9 1-0 BUS Voltage {339 3 Asps 9 C-11 Sack C-11A Contalrunent Area Monitors (R/Hr) RIA 1805 ??? RIA 1806 ??? RIA 1807 221 RIA 1808 222 High Range Contalrunent Monitors (R/Hr) RIA 2321 1E+01 RIA-2322 1E+01 Contalrunent Hydrogen concentration (1) Al-2401R 9 Al 2401L 9 Main Steam Line Ganna (cpm) RIA-2324 .23E+02 RIA 2323 .25E+02 Stack Monitors RIA 2325 .4E+03 cpm RIA 2326 .15E+03 cpo RIA 2327 J mc/hr i 1 l v i

Scenario: PALEX-94 Time: 1030 Message No: 16 Scenario Time: 0200 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE _ FORM Message For: Control Room Personnel Simulated Plant Conditions: Message: See data sheets. Alarm conditions are the same as at scenario time 0130. 6 ( s O FOR CONTROLLER USE ONLY controller Notes: Defeat efforts to develope a legitimate PCS inventory addition success path until problem time 0215. Action expected: -l O

VMe A V4 Date Mtv 17, 1994 Messige # M (Pts: 1) Timej0J,0 0 Scenario Time 2109 - Time Jump Scenario Time Jtap k95 SW Susps P-7A ON P 78 0FF P 7C ON SW Critical Nde Press A 94 8 ,9,4 psig O CCW Pums Fire Pumps P 52A 0FF P 9A 0FF P 528 ON P 98 0FF P 52C OFF P 41 ON FPC Pumps P 51A gF1

                                                                                                                ' P 518 0F F Contalrunent Cooter Rect re Fans V1A ON     V2A ON      V!A ON       V4A 0FF                                           VIB ON        V28 ON        V38 ON      V48 0FF 8

C CCW Cooler Outlet Tenp A 40 F S 39 F Contairunent Spray Ptaps P 54A 0FF P 54B 0FF P 54C 0FF WPSI Ptsps P-66A 0FF P 668 0FF LPSI Ptaps P 67A 0FF P 678 0FF Safety Infection Suction Supply Train A Train B CV 3057 (SIRW) CLOSED CV-3029 (SIRW) CLOSED CV 3031 (SIRW) CLOSED CV-3030 (Susp) CLOSED C:)$ CVCS

                                                                               ~

Letdown Charging Interediate Press Letdown Tenp 104 F Flow 0 gpn Letdows' Line Teep &F Line Teap 1,0g F Letdowr Flow 0 gpm Puups P 55A 0FF P-558 0FF P 55C 0FF Voltaw Control Tank Tenp J 6 F Pressure {1 psi Level 54 % PCP Controt 8teedoff Pressure j3 psig Shutdown Cootina System SDCS from PCS (R) jgj F SDCS to PCS (R) 9ji, F Quench Tank I. Temp 101 F Pressure o psig Level 63 3  % Primary Coolant System Pressuciter Pressure (R) j3 psia PCS Tave (R) Loop 1 (TR 0111) J 9 Loop 2 (TR 0121) M Pressurfrer Level (R) LRC 0101A 0  % LRC-01018 0  % LIA 0102A 3 % Pzr Mtr Aaps LCC 15 g LCC 16 g PORV PRV 10428 CLOSED PRV 10438 CLOSED Block Valve MOV 1042A gPg3 MOV 1043A gg PCPs P 50A 0FF P 508 0FF P-50C 077 P 500 0FF Reactor Power Level NI 01 14E+03 NI 02 ,13E+03 N1 03 ~i3E-06 N! 04 TIE 06 N! 05 14E-06 N! 06 .14E-06 N! 07 14E 06 N! 06 .15E-06 E *.0,,1 AFV System AFW Puup P 8A 0FF P 88 0FF P-8C OFF AFW Pump Asps P 8A Q P-8C Q AFW Puup P 88 Steam Pressure 9 pelg AFW Disch Press P 8A & P-88 18 P 8C 18 pal Secondary System MSIV Bypass MOV-0501 CLOSED MOV 0510 CLOSED MS!vis CV-0501 CLOSED CV 0510 CLOSED MFP Suct8 cn P essure j5 psig MFP Discharge Pressure- A 15 B 15 psi Moistur9 Separator Drain Tank Levet j,4, % Condenser Motwell Level (( % Atmospherir Dtap Valves CLOSED Condenser Vacuun 9 in Ng. . . Heater prain Ptmp Status P 10A 0FF P-108 0FF Gland Seal Condenser Vacuun jM in Ng. Condensate Puup Status P*2A 0FF P 28 0FF Elf (Demand Log + constant, Rod, or Flux / Temp) Gross MW Q Net MW 9 Core Exit Thermocouple Teaperature 0,, F Control Rod Position GP1g GP2 0~ GP3 0~ GP4 0~ GP5(P) ~1 GP6(A) ~0 GP7(8) 0~ Stuck Rods E #9 d

D ts May 17. 1994 Messige # 16 (Pegt 2) Time 1030 Setnario Time 0200 fine Jum Scentrio Time Junp S.*11 T 81 Level 90 % T 939 Level 97 % Condensate Storage Tank Level T 2 86 %

                                                                                                                 ~

[m 1rutrument AE Pressure k psig HuniJi ty 10Q % ( Contairment Building Pressure S/G A Compartsent M psig Dome Tenperature 299 F Terperature 1909Q F Hunl11ty Igg % S/G B Compartment Terperature 13 F Hunit'i ty Igg % SIRW Tank Level J 8  % WR Contalraent Pressure (R) 18 psie Contairment Surp Level 5,9J% Contairvnent Water Level (R) M% St Tank Level (%) A 41 8 41 C 41 D 41 St Tank Pressure (psig) A 232 8 232 C 232 0 2 2,29 PANEL K 13 SlAS Alarm HQ Contairment High Pressure Alarm IEj Containment High Radiation Alarm IEj til Concentrated Boric Acid Tank Levels T53A 10Q % T538 100 % Reactor Vessel DP Ej psid PORV Discharge Tenperature 113 F P2r Safety Valve Discharge Teno (F) Rv 1039 127 Rv-1040 142 Rv-1041 7 1_7 PCP Current (Aaps) P 50A 9 P-508 Q P-50C g P 500 g PCS Flow g  % Pressure Level (cold) -j  % Loop Thot (F) Loop 1 99 Loop 2 199 Loop Teold (F) Loop 1 D_ Loop 2 9_1, Teold Wide range Loop 1 M Loop 2 J 9 Stbcooling Tecp 196 F Press 12 psi PCS Prssure WR j] NR 3 psia Steam Generator A Steam Generator B Level (WR) Q  % (WR) Q  % (WR) Q  % (NR) 9  % Press 1 psia li psia Flow Steam 0

                                           ~

PPH Feed 0 PPH Steam 0 PPH Feed 0

                                                                                                                ~

PPH [N, Note! Steam and Feed Flow X I000000 I v/ e AFW Flow to A S/G Fran P 8A18 g Fran P 8C 9 AFW Flow to B S/G From P 8A&B g Fron P 8C g Condenser Vacuun (2) 9 PCP Seal Leakoff Flow P 50A 9 PPH P-508 9 PPM P 50C g PPH P-500 g PPH d Diesel Generator Frequency 11 0 12 60 1 C BUS voltage 9 Aaps 9 10 BUS Voltage 2339 Aaps Q C-11 Back C-11A Contairment Area Monitors (R/Hr) RIA 1805 ??? RIA-1806 ??? RIA 1807  ? 2?2 RIA-1808 221 High Range Contairnent Monitors (R/Hr) RIA 2321 .2E+01 RIA 2322 .2E+01 Contairment Hydrogen concentration (%) Al-2401R g Al 2401L g Main Steam Line Canma (cpn) RIA-2324 .23E+02 RIA 2323 ,25E+02 Stack Monitors RIA 2325 43E+03 cpn RIA-2326 2E+03 cpn RIA 2327 J mr/hr i

  \

O l

i Scenario: PALEX-94 Time: 1045 Message No: 17 I Scenario Time: 0215 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Control Room Personnel Simulated Plant Conditions: Message: See data sheets. Alarm conditions are the same as at scenario time 0130. FOR CONTROLLER USE ONLY Controller Notes: The fuel in the RV is now uncovered. As major fuel damage is now inevitable, whichever PCS inventory addition path has been best pursued can be permitted to be successful. Action expected: O < i

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

Pf4t A V4 Date M*y 17. 1994 Mtssage#jl (Paga 1) Time 194,,5, ScenarioTime9M Time Jump Scenario Time Jtasp E.* 20 O SW Sunps P 7A ce! P 7B 0FF P 7C ON SW Critical Ndr Press FPC Ptaps A 94 B 94 psig t,Uj CCV Ptsps Fire Pumps P-52A DE P 9A 0FF P 528 ON P 98 0FF P 52C OFF P 41 Om P-51A OE P-51B 0FF Contairment Cooler Rectre Fans VIA ON V2A ON V3A ON V4A 0FF V1B ON V2B ON V3B ON V4B 0FF E.*$ CCV Cooler Outlet Teg A 49 F B H F Contalrnent spray Ptmps P 54A 0FF P-548 0FF P 54C OE HPSI Punps P 66A 0FF P 668 0FF LPSI Ptsps P 67A 0FF P 678 0FF Safety injection Suction Supply Train A Train B CV 3057 (SIRW) CLOSED CV-3029 (SIRW) CLOSED CV 3031 (SIRW) Closed CV-3030 (Stap) CLOSED kM E Charging letdown Intermediate Press Letdown Tenp 104 7 Flow 0 gpn Letdown Line Teap 104 F Line Temp 102, F Letdown Flow g gpm Ptmps P-55A 0FF P 55B 0FF P-55C OFF Volune Control Tank fesp M F Pressure 1,1, psi Level M % PCP Control Bleedoff Pressure j,33 psig

                                                                               $hutdown Cooling System SDCS from PCS (R) 193 F                                                                    MCS to PCS (R)      J 9     F ouench f ar*

Temp 101 F Pressure 0 psig Level M % Primary Coolant Systen Pressurizer Pressure (R) 13 psia PCS Tave (R) Loop 1 (TR 0111) 95 Loop 2 (TR 0121) %_ Pressuriger Level (R) LRC 0101A 9_  % LRC 0101B 0  % LIA 0102A .- 3 % Pzr Htr Amps LCC 15 9 LCC 16 9 PORV PRV 1042B CLOSED PRV 10438 CLOSED Block Valve MOV-1042A gPE MOV 1043A QP3 PCPS P 50A 0FF P 508 OFF P 50C OFF P 500 0FF Reactor Power Level NI-01 3E+03 NI*02 .13E+03 NI 03 .13E 06 NI 04 ~I2E 06 NI-05 14E 06 NI 06 .14E-06 NI 07 .14E-06 N!-08 .15E-06 k91 AFW System l AFW Puup P 8A 0FF P 88 0FF P 8C OFF AFW Ptap Asps P 8A 9 P 8C Q AFW Ptap P 88 Steam Pressure g psig AFW Olsch Press P-8A & P 8B j8 P 8C j,8,8 psi Secondary System MSiv Bypass MOV 0501 CLOSED MOV 051# CLOSED MSIV's CV 0501 CLOSED CV 0510 CLOSED MFP Suction Pressure . 15 psig MFP Olscharge Pressure A 15 B 15 psi Moisture Separator Orain Tank Level 14 % condenser Hotwell Level !1 % in Hg. Atmospheric Duup Valves CLOSE0 Condenser Vactaan 9 Heater Drain Ptmp Status P-10A CE P 108 pfF Gland Seal Condenser Vacuun 142 1 in Ng. Condensate Ptap Status P 2A 0FF P 28 0FF vi 1 (Demand Log + Constant, Rod, or Flux /f esp)  ; Gross MW g Net MW 9 Core Exit Thermocotple Temperature 0 F  ; Control Rod Position GP1 0 GP29 GP3 9 GP4 9 GP5(P)j, GP6(A)g GP7(B) 0 l Stuck Rods WONE 89

__ _ _ .. -. - .__ -.m_ _ _ _ _ _ _ _ _ _ _ DIts May 17. 1994 Messags#j7 (Psge 2) Time 1945, Scenario Time Q G fine Jurp Scenario Time Jump d T 81 Level 9J % T 939 Level 97 % Condensate Storage Tank Level T 2 06 % instrument Air Pressure lgi psl0 Contaltiment Building Pressure M psig Done Temperature 209 F Humidity jpQ % S/G A Compartment Tesperature 199 F Hunidity 109 % S/G B Compartment Temperature 199 F Hunidity 199 % SIRW Tank Level J 8 psia WR Containment Pressure (R) 1 Contairement Sump Level h)  % Containment Water Level (R) M% Si Tank Level (%) A 41 8 41 C 41 0 41 St Tank Pressure (psig) A b 8 2)ll CM D N} PANEL K-13 SlAS Alarm Ng Containment High Pressure Alarm IES Contalrinent High Radiation Alarm IES E*l.E Concentrated Boric Acid Tank Levels T53A 199 % T538 1bo % Reactor vessel DP 8.3 psid PORV Discharge Temperature Ptr Safety Valve Discharge Temp (F) 3F RV 1041 g RV 1039 R7 RV 1040 143 PCP Current (Amps) P 50A 2 P 508 Q P-50C 9 P 500 g PCS Flow Q  % Pressure Level (cold) d  % Loop thot (F) Loop 1 99 Loop 2 0 102 Loop Teold (F) Loop 1 91 Loop 2 91, Teold Wide range Loop 1 6 Loop 2 J 9 Subcooling Temp 106 F Press R pst PCS Prssure WR _17 NR jJ1 psia Steam Generator A Steam Generator 8 Level (WR) Q  % (NR) Q  % (WR) Q  % (NR) Q  % Press 1 pela 14 psia Flow Steam 0

                                                                          ~

PPH Feed 0 PPH Steam 0 PPH Feed 0

                                                                                                                                                                                           ~

PPH f Note Steam and Feed Flow X I000000 Sd1 AFW Flow to A S/G Fria P 8A18 Q From P 8C Q AFW Flow to 8 S/G From P 8A&8 9 From P 8C Q Condanner vacuus (R) 9 PCP Seal Leskoff Flow

• 50A 9 PPH P 508 Q PPH P 50C Q PPH P 500 g PPH

                    $*Si Diesel Generator Frequency             11 0                                             12 60 1 C BUS                           Voltage p                                           Asps 9 1-0 BUS                           Voltage 133.9                                       Anps g C 11 Back C 11A Contairement Area Monitors (R/Mr)                                                 RIA 1805 221                             RIA 1806 122 RIA 1807 ???                             RIA 1808 112 Nigh Range Contairment Monitors (R/Hr)                                            RfA 2321           .2E+02                RIA 2322 .2E+02 Contalrenant Hydrogen Concentration (%)                                           Al 2401R 0                               Al 2401L g Main Steam Line Ganne (cpe)                                                       R!A 2324 .23E+02                         RIA 2323 .25E+02 Stack Monitors          RIA*2325      43E+03 epa                                RIA 2326 .25E+03 cp RIA 2327 J                                       mr/hr I

o 4

p,,,, . - ,, , a- , , , , - - - - - , . . - - - - - , - - - , , , , - - .- , , - - ,, , -~r.. . - . ,n.. --- - , , -g -

Scenario: PALEX-94 Time: 1100 Message No: 18 Scenario Time: 0230 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Control Room Personnel simulated Plant Conditions: Message: See data sheets. Alarm conditions are the same as at scenario time 0130. 4 3 O U FOR CONTROLLER USE ONLY Controller Notes: Since we don't know which hydrogen monitoring channel will be in service at this point, respond to questions regarding Containment hydrogen concentration by ramping AIT-240ll/R indication from 0% to 10% between 0315 and 0415. Action expected: l 1 1 I l

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

rnta v. Date thy 17. 1994 Message # if (Page 1) Time 1109 ScenarioTime9,2,}g Time Jump Scenario Time Jtap kEI SW Simps P 7A ON P 78 0FF P 7C ON SW Critical Mdr Press A 94 8g psig CCW Ptsps P 52A 0FF P 528 ON P*52C OFF FPC Ptaps P 51A g g Fire Purps P 9A 0FF P-98 0FF P 41 ON 'P 518 0FF Contairvnent Cooler sectre Fans v2A ON V3A ON V4A 0FF V10 ON V28 ON v38 ON V48 0FF V1A Da!

       . 21 C:

CCW Cooler outlet Tenp A 40 F 8 39 F Contaironent Spray Pumps P 54A OFF P 548 0FF P 54C OFJF HPSI Purps P 66A 0FF P 668 0FF LPSI Puups P 67A DE P-678 QFfF, safety injection Suetion Supply Train A Train 8 CV 3057 (SIRW) Cl0 SED CV-3029 (SIRW) Cl0 SED CV 3031 (SIRW) CLOSED CV 3030 (Stap) Ct0 SED C 02 E Charging Letdown Intermediate Press Letdown Temp 104 F Flow 0 gpn Letdown Line Teep 104 F Line Temp jo2 F Letdow1 Flow g gpn Ptaps P 55A OFF P 55B 0FF P 55C 0FF Volune Control Tank Tecp 69 F Pressure 21 psi Level j,4,g/  % PCP Control 8leedoff Pressure j)3, pelg Shutdown Cooling System SOCS from PCS (R) 10.2 2 F SOCS to PCS (R) U F ovench Tank Temp 101 F Pressure 0 psig Level Q % Primary Coolant Systeen Pressuriter Pressure (R) 13 psia PCS Tave (R) Loop 1 (TR 0111) $ Loop 2 (TR 0121) M Pressuriter level (R) ' LRC 0101A 0  % LRC-01018 0  % LIA 0102A 3 % Ptr Htr Amps LCC 15 9 LCC 16 9 PORV PRV-10428 CLOSED PRV 10438 CLOSED Block Valve MOV-1042A QPE MOV 1043A gPE PCPs P 50A 0FF P 508 0FF P 50C OFF P 500 0FF Reactor Power Level NI 01 3E+03 NI 02 ".T3E +03 N! 03 3E06 NI 04 ME 06 N! 05 .14E-06 Mi 06 .14E 06 N!*07 14E 06 N! 06 .15E 06 C-01

       ~

AFV System AFW Pump P 8A 0FF P 88 0FF P 8C 0FF AFW Puup Asps P 8A 9 P 8C 9 AFW Pusp P 88 Steam Pressure O psig AFW Olsch Press P 8A & P 88 j8 P-8C Jg pel Secondary System MSIV Bypass MOV 0501 CLOSED. MOV 0510 CLOSED MS!V's CV 0501 CLOSE0 CV 0510 D gggg pe, l MFP Suction Pressure M psig MFP Olscharge Pressure AH 8 L5 J Moisture Separator Drain Tank Level M % Condenser Hotwell Level (( % Atmospheric Otmp Valves CLOSED Condenser Vacuun 0 in Ng. Heater Drain Puup Status P 10A OH P 108 03 Gland Seal Condenser Vacuun j4J in Ng. Condensate Pump Status P 2A 0FF P 26 0FF f!E (Demand Log + Constant, Rod, or Flux / Temp) Gross MW g Net MW 9 Core Exit Thermocotple Temperature  ! F Control Rod Position GP1 9 GP2g GP3 0 GP49 CP5(P)1 GP6(A)9 GP7(8)Q ( Stuck Rods !LONg, #9 i

 - - -                                                                                                                                                                           'l

J D t3 May 17,1994 Message #!! (Page 2) Time jlpg Scenario Time 0230 Time Jupp Scersrlo Time Juy S.d.l , T 81 Level 90 % T 939 Level 97 % Condensate Storage Tank Level T 2 ~ 86 % 1rwtrument Air Pressure I,g~4 psIg Contairment Sullding Pressure ,2d psig Dome Tenperature 225 F Hunidity log %

       $/G A Compartment                                                                   Teeperature         jl5 F          Hunidi ty j,00 %

S/G B Compartment Tenperature MF Hunidity 109 %

       $1RW Tank Level                                81 %

WR Contairment Pressure (R)  !! psia Contalruent Sump Level 591 % contairment Water Level (R) 195 %

       $1 Tank Level (%)                          A 41                           8 41                       C 41                          0 41 St Tank Pressure (psig)                    A _{32                         B gJ,2                     C j323                        0 229 PANEL D 13 SIAS Alarm Ng                       Contairinent High Pressure Alarm IES                              Contairment Nigh Radiation Alare IES                   E
       $*1E Concentrated Boric Acid Tank Levels                        T53A                log %          T538      100 %

Reactor Vessel DP 8J psid PORY Discharge Temperature 113 F Par Safety Valve Olscharge Teep (F) Rv-1039 13Z Rv-1040 1M Rv 1041 E PCP Current (Amps) P-50A 9 P 508 g P-50C 0 P-500 g PCS Flw 0  % Pressure Level (cold) ,,3  % Loop Thot (F) Loop 1 99 Loop 2 100, Loop Teold (F) Loop 1 91 Loop 2 91 Teold Wide range Loop 1 91 Loop 2 91 Subcooling Temp 106 F Press 12 psi PCS Prssure WR 13 NR 13 psia Steam Generator A Steam Generator B Level (WR) 0  % (NR) 0

                                                                                      ~
                                                                                            %        (WR)     0         %      (NR)          0
                                                                                                                                             ~

Press _I pela J I psia Flow Steam 0

                                                     ~

PPM Feed 0

                                                                                      ~

PPH Stean 0 PPH Feed 0

                                                                                                                                             ~

PPH Notet St am and Feed Flow X I000000

       $1.11 AFW Flow to A S/G              From P*8A&B g             Frcen P-8C g AFW Flow to 5 S/G              From P 8A&8 0             From P-8C 0-Condww.r vacuse (R)

P 50A g P 508 g P 50C g PPH P 500 g PPM PCP Seal Leskoff Flow PPM PPM SS Diesel Generator Frequency 11 0 12 60 1 C BUS Voltage @ Anps 9 1 D BUS Voltage 233p Anos g C 11 Back C 114 Contairment Area Monitors (R/Hr) RIA 1805 2,t2 RIA 1806 2n RIA 1807 2n RIA 1808 2n High Range Contairment Monitors (R/Hr) RIA-2321 2,JJ RIA 2322 .35E+03 Contairment Hydrogen Concentration (%) Al 2401R g. Al *.r11L g Main Steam Line Gamma (cpa) RIA 2324 .1 t e02 RIA 2323 ,25E+02 Stack Monitors RIA 2325 45E+03 cpn RIA 2326 4E+03 cpm RIA 2327 d ar/hr

 - v                      n               ,   w                                                         w ,                     __   ..--,-s   .

Scenario: PALEX-94 Time: 1115 Message No: 19 Scenario Time: 0245 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message Fort Control Room Personnel 4 Simulated Plant Conditions: Message: See data sheets. Alarm conditions are the same as at scenario time 0130. 4 O ~ 1 FOR CONTROLLER USE ONLY Controller Notes: Action expected:

_. _-_. _ . _ - _ . _ _ . _ . _ -. . __m -

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

MLt A W Date May 17. 1994 Massags#19, (Page 1) Time 1115 Scenselo Time 022 Time Jump Scenario Time Jump

                        $d5 SW Susps               P 7A ON               P 78 0FF                  P-7C ON                      SW Critical Ndr Press                             A 94                                 8$ psIg CCW Ptsps              P-52A 0FF             P 528 ON                  P 52C 03                      FPC Pumps                                   P 51A 0FF Fire Pumps             P 9A 0FF              P 98 0FF                  P 41 ON                                                                  'P 518 0FF Contairment Cooler Rectre Fans VIA ON              V2A ON      V3A ON                  V4A 0FF                                                        V1B ON                 V2B ON         V38 ON              V48 0FF C.:91 CCW Cooler Outlet Temp                  A               40 F           8       39 F Contaltwent Spray Punps                 P-54A 0FF                      P 548 0FF                    P 54C OFF HPSI Ptaps                              P 66A 0FF                      P 668 0FF                    LPSI Ptaps                               P 67A 0FF                         P 67B 0FF Safety Inlectlon Suction SuCDIY Train A                                                                                                                      Train B CV-3057 (SIRW) CLOSED CV 3029 ($1RW) CLOSED                                                                                CV 3031 ($1RW) CLOSED CV 3030 (Sump) CLOSED S.*SE CVCS
                                                                                                                ~

Letdown Charging Intermediate Press Letdown Teng 104 F Flow 0 gpm Letdown Line Tenp J04 F Line Temp 102 F i Letoown Flow g gpm Ptaps P-55A 0FF P 558 0FF P-55C OFF Volune Control Tank Terp 69 F Pressure M psi Level M % PCP Control Bleedoff Pressure 13 pelg Shutdown Cooline System SOCS from PCS (R) 101 F SOCS to PCS (R) H F Oueneh Tarik l Temp 101 F Pressure 0 pelg Level Q % Primary Coolant System Pressuriter Pressure (R) 1} psia PCS Tave (R) Loop 1 (TR 0111) $ Lo@ 2 (TR 0121) M Pressuriter Level (R) LRC 0101A 9  % LRC-01018 Q  % LIA 0102A j % P2r Mtr Amps LCC 15 9 LCC 16 0 PONV PRV 10428 CLOSED PRV-1043B CLOSED Block Valve MOV 1042A OPEN Mov 1043A CPEN PCPs- P-50A 0FF P-508 0FF P 50C OFF P 500 0FF I Reactor Power Level NI 01 3E+03 N! 02 3E+03 NI 03 73E 06 N! 04 3 E 06-N1 05 14E 06 NI 06 .14E 06 N! 07 .14E 06 NI 06 .15E-06 C2 AFW System AFW Ptap P 8A 0FF P 88 0FF P-8C OFF AFW Pusp Aaps P 8A 9 P-8C 9 AFW Pump P 88 Steam Pressure 9 psig AFW Disch Press P 8A & P 88 Jg P 8C j8 psi SecordarY System MSiv Bypass MOV-0501 Closed Mov-0510 Ct.0$FD MSIV's CV 0501 CLOSED CV 0510 CLOSED MFP Suction Pressure J5 psig MFP Discharge Pressure A 15 B 15 pel

                  ' Moisture Separator Drain Tank Level 14 %                                                              Cordenser Hotwell Level                               (( %

Atmospheric Dusp Valves CLOSED Condenser vacuun 0 in Hg. Heater Drain Ptsp Status P 10A 03 P-106 03 Gland Seal Condenser Vacuun j4_d in Ng. l Condensate Ptap Status P 2A 0FF P 28 0FF

                                                                                                                  .P.1P (Demand Log + Constant, Rod, or Flux / Temp)

Gross MW- Q Net MW 0 Core Exit Thermocouple Temperature 9 F Control Rod Position GP1 Q GP2Q GP3 0 GP4 9 GP5(P) 1 GP6(A)Q GP7(B)Q Stuet Rods MONE #0 2 1 1 1 l

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

DIts May 17. 1994 Messegs # M (Psgt 2) Time U M ScenarioTimeg245, Time Jurp Scenario Time Jtap DU T 81 Level 3 % T 939 Level J 9  % Condensate Storage Tank Level T 2 as % n\ Instrument Air Pressure 104, psig [ V Contaltment Building Pressure L,4, psig Dome Temperature M9 F Hunidity 19Q % S/G A Compartment Tenperature 149 F Hunidity Igg %

           $/G B Compartment                                                                           Tenperature        2,41 F            Hunidity 100 %

SitW Tank Ltvel J 8  % WR Contairment Pressure (R) 18 pela Contalruent Suy) Level 5~9,1 % Contairment Water Level (R) M%

           $1 Tank Level (%)                                          A 41 B 41                   C 41                        0 41 St Tank Pressure (psig)                                    A  23{                    8 2E                  C 332                        0    2 22]

PANEL K 13 SIAS Alare Mg Contairment High Pressure Alarm El Contalrnent High Radiation Alare 1[S E*1E concentrated Boric Aeld Tank Levels T53A 109 % T538 100 % Reactor Vessel DP 8.3 psid PORY Discharge Temperature 1L3 F Par Safety Valve Olscharge Tesp (F) RV 1039 127 RV 1040 142 RV 1041 JE PCP Current (Aaps) P 50A 9 P 508 0 P 50C 9 P 500 0 PCS Flow 9  % Pressure Level (cold) ;3  % Loop Thot (F) Loop 1 M Loop 2 190 Loop Teold (F) Loop 1 9_1 Loop 2 9_1 Teold Wide range Loop 1 91 Loop 2 J 9 St.bcooling Teap 106 F Press lg poi PCS Prssure WR J,i~ NR y psla Steam Generator A Steam Generator B Level (WR) 0  % (NR) Q  % (WR) Q  % (NR) Q  % Press } pela 0 Steam 14 pela 0 Feed 0 PPH Flow Steam 0~ PPH Feed PPH PPH ~ Note: Steam and Feed Flow x I000000 t E;11 AFW Flow to A $/G From P 8AAB 9 From P 8C Q AFW Flow to B S/G From P 8A&B 9 Fresa P 8C 9 Condenser Vacuun (R) Q PCP Seat Leakoff Flow P 50A 9 PPH P 508 Q PPM P 50C Q PPH P 500 g PPH E*94 Diesel Generator Frequency 11 9 12 69 1 C BUS Voltage 9 Anps 9 1 0 BUS Voltage {333 Anps Q C 11 Sack C 11A Contalruent Area Monitors (R/Hr) RIA 1805 221 RIA 1806 221 RIA 1807 ??? RIA 1808 ??? Migh Ranee Contaltwent Monitors (R/Hr) RIA 2321 .5E+03 RIA 2322 .5E+03 Contairment Hydrogen Concentration (%) Al 2401R g Al 2401L 9 Main Steam Line Gamma (cpm) RIA 2324 .23E+02 RIA 2323 .25E+02 Stack Monitors RIA 2325 45E+03 cpn RIA 2326 .6E+03 cpn RIA 2327 J mr/hr O

Scenario: PALEX-94 Time: 1130 Message No: 20 Scenario Time: 0300 O PALISADES NUCLEAR PLANT fjERGENCY PREPAREDNESS EXERCISE FORM Message For: Control Room Personnel Simulated Plant Conditions: Message: See data sheets. Alarm conditions are the same as at scenario time 0130. 4 O FOR CONTROLLER USE ONLY controller Notes: Action expected:

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

m en w. Date N'y 17, 1994 Ekssagn # {g (Pegs 1) Time 1))Q ScenarioTimeOJ399 Time Jump Scenario Time Jump E*9$ P 7A ON P 7B 0FF SW Critical Hde Press A% 8M pelg f SW Susps CCW Puupe P 52A gg P 528 ON P+7C ON P 52C OFF FPC Pumps P 51A DE Fire Pumps P 9A 0FF P 98 0FF P 41 ON 'P 518 0FF Contalruent Cooler Recire Fans V1A ON V2A ON V3A ON V4A 0FF V18 ON V28 ON V3B ON V48 0FF 3 E191 CCW Cooler Outlet Temp A 40 F S 39 F Contairvient spray Ptsps P 54A 0FF P 548 0FF P 54C g H HPSI Puips P 66A 08F P 668 0FF LPSI Ptaps P 67A 0FF P 67B 0FF Safety injection Suction Supply Train A Train B CV 3057 ($1RW) CLOSED CV 3029 (SIRW) CLOSED CV 3031 (SIRW) CLOSED CV 3030 (Suip) CLOSED C-02

     ~

CVCS

                                                                                                                 ~

Letdown Charging Intermediate Press Letdown Temp 104 F Flow 0 g;n Letdown Line Temp 104 F Line Temp J02 F Letdown Flow 0, 95n Pumps P SSA 0FF P 55B 0FF P 55C 0FF Volume Control tank Temp g F Pressure 2), psi Level M % PCP Control Bleedoff Pressure M psig Shutdown Cooting System SOCS from PCS (R) 10] F SOCS to PCS (R) 91, F Quench Tank Temp 101 F Pressure 0 psig Level Q % Primary Coolant System Pressurizer Pressure (R) jj psia PCS Tave (R) Loop 1 (TR 0111) 95 Loop 2 (TR 0121) M Pressurfter Level (R) LRC 0101A 0 _ % LRC-01018 9  % LIA-0102A ;}, % Par Mtr Aaps LCC 15 g LCC 16 9 PORV PRV 10428 CLOSED PRV 10438 CLOSED Stock Valve MOV 1042A CPEN MOV 1043A OPEN PCPs P 50A 0FF P 508 0FF P-50C OFF P 500 0FF Reactor Power Level N1 01 "IIE+03 NI 02 ' TIE +03 N1 03 .13E 06 Ni 04 .12s 06 NI 05 14E 06 NI 06 14E 06 N! 07 .14E 06 N1 08 .15E*06 E'.91 AFW System AFW Ptap P 8A 0FF P 88 0FF P 8C OFF AFW Puup Asps P 8A Q P 8C Q AFW Puup P 88 Steam Pressure g psig AFW Disch Press P 8A & P 88 !! P 8C 18 pal Secondary System MSIV Bypass MOV 0501 CLOSED MOV 0510 CLOSED MSIV's CV 0501 CLOSED CV-0510 CLOSED. MFP Suction Pressure H psig MFP Discharge Pressure A 15 8 15 psi Moisture Separator Drain Tank Level 14 % Condenser Notwell Level (( % Atmospheric Dung Valves CLOSED Condenser Vacuun 0 in Ng. Heater Crain Pulp Status P 10A 0FF P 108 0FF Gland Seal Condenser Vacuun 14.2, in Hg. Condensate Puup Status P 2A ,0_Q_ P 28 OE ElP. (Demand Log + Constant, Rod, or Flux / Temp) Gross MW g Net MW Q Core Exit Thermocotple Temperature Q F r Control Rod Position GP1 g GP2 0 GP39 GP49 GP5(P)1 GP6(A)g GP7(8)9 ( Stuck Rods NONE #0 l 1 a ,~ n , - . .

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

Dats May 17. 1994 Messigt829 (Pags 2) Timej,l}Q Scenariotime9100 1 Time Juro scenario Time Jutp Edd

 ,             T 81 Level 90 %              T 939 Level                     97 %                                      Condensate Storage Tank Level T 2                               $$ %

Instrtment air Pressure $ pelg 2.d psig Dome fewperature 275 F Hunidity 100 % ( Containment Building Pressure S/G A Ccapartment Teaperature @F Hunidi ty @% S/G S Compartment Temperature {g F Hunidity log % SIRW Tank Level 8,,1  % WR Contairment Pressure (R) 18 pela Containment Stmp Level El % Contalrunent Water Level (R) M% St Tank Levet (%) A 41 8 41 CM DM St Tank Pressure (psig) A 232 1 8 23] C 11? D 220 PANEL K 13 Contairveent High Pressure Alarm 1E.1, Contairment High Radiation Alarm E

               $1AS Alarm $                                                                                                                                                                         JE.S Ed3 Concentrated Boric Acid Tank Levels                                                 T53A            10,0 %          T538             100 %

Reactor Vessel DP M psid PORV Discharge Temperature 113 F Pzr Safety Valve Olscharge Temp (F) Rv-1039 127 Rv-1040 142 Rv 1041 E PCP Current (Asps) P 50A Q P-508 9 P 50C 9 P 500 g PCS Flow 0  % Pressure Level (cold) ~

                                                                                                                                                    -3     %

Loop Thot (F) Loop 1 59 Locp 2 199 Loop Tcold (F) Loop 1 91 _ Loop 2 9 J Teold Wide range Loop 1 91 Loop 2 J 9 Sthcooling Temp 106 F Press 12 psi . PCS Prssure WR [ NR 3 psia j Steam Generator A Steam Generator B Level (WR)  % (NR) Q  % (WR) Q  % (NR) Q  % Q Press 1 psia 14 psia Flow Steam 0 PPH Feed Q PPH Steam 0 PPH Feed 9 PPH Note: Steam and Feed Flow X 1000000

               $*11 AFW Flow to A $/G                From P 8A18 g                             From P 8C Q AFW Flow to 8 S/G -              Fran P 8A&8 g                             Fran P 8C 0 Condenser vacuun (R)                                        g

. PCP Seal Leskoff Flow P 5(>A 0 PPH P 508 g PPH P 50C 9 PPM P 500 Q PPH E9i Dieset Generator Frequercy 11 0 12 60 4 1 C SUS Voltage 9 Aaps 9 1 0 sus Voltage 23}Q Amps Q C 11 Sack C 11A Containment Area Monitors (R/Mr) RIA 1805 2)), RIA 1806 ?,n RIA 1807 ??? RIA+1808 ??? Migh Range Containment Monitors (R/Mr) RIA 2321 . 7E + 03 RIA 2322 .7E+03 Containment Hydrogen Concentration (%) Al 2401R Q Al 2401L g Main Steam Line Gamune (cpa) RIA 2324 .23E+02 RIA 2323 ,25E+02 Stack Monitors RIA 2325 48E+03 cpm RIA 2326 .1E+04 cpm RIA 2327 J mc/hr

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

r . , - - . - ,

4 Scenario: PALEX-94 Time: 1145 Message No: 21 Scenario Time: 0315 PALISADES NUCLEAR PLANI EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Control Room Personnel Simulated Plant Conditions: Message: See data sheets, Alarm conditions are the same as at scenario time 0130. i O FOR CONTROLLER USE ONLY controller Notes: Action expected: I LO

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

FRttA y% Date May 17, 1994 Messege#{,! (Pegs 1) Time 114,,5, ScenarioTime93M Time Jtap Scenario flee Jtap j

         $.'.90 SW Sunps                P 7A QN             P 78 0FF                 P 7C ON                          SW Critical Mdr Press                              AM                       8M psig CCW Ptsps                P 52A 02            P 528 ON                 P 52C OFF                        FPC Pums                             P51AgffF, Fire Ptaps              P 9A E              P 99 0FF                 P 41 ON                                                             'P 518 gfff Contalrvnent Cooler Rect re Fans VIA ON               V2A ON      V3A ON             V4A 0FF                                                             V18 ON          V28 ON              V38 ON      V48 0FF d

CCV Cooler Outlet Temp A 49 F S 19 F Contairunent Spray Ptsps P 54A gf7 P 548 OE P 54C grF NPSI Ptsps P+66A 0FF P 668 0FF LPSI Ptsps P 67A gf7 P-678 off, Saf ety Inlection Suetion Staty Train A Train 8 CV 3057 (SIRW) Closto CV-3029 (SIRW) CL0 SED CV 3031 (SIRW) CL0sto CV 3030 (Sump) CLOSED LE$ SYSS Letdown Charging Intermediate Press Letdown Temp 1,04, F Flow 0 spn Letdown Line Temp 104, F Line Teap 10{ F Letdown Flow Q gpn Ptaps P-55A 0FF P 558 0FF P 55C OFF Volume Control tank Temp 69 F Pressure 21 psi Level M % PCP Control Bleedoff Pressure jj psig

Shutdown Cootino System SOCS frora PCs (R) 10,2 F SOCS to PCS (R) 91 F cuench Tank T enp 101 F Pressure 0 psig Level M %

Primary Coolant System Pressurizer Pressure (R) 13 pela PCS Tave (R) Loop 1 (TR 0111) 95, loop 2 (TR 0121) 96, , Pressurizer Level (R) LRC 0101A Q 1 LRC 01018 9  % LIA-0102A ;3,  % P2r Ntr Anps LCC 15 9 LCC 16 9 PORV PRV 10428 CloSFO PRV 10438 Closto Block Valve McV 1042A gPg Mov 1043A O,_PE,3 PCPs P 50A 0FF P 508 0FF P 50C OFF P 500 gf.f Reactor Power Levet NI 01 3E+03 NI 02 me+03 mi 03 3E06 ul 04 .12s 06 NI*05 .14E 06 NI 06 14E 06 NI 07 14E 06 N1 08 .155 06 LE1 AFW System AFW Ptsp P 8A Of P 88 0FF P-8C 0FF AFW Ptap Aaps P 8A 0 P 8C 9 l AFW Ptap P 88 Steam Pressure Q psig AFV Disch Press P 8A & P 88 M P 8C M pel

                                                                                            $econdary System MSIV Bypass MOV 0501 Ct0$F0 MOV 0510 CLOSED                                                           MSIV's                            CV 0501 ClosE0                    CV 0510 Closto 4

MFP Suction Pressure M psig MFP Olscharge Pressure AM 8 ,1,1 pel Moisture Separator Drain Tank Levon M % Corulenser Notwell Level 8g % 4tmospheric Dump Valves CLOSED Condenser Vacuun 9 in Ng. Heater Drain Puup Status P 10A 0FF P 108 0FF Gland Seal Condenser Vacuus M in Ng. Condensate Ptamp Status P 2A gff, ,F P 2s 0,f F, PlP. (Demand Log + Constant, Rod, or Flux / Temp) Gross MW Q Net MW 9 Core (mit Thersocotple Temperature 0 F Control Rod Position GPlg GP29 GP3Q GP4 0 GP5(P)j, GP6(A)2 GP7(8)g Stuck Rods g N #0

          - -:    y-   - - , , . -+,                              -       --              ,m.-                        -     - - - - , ,

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

Dets May 17. 1994 Messags#21 (Page 2) TimejlM ScenarioTimeg},11 Time Jisp Scenario Time Jurp E*1.E T 81 Level 90 % T 939 Level 92 % Condensate Storage Tank Level T 2 as % instrument air Pressure j o4, pelg s Contairment Sullding Pressure M psig Dane Temperature }QQ F Hmidity LOO % S/G A Coupertment Tenperature _290 F Munidi ty 3 1 % S/G B Compartment Tenperature 392 F Hunidity 199 % SIRW Tank Level  !! % WR Contalnuent Pressure (R) 18 psia Contairment Samp Level 191 % Contairment Water Level (R) 191 % 5

        $1 Tank Levst (%)                            AM                       8M                            CM                    D s1 St Tank Pressure (pulg)                      A jJ3]                   8 232                         C  23]

3 D lig PANEL K 13 SlAS Alarm M Contairment High Pressure Alarm $ Contairment High Radiation Alaren MS, E*1$ Concentrated Boric Acid Tank Levels T53A 10 9 % T538 100 % Reactor vessel DP J 8 psid PORV Olscharge Temperature 1 13 F Par Safety Valve Discharge Teep (F) RV-1039 127 RV 1040 142 RV 1041 177 PC8 Current (Asps) P-50A 9 P-508 g P 50C 9 P 500 f PCS Flow g  % Pressure Level (cold) d  % Loop Thot (F) Loop 1 M Loor 2 100 Loop Teold (F) Loop 1 9,1 Loop 2 91 Tcold Wide range Loop 1 91 Loop 2 @ Subcooling Temp 1% F Press 12 psi PCS Prssure WR [ NR j)3 pSla Stem Generator A Steam Generator 8 Level (WR) 0  % (NR) 0

                                                                                  ~
                                                                                           %       (WR)        0     %      (NR)      0
                                                                                                                                      ~

Press } psia Stem li psia Feed PPH FLW Stem Q PPH Feed 9 PPM 9 PPH Q j f Note: Steam and Feed Flow X 1000000 I 1 g AFW Flow to A $/G From P 8A18 9 Frosi P 8C g AFW Flow to B $/G From P 8AA8 9 From P-8C g condenser vacuun (R) g PCP Seat Leakoff Flow P 50A g PPH P 5OR Q PPH P 50C 9 PPH P 500 g PPH

        $*Si Olesel Generator Fregancy                  11 g                     1 2 sg 1 C BUS                              voltage g                    Amps 9 1 0 BUS                              voltage 2339                 Anps g C 11 Back C-11A Contairment Area Monitors (R/Hr)                            RIA 1805 111                     RIA 1806 I?!

RIA 1807 122 RIA 1808 121 High Range Contalnuent Honitors (R/Hr) RIA 2321 .9E+03 RIA 2322 .9E+03 Containment Hydrogen Concentration (%) Al 2401R g Al 2401L g Main Steam Line Gaune (cpm) RIA 2324 .23(+04 RIA 2323 m25E+02 Stack Monitors RIA 2325 .5E+03 cpn RIA 2326 111 cpn RIA 2327 M mr/hr O

Scenario: PALEX-94 Time: 1200 Message No: 22 Scenario Time: 0330 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM i Message For: Control Room Personnel Simulated Plant Conditions: 1 Message: See data sheets. Alarm conditions are the same as at scenario time 0130. 4 i FOR CONTROLLER USE ONLY Controller Notes: Action expected: O

nica y* Data May 17. 1994 Missage # 22 (Ptge 1) 20 Time 1200 Scenario Time 0330 Time Jump Scmario Time Jusp

      $I.$$

SW Swps P 7A ON P TB 0FF P-7C ON SV Critical Hde Press A 94 B 94 pelg CCW Purps P*52A 0FF P 528 ON P 52C 03 FPC Purps P 51 A DE Fire Purps P 9A 0FF P 98 OFF P 41 ON P 51B pH Contaltnent Cooler Rectre Fans V1A ON V2A ON V3A 04 V4A 0FF V1B ON V2B ON V3B ON V48 0FF d CCW Cooler Outlet Teep A 40 F 8 39 F Contairment Spray Puups P-54A 0FF P 548 0FF P 54C orF HPSI Purps P-66A 0FF P 668 0FF LPSI Pumps P 67A 0FF P 678 0FF Safety inlection Suetion Stroty Train A Train B CV 3057 ($1RW) CLOSED CV-3029 (SIRW) CLOSED CV-3031 (SIRW) CLOSED CV 3030 (Simp) CLOSED E*E$ CVCS

                                                                                       ~

Letdown Charging Intermediate Press Letdown Tesp 104 F Flow 0 gpn Letdown Line Tenp 104, F Line Teap ,10] F Letdown Flow g gpn Pumps P 55A pH P 558 0FF P-55C OFF Volune Control Tank Tenp 69 F Pressure 21 psi Level 14,  % 'PCP Control Bleedoff Pressure y psig Shutdown Cooling System SOCS from PCS (R) ,103 F SOCS to PCS (R) 9,1 F Quench 1ank Tenp 101 F Pressure O psig Level Q % Primary Coolant System Pressurizer Pressure (R) 13 psia PCS Tave (R) Loop 1 (TR 0111) M Loop 2 (TR 0121) 96 Pressurizer Level (R) LRC 0101A 9  % LRC 0101B g  % LIA 0102A 3 _3,  % Par Htr Anps LCC 15 0 LCC 16 9 PORY PRV 10428 CLOSED PRV 10438 CLOSED Block Valve MOV 1042A gPE MOV 1043A gP,Et PCPs P-50A 0FF P 508 0FF P 50C OFF P 500 0FF Reactor Power level N!*01 .14E+03 NI 02 .13E+03 N!*03 .13E 06 N1*04 .12E 06 N1 05 14E-06 NI 06 14E 06 N1 07 .14E 06 Ni 06 .15E 06 S.$1 AFV System AFW Puup P 8A 0FF P 88 0FF P 8C 0FF AFW Pump Asps P 8A 9 P 8C 9 AFW Pulp P 88 Steam Pressure g psig AFW Disch Press P 8A & P 88 ,1,! P 8C j,8, pal Secondary System MSiv 8ypass Mov 0501 Closed MOV 0510 Cl0 SED MS!V's CV 0501 Cl0 SED CV 0510 CLOSED MFP Suction Pressure J.5, psig MFP Discharge Pressure A 15 8 15 psi Moisture Separator Drain Tank Level J,4 % Condenser Notwell Level !2 % Atmospheric Dump Valves CLOSED Condenser Vacuuo g in Ng. Nester Drain Pump Status P 10A 0FF P 108 0FF Gland Seal Condenser Vacu e 14 2 in Ng. Condensate Ptap Status P 2A 0FF P 28 0FF f.!E (Demand Log + Constant, Rod, or Flux /Teap) Gross MW g Net MW 9 Core Exit Thermocouple Tenperature g F Control Rod Position GP1 0 GP2g CP39 GP4g GP5(P)j, GP6(A)g OP7(B) g O Stuck Rods M #g

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

DSte M*v 17, 1994 Messtge # H (Pagt 2) Time 1209 ScenarioTime033Q Time arp Scenario Time Jurp f Gdl T 81 Level 90 1 T 939 Level 97 % Condensate Storage Tank Level T 2 QQ % Instrument Air Pressure $ psig Contairement Building Pressure M psig Dome Temperature }0Q F H midity 100 % S/G A Compartment Teeperature 22Q F Hunidity M% i, S/G B Ccapartment Tesperature H2 F Hunidity 10Q Q  % SIRW Tank Levet 91 % WR Contalrunent Pressure (R) 18 Contafrument Stmp Level @ psia  % Contairment Water Level (R) M% St Tank Level (%) AM B 41 C 41 0 41 St Tank Pressure (palg) A 331 B@ C 23) D HQ PANEL K 13 SIAS Alarm !!0 Contairment High Pressure Alarm !!g Containment High Radiation Alarm JJ,1 M Concentrated Boric Acid Tank Levels T53A 10Q % T530 100 % Reactor Vessel DP QJ psid PORV Discharge Temperature jl} F Par Safety Valve Discharge Temp (F) RV 1039 !!! RY 1040 142 RV 1041 1E PCP Current (Asps) P 50A Q P 508 Q P 50C Q P-500 0 . PCS Flow Q  % Pressure Level (cold) J  % 1 Loop Thot (F) Loop 1 _99 Loop 2 10Q Loop Teold (F) Loop 1 91 Loop 2 1, 4 Tcold Wide range Loop 1 91 Loop 2 1,

               $4 cooling                       Temp          _106 F               Press             12 pst PCS Prssure                      WR            13                   NR                13     psia Steam Generator A                                                Steam Generator 8 Level                            (WR)          Q         %          (NR)             Q     %       (WR)         Q         %           (NR)           Q           %

Press 1 pela 14, psia Flow Steme g PPH Feed 0 PPH Steam 0 PPM Feed 0 PPM h Note Steam and Feed Flow X T000000

                                                                                                                                                                    ~

U M AFW Flow to A S/G From P 8A18 Q Fran P 8C Q AFW Flow to B S/G From P 8A&B Q Frce P-8C 9 Condenser Vac w n (R) Q PCP Seal Leakoff Flow P 50A Q PPH P 508 Q PPH P 50C Q PPH P 500 Q PPM M Diesel Generator Frequency 11 0 12 60 1 C BUS Voltage Q Anpe Q 1 0 BUS Voltage gjj0 Aaps g C 11 8ack C 11A Containment Area Monitors (R/Hr) RIA 1805 lit RIA 1806 221 RIA 1807 In RIA 1808 In High Range Contalrument Monitors (R/Hr) RIA 2321 .1t+04 RIA 2322 .tE+04 Contalrument Hydrogen Concentration (%) Al*2401R g Al 2401L Q Main 3 team LIne Gammo (cpa) RIA 2324 .23E+02 RIA 2323 .25E+02 Stack Monitors R1A 2325 .5E+03 cpm R1A 2326 2,21 epe RIA 2327 g er/hr

    ., , . , . - - , - - -                  . -      , , = .      - . -- . , . ,                                  .- -           - - -                    - - - - . - - . . . - - - - - - . - - -

Scenario: PALEX-94 Time: 1205 Scenario Time: 0335 k PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Control Room Personnel Simulated Plant Conditions: Message: A sharp concussion is felt throughout the plant. All Containment pressure indicators briefly pegged upscale and now indicate 0 psig. t FOR CONTROLLER USE ONLY Controller Notes: A hydrogen " burn" has occurred in Containment. Any previously existing water seal in the Fuel Transfer Tube is expelled, and the Containment now freely vents to the Fuel Handling Building. Action expected:

1. Inject the remaining contents of the SIRWT to the PCS/ Containment Sump.

2. Efforts will focus on sealing the Containment breach, 1"%

V

Scenario: PALEX-94 Time: 1215 Message No: 24 Scenario Time: 0345 PALISADES NUCLEAR PLAMI EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Control Room Personnel Simulated Plant Conditions: Message: See data sheets. Alarm conditions are the same as at scenario time 0130, except that Containment Pressure Off-normal (EK-13 Annunciator no. 62) has cleared. O FOR CONTROLLER USE ONLY Controller Notes: If desired by the Lead Controller, the time jump to new plant conditions can be made anytime after time 0345. Action expected:

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

FAltA V4 Cate May 17, 1994 Message # M (Pags 1) Time R H Seensrlo Time 0345 Time Jtap Scenarlo Time Jtsp S*S$ i SW Simps P 7A QN P 78 0 3 P*7C QN SW Celtical Nde Press A 94 8g pelg CCW Ptaps P*52A 077 P 528 ON P52Cpfl FPC Ptsps P51Agg

,                     Fire Ptsps        P 9A Q11                    P 98 gff                      P 41 93                                                                                           'P 518 93 Contaltvnent Cooler Rectre Fans l                          V1A QN           V2A QN            V3A QN               V4A 0FF                                                                                      V18 ON                  V28 ON           V38 ON             V4B 0FF I                    E:21 l                    CCW Cooler Outlet Temp                       A        40 F                   8         30 F i                    Contalrment spray Ptaps                      P 54A 0FF                       P 548 0FF                        P 54C OFF j                     HPSI Ptmps                                   P 66A OFF                       P 668 0FF                        LPSI Ptaps                                                      P 67A 0FF                            P 678 0FF 1

l Safety infection Suetion Supply Train A Train 8 CV 3057 (SIRW) Cl0 SED CV 3029 (SIRW) Cl0 SED CV 3031 (SIRW) CLOSED CV 3030 (Stap) CLOSED C:.9L SES Letdown Charging Intermediate Press Letdown Tenp 104 F Flow . O gen Letdown Line Temp 194, F Line f eng 101 F Letdown Flow 0 gpn Ptaps P 55A pH P 558 077 P 55C OFF Volts

• Control tank fenp _ 69 F Pressure U pal Level 54,  % PCP control Steedoff Pressure H psig Shutdown Cooling System SDCS from PCS (R) 02 F

                                                                                ,1_02                                                                                   SOCS to PCS (R) 91 F Quench tank i                                                              Temp 101 F                           Pressure 0                 pelg                                                           Levet M %

Primary Coolant System Pressuelter Pressure (R) M pela PCS Tave (R) Loop 1 (TR 0111) 95 Loop 2 (TR 0121) % Pressuriter Level (R) LRC 0101A fX LRC 01018 [ % LIA 0102A 3

                                                                                                                                                                                                             ,,,3    %

Par Htr Anpa LCC 15 9 LCC 16 g PORV PRV 10428 Cl0 SED PRV 1M38 CLOSED Block Valve Mov 1042A OPEN N0V 1043A gPJ3 PCPs P 50A 0FF P 508 OFF P*50C OFF P 500 OFF Reactor Power Level NI 01 ~I4E+03 NI 02 "I3E+03 N1 03 " T5E 06 NI 04 ~ilt 06 NI 05 14E-06 N! 06 ,14E 06 NI 07 14E 06 N! 08 .15E 06

                    $*.93 AFW System AFW Pulp P 8A 0FF P 88 0FF P 8C OFF                                                                            AFW Ptap Amps                                                     P 8A 9                              P 8C 9 AFW Pulp P 88 Steam Pressure                               g          psig                                     AFW Disch Press P 8A & P 88 3                                                                         P 8C Ig    pal Secondary System MSIV Bypass Mov 0501 CLOSED MOV 0510 CLOSED                                                                    MSIV's                                                         CV 0501 CLOSED                     cv 0510 Ekggg MFP Suction Pressure                                       M psig                                              MFP Discharge Pressure                                                AM                                  8g     pel Moisture separator Drain Tank Level M %                                                                        Cordenser Notwell Level                                                  gg 1 Atmossheric Otmp Valves                                    CLOSED                                              Condenser Vactaan                                                        g           ln Ng.

Neater Drain Ptsp Status P 10A 0FF P 108 0FF Gland Seat Condenser vacuun 14.2 ln Ng. Condensate Puup Status P 2A pfl P 28 Of d f.l.P. (Demand Log + Constant, Rod, or Flux /fesp) Gross MW 9 Net NW 0 Core Exit Thermocouple fesperature 0 f Control Red Position GP1 0 GP2 0 GP3 0 GP4g GP5(P)1 GP6(A)g GP7(8)g Stuck Rods NON( #g w g - - - - -

                   - >              ww                -w,.   ,,wa       -,                    .,wm-,,        ,,.am--e       .-wr,-     --,,--n--      - - - - - - , - - - - , . . , . , . - - , -                     -     --v-.      -

Date May 17, 1994 Mststg3#{4 (Pagt 2) TimeJM ScenarioTimeOj4j, l ! Time Jurp scenario Tise Jung S-1} T 81 Level 99 % T 939 Level 97 % condensate Storage Tank Level T 2 86

                                                                                                                                        ~    %

Instrument Air Pressure $ psig k Contalruent tullding Pressure 9 psig Dose Teeperature }0g F Munidity log % S/G A Compartment Tenperature 299 F Humidity log X S/G B Co e rtment Temperature 291 F ' Hunidity 199 % SIRW Tank Level 8_1 % WR Conteirunent Pressure (R) 15 Contalrnent Susp Level @ pela

                                                          %                       Containnent Water Level (R)                           595, %

St Tank Level (%) A 41 8 4_1 C 41 0 41 St Tank Pressure (psig) A j]3l B jj,2 C j},{ 0 2,2! PANEL K 13 i S!As Alarm j@ Contaltnent Nigh Pressure Alarm Ng Contairment High Radiation Alarm ES JES Sill i concentrated Boric Acid Tank Levels T53A 100 % T538 100 % Reactor Vessel DP Q psid PORY Discharge Temperature 113 F Par Safety Valve Discharge Temp (F) RV 1039 m RV 1040 142 Rv 1041 177 BCP Current (Asps) P 50A Q P 500 g P 50C 9 P 500 0 PCS Flow g  % Pressure Level (cold) J3  % Loop Thot (F) Loop 1 99 Loop 2 100 Loop Tcold (F) Loop 1 91 Loop 2 9l Teold Wide range Loop 1 6 Loop 2 _91 S4 cooling Tenp 106 F Press 12 pal PCS Prssure. WR 7 NR h psia Steam Generator A Steam Generator 8 Level (WR) 9  % (NR) 9  % (WR) 0  % (NR) 9  % Press 1 pela h psia Flow stean 0

                                                    ~

PPH Feed 0 PPH Steam PPH Feed ~ 0 PPH Note: Steam and feed Flow X 000000 Sall AfW Flow to A S/G Fran P 8A&8 Q From P 8C 0 AFW Flow to B S/G Free P 8A&8 9 From P 8C 9 Condenser vacuun (R) 9 PCP Seel Leakoff Flow P 50A g PPH P 508 Q PPM P 50C g PPH P 500 Q PPH St.9! Diesel Generator frequency 11 g 12 60 e 1 C BUS Voltage 0 Aaps Q 1 0 sus Voltage'1]32 Aaps 2 C 11 Back C 11A Contalruent Area Monitors (R/Hr) RIA 1805 m RIA 1806 m RfA 1807 m RIA 1808 m High Range Contalruent Monitors (R/Hr) RIA 2321 1E+04 RIA 2322 ,1E+04 Contalruent Hydrogen Concentration (%) Al 2401R g Al 2401L 9 Main Steam Line Ganae (eps) RIA 2324 ,23P02 RIA 2323 .25E+02 Stack Monitors RlA 2325 .5E+03 cpn RIA 2326 m epn RIA 2327 H mr/hr O

l Scenario: PALEX-94 Time: 1230 Scenario Time: 0400 O PALISADES NUCLEAR PLANT ENERGENCY PREPAREDNESS EXERCISE FORM (' Message For: Control Room Personnel ( simulated Plant conditions: 1 Message: See data sheets. Alarm conditions are the same as at scenario time 0130.

                                                                              )

ll i-1 g l FOR CONTROLLER USE ONLY controller Notes: If desired by the Lead Controller, the time jump to new plant conditions can be made anytime after time 0345, Action expected: l 1

                                                                              .i

 .- _ _ _ . _ _ _ _ . . _ _ . _ .           _ . _ . _                                                      -m          _ _ _ _ . _ . _ _                                  _                       _ . _ _ _

gfgp v. Date May 17, 1994 Messags # D (Pcge 1) Time,Qlg $cenarlo flee 94,99 Time Juip $cenario Time Juip L'20 sw Susps P*7A @ P 75 QQ P*7C go! $W Critical Nde Press A94 8M psig CCV Pusps P 52A 03 P+528 go! P 52C gg FPC Purps P 51A gg Fire Pusps P 9A g,Q P 98 0FF P 41 ON 'P 518 0FF Contairement Cooter Rectre Fans VIA B V2A Qt! V3A ON, V4A Og Vit gti, V2a ON V38 ON V48 0FF S.'$.1 CCW Cooler Outlet Temp A 4g F 0 39 F Contairment spray Puips P 54A 0FF P 548 0FF P 54C g g MP11 Pumps P MA 02 P 668 gfg LPSI Pumps P67AgM P 678 OE safety Inleetion suction si a ty Train A Train 8 CV 3057 ($1RW) CtosE0 CV 3029 ($1RW) Closed CV 3031 ($1RW) ClosE0 CV 3030 ($unp) CLOSED 5:9E US$ Letdown Charging Intermediate Press Letdown Temp 104 F Flow 0 gpm Letdown Line Temp 104 F Line Teap ig{ F Letdown Flow g gFat Pups P 55A OfE P 558 0FF P 55C 0FF Volune Control Tank Teep (9 F Pressure U pal Level 8 % Pt? G itrol Bleedoff Pressure 1,} psig shutdown Coolind System 50C$ from PCs (R) 10{ F SOC $ to PCs (R) 9,1 F ovench Tank fenp 101 F Pressure g psig Level j,} % Primary Coolant $ystem Pressuciter Pressure (R) 1} psia PC$ Tave (R) Loop 1 (TR 0111) n Loop 2 (TR 0121) M Pressuciter Level (R) LRC 0101A 0  % LRC 01010 9  % LIA 0102A d % Par Mtr Asps LCC 15 g LCC 16 g PORV PRV 10428 CLO$ED PRV 10438 CL0$E0 Block valve Mov 1042A gPJ MOV 1043A QPE PCPs P 50A gg P 508 OFF P 50C gfg P 500 QLF Reactor Power Level NI 01 14E+03 NI 02 ~'3E+031 N!*03 13E 06 NI 04 T. at 06 Nl.05 .i4E*06 Wl 06 14E 06 NI 07 2.14f 06 NI 08 .15E 06 AFV System l AFV Pusp P 8A gH P 88 QfQ P 8C 03 AFW Pump Amps P 8A .9 P 8C 9 AFV Puup P*88 Steam Pressure g psig AFV Olsch Press P 8A & P 88 Il P 8C Jj pel

                                                                                                                                                                                                              ]

Secondary System MSIV Oypass MOV 0501 CLO$E0 MOV 0510 Cte$E0 M$lvis CV 0501 EE$g_0 CV 0510  ! MFP Suction Pressure 15 psig MFP Discharge Pressure A _15, Egggy, 81.5, ps i l Moisture Separator Orain tank Level 3 % Condenser Hotwell Level ((  % Atmospheric Ousp Valves CLOSED Corutenser Vacuun 0 in No. Heater Drain Puip status P 10A 92 P 108 OE Gland $eal Condenser vacuta M in Ng. Condensate Pump Status P 2A pfg P 28 9.Q EM (Desend Log + Constant, Rod, or Flux / Teep) Gross MW Q Net MW g Core Exit thermocotele fenperature g F Control Rod Position CP1g GP2g CP3g GP4 g GP5(P)1 GP6(A)Q CP7(B)g stu:k Rods NONE #2 _ ~ . _ _ . _ _ _ . _ ___ _ - __ _ , -

0:ts MaY 17,1994 Message # 25 (Page 2) Time 1230 Scenario Time 0400 Time Jtap Scenario Time Jupp E*11 T 81 Level 99 % T 939 Level 97 % Condensate Storage Tank Level T 2 86 %

          \    Instrument Air Pressure                           104 pig
      ~d ' Contalrunent Building Pressure                        9    peig                     Dome Temperature }09 F                                      Humidity 199 %

S/G A Coopertment Temperature g99 F kunidity 10Q % S/G B Coupertment Temperature 292 F Hunidity 10Q % SIRW Tank Level 8J % WR Contairment Pressure (R) 15 psia Contalrunent Sep Level F 3% Containment Water Level (R) M% SI Tank Level (%) A 41 B 41 C 41 0 41 SI fank Pressure (psig) A l.lg 8 {}] C g}3] O 2 22@ PANEL K-13 SIAS Alarm $ Contairunent High Pressure Alarm $ Contairvnent High Radiation Alarm 1{S, til concentrated Boric Acid Tank Levels T53A 199 % T538 100 % Reactor Vessel DP 8J psid PORV Discharge Temperature 11} F Pzr Safety Valve Olscharge Temp (F) RV 1039 127 RV 1040 142 Rv 1041 E PCP Current (Asps) P 50A Q P-50B Q P-50C 0 P 500 g PCS Flow 9  % Pressure Level (cold) . ;}  % Loop Thot (F) Loop 1 99 Loop 2 q

                                                                                         ,1,0q Loop Tcold (F)                Loop 1 91                         Loop 2 91 Teold Wide range              Loop 1 91                         Loop 2 .91 _

Subcooling Temp 31 F Press 12 psi PCS Prssure WR 1}} NR 13 psia Steam Generator A Steam Generator B Level ('A) 9  % (NR) Q  % (WR) Q  % (NR) Q  % Press 1 psia li psw Flow Steam 9 PPH Feed Q PPH Steam Q PPH Feed g PPH Note Steam and Feed Flow X 1000000 ( E.11 AFW Flow to A $/G Fran P-8A&S 9 from P 8C 9 AFW Flow to B S/G From P 8A&8 9 From P 8C 9 Condenser Vacuun (R) 9 PCP Seal Leakoff Flow P-50A g PPM P 508 g PPH P-50C g PPH P-500 2 PPH ES'. Olesel Generator Frequency 11 Q 12 sg 1 C BUS Voltage g Amps 9 1 0 BUS Voltage 1339 Anps g C-11 Back C-11A Contalrusent Area Monitors (R/Hr) RIA 1805 111 RIA 1806 m RIA 18 F ??? RIA 1808 ??? High Range Containment Monitors (R/Hr) RIA 2321 .1E+04 RIA 2322 1E+04 Contalrunent Hydrogen Concentration (%) AI 2401R 9 Al 2401L 9 Main Steam Line Gamme (cpm) RIA-2324 .23E+02 RIA 2323 .2SE+02 Stack Monitors RIA 2325 M43 cW RIA 7326 122 cpm RIA 2327 5 mr/hr I i g ._,, ., , - . , . _ , - . _ , ,_...A. _ . . . _ . - . - . . _ _ , . . _ . _ _ _ .

                                                                                 }

Scenario: PALEX-94 Time: 1245 Message No: 26 Scenario Time: 0415 PALISADES NUCLEAR PLANT ENERGENCY PREPAREDNESS EXERCISE FORM Message For: Control Room Personnel Simulated Plant Conditions: Message: See data sheets. Alarm conditions are the same as at scenario time 0130. O 1 FOR CONTROLLER USE ONLY Controller Notes: If desired by the Lead Controller, the time jump to new plant conditions can be made anytime after time 0345. Action expected: t l j

FAttA v4 Date May 17, 1994 M3sstga # M (Pege 1) Time 1245 Scenario Time 04j5 Time Jump Scenario Time Jtap

                 $.*9$
 /~'              SW Surps            P 7A ON           P 78 0FF                P 7C ON                   SW Critical Mdr Press              A 94                                   8 94 psig i                CCW Pumps           P 52A DE          P 528 ON                P 52C OFF                 FPC Punps                     P 51A OH f ire Purps         P 9A QF1          P 99 0FF                P-41 ON                                                'P 518 0FF Contairunent Conter Recire Fans VIA ON         V2A ON       V3A ON            V4A 0FF                                              V1B ON          V28 DN                V38 ON           V48 0FF
                $*S}

CCW Cooler Outlet Temp A 40 F B 39 F Contairunent Spray Pumps P-54A c'F P-548 0FF P 54C pir, HPS! Pumps P 66A OFF P-668 0FF LPSI Ptaps P 67A g,8,F P 678 pff, Safety injection Suction Steply Train A Train B CV 3057 (SIRW) CLOSED CV 3029 ($1RW) Ct 0 SED CV 3031 (SIRW) CLOSED CV-3030 (Simp) CLOSED E*.El CVCS

                                                                                                ~

Letdown Charging intermediate Press Letdown Tenp 104 F F' -* 0 gpm Letdown Line Temp jo4, F 2r- f esp j.01 F Letdown Flow 0 gpm Puups P-55A 0FF P 55B 0FF P 55C OFF Volune Control Tank fenp 69 F Pressure U psi Level 54,  % PCP Control Bleedoff Pressure j 3, psig Shutdown Cooling System SDCS from PCS (R) J01 0 F SOCS to PCS (R) ,9,,,1, F Ouench Tank F Pressure 0 psig Temp 101 F Level @ % Primary Coolant System Pressurizer Pressure (R) j3 psia PCS Tave (R) Loop 1 (TR 0111) 95 Loop 2 (TR 0121) M Pressuciter Level (R) LRC-0101A 0 _ % LRC-01018 0  % LIA 0102A -3  % P2r Mtr Anps LCC 15 g LCC 16 0 PORV PRV 10428 CLOSED PRV 10438 CLOSED Block Valve MOV 1042A gPE MOV-1043A gP[N PCPs P-50A 0FF P 508 0FF P 50C OFF P-500 0FF Reactor Power Level NI 01 .14E+03 NI 02 _.13E+03 NI 03 13E 06 NI 04 .12E 06 NI 05 .14E-06 NI 06 14E-06 N! 07 .14E 06 NI 08 .15E 06 E*El AFW Systte AFW Pump P-8A 0FF P 88 0FF P 8C OFF AFW Puup Anps P BA 9 P 8C 9 AFW Puup P 88 Steam Pressure 2 psig AFW Disch Press P 8A & P-88 18 P 8C 18 psi jecordary System MSIV Bypass Mov 0501 CLOSED MOV 0510 CLOSED MSIV's CV-0501 CLOSED CV-0510 CLOSED EFP Suction Pressure H psig MFP Discharge Pressure A ijt B3 psi l Moisture Separator Drain f ar* Level j4,  % Condenser Hotwell Level _8.2,  % AtmosF A eric Dunp Valves CLOSED Condenser Vacuun 9 in Ng. l heater Drain Puup Status P-10A 0,fF, P 108 Off, Gland Seal Condenser vacuun jM in Hg. l Condensate Puup Status P-2A 0FF P 28 0FF PJ P,, (Demand Log + Constant, Rod, or Flux / Temp) Gross MW g Net MW g Core Exit Thermocouple Temperature p F g Control Rod Position GP1 ,0 CP2 0 GP3 0 GP4 g GP5(P)j, GP6(A) 0 GP7(B) 0 p Stuck Reds N,0N,{ fg x

                     ..       .     ~.                  .       .                                          .            -                 .      - -

N Data May 17. 1994 Messige#{6 (Pcg* 2) Time 1245 Scenario Time 0415 Time Jtsp Scenario Time Jtap E*11 T 81 Level 90 % T 939 Level 97 % Condensate Storage Tank Level T-2 - 86 %

                                                  @ psig

( -- Instrument air Pressure Contalrunent Building Pressure Q psig Dome Temperature }QQ F Mtsnidity 10Q % S/G A Compartment Temperature 29_Q F Honidity 109 % S/G 8 Compartment Tenperature 29_{ F HLaidity Igg % SIRW Ter* Level 8J % WR Contalrunent Pressure (R) 15 Contairment Stsp Level @ psia

                                                      %                        Contairment Water Level (R)                 M%

St Tank Level (%) A 41 8 41 C 41 0 41

       $1 Tank Pressure (psig)                A 232                  8 j}31                    C 232                  0 228 PANEL K-13
       $1AS Alarm M                    Contairment High Pressure Alarm M                        Containment High Radiation Alarm        E Y_ES E*1.2 Concentrated Boric Acid Tank Levels                   T53A        100 %          T538      100 %

Reactor Vessel DP 83 2 psid PORY Discharge Temperature 113 F P2r Safety Valve Discharge Tenp (F) Rv 1039 127 _ Rv-1040 142 Rv 1041 g PCP Current (Amps) P 50A Q P 508 Q P 50C Q P 500 0 PCS Flow Q  % Pressure Level (cold) -3  % Loop Thot (F) Loop 1 B Loop 2 100 Loop Tcold (F) Loop i H Loop 2 H Tcold Wide range Loop 1 B Loop 2 J 9 Sthcooling Tenp 106 F Press 12 psi PCS Prssure WR 13 NR 13 psia Steen Canerator A Steam Generator 8 Level (WR) Q  %. (MR) Q  % (WR) Q  % (NR) Q  % Press 1 psia li psia Flow Steam 0

                                                ~

PPH Feed 0 PPH Steam 0 PPM Feed 0 PPH Note: Steam and Feed Flow X I000000 E*11 AFV Flow to A S/G From P-8A&B Q From P-8C Q AFW Flow to 8 $/G From P 8A&8 0 From P 8C ~0 Condenser Vacuun (R) Q PCP Seal'Leskoff Flow P 50A Q PPH P 508 Q PPH P-50C Q PPN P 500 Q PPH E'E$ Diesel Generator Frequency 11 0 12 60 1 C sus Voltage Q Anps 0 l 1-D BUS Voltage 2330 Anps Q  ; I C-11 Back C-11A Contairment Area Monitors (R/Hr) RIA 1805 222 RIA 1806 212 RIA 1807 222 RIA-1808 I?2 High Range Contalrunent Monitors (R/Hr) RIA 2321 .1E+04 RIA 2322 .1E+04 Contalrunent Hydrogen Concentration (%) Al 2401R 0 Al 2401L Q Main Steam Line Gasma (cpm) RIA-2324 .23E+02 RIA 2323 .25E+02 I Stack Monitors RIA 2325 .5E+03 cpn RIA-2326 22ft epm RIA232729 mr/hr l l l l

Scenario: PALEX-94 Tite: 1245+ Message No: 27 Scenario Time: 0415+ PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Control Room Personnel Simulated Plant conditions: Time jump to new plant conditions Message: A. Several days has passed since the accident. Bus 10 has been repaired; Shutdown Cooling Pump P-67B is recirculating Primary Coolant from the Containment Sump through the Shutdown Cooling Heat Exchangers. Portions of the Reactor core remain uneffectively cooled, and PCS temperature has stabilized at approximately 200*F. Radiation levels in Containment remain very high; no attempts at Containment entry have yet been made. See attached alarm and data sheets. B. The south tilt pit has been sealed with a pressure-tight enclosure and the Fuel Handling building is being ventillated using truck-mounted high efficiency filters; no further release is occurring, although detectable ground deposits in the former direction of the plume exist for many miles.

C. Most plant personnel are at or near their yearly exposure limits.

Maintenance efforts are presently focused on maximizing the reliability of Shutdown Cooling, radiation levels permitting (both Safeguards Rooms have i extremely high general area dose rates). FOR CONTROLLER USE ONLY Controller Notes: Real time CFMS and simulator data is not available. Use the attached alarm and data sheets for recovery planning. Action expected: Commence recovery planning 1 O v

FAttA vie Osts Mw 20, 1994 Miss191 # 27 (Ptg* 1) Time j.29 Scenario Time 0415+ Time Jum 30AYS Scenario Time Junp 76j5 E.9$

/^     SW Sunps      P-7A ON          P 7B 0FF           P-7C ON               SW Critical Nde Press             A 91                       B 91 psig

( CCW Pumps P 52A 0FF P 528 ON P-52C ON FPC Pums P 51A gN

\      Fire Punps    P-9A ON          P 98 0FF           P-41 0FF                                          'P-518 0FF Contairvent Cooter Recire Fans V1A ON    V2A DN      V3A ON       V4A CW                                            V1B ON        V2B ON        V38 ON      V4B ON 2

C CCV Cooter Outlet Tenp A 63 F B 63 F Containment Spray Purps P-54A 0FF P-548 OFF P 54C OFF HPSI Purps P 66A 0FF P-668 0FF LPSI Punps P 67A 0FF P 678 ON Safety iniection Suction Supply Train A Train B CV-3057 (SIRW) CLOSED CV-3029 ($1RW) CLOSED CV 3031 ($1RW) CLOSED CV-3030 (Susp) gP.EN C.~.2L EVC. S Letdown Charging intermediate Press Letdown Tenp 104 F Flow 0 gpn Letdown Line Terrp j 04 F Line Tesp gF Letdown Flow g gun Pums P-55A 0FF P 55B 0FF P 55C OFF Voluw Control Tank Tenp 69 F Pressure 2,1 psi Level M % PCP Control Bleedoff Pressure j3 psig Shutdown Cootino System SDCS from PCS (R) 209 F SDCS to PCS (R) j,80 8 F ,q Quench Tank i (V Temp 141 F Pressure 0 psig Level 9 % Palmary Coolant System Pressurl2er Pressure (R) M psie PCS Tave (R) Loop 1 (TR 0111) j$ Loop 2 (TR-0121) 200_ Pressurizer Level (R) LRC 0101A g  % LRC-01018 9  % LIA-0102A 0  % P2r Htr Airps LCC 15 g LCC 16 9 PORV PRV-10428 OPEN PRV 1043B OPEN Block Valve MOV 1042A QPEN MOV 1043A grE PCPs P 50A 0FF P-508 0FF P 50C OFF P 500 0FF Reactor Power level NI-01 .29E+02 N!-02 J8E+02 N!-03 j9E-07 N! 04 18E 07 NI-05 .23E-07 NI-06 .24E 07 NI 07 .24E b7 NI 08 .24E 07 E$ AFW System AFW Pulp P 8A 0FF P 88 0FF P 8C OFF AFW Pump Asps P-8A 9 P-8C 9 AFW Punp P 88 Steam Pressure g psig AFW Disch Press P-8A & P-88 18 P-8C 18 psi secondary System MSiv Bypass MOV-0501 CLOSED MOV 0510 CLOSED MSIV's CV 0501 CLOSED CV-0510 CLOSED MFP Suction Pressure j5 psig MFP Discharge Pressure A 15 B 15 psi Moisture separator Drain Tank Level J4 % Condenser Hotwell Level g % Atmospheric Dum Valves CLOSED Condenser Vacuun p in Hg. Heater Drain Punp Status P-10A DE P 10B OE Gland Seal Condenser Vacuun p in Hg. Condensate Pung Status P-2A 0FF P 28 0FF fl (Demand Log + Constant, Rod, or Flux /Tenp) Gross MW 9 Net MW 9 Core Exit Thermocowle Tenperature p F control Rod Position p} GP) g GP2 0 GP3 0 CP4 0 CP5(P)J, CP6(A) 0,, GP7(B) 0 Stuck Rods NONE #0 ( m,

0:t2 May 20. 1994 Mtssage # jZ (Ptg3 2) Time 1345, $ctnario Time 0415+ Time Junp 30AYS Scenario Time Junp Z615,5 E*11 T 81 Level 90 1 T 939 Level 99 % Condensate Storage Tank Level T 2 g6 % g Instrument Air Pressure 95, psig

~ Contairment Building Pressure pd psig Dome Tenperature 159 F Humidity 109 %

S/G A Compartment Tenperature M1 F Hunidity 190 % S/G B Conpartment Tenperature 145, 5 F Hunidity 100 % SIRW Tank Level 2,  % WR Contairsent Pressure (R) 15, psia Contairment Surp Level 591 % Contalrment Water Level (R) M% St Tank Level (%) A 41 8 41 C 41 D 41 SI fank Pressure (psig) A 231 B 231 C 231 0 227 PANEL K 13 SIAS Alarm NJQ Containment High Pressure Alarm @ Contairment High Radiation Alarm ,Y, E S E*1$ Concentrated Boric Acid Tank Levels T53A 49  % T538 0  % Reactor Vessel DP 8.3 psid PORY Olscharge Temperature Par Safety Valve Discharge Tenp (F) MF RV 1039 128 RV-1040 143 RV 1041 17,g PCP Current (Aaps) P 50A Q P-508 9 P-50C 9 P-500 g PCS Flow Q  % Pressure Level (cold) 19 % Loop Thot (F) Loop 1 292 Loop 2 193 Loop Teold (F) Loop 1 151 Loop 2 1ZI Tcold Wide range Loop 1 ,1M Loop 2 161 Subcooling Tewp 51 F Press 22 psi PCS Prsture WR 3 NR 13 psia Steam Generator A Steam Generator B Level (WR) Q  % (NR) Q  % (WR) Q  % (NR) g  % Press 1 psia H psia Flow Steam 0

                                          ~

PPH Feed 0 PPH Steam 0 PPH Feed 0

                                                                                                               ~

PPH Note Steam and Feed Flow X I000000 v a AFW Flow to A $/G From P-8AAB Q Frcm P-8C 9 AFW Flow to B S/G From P-8A&B Q From P-8C 9 Condenser Vacuum (R) Q PCP Seat Leakoff Flow P 50A 9 PPH P-508 9 PPH P-50C 9 PPH P 500 Q PPH E2t Diesel Generator Fregaency 11 9 1-2 9 1 C BUS Voltage 245! Aaps 2_66_ 1 0 BUS Voltage 2449 Anps 345 C 11 Back C 11A Centairment Area Monitors (R/lfe) RIA 1805 ??? RIA 1806 ??? RIA 1807 221 RIA-1808 121 High Range Containment Monitors (R/Mr) RIA 2321 .86+03 RIA 2322 .8E+03 Contairment Hydrogen Concentration (%) Al 2401R 9 Al 2401L 9 Main Stean Line Gasma (cpu) RIA 2324 .23E+02 RIA 2323 .25E+02 Stack Monitors alA 2325 .5E+03 cpn RIA 2326 21? cpn RIA 2327 1 mr/hr C\ v

PALEX-94 TIME: h E MESSAGE Not O SCENARIO TIME: ON8 ANNUNCIATOR DISPLAYS K-07 en 1 ***e , e e 2 **** 3 **** e

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O  ; I l I CFMS OPERATIONS DATA O 1 O

1 o o o 1 SHAVPALI TSC STATUS PAGE PALEX 94 i + Time 0800 Scenario Time -0030 Message # 1 Time Jump 140 Scenario Time Jump - C-13 C-12 , PCP Current (Amps) Condensate Storage Tank Level T-2 86  % P-50A 0 P-50B 0  ! Instrument Air Pressure YB psig P-50C U P-500 U , (15) Containment Building Pressure U~ psig (6) PCS Flow -

                                                                                                     ~

(16) S/G A' Compartment Temperature E0 F S/G A COMPARTMENT Humidity 55  % (3) Thot (F) Loop 1 101 F loop 2 TUU F ! (16) S/G B Compartment Temperature H5 F (2) Tcold (F) Loop 1A S/G B Humidity 55  % DT F toop 2A 9T F (16) Dome Temperature TU3 F Loop IB 9T F (11) SIRW Tank Level BT % loop 2B 9T F (15) WR Containment Pressure (R) IT psia (5) Subcooling IU4 F 12 PSIA (14) Containment Sump Level 585 % (7) PCS WR Pressure (R) IT PSIA-(14) Containment Water Level (R) (22) SI Tank Level (%)

                                         -U%                           (7) PCS NR Pressure (R) T3           PSIA A 41        B 41      C 41 (30) S/G A LEVEL WR          F         %

' ~~ 0 41~~- (30) S/G A LEVEL (R) U  % SI TanEPressure7psig) (30) S/G A PRESS T psia-A 236 B 236 C 236 0 232 S/G A STM FLW (R) U X10**6 PPH (21) SIAS ATarm NO

                                          -~

S/G A FD FLW (R) U X10**6 PPH (30) S/G B LEVEL WR U  % ! C-12 (30) S/G B LEVEL (R) U  % , (30) S/G B PRESS T4 psia Concentrated Boric Acid Tank Levels U~ X10**6 PPH T53A 100  % S/G B STM FLW (R) S/G B FD FLW (R) U X10**6 PPH i T538 165  % i Reactor Vessel DP BT psid PANEL K-13 (12) PORY Discharge Temperature III F (13) Pzr Safety Valve Discharge Temp (F) (20) CONTAINMENT HIGH PRESS RV-1039 125 F N0 4

'             RV-1040                    T45      F                                               -

RV-1041 175 'F (20) Containment High Radiation Ng i

Q ,' O SHAVPAL1 TSC STATUS PAGE PALEX 94 Time 0800 Scenario Time -0030 Message # 1 141 Time Jump Scenario Time Jump C-01 C-04 MFP Suction Pressure 15 psig (32) D/G Freq 1-1 0 1-2 0 MFP A Discharge Pressure 15 psig (32) 1-C BUS VOLTS 2431 Amps 513 MFP B Discharge Pressure 15 psig (32) 1-D BUS VOLTS 2471 Amps 149 AFW Pump P-8C Amperes O AMPS AFW Discharge Pressure P-8C 18 psig C-11 BACK C-11A AFW Pump P-8A Amperes O AMPS AFW Pump P-8B Steam Pressure o psig (17) Containment Area Monitors AFW Discharge Pressure P-8A & P-8B 18 psig RIA-1805 .025 R/Hr Moisture SEP Drain Tank Level 26  % RIA-1806 .015 R/Hr Condensor Hotwell Level 71  % RIA-1807 .02 R/Hr Condensor Vacuum 0 in Hg. RIA-1808 .015 R/Hr Gland Seal Condensor Vacuum 14.2 in Hg. (17) High Range Containment Monitors Atmospheric Dump Valves CLOSED RIA-2321 .1E+01 R/Hr AFW Pump P-8A OFF P-8B OFF P-8C OFF RIA-2322 .1E+01 R/Hr Heater Drain Pump P-10A OFF P-10B OFF (19) Containment Hydrogen Concentration Condensate Pump P-2A OFF P-2B OFF AI-2401R 0  % AI-2401L 0  % C-11 (30) Main Steam Line Gamma RIA-2324 .23E+02 CPM (31) AFW FLOW TO SGA RIA-2323 .25E+02 CPM FROM P8A, B0 From P-8C 0 gpm (31) AFW FLOW TO SGB EQUIPMENT STATUS: FROM P-8A&B 0 From P-8C 0 gpm Condensor Vacuum (R) 0 IN HG. 1. SIGNIFICANT EQUIP OUTAGES PCP A Leak-off Flow (R) 0 (INOPERABLE EQUIPMENT) PCP B Leak-off Flow (R) 0 2. SURVEILLANCE DUE/ PROGRESS PCP C Leak-off Flow (R) 0 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off Flow (R) 0 OR OUTAGES

(- O O L) SHAVPAll TSC STATUS PAGE PALEX 94 Time 0800 Scenario Time -0030 Message # 1 - 142 Time Jump Scenario Time Jump C-08 C-02 SW Pumps P-7A STBY P-78 ON P-7C ON (10) VCT Temp 69 F CCW Pumps P-52A D F P-528 5TBY P-52C UN- (10) VCT Pressure 2T psi FPC Pumps P-51A UH_ P-518 UTF- (10) VCT Level 54  % PCP Control Bleedoff Pressure II psig CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow D- gpm (26) Charging Flow U gpm VIA 0FF V2A ON V3A 0FF V4A ON (9) Quench Tank Temp Tol F VlB DTF V2B UR V3B DTF V4B UN (9) Quench TANK Pressure D- psig (9) Quench TANK Level E3  % C-03 (7) Pressurizer Pressure (R) T3 psia (8) PZR Level (R) LT0102A 3  % (23) HPSI Pumps P-66A 0FF P-66B 0FF LT0103 ~3.1 % (25) LPSI Pumps P-67A UTF P-678 DF - (12) PORV PRV-1042A CLOSED 1043B LT05ED (18) Containment Spray Pumps (12) BLOCK MOV-1042A OPEN 1043A OPEN P-54A 0FF P-54B 0FF P-54C OFF CHARGING PUMPS (27) HPSIA, LPSIA SPRAY A SUCTION P55A 0FF P55B 0FF P55C OFF CV-3057 (SIRWT) CV-3030 (Sump) (6) PCPS P50A UFF P50B UFF P50C DFF P500 0FF CLOSED CLOSED PZR HTR AMPS LC15 0 LCC 16 0 (1) PCS TAVE (R) LOOPI-(TR-Olll) V6 F LOOP 2 (TR-0121) 95 F C-02 (25) REACTOR POWER LEVEL nil .20E+02 cps NI3 .98E-08  % NI7 .12E-07 % Intermediate Press Letdown Temp 104 F NI2 .20E+02 cps NI4 .96E-08  % NI8 .12E-07 % Charging Line Temperature BU- F NI-05 .12E-07  % NI-09 Letdown Line Temp TU4 F NI-06 .12E-07  % NI-10 SDCS from PCS (R) TUU F SDCS to PCS (R) 9T F PIP (DEMAND LOG + CONSTANT 3 00, OR FLUX / TEMP) Gross MW 0 Net MW !3 (28) Control Rod PositIHn l GPl 0 GP2 0 GP3 0 GP4 0-GP6(A) U GP7(B) U Stuck Rids NONE < optional ># 0 Core Exit Temp U F l

O O O

  .SHAVPALI                                          TSC STATUS PAGE                                        PALEX'94 t-Time 0835                 Scenario Time 0005           Message # 3                  140 Time Jump Scenario Time Jump C-13                                                      C-12 i

PCP Current (Amps) Condensate Storage Tank Level T-2 86  % P-50A 0 P-50B 0 Instrument Air Pressure 56 psig P-50C U P-500 U (15) Containment Building Pressure F psig (6) PCS Flow - (16) S/G A Compartment Temperature B3 F (3) Thot (F) Loop 1 100 F S/G A COMPARTMENT Humidity ET  % toop 2 TUU F (16) S/G B Compartment-Temperature BT F (2) Tcold (F) Loop 1A 9F F S/G B Humidity ET  % Loop 2A 9T F (16) Dome Temperature 133 F Loop IB- UT F I (11) SIRW Tank Level- BT  % Loop 2B UT F (15) WR Containment Pressure (R) T5 psia (5) Subcooling IDS F 12 PSIA (14) Containment Sump Level 555 % (7) PCS WR Pressure (R) T3- PSIA-(14) Containment Water Level (R) D- %

                                           -                         (7) PCS NR Pressure (R) TI PSIA (22) SI Tank Level (%)                                          (30) S/G A LEVEL WR           U- %

A 41 B 41 C 41 U

                                        -       D 41-               (30) S/G A LEVEL (R)               %

i SI Tanli Pressure-{psig) (30) S/G A PRESS T psia

              -A 236     B 236      C 236       D 231                                             D    X10**6 PPH S/G A STM FLW (R) l   (21) SIAS ATarm                         NO
                                           -                              S/G A FD FLW (R)        D    X10**6 PPH i

(30) S/G B LEVEL WR U  % C-12 (30) S/G B LEVEL (R) U  % (30) S/G B PRESS- T4 psia Concentrated Boric Acid Tank Levels S/G B STM FLW (R) U- X10**6 PPH T53A 100  % U X10**6 PPH S/G B FD FLW (R) T53B TUU  % , Reactor Vessel DP B1 psid PANEL K-13 (12) PORV Discharge Temperature IT2 .F i (13) Pzr Safety Valve Discharge Temp (F) (20) CONTAINMENT HIGH PRESS RV-1039 126 F NO RV-1040 T4T F RV-1041 176 F (20) Containment High Radiation NQ  ;

m m m SHAVPAL1 TSC STATUS PAGE PALEX 94 Time 0835 Scenario Time 0005 ' "tsage # 3 141 Time Jump Scenario Time Jump C-01 C-04 MFP Suction Pressure 15 psig (32) D/G Freq 1-1 0 1-2 60 MFP A Discharge Pressure 15 psig (32) 1-C BUS VOLTS O Amps 0 MFP B Discharge Pressure 15 psig (32) 1-D BUS VOLTS O Amps 0 AFW Pump P-8C Amperes O AMPS AFW Discharge Pressure P-8C 18 psig C-11 BACK C-11A AFW Pump P-8A Amperes O AMPS AFW Pump P-8B Steam Pressure O psig (17) Containment Area Monitors AFW Discharge Pressure P-8A & P-8B 18 psig RIA-1805 .025 R/Hr Moisture SEP Drain Tank Level 26  % RIA-1806 .015 R/Hr Condensor Hotwell Level 0  % RIA-1807 .02 R/Hr Condensor Vacuum o in Hg. RIA-1808 .015 R/Hr Gland Seal Condensor Vacuum 14.2 in Hg. (17) High Range Containment Monitors Atmospheric Dump Valves CLOSED RIA-2321 .1E+01 R/Hr AFW Pump P-8A OFF P-8B OFF P-8C OFF RIA-2322 .1E+01 R/Hr Heater Drain Pump P-10A OFF P-10B OFF (19) Containment Hydrogen Concentration Condensate Pump P-2A OFF P-2B OFF AI-2401R 0  % AI-2401L 0  % C-11 (30) Main Steam Line Gamma RIA-2324 .23E+02 CPM (31) AFW FLOW TO SGA RIA-2323 .25E+02 CPM FROM P8A, B0 From P-8C 0 gpm (31) AFW FLOW TO SGB EQUIPMENT STATUS: FROM P-8A&B 0 From P-8C 0 gpm Condensor Vacuum (R) O IN HG. 1. SIGNIFICANT EQUIP OUTAGES PCP A Leak-off Flow (R) 0 (INOPERABLE EQUIPMENT) PCP B Leak-off Flow (R) 0 2. SURVEILLANCE DUE/ PROGRESS PCP C Leak-off Flow (R) O 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off Flow (R) O OR OUTAGES

g

    !                                                     t
                                                                                                                       )

SHAVPAll TSC STATUS PAGE PALEX 94 Time 0835 Scenario Time 0005 Message # 3 142 Time Jump Scenario Time Jump C-08 C-02 SW Pumps P-7A 0FF P-7B 0FF P-7C OFF (10) VCT Temp 69 F CCW Pumps P-52A UFF P-52B DTF P-52C DTF (10) VCT Pressure H psi FPC Pumps P-51A UFF P-51B UFF (10) VCT Level 54  % PCP Control Bleedoff Pressure II psig CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow 6~ gpm (26) Charging Flow U gpm VIA 0FF V2A 0FF V3A 0FF V4A 0FF (9) Quench Tank Temp Tol F VIB UFF V2B DFF V3B DFF V48 UFF (9) Quench TANK Pressure D- psig (9) Quench TANK Level B3  % C-03 (7) Pressurizer Pressure (R) TI psia (8) PZR Level (R) LT0102A 3  % (23) HPSI Pumps P-66A 0FF P-66B 0FF LT0103 U.0 % (25) LPSI Pumps P-67A DFF P-67B UFF (12) PORV PRV-1042A CLOSED 1043B TIU5ED (18) Containment Spray Pumps (12) BLOCK MOV-1042A OPEN 1043A OPEN P-54A 0FF P-548 0FF P-54C OFF CHARGING PUMPS (27) HPSIA, LPSIA 3 PRAY A SUCTION P55A 0FF P558 0FF P55C 0FF CV-3057 (SIRWT) CV-3030 (Sump) (6) PCPS P50A UFF P50B UTF P50C DFF P500 0FF CLOSED CLOSED PZR HTR AMPS LC15 0 LCC 16 U~~ (1) PCS TAVE (R) LOOPl-(TR-Olll) 96 F LOOP 2 (TR-0121) 95 F C-02 (25) REACTOR POWER LEVEL nil .20E+02 cps NI3 .98E-08  % NI7. 12E-07 % Intermediate Press Letdown Temp 104 F NI2 .20E+02 cps NI4 .96E-08  % NI8 .12E-07 % Charging Line Temperature YT- F NI-05 .12E-07  % NI-09 Letdown Line Temp T54 F NI-06 .12E-07  % NI-10 SDCS from PCS (R) 70- F SDCS to PCS (R) 55 F PIP (DEMAND LOG + CONSTANT'- R00, OR FLUX / TEMP) Gross HW 0 Net MW D (28) Control Rod Position GPl O GP2 0 GP3 0- GP4 0-GP6(A) U GP7(B) U Stuck Rods NONE < optional ># 0 Core Exit Temp _U F

O O O  ; SHAVPALI TSC STATUS PAGE PALEX 94 , Time ~0845 Scenaria Time 0015 Message # 5 140 Time Jump Scenario Time Jump l C-13 C-12 PCP Current (Amps) Condensate Storage Tank Level T-2 86  % P-50A 0 P-50B 0 t Instrument Air Pressure F psig P-50C U P-500 D  : (15) Containment Building Pressure U _psig (6) PCS Flow - (16) S/G A Compartment Temperature B6 F (3) Thot (F) Loop 1 100 F " i S/G A COMPARTMENT Humidity E  % Loop 2 TUU F (16) S/G B Compartment Temperature B7 F (2) Tcold (F) Loop 1A DT- F S/G B Humidity E % Loop 2A 9T F < (16) Dome Temperature TU2 F Loop 1B 9T F (11) SIRW Tank Level BT- % Loop 28 YI F (15) WR Containment Pressure (R) T5 psia (5) Subcooling TU6 F 12 PSIA , (14) Containment Sump Level 556 % (7) PCS WR Pressure (R) IT PSIF i (14) Containment Water Level (R) D- %

                                             -                                          (7) PCS NR Pressure (R) TI                      PSIA (22) SI Tank Level (%)                                                            (30) S/G A LEVEL WR                        U-      %                                  <

! A 41 B 41 C 41-- D 41- (30) S/G A LEVEL (R) U  % S1 Tanli Pressure-(psig) (30) S/G A PRESS T psia A 238 B 238 C 238 D 233 S/G A STM FLW (R) U X10**6 PPH (21) SIAS ATirm NO

                                             -                                                  S/G A FD FLW (R)                U       X10**6 PPH (30) S/G B LEVEL WR                        U       %

C-12 (30) S/G B LEVEL (R) U  % i (30) S/G B PRESS T4 psia Concentrated Boric Acid Tank Levels S/G B STM FLW (R) F X10**6 PPH , T53A 100  % S/G B FD FLW (R) U X10**6 PPH T53B' TUU  % ! Reactor Vessel DP B3 psid PANEL K-13 (12) PORY Discharge Temperature ITZ F (13) Pzr Safety Valve Discharge Temp (F) (20) CONTAINMENT HIGH PRESS ! RV-1039 126 F N0 i RV-1040 T4T F l RV-1041 T75 F (20) Containment High Radiation Np i

O O O - SHAVPAL1 TSC STATUS PAGE PALEX 94 Time 0845 Scenario Time 0015 Message # 5 141 j Time Jump Scenario Time Jump i~ C-01 C-04 i MFP Suction Pressure 15 psig (32) D/G Freq 1-1 0 1-2 60 i MFP A Discharge Pressure 15 psig (32) 1-C BUS VOLTS O Amps 0 MFP B Discharge Pressure 15 psig (32) 1-D BUS VOLTS O Amps 0 AFW Pump P-8C Amperes O AMPS AFW Discharge Pressure P-8C 18 psig C-11 BACK C-11A AFW Pump P-8A Amperes O AMPS AFW Pump P-8B Steam Pressure O psig (17) Containment Area Monitors AFW Discharge Pressure P-8A & P-8B 18 psig RIA-1805 .025 R/Hr l Moisture SEP Drain Tank Level 14  % RIA-1806 .015 R/Hr. Condensor Hotwell Level 0  % RIA-1807 .02 R/Hr Condensor Vacuum o in Hg. RIA-1808 .015 R/Hr Gland Seal Condensor Vacuum 14.2 in Hg. (17) High Range Containment Monitors Atmospheric Dump Valves CLOSED RIA-2321 .1E+01 R/Hr l AFW Pump P-8A OFF P-8B OFF P-8C OFF RIA-2322 .1E+01 R/Hr i Heater Drain Pump P-10A OFF P-10B OFF (19) Containment Hydrogen Concentration Condensate Pump P-2A OFF P-2B OFF AI-2401R 0  % , AI-2401L 0  % }' C-11 (30) Main Steam Line Gamma ' RIA-2324 .23E+02 CPM (31) AFW FLOW TO SGA RIA-2323 .25E+02 CPM FROM P8A, B0 From P-8C 0 gpm (31) AFW FLOW TO SGB ! EQUIPMENT STATUS: FROM P-8A&B 0 From P-8C 0 gpn i Condensor Vacuum (R) 0 IN HG. 1. SIGNIFICANT EQUIP OUTAGES { PCP A Leak-off Flow (R) 0 (INOPERABLE EQUIPMENT) ! PCP B Leak-off Flow (R) 0 2. SURVEILLANCE DUE/ PROGRESS l PCP C Leak-off Flow (R) 0 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off Flow (R) 0 OR OUTAGES 4 i

O O O SHAVPAtl TSC STATUS PAGE PALEX 94 Time 0845 Scenario Time 0015 Message # 5-142 Time Jump Scenario Time Jump C-08 C-02 SW Pumps P-7A 0FF P-7B 0FF P-7C OFF (10) VCT Temp 69 F CCW Pumps P-52A UFF P-52B UFF P-52C UFF (10) VCT Pressure IT psi FPC Pumps P-51A UFF P-51B UFF (10) VCT Level 54  % PCP Control Bleedoff Pressure U psig CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow U- gpm (26) Charging Flow U gpm VIA 0FF V2A 0FF V3A 0FF V4A 0FF (9) Quench Tank Temp T01 F VlB DFF V2B DTF V3B UFF V4B DTF (9) Quench TANK Pressure O psig (9) Quench TANK Level 53  % C-03 (7) Pressurizer Pressure (R) TI psia (8) PZR Level (R) LT0102A 7  % (23) HPSI Pumps P-66A 0FF P-66B 0FF LT0103 ~2.9 % (25) LPSI Pumps P-67A UFF P-678 DFF (12) PORV PRV-1042A CLOSED 1043B I.TUIED (18) Containment Spray Pumps (12) BLOCK MOV-1042A OPEN 1043A OPEN P-54A 0FF P-548 0FF P-54C 0FF CHARGING PUMPS (27) HPSIA, LPSIA 5 PRAY A SUCTION P55A 0FF P55B 0FF P55C 0FF CV-3057 (SIRWT) CV-3030 (Sump) (6) PCPS P50A UFF P508 UFF P50C DTF P500 0FF CLOSED CLOSED PZR HTR AMPS LC15 0 LCC 16 D-~ (1) PCS TAVE (R) LOOPI-(TR-0111) US F LOOP 2 (TR-0121) Y5 F C-02 (25) REACTOR POWER LEVEL nil .20E+02 cps NI3 .98E-08  % NI7. 12E-07 % Intermediate Press Letdown Temp 104 F NI2 .20E+02 cps NI4 .96E-08  % NI8 .12E-07 % Charging Line Temperature WF NI-05 .12E-07  % NI-09 Letdown Line Temp TU4 F NI-06 .12E-07  % NI-10 SDCS from PCS (R) F F SDCS to PCS (R) 76 F PIP (DEMAND LOG + CONSTANT ~~ ROD, OR FLUX / TEMP) Gross MW 0 Net MW U (28) Control Rod PositTon GPl O GP2 0 GP3 0-GP4 0 - GP6(A) U GP7(B) U i Stuck Rods NONE < optional ># 0 l Core Exit Temp U F I

O O O ' SHAVPALI TSC STATUS PAGE PALEX 94 Time 0853 Scenario Time 0023 Message # 7-140 Time Jump Scenario Time Jump C-13 C-12 ! PCP Current (Amps) Condensate Storage Tank Level T-2 86  % P-50A 0 P-508 0 Instrument Air Pressure BT psig P-50C D P-500 U-(15) Containment Building Pressure U- psig (6) PCS Flow - (16) S/G A Compartment Temperature E3 F (3) That (F) Loop 1 100 F , S/G A COMPARTMENT Humidity 55  % toop 2 TUU F !' (16) S/G B Compartment Temperature BT F (2) Tcold (F) Loop 1A DI- F S/G B Humidity 50  % Loop 2A UT F

(16) Dome Temperature TU3 F Loop IB UI F (11) SIRW Tank Level HT  % Loop 2B UI F

(15) WR Containment Pressure (R) T5 psia (5) Subcooling TU6 F 12 PSIA (14) Containment Sump Level 5H8 % (7) PCS WR Pressure (R) T3- PSIA-(14) Containment Water Level (R) U%

                                                                                         -                               (7) PCS NR Pressure (R) T3 PSIA (22) SI Tank Level (%)                                                  (30) S/G A LEVEL WR          U- %

A 41 B 41 C 41 D 41

                                                                                                  --                    (30) S/G A LEVEL (R)         U    %                  .

SI Tanli Pressure 7psig) (30) S/G A PRESS T psia A 237 8 237 C 237 0 233 S/G A STM FLW (R) U X10**6 PPH i (21) SIAS ATarm - NO S/G A FD FLW (R) U X10**6 PPH (30) S/G B LEVEL WR U  % 3 C-12 (30) S/G B LEVEL (R) U  %

;                                                                                                                       (30) S/G B PRESS             T4    psia Concentrated Boric Acid Tank Levels                                     S/G B STM FLW (R)      U-    X10**6 PPH T53A                           100    %                           S/G B FD FLW (R)       U    X10**6 PPH T53B                         TUU      %

Reactor Vessel DP B3 psid PANEL K-13 (12) PORY Discharge Temperature TIY F (13) Pzr Safety Valve Discharge Temp (F) (20) CONTAINMENT HIGH PRESS RV-1039 126 F NO TTI RV-1040 F i

RV-1041 T76 F (20) Containment High Radiation ,

NO r

O O O SHAVPAL1 TSC STATUS PAGE PALEX 94 Time 0853 Scenario Time 0023 Message # 7 141 Time Jump Scenario Time Jump C-01 C-04 MFP Suction Pressure 15 psig (32) D/G Freq 1-1 0 1-2 60 MFP A Discharge Pressure 15 psig MFP B Discharge Pressure (32) 1-C BUS VOLTS 0 Amps 0 15 psig (32) 1-D BUS VOLTS 2332 Amps 0 AFW Pump P-8C Amperes O AMPS AFW Discharge Pressure P-8C 18 psig C-11 BACK C-11A AFW Pump P-8A Amperes O AMPS AFW Pump P-8B Steam Pressure O psig (17) Containment Area Monitors AFW Discharge Pressure P-8A & P-8B 18 psig RIA-1805 Moisture SEP Drain Tank Level 14

                                                                                                                                 .025        R/Hr
                                                    %                RIA-1806                                                    .015        R/Hr Condensor Hotwell Level                      81   %                RIA-1807                                                    .02         R/Hr Condensor Vacuum                             o       in Hg.        RIA-1808 Gland Seal Condensor Vacuum                  14.2
                                                                                                                                 .015        R/Hr in Hg.  (17) High Range Containment Monitors Atmospheric Dump Valves                      CLOSED                RIA-2321 AFW Pump      P-8A OFF     P-8B OFF    P-8C OFF
                                                                                                                                 .1E+01      R/Hr RIA-2322                                                    .1E+01      R/Hr Heater Drain Pump        P-10A OFF    P-10B OFF              (19) Containment Hydrogen Concentration Condensate Pump            P-2A OFF    P-2B OFF                    AI-2401R                                                    0        %

AI-2401L 0  % C-11 (30) Main Steam Line Gamma RIA-2324 .23E+02 CPM (31) AFW FLOW TO SGA RIA-2323 .2SE+02 CPM FROM P8A, BO From P-8C 0 gpm (31) AFW FLOW TO SGB EQUIPMENT STATUS: FROM P-8A&B 0 From P-8C 0 gpm Condensor Vacuum (R) 0 IN HG. 1. SIGNIFICANT EQUIP OUTAGES PCP A Leak-off Flow (R) 0 (INOPERABLE EQUIPMENT) PCP B Leak-off Flow (R) 0 2. SURVEILLANCE DUE/ PROGRESS PCP C Leak-off Flow (R) 0 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off Flow (R) 0 OR OUTAGES

g g

                                            'd b                                                       d SHAVPAll                                          TSC      STATUS PAGE PALEX 94 Time 0853                    Scenario Time 0023              Message # 7-142 Time Jump                     Scenario Time Jump C-08                                                              C-02 SW Pumps         P-7A ON       P-7B 0FF     P-7C ON              (10) VCT Temp                                  69     F CCW Pumps P-52A UFF          P-528 UT      P-52C UFF             (10) VCT Pressure                              IT     psi FPC Pumps P-51A DFF          P-518 UFF                           (10) VCT Level                                 54     %

PCP Control Bleedoff Pressure II psig CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow U- gpm (26) Charging Flow U gpm VIA ON V2A ON V3A ON V4A 0FF (9) Quench Tank Temp Tol F VlB DFF V2B DFF V3B DFF V4B UFF (9) Quench TANK Pressure U-- psig (9) Quench TANK Level 53  % C-03 (7) Pressurizer Pressure (R) II psia (8) PZR Level (R) LT0102A U  % (23) HPSI Pumps P-66A 0FF P-668 0FF LT0103 7  % (25) LPSI Pumps P-67A DFF P-67B UFF (12) PORY PRV-1042A CLOSED 10438 LTOSED (18) Containment Spray Pumps (12) BLOCK MOV-1042A OPEN 1043A OPEN P-54A 0FF P-54B 0FF P-54C OFF CHARGING PUMPS (27) HPSIA, LPSIA~ 5 PRAY A SUCTION P55A 0FF P558 0FF P55C 0FF CV-3057 (SIRWT) CV-3030 (Sump) (6) PCPS P50A UFF P508 UFF P50C DTF P500 0FF CLOSED CLOSED PZR HTR AMPS LC15 0 LCC 16 0 (1) PCS TAVE (R) LOOPI-(TR-Olll) 95 F LOOP 2 (TR-0121) 95 F C-02 (25) REACTOR POWER LEVEL HIl .20E+02 cps NI3 .98E-08  % NI7. 12E-07 % Intermediate Press Letdown Temp 104 F NI2 .20E+02 cps NI4 .96E-08  % NI8 .12E-07 % Charging Line Temperature 9T F NI-05 .12E-07  % NI-09 Letdown Line Temp TU4 F NI-06 .12E-07  % NI-10 SDCS from PCS (R) TUU F SDCS to PCS (R) -9T F PIP (DEMAND LOG + CONSTANT' ROD, OR FLUX / TEMP) Gross MW 0 Net MW U (28) Control Rod PositTon GPl 0 GP2 0 GP3 0-GP4 0 GP6(A) U GP7(B) U Stuck Rods NONE < optional >f 0 Core Exit Temp U F

L O O O SHAVPALI TSC STATUS PAGE PALEX 94 Time 0900 Scenario Time 0030 Message # 9 140 4 Time Jump Scenario Time Jump C-13 C-12 PCP Current (Amps)

Condensate Storage Tank Level T-2 85  % P-50A 0 P-50B 0 1 Instrument Air Pressure M psig F-50C U P-500 5~

(15) Containment Building Pressure D- psig (6) PCS Flow ~ (16) S/G A Compartment Temperature H3 F (3) Thot (F) Loop 1 100 F S/G A COMPARTMENT Humidity 55  % toop 2 TUU F (16) S/G B Compartment Temperature M F (2) Tcold (F) Loop IA 9F F S/G B Humidity 55  % Loop 2A 9T F 4 (16) Dome Temperature TU3 F Loop 18 UT F i (11) SIRW Tank Level HF % toop 2B 9T F (15) WR Containment Pressure (R) 15 psia (5) Subcooling TU6 F 12 PSIA (14) Containment Sump Level 5H8 % (7) PCS WR Pressure (R) 13- PSIX-(14) Containment Water Level (R) 0  %

                                               -                         (7) PCS.NR Pressure-(R) II PSIA (22) 51 Tank Level (%)                                          (30) S/G A LEVEL WR          D- %

A 41 B 41 C 41 - D 41

                                                      -                 (30) S/G A LEVEL (R)         U    %

S1 TanF Pressure-{psig) (30) S/G A PRESS I psia , A 237 8 237 C 237 D 233 U X10**6 PPH S/G A STM FLW (R) (21) SIAS ATEm NO

                                               -                              S/G A FD FLW (R)       U    X10**6 PPH (30) S/G B LEVEL WR           D    %

C-12 (30) S/G B LEVEL (R) U  % (30) S/G B PRESS I4 psia Concentrated Boric Acid Tank levels S/G B STM FLW (R) F X10**6 PPH T53A 100  % U X10**6 PPH S/G B FD FLW (R) , T53B TUU  % ! Reactor Vessel DP HT psid PANEL K-13 l (12) PORY Discharge Temperature TTY F (13) Pzr Safety Valve Discharge Temp (F) (20) CONTAINMENT HIGH PRESS l RV-1039 126 F NO ! RV-1040 T4T F- ~~ RV-1041 ITE F (20) Containment High Radiation NO l i

O O O l SHAVPAL1 TSC STATUS PAGE PALEX 94 Time 0900 Scenario Time 0030 Message # 9 141 Time Jump Scenario Time Jump C-01 C-04 MFP Suction Pressure 15 psig (32) D/G Freq 1-1 0 1-2 60 MFP A Discharge Pressure 15 psig (32) 1-C BUS VOLTS 0 Amps 0 MFP B Discharge Pressure 15 psig (32) 1-D BUS VOLTS 2332 Amps 0 AFW Pump P-8C Amperes O AMPS AFW Discharge Pressure P-8C 18 psig C-11 BACK C-11A AFW Pump P-8A Amperes O AMPS AFW Pump P-8B Steam Pressure o psig (17) Containment Area Monitors AFW Discharge Pressure P-8A & P-8B 18 psig RIA-1805 .025 R/Hr Moisture SEP Drain Tank Level 14  % RIA-1806 .015 R/Hr Condensor Hotwell Level 81  % RIA-1807 .02 R/Hr Condensor vacuum 0 in Hg. RIA-1808 .015 R/Hr Gland Seal Condensor Vacuum 14.2 in Hg. (17) High Range containment Monitors Atmospheric Dump Valves CLOSED RIA-2321 .1E+01 R/Hr AFW Pump P-8A OFF P-8B OFF P-8C OFF RIA-2322 .1E+01 R/Hr Heater Drain Pump P-10A OFF P-10B OFF (19) Containment Hydrogen Concentration Condensate Pump P-2A OFF P-2B OFF AI-2401R 0  % AI-2401L 0  % C-11 (30) Main Steam Line Gamma RIA-2324 .23E+02 CPM (31) AFW FLOW TO SGA RIA-2323 .25E+02 CPM FROM P8A, B0 From P-8C 0 gpm (31) AFW FLOW TO SGB EQUIPMENT STATUS: FROM P-8A&B 0 From P-8C 0 gpm Condensor Vacuum (R) 0 IN HG. 1. SIGNIFICANT EQUIP OUTAGES PCP A Leak-off Flow (R) 0 (INOPERABLE EQUIPMENT) PCP B Leak-off Flow (R) 0 2. SURVEILLANCE DUE/ PROGRESS PCP C Leak-off Flow (R) 0 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off Flow (R) O OR OUTAGES

v L' v SHAVPAll TSC STATUS PAGE PALEX 94 Time 0900 Scenario Time 0030 Message # 9 ~ 142 Time Jump Scenario Time Jump C-08 C-02 SW Pumps P-7A ON P-7B 0FF P-7C ON (10) VCT Temp 69 F CCW Pumps P-52A DTF P-52B DN- P-52C UFF (10) VCT Pressure 2T pst FPC Pumps P-51A DTF P-51B DFF (10) VCT Level 54  % PCP Control Bleedoff Pressure U psig CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow D- gpm (26) Charging Flow D gpm VIA ON V2A ON V3A ON V4A 0FF (9) Quench Tank Temp Tol F VlB DTF V2B DTF V3B DFF V4B DFF (9) Quench TANK Pressure O psig (9) Quench TANK Level 63  % C-03 (7) Pressurizer Pressure (R) TI psia (8) PZR Level (R) LT0102A U  % (23) HPSI Pumps P-66A 0FF P-668 0FF LT0103 7 % (25) LPSI Pumps P-67A DFF P-67B UFF (12) PORV PRV-1042A CLOSED 1043B LTOSED (18) Containment Spray Pumps (12) BLOCK MOV-1042A OPEN 1043A OPEN P-54A 0FF P-54B 0FF P-54C OFF CHARGING PUMPS (27) HPSIA, LPSIA D PRAY A SUCTION P55A 0FF P558 0FF P55C OFF CV-3057 (SIRWT) CV-3030 (Sump) (6) PCPS P50A UFF P508 DTF P50C UTF P500 0FF CLOSED CLOSED PZR HTR AMPS LC15 0 LCC 16 D-'~ (1) PCS TAVE (R) LOOPI-(TR-0111) US F LOOP 2 (TR-0121) V5 F C-02 (25) REACTOR POWER LEVEL nil .20E+02 cps NI3 .98E-08  % NI7. 12E-07 % Intermediate Press Letdown Temp 104 F NI2 .20E+02 cps NI4 .96E-08  % NI8 .12E-07 % Charging Line Temperature DT F NI-05 .12E-07  % HI-09 Letdown Line Tema IU4 F NI-06 .12E-07  % NI-10 SDCS from PCS (R) IUD F SDCS to PCS (R) -9T F PIP (DEMAND LOG + CONSTANT 3 0D, OR FLUX / TEMP) Gross NW 0 Net MW U (28) Control Rod PositTon GPl 0 GP2 0 GP3 0- GP4 0-GP6(A) U GP7(B) U Stuck R ds RONE <optiona1># 0 Core Exit Temp 5 F

9 <m J SHAVPAll TSC STATUS PAGE PALEX 94 Time 0915 Scenario Time 0045 Message # 10 140 Time Jump Scenario Time Jump C-13 C-12 PCP Current (Amps) Condensate Storage Tank Level T-2 86  % P-50A 0 P-50B 0 Instrument Air Pressure M psig P-50C U P-50D D (15) Containment Building Pressure D~ psig (6) PCS Flow - (16) S/G A Compartment Temperature B3 F (3) Thot (F) Loop 1 100 F S/G A COMPARTMENT Humidity EU  % loop 2 T6U F (16) S/G B Compartment Temperature BT F (2) Tcold (F) Loop 1A 91~ F S/G B Humidity 5U  % Loop 2A M F (16) Dome Temperature TU3 F Loop 1B UI F (11) SIRW Tank Level BI % Loop 2B 9T F (15) WR Containment Pressure (R) T5 psia (5) Subcooling TU6 F 12 PSIA (14) Containment Sump Level 5H8 % (7) PCS WR Pressure (R) T3- PSIA-(14) Containment Water Level (R) D-~ %

                                         -                        (7) PCS NR Pressure (R) U PSIA (22) SI Tank Level (%)                                         (30) S/G A LEVEL WR                                F     %

A 41 B 41 C 41

                                    -        D 41-               (30) S/G A LEVEL (R)                               U     %

SI TanEPressure-{psig) (30) S/G A PRESS T psia A 237 B 237 C 237 D 233 S/G A STM FLW (R) U X10**6 PPH (21) SIAS ATarm - NO S/G A FD FLW (R) U X10**6 PPH (30) S/G B LEVEL WR U  % C-12 (30) S/G B LEVEL (R) U  % (30) S/G B PRESS T4 psia Concentrated Boric Acid Tank Levels S/G B STM FLW (R) U- X10**6 PPH T53A 100  % S/G B FD FLW (R) U X10**6 PPH T53B IDU  % Reactor Vessel DP BI psid PANEL K-13 (12) PORV Discharge Temperature III F (13) Pzr Safety Valve Discharge Temp (F) (20) CONTAINMENT HIGH PRESS RV-1039 126 F NO RV-1040 Til F RV-1041 T75 F (20) Containment High Radiation NO

y ,e

         )                                        {                                                s s'

SHAVPAL1 TSC STATUS PAGE PALEX 94 Time 0915 Scenario Time 0045 Message # 10 141 Time Jump Scenario Time Jump C-01 C-04 MFP Suction Pressure 15 psig (32) D/G Freq 1-1 0 1-2 60 MFP A Discharge Pressure 15 psig (32) 1-C BUS VOLTS O Amps 0 MFP B Discharge Pressure 15 psig (32) 1-D BUS VOLTS 2332 Amps 0 AFW Pump P-8C Amperes O AMPS AFW Discharge Pressure P-8C 18 psig C-11 BACK C-11A AFW Pump P-8A Amperes O AMPS AFW Pump P-8B Steam Pressure o psig (17) Containment Area Monitors AFW Discharge Pressure P-8A 4 P-8B 18 psig RIA-1805 Moisture SEP Drain Tank Level 14

                                                                                       .025        R/Hr
                                                    %                 RIA-1806         .015        R/Hr Condensor Hotwell Level                     81    %                 RIA-1807         .02         R/Hr Condensor Vacuum                            o        in Hg.         RIA-1808 Gland Seal Condensor Vacuum
                                                                                       .015        R/Hr 14.2     in Hg.  (17) High Range Containment Monitors Atmospheric Dump Valves                     CLOSED                  RIA-2321         .1E+01      R/Hr AFW Pump     P-8A OFF      P-8B OFF    P-8C OFF                    RIA-2322 Heater Drain Pump        P-10A OFF    P-10B OFF
                                                                                       .1E+01      R/Hr (19) Containnent Hydrogen Concentration Condensate Pump            P-2A OFF    P-2B OFF                    AI-2401R          0        %

AI-2401L 0  % C-11 (30) Main Steam Line Gamma RIA-2324 .23E+02 CPM (31) AFW FLOW TO SGA RIA-2323 .25E+02 CPM FROM P8A, B0 From P-8C 0 gpm (31) AFW FLOW TO SGB EQUIPMENT STATUS: FROM P-8A&B 0 From P-8C 0 gpm i Condensor Vacuum (R) 0 IN HG. 1. SIGNIFICANT EQUIP OUTAGES l PCP A Leak-off Flow (R) 0 (INOPERABLE EQUIPMENT) PCP B Leak-off Flow (R) 0 2. SURVEILLANCE DUE/ PROGRESS PCP C Leak-off Flow (R) 0 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off Flow (R) 0 OR OUTAGES

p. A p V V V SHAVPAll TSC STATUS PAGE PALEX 94 Time 0915 Scenario Time 0045 Message # 10 142 Time Jump Scenario Time Jump C-08 C-02 SW Pumps P-7A ON P-76 0FF P-!C ON (10) VCT Temp 69 F CCW Pumps P-52A DTF P-52B DN~ P-5U. DFF (10) VCT Pressure 7T psi FPC Pumps P-51A UFF P-518 UFF (10) VCT Level 54  %

PCP Control Bleedoff Pressure II psig CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow D- gpm (26) Charging Flow U gpm VIA ON V2A ON V3A ON V4A 0FF (9) Quench Tank Temp T01 F VIB DTF V2B UFF V3B UFF V4B DTF (9) Quench TANK Pressure o psig (9) Quench TANK Level 53  % C-03 (7) Pressurizer Pressure (R) TI psia (8) PZR Level (R) LT0102A I  % (23) HPSI Pumps P-66A 0FF P-66B 0FF LT0103 I  % (25) LPSI Pumps P-67A DFF P-67B DTF (12) PORV PRV-1042A CLOSED 1043B LTOSED (18) Containment Spray Pumps (12) BLOCK MOV-1042A OPEN 1043A OPEN P-54A 0FF P-548 0FF P-54C 0FF CHARGING PUMPS (27) HPSIA, LPSIA' 5 PRAY A SUCTION P55A 0FF P55B 0FF P55C 0FF CV-3057 (SIRWT) CV-3030 (Sump) (6) PCPS P50A UFF P508 UTF P50C DFF P50D OFF CLOSED CLOSED PZR HTR AMPS LCIS 0 LCC 16 D--~ (1) PCS TAVE (R) LOOPI-(TR-Olll) 95 F LOOP 2 (TR-0121) 95 F C-02 (25) REACTOR POWER LEVEL nil .20E+02 cps NI3 .98E-00  % NI7. 12E-07 % Intermediate Press Letdown Temp 104 F NI2 .20E+02 cps NI4 .96E-08  % NI8 .12E-07 % Charging Line Temperature 9T F NI-05 .12E-07  % NI-09 Letdown Line Temp IU4 F NI-06 .12E-07  % NI-10 SDCS from PCS (R) TOU F SDCS to PCS (R) --9T- F PIP (DEMAND LOG + CONSTANT' ROD, OR FLUX / TEMP) Gross MW 0 Net MW D (28) Control Rod PositTon GPl 0 GP2 0 GP3 0- GP4 0-GP6(A) U GP7(B) U Stuck Rods RONE < optional ># 0 Core Exit Temp _U F

    !                                                   O                                                  O V                                                   O                                                  V SHAVPAll                                         TSC STATUS   PAGE                                       PALEX 94 Time 0930                 Scenario Time 0100              Message # 12 140 Time Jump                 Scenario Time Jump C-13                                                         C-12 PCP Current (Amps)

Condensate Storage Tank Level T-2 85  % P-50A 0 P-50B 0 Instrument Air Pressure 95 psig P-50C U P-50D 5 (15) Containment Building Pressure D~ psig (6) PCS Flow - (16) S/G A Compartment Temperature El F (3) Thot (F) Loop 1 100 F S/G A COMPARTMENT Humidity M  % Loop 2 TUU F (16) S/G B Compartment Temperature El F (2) Tcold (F) Loop 1A DT- F S/G B Humidity M % Loop 2A 9T F (16) Dome Temperature TU3 F Loop IB 9T F (11) SIRW Tank Level HT- % toop 2B II F (15) WR Containment Pressure (R) T5 psia (5) Subcooling TU6 F 12 PSIA (14) Containment Sump Level 590 % (7) PCS WR Pressure (R) IT PSIA-(14) Containment Water Level (R) U- %

                                       ~                            (7) PCS NR Pressure (R) TI PSIA (22) SI Tank Level (%)                                            (30) S/G A LEVEL WR          U-   %

A 41 B 41 C 41

                                  --         0 41-                 (30) S/G A LEVEL (R)         U    %

SI TanFPressure {psig) (30) S/G A PRESS T psia A 236 B 236 C 236 D 232 S/G A STM FLW (R) U X10**6 PPH (21) SIAS ATirm NO

                                       -                                 S/G A FD FLW (R)       U    X10**6 PPH (30) S/G B LEVEL WR          D    %

C-12 (30) S/G B LEVEL (R) U  % (30) S/G B PRESS I4 psia Concentrated Boric Acid Tank Levels S/G B STM FLW (R) 5- X10**6 PPH T53A 100  % S/G B FD FLW (R) X10**6 PPH U_ T53B TUU  % Reactor Vessel DP H1 psid PANEL K-13 (12) PORV Discharge Temperature TIZ F (13) Pzr Safety Valve Discharge Temp (F) (20) CONTAINMENT HIGH PRESS RV-1039 126 F NO RV-1040 T4T F RV-1041 T76 F (20) Containment High Radiation EO

O O O SHAVPAL1 TSC STATUS PAGE PALEX 94 Time 0930 Scenario Time 0100 Message # 12 141 Time Jump Scenario Time Jump C-01 C-04 MFP Suction Pressure 15 psig (32) D/G Freq 1-1 0 1-2 60 MFP A Discharge Pressure 15 psig (32) 1-C BUS VOLTS O Amps 0 MFP B Discharge Pressure 15 psig (32) 1-D BUS VOLTS 2330 Amps 0 AFW Pump P-8C Amperes O AMPS AFW Discharge Pressure P-8C 18 psig C-11 BACK C-11A AFW Pump P-8A Amperes O AMPS AFW Pump P-8B Steam Pressure O psig (17) Containment Area Monitors AFW Discharge Pressure P-8A & P-8B 18 psig RIA-1805 .025 R/Hr Moisture SEP Drain Tank Level 14  % RIA-1806 .015 R/Hr condensor Hotwell Level 81  % RIA-1807 .02 R/Hr Condensor Vacuum 0 in Hg. RIA-1808 .015 R/Hr Gland Seal Condensor Vacuum 14.2 in Hg. (17) High Range Containment Monitors Atmospheric Dump Valves CLOSED RIA-2321 .1E+01 R/Hr AFW Pump P-8A OFF P-8B OFF P-8C OFF RIA-2322 .1E+01 R/Hr Heater Drain Pump P-10A OFF P-10B OFF (19) Containment Hydrogen Concentration Condensate Pump P-2A OFF P-2B OFF AI-2401R 0  % AI-2401L 0  % C-11 (30) Main Steam Line Gamma RIA-2324 .23E+02 CPM (31) AFW FLOW TO SGA RIA-2323 .25E+02 CPM FROM P8A, B0 From P-8C 0 gpm (31) AFW FLOW TO SGB EQUIPMENT STATUS: FROM P-8A&B 0 From P-8C 0 gpm Condensor Vacuum (R) 0 IN HG. 1. SIGNIFICANT EQUIP OUTAGES PCP A Leak-off Flow (R) 0 (INOPERABLE EQUIPMENT) PCP B Leak-off Flow (R) 0 2. SURVEILLANCE DUE/ PROGRESS PCP C Leak-off Flow (R) 0 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off Flow (R) 0 OR OUTAGES

O O O SHAVPAL1 TSC STATUS PAGE PALEX 94 Time 0930 Scenario Time 0100 Message # 12-142 Time Jump Scenario Time Jump C-08 C-02 SW Pumps P-7A ON P-78 0FF P-7C ON (10) VCT Temp 69 F CCW Pumps P-52A UFF P-52B DTI- P-52C DFF (10) VCT Pressure 2T psi FPC Pumps P-51A UFF P-518 UFF (10) VCT Level M  % PCP Control Bleedoff Pressure U psig CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow U- gpm (26) Charging Flow U gpm VIA ON V2A ON V3A ON V4A 0FF (9) Quench Tank Temp T01 F VlB DN

          -       V2B UN-      V3B DH~-    V4B UFF                (9) Quench TANK Pressure                      U- psig (9) Quench TANK Level                         33     %

C-03 (7) Pressurizer Pressure (R) TI psia (8) PZR Level (R) LT0102A 7  % (23) HPSI Pumps P-66A 0FF P-66B 0FF LT0103 7 % (25) LPSI Pumps P-67A UFF P-67B DFF (12) PORV PRV-1042A CLOSED 1043B LTOSED (18) Containment Spray Pumps (12) BLOCK L.-1042A OPEN 1043A OPEN P-54A 0FF P-548 0FF P-54C OFF CHARGING PUMPS (27) HPSIA, LPSIA-~3 PRAY A SUCTION P55A 0FF P55B 0FF P55C OFF CV-3057 (SIRWT) CV-3030 (Sump) (6) PCPS P50A DTF P50B DTF P50C UFF P50D OFF CLOSED CLOSED PZR HTR AMPS LC15 0 LCC 16 D-(1) PCS TAVE (R) LOOPl~(TR-Olll) 95 F LOOP 2 (TR-0121) 95 F C-02 (25) REACTOR POWER LEVEL nil .20E+02 cps NI3 .98E-08 % NI7 .12E-07  % Intermediate Press Letdown Temp 104 F NI2 .20E+02 cps NI4 .96E-08 % NI8 .12E-07  % l Charging Line Temperature UF F NI-05 .12E-07  % NI-09 Letdown Line Temp TU4 F NI-06 .12E-07  % NI-10 l SDCS from PCS (R) TDY F SDCS to PCS (R) VD~ F PIP ! (DEMAND LOG + CONSTANT 3 00, OR FLUX / TEMP) l Gross MW 0 ! Net MW D (28) Control Rod PositTon ! GPl 0 GP2 0 GP3 0- GP4 0 GP6(A) U GP7(B) U Stuck Rods NONE < optional ># 0 Core Exit Temp U F

O O O SHAVPAll TSC STATUS PAGE PALEX 94 Time 0945 Scenario Time 0115 Message # 13 140 Time Jump Scenario Time Jump C-13 C-12 PCP Current (Amps) Condensate Storage Tank Level T-2 86  % P-50A 0 P-50B 0 Instrument Air Pressure 95 psig P-50C U P-500 U (15) Containment Building Pressure 6- psig (6) PCS Flow - (16) S/G A Compartment Temperature 90 F (3) Thot (F) Loop 1 100 F S/G A COMPARTMENT Humidity 75  % toop 2 TDU F p (16) S/G B Compartment Temperature DT F (2) Tcold (F) Loop 1A 9T F S/G B Humidity 76  % loop 2A DT F (16) Dome Temperature T20 F Loop 1B FT F

(11) SIRW Tank Level BI % toop 2B UT F (15) WR Containment Pressure (R) T5 psia (5) Subcooling TU6 F 12 PSIA l (14) Containment Sump level 590 % (7) PCS WR Pressure (R) T3- PSIK~

i (14) Containment Water Level (R) -D-~  % (7) PCS NR Pressure (R) II PSIA (22) SI Tank Level (%) (30) S/G A LEVEL WR D-  % A 41 8 41 C 41

                                                                          -         D 41--                        (30) S/G A LEVEL (R)          U    %

i SI TanFPressure7psig) (30) S/G A PRESS I psia A 236 8 236 C 236 0 232 S/G A STM FLW (R) U X10**6 PPH (21) SIAS Alarm NO

                                                                               -                                        S/G A FD FLW (R)        U    X10**6 PPH (30) S/G B LEVEL WR           U    %

C-12 (30) S/G B LEVEL (R) U  % (30) S/G B PRESS T4 psia Concentrated Boric Acid Tank Levels S/G B STM FLW (R) U- X10**6 PPH T53A 100  % U X10**6 PPH S/G B FD FLW-(R) T538 TOU  % Reactor Vessel DP BJ psid PANEL K-13 (12) PORY Discharge Temperature TIY F i (13) Pzr Safety Valve Discharge Temp (F) (20) CONTAINMENT HIGH PRESS RV-1039 126 F N0 i RV-1040 T4T F

                                                                                                                                               -~~

RV-1041 175 F (20) Containment High Radiation NO  ! i

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

O O O  !

 ,   SHAVPAL1.                                             TSC       STATUS         PAGE                                                        l d'    PALEX 94                                                                                                                                   i i
!             Time 0945               Scenario Time 0115                             Message # 13 ~~

141 < j Time Jump Scenario Time Jump ,

- C-01 C-04 i

)  ! ] MFP Suction Pressure _ 15 psig (32) D/G Freq 1-1 0 1-2 60 j MFP- A Discharge Pressure. 15 psig (32) 1-C BUS VOLTS O Amps 0 - l' MFP B Discharge. Pressure 15 psig (32) 1-D BUS VOLTS 2330 Ampso  ! j AFW Pump P-8C Amperes O AMPS AFW Discharge Pressure'P-8C 18 psig C-11 BACK C-11A AFW Pump P-8A Amperes O AMPS AFW Pump P-8B Steam Pressure O psig (17) Containment Area Monitors AFW Discharge Pressure P-8A & P-8B 18 psig RIA-1805 .025 R/Hr Moisture SEP Drain Tank Level 14  % RIA-1806 .015 R/Hr Condensor Hotwell Level 81  % RIA-1807 .02 R/Hr i Condensor Vacuum O in Hg. RIA-1808 .015 R/Hr Gland Seal Condensor Vacuum 14.2 in Hg. (17) High Range Containment Monitors-Atmospheric Dump Valves CLOSED RIA-2321 .1E+01 R/Hr AFW Pump P-8A OFF P-8B OFF P-8C OFF RIA-2322 .1E+01 R/Hr 'i Heater Drain Pump P-10A OFF P-10B OFF (19) Containment Hydrogen Concentration Condensate Pump P-2A OFF P-2B OFF AI-2401R 0  % AI-2401L 0  % j C-11 (30) Main Steam Line Gamma RIA-2324 . 23E+02 CPM 1 (31) AFW FLOW TO SGA RIA-2323 .25E+02 CPM ! FROM P8A, BO From P-8C 0 gpm ! (31) AFW FLOW TO SGB . EQUIPMENT STATUS:. ! FROM P-8A&B 0 From P-8C 0 gpm l Condensor Vacuum (R) 0 IN HG. 1. SIGNIFICANT EQUIP OUTAGES PCP A Leak-off. Flow (R). 0 (INOPERABLE EQUIPMENT) PCP B Leak-off Flow;(R) 0 2. SURVEILLANCE DUE/ PROGRESS PCP C Leak-off Flow (R) 0 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off Flow (R) O OR OUTAGES' i } 2

7~ b SHAVPAll TSC STATUS PAGE PALEX 94 Time 0945 Scenario Time 0115 Message # 13 142 Time Jump Scenario Time Jump C-08 C-02 SW Pumps P-7A CN P-7B 0FF P-7C ON (10) VCT Temp 69 F CCW Pumps P-52A UTF P-528 DH- P-52C UFF (10) VCT Pressure H psi FPC Pumps P-51A OTF P-SIB DTF (10) VCT Level 5T  % PCP Control Bleedoff Pressure U psig CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow U- gpm (26) Charging Flow U gpm VIA ON V2A ON V3A ON V4A 0FF (9) Quench Tank Temp Tol F VlB DN V2B DH

                                                                                        -              V3B DH--    V4B DTF                 (9) Quench TANK Pressure                      U-~    psig (9) Quench TANK Level                        53      %

C-03 TI psia (7) Pressurizer Pressure (R) (8) PZR Level (R) LT0102A U  % (23) HPSI Pumps P-66A 0FF P-66B 0FF LT0103 7  % (25) LPSI Pumps P-67A DFF P-67B UTT (12) PORV PRV-1042A CLOSED 10438 LTOSED (18) Containment Spray Pumps (12) BLOCK MOV-1042A OPEN 1043A OPEN P-54A 0FF P-548 0FF P-54C 0FF CHARGING PUMPS (27) HPSIA, LPSIA D PRAY A SUCTION P55A 0FF P558 0FF P55C 0FF CV-3057 (SIRWT) CV-3030 (Sump) (6) PCPS P50A DFF P50B D7F P50C DTF P500 0FF CLOSED CLOSED PZR HTR AMPS LC15 0 LCC 16 6-~ (1) PCS TAVE (R) LOOPl (TR-Olll) US F LOOP 2 (TR-0121) 95 F C-02 (25) REACTOR POWER LEVEL nil .20E402 cps NI3 .9BE-08  % NI7.._12E-07 % Intermediate Press Letdown Temp 104 F NI2 .20E+02 cps NI4 .96E-08  % NI8 .12E-07  % Charging Line Temperature W F NI-05 .12E-07  % NI-09 Letdown Line Temp TG4 F NI-06 .12E-07  % NI-10 SDCS from PCS (R) TDY F SDCS to PCS (R) WF PIP (DEMAND LOG + CONSTANT 3 00, OR FLUX / TEMP) Gross MW 0 Net MW U (28) Control Rod Position GPl O GP2 0 GP3 0 GP4 0 - GP6(A) U GP7(B) 5 Stuck Rods NONE < optional ># 0 Core Exit Temp _U F

O O O SHAVPALI TSC STATUS PAGE PALEX 94 Time 1000 Scenario Time 0130 Message # 14

                                                                           ~-

140 Time Jump Scenario Time Jump C-13 C-12 PCP Current (Amps) Condensate Storage Tank Level T-2 86  % P-50A 0 P-508 0 Instrument Air Pressure TU4 psig P-50C U P-500 U-(15) Containment Building Pressure U 2 psig (6) PCS Flow -

(16) S/G A Compartment Temperature T96 F (3) That (F) Loop 1 99 F i S/G A COMPARTMENT Humidity EU % Loop 2 TUO F (16) S/G B Compartment Temperature 195 F (2) Tcold (F) Loop 1A 9T- F i S/G B Humidity TUU % loop 2A UT F (16) Dome Temperature YUU F Loop 1B UT F (11) SIRW Tank Level BT  % toop 2B 9T F (15) WR Containment Pressure (R) T5 psia (5) Subcooling IU6 F 12 PSIA (14) Containment Sump Level 591 % (7) PCS WR Pressure (R) TI- PSIK~

(14) Containment Water Level (R) 595 % (7) PCS NR Pressure (R) T3 PSIA (22) SI Tank Level (%) (30) S/G A LEVEL WR D~  % A 41 B 41 C 41

                                    -         D 41--               (30) S/G A LEVEL (R)           U    %

SI Tan F Pressure-{psig) (30) S/G A PRESS T psia A 232 8 232 C 232 D 228 S/G A STM FLW (R) U X10**6 PPH (21) SIAS ATirm NO

                                         --                              S/G A FD FLW (R)         U    X10**6 PPH (30) S/G B LEVEL WR            U    %

C-12 (30) S/G B LEVEL (R) U  % (30) S/G B PRESS T4 psia Concentrai.ed Boric Acid Tank Levels S/G B STM FLW (R) F X10**6 PPH

T53A 100  % S/G B FD FLW (R) U X10**6 PPH I T53B NU  %

Reactor Vessel DP BT psid PANEL K-13 (12) PORV Discharge Temperature TTI F (13) Pzr Safety Valve Discharge Temp (F) (20) CONTAINMENT HIGH PRESS RV-1039 127 F NO RV-1040 TTZ F RV-1041 T77 F (20) Containment High Radiation YES

O O O SHAVPAL1 TSC STATUS PAGE PALEX 94 Time 1000 Scenario Time 0130 Message # 14 141 Time Jump Scenario Time Jump C-01 C-04 MFP Suction Pressure 15 psig (32) D/G Freq 1-1 0 1-2 60 MFP A Discharge Pressure 15 psig (32) 1-C BUS VOLTS O Amps 0 MFP B Discharge Pressure 15 psig (32) 1-D BUS VOLTS 2330 Amps 0 AFW Pump P-8C Amperes O AMPS AFW Discharge Pressure P-8C 18 psig C-11 BACK C-11A AFW Pump P-8A Amperes O AMPS AFW Pump P-8B Steam Pressure O psig (17) Containment Area Monitors AFW Discharge Pressure P-8A & P-8B 18 psig RIA-1805  ??? R/Hr Moisture SEP Drain Tank Level 14  % RIA-1806  ??? R/Hr Condensor Hotwell Level 82  % RIA-1807  ??? R/Hr Condensor Vacuum 0 in Hg. RIA-1808  ??? R/Hr Gland Seal Condensor Vacuum 14.2 in Hg. (17) High Range Containment Monitors Atmospheric Dump Valves CLOSED RIA-2321 .1E+01 R/Hr AFW Pump P-8A OFF P-8B OFF P-8C OFF RIA-2322 .1E+01 R/Hr Heater Drain Pump P-10A OFF P-10B OFF (19) Containment Hydrogen Concentration Condensate Pump P-2A OFF P-2B OFF AI-2401R 0  % AI-2401L 0  % C-11 (30) Main Steam Line Gamma RIA-2324 .23E+02 CPM (31) AFW FLOW TO SGA RIA-2323 .25E+02 CPM FROM P8A, B0 From P-8C 0 gpm (31) AFW FLOW TO SGB EQUIPMENT STATUS: FROM P-8A&B 0 From P-8C 0 gpm Condensor Vacuum (R) 0 IN HG. 1. SIGNIFICANT EQUIP OUTAGES PCP A Leak-off Flow (R) 0 (INOPERABLE EQUIPMENT) PCP B Leak-off Flow (R) 0 2. SURVEILLANCE DUE/ PROGRESS PCP C Leak-off Flow (R) 0 3. ABNORMAL ELECTRICAL LINEUPS , PCP D Leak-off Flow (R) 0 OR OUTAGES

SHAVPALI TSC STATUS PAGE PALEX 94 Time 1000 Scenario Time 0130 Message # 14~ 142 Time Jump Scenario Time Jump , C-08 C-02 . SW Pumps P-7A ON P-7B 0FF P-7C ON (10) VCT Temp 69 F CCW Pumps P-52A UFF P-528 UN- P-52C UFF (10) VCT Pressure IT psi FPC Pumps P-51A UTF P-518 UFF (10) VCT Level 54  % PCP Control Bleedoff Pressure TI psig CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow U~ gpm 4 (26) Charging Flow U gpm , VIA ON V2A ON V3A ON V4A 0FF (9) Quench Tank Temp T01 F VlB UN- V2B UN- V3B UR-- V4B UFF (9) Quench TANK Pressure D- psig (9) Quench TANK Level 53  % i C-03 (7) Pressurizer Pressure (R) TI psia ' (8) PZR Level (R) LT0102A U  % (23) HPSI Pumps P-66A 0FF P-66B 0FF LT0103 7  % i (25) LPSI Pumps P-67A UFF P-678 UFF (12) PORV PRV-1042A CLOSED 10438 LTOSED (18) Containment Spray Pumps (12) BLOCK HOV-1042A OPEN 1043A OPEN l 4 P-54A 0FF P-54B 0FF P-54C OFF CHARGING PUMPS {27) HPSIA, LPSIA- 5 PRAY A SUCTION P55A 0FF F55B 0FF P55C OFF CV-3057 (SIRWT) CV-3030 (Sump) (6) PCPS P50A UFF .P508 UTF P50C UFF P500 0FF CLOSED CLOSED PZR HTR AMPS LC15 0 LCC 16 U - (1) PCS TAVE (R) LOOPI-(TR-Olll) 95 F LOOP 2 (TR-0121) 95 F C-02 (25) REACTOR POWER LEVEL nil .14E+03 cps NI3 .13E-06  % NI7. 14E-06 % Intermediate Press Letdown Temp 104 F NI2 .13E+03 cps NI4 .12E-06  % NI8 .15E-06 % l Charging Line Temperature TUI F NI-05 .14E-06  % NI-09 , Letdown Line Temp TUT F NI-06 .14E-06  % NI-10 SDCS from PCS (R) IUZ F

    .SDCS to PCS (R)                                                                                                           9T- F PIP (DEMAND LOG + CONSTANT 3 00, OR FLUX / TEMP) l                                                                                                                                                         Gross MW            0 Net MW             U l

(28) Control Rod Position GPl 0 GP2 0 GP3 0- GP4 0 - GP6(A) U GP7(B) U Stuck Rods NONE < optional >f 0 Core Exit Temp U_ F 3

O O O SHAVPAll TSC STATUS PAGE PALEX 94 Time 1015 Scenario Time 0145 Message # 15 140 Time Jump Scenario Time Jump C-13 C-12 PCP Current (Amps) Condensate Storage Tank Level T-2 86  % P-50A 0 P-508 0 Instrument Air Pressure 104 psig P-50C U P-50D D-(15) Containment Building Pressure T 2 psig (6) PCS Flow - (16) S/G A Compartment Temperature T95 F (3) That (F) Loop 1 99 F S/G A COMPARTMENT Humidity TUU % Loop 2 T60 F (16) S/G B Compartment Temperature 195 F (2) Tcold (F) Loop 1A DI~ F S/G B Humidity TUU % Loop 2A DI F (16) Dome Temperature IUU F Loop IB UT F (11) SIRW Tank Level BT  % Loop 2B 9T F (15) WR Containment Pressure (R) 17 psia (5) Subcooling IU6 F 12 PSIA (14) Containment Sump Level 591 % (7) PCS WR Pressure (R) 13- PSIX-(14) Containment Water Level (R) 595 % (7) PCS NR Pressure (R) II PSIA (22) SI Tank Level (%) (30) S/G A LEVEL WR D-  % A 41 8 41 C 41

                                 --        0 41-               (30) S/G A LEVEL (R)          U   %

SI TanE Pressure-{psig) (30) S/G A PRESS T psia A 232 B 232 C 232 D 228 U X10**6 PPH S/G A SIM FLW (R) (21) SIAS ATirm NO

                                      ~~                             S/G A FD FLW (R)        U   X10**6 PPH (30) S/G B LEVEL WR           U   %

C-12 U (30) S/G B LEVEL (R)  % (30) S/G B PRESS T4 psia Concentrated Boric Acid Tank Levels S/G B STM FLW (R) D- X10**6 PPH T53A 100  % U X10**6 PPH T53B S/G B FD FLW (R) IUU  % Reactor Vessel DP B3 psid PANEL K-13 (12) PORV Discharge Temperature III F (13) Pzr Safety Valve Discharge Temp (F) (20) CONTAINMENT HIGH PRESS RV-1039 127 F YES RV-1040 ITZ F RV-1041 177 F (20) Containment High Radiation YES

O O O SHAVPAL1 TSC STATUS PAGE PALEX 94 Time 1015 Scenario Time 0145 Message # 15

                                                                                                                         ~~

141 Time Jump Scenario Time Jump C-01 C-04 MFP Suction Pressure 15 psig (32) D/G Freq 1-1 0 1-2 60 MFP A Discharge Pressure 15 psig (32) 1-C BUS VOLTS 0 Amps 0 MFP B Discharge Pressure 15 psig (32) 1-D BUS VOLTS 2330 Amps 0 AFW Pump P-8C Amperes O AMPS AFW Discharge Pressure P-8C 18 psig C-11 BACK C-11A AFW Pump P-8A Amperes O AMPS AFW Pump P-8B Steam Pressure O psig (17) Containment Area Monitors AFW Discharge Pressure P-8A & P-8B 18 psig RIA-1805  ??? R/Hr Moisture SEP Drain Tank Level 14  % RIA-1806  ??? R/Hr Condensor Hotwell Level 82  % RIA-1807  ??? R/Hr Condensor Vacuum 0 in Hg. RIA-1808  ??? R/Hr Gland Seal Condensor Vacuum 14.2 in Hg. (17) High Range Containment Monitors Atmospheric Dump Valves CLOSED RIA-2321 .1E+01 R/Hr AFW Pump P-8A OFF P-8B OFF P-8C OFF RIA-2322 .1E+01 R/Hr Heater Drain Pump P-10A OFF P-10B OFF (19) Containment Hydrogen Concentration Condensate Pump P-2A OFF P-2B OFF AI-2401R 0  % AI-2401L 0  % C-11 (30) Main Steam Line Gamma RIA-2324 .23E+02 CPM (31) AFW FLOW TO SGA RIA-2323 .25E+02 CPM FROM P8A, B0 From P-8C 0 gpm , (31) AFW FLOW TO SGB EQUIPMENT STATUS: FROM P-8A&B 0 From P-8C 0 gpm Condensor Vacuum (R) 0 IN HG. 1. SIGNIFICANT EQUIP OUTAGES PCP A Leak-off Flow (R) 0 (INOPERABLE EQUIPMENT) PCP B Leak-off Flow (R) 0 2. SURVEILLANCE DUE/ PROGRESS PCP C Leak-off Flow (R) 0 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off Flow (R) 0 OR OUTAGES

O O O SHAVPALI TSC STATUS PAGE PALEX 94 l Time 1015 Scenario Time 0145 Message # 15 142 4 Time Jump Scenario Time Jump -~ i { C-08 C-02 SW Pumps P-7A ON P-78 0FF P-7C ON (10) VCT Temp 69 F l CCW Pumps P-52A UFF P-52B UN- P-52C UFF (10) VCT Pressure H psi j FPC Pumps P-51A UTF P-51B DTF (10) VCT Level 5T  % i PCP Control Bleedoff Pressure U psig  ! CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow U- gpm  ; (26) Charging Flow U gpm ' VIA ON V2A ON V3A ON V4A 0FF VlB UN V2B DN (9) Quench Tank Temp 101 F

                         -           -~        V3B DN-     V4B UTF                 (9) Quench TANK Pressure                            D- psig l;

(9) Quench TANK Level 53  % C-03 U psia (7) Pressurizer Pressure (R) (23) HPSI Pumps (8) PZR Level (R) LT0102A ~1  % P-66A 0FF P-66B 0FF LT0103 l % , (25) LPSI Pumps P-67A UFF P-678 UFF. (12) PORV PRV-1042A CLOSED 1043B LTOSED (18) Containment Spray Pumps (12) BLOCK MOV-1042A OPEN 1043A OPEN

                       .       P-54A 0FF P-54B 0FF P-54C OFF                              CHARGING PUMPS                                                i

. (27) HPSIA, LPSIA- 5 PRAY A SUCTION P55A 0FF P55B 0FF P55C OFF CV-3057 (SIRWT) CV-3030 (Sump) (6) PCPS P50A UFF P508 DTF P50C DTF P500 0FF CLOSED CLOSED PZR HTR AMPS LC15 0 LCC 16 U- ,

'                                                                                 (1) PCS TAVE (R)         LOOPI-(TR-Olll)            95      F LOOP 2 (TR-0121)           V5      F C-02.                                   (25) REACTOR POWER LEVEL nil .14E+03        cps         NI3 .13E     %     NI7. 14E-06 %

Intermediate Press Letdown Temp 104 F NI2 .13E+03 cps N!4 .12E-06  % NIB .15E-06 % Charging Line Temperature TUZ F NI-05 .14E-06  % NI-09 Letdown Line Temp TDT F l NI-06 .14E-06  % NI-10 SDCS from PCS (R) 162 F , SDCS to PCS (R) ~~9T- F PIP  ! 4 (DEMAND LOG +CONSTAN O OD, OR FLUX / TEMP) Gross MW 0 Net MW D (28) Control Rod PositTon GPl O GP2 0 GP3 0 GP4 0 - i GP6(A) U GP7(B) 5 Stuck Rods NONE <optiona1># 0 Core Exit Temp _5 F

o q SHAVPAtl TSC STATUS PAGE PALEX 94 Time 1030 Scenario Time 0200 Message # 16 -'- 140 Time Jump Scenario Time Jump C-13 C-12 PCP Current (Amps) Condensate Storage Tank Level T-2 86 % P-50A 0 P-508 0 Instrument Air Pressure TU4 psig P-SOC U P-500 U (15) Containment Building Pressure 2 T psig

                                                                                                                                                                       ~               ~

(6) PCS Flow (16) S/G A Compartment Temperature T9U F (3) Thot (F) Loop 1 99 F S/G A COMPARTMENT Humidity TUU % Loop 2 TU0 F (16) S/G B Compartment Temperature E U F (2) Tcold (F) Loop 1A 9T F S/G B Humidity TUU % Loop 2A DT F (16) Dome Temperature 755 F Loop IB DT F (11) SIRW Tank Level UT  % Loop 2B UI F (15) WR Containment Pressure (R) H psia (5) Subcooling 156 F 12 PSIA (14) Containment Sump Level 591 % (7) PCS WR Pressure (R) IT PSIA-(14) Containment Water Level (R) E95 % (7) PCS NR Pressure (R) TI PSIA (22) SI Tank Level (%) (30) S/G A LEVEL WR U~  % A 41 B 41 C 41

                                                                                                                  -         D 41-                    (30) S/G A LEVEL (R)            U   %

SI TanE PressureTpsig) (30) S/G A PRESS T psia A 232 8 232 C 232 D 228 S/G A STM FLW (R) U X10**6 PPH (21) SIAS ATarm NO

                                                                                                                       -                                     S/G A FD FLW (R)        U   X10**6 PPH (30) S/G B LEVEL WR             D   %

C-12 (30) S/G B LEVEL (R) U  % (30) S/G B PRESS T4 psia Concentrated Boric Acid Tank Levels S/G B STM FLW (R) F X10**6 PPH T53A 100  % S/G B FD FLW (R) U X10**6 PPH T53B TUU  % Reactor Vessel DP EI psid PANEL K-13 . (12) PORV Discharge Temperature III F j (13) Pzr Safety Valve Discharge Temp (F) (20) CONTAINMENT HIGH PRESS l RV-1039 127 F YES i RV-1040 T47 F I RV-1041 TT7 F (20) Containment High Radiation YES l l l l

O O O SHAVPAL1 TSC STATUS PAGE PALEX 94 Time 1030 Scenario Time 0200 Message # 16 141 Time Jump Scenario Time Jump C-01 C-04 MFP Suction Pressure 15 psig (32) D/G Freq 1-1 0 1-2 60 MFP A Discharge Pressure 15 psig (32) 1-C BUS VOLTS 0 Amps 0 MFP B Discharge Pressure 15 psig (32) 1-D BUS VOLTS 2330 Amps 0 AFW Pump P-8C Amperes O AMPS AFW Discharge Pressure P-8C 18 psig C-11 BACK C-11A AFW Pump P-8A Amperes O AMPS AFW Pump P-8B Steam Pressure O psig (17) Containment Area Monitors AFW Dis;harge Pressure P-8A & P-8B 18 psig RIA-1805  ??? R/Hr Moisture SEP Drain Tank Level 14  % RIA-1806  ??? R/Hr Condensor Hotwell Level 82  % RIA-1807  ??? R/Hr Condensor Vacuum 0 in Hg. RIA-1808  ??? R/Hr Gland Seal Condensor Vacuum 14.2 in Hg. (17) High Range Containment Monitors Atmospheric Dump Valves CLOSED RIA-2321 .2E+01 R/Hr AFW Pump P-8A OFF P-8B OFF P-8C OFF RIA-2322 .2E+01 R/Hr Heater Drain Pump P-10A OFF P-10B OFF (19) Containment Hydrogen Concentration Condensate Pump P-2A OFF P-2B OFF AI-2401R 0  % AI-2401L 0  % C-11 (30) Main Steam Line Gamma RIA-2324 .23E+02 CPM (31) AFW FLOW TO SGA RIA-2323 .25E+02 CPM FROM P8A, BO From P-8C 0 gpm (31) AFW FLOW TO SGB EQUIPMENT STATUS: FROM P-8A&B O From P-8C 0 gpm Condensor Vacuum (R) O IN HG. 1. SIGNIFICANT EQUIP OUTAGES PCP A Leak-off Flow (R) 0 (INOPERABLE EQUIPMENT) PCP B Leak-off Flow (R) 0 2. SURVEILLANCE DUE/ PROGRESS PCP C Leak-off Flow (R) O 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off Flow (R) 0 OR OUTAGES l l

O O O SHAVPALI TSC STATUS PAGE PALEX 94 Time 1030 Scenario Time 0200 Message 4 16 142 Time Jump Scenario Time Jump

 ;                                                    C-08                                                                 C-02 SW Pumps      P-7A ON       P-78 0FF       P-70 ON              (10) VCT Temp                                    69     F CCW Pumps P-52A UFF       P-528 Ofr       P-52C UFF             (10) VCT Pressure                                IT     psi

, FPC Pumps P-51A UFF P-518 DFF (10) VCT Level ET  % PCP Control Bleedoff Pressure II psig CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow D- gpm (26) Charging Flow 5 gpm VIA ON V2A ON V3A ON V4A 0FF (9) Quench Tank Temp Tol F V1s UN- V2B UN- V3B UR-V4B UFF (9) Quench TANK Pressure D psig (9) Quench TANK Level 53  % C-03 (7) Pressurizer Pressure (R) II psia (8) PZR Level (R) LT0102A I  % (23) HPSI Pumps P-66A 0FF P-668 0FF LT0103 7  % (25) LPSI Pumps P-67A UFF P-67B DFF (12) PORV PRV-1042A CLOSED 1043B LTOSED (18) Containment Spray Pumps (12) BLOCK MOV-1042A OPEN 1043A OPEN P-54A 0FF P-548 0FF P-54C OFF CHARGING PUMPS (27) HPSIA, LPSIA~~5 PRAY A SUDTION P55A 0FF P55B 0FF P55C OFF CV-3057 (SIRWT) CV-3030 (Sump) (6) PCPS P50A DTF P508 UFF P50C UFF P50D OFF CLOSED CLOSED PZR HTR AMPS LC15 0 - LCC 16 5-(1) PCS TAVE (R) LOOPI (TR-Olll) 95 F

95 F

' LOOP 2 (TR-0121) - C-02 (25) REACTOR POWER LEVEL nil .14E+03 cps NI3 .13E-06  % NI7 .14E-06  %

Intermediate Press Letdown Temp 104 F NI2 .13E+03 cps NI4 .12E-06  % NI8 .15E-06  %

l Charging Line Temperature TDI F NI-05 .14E-06  % NI-09 Letdown Line Temp TUT F NI-06 .14E-06  % NI-10 SDOS from PCS (R) IDY F i' SDCS to PCS (R) -9T- F PIP (DEMAND LOG + CONSTANT ~ ROD, OR FLUX / TEMP) Gross MW 0 Net MW D (28) Control Rod PositTon GPl O GP2 0 GP3 0

                                                                                                                                         ~       GP4 0~

GP6(A) U GP7(B) U l Stuck Rods NONE < optional ># 0 Core Exit Temp 5 F

O O O SHAVPALI TSC STATUS PAGE PALEX 94 Time 1045 Scenario Time 0215 Message # 17 140 Time Jump Scenario Time Jump C-13 C-12 PCP Current (Amps) Condensate Storage Tank Level T-2 86 % P-50A 0 P-50B 0 Instrument Air Pressure TU4 psig P-50C U P-500 D (15) Containment Building Pressure T~4 psig (6) PCS Flow - (16) S/G A Compartment Temperature T M F (3) That (F) Loop 1 99 F S/G A COMPARTMENT Humidity TUU % toop 2 TUO F (16) S/G B Compartment Temperature TUU F (2) Tcold (F) Loop 1A 91- F S/G B Humidity 165 % Loop 2A VI F (16) Dome Temperature YUU F Loop 1B UT F (11) SIRW Tank Level HT  % Loop 2B 9T F (15) WR Containment Pressure (R) IB psia (5) Subcooling TU6 F 12 PSIA (14) Containment Sump Level 591 % (7) PCS WR Pressure (R) T3- PSIA-(14) Containment Water Level (R) 595 % (7) PCS NR Pressure (R) TI PSIA (22) SI Tank Level (%) (30) S/G A LEVEL WR U~  % A 41 B 41 C 41

                                  -          D 41--             (30) S/G A LEVEL (R)         U    %

SI TanE~ Pressure {psig) (30) S/G A PRESS T psia A 232 8 232 C 232 D 228 S/G A STM FLW (R) U X10**6 PPH (21) SIAS ATirm NO

                                       -                              S/G A FD FLW (R)       U    X10**6 PPH (30) S/G B LEVEL WR          H    %

C-12 (30) S/G B LEVEL (R) U  % (30) S/G B PRESS T4 psia Concentrated Boric Acid Tank Levels S/G B STM FLW (R) D- X10**6 PPH T53A 100  % S/G B FD FLW (R) U X10**6 PPH T53B TUU  % Reactor Vessel DP BI psid PANEL K-13 (12) PORY Discharge Temperature III F , (13) Pzr Safety Valve Discharge Temp (F) (20) CONTAINMENT HIGH PRESS RV-1039 127 F YES RV-1040 T47 F RV-1041 T77 F (20) Containment High Radiation YES

O O O SHAVPAL1 TSC STATUS PAGE PALEX 94 Time 1045 Scenario Time 0215 Message # 17 141 Time Jump Scenario Time Jump C-01 C-04 MFP Suction Pressure 15 psig (32) D/G Freq 1-1 0 1-2 60 MFP A Discharge Pressure 15 psig (32) 1-C BUS VOLTS O Amps 0 MFP B Discharge Pressure 15 psig (32) 1-D BUS VOLTS 2330 Amps 0 AFW Pump P-8C Amperes O AMPS AFW Discharge Pressure P-8C 18 psig C-11 BACK C-11A AFW Pump P-8A Amperes O AMPS AFW Pump P-8B Steam Pressure O psig (17) Containment Area Monitors AFW Discharge Pressure P-8A & P-8B 18 psig RIA-1805  ??? R/Hr Moisture SEP Drain Tank Level 14  % RIA-1806  ??? R/Hr Condensor Hotwell Level 82  % RIA-1807  ??? R/Hr Condensor Vacuum 0 in Hg. RIA-1808  ??? R/Hr Gland Seal Condensor Vacuum 14.2 in Hg. (17) High Range Containment Monitors Atmospheric Dump Valves CLOSED RIA-2321 .2E+02 R/Hr AFW Pump P-8A OFF P-8B OFF P-8C OFF RIA-2322 .2E+02 R/Hr Heater Drain Pump P-10A OFF P-10B OFF (19) Containment Hydrogen Concentration Condensate Pump P-2A OFF P-2B OFF AI-2401R 0  % AI-2401L 0  % C-11 (30) Main Steam Line Gamma RIA-2324 .23E+02 CPM (31) AFW FLOW TO SGA RIA-2323 .25E+02 CPM FROM P8A, B0 From P-8C 0 gpm (31) AFW FLOW TO SGB EQUIPMENT STATUS: FROM P-8A&B 0 From P-8C 0 gpm Condensor Vacuum (R) 0 IN HG. 1. SIGNIFICANT EQUIP OUTAGES PCP A Leak-off Flow (R) 0 (INOPERABLE EQUIPMENT) PCP B Leak-off Flow (R) 0 2. SURVEILLANCE DUE/ PROGRESS PCP C Leak-off Flow (R) 0 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off Flow (R) O OR OUTAGES

L O O O SHAVPALI TSC STATUS PAGE PALEX 94 i Time 1045 Scenario Time 0215 Message # 17 142 T he Jump Scenario Time Jump - C-08 C-02 i SW Pumps P-7A ON P-78 0FF P-7C ON (10) VCT Temp I 69 F i CCW Pumps P-52A UFF P-52B UN- P-52C UFF FPC Pumps P-51A UFF P-518 UFF (10) VCT Pressure IT psi 3 (10) VCT Level 5T  % PCP Control Bleedoff Pressure CONTAINMENT COOLER RECIRC FANS II psig (26) Letdown Flow U- gpm , (26) Charging Flow U gpm VIA ON V2A ON V3A ON V4A 0FF (9) Quench Tank Temp V2B UR V3B UR T01 F VIB UN- -- - V4B UFF (9) Quench TANK Pressure o psig (9) Quench TANK Level 33  % C-03 (7) Pressurizer Pressure (R) II psia (23) HPSI Pumps P-66A 0FF P-66B 0FF (8) PZR Level (R) LT0102A 7  % (25) LPSI Pumps LT0103 7  % P-67A UFF P-678 UFF (12) PORV PRV-1042A CLOSED 10438 CEOSED (18) Containment Spray Pumps (12) BLOCK MOV-1042A OPEN 1043A OPEN P-54A 0FF P-54B 0FF P-54C OFF CHARGING PUMPS l (27) HPSIA, LPSIA 7 PRAY A SUCTION P55A 0FF P55B 0FF P55C OFF 1 CV-3057 (SIRWT) CV-3030 (Sump) (6) PCPS P50A UFF P508 UTF P50C UFF P50D OFF ' }- CL6 SED CLOSED PZR HTR AMPS LC15 0 LCC 16 U-

'                                                                                 (1) PCS TAVE (R)        LOOPI-(TR-Olll)               95     F LOOP 2 (TR-0121)              9E     F         l' C-02                                        (25) REACTOR POWER LEVEL s

i nil .14E+03 cps NI3 .13E-06  % NI7 .14E-06 % Intermediate Press Letdown Temp 104 F NI2 .13E+03 cps NI4 .12E-06  % NI8-.15E-06 % Charging Line Temperature TUI F NI-05 .14E-06  % NI-09 Letdown Line Temp TUI F NI-06 .14E-06  % NI-10 t SDCS from PCS (R) TUZ F i SDCS to PCS (R) _9I F PIP  ! (DEMAND LOG + CONSTANT 3 00, OR FLUX / TEMP) Gross MW 0 Net MW D (28) Control Rod Position GPl O GP2 0 GP3 0 - GP4 0-I GP6(A) U GP7(B) 5 l

'                                                                                      Stuck Rods               RONE       < optional >f 0               f Core Exit Temp                                               F

_U 1

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

O O O SHAVPALI TSC STATUS PAGE PALEX 94 !

i i L Time 1100 Scenario Time 0230 Message # 18 140

                                                                                             ~~

Time Jump Scenario Time Jump ' i C-!? C-12

Pr" 2;rrent (Amps) i Condensate Storage Tank Level T-2 86 % P-50A 0 P-508 0 i Instrument Air Pressure T54 psig P-50C U P-500 D (15) Containment Building Pressure E4 psig (6) PCS Flow (16) S/G A Compartment Temperature II5 F (3) Thot (F) Loop 1 99 F  ;

S/G A C6MPARTMENT Humidity TUU % toop 2 TUO F i (16) S/G B Compartment Temperature 2T5 F (2) Tcold (F) Loop 1A VI- F  ! S/G B Humidity TUU % toop 2A DT F ' (16) Dome Temperature II5 F Loop IB UT F. (11) SIRW Tank Level BF  % Loop 2B UT F 4 (15) WR Containment Pressure (R) TU psia (5) Subcooling TU6 F 12 PSIA , (14) Containment Sump Level 591 % (7) PCS WR Pressure (R) IT PSIK-(14) Containment Water Level (R) 595 % (7) PCS NR Pressure (R) Il PSIA (22) SI Tank Level (%) (30) S/G A LEVEL WR F  % A 41 B 41 C 41

                                                    --       0 41--                (30) S/G A LEVEL (R)                   U    %

SITanFPressure7psig) (30) S/G A PRESS T psia , A 232 8 232 C 232 0 228 S/G A STM FLW (R) U X10**6 PPH (21) SIAS ATarm NO

                                                        --                                 S/G A FD FLW (R)               U    X10**6 PPH (30) S/G B LEVEL WR                    U    %

C-12 (30) S/G B LEVEL (R) U  % (30) S/G B PRESS T4 psia 1 Concentrated Boric Acid Tank Levels S/G B STM FLW (R) D- X10**6 PPH  ; T53A 100  % S/G B FD FLW (R) U X10**6 PPH  ! T53B TUU  % i Reactor Vessel DP BI psid PANEL K-13 i (12) PORY Discharge Temperature III F  ! (13) Pzr Safety Valve Discharge Temp (F) (20) CONTAINMENT HIGH PRESS RV-1039 127 F YES '

RV-1040 T47 F RV-1041 177 F (20) Containment High Radiation i YES

[

O O O SHAVPAL1 TSC STATUS PAGE PALEX 94 Time 1100 Scenario Time 0230 Message # 18 141 Time Jump Scenario Time Jump C-01 C-04 MFP Suction Pressure 15 psig (32) D/G Freq 1-1 0 1-2 60 MFP A Discharge Pressure 15 psig (32) 1-C BUS VOLTS O Amps 0 MFP B Discharge Pressure 15 psig (32) 1-D BUS VOLTS 2330 Amps 0 AFW Pump P-8C Amperes O AMPS AFW Discharge Pressure P-8C 18 psig C-11 BACK C-11A AFW Pump P-8A Amperes O AMPS AFW Pump P-8B Steam Pressure o psig (17) Containment Area Monitors AFW Discharge Pressure P-8A & P-8B 18 psig RIA-1805  ??? R/Hr Moisture SEP Drain Tank Level 14  % RIA-1806  ??? R/Hr Condensor Hotwell Level 82  % RIA-1807  ??? R/Hr Condensor vacuum o in Hg. RIA-1808  ??? R/Hr Gland Seal Condensor Vacuum 14.2 in Hg. (17) High Range Containment Monitors Atmospheric Dump Valves CLOSED RIA-2321 .35E+03 R/Hr AFW Pump P-8A OFF P-8B OFF P-8C OFF RIA-2322 .35E+03 R/Hr Heater Drain Pump P-10A OFF P-10B OFF (19) Containment Hydrogen Concentration Condensate Pump P-2A OFF P-2B OFF AI-240lR 0  % AI-2401L 0  % C-11 (30) Main Steam Line Gamma RIA-2324 .23E+02 CPM (31) AFW FLOW TO SGA RIA-2323 .25E+02 CPM FROM P8A, B0 From P-8C 0 gpm (31) AFW FLOW TO SGB EQUIPMENT STATUS: FROM P-8A&B 0 From P-8C 0 gpm Condensor Vacuum (R) 0 IN HG. 1. SIGNIFICANT EQUIP OUTAGES PCP A Leak-off Flow (R) 0 (INOPERABLE EQUIPMENT) PCP B Leak-off Flow (R) 0 2. SURVEILLANCE DUE/ PROGRESS PCP C Leak-off Flow (R) 0 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off Flow (R) 0 OR OUTAGES

O f% r O '& N)) SHAVPALI TSC STATUS PAGE PALEX 94 Time 1100 Scenario Time 0230 Message # 18-- 142 Time Jump Scenario Time Jump C-08 C-02 SW Pumps P-7A ON P-7B 0FF P-7C ON (10, VCT Temp 69 F CCW Pumps P-52A UFF P-528 Uff- P-52C DTF (10) VCT Pressure IT psi FPC Pumps P-51A UTF P-518 UFF (10) VCT Level 54  % FCP Control Bleedoff Pressure TI psig CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow U- gpm (26) Charging Flow 5 gpm VIA ON V2A ON V3A ON V4A 0FF (9) Quench Tank Temp Tol F VIB UN - V2B UN v3B DN V4B UFF (9) Quench TANK Pressure D- psig (9) Quench TANK Level 53  % C-03 (7) Pressurizer Pressure (R) II psia (8) PZR Level (R) LT0102A 7  % (23) HPSI Pumps P-66A 0FF P-66B 0FF LT0103 7  % (25) LPSI Pumps P-67A UFF P-678 UFF (12) PORV PRV-1042A CLOSED 1043B LTOSED (18) Containment Spray Pumps (12) BLOCK MOV-1042A OPEN 1043A OPEN P-54A 0FF P-54B 0FF P-54C OFF CHARGING PUMPS (27) HPSIA, LPSIA- 5 PRAY A SUCTION P55A 0FF P55B 0FF P55C OFF CV-3057 (SIRWT) CV-3030 (Sump) (6) PCPS P50A UFF F508 DTF P50C UFF P500 0FF CLOSED CLOSED PZR HIR AMPS LC15 0 LCC 16 D-- (1) PCS TAVE (R) LOOPI-(TR-Olll) US F LOOP 2 (TR-0121) 55 F C-02 (25) REACTOR POWER LEVEL nil .14E+03 cps NI3 .13E-06  % NI7 .14E-06 % Intermediate Press Letdown Temp 104 F HI2 .13E+03 cps NI4 .12E-06  % NI8 .15E-06 % Charging Line Temperature T67 F NI-05 .14E-06  % NI-09 Letdown Line Temp TUT F NI-06 .14E-06  % NI-10 SDCS from PCS (R) TU7 F SDCS to PCS (R) -91 F PIP (DEMAND LOG + CONSTANT ~ ROD, OR FLUX / TEMP) Gross MW 0 Net MW U (28) Control Rod PositTon GPl 0 GP2 0 GP3 0 GP4 0-GP6(A) U GP7(B) U Stuck Rods NONE < optional >f 0 Core Exit Temp U F

O O O SHAVPAtl TSC STATUS PAGE PALEX 94 Time 1115 Scenario Time 0245 Message # 19 140 Time Jump Scenario Time Jump C-13 C-12

PCP Current (Amps)

~ Condensate Storage Tank Level T-2 86 % P-50A 0 P-508 0 e

Instrument Air Pressure TU4 psig P-50C D P-50D D (15) Containment Building Pressure D psig (6) PCS Flow (16) S/G A Compartment Temperature RU F (3) Thot (F) Loop 1 99 F , S/G A COMPARTMENT Humidity IUU % Loop 2 TUO F

• j (16) S/G B Compartment Temperature N T F (2) Tcold (F) Loop IA 9T- F ,

S/G B Humidity TUU % Loop 2A UT F  ;

(16) Dome Temperature EU F Loop IB UT F  ;

(11) SIRW Tank Level W% Loop 2B 9T F (15) WR Containment Pressure (R) TH psia (5) Subcooling TU6 F 12 PSIA ; (14) Containment Sump Level 591 % (7) PCS WR Pressure (R) IT PSIF (14) Containment Water Level (R) 595 % (7) PCS NR Pressure (R) U PSIA  ;

(22) SI Tank Level (%) (30) S/G A LEVEL WR U-  %

i A 41 B 41 C 41- 0 41- (30) S/G A LEVEL (R) U  % SI TanE Pressure Tpsig) (30) S/G A PRESS T psia  ; A 232 B 232 C 232 0 228 S/G A STM FLW (R) U X10**6 PPH  ! l (21) SIAS Alarm NO S/G A FD FLW (R) U X10**6 PPH l (30) S/G B LEVEL WR U  % , l C-12 (30) S/G B LEVEL (R) U  % l l (30) S/G B PRESS T4 psia t ! Concentrated Boric Acid Tank Levels S/G B STM FLW (R) U- X10**6 PPH [ T53A 100  % S/G B FD FLW (R) U X10**6 PPH i T53B TUU  % l Reactor Vessel DP B3 psid PANEL K-13

(12) PORY Discharge Temperature TU F 1

(13) Pzr Safety Valve Discharge Temp (F) (20) CONTAINMENT HIGH PRESS l ! RV-1039 127 F YES ,

Rv-1040 T47 F

RV-1041 T77 F (20) Containment High Radiation  : ) YES i i  ! l .

O O O SHAVPAL1 TSC STATUS PAGE PALEX 94 Time 1115 Scenario Time 0245 Message # 19 141 Time Jump Scenario Time Jump C-01 C-04 MFP Suction Pressure 15 psig (32) D/G Freq 1-1 0 1-2 60 MFP A Discharge Pressure 15 psig (32) 1-C BUS VOLTS O Amps 0 MFP B Discharge Pressure 15 psig (32) 1-D BUS VOLTS 2330 Amps 0 AFW Pump P-8C Amperes O AMPS AFW Discharge Pressure P-8C 18 psig C-11 BACK C-11A AFW Pump P-8A Amperes O AMPS AFW Pump P-8B Steam Pressure O psig (17) Containment Area Monitors AFW Discharge Pressure P-8A & P-8B 18 psig RIA-1805  ??? R/Hr Moisture SEP Drain Tank Level 14  % RIA-1806  ??? R/Hr Condensor Hotwell Level 82  % RIA-1807  ??? R/Hr Condensor Vacuum 0 in Hg. RIA-1808  ??? R/Hr Gland Seal Condensor Vacuum 14.2 in Hg. (17) High Range Containment Monitors Atmospheric Dump Valves CLOSED RIA-2321 .5E+03 R/Hr AFW Pump P-8A OFF P-8B OFF P-8C OFF RIA-2322 .5E+03 R/Hr Heater Drain Pump P-10A OFF P-10B OFF (19) Containment Hydrogen Concentration Condensate Pump P-2A OFF P-2B OFF AI-2401R 0  % AI-2401L 0  % C-11 (30) Main Steam Line Gamma RIA-2324 .23E+02 CPM (31) AFW ? LOW TO SGA RIA-2323 .25E+02 CPM FROP1 P8A, B O_ From P-8C 0 gpm , (31) AFW FLOW TO SGB EQUIPMENT STATUS: i FROM P-8A&B O From P-8C 0 gpm Condensor Vacuum (R) 0 IN HG. 1. SIGNIFICANT EQUIP OUTAGES PCP A Leak-off Flow (R) 0 (INOPERABLE EQUIPMENT) PCP B Leak-off Flow (R) 0 2. SURVEILLANCE DUE/ PROGRESS PCP C Leak-off Flow (R) 0 3. ABNORMAL ELECTRICAL LINEUPS l PCP D Leak-off Flow (R) 0 OR OUTAGES l l t

    ,m                                                    p                                                        a b

SHAVPAll TSC STATUS PAGE PALEX 94 Time 1115 Scenario Time 0245 Messa9e # 19-- 142 Time Jump Scenario Time Jump C-08 C-02 SW Pumps P-7A ON P-78 0FF P-7C ON (10) VCT Temp 69 F CCW Pumps P-52A DTF P-528 UIT- P-52C DTF (10) VCT Pressure H psi FPC Pumps P-51A UFT P-51B UTF (10) VCT Level R  % PCP Control Bleedoff Pressure U psig CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow U~ gpm (26) Charging Flow U gpm VIA ON V2A ON V3A ON V4A 0FF (9) Quench Tank Temp T01 F VlB UN

       -       V2B DN-      V3B UN V4B UFF                (9) Quench TANK Pressure                     D      psig (9) Quench TANK Level                       53     %

C-03 (7) Pressurizer Pressure (R) U psia (8) PZR Level (R) LT0102A ~I  % (23) HPSI Pumps P-66A 0FF P-66B 0FF LT0103 ~I  % (25) LPSI Pumps P-67A DTF P-67B DTF (12) PORV PRV-1042A CLOSED 1043B LTOSED (18) Containment Spray Pumps (12) BLOCK MOV-1042A UP C 1043A DTEfr-P-54A 0FF P-54B 0FF P-54C OFF CHARGING PUMPS (27) HPSIA, LPSIA 5 PRAY A SUCTION P55A 0FF P558 0FF P55C OFF CV-3057 (SIRWT) CV-3030 (Sump) (6) PCPS P50A UTF P508 DTF P50C DFF P500 0FF CLOSED CLOSED PZR HTR AMPS LC15 0 LCC 16 D-(1) PCS TAVE (R) LOOPI-(TR-Olll) 95 F LOOP 2 (TR-0121) E F C-02 (25) REACTOR POWER LEVEL nil .14E+03 eps NI3 .13E-06  % HI7 .14E-06 % Intermediate Press Letdown Temp 104 F NI2 .13E+03 cps NI4 .12E-06  % NI8 .15E-06 % Charging Line Temperature TD7 F NI-05 .14E-06  % NI-09 Letdown Line Temp TUT F NI-06 .14E-06  % NI-10 SDCS from PCS (R) TUY F SDCS to PCS (R) -9T F PIP (DEMAND LOG + CONSTANT- ROD, OR FLUX / TEMP) Gross MW 0 Net MW U (28) Control Rod PositTon GPl O GP2 0 GP3 0 GP4 0-GP6(A) U GP7(B) U Stuck Rods HONE < optional ># 0 Core Exit Temp _U F

O O O SHAVPAll TSC STATUS PAGE PALEX 94 Time 1130 Scenario Time 0300 Message # 20

                                                                                     '~

140 Time Jump Scenario Time Jump C-13 C-12 PCP Current (Amps) Condensate Storage Tank Level T-2 86  % P-50A 0 P-50B 0 Instrument Air Pressure M4 psig P-50C D P-500 U (15) Containment Buildire, Pressure 7 T psig (6) PCS Flow ~

                                                                                                                 ~

(16) S/G A Compartment i mperature 2E5 F (3) Thot (F) Loop 1 99 F S/G A COMPARTMENT Humidity TUU % toop 2 TU0 F (16) S/G B Compartment Temperature 235 F (2) Tcold (F) Loop 1A 9T F S/G B Humidity IDU % Loop 2A 9T F (16) Dome Temperature 775 F Loop 1B UT F  ! (11) SIRW Tank Level BF % Loop 2B 9T F (15) WR Containment Pressure (R) TH psia (5) Subcooling M6 F 12 PSIA (14) Containment Surrp Level 591 % (7) PCS WR Pressure (R) TT PSIK-(14) Containment Water Level (R) 595 % (7) PCS NR Pressure (R) TI PSIA (22) SI Tank Level (%) -(30) S/G A LEVEL WR U~  % A 41 B 41 C 41

                                            -         0 41~~                 (30) S/G A LEVEL (R)            U     %

SI TanEPressure7psig) (30) S/G A PRESS T psia A 232 B 232 C 232 0 228 S/G A STM FLW (R) 5 X10**6 PPH  ! (21) SIAS ATirm NO

                                                 -                                 S/G A FD FLW (R)          D     X10**6 PPH (30) S/G B LEVEL WR-            U     %                                                     i C 12
                                -                                            (30) S/G B LEVEL (R)            5     %                                                     ;

(30) S/G B PRESS T4 psia , Concentrated 89ric Acid Tank Levels S/G B STM FLW (R) D- X10**6 PPH T53A 100  % S/G B FD FLW (R) D X10**6 PPH , T53B IUU  % B3

                                                            ~

! Reactor Vessel DP i' i PANEL K-13 l (12) PORY Discharge Temperature TTI 4 (13) Pzr Safety Valve Discharge Temp (F) (20) CONTAINMENT HIGH PRESS ' i RV-1039 127 F YES j RV-1040 TIZ F

• RV-1041 177 F (20) Containment High Radiation -

YES l i i

m , (d L> b SHAVPAL1 TSC STATUS PAGE PALEX 94 Time 1130 Scenario Time 0300 Message # 20 141 Time Jump Scenario Time Jump C-01 C-04 MPP Suction Pressure 15 psig (32) D/G Freq 1-1 0 1-2 60 MFP A Discharge Pressure 15 psig (32) 1-C BUS VOLTS 0 Amps 0 MFP B Discharge Pressure 15 psig (32) 1-D BUS VOLTS 2330 Amps 0 AFW Pump P-8C Amperes O AMPS AFW Discharge Pressure P-8C 18 psig C-11 BACK C-11A AFW Pump P-8A Amperes O AMPS AFW Pump P-8B Steam Pressure O psig (17) Containment Area Monitors AFW Discharge Pressure P-8A & P-8B 18 psig RIA-1805  ??? R/Hr Moisture SEP Drain Tank Level 14  % RIA-1806  ??? R/Hr Condensor Hotwell Level 82  % RIA-1807  ??? R/Hr Condensor Vacuum 0 in Hg. RIA-1808  ??? R/Hr Gland Seal Condensor Vacuum 14.2 in Hg. (17) High Range Containment Monitors Atmospheric Dump Valvec CLOSED RIA-2321 .7E+03 R/Hr AFW Pump P-8A OFF P-8B OFF P-8C OFF RIA-2322 Heater Drain Pump P-10A OFF

                                                                                      .7E+03           R/Hr P-10B OFF               (19) Containment Hydrogen Concentration Condensate Pump            P-2A OFF    P-2B OFF                     AI-2401R          0             %

AI-2401L 0  % C-11 (30) Main Steam Line Gamma RIA-2324 .23E+02 CPM (31) AFW FLOW TO SGA RIA-2323 .25E+02 CPM FROM P8A, B0 From P-8C 0 gpm (31) AFW FLOW TO SGB EQUIPMENT STATUS: FROM P-8A&B 0 From P-8C 0 gpm Condensor Vacuum (R) 0 IN HG. 1. SIGNIFICANT EQUIP OUTAGES PCP A Leak-off Flow (R) 0 (INOPERABLE EQUIPMENT) PCP B Leak-off Flow (R) 0 2. SURVEILLANCE DUE/ PROGRESS PCP C Leak-off Flow (R) 0 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off Flow (R) 0 OR OUTAGES

O O O SHAVPAll TSC STATUS PAGE PALEX 94 Time 1130 Scenario Time 0300 Message # 20 142 Time Jump Scenario Time Jump

                                                                                                        ~~

C-08 C-02 SW Pumps P-7A ON P-7B 0FF P-7C ON (10) VCT Temp 69 F CCW Pumps P-52A DFF P-52B Ufr P-52C DFF~~- (10) VCT Pressure 2T pst FPC Pumps P-51A UFF P-518 DTF (10) VCT Level 54  % PCP Control Bleedoff Pressure T3 psig CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow D- gpm (26) Charging Flow U gpm VIA ON V2A ON V3A ON V4A 0FF (9) Quench Tank Temp Tol F VlB DN

                          -             V2B DN-      v3B UN--       V4B UTF                (9) Quench TANK Pressure                       D- psig (9) Quench TANK Level                          53    %

C-03 (7) Pressurizer Pressure (R) TJ psia (23) HPSI Pumps (8) PZR Level (R) LT0102A U  % P-66A 0FF P-66B 0FF LT0103 ~I  % (25) LPSI Pumps P-67A UFF P-678 UFF (12) PORV PRV-1042A CLOSED 10438 LTOSED (18) Containment Spray Pumps (12) BLOCK MOV-1042A OPEN 1043A UFEN-P-54A 0FF P-548 0FF P-54C OFF CHARGING PUMPS (27) HPSIA, LPSIA-~5 PRAY A SUCTION P55A 0FF P558 0FF P55C 0FF CV-3057 (SIRWT) CV-3030 (Sump) (6) PCPS P50A UFF P50B UTF P50C UFF P50D OFF CLOSED CLOSED PZR HTR AMPS LC15 0 LCC 16 D-(1) PCS TAVE (R) LOOPI-(TR-Olll) 95 F  ! LOOP 2 (TR-0121) 95 F C-02 (25) REACTOR POWER LEVEL

                                                                                                                                          ~~

nil .14E+03 cps NI3 .13E-06  % NI7. 14E-06 % Intermediate Press Letdown Temp 104 F NI2 .13E+03 cps NI4 .12E-06  % NI8 .15E-06 % Charging Line Temperature TDY F NI-05 .14E-06  % NI-09 Letdown Line Temp TUT F NI-06 .14E-06  % NI-10 SDCS from PCS (R) TDY F SDCS to PCS (R) _9T_~ F PIP (DEMAND LOG + CONSTANT- ROD, OR FLUX / TEMP) Gross MW 0 i Net MW U (28) Control Rod Position , GPl 0 GP2 0 GP3 0- GP4 0-GP6(A) U GP7(B) U Stuck Rods NONE < optional ># 0 l Core Exit Temp _U F

O O O SRAVPAll TSC STATUS PAGE PALEX 94 Time 1145 Scenario Time 0315 Message # 21 140 Time Jump Scenario Time Jump C-13 C-12 PCP Current (Amps) Condensate Storage Tank Level T-2 86 % P-50A 0 P-508 0 Instrument Air Pressure IU4 psig P-50C U P-500 U (15) Containment Building Pressure 2.4 psig (6) PCS Flow - (16) S/G A Compariment Temperature 290 F (3) Thot (F) Loop 1 99 F S/C A COMPARTMENT Humidity TUU % toop 2 150 F (16) S/G B Compartment Temperature 2 M F (2) Tcold (F) Loop 1A 9T- F S/G B Humidity TUU % Loop 2A 9T F (16) Dome Temperature 3DU F Loop IB 9T F (11) SIRW Tank Level BT~  % Loop 2B 9T F (15) WR Containment Pressure (R) i's psia (5) Subcooling TU6 F 12 PSIA (14) Containment Sump Level 591 % (7) PCS WR Pressure (R) IT PSIK-(14) Containment Water Level (R) 595 % (7) PCS NR Pressure (R) TI PSIA (22) SI Tank Level (%) (30) S/G A LEVEL WR D~  % A 41 B 41 C 41

                                                                                                              -~        D 41~               (30) S/G A LEVEL (R)          U    %

SI Tank Pressure 7psig) (30) S/G A PRESS T psia A 232 B 232 C 232 0 228 S/G A STM FLW (R) U X10**6 PPH (21) SIAS ATarm NO

                                                                                                                   -                              S/G A FD FLW (R)        U    X10**6 PPH (30) S/G B LEVEL WR           D    %

C-12 (30) S/G B LEVEL (R) U  % (30) S/G B PRESS T4 psia Concentrated Boric Acid Tank Levels S/G B STM FLW (R) U- X10**6 PPH T53A 100  % S/G B FD FLW (R) U X10**6 PPH T53B TUU  % Reactor Vessel DP BI psid PANEL K-13 (12) PORV Discharge Temperature III F (13) Pzr Safety Valve Discharge Temp (F) (20) CONTAINMENT HIGH PRESS RV-1039 127 F NO RV-1040 TU F

                                                                                                                                                                          ~~

RV-1041 177 F (20) Containment High Radiation YES

O O O SHAVPAL1 TSC STATUS PAGE PALEX 94 Time 1145 Scenario Time 0315 Message # 21 141 Time Jump Scenario Time Jump C-01 C-04 MFP Suction Pressure 15 psig (32) D/G Freq 1-1 0 1-2 60 MFP A Discharge Pressure 15 psig (32) 1-C BUS VOLTS 0 Amps 0 MFP B Discharge Pressure 15 psig (32) 1-D BUS VOLTS 2330 Amps 0 AFW Pump P-8C Amperes O AMPS AFW Discharge Pressure P-8C 18 psig C-11 BACK C-11A AFW Pump P-8A Amperes O AMPS AFW Pump P-8B Steam Pressure O psig (17) Containment Area Monitors AFW Discharge Pressure P-8A & P-8B 18 psig RIA-1805  ??? R/Hr Moisture SEP Drain Tank Level 14  % RIA-1806  ??? R/Hr Condensor Hotwell Level 82  % RIA-1807  ??? R/Hr Condensor Vacuum 0 in Hg. RIA-1808  ??? R/Hr Gland Seal Condensor Vacuum 14.2 in Hg. (17) High Range Containment Monitors Atmospheric Dump Valves CLOSED RIA-2321 .9E+03 R/Hr AFW Pump P-8A OFF P-8B OFF P-8C OFF RIA-2322 .9E+03 R/Hr Heater Drain Pump P-10A OFF P-10B OFF (19) Containment Hydrogen Concentration Condensate Pump P-2A OFF P-2B OFF AI-2401R 0  % AI-2401L 0  % C-11 (30) Main Steam Line Gamma RIA-2324 .23E+02 CPM (31) AFW FLOW TO SGA RIA-2323 .25E+02 CPM FROM P8A, B0 From P-8C 0 gpm (31) AFW FLOW TO SGB EQUIPMENT STATUS: FROM P-8A&B 0 From P-8C 0 gpm Condensor Vacuum (R) 0 IN HG. 1. SIGNIFICANT EQUIP OUTAGES PCP A Leak-off Flow (R) 0 (INOPERABLE EQUIPMENT) PCP B Leak-off Flow (R) 0 2. SURVEILLANCE DUE/ PROGRESS PCP C Leak-off Flow (R) O 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off Flow (R) 0 OR OUTAGES

o q <g SHAVPALI TSC STATUS PAGE PALEX 94 a Time 1145 Scenario Time 0315 Message # 21'-- 142 Time Jump Scenario Time Jump C-08 C-02 SW Pumps P-7A ON P-78 0FF P-7C ON (10) VCT Temp 69 F CCW Pumps P-52A DTF P-528 DH- P-52C UFF (10) VCT Pressure II psi FPC Pumps P-51A UFF P-51B DFF (10) VCT Level 54  % PCP Control Bleedoff Pressure TJ psig CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow D- gpm (26) Charging Flow U gpm VIA ON V2A ON V3A ON V4A 0FF (9) Quench Tank Temp T01 F VlB UN

                      -      V2B DR-      V3B DH-     V4B UFF                 (9) Quench TANK Pressure                     U-- psig (9) Quench TANK Level                        53      %

C-03 (7) Pressurizer Pressure (R) TI psia (8) PZR Level (R) LT0102A I  % (23) HPSI Pumps P-66A 0FF P-66B 0FF LT0103 I  % (25) LPSI Pumps P-67A UFF P-678 UFF (12) PORV PRV-1042A CLOSED 10438 UEOSED (18) Containment Spray Pumps (12) BLOCK MOV-1042A OPEN 1043A OPEN P-54A 0FF P-54B 0FF P-54C 0FF CHARGING PUMPS (27) HPSIA, LPSIA 5 PRAY A SUCTION P55A 0FF P55B 0FF P55C 0FF CV-3057 (SIRWT) CV-3030 (Sump) (6) PCPS P50A DTF P508 DTF P50C DTF P500 0FF CLOSED CLOSED PZR HTR AMPS LC15 0 LCC 16 D-(1) PCS TAVE (R) LOOPI-(TR-Olll) 95 F LOOP 2 (TR-0121) 95

                                                                                                                           ~'-

F C-02 (25) REACTOR POWER LEVEL _ nil .14E+03 cps NI3 .13E-06 % NI7 .14E-06  % Intermediate Press Letdown Temp 104 F NI2 .13E+03 cps NI4 .12E-06 % NI8 .15E-06  % Charging Line Temperature TU2 F NI-05 .14E-06  % NI-09 Letdown Line Temp TOT F NI-06 .14E-06  % NI-10 SDCS from PCS (R) 152 F SDCS to PCS (R) '--9T~ F PIP (DEMAND LOG + CONSTANT ROD, OR FLUX / TEMP) Gross MW 0 Net MW U (28) Control Rod PositTon GPl 0 GP2 0 GP3 0

                                                                                                                   ~

GP4 0 - GP6(A) U GP7(B) U Stuck Rods NONE < optional ># 0 Core Exit Temp 5 F

O O O SHAVPAll TSC STATUS PAGE PALEX 94  ! Time 1200 Scenario Time 0330 Message # 22 140 Time Jump Scenario Time Jump C-13 C-12 PCP Current (Amps) Condensate Storage Tank Level T-2 86 % P-50A 0 P-50B 0 Instrument Air Pressure TU4 psig P-50C U P-50D U (15) Containment Building Pressure 2.4 psig (6) PCS Flow l (16) S/G A Compartment Temperature 290 F (3) That (F) Loop 1 99 F - S/G A COMPARTMENT Humidity TUU % toop 2 1U0 F

(16) S/G B Compartment Temperature 197 F (2) Tcold (F) Loop 1A WF S/G B Humidity TUU % Loop 2A DI F (16) Dome Temperature IUU F Loop IB VT F (11) SIRW Tank Level W% Loop 2B II F (15) WR Containment Pressure (R) 15 psia (5) Subcooling TU6 F 12 PSIA (14) Containment Sump Level 591 % (7) PCS WR Pressure (R) IT PSIX-  ;

(14) Containment Water Level (R) 595 % (7) PCS NR Pressure (R) II PSIA * (22) SI Tank level (%) (30) S/G A LEVEL WR D-  % i A 41 B 41 C 41

                                           -          D 41-              (30) S/G A LEVEL (R)              U   %

SI TanFPressure7psig) (30) S/G A PRESS T psia A 232 B 232 C 232 D 228 S/G A STM FLW (R) U X10**6 PPH (21) SIAS ATarm - NO S/G A FD FLW (R) U X10**6 PPH (30) S/G B LEVEL WR U  % C-12 (30) S/G B LEVEL (R) U  % (30) S/G B PRESS T4 psia Concentrated Boric Acid Tank Levels S/G B STM FLW (R) D- X10**6 PPH

T53A 100  % S/G B FD FLW (R) U X10**6 PPH i T53B TUU  %

Reactor Vessel DP BI psid PANEL K-13 1 (12) PORY Discharge Temperature III F i (13) Pzr Safety Valve Discharge Temp (F) (20) CONTAINMENT HIGH PRESS RV-1039 127 F NO RV-1040 T42 F RV-1041 T77 F (20) Containment High Radiation YES 4 1

O O - O

;  SHAVPAL1                                       TSC      STATUS     PAGE

, PALEX 94 Time 1200 Scenario Time 0330 Message # 22 141 Time Jump Scenario Time Jump - C-01 C-04 MFP Suction Pressure 15 psig (32) D/G Freq 1-1 0 1-2 60 . MFP A Discharge Pressure 15 psig (32) 1-C BUS VOLTS 0 Amps 0 MFP B Discharge Pressure 15 psig (32) 1-D BUS VOL,TS 2330 Amps 0 AFW Pump P-8C Amperes O AMPS AFW Discharge Pressure P-8C 18 psig C-11 BE

• C-11A AFW Pump P-8A Amperes O AMPS l AFW Pump P-8B Steam Pressure o psig (17) Containment A.. a Monitors AFW Discharge Pressure P-8A & P-8B 18 psig RIA-1805  ??? R/Hr Moisture SEP Drain Tank Level 14  % RIA-1806  ??? R/Hr
• Condensor Hotwell Level 82  % RIA-1807  ??? R/Hr Condensor Vacuum o in Hg. RIA-1808  ??? R/Hr ,

Gland Seal Condensor Vacuum 14.2 in Hg. (17) High Range Containment Monitors l l Atmospheric Dump Valves CLOSED RIA-2321 .1E+04 R/Hr i AFW Pump P-8A OFF P-8B OFF P-8C OFF RIA-2322 .1E+04 R/Hr  ; Heater Drain Pump P-10A OFF P-10B OFF (19) Containment Hydrogen Concentration Condensate Pump P-2A OFF P-2B OFF AI-2401R 0  %  ! AI-2401L 0  % i C-11 (30) Main Steam Line Gamma i' 4 RIA-2324 .23E+02 CPM (31) AFW FLOW TO SGA RIA-2323 .25E+02 CPM i FROM P8A, B0 From P-8C 0 gpm (31) AFW FLOW TO SGB EQUIPMENT STATUS: l l FROM P-8A&B 0 From P-8C 0 gpm  : Condensor Vacuum (R) 0 IN HG. 1. SIGNIFICANT EQUIP OUTAGES PCP A Leak-off Flow (R) 0 (INOPERABLE EQUIPMENT) i PCP B Leak-off Flow (R) 0 2. SURVEILLANCE DUE/ PROGRESS j PCP C Leak-off Flow (R) 0 3. ABNORMAL ELECTRICAL LINEUPS  ; [ PCP D Leak-off Flow (R) 0 OR OUTAGES i l l

                                                                                                              +

i

O O O SHAVPAll TSC STATUS PAGE PALEX 94

                       -Time 1200                     Scenario Time 0330               Message # 22-142 Time Jump                       Scenario Time Jump
 ,                                        C-08                                                                 C-02 SW Pumps          P-7A ON        P-78 0FF     P-7C ON                (10) VCT Temp                                  69     F CCW Pumps P-52A UFF             P-52B DN-    P-52C UFF               (10) VCT Pressure                              2T     psi i               FPC Pumps P-51A DFF             P-SIB DTF                            (10) VCT Level                                 54    %

PCP Control Bleedoff Pressure II psig i CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow D- gpm (26) Charging Flow U gpm VIA ON V2A ON V3A ON V4A 0FF (9) Quench Tank Temp T01 F VlB DR - V2B UN- V3B UN V4B UFF (9) Quench TANK Pressure D-- psig (9) Quench TANK Level 53  % C-03 (7) Pressurizer Pressure (R) U psia (8) PZR Level (R) LT0102A U  % ! (23) HPSI Pumps P-66A 0FF P-668 0FF LT0103 7  % (25) LPSI Pumps P-67A DFF P-67B UFF (12) PORV PRV-1042A CLOSED 1043B LTOSED (18) Containment Spray Pumps (12) BLOCK MOV-1042A OPEN 1043A OPEN P-54A 0FF- P-54B 0FF P-54C OFF CHARGING PUMPS (27) HPSIA, LPSIA 3 PRAY A SUCTION P55A 0FF P55B 0FF P55C 0FF CV-3057 (SIRWT) CV-3030 (Sump) (6) PCPS P50A UFF P50B DFF P50C DTF P500 0FF CLOSED -CLOSED PZR HTR AMPS LC15 0 LCC 16 D-i (1) PCS TAVE (R) LOOPI-(TR-0111) 95 F LOOP 2 (TR-0121) 95 F C-02 (25) REACTOR POWER LEVEL nil .14E+03 cps NI3 .13E-06  % NI7. 14E-06 % Intermediate Press Letdown Temp 104 F NI2 .13E+03 cps NI4 .12E-06  % NI8 .15E-06 % . Charging Line Temperature TUZ F NI-05 .14E-06  % NI-09 Letdown Line Temp TUT F NI-06 .14E-06  % NI-10 SDCS from PCS (R) TUZ F - SDCS to PCS (R) -9F F PIP (DEMAND LOG + CONSTANT 3 00, OR FLUX / TEMP) Gross MW 0 Net MW U (28) Control Rod PositTon GPl O GP2 0 GP3 0- GP4 0-GP6(A) U GP7(B) U Stuck Rods NONE <optiona1># 0 Core Exit Temp D F

                                                                                                                                                    ~

.- SHAVPAll TSC S'T-A T U S PAGE PALEX 94 Time 1215 Scenario Time 0345 Message # 24 -- 140 Time Jump Scenario Time Jump i C-13 C-12 ' l . PCP Current (Amps) Condensate Storage Tank Level T-2 86  % P-50A 0 P-50B 0 i-Instrument Air Pressure T54 psig P-50C U P-50D 5 (15) Containment Building Pressure D-- psig (6) PCS Flow - 3 (16) S/G A Compartment Temperature Y90 F (3) That (F) Loop 1 99 F S/G A COMPARTMENT Humidity T55 % Loop 2 T50 F (16) S/G B Compartment Temperature 272 F (2) Tcold (F) Loop 1A UT- F l S/G B Humidity TUU % Loop 2A UT F j (16) Dome Temperature IUU F Loop IB NT F (11) SIRW Tank Level BT % Loop 2B UT F (15) WR Containment Pressure (R) T5 psia (5) Subcooling TU6 F 12 PSIA , i (14) Containment Sump Level 591 % (7) PCS WR Pressure (R) IF PSIF (14) Containment Water Level (R) 595 % (7) PCS NR Pressure (R) II PSIA  :

(22) SI Tank Level.(%) (30) S/G A LEVEL WR U-  %  !

A 41 B 41 C 41 - D 41-- (30) S/G A LEVEL (R) U  % SI TanFPressure7psig) (30) S/G A PRESS T psia A 232 B 232 C 232 D 228 S/G A STM FLW (R) U X10**6 PPH + (21) SIAS ATarm NO

                                             -                                    S/G A FD FLW (R)           U    X10**6 PPH l                                                                          (30) S/G B LEVEL WR                U    %

C-12 (30) S/G B LEVEL.(R) U  %

(30) S/G B PRESS T4 psia Concentrated Boric Acid Tank Levels S/G B STM FLW (R)l U- - X10**6 PPH T53A 100  % S/G B FD FLW (R) U X10**6 PPH T53B- TUU  %

Reactor Vessel DP E I- psid P!YEL K-13 l (12) PORV Discharge Temperature TTI F (13) Pzr Safety Valve Discharge Temp (F) (20) CONTAINMENT HIGH PRESS RV-1039 127 F NO RV-1040 IT2 F RV-1041 177 F (20) Containment High Radiation ,

j YES

O O O SHAVPAL1 T S^C STATUS PAGE PALEX 94 Time 1215 Scenario Time 0345 Message # 24 141 Time Jump Scenario Time Jump C-01 C-04 MFP Suction Pressure 15 psig (32) D/G Freq 1-1 0 1-2 60 MFP A Discharge Pressure 15 psig (32) 1-C BUS VOLTS 0 Amps 0 MFP_ B Discharge Pressure 15 psig (32) 1-D BUS VOLTS 2330 Amps 0 AFW Pump P-8C Amperes O AMPS AFW Discharge Pressure P-8C 18 psig C-11 BACK C-11A AFW Pump P-8A Amperes o AMPS AFW Pump P-8B Steam Pressure O psig (17) Containment Area Monitors AFW Discharge Pressure P-8A & P-8B 18 psig RIA-1805  ??? R/Hr Moisture SEP Drain Tank Level 14  % RIA-1806  ??? R/Hr Condensor Hotwell Level 82  % RIA-1807  ??? R/Hr Condensor vacuum o in Hg. RIA-1808  ??? R/Hr Gland Seal Condensor Vacuum 14.2 in Hg. (17) High Range Containment Monitors Atmospheric Dump _ Valves CLOSED RIA-2321 .1E+04 R/Hr AFW Pump P-8A OFF P-8B OFF P-8C OFF RIA-2322 .1E+04 R/Hr Heater Drain Pump P-10A OFF P-10B OFF (19) Containment Hydrogen Concentration Condensate Pump P-2A OFF P-2B OFF AI-2401R 0  % AI-2401L 0  % C-11 (30) Main Steam Line Gamma RIA-2324 .23E+02 CPM (31) AFW FLOW TO SGA RIA-2323 .25E+02 CPM FROM P8A, BO From P-8C 0 gpm (31) AFW FLOW TO SGB EQUIPMENT STATUS: FROM P-8A&B O_ From P-8C 0 gpm Condensor Vacuum (R) 0 IN HG. 1. SIGNIFICANT EQUIP OUTAGES PCP A Leak-off Flow (R) 0 (INOPERABLE EQUIPMENT) PCP B Leak-off Flow (R) 0 2. SURVEILLANCE DUE/ PROGRESS PCP C Leak-off Flow (R) O 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off Flow-(R) 0 OR OUTAGES 4 i i _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ ___m _

n d b,~ b SHAVPAll TSC STATUS PAGE PALEX 94 Time 1215 Scenario Time 0345 Message # 24 142 Time Jump Scenario Time Jump C-08 C-02 SW Pumps P-7A ON P-7B 0FF P-70 ON (10) VCT Temp 69 F CCW Pumps P-52A DFF P-528 UF P-52C DFF (10) VCT Pressure 2T psi FPC Pumps P-51A UTF P-51B DTF (10) VCT Level 5T  % PCP Control Bleedoff Pressure U psig CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow D~ gpm (26) Charging Flow U gpm VIA ON V2A ON V3A ON V4A 0FF (9) Quench Tank Temp 101 F VlB UN

          -      V2B UN-      V3B UH-     V4B UFF                (9) Quench TANK Pressure                      U-~     psig (9) Quench TANK Level                        63      %

C-03 (7) Pressurizer Pressure (R) U psia (8) PZR Level (R) LT0102A U  % (23) HPSI Pumps P-66A 0FF P-66B 0FF LT0103 7  % (25) LPSI Pumps P-67A DFF P-678 DTF (12) PORV PRV-1042A CLOSED 1043B LTOSED (18) Containment Spray Pumps (12) BLOCK MOV-1042A OPEN 1043A OPEN P-54A 0FF P-54B 0FF P-54C OFF CHARGING PUMPS (27) HPSIA, LPSIA 5 PRAY A SUCTION P55A 0FF P55B 0FF P55C 0FF CV-3057 (SIRWT) CV-3030 (Sump) (6) PCPS P50A DFF P50B UFF P50C UFF P500 0FF CLOSED CLOSED PZR HTR AMPS LC15 0 LCC 16 D-(1) PCS TAVE (R) LOOPl-(TR-Olll) 55 F LOOP 2 (TR-0121) 55 F C-02 (25) REACTOR POWER LEVEL , nil .14E+03 cps N13 .13E-06 % NI7. 14E-06  % i Intermediate Press Letdown Temp 104 F NI2 .13E+03 cps NI4 .12E-06 % NI8 .15E-06 % i Charging Line Temperature IDY F NI-05 .14E-06  % NI-09 ! Letdown Line Temp TUT F NI-06 .14E-06  % NI-10 l SDCS from PCS (R) TDZ F SDCS to PCS (R) 9T F PIP l (DEMAND LOG + CONSTANT- ROD, OR FLUX / TEMP) Gross MW 0 Net MW D (28) Control Rod Position

GP1 0 GP2 0 GP3 0-GP4 0-l GP6(A) U GP7(B) U l Stuck Rods RONE <optiona1># 0 Core Exit Temp U F i

V SHAVPAll TSC STATUS PAGE PALEX 94 Time 1230 Scenario Time 0400 Message # 25 140 Time Jump Scenario Time Jump C-13 C-12 PCP Current (Amps) Condensate Storage Tank Level T-2 86  % P-50A 0 P-508 0 Instrument Air Pressure M4 psig P-50C U P-50D D (15) Containment Building Pressure F - psig (6) PCS Flow - (16) S/G A Compartment Temperature 290 F (3) Thot (F) Loop 1 99 F S/G A COMPARTMENT Humidity IUU % Loop 2 E0 F (16) S/G B Compartment Temperature 292 F (2) Tcold (F) Loop 1A 9F F S/G B Humidity IUU % Loop 2A DT F (16) Dome Temperature IUU F Loop 1B 9T F (11) SIRW Tank Level BT  % Loop 2B 9T F (15) WR Containment Pressure (R) T5 psia (5) Subcooling TU6 F 12 PSIA (14) Containment Sump Level 591 % (7) PCS WR Pressure (R) IT PSIX-(14) Containment Water Level (R) 595 % (7) PCS NR Pressure (R) TI PSIA (22) SI Tank Level (%) (30) S/G A LEVEL WR D-  % A 41 8 41 C 41

                                 -         D 41-               (30) S/G A LEVEL (R)         U     %

SI TanF Pressure Tpsig) (30) S/G A PRESS T psia A 232 B 232 C 232 0 228 S/G A STM FLW (R) U X10**6 PPH (21) SIAS Alarm NO

                                      --                             S/G A FD FLW (Ri       U     X10**6 PPH (30) S/G B LEVEL WR          U     %

C-12 (30) S/G B LEVEL (R) U  % (30) S/G B PRESS T4 psia Concentrated Boric Acid Tank Levels _ S/G B STM FLW (R) F X10**6 PPH T53A 100  % ' S/G B FD FLW (R) U X10**6 PPH T53B TUU  % Reactor Vessel DP B~I psid PANEL K-13 (12) PORV Discharge Temperature TTI F (13) Pzr Safety Valve Discharge Temp (F) (20) CONTAINMENT HIGH PRESS RV-1039 127 F NO

                                                                                            --~

RV-1040 T42 F RV-1041 T77 F (20) Containment High Radiation YES

p\ SHAVPAL1 TSC STATUS PAGE PALEX 94 Time 1230 Scenario Time 0400 Message # 25 141 Time Jump Scenario Time Jump

                                                                                                                                   -~

C-01 C-04 MFP Suction Pressure 15 psig (32) D/G Freq 1-1 0 1-2 60 MFP A Discharge Pressure 15 psig (32) 1-C BUS VOLTS O Amps 0 MFP B Discharge Pressure 15 psig (32) 1-D BUS VOLTS 2330 Amps 0 AFW Pump P-8C Amperes O AMPS AFW Discharge Pressure P-8C 18 psig C-11 BACK C-11A AFW Pump P-8A Amperes O AMPS AFW Pump P-8B Steam Pressure O psig (17) Containment Area Monitors AFW Discharge Pressure P-8A & P-8B 18 psig RIA-1805  ??? R/Hr Moisture SEP Drain Tank Level 14  % RIA-1806  ??? R/Hr Condensor Hotwell Level 82  % RIA-1807  ??? R/Hr Condensor Vacuum o in Hg. RIA-1808  ??? R/Hr Gland Seal Condensor Vacuum 14.2 in Hg. (17) High Range Containment Monitors Atmospheric Dump Valves CLOSED RIA-2321 .1E+04 R/Hr AFW Pump P-8A OFF P-8B OFF P-8C OFF RIA-2322 .1E+04 R/Hr Heater Drain Pump P-10A OFF P-10B OFF (19) Containment Hydrogen Concentration Condensate Pump P-2A OFF P-2B OFF AI-2401R 0  % AI-2401L 0  % C-11 (30) Main Steam Line Gamma RIA-2324 .23E+02 CPM (31) AFW FLOW TO SGA RIA-2323 .25E+02 CPM FROM P8A, B0 From P-8C 0 gpm (31) AFW FLOW TO SGB EQUIPMENT STATUS: FROM P-8A&B 0 From P-8C 0 gpm Condensor Vacuum (R) 0 IN HG. 1. SIGNIFICANT EQUIP OUTAGES PCP A Leak-of f Flow (R) 0 (INOPERABLE EQUIPMENT) PCP B Leak-off Flow (R) 0 2. SURVEILLANCE DUE/ PROGRESS PCP C Leak-off Flow (R) 0 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off Flow (R) O OR OUTAGES

O O O SHAVPAtl TSC STATUS PAGE PALEX 94

;            Time 1230                 Scenario Time 0400              Message # 25-                         142                           :

Time Jump Scenario Time Jump C-08 C-02 SW Pumps P-7A ON P-78 0FF P-7C ON (10) VCT Temp 69 F CCW Pumps P-52A UFF P-528 DN~ P-52C DFF (10) VCT Pressure IT psi - FPC Pumps P-51A DFF P-518 UTF (10) VCT Level ET  % PCP Control Bleedoff Pressure TI psig CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow T gpm (26) Charging Flow 0 gpm VIA ON V2A ON V3A ON V4A 0FF (9) Quench Tank Temp 101 F VIB UN- V2B UN~~ V3B UN~ V4B DFF (9) Quench TANK Pressure D- psig (9) Quench TANK Level 53  % C-03 (7) Pressurizer Pressure (R) II psia (8) PZR Level (R) LT0102A 'T  %  ; (23) HPSI Pumps P-66A 0FF P-66B 0FF LT0103 ~I % ' (25) LPSI Pumps P-67A UFF P-67B DTF (12) PORV PRV-1042A CLOSED 10438 LTOSED (18) Containment Spray Pumps (12) BLOCK MOV-1042A OPEN 1043A OPEN i , P-54A 0FF P-548 0FF P-54C 0FF CHARGING PUMPS  : (27) HPSIA, LPSIA-~3 PRAY A SUCTION P55A 0FF P55B 0FF P55C OFF  : 1 CV-3057 (SIRWT) CV-3030 (Sump) (6) PCPS P50A UFF P508 UFF P50C DFF P500 0FF r

                      -CLOSED                  CLOSED                        PZR HTR AMPS     LC15 0         LCC 16 D-(1) PCS TAVE (R)        LOOP 1-(TR-0111)        95      F LOOP 2 (TR-0121)        95
                                                                                                                      ~~

F

.                            C-02                                   (25) REACTOR POWER LEVEL nil .14E+03        cps    NI3 .13E-06       %     NI7. 14E-06     %

Intermediate Press Letdowr Temp 104 F NI2 .13E+03 cps NI4 .12E-06  % NI8 .15E-06  % Charging Line Temperature IUZ F NI-05 .14E-06  % NI-09 , l Letdown Line Temp TUT F NI-06 .14E-06  % NI-10 t SDCS from PCS (R) IUZ F SDCS to PCS (R) --UT~ F PIP (DEMAND LOG + CONSTANT 3 0D, OR FLUX / TEMP) Gross MW 0 ' Net MW D (28) Control Rod PositTon l GP1 0 GP2 0 GP3 0 GP4 0-l GP6(A) U GP7(B) U Stuck Rods NONE < optional ># 0 Core Exit Temp 5 F , t

b SHAVPAll TSC STATUS PAGE PALEX 94 Time 1245 Scenario Time 0415 Message # 26 140 Time Jump Scenario Time Jump C-13 C-12 PCP Current (Amps) Condensate Storage Tank Level T-2 86 % P-50A 0 P-50B 0 Instrument Air Pressure 154 psig P-50C P-500 D (15) Containment Building Pressure U-- psig (6) PCS Flow -D - (16) S/G A Compartment Temperature 290 F (3) Thot (F) Loop 1 99 F S/G A COMPARTMENT Humidity TUU % toop 2 TUO F (16) S/G B Compartment Temperature 292 F (2) Tcold (F) Loop 1A 91 F S/G B Humidity TUU % Loop 2A 9T F (16) Dome Temperature 3UU F Loop IB UT F (11) SIRW Tank Level BT  % toop 2B 9T F (15) WR Containment Pressure (R) 13 psia (5) Subcooling IU6 F 12 PSIA (14) Containment Sump Level 591 % (7) PCS WR Pressure (R) 13- PSIX~ (14) Containment Water Level (R) 595 % (7) PCS NR Pressure (R) TI PSIA (22) SI Tank Level (%) (30) S/G A LEVEL WR D-  % A 41 8 41 C 41 U

                                 -        D 41~~              (30) S/G A LEVEL (R)               %

SI Tanli Pressure 7psig) (30) S/G A PRESS T psia A 232 B 232 C 232 D 228 D X10**6 PPH S/G A STM FLW (R) (21) SIAS ATirm NO

                                     --                             S/G A FD FLW (R)       U     X10**6 PPH (30) S/G B LEVEL WR          U     %

C-12 (30) S/G B LEVEL (R) U  % (30) S/G B PRESS T4 psia Concentrated Boric Acid Tank Levels S/G B STM FLW (R) D~ X10**6 PPH T53A 100  % S/G B FD FLW (R) U X10**6 PPH T53B TUU  % Reactor Vessel DP B~3 psid PANEL K-13 (12) PORV Discharge Temperature III F (13) Pzr Safety Valve Discharge Temp (F) (20) CONTAINMENT llIGH PRESS RV-1039 127 F NO RV-1040 TTZ F

                                                                                           ~

RV-1041 T77 F (20) Containment High Radiation YES

O O O l

I SHAVPAL1 TSC STATUS PAGE  ! PALEX 94 ! i

                                                                                                                           \

i

Time 1245 Scenario Time 0415 Message # 26-- 141 i Time Jump Scenario Time Jump ,

C-01 C-04  ; t

MFP Suction Pressure 15 psig (32) D/G Freq 1-1 0 1-2 60

MFP A Discharge Pressure 15 psig (32) 1-C BUS VOLTS O Amps 0 ,

MFP B Discharge Pressure 15 psig (32) 1-D BUS VOLTS 2330 Amps 0  ! , AFW Pump P-8C Amperes O_ AMPS ' l

  .AFW Discharge Pressure P-8C                          18      psig                        C-11 BACK    C-11A            t

AFW Pump P-8A Amperes O AMPS  ;

AFW Pump P-8B Steam Pressure O psig (17) Containment Area Monitors

AFW Discharge Pressure P-8A & P-8B 18 psig RIA-1805  ??? R/Hr ,

Moisture SEP Drain Tank Level 14  % RIA-1806  ??? R/Hr 6 Condensor Hotwell Level 82  % RIA-1807  ??? R/Hr i 1 Condensor Vacuum o in Hg. RIA-1808  ??? R/Hr  ! l Gland Seal Condensor Vacuum 14.2 in Hg. (17) High Range Containment Monitors i I Atmospheric Dump Valves CLOSED RIA-2321 .1E+04 R/Hr >

AFW Pump. P-8A OFF P-8B OFF P-8C OFF RIA-2322 .1E+04 R/Hr t i Heater' Drain Pump P-10A OFF P-10B OFF (19) Containment Hydrogen Concentration 1

Condensate Pump P-2A OFF P-2B OFF AI-2401R 0  %' ' AI-2401L 0  % C-11 (30) Main Steam Line Gamma , RIA-2324 .23E+02 CPM I (31) AFW FLOW TO SGA RIA-2323 .2SE+02 CPM FROM P8A, B0 From P-8C 0 gpm j ! (31) . AFW FLOW TO SGB EQUIPMENT STATUS: FROM P-8A&B 0 From P-8C 0 gpm i Condensor Vacuum (R) 0 IN HG. 1. SIGNIFICANT_ EQUIP OUTAGES PCP A Leak-off Flow (R) 0 (INOPERABLE EQUIPMENT) l PCP B Leak-off Flow (R) 0 2. SURVEILLANCE DUE/ PROGRESS PCP C Leak-off Flow (R) O 3. ABNORMAL ELECTRICAL' LINEUPS . 1 PCP D Leak-off Flow (R) 0 OR OUTAGES  ! ! i 1 I 1  ! 1

O O O SHAVPAll TSC STATUS PAGE PALEX 94 Time 1245 Scenario Time 0415 Message # 26 142 Time Jump Scenario Time Jump C-08 C-02 l' SW Pumps P-7A ON P-78 0FF P-7C ON (10) VCT Temp 69 F CCW Pumps P-52A DFF P-528 UR- P-52C UFF (10) VCT Pressure H psi FPC Pumps P-51A UFF P-518 UFF (10) VCT Level 54  % i PCP Control Bleedoff Pressure U psig CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow D~ gpm i (26) Charging Flow U gpm VIA ON V2A ON V3A ON V4A 0FF (9) Quench Tank Temp Tol F VlB DR V2B DR - V3B UN-- V4B UFF (9) Quench TANK Pressure U-- psig (9) Quench TANK Level 53  % C-03 (7) Pressurizer Pressure (R) U psia i (8) PZR Level (R) LT0102A U  %

(23) HPSI Pumps P-66A 0FF P-66B 0FF LT0103 3  %

(25) LPSI Pumps P-67A UFF P-67B DFF (12) PORV PRV-1042A CLOSED 10438 LTOSED

!                                     (18) Containment Spray Pumps                                                          (12) BLOCK        MOV-1042A OPEN        1043A OPEN P-54A 0FF P-54B 0FF P-54C OFF                                                 CHARGING PUMPS (27) HPSIA, LPSIA N PRAY A SUCTION                                                                      P55A 0FF P55B 0FF P55C 0FF CV-3057 (SIRWT)                  CV-3030 (Sump)                       (6) PCPS        P50A DFF P508 UTF P50C DFF P50D OFF i                                                         CLOSED                           CLOSED                                     PZR HTR AMPS    LCIS 0        LCC 16 D-(1) PCS TAVE (R)        LOOPI-(TR-0Ill)       95     F LOOP 2 (TR-0121)      95     F

, C-02 (25) REACTOR POWER LEVEL nil .14E+03 cps NI3 .13E-06  % NI7 .14E-06  %

                                     . Intermediate Press Letdown Temp                                     104 F                NI2 .13E+03      cps   NI4 .12E-06       %    NI8 .15E-06   %

) Charging Line Temperature RY F NI-05 .14E-06  % NI-09 i Letdown Line Temp IUT F NI-06 .14E-06  % NI-10 ' i

• SDCS from PCS (R) TDY F .

SDCS to PCS (R) -91 F PIP l'

'                                                                                                                             (DEMAND LOG + CONSTANT 3 0D, OR FLUX / TEMP)

Gross MW 0 Net MW U (28) Control Rod PositTon  : GPl O GP2 0 GP3 0- GP4 0-GP6(A) U GP7(B) 5  ! Stuck Rods NONE < optional ># 0  ; Core Exit Temp 5 F

O O O SHAVPALI TSC STATUS PAGE PALEX 94 Time 1245 Scenario Time 0415+ Message # 27 -- 140 , Time Jump 3 DAYS Scenario Time Jump 75T5-C-13 C-12  :

PCP Current (Amps) 1 Condensate Storage Tank Level T-2 85  % P-50A 0 P-50B 0 Instrument Air Pressure Y5 psig P-50C D P-500 D l (15) Containment Building Pressure 5 2 psig (6) PCS Flow (16) S/G A Compartment Temperature T4T F (3) Thot (F) Loop 1 202 F  ;

S/G A COMPARTMENT Humidity IUU % toop 2 TU F ' l (16) S/G B Compartment Temperature T45 F (2) Tcold (F) Loop IA T52 F S/G B Humidity TUU % Loop 2A T77 F  ! (16) Dome Temperature TEU F Loop IB T5T F - (11) SIRW Tank Level F% Loop 28 TU F  ; i (15) WR Containment Pressure (R) T5 psia (5) Subcooling 51- F 22 PSIA i (14) Containment Sump Level 591 % (7) PCS WR Pressure (R) T.T PSIA ~ ' l (14) Containment Water Level (R) 595 % (7) PCS NR Pressure (R) U PSIA i (22) SI Tank Level (%) (30) S/G A LEVEL WR D-  % A 41 B 41 C 41 0 41- (30) S/G A LEVEL (R) U  % i SI TanFPressure {psig) (30) S/G A PRESS T psia

A 231 B 231 C 231 0 227 S/G A STM FLW (R) U X10**6 Fd (21) SIAS Alarm -

NO S/G A FD FLW (R) U X10**6 PPH ' j (30) S/G B LEVEL WR U  % C-12 (30) S/G B LEVEL (R) U  %  ; (30) S/G B PRESS T4 psia l Concentrated Boric Acid Tank Levels S/G B STM FLW (R) 5- X10**6 PPH  ! l T53A 40  % S/G B FD FLW (R) D X10**6 PPH i T53B D-  % , l Reactor Vessel DP H.3 psid PANEL K-13 (12) PORY Discharge Temperature T5T F I l (13) Pzr Safety Valve Discharge Temp (F) (20) CONTAINMENT HIGH PRESS t RV-1039 128 F NO RV-1040 TU F RV-1041 175 F (20) Containment High Radiation

• YES ,

l l l i

O O O SHAVPAL1 TSC STATUS PAGE PALEX 94 Time 1245 Scenario Time 0415+ Message # 27 141 Time Jump 3 DAYS Scenario Time Jump 7615 C-01 C-04 MFP Suction Pressure 15 psig (32) D/G Freq 1-1 0 1-2 0 MFP A Discharge Pressure 15 psig (32) 1-C BUS VOLTS 2458 Amps 266 MFP B Discharge Pressure 15 psig (32) 1-D BUS VOLTS 2449 Amps 345 AFW Pump P-8C Amperes O AMPS AFW Discharge Pressure P-8C 18 psig C-11 BACK C-11A AFW Purip P-8A Amperes O AMPS AFW Pump P-8B Steam Pressure O psig (17) Containment Area Monitors AFW Discharge Pressure P-8A & P-8B 18 psig RIA-1805  ??? R/Hr Moisture SEP Drain Tank Level 14  % RIA-1806  ??? R/Hr Condensor Hotwell Level 87  % RIA-1807  ??? R/Hr Condensor Vacuum o in Hg. RIA-1808  ??? R/Hr Gland Seal Condensor Vacuum o in Hg. (17) High Range Containment Monitors Atmospheric Dump Valves CLOSED RIA-2321 .8E+03 R/Hr AFW Pump P-8A OFF P-8B OFF P-8C OFF RIA-2322 .8E+03 R/Hr Heater Drain Pump P-10A OFF P-10B OFF (19) Containment Hydrogen Concentration Condensate Pump P-2A OFF P-2B OIF AI-2401R 0  % AI-2401L 0  % C-11 (30) Main Steam Line Gamma RIA-2324 .23E+02 CPM (31) AFW FLOW TO SGA RIA-2323 .25E+02 CPM FROM P8A, B0 From P-8C 0 gpm (31) AFW FLOW TO SGB EQUIPMENT STATUS: FROM P-8A&B 0 From P-8C 0 gpm Condensor Vacuum (R) 0 IN HG. 1. SIGNIFICANT EQUIP OUTAGES PCP A Leak-off Flow (R) 0 (INOPERABLE EQUIPMENT) PCP B Leak-off Flow (R) 0 2. SURVEILLANCE DUE/ PROGRESS PCP C Leak-off Flow (R) 0 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off Flow (R) 0 OR OUTAGES I

O O O SHAVPALI TSC STATUS PAGE PALEX 94 Time 1245 Scenario Time 0415+ Message # 27 142 Time Jump 3 DAYS Scenario Time Jump 7515~ - C-08 C-02 SW Pumps P-7A ON P-7B 0FF P-7C Ott (10) VCT 77 69 F CCW Pumps P-52A DFF P-528 UN~ P-52C DR

                                                                                                                  -              (10) VCT Pressure                           YT     psi FPC Pumps P-51A DN-          -

P-51B DTF (10) VC1 Level M  % PCP Control Bleedoff Pressure II psig CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow D~ gpm (26) Charging Flow U gpm VIA ON V2A ON V3A ON V4A ON (9) Quench Tank Temp T41 F VIB DR V2B DR

                                                                                      --       V3B UN-     V4B UN
                                                                                                               -                  (9) Quench TAf!K Pressure                  O      psig (9) Quench TANK Level                      53     %

C-03 M psia (7) Pressurizer Pressure (R) (8) PZR Level (R) LT0102A U- % (23) HPSI Pumps P-66A 0FF P-66B 0FF LT0103 77.9 % (25) LPSI Pumps P-67A DTF P-67B DN~~- (12) PORY PRV-1042A OPEN 1043B DTEN (18) Containment Spray Pumps (12) BLOCK MOV-1042A 07ER 1043A DFEN P-54A 0FF P-54B 0FF P-54C 0FF CHARGING PUMPS (27) HPSIA, LPSIA 5 PRAY A SUCTION P55A 0FF P55B 0FF F55C 0FF CV-3057 (SIRWT) CV-3030 (Sump) (6) PCPS P50A DTF P508 UTF P50C DFF P500 0FF CLOSED CLOSED PZR HTR AMPS LC15 0 LCC 16 U-(1) PCS TAVE (R) LOOPl-(TR-0111) T99 F LOOP 2 (TR-0121) 755 F C-02 (25) REACTOR POWER LEVEL nil .29E+02 cps NI3 .19E-07  % NI7. 24E-07 % Intermediate Press Letdown Temp 104 F NI2 .28E+02 cps NI4 .18E-07  % NI8 .24E-07 % Charging Line Temperature TM F NI-05 .23E-07  % NI-09 Letdown Line Temp IM F NI-05 .24E-07  % NI-10 SOCS from PCS (R) IDU F SOCS to PCS (R) IEU F PIP (DEMAND LOG + CONSTANT ROD, OR FLUX / TEMP) Gross MW 0 Net MW D (28) Control Rod Position GP1 0 GP2 0 CP3 0~ GP4 0~ U Stuck Rods U GP7(B) GP6(A) ~ K?Pr

                                                                                                                                                                    < optional >f 0 Core Exit Temp                             _U     F

m. - . Am - ._a. - _.. _ .m_ _ a., _,,a O

CFMS RADIATION DATA O O  ; 1

S r(ARIO TIME: 00OO LJ RADIOL 0u CAL NY RIA-2326 [3 O CPH TIME: 4 730 RIA-2327 - 2 MR/liR FUEL HANDLI!!G AREAS LIQUID RADIATI0tt M0fitTORS HON 1 005 HR/llR BACKUP STACK HON 2 OOJ HR/IIR RIA-2318 OOI CPH

• COMPONENT COOLING WATER 0915 RIA-2319 OOS CPM

       /EO        CPM a

SERVICE WATER CONTAINHENT ISOLATION - CONTROL ROCH RAD f00 CPM RIA-1805 ,02[ R/HR RADWASTE DISCl!G RIA-1806 , o/f R/IIR COND OFF GAS 1049 7 70 CPH RIA-1807 .o2 R/HR 12 2 CPM STM GEN BLOWDOWil RIA-1808 . o /[ R/IIR *RADWASTE PLENUM 1410 CPM HI RANGE L / R/HR /d O CPM

• HIXING BASIN HI RANGE R I R/HR *EESG RAD 1323 y

      /20          CPH                                                                   /20                                                       CPH

• FAILED FUEL DIRTY WASTE DRAIN TANKS *WESG RAD 02028 -

          /0       CPM       T-60W L          60       %

YOO CPH HAIN STEAM A 2324 T-60E L 80  % RADWASTE VENT

                                                               ^

23 CPM /[ CpH HAIN STEAM B 2323 SFP NORTH 2f CPM 5709 . 77 HR/liR

• DECADE DEPENDENT SFP SOUTil ON CR SWITCil POSITION 2313 .f2 HR/HR

         ~

p (n) SCtHARio TIME: 60/[ (e o RADIOL 0titCAL RIA-2326 bO CPH TIME: /)fe/f RIA-2327 -2 MR/IIR FUEL llAliDLING AREAS LIQUID RADIATION MONITORS H0ft 1 005 MR/IIR BACKUP STACK MGft 2 OOJ HR/IIR RIA-2318 COS CPM

• COMPONENT COOLING I WATER 0915 RIA-2319 COS CPM

        /50        CPM u

SERVICE WATER CONTAINHENT ISOLATION - CONTROL R00H RAD 4oO CPM RIA-1805 , C2 f R/IM RADWASTE DISCitG RIA-1806 ,O/f R/llR COND OFF GAS

         ?70       CPM       RIA-1807      .O2              R/flR                       122.       CPM STH GEN BLOWDOWN           RIA-1808      , O/[            R/HR          *RADWASTE PLENUM
       / e/ID      CPH       HI RANGE L          I          R/IIR                       /4 O        CPM
*HIXING BASIN                HI RANGE R          /          R/IIR            *EESG RAD 1323 y

120 CPH l2O CPM

                                                                     ~

• FAILED FUEL DIRTY WASTE DRAIN TANKS *WESG RAD 0202B

          /0       CPM           T-60W L           60         %                          YOO        CPH HAIN STEAM A 2324              T-60E L           SO         %            RADWASTE VENT
                                                                      ^

23 CPH I f CPH HAIN STEAM B 2323 SFP NORTil 2[ CPH 5709 .M HR/flR

• DECADE DEPENDENT SFP SOUTil DN CR SWITCll POSITION 2313 82 HR/flR

4;; f**

       .A        A                                                                                            (O e%

vg. a% p \\ eA. IMAGE EVALUATION 4/f

      .1,[*

f'

                                                                                                               / q'fi

\ qp!!* TEST TARGET (MT-3) ff N

 %9   W 4,           f                                                                                 /4<u4h w:w u H! 9 23   L --

[; n 1S 2p, j,l J. 3 h m-2 4 1.8 I! IEis 1.25 1.4 1 m ws: l w.6 t a

                                                                            -150mm

• 6" -

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i TEST TARGET (MT-3) k/ f. O's ' / hf q { l.0 -

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NARIO TIME: Od30 RADIO (ItilCAL RIA-2326 SO CP TIME: O900 RIA-2327 2 MR/llR FUEL llANDLING AREAS LIQUID RADIATION MONITORS HON 1 OO$ HR/llR BACKUP STACK HON 2 OOJ HR/IIR RIA-2318 OOS CPM

• COMPONENT COOLING WATER 0915 150 CPM RIA-2319 00J CPM a .

SERVICE WATER CONTAINHENT ISOLATION - CONTROL R00H RAD 4oO CPM RIA-1805 . 02f R/IIR RA0 WASTE DISCllG RIA-1806 .dif R/IIR COND OFF GAS 1049 770 CPM RIA-1807 .02 R/llR I22 CPM STH GEN BLOWDOWil RIA-1808 , Dlf R/HR 0707 *RADWASTE PLENUM l'lIO CPH 111 RANGE L I R/HR /4 O CPM

• HIXING BASIN 111 RAN6c R I R/ilR *EESG RAD 1323

     /20           CPH
                                                                               /20        CPM

• FAILED FUEL DIRTY WASTE DRAIN TANKS *WESG RAD 0202B

         /0        CPM      T-60W L           IO       %                        YOO        CPH HAIN STEAM A 2324          T-60E L         80         %           RADWASTE VENT 23         CPM
                                                                                 /[        CPM MAIN STEAM B 2323 2[          CPH SFP NORTH 5709       28    HR/IIR

• DECADE DEPEftDENT SFP SOUTil ON CR SWITCll POSITION 2313 .I2 HR/HR

() ,y (' L.o.ARIO TIME: 00'/I RADIOL tilCAL RIA-2326 6O V CPM TIME: dil[ RIA-2327 2 FUEL llANDLING AREAS MR/ilR LIQUID RADIATION HONITORS HON 1 OO5 MR/llR BACKUP STACK

• COMPONENT C0dLING WATER 0915

                                                                            /CO            CPH RIA-2319    DOS       CPM a ,

SERVICE WATER CONTAINMENT ISOLATION - CONTROL ROOM RAD 4oO CPM RIA-1805 .02.5' R/HR RADWASTE DIScilG RIA-1806 .O/f 1049 R/IIR COND OFF GAS 7 ~70 CPM RIA-1807 .O2 R/ilR /22 CPM STH GEN BLOWDOWN RIA-1808 .O/f R/IIR *RADWASTE PLENUM l'/ /0 CPM HI RANGE L I R/ilR /6 O CPM

                                             *HIXIllG BASIN                                                       111 RANGE R             I 1323                                                                                        R/liR            *EESG RAD
                                                                          /20              CPM
                                                                                                                                                                               /2O        CPM

• FAILED FUEL DIRTY WASTE DRAIN TANKS *WESG RAD 02028

                                                                              /0                                                            IO CPM V00 T-60W L                        %                                     CPn HAIN STEAM A 2324                                                T-60E L               80       %             RADWASTE VENT 23            CPn                                                                ^
                                                                                                                                                                                 /5 Cry MAIN STEAM B 2323                                                                                                                          _

2f CPM SFP NORTil 5709 28 HR/ilR

• DECADE DEPENDENT DN CR SWITCil POSITION SFP SOUTil 2313 *M HR/HR

9tNARIOTIME: d/OO O RADIOLou1 CAL RIA-2326 dO O CPM A TIME: 0930 RIA-2327 ,R FUEL HANDLING AREAS HR/IIR 1 4010 RADIATION HONITORS HON 1 00$ HR/HR BACKUP STACK HON 2 OOJ MR/HR RIA-2318 COS CPM

• COMPONENT COOLING WATER 0915

                      /50          CPM RIA-2319     DOS            CPM L

SERVICE WATER CONTAINHENT ISOLATION - CONTROL R00H RAD 4OO CPM RIA-1805 ,C2f R/HR l RADWASTE DIStilG 1049 RIA-1806 . O /f R/HR COND CFF GAS

                       ?70      _ CPM       RIA-1807      ,O2             R/HR                        I22          CPM      i STM GEN BLOWDOWN           RIA-1808      . O/[           R/HR       *RADWASTE PLENUM 0707
                     / *llo        CPM      HI RANGE L         I          R/HR                        /d O          CPM
          *HIXING BASIN                     HI RANGE R        I           R/HR           *EESG RAD                          f 1323

, /20 CPM

                                                                                                      /2O           CPM i

• FAILED FUEL DIRTY WASTE DRAIN TANKS 02028 *WESG RAD

                        /0         CPR          T-60W L          IO        %

YOO CPM HAiN STEAR A 2324 T-60E L 80  % RADWASTE VENT i 23 CPR IE CPM MAIN STEAM B 2323 2( CPR SFP NORTH 5709 .28 HR/HR t

• DECADE DEPENDENT ON CR SWITCH POSITION SFP SOUTH 2313 . S.R HR/HR t i

O O//5 O O kiENARIOTIME: RADIOLOGICAL RIA-2326 90 CPM TIME: ON[ f RIA-2327 ,2 HR/IIR FUEL llANDLING AREAS LIQUID RADIATION H0tilTORS Hort 1 005 HR/IIR BACKUP STACK HCN 2 OOJ HR/llR RIA-2318 COS CPH

• COMP 0! LENT COOLING WATER 0915 RIA-2319 DOS CPM

         /EO           CPM t

SERVICE WATER CONTAINHENT ISOLATION - CONTROL R00H RAD 0833 _ HON -/ HR/llR 400 CPM RIA-1805 ,026 R/ilR RA0 WASTE DIScilG RIA-1806 .O/[ R/ilR COND OFF GAS 970 CPM RIA-1807 .O2 R/IIR I22, CPH STM GEN BLOWDOWN RIA-1808 ,O/I R/IIR *RADWASTE PLENUM 1410 CPM 111 RANGE L l R/IIR /4 O CPH

  *HIXING BASIN               111 RANGE R       I R/IIR           *EESG RAD 1323 y
        /20            CPM
                                                                                     /20         CPM

• FAILED FUEL DIRTY WASTE DRAIN TANKS *WESG RAD 0202B

           /0 CPM        T-60W L         IO         %

V00 CPH HAIN STEAM A 2324 T-60E L 80  % RADWASTE VENT 23 CPM IS CPH HAIN STEAM B 2323 SFP NORTil 2[ CPM 5709 .28 HR/IIR

• DECADE DEPENDENT SFP SOUTil DN CR SWITCil POSITION 2313 42 HR/IIR

( r L.::ARIO TlHE: O/30 RADIOLuJiCAL RIA-2326 180 CPM TIME: /000 RIA-2327 2 FUEL llANDLING AREAS HR/llR LIQUID RADIATION HONITORS H0N 1 00$ HR/ilR BACKUP STACK

• COMPONENT COOLING HON 2 OOJ HR/ItR RIA-2318 COS CPM WATER 0915

                                               /EC         CPH RIA-2319   COS        CPM t

SERVICE WATER CONTAINMENT ISOLATION - CONTROL ROOM RAD 0833 4oO CPH RIA-180S opp H0N ./ HR/HR I. .. R/ilR RADWASTE DIScilG RIA-1806 f77 R/IIR COND OFF GAS "y'70 CPM RIA-1807 7 R/IIR /22 CPH STM GEN BLOWDOWN RIA-1808 7 R/llR *RADWASTE PLENUM 0707 14/O CPM 111 RANGE L I R/HR /4 O CPM

                                *HIXING BASIN                    lil RANGE R           I 1323                                                           R/IIR          *EESG RAD
                                         /20              CPH  ,
                                                                                                                           /20        CPM

• FAILED FUEL- DIRTY WASTE DRAIN TANKS 0202B *WESG RAD

                                                /D        CPM                             IO l

T-60W L  % YOO CPM HAIN STEAM A 2324 T-60E L 80  % RADWASTE VENT 23 CPM ^

                                                                                                                              /Y       CPM MAIN STEAM B 2323 2[         CPM                                                  SFP NORTH 5709     .MI     HR/IIR

• DECADE DEPENDENT ON CR SWITCil POSITION SFP SOUTil 2313 ,(2 HR/HR l

fm (~T ^'s

 'w]                                      \_)                                                       [O SCtNARIO TIME:     O /4[          RADIOL 0tilCAL                         RIA-2326    /SO        CPM TIME:   /OII                                                  RIA-2327       2       MR/IIR FUEL llANDLING AREAS LIQUID RADIATION MONITORS               HON 1      005        HR/IIR                 BACKUP STACK H0N 2      OOJ        HR/IIR                 RIA-2318    OOS        CPH

• COMPONENT C00LillG -

WATER 0915 RIA-2319 00J CPH

        /f0         CPH u

SERVICE WATER CONTAINHENT ISOLATION - CONTROL ROOM RAD 0833 ,/ 400 CPH RIA-1805 7 77 R/IIR HON HR/llR RADWASTE DISCl!G RIA-1806 R/IIR COND OFF GAS

         ?70        CPM   RIA-1807         f            R/llR                          I22        CPM STM GEN BLOWDOWN       RIA-1808                      R/IIR            *RADWASTE PLElluH 14/O        CPM   HI RANGE L         I           R/llR                         /4 O        CPM
 *HIXING BASIN            111 RANGE R         l          R/IIR               *EESG RAD 1323 4
       /20           CPM                                                               /20         CPH

• FAILED FUEL DIRTY WASTE DRAIN TANKS *WESG RAD 02028 -

          /0         CPM      T-60W L           IO        %

YOO CPM HAIN STEAM A 2324 T-60E L 80  % RADWASTE VENT 23 CPn If ~ Con MAIN STEAH B 2323 SFP NORTH 2[ CPM 5709 .23 HR/HR

• DECADE DEPENDENT SFP SOUTH ON CR SWITCH POSITION 2313 .82 HR/HR l

l -

                                          ,,                                                    ,~

NARIO TIME: O300 RADIOLOGICAL RIA-2326 200 CPM n FUEL llAtt0LillG AREAS LIQUID RADIATI0tt M0tlITORS HON 1 005 MR/IIR BACKUP STACK H0tt 2 OOJ HR/IIR RIA-2318 6OS CPH

• COMPONEllT C00LitlG -

WATER 0915

      /50         CPH RIA-2319    d0f          CPM u

SERVICE WATER CONTAINHENT ISOLATION 0833 00tiTROL R00H RAD 400 CPM RIA-1805 77.p . R/HR HON ,I HR/ilR RADWASTE DISCIIG RIA-1806 R/llR COND OFF GAS 1049

       ?70        CPM   RIA-1807      7??                       y R/llR                     l22         CPit SIM GEN BLOWDOWN       RIA-1808      b               R/ilR       *RADWASTE PLENUM P//0        CPM   111 RANGE L        2          R/IIR                     /4 O         CPM

• HIXING BASIN 1323 111 RANGE R 2 R/llR *EESG RAD

     /20          CPH
                                                                               /2O           CPM

• FAILED FUEL DIRTY WASTE DRAIN TANKS *WESG RAD 0202B

        /0        CPH       T-60W L           IO        %                      #00           CpH HAIN li. 3 A 2324          T-60E L           80        %          RADWASTE VENT 23         CPM CPM MAIN STEAM B 2323 2[          CPM SFP NORTH 5709      .28     HR/IIR

• DECADE DEPENDENT SFP SOUTl1 DN CR SWITCil POSITION 2313 .62 HR/IIR

O ' k htINARIOTIME: 62/[ RADIOL 0IlilCAL - RIA-2326 280 CPM TlHE: /O'1[f RIA-2327 2 HR/l!R FUEL liANDLING AREAA LIQUID RADIATION HONITORS HON 1 005 HR/ilR BACKUP STACK

• COMPONENT COOLING WATER 0915

                                       /50         CPH RIA-2319     dOJ       CPM u

SERVICE WATER CONTAINHENT ISOLATION - CONTROL R00H RAD 400 CPM RIA-1805 2[ R/IIR

                                                                                                                  ~

RADWASTE DIScilG RIA-1806 f R/IIR COND OFF GAS 7 /O CPM RIA-1807 7 R/flR I22 CPH STH GEN BLOWDOWN RIA-1808 R/IIR *RADWASTE PLENUM 0707 l'/10 CPM 111 RANGE L .2O R/IIR

                                                                                                            ~
                                                                                                                    /4 O       CPM
                                *HIXING BASIN 1323 111 RANGE R     20             R/ilR            *EESG RAD
                                      /20          CPM
                                                                                                                    /20        CPM

• FAILED FUEL DIRTY WASTE DRAIN TANKS 02028 *WESG RAD

                                         /0        CPM       T-60W L           IO        %

MOO CPM MAIN STEAM A 2324 T-60E L 80  % RADWASTE VENT 23 CPM l$ CPM MAIN STEAM B 2323 2f CPM SFP NORTil 5709 .28 HR/IIR

• DECADE DEPENDENT ON CR SWITCil POSITION SFP SOUTil 2313 82 HR/IIR

O SCENARIO TIME: O23O O O RADIOLOGICAL. RIA-2326 MOO CPM TIME: //OO RIA-2327 .2 MR/ilR FUEL llANDLING AREAS LIQUID RADIATION MONITORS HON 1 OO5 HR/IIR BACKUP STACK H0N 2 OOJ HR/IIR RIA-2318 d0S CPH

• COMPONENT COOLING WATER 09I5 RIA-2319 COf CPH

             /50          CPM 2.

SERVICE WATER CONTAINHENT ISOLATION - CONTROL R00H RAD 0833 400 CPM RIA-1805 7.pp R/HR H0N ,/ HR/ilR RADb ASTE DIstilG RIA-1806 7? R/IIR COND OFF GAS 970 CPH RIA-1807 ?f R/IIR /22 CPM STH GEN BLOWDOWN RIA-1808 f?7 R/NR *RADWASTE PLENUM

            / 410         CPM  111 RANGE L 380              R/llR                       /4 O       CPM
      *HIXING BASIN            !!! RANGE R NO               R/l!R            *EESG RAD 1323
            /20           CPM
                                                                                        /20        CPM

• FAILED FUEL DIRTY WASTE DRAIN TANKS *WESG RAD 02028 -

! 10 CPM T-60W L EO x 40O CpH HAIN STEAM A 2324 T-60E L 80  % RADWASTE VENT 27 CPM /IO CPM MAIN STEAM B 2323 SFP NORTil l 2[ CPH 5709 3 HR/IIR

• DECADE DEPENDENT SFP SOUTil ON CR SWITCil POSITION 2313 /O HR/llR

                                                    ,~,                                                                                           ,.

su.3RIO TIME: 0-7 8/f RADI0Lts CAL RIA-2326 600 CPM TIME: / / /f FUEL llANDLING AREAS RIA-2327 2 MR/IIR LIQUID RADIATION MONITORS MON 1 005 MR/IIR BACKUP STACK H0N 2 OOJ MR/llR RIA-2318 60S CPM

• COMPONENT COOLING WATER 0915 150 CPM RIA-2319 OOJ CPM n

SERVICE WATER CONTAINMENT ISOLATION - CONTROL ROOM RAD 400 CPM RIA-1805 ?2f R/IIR RADWASTE DIStilG RIA-1806 7 R/liR COND OFF GAS 9 ~70 CPM RIA-1807 2 7 R/IIR I22 CPM STM GEN BLOWDOWN 0707 RIA-1808 fff R/IIR *RADWASTE PLENUM l'/ /O

• CPM  !!! RANGE L 500 R/IIR /4 O CpH
• MIXING BASIN 111 RANGE R 800 R/IIR *EESG RAD 1323

                                                         /20           CPM
                                                                                                                                   /20        CPM

• FAILED FUEL DIRTY WASTE DRAIN TANKS 0202B *WESG RAD

                                                              /0       CPM        T-6CW L        IO        %                        YOO       CPM MAIN STEAM A 2324            T-60E L        80        %           RADWASTE VENT 23         CPM
                                                                                                                                    /500      CPn MAIN STEAM B 2323 2f          CPM SFP NORTil 5709      30     MR/ilR

• DECADE DEPENDENT SFP SOUTil ON CR SWITCil POSITION 2313 /00 HR/IIR

O SCtHARIO TlHE: 6300 O O RADIOL 0ulCAL RIA-2326 /OOO CPM TIME: //30 RIA-2327 2 MR/llR FUEL HANDLING AREAS LIQUID RADIATION HONITORS HON 1 005 HR/IIR BACKUP STACK HON 2 OOJ HR/IIR RIA-2318 OOS CPM

• COMPONENT C00LIllG WATER 0915 RIA-2319 dOJ CPH

                                         /50         CPM a ,

SERVICE WATER CONTAINMENT ISOLATION - CONTROL R00H RAD 0833 ,/ 400 CPM RIA-1805 p7.p R/HR H0N HR/flR RADWASTE DISCllG RIA-1806 7ff R/IIR COND OFF GAS

                                          ?70        CPM   RIA-1807          7         R/IIR                        I22        CPH STH GEN BLOWDOWN        RIA-1808        ff          R/IIR          *RADWASTE PLENUM 14t0         CPM   111 RANGE L     700         R/HR                         /l> O       CPM
                                 *HIXING BASIN             111 RANGE R     700         R/llR             *EESG RAD 1323 y
                                        /20          CPH
                                                                                                                    /20         CPM

• FAILED FUEL DIRTY WASTE DRAIN TANKS *WESG RAD 0202B -

                                           /0        CPH       T-60W L        IO         %

40O CPM HAIN STEAM A 2324 T-60E L 80  % RADWASTE VENT 22 CPM /WO CPH HAIN STEAM B 2323 SFP NORTil 2[ CPM 5709 3I HR/IIR

• DECADE DEPENDENT SFP S00T11 ON CR SWITCll POSITION 2313 #/O HR/llR

73 S NARIO TIME: /) 3 15

                         -                  J RADIOLOGICAL                                         77                          U RIA-2326          .                     CPM TIME:  /J I                                                     RIA-2327      [oO_                      MR/llR FUEL llAtlDLING AREAS LIQUID RADIATION MONITORS                   HON 1     005       HR/llR                  BACKUP STACK H0N 2    O 0,5      HR/llR                  RIA-2318   OOS                          CPM

• COMPONENT COOLING -

WATER 0915 RIA-2319 00f CPM

       /EO          CPM s,

SERVICE WATER CONTAINHENT ISOLATION - CONTROL R00H RAD 4CO CPM RIA-1805 2ff R/IIR RADWASTE DISCl!G RIA-1806 f R/IIR COND OFF GAS 970 CPM RIA-1807 7 7 R/llR / 2 2. CPM STM GEN 8 LOWDOWN RIA-1808 R/IIR *RADWASTE PLENUM 0707 l'/IO CPM HI RANGE L TOO R/IIR /4 O CPM

• HIXING BASIN 111 RANGE R 70 0 R/IIR *EESG RAD 1323 y

     /20            CPM                                                                /20                          CPM

• FAILED FUEL DIRTY WASTE DRAIN TANKS *WESG RAD 0202B -

         /0         CPM        T-60W L          60        %

YOO CPM HAIN STEAM A 2324 T-60E L 80  % RADWASTE VENT 23 CPM - CPM HAIN STEAM B 2323 SFP HORTil 2[ CPM 5709 (,0000 HR/l!R

• DECADE DEPENDENT SFP SOUTH ON CR SWITCll POSITION 2313 70000 HR/IIR

o SCENARIO TIME: 0330 O RADIOLOGICAL RIA-2326 CPM O TlHE: /200 RIA-2327 lof HR/llR FUEL l!ANDLING AREAS L! QUID RADIAT10tl HONITORS HON 1 005 HR/llR BACKUP STACK HON 2 OOJ HR/IIR RIA-2318 COI . CPM

• COMPONENT COOLING WATER 0915

       /50         CPM RIA-2319    00J         CPM u

SERVICE WATER CONTAINHENT ISOLATION 0833 CONTROL R00H RAD HON -1 400 CPH RIA-1805 7. 7 7 R/IIR HR/llR RADWASTE DIStilG RIA-1806 2 R/IIR COND OFF GAS 770 CPM RIA-1807 ff R/llR 122 CPM STH GEN BLOWDOWN RIA-1808 2ff R/IIR *RADWASTE PLENUM isf10 CPH 111 RANGE L /ooO R/IIR /4 O CPH

• HlXING BASIN 111 RANGE R /000 R/IIR *EESG RAD 1323

      /20          CPM
                                                                               /20         CPM

• FAILED FUEL DIRTY WASTE DRAIN TANKS *WESG RAD 0202B

         /0        CPH       T-60W L         IO        %

YOO CPM MAIN STEAM A 2324 T-60E L 80  % RADWASTE VENT 23 CPM

                                                                                   .        CPH HAlH STEAM B 2323 2f          CPM SFP NORTil 5709 65000        HR/IIR

• DECADE DEPENDENT SFP 500111 ON CR SWITCil POSITION 2313 80000 HR/ilR

SCENARIO TIME: 03'/f RADIOLOGICAL RIA-2326 7. 7. CPM TlHE: 12/8 RIA-2327 7O HR/llR FUEL llAllDLING AREAS LIQUID RADIAT10ft MONITORS H0N 1 005 HR/IIR BACKUP STACK

                ,             HON 2     OOJ         HR/IlR                 RIA-2318    DOS         CPM

• COMPONENT C00LillG WATER 0915 RIA-2319 d O d' CPM

       /50           CPH n

SERVICE WATER CONTAINHENT ISOLATION - CONTROL R00H RAD 0833 H0!I 1 MR/IIR 4OO CPM RIA-1805 7. 7 7 R/IIR RA0 WASTE DISCllG RIA-1806 R/IIR COND OFF GAS 9 70 CPM RIA-1807 7 R/llR I22 CPH STH GEN BLOWDOWN RIA-1808 7ff P/IIR *RADWASTE PLENUM

       /'llO         CPM   111 RANGE L       /000         R/ilR                         /4 O         CPM

• HlXING BASIN 111 RANGE R /ooO R/IIR *EESG RAD 1323 y

      /20            CPH
                                                                                        /20          CPM
                                                                    ~

• FAILED FUEL DIRTY WASTE DRAIN TANKS *WESG RAD 02028 -

          /0         CPM       T-60W L            IO       %

VOO CPM MAIN STEAH A 2324 T-60E L 80  % RADWASTE VEH1 27 CPM

                                                                                            .        CPH HAlH STEAM 8 2323 SFP NORTil 2[           CPH                                                    5709   20000       HR/IIR

• DECADE DEPENDENT SFP SOUTil DN CR SWITCll POSITION 2313 90cco MR/IIR

O SCtNARIO TIME: CVOO O O RADIOLOGICAL RIA-2326 CPH A TlHE: 1220 RIA-2327 7f HR/IIR FUEL llANDLING AREAS ' LIQUID RADIATION i HONITORS HON 1 OO5 HR/llR BACKUP STACK HON 2 O 0,5 HR/IIR RIA-2318 60S CPM

• COMPONENT COOLING i WATER 0915

                                      /50            CPM RIA-2319    OOJ                  CPM L

SERVICE WATER CONTAINHENT ISOLATION - CONTROL ROOM RAD 0833 HON ./ 400 CPM RIA-1805 7. 7 7 R/IIR HR/IIR RADWASTE DIStilG RIA-1806 S R/IIR COND OFF GAS 970 CPM RIA-1807 f7 R/IIR I22 CPM , SIM GEN BLOWDOWN 0707 RIA-1808 2ff R/IIR *RADWASTE PLENUM l'/ /0 CPH 111 RANGE L /OoO R/llR /4 O CPM

                         *HlXING BASIN                          !!! RANGE R        /000          R/llR           *EESG RAD 1323
                                   /20               CPM
                                                                                                                           /20                       EPH

• FAILED FUEL DIRTY WASTE DRAIN TANKS *WESG RAD 1

0202B

                                        /0           CPM              T-60W L           80        %                         YOO                      CPM HAIN STEAM A 2324                          T-60E L           80        %            RADWASTE VENT

\ 23 CPM

                                                                                                                               .                     CPM l

l HAIN STEAM B 2323 l 2[ CPM SFP NORTil 5709 F0000 HR/IIR !

• DECADE DEPENDENT SFP S00111 ON CR SWITCil POSITION ,

2313 90006 MR/llR

O SCENARIO TIME: D4/f

                              ~

O RADIOLOGICAL

                                                                                     ~

RIA-2326 m. . . O CPM TIME: f_2 4[ RIA-2327 70 HR/IIR FUEL I!ANDLING AREAS LIQUID RADIATION MONITORS MON 1 005 MR/IIR BACKUP STACK HON 2 OOJ MR/IIR RIA-2318 60S CPM

• COMPONENT C00L1HG WATER 0915 150 CPM RIA-2319 OOJ . CPM u

4 SERVICE WATER CONTA!NMENT ISOLATION CONTROL ROOM RAD ' 0833 M0! .I 4OO CPM RIA-1805 Y77.. R/IIR HR/IIR i RADWASTE DIScilG RIA-1806  ? R/llR COND OFF GAS  ; 770 CPM RIA-1807 ff R/IIR l22 CPM SIM GEN BLOWDOWN 0707 RIA-1808 2ff R/HR *RADWASTE PLENUM 12//0 4 CPM HI RANGE L _ /000 R/IIR /4 O CPM

  *HIXING BASIN                 HI RANGE R      /000         R/llR                 *EESG RAD                         ,

1323 '

         /20              CPM
                                                                                                /20         CPM

• FAILED FUEL DIRTY WASTE DRAIN TANKS *WESG RAD 02028 l /0 CPM T-60W L EO  % YOO CPM MAIN STEAM A 2324 T-60E L 80  % RA0 WASTE VENT 23 CPM

                                                                                                    .        CPM       ,

MAIN STEAM B 2323 SFP NORTH

2[ CPM 5709 25000 HR/IIR

• DECADE DEPENDENT SFP S0UIll DN CR SWITCll POSITION 2313 F5000 MR/llR

{ARIO TIME: 06/30 RADIOL CAL RIA-2326  ? CP TIME: Of DO RIA-2327 SE HR/llR FUEL llANDLING AREAS LIQUID RADIATION HONITORS HON 1 OO5 HR/IIR BACKUP STACK H0N 2 OOJ HR/IIR RIA-2318 OOS CPM

• COMPONENT COOLING WATER 0915

      /50          CPM RIA-2319 00J            CPM u

SERVICE WATER CONTAINHENT ISOLATION CONTROL R00H RAD 0833 HON -I HR/llR 4OO CPH RIA-1805 7. 7 7 R/HR RADWASTE DIStilG RIA-1806  ? R/IIR COND OFF GAS 9 70 CPH RIA-1807 [ R/llR I22 CPM STH GEN BLOWDOWN RIA-1808 )ff R/ilR *RADWASTE PLENUH 1410 CPM NI RANGE L /000 R/IIR /40 CPH

• HIXING BASIN 111 RANGE R /ooO R/ilR *EESG RAD 1323

      /20          CPM
                                                                                 /2O         CPH

• FAILED FUEL DIRTY WASTE DRAIN TANKS *WESG RAD 0202B i

        /0         CPM       T-60W L          IO         %                        YOO        CPH HAIN STEAM A 2324           T-60E L         80          %           RADWASTE VENT 23          CPM
                                                                 ^
                                                                                ? ? .?        CPH HAIN STEAM B 2323 SFP NORTil 2[          CPM 5709   70000      HR/IIR

• DECADE DEPENDENT SFP SOUTil DN CR SWITCil POSITION 2313 f(Coco MR/llR

S ARIO TIME: d46 RADIOL CAL RIA-2326 CPM TIME: /3/f RIA-2327 bO MR/IIR FUEL HANDLING AREAS LIQUID RADIATION MONITORS MON 1 OO5 MR/IIR BACKUP STACK HON 2 OOJ MR/HR RIA-2318 60S CPM

• COMPONENT COOLING '

WATER 0915 RIA-2319 dOf CPM

                                             /EO         CPM u

SERVICE WATER CONTAINHENT ISOLATION - CONTROL R00H RAD 0833 MON -1 400 CPM RIA-1805 7. 7 7 R/HR MR/IIR RADWASTE DISCllG RIA-1806 R/llR COND OFF GAS

                                              ? 70       CPM                  RIA-1807     ff              R/HR                         I22         CPM STM GEN BLOWDOWN 0707 RIA-1808     2ff             R/HR           *RADWASTE PLENUM

, 12/10 CPM HI RANGE L /000 R/IIR

                                                                                                                                        /4 O         CPM

• MIXING BASIN HI RANGE R /000 R/IIR *EESG RAD 1323 y

                                             /20         CPM
                                                                                                                                        /20          CPM

• FAILED FUEL DIRTY WASTE DRAIN TANKS *WESG RAD 0202B -

                                               /0        CPM                      T-60W L        IO         %

V00 CPM i MAIN STEAM A 2324 T-60E L 80  % RA0 WASTE VENT 23 CPn

                                                                                                                                        ? ? .?       CPn MAIN STEAM B 2323 SFP NORTH 2[          CPM 5709 ]OQOO         MR/HR

• DECADE DEPENDENT SFP S00I11 ON CR SWITCH POSITION 2313 80000 MR/llR e

O RADIATION MONITOR DATA O 1 l O

( l l l l i i l CONT RW 2.4 kV CONTR0L'O ACCESS PERS PURGE CUTS 10E CRTL RM OLD EAST RM SERV SPENT CONTROL SWITCH LAB CONTROL AIRLOCK UNIT RW OEMIN CRTL RM MAIN EAST TUR8 LUNCH FUEL SAFEGRDS CORRIDOR AREA CEAR CORRIDOR STATION OUTSIDE RM NORTH RM F00F CORRIDOR ENTRANCE OP FLOGR ROOM P00L RM mR/h mR/h mR/h mR/h mR/h mR/h mR/h mR/h mR/h mR/h mR/h mR/h mR/h mR/h TIME 1300 2301 2302 2303 2304 2305 2306 2307 2308 2309 2310 2311 2312 2313 08:00 AM 7 0.8 0.8 1 0.9 0.2 .16 .11 0.4 0.2 .1 0.4 08:15 AM 0.8 0.8 0.4 0.52 7 1 0.9 0.2 .16 .11 0.4 0.2 .1 0.4 0.4 0.52 08:30 AM 7 0.8 0.8 1 0.9 0.2 .16 .11 0.4 0.2 .1 0.4 08:45 AM 0.8 0.8 0.4 0.52 7 1 0.9 0.2 .16 .11 0.4 0.2 .1 0.4 0.4 0.52 09:00 AM 7 0.S 0.8 1 0.9 0.2 .16 .11 0.4 0.2 09:15 AM 0.8

                                                                                                                                                                                        .1       0.4   0.4    0.52 7                                           0.8      1       0.9           0.2      .16      .11       0.4      0.2         .1       0.4   0.4 09:30 AM                                             0.8     0.8                                                                                                   0.52 7                                                    1       0.9           0.2      .16      .11       0.4      0.2         .1       0.4   0.4    0.52 09:45 AM         7                                   0.8     0.8      1       0.9           0.2      .16      .11       0.4      0.2         .1       0.4 10:00 AM         7                                   0.8     0.8                                                                                            0.4    0.52 1       0.9           0.2      .16      .11       0.4      0.2        .1        0.4   0.4    0.52 10:15 AM         7                                   0.8     0.8      1       0.9           0.2      .16      .11       0.4      0.2        .1        0.4 10:30 AM         7                                   0.8     0.8                                                                                            0.4    0.52 1       0.9           0.2      .16      .11       0.4      0.2         .1       0.4   0.4    0.52 10:45 AM         7                                   0.8     0.8      1       0.9           0.2      .16      .11       0.4      0.2        .1        0.4 11:00 AM         7                                   0.8     0.8                                                                                            0.4       3 1       0.9           0.2      .16      .11       0.4      0.2        .1        0.4   0.4      30 11:15 AM         7                                   0.8     0.8      1       0.9           0.2      .16      .11       0.4      0.2        .1        0.4   0.4 0.8                                                                                                             35 11:30 AM         7                                           0.8      1       C.9           0.2      .16      .11       0.4      0.2        .1        0.4   0.4 0.8                                                                                                             40 11:45 AM         7                                           0.8      1       0.9           0.2      .16      .11       0.4      0.2        .1        0.4 0.8                                                                                                    150   70000 12:00 PM         7                                           0.8      1       0.9           0.2      .16      .11       1.0      0.2        .1        0.4 12:15 FM                                             0.8     0.8                                                                                            160   80000 7                                                    1       0.9           0.2      .16      .11       1.0      0.2        .1        0.4   160   90000 12:30 PM         7                                   0.8     0.8      1       0.9           0.2      .16      .11       1.0      0.2        .1        0.4 12:45 PM         7                                   0.8     0.8                                                                                            160   90000 1       0.9           0.2      .16      .11       1.0      0.2        .1        0.4   160   85000 01:00 PM         7                                   0.8     0.8      1       0.9           0.2      .16      .11       1.0      0.2        .1        0.4 01:15 PM                                                                                                                                                    160   80000 7                                   0.8     0.8      1       0.9           0.2      .16      .11       1.0      0.2        .1        0.4 01:30 PM                                             0.8                                                                                                    160   80000 7                                           0.8      1       0.9           0.2      .18      .11       1.0      0.2        .1        0.4   160 01:45 PM                                             0.8                                                                                                          80000 7                                           0.8      1       0.9           0.2      .16      .11       1.0      0.2        .1        0.4   ISO 02:00 PM                                             0.8                                                                                                          80000 0.8              0.9 7                                                    1                     0.2      .16      .11       1.0      0.2        .1        0.4   160   80000 02:15 PM         7                                   0.8     0.8      1       0.9           0.2      .16      .11       1.0      0.2        .1        0.4 02:30 PM                                             0.8                                                                                                    160   80000 7                                           0.8      1       0.9           0.2      .16      .11       1.0      0.2        .1        0.4   160   80000

O O O AIRLOCK 590' INSIDE CONT CONT CONT CONT AIR RM CONT RAD MON RAD MON RAD MON RAD MON l mR/h mR/h R/h R/h R/h R/h TIME 2314 2315 1805 1806 1807 1808 08:00 AM 3.1 2.7 .025 .015 .02 .015 08:15 AM 3.1 2.7 .025 .015 .02 .015 08:30 AM 3.1 2.7 .025 .015 .02 .015 08:45 AM 3.1 2.7 .025 .015 .02 .015 09:00 AM 3.1 2.7 .025 .015 .02 .015 09:15 AM 3.1 2.7 .025 .015 .02 .015 09:30 AM 3.1 2.7 .025 .015 .02 .015 09:45 AM 3.1 2.7 .025 .015 .02 .015 10:00 AM OSH OSH OSH OSH OSH OSH 10:15 AM OSH OSH OSH OSH OSH OSH 10:30 AM OSH OSH OSH OSH OSH OSH 10:45 AM OSH OSH OSH OSH OSH OSH 11:00 AM OSH OSH OSH OSH OSH OSH 11:15 AM OSH OSH OSH OSH OSH OSH 11:30 AM OSH OSH OSH OSH OSH OSH 11:45 AM OSH OSH OSH OSH OSH OSH 12:00 PM OSH OSH OSH OSH OSH OSH 12:15 PM OSH OSH OSH OSH OSH OSH 12:30 PM OSH OSH OSH OSH OSH OSH 12:45 PM OSH OSH OSH OSH OSH OSH 01:00 PM OSH OSH OSH OSH OSH OSH ' 01:15 PM OSH OSH OSH OSH OSH OSH 01:30 PM OSH OSH OSH OSH OSH OSH 01:45 PM OSH OSH OSH OSH OSH OSH 02:00 PM OSH OSH OSH OSH OSH OSH 02:15 PM OSH OSH OSH OSH OSH OSH 02:30 PM OSH OSH OSH OSH OSH

           )

EVAP RW CONTROL *D RW RW SPENT FUEL EIHAUST RW FUEL DECOM CONTROL DECAY LA8 PACKAGING PACKAG1HG POOL FAN A001T10N HANDLING ROOM EVAP A EVAP 8 PANEL TANKS CORR 100R AREA NO AREA WEST CRITICALITY DUCT VENT RM YEhT mR/h mR/h mR/h mR/h mR/h mR/h mR/h mR/h mR/h mR/h cpm cpe TIME 5701 5702 5703 5704 5705 5706 5707 5708 5709 5710 5711 5712 08:00 AM 0.3 0.35 18 .13 0.2 0.9 .25 .01 0.28 .1 08:15 AM 0.3 15 18 0.35 18 .13 0.2 0.9 .25 .01 0.28 .1 08:30 AM 0.3 15 18 0.35 18 .13 0.2 0.9 .25 .01 0.28 .1 08:45 AM 0.3 15 18 0.35 18 .13 0.2 3.9 .25 .01 0.28 .1 09:00 AM 0.3 15 18 0.35 18 .13 0.2 0.9 .25 .01 0.28 .1 15 18 09:15 AM 0.3 0.35 18 .13 0.2 0.9 .25 .01 0.28 09:30 AM 0.3 .1 15 18 0.35 18 .13 0.2 0.9 .25 .01 0.28 .1 15 18 09:45 AM 0.3 0.35 18 .13 0.2 0.9 .25 .01 0.28 10:00 AM 0.3 .1 15 18 0.35 18 .13 0.2 0.9 .25 .01 0.28 .1 15 18 10:15 AM 0.3 0.35 18 .13 0.2 0.9 .25 .01 0.26 .1 10:30 AM 0.3 15 18 0.35 18 .13 0.2 0.9 .25 .01 0.28 .1 10:45 AN 0.3 15 18 0.35 18 .13 0.2 0.9 .25 .01 0.28 .1 15 18 11:00 AM 0.3 0.35 18 .13 0.2 0.9 .25 .01 3 .1 11:15 AM 0.3 150 150 - 0.35 18 .13 0.2 0.9 .25 .01 30 .1 11:30 AM 0.3 1500 1500 0.35 18 .13 0.2 0.9 .25 .01 35 11:45 AM 0.3 0.35 .1 1600 1600 18 .13 0.2 0.9 .25 .01 60000 .1 1800 1800 12:00 PM 0.3 0.35 18 .13 0.2 09 .25 .01 65000 12:15 PM 0.3 0.35 .1 OSH OSH 18 .13 0.2 0.9 .25 .01 80000 .1 OSH OSH 12:30 PM 0.3 0.35 18 .13 0.2 0.9 .25 .01 80000 12:45 PM 0.3 0.35 .1 OSH OSH 18 .13 0.2 0.9 .25 .01 75000 .1 OSH OSH 01:00 PM 0.3 0.35 18 .13 0.2 0.9 .25 .01 70000 .1 OSH OSH 01:15 PM 0.3 0.35 18 .13 0.2 0.9 .25 .01 70000 01:30 PM 0.3 .1 OSH OSH 0.35 18 .13 0.2 0.9 .25 .01 70000 .1 CSH OSH 01:45 PM 0.3 0.35 18 .13 0.2 0.9 25 .01 70000 02:00 PM 0.3 .1 OSH OSH 0.35 18 .13 0.2 0.9 .25 .01 70000 02:15 PM 0.3 0.35 .1 OSH OSH 18 .13 0.2 0.9 .25 .01 70000 .1 OSH OSH 02:30 PM 0.3 0.35 18 .13 0.2 0.9 .25 .01 70000 .1 OSH OSH _ _. .-___________--____--_-_-_____-------=_----------------- - - -

O O O SERVICE STEAM COMPONENT CIRC LIQUID TURB WATER GENERATOR COOLING WATER RW BLDG DISCHARGE BLOWDOWN WATER DISCHARGE MONITOR SUMP cpm cpm cpm cpm cpm cpm ~ TIME 0833 0707 0915 1323 1049 5211 08:00 AM 600 1410 150 120 870 150 08:15 AM 600 1410 150 120 870 150 03:30 AM 600 1410 150 120 870 159 08:45 AM 600 1410 150 120 870 150 09:00 AM 600 1410 150 120 870 150 09:15 AM 600 1410 150 120 870 150 09:30 AM 600 1410 150 120 870 150 09:45 AM 600 1410 150 120 870 150 10:00 AM 600 1410 150 120 870 150 10:15 AM 600 1410 150 120 870 150 10:30 AM 600 1410 150 120 870 150 10:45 AM 600 1410 150 120 870 150 11:00 AM 600 1410 150 120 870 150 11:15 AM 600 1410 150 120 870 150 11:30 AM 600 1410 150 120 870 150 11:45 AM 600 1410 150 120 870 150 12:00 PM 600 1410 ISO 120 870 150 12:15 PM 600 1410 150 120 870 150 12:30 PM 600 1410 150 120 870 150 12:45 PM 600 1410 150 120 870 150 01:00 PM 600 1410 150 120 870 150 01:15 PM 600 1410 150 120 870 150 01:30 PM 600 1410 150 120 870 150 01:45 PM 600 1410 150 120 870 150 02:00 PM 600 1410 150 120 870 510 02:15 PM 600 1410 150 120 870 150 02:30 PM 600 1410 150 120 870 150

O O O i IODINE / NORMAL HIGH MAIN MAIN CONT CONT FAILED HIGH RANGE

PART NOBLE GAS RANGE STEAM STEAM HIGH HIGH FUEL EFFLUENT i GAS EFF EFFLUENT NOBLE GAS GAMMA B GAMMA A RANGE RANGE MONITOR MONITOR cpm cpm mr/hr cpm cpm R/h R/h  % mR/h TIME 2325 2326 2327 2323 2324 2321 2322 0202 l

(RAD GUN) l l 08:00 AM 300 60 0.2 25 23 1 1 10 00S i 08:15 AM 300 60 0.2 25 23 1 1 10 OOS 08:30 AM 300 60 0.2 25 23 1 1 10 00S 08:45 AM 300 60 0.2 25 23 1 1 10 OOS l 09:00 AM 300 60 0.2 25 23 1 1 10 00S 09:15 AM 300 60 0.2 25 23 1 1 10 00S 09:30 AM 300 90 0.2 25 23 1 1 10 00S 09:45 AM 350 120 0.2 25 23 1 1 10 00S  ! 10:00 AM 375 150 0.2 25 23 1 1 10 00S 10:15 AM 400 150 0.2 25 23 1 1 10 005 10:30 AM 425 200 0.2 25 23 2 2 10 00S 10:45 AM 425 250 0.2 25 23 20 20 10 00s 11:00 AM 450 400 0.2 25 23 350 350 10 00S 11:15 AM 450 600 0.2 25 23 500 500 10 00S 11:30 AM 475 1000 0.2 25 23 700 700 10 00s 11:45 AM 500 OSH 60 25 23 900 900 10 00S 12:00 PM 500 OSH 65 25 23 1000 1000 10 00S 12:15 PM 500 OSH 70 25 23 1000 1000 10 00s 12:30 PM 500 OSH 75 25 23 1000 1000 10 00S 12:45 PM 500 OSH 70 25 23 1000 1000 10 00S 01:00 PM 500 OSH 65 25 23 1000 1000 10 00S 01:15 PM 500 OSH 60 25 23 1000 1000 10 00S 01:30 PM 500 OSH 60 25 23 1000 1000 10 00S 01:45 PM 500 OSH 60 25 23 1000 1000 10 005 02:00 PM 500 OSH 60 25 23 1000 1000 10 OOS 02:15 PM 500 OSH 60 25 23 1000 1000 10 00S 02:30 PM 500 OSH 60 25 23 1000 1000 10 00S ______.___.___..__._.__________________--_-__m.__w __

O O O STACK GAS STACK GAS EAST WEST CONT BLDG WASTE BLOWDOWN GROSS SINGLE RW SAFEGRDS SAFEGRDS GAS GAS CONDENSER TANK VENT ACTIVITY ISOTOPE VENT VENT VENT MONITOR MONITOR OFFGAS MONITOR

                             . cpm       cpm  cpm      cpm       cpm       cpm      cpm           cpm       cpm TIME        2318        2319 1809     1810      1811      1817     1113          0631      2320 1

08:00 AM 00S 00S 160 120 400 3900 <100 122 400 08:15 AM OOS 00S 160 120 400 3900 <100 122 400 08:30 AM 00S 00S 160 120 400 3900 <100 122 400 08:45 AM 00S 00S 160 120 400 3900 <100 122 400 09:00 AM 00S 005 160 120 400 3900 <100 122 400 09:15 AM 00S 00S 160 120 400 3900 <100 122 400 09:30 AM 00S 00S 160 120 400 3900 <100 122 400 09:45 AM 005 OOS 160 120 400 3900 <100 122 400 10:00 AM 00S 005 160 120 400 3900 <100 122 400 10:15 AM OOS 005 160 120 400 3900 <100 122 400 10:30 AM OOS 00S 160 120 400 3900 <100 122 400 i 10:45 AM 00S 00S 160 120 400 3900 <100 122 400 11:00 AM 00S 00S 160 120 400 OSH <100 122 400 11:15 AH OOS 00S 160 120 400 OSH <100 122 400 11:30 AM 00S 00S 160 120 400 OSH <100 122 400 11:45 AM 00S 00S 160 120 400 OSH <100 122 400 12:00 PM 00S 00S 160 120 400 OSH <100 122 400 12:15 PM 00S 00S 160 120 400 OSH <100 122 400 ' 12:30 PM 00S 00S 160 120 400 OSH <100 122 400 l 12:45 PM 00S 00S 160 120 400 OSH <100 122 400 i 01:00 PM OOS 005 160 120 400 OSH <100 122 400 01:15 PM OOS DOS 160 120 400 OSH <100 122 400 01:30 PM 005 OOS 160 120 400 OSH <100 122 400 01:45 PM OOS 00S 160 120 ~400 OSH <100 122 400 02:00 PM 005 OOS 160 120 400 OSH <100 122 400 02:15 PM 00S 00S 160 120 400 OSH <100 122 400 02:30 PM OOS 00S 160 120 400 OSH <100 122 400 l l

O INPLANT RADIATION DATA O i i l l 1 l l l O i

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