ML18058B087

1992 Palisades Emergency Exercise Scenario for 920901 Emergency Exercise

ML18058B087
Person / Time
Site:	Palisades
Issue date:	09/01/1992
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
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ML18058B086	List: ML18058B085 ML18058B087
References
NUDOCS 9209240091
Download: ML18058B087 (460)

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{{#Wiki_filter:* ATTACHMENT Consumers Power Company Palisades Plant Docket 50-255 1992 PALISADES EMERGENCY EXERCISE SCENARIO

• September 15, 1992

PALEX-92

• 9209240091 920915 PDR ADOCK 05000255 F PDR
• TABLE OF CONTENTS SCOPE AND OBJECTIVES EXERCISE CONDUCT EXERCISE ORGANIZATION CONTROLLER ORGANIZATION EXERCISE DATA AND MESSAGES EXERCISE GROUND RULES CRITIQUES EVALUATOR CHECKLISTS EXERCISE DATA SEQUENCE OF EVENTS NARRATIVE

SUMMARY

• MESSAGE SHEETS CFMS OPERATIONS DATA CFMS RAD DATA RAD MONITOR DATA INPLANT RAD DATA ONSITE RAD DATA OFFSITE RAD DATA CFMS MET DATA WSI FORECAST WSI HOURLY MET DATA ONSITE MET TOWER

SCOPE AND OBJECTIVES

PALEX-92 SCOPE AND OBJECTIVES

• SCOPE PALEX-92 is designed to meet exercise requirements specified in 10 CPR 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 exercise will include participation by Allegan County, Berrien County, Van Buren County 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.

• 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.

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

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

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

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

3. Radiological Assessment and Control

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

b. Analyze plant radiological conditions and implement protective actions for site

• c.

d. personnel in accordance with procedures . Prepare and brief personnel for activities required in high radiation areas. 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 classification.

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

• c.

d. e. Update status boards at least every 30 minutes. Document field team activities in logs and on appropriate status boards. Track and prioritize status of key in plant jobs.

5. Direction and Control

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

b. Coordinate maintenance activities.

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

d. Dispatch field teams in accordance with procedures.

e. Direct and monitor field team actions.

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

g. Perform accountability within approximately 30 minutes of the Alert 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, ~eld 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 .

 -EXERCISE CONDUCT

EXERCISE CONDUCT EXERCISE ORGANIZATION The exercise organization is comprised of Controller/Evaluators, Players and Observers. Controller/Evaluators observe player activities and judge the effectiveness of Player actions based on Evaluator Checklists provided in this section. F.ac~ 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 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/Evaluato.r in charge. Players include all personnel responding to simulated emergency conditions. 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 assign'ed 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.

EXERCISE DATA AND MESSAGES Messages and data to drive Player actions are contained in the Exercise Data Section. 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. Leading questions and hints are not allowed at any time. If confidential scenario information must be provided to a Player, it must be formally noted in the critique tbat the Player was prompted. ., EXERCISE GROUND RULES

1. Be aware of and know your CPCo Controller/Evaluators and NRC Evaluators in our area. Be aware that Visitors/Observers may also be present.

2. 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.

3. The Controllers/Evaluators may be exempt from acting as if simulated radiation levels are preent. Do not let them confuse you.

4. Observe all rules and procedures when entering normal station radiation areas.

No one (even Controllers/Evaluators) are exempt from normal station radiological practices and procedures.

5. 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.

6. Keep your focus on the exercise. Unrelated cbnversations detract from your performance,including conversations with visitors/observers.

7. Whenever a Controller/Evaluator provides a message or data, accept it for face value. They are essential to your successful performance. If you do not understand a message or any Controller/Evaluator provided information, ask for clarification - the Controller/Evaluator will not prompt you. Exercise data is intended to be clear and straight forward. Scenario developers will never provide data the intentionally misleads Players .

8. If your Controller/Evaluator asks you a question or provides directions, you

• 9.

should answer or comply as appropriate; it is for a good reason. If you think he/she is in error, feel free to discuss your concerns. You must, however, accept his/her word as final with respect to s~~ario related matters. 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. You must not accept any messages/instructions from NRC Evaluators. They must work through your Controller. ..

10. Follow through on all actions. It is okay to adjust priorities, but not without thinking through. Start and stop syndrome is not good. Keep an open mind on your options.

11. Although it may seem artificial, speak out loud to identify your actions and decisions to Controller/Evaluators. This will assist in the evaluation process andd is to your benefit. Additionally, the use of the following enhanced verbal communications will result in improved and more consistent performance.

a. Communication must be free of ambiguity; avoid the use of slang _terms and

• words that sound alike (eg, avoid the use of "increase" and "decrease", use "raise" and "lower" instead.)
• b. Be specific; use equipment noun names and numbers, (eg, "Open feedwater c.

pump discharge valve F016, that is discharge valve Foxtrot zer one six.") Repeat messages, either paraphrased in your own words or verbatim.

d. Listen carefully to repeat-backs to ensure the message is understood by the receiver. Acknowledge that you received a ccorrect repeat-back.

e. When asked to complete a task, report to the supervisor that the job is complete or inform him of the difficulties.

f. Write down complicated instructions such as aligning more than one or two components; do not rely on memory.

g. Keep everyone informed; it is better to tell too much than too little.

h. Provide work station and name when answering the telephone (eg, operator John Smith in the control room would answer - "Main control room, Smith.')

i. Use of formal titles when communicating on a party system each time a message is conveyed (eg, "Reactor building operator, this is the control

• room operator. Come to the control room.")

J~. Take time when reporting abnormal conditions, provide the nature and

• 12.

severity of the problem, and above all keep the communication line open, if possible. Keep a list of items you feel will improve your *plans and procedures. Provide this to your lead player. Lead players will ensure these are considered. If necessary, they will identify them to the controller. Remember one of the main purposes of the exercise is for you, the player, to assure yourself that you are prepared adequately. Areas for improvement or lessons learned, when identified, will improve your overall emergency preparedness.

13. At the conclusion of the exercise there will be a critique. Team Leaders will be asked for suggestions and comments. If you have any recommended solutions, be sure to let your Team Leader know .

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

• 1.

a. Control Room Evaluator Checklist Assessment and Classification Assess conditions which warrant Overall: MET NOT MET MET MET/PROBLEM NOT MET NIA classification within fifteen EXPLANATION: minutes of being provided those conditions.

b. Classify posed conditions in MET MET/PROBLEM NOT MET NIA accordance with Emergency EXPLANATION:

Action Levels within fifteen minutes of determination that conditions warrant classification.

2. Communications Overall: MET NOT MET

a. Upon making an emergency MET MET/PROBLEM NOT MET NIA classification, complete initial EXPLANATION:

notifications within fifteen minutes to the State and locals and within one hour to the NRC

• b.

using the Notification.Form. Complete subsequent notifications to the State, locals, and NRC on a routine fifteen MET MET/PROBLEM NOT MET NIA EXPLANATION: minute basis or as mutually agreed.

c. Contact other organizations such MET MET/PROBLEM NOT MET NIA as contractors, utilities, fire or EXPLANATION:

medical support within one hour of recognizing that conditions exist that warrant their assistance.

e. Provide updates between MET MET/PROBLEM NOT MET NIA appropriate Emergency Response EXPLANATION:

Facilities at least every 30 minutes .

• Page 1of3

3. Radiological Assessment and Control Overall: MET NOT MET

• 4.

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

Emergency Response Facilities MET MET/PROBLEM NOT MET NIA EXPLANATION: Overall: MET NOT MET

a. Staff and activate onsite MET MET/PROBLEM NOTMET NIA Emergency Response Facilities EXPLANATION:

within approximately 30 minutes of an Alert classification.

b. Staff and activate the Emergency MET MET/PROBLEM NOT MET NIA Operations Facility within about EXPLANATION:

an hour of the Site Area Emergency declaration.

e. Track.and prioritize status of key MET MET/PROBLEM NOT MET NIA inplant-jobs. EXPLANATION:

5. Direction and Control Overall: MET NOT MET

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

Coordinate maintenance MET MET/PROBLEM NOT MET NIA EXPLANATION: MET MET/PROBLEM NOT MET NIA b. activities. EXPLANATION:

c. Take appropriate measures to MET MET/PROBLEM NOT MET NIA secure emergency equipment, EXPLANATION:

supplies, and support.

f. Transfer Command and control MET MET/PROBLEM NOT MET NIA in accordance with the Site EXPLANATION:

Emergency Plan .

• Page2of3

Date: Page 3 of 3

TSC Evaluator Checklist

• 1. Assessment and Classification

a. Assess conditions which warrant classification within fifteen Overall: MET NOTMET MET MET/PROBLEM NOT MET NIA EXPLANATION:

minutes of being provided those conditions.

b. Classify posed conditions in MET MET/PROBLEM NOT MET NIA accordance with Emergency EXPLANATION:

Action Levels within fifteen minutes of determination that conditions warrant classification.

2. Communications Overall: MET NOT MET

a. Upon making an emergency MET MET/PROBLEM NOT MET NIA classification, complete initial EXPLANATION:

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

• b. Complete subsequent notifications to the State, locals, and NRC on a routine fifteen minute basis or as mutually MET MET/PROBLEM NOT MET NIA EXPLANATION:

agreed.

c. Contact other organizations such MET MET/PROBLEM NOT MET NIA as contractors, utilities, fire or EXPLANATION:

medical support within one hour of recognizing that conditions exist that warrant their assistance.

e. Provide updates between MET MET/PROBLEM NOT MET N\A appropriate Emergency Response EXPLANATION:

Facilities at least every 30 minutes. Page 1of3

3. Radiological Assessment and Control Overall: MET NOT MET

• a.

b. Collect, analyze, document and trend radiological survey data. Analyze plant radiological MET MET/PROBLEM NOT MET NIA EXPLANATION: MET MET/PROBLEM NOTMET NIA conditions and implement EXPLANATION: protective actions for site personnel in accordance with procedures.

e. Calculate dose projections based MET MET/PROBLEM NOT MET NIA on sample results or monitor EXPLANATION:

readings.

f. Identify appropriate protective MET MET/PROBLEM NOTMET NIA action recommendations. EXPLANATION:

4. Emergency Response Facilities Overall: MET NOT MET

a. Staff and activate onsite MET MET/PROBLEM NOT MET NIA Emergency Response Facilities EXPLANATION:

within approximately 30 minutes

• c.

of an Alert classification. Update status boards at least every 30 minutes. MET MET/PROBLEM NOTMET NIA EXPLANATION:

e. Track and prioritize status of key MET MET/PROBLEM NOT MET NIA in plant jobs. EXPLANATION:

5. Direction and Control Overall: MET NOT MET

a. Command and control of MET MET/PROBLEM NOTMET NIA Emergency Response Facilities EXPLANATION:

in accordance with assigned functions.

c. Take appropriate measures to MET MET/PROBLEM NOT MET NIA secure emergency equipment, EXPLANATION:

supplies, and support. Page 2 of 3

d. Dispatch field teams in MET MET/PROBLEM NOTMET NIA accordance with procedures. EXPLANATION:

f. Transfer Command and control MET MET/PROBLEM NOT MET NIA in accordance with the Site EXPLANATION:

Emergency Plan.

g. Perform accountability within MET MET/PROBLEM NOTMET NIA approximately 30 minutes of the EXPLANATION:

Alert classification.

h. Control site access and site MET MET/PROBLEM NOT MET NIA evacuation as directed. EXPLANATION:

1. Brief Emergency Response MET MET/PROBLEM NOT MET NIA Facility staffs approximate! y EXPLANATION:

every 30 minutes on changes in plant status, emergency classification, field team progress, and offsite actions as appropriate. J. Effectively coordinate with state MET MET/PROBLEM NOTMET NIA and local governments as EXPLANATION: appropriate.

k. Demonstrate reentry and MET MET/PROBLEM NOTMET NIA recovery in accordance with EXPLANATION:

procedures.

6. Exercise Control Overall: MET NOT MET

a. Allow adequate free play for MET MET/PROBLEM NOT MET NIA players to demonstrate their EXPLANATION:

capabilities.

b. Accurately assess performance of MET MET/PROBLEM NOTMET NIA exercise players and controllers. EXPLANATION:

c. Adequacy of scenario data. MET MET/PROBLEM NOTMET NIA EXPLANATION:

Date: Page 3 of 3

OSC/MSC Evaluator Checklist

• 2. Communications

e. Provide updates between appropriate Emergency Response Facilities at least every 30 Overall: MET NOTMET MET MET/PROBLEM NOT MET NIA EXPLANATION:

minutes.

3. Radiological Assessment and Control Overall: MET NOT MET

a. Collect, analyze, document and MET MET/PROBLEM NOT MET NIA trend radiological survey data. EXPLANATION:

c. Prepare and brief personnel for MET MET/PROBLEM NOT MET NIA activities required in high EXPLANATION:

radiation areas.

d. Monitor, track and document MET MET/PROBLEM NOT MET NIA radiation exposure to* EXPLANATION:

maintenance, operations, and monitoring team personnel. Emergency Response Facilities Overall: MET NOT MET

a. Staff and activate onsite MET MET/PROBLEM NOT MET NIA Emergency Response Facilities EXPLANATION:

within approximately 30 minutes of an Alert classification.

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

d. Document field team activities in MET MET/PROBLEM NOT MET NIA logs and on appropriate status EXPLANATION:

boards.

e. Track and prioritize status of key MET MET/PROBLEM NOT MET NIA in plant Jobs. EXPLANATION:

Page 1of2

5. Direction and Control Overall: MET NOT MET

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

MET MET/PROBLEM NOTMET NIA EXPLANATION:

b. Coordinate maintenance MET MET/PROBLEM NOTMET NIA activities. EXPLANATION:

c. Take appropriate measures to MET MET/PROBLEM NOT MET NIA secure emergency equipment, EXPLANATION:

supplies, and support.

d. Dispatch field teams in MET MET/PROBLEM NOT MET NIA accordance with procedures. EXPLANATION:

e. Direct and monitor field team MET MET/PROBLEM NOTMET NIA actions. EXPLANATION:

g. Perform accountability within MET MET/PROBLEM NOT MET NIA approximately 30 minutes of the EXPLANATION:

Alert classification .

• 1. Brief Emergency Response Facility staffs approximately every 30 minutes on changes in plant status, emergency MET MET/PROBLEM NOT MET NIA EXPLANATION:

classification, field team progress, and offsite actions as appropriate.

6. Exercise Control Overall: MET NOT MET

a. Allow adequate free play for MET MET/PROBLEM NOT MET NIA players to demonstrate their EXPLANATION:

capabilities.

b. Accurately assess performance of MET MET/PROBLEM NOTMET NIA exercise players and controllers. EXPLANATION:

c. Adequacy of scenario data. MET MET/PROBLEM NOTMET NIA EXPLANATION:

Name:

• Date: Page 2of2

EOF Evaluator Checklist

• 1. Assessment and Classification Overan: MET NOT MET

a. Assess conditions which warrant MET MET/PROBLEM NOT MET NIA classification within fifteen EXPLANATION:

minutes of being provided those conditions.

b. Classify posed conditions in MEf MET/PROBLEM NOT MET NIA accordance with Emergency EXPLANATION:

Action Levels within fifteen minutes of determination that conditions warrant classification.

2. Communications Overall: MET NOT MET

a. Upon making an emergency MET MET/PROBLEM NOT MET NIA classification, complete initial EXPLANATION:

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

• 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 NIA EXPLANATION:

c. Contact other organizations such MET MET/PROBLEM NOT MET NIA as contractors, utilities, fire or EXPLANATION:

medical support within one hour of recognizing that conditions exist that warrant their assistance.

d. Provide accurate press release MET MET/PROBLEM NOT MET N\A information on plant conditions EXPLANATION:

within one hour after occurrence.

• Page 1 of3

e. Provide updates between MET MET/PROBLEM NOTMET NIA appropriate Emergency Response EXPLANATION:

Facilities at least every 30 minutes.

3. Radiological Assessment and Control Overall: MET NOT MET

a. Collect, analyze, document and MET MET/PROBLEM NOT MET NIA trend radiological survey data. EXPLANATION:

e. Calculate dose projections based MET MET/PROBLEM NOT MET NIA on sample results or monitor EXPLANATION:

readings.

f. Identify appropriate protective MET MET/PROBLEM NOT MET NIA action recommendations. EXPLANATION:

g. Perform environmental MET MET/PROBLEM NOT MET NIA monitoring in accordance with EXPLANATION:

procedures.

4. Emergency Response Facilities Overall: MET NOT MET

• b. Staff and activate the Emergency MET MET/PROBLEM NOT MET NIA Operations Facility within about EXPLANATION:

an hour of the Site Area Emergency declaration.

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

d. Document field team activities in MET MET/PROBLEM NOT MET NIA logs and on appropriate status EXPLANATION:

boards.

5. Direction and Control Overall: MET NOT MET

a. Command and control all MET MET/PROBLEM NOT MET NIA Emergency Response Facilities EXPLANATION:

in accordance with assigned functions.

c. Take appropriate measures to MET MET/PROBLEM NOT MET NIA secure emergency equipment, EXPLANATION:

supplies, and support. Page 2 of 3

e. Direct and monitor field team MET MET/PROBLEM NOTMET NIA

• f.

actions. Transfer Command and control in accordance with the Site Emergency Plan. EXPLANATION: MET MET/PROBLEM NOT MET NIA EXPLANATION:

i. Brief Emergency Response MET MET/PROBLEM NOT MET NIA Facility staffs approximately EXPLANATION:

every 30 minutes on changes in plant status, emergency classification, field team progress, and offsite actions as appropriate.

j. Effectively coordinate with state MET MET/PROBLEM NOT MET NIA and local governments as EXPLANATION:

appropriate.

k. Demonstrate reentry and MEf Mil/PROBLEM NOTMET NIA recovery in accordance with EXPLANATION:

procedures.

• 6. Exercise Control

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

Overall: MET NOT MET MEf MET/PROBLEM NOTMET NIA EXPLANATION:

b. Accurate!y assess performance of MET MET/PROBLEM NOT MET NIA exercise players and controllers. - EXPLANATION:

c. Adequacy of scenario data. MET MET/PROBLEM NOT MET NIA EXPLANATION:

Date: Page 3 of 3

RMT Evaluator Checklist

• 2. Communications

e. Provide updates between Overall: *

• MET NOT MET MET MET/PROBLEM NOT MET NIA appropriate Emergency Response EXPLANATION:

Facilities at least every 30 minutes.

3. Radiological Assessment and Control Overall: MET NOT MET

a. Collect radiological survey data. MET MET/PROBLEM NOT MET NIA EXPLANATION:

g. Perform environmental MET MET/PROBLEM NOT MET NIA monitoring in accordance with EXPLANATION:

procedures.

1. Brief Emergency Response MET MET/PROBLEM NOT MET NIA Facility staffs approximately EXPLANATION:

every 30 minutes on changes in plant status, emergency classification, field team progress, and offsite actions as appropriate.

6. Exercise Control Overall: MET NOT MET

a. Allow adequate free play for MET MET/PROBLEM NOT MET NIA players to demonstrate their EXPLANATION:

capabilities.

b. Accurately assess performance of MET MET/PROBLEM NOT MET NIA exercise players and controllers. EXPLANATION:

c. Adequacy of scenario data. MET MET/PROBLEM NOT MET NIA EXPLANATION:

Date:

JPIC Evaluator Checklist

• 2. Communications Overall: MET NOTMET

d. Provide accurate press release information on MET MET/PROBLEM NOT MET NIA plant conditions within one EXPLANATION:

hour after occurrence.

e. Provide updates between MET MET/PROBLEM NOT MET NIA appropriate Emergency EXPLANATION:

Response Facilities at least every 30 minutes.

5. Direction and Control Overall: MET NOTMET J. Effectively coordinate with MET MET/PROBLEM NOT MET NIA state and local governments EXPLANATION:

as appropriate.

6. Exercise Control Overall: MET NOTMET

a. Allow adequate free play MET MET/PROBLEM NOT MET NIA for players to demonstrate EXPLANATION:

their capabilities .

b. Accurately assess MET MET/PROBLEM NOT MET NIA performance of exercise EXPLANATION:

players and controllers.

c. Adequacy of scenario data. MET MET/PROBLEM NOT MET NIA EXPLANATION:

Name: ____________ Date:

SEQUENCE OF EVENTS

SCENARIO

SUMMARY

PALEX-92 is a Steam Generator Tube Rupture event with coincident loss of startup power. It loosely follows the analysis described by the FSAR, Sectfo_n 14.15 and includes additional complications suggested by the Ginna Steam Generator Tube Rupture event of January 25, 1982. The Control Room simulator will be used, and to the extent possible, will be run in real time mode. Data sheets have been prepared and will be used if needed. .. SEQUENCE OF EVENTS:

 -0030/0800      Initial conditions are provided to Players:

The reactor is operating at full power at the end of core life. Equipment degraded/out of service: Radwaste Evaporators M-59A and M-59B Limited radwaste storage capacity Miscellaneous Waste Transfer Pump P-92A Letdown flow indicator FIC-0202 Containment Sump Level Indicator LIA-0359 Alarms: Annunciator EK-11-60, "Radwaste Panel C-105 off-normal" Annunciator EK-13-68, "Radwaste Panel C-40 off-normal" Annunciator EK-07-71, "Volume Control Radiation Monitor High Radiation" PCS leak rate (most recent results): 0.08 gpm identified, 0.044 gpm unidentified, 0.124 gpm total. Estimated primary to secondary leak rate: 0.001 gpm. 0000/0830 The exercise begins with receipt of PCS activity sample results indicating a small amount of failed fuel. An ALERT should be declared. 0030/0900 Site Emergency Plan activation complete. A small seal leak develops on CRD-

17. A Service Water leak in Containment develops on Containment Air Cooler VHX-3. Progressive fuel rod failures commence.

• 0115/0945 PCS activity levels greater than permitted by Technical Specifications (confirmed by sample).

0130/1000 A double-ended rupture of a single tube in Steam Generator E-50B occurs, resulting in Reactor trip and loss of Startup power. 0135/1005 GENERAL EMERGENCY should be declared. 0145/1015 Operators commence cooldown, resulting in first release at low S/G 'B' activity levels. Auxiliary Spray CV-2117 fails. 0225/1055 The ability to drain SIG 'B' to radwaste is lost. 0325/1155 The second release at high S/G 'B' activity levels commences. 0425/1255 (Estimated) Time jump conditions are provided to players; recovery planning begins . Players not involved in recovery planning begin critiques. 0630/ 1500 Recovery planning is completed; the exercise is terminated .

NARRATIVE

SUMMARY

0800 (-0030) A. The plant is at full power at the end of core life (11.1 GWD/MTU). No Technical Specification surveillance activities are in progress. B. The plant will commence coast down shortly, with shutdown for refueling outage scheduled for next weekend. Based on current PCS activity trends, Reactor Engineering anticipates finding approximately 5 leaking fuel assemblies during the refueling (all burnt assemblies are to be inspected during the shuffle). C .. Operators are unaware that various additional fuel rods within a single reload "L" fuel bundle are in the process of failing due to vibration-induced mechanical fretting. D. Plant radwaste capability is extremely taxed. Both radwaste evaporators and the VRS are currently out of service, and just enough clean waste holdup capacity is available to support operation to the weekend and subsequent shutdown and boration. E. Management expectations as conveyed to operators are that, due to high system demand created by the unseasonably early warm spring weather, every attempt consistent with safe plant operation shall be made to adhere to the scheduled weekend shutdown and that no testing or evolutions which have the potential to jeopardize this goal are to be authorized (the reason for this admonition is that an attempt to perform turbine valve testing the previous weekend to check out new DEH controls had resulted in an unanticipated derate to 60%). F. Equipment in a degraded mode: - .

1. Radwaste Evaporator M-59A has been out of service for one month due to non-availability of obsolete parts.

2. Radwaste Evaporator M-59B is out of service to replace "rocked up" recirculation pump discharge lines.

3. The Volume Reduction System is out of service while repairs are made to the extruder.

4. Miscellaneous Waste Transfer Pump P-92A is tagged out for pump rebuild and motor replacement and is completely disassembled.

5. Letdown Flow Indicator FIC-0202, while in service, is out of calibration and reads approximately 5 gpm too low. A work request has been submitted .

6. Containment Sump Level Indicator LIA-0359 is out of service due to failed meter movement. A replacement meter is on order. (This malfunction is necessary due to simulator modeling limitations.)

G. Rad waste Systems tank status: Clean Waste System: Dirty Waste System: T-64A CWRT Level 95% T-92A Misc Waste Tk Level 97% T-64B CWRT Level 95% T-92B Misc Waste Tk Level 98 % T-64C CWRT Level 56% T-92C Misc Waste Tk Level 75 % T-64D CWRT Level 0% T-94A Clean Cone Tk Level 98 % T-96 RBAT Level 10 % 15 ,200ppm T-94B Clean Cone Tk Level 97% T-95A Dirty Cone Tk Level 97% T-95B Dirty Cone Tk Level 98 % H. Existing Alarm Conditions:

1. Annunciator EK-11-60, "Radwaste Panel C-105 off-normal"

2. Annunciator EK-13-68, "Radwaste Panel C-40 off-normal"

3. Annunciator EK-07-71, "Volume Control Radiation Monitor High Radiation" has just been received. Chemistry has been directed to sample the PCS for activity and is in the process of obtaining the sample.

I. Meteorological Conditions are as follows:

1. Unusually warm and dry spring conditions exist, with sustained winds from the southwest.

a. Wind Speed: 2-4 mph

b. Wind Direction: 225 degrees

c. Stability: D/E

d. Ambient Temperature: 80-90 degrees Fahrenheit J. Primary and Secondary Chemistry

1. Primary System Chemistry (prior to sample in progress)

a. pH: 7.07

b. Boron: 5 ppm

• c. Dissolved Oxygen: less than 0.002 ppm
• d. Hydrogen: 25 cc/kg

e. Total Beta Gamma Activity: 2.04 pCi/ml

f. Iodine Dose :Equivalent: 0.053 µCi/ml

g. Total PCS Gas Activity: 15.2 pCi/ml

h. PCS Xe-133 Specific Isotope Activity: 40.0 pCi/ml

2. Secondary System Chemistry

a. Primary to Secondary Leak Rate: 0.001 gpm

b. Offgas Xe-133: 5.42E-6 pCi/ml

c. Condenser Air In-leakage: 1 scfm

d. A and B Steam Generator Gross Gamma Activities: Less than 5.6E6

                      µCi/ml

• K. PCS Leak Rate (most recent results)

1. Identified: 0.08 gpm

2. Unidentified: 0.044 gpm

3. Total: 0.124 gpm 0830 - 0900 (0000 - 0030)

A. The exercise begins with the hot lab Chemistry Technician reporting initial PCS activity results of 30 pCi/gm Iodine dose equivalent 1-131. Subsequent backup samples will yield similar results, ie, results that permit continued operation for up to 72 hours under the LCO of Technical Specifications 3.1.4.b and c (which are designed to accommodate possible Iodine spiking phenomenon resulting from thermal power excursions such as the previous weekend). B. Expected Actions:

1. Conclude that fuel damage may be indicated and refer to ONP-11.1, "Fuel Cladding Failure" and Emergency Plan Implementing Procedure EI-1.

2. The Shift Supervisor will assume the Site Emergency Director (SED) position

• and:

a. Classify an "ALERT" based on "Primary.Coolant Iodine-131 Dose Equivalent Concentration greater than 25 J,iCi/gm."

b. Directs a public address announcement on the situation and sounding of the emergency siren.

c. Delegates actions and notifications identified in EI-1 and marked on EI-2.1 Attachment 1, including emergency staff augmentation; personnel

                   . accountability; activation of the Operational Support Center (OSC) and Technical Support Center (TSC); dose assessment; and activation of the Emergency Response Data System (ERDS).

d. Directs completion of the emergency notification forms of EI-3 and NOD Form 3160.

e. Commences 15 minute notifications per EI-3.

3. The PCS Sample requirements for isotopic Iodine analysis of Technical Specification Table 4.2.1 will be invoked .

• 0900 - 0930 (0030 - 0100)

A. Activation of the Site Emergency Plan continues. B. "Rod Drive Seal Leakoff High Temperature" Alarm is received (EK-09-54) due to a small (approximately.0.1 gpm)_ increase in seal leakage on CRD-17. C. "Containment Sump High Level" Alarm is received (EK-13-51) due to a Service Water leak of approximately 15 gpm which has developed on Containment Air Cooler VHX-3. (NOTE: Due to simulator modeling limitations, indicated Containment Sump Level will ramp to 10% and remain there for the duration of the exercise, rather than respond as expected to attempts to drain the sump.) D. Progressive fuel rod failures in the affected Reload "L" fuel bundle commence. E. Expected Actions:

1. Complete staffing of the OSC, MSC and TSC and turnover responsibility.

2. Continue PCS activity samples via NSSS sample system while considering implementation of EJ,..7 .0, Emergency Post-Accident Sampling Decision

• Process.

3. Alarm Response Procedures will force players to consider the possibility of a

• PCS leak, although the two alarming conditions (Rod Drive Seal Leakoff High Temperature and Containment Sump High Level) are actually unrelated.

No other corresponding symptoms are present, and it would be appropriate to consider a Containment entry, although contllhment conditions are somewhat suspect. Also, performance of a quick (one hour) PCS leak rate calculation would be prudent (if performed, an increase of approximately 0.1 gpm due to the leaking CRD-17 seal would be indicated).

4. Players will attempt to obtain a sample of Containment Sump contents to assist in determining leakage source. If successful, high sodium will be indicated, symptomatic of a Service Water leak.

5. Players will recognize that the Containment Sump leakage represents a new dirty radwaste source (greater than 21,000 gallons/day) that will quickly expend remaining dirty waste storage capaCity and will attempt to identify alternate storage options and maintenance activities to increase radwaste processing capability (eg, expedite repairs to "B" evaporator).

6. Repairs will be expedited to Letdown Flow Indicator FIC-0202.

0930 - 0945 (0100 - 0115)

• A.

B. JPIC is operational. PCS activity levels increase as the Reload "L" fuel bundle rods fail. C. Players make preparations to transfer radwaste to alternate storage locations using available equipment and temporary modifications as necessary. Meanwhile, dirty radwaste activity levels continue to' increase due to CRD seal leakage to the Containment Sump and NSSS sampling activities. D. Control Room personnel continue activities to identify and quantify the containment water source. E. Expected Actions:

1. Players will identify adequate radwaste storage capacity to accommodate dirty waste and permit continued operation. Acceptable options include:

a. Treated Waste Monitor Tanks T-66A and T-66B (10,800 gallons capacity).

b. Filtered Waste Monitor Tanks T-63A and T-63B (5,400 gallons capacity) .

c. Laundry Drain Tanks T-70A and T-70B (1,100 gallons capacity) .

• d. Temporary modifications, valve lineups and procedures are required for all options identified.

2. The containment water source will be identified as service water and the LCO of Technical Specification 3.4.2 will be entered.

3. Players will not elect to retain water in the Containment Sump due to negative implications for various accident analyses.

4. Players may decide that they cannot support continued operation and commence plant shutdown. This is permissible, although unnecessary at this point, but if undertaken it must be controlled to as slow a rate as possible

("to minimize fuel effects") since scenario data sheets will not reflect the shutdown until 0945 (0115). 0945 - 1000 (0115 - 0130) A. The latest PCS activity sample indicates 50 pCi/gm Iodine dose equivalent 1-131. This is confirmed by a second sample.

• B. Expected Actions:

1. Commence plant shutdown to conform to Technical Specification 3.1.4.c.

1000 - 1007 (0130 - 0137) A. A double-ended rupture of a single tube in Steam Generator E-50B occurs, resulting in a primary to secondary leak which exceeds the capacity of the Charging Pumps. B. Operators trip the Reactor, or an automatic trip on Thermal Margin/Low Pressure occurs. C. Two seconds after the Turbine Generator trips and busses lA and lB fast transfer to Startup Transformers 1-1 and 1-3, respectively, the 'R' Bus trips due to failed sudden pressure relay 486X-l l on Startup Transformer 1-1, deenergizing Busses lA and lB and supplied loads (Primary Coolant Pumps and Condensate Pumps). D. An Iodine splice generated by the trip (spiking factor = 500) occurs. E. Auxiliary Feedwater Automatic Actuation occurs due to low level in the 'A'

• Steam Generator and commences feeding both S/G's.

F. Five minutes after the trip, Safety Injection is automatically initiated at 1605

• G.

psia. Flow to the PCS begins approximately fourteen minutes after the trip. Expected Actions:

1. EOP-1.0 standard post-trip actions will be commenced.

2. A GENERAL EMERGENCY will be declared due to loss of all three fission product barriers, as all Atmospheric Dump Valves automatically open on the trip for core heat removal.

1007 - 1015 (0137 - 0145) A. EOP-1.0 standard post-trip actions are completed. B. The Pressurizer, which had emptied shortly after the trip, begins to refill from Safety Injection flow. C. Expected Actions:

1. The EOF will be declared operational and assume responsibilities for Protective Action Recommendations .

• 2. EOP-5.0, "Steam Generator Tube Rupture" will be invoked (EOP-9.0, "Functional Recovery Procedure" is also acceptable, although unnecessary).

1015 - 1055 (0145 - 0225) A. Operators implement Eo:P.:5.0 actions and, since no Primary Coolant Pumps are operating and the Turbine Bypass valve is disabled by low condenser vacuum, commence steaming both Steam Generators via the Atmospheric Dump Valves to provide uniform PCS cooling. This creates a direct release path via 'B' Steam Generator Atmospheric Dump Valves. B. The faulted Steam Generator is readily recognized as E-50B, but isolation is not permitted until the PCS is cooled below 525 degrees Fahrenheit as forced circulation does not exist. C. Since PCP's are not is service, PCS depressurization is attempted using Charging Pumps and Auxiliary Spray CV-2117; however, CV-2117 is failed in the closed position due to a burned up solenoid (position indication is still operable). This will hamper pressure reduction and place reliance on Safety Injection throttling to minimize the d/p across the failed S/G 'B' tube, which will not be effective in

• preventing the SIG from filling solid and challenging the code safeties.

D. Expected Actions:

• 1. Operators will terminate Auxiliary Feedwater to SIG 'B' (it will continue to fill via the Failed Tube).

2. The PCS will be cooled below 525 degrees fahrenheit using Atmospheric Dump Valves and Auxiliary Feedwater to SIG 'A' and SIG 'B' will be isolated. The release via the SIG 'B' Atmospheric Dump Valves will thus cease for the present.

3. Protective Action Recommendations will be made to the State recommending evacuation of affected sectors in Van Buren and Allegan counties.

1055 - 1145 (0225 - 0315) A. 'B' Steam Generator, although isolated, continues to fill rapidly via the ruptured tube due to the high primary-to-secondary dP created by the inability to . adequately reduce PCS pressure (Note: The fill rate will be artificially adjusted on the simulator such that the 'B' SIG and connecting steam piping will fill solid in one hour.)

• B.

C. Operators continue to cool down as rapidly as possible under natural circulation conditions using the unaffected 'A* Steam Generator (approximately* 50 degrees Fahrenheit/hr). Expected Actions:

1. Operators will attempt to combat the rapidly increasing S/G 'B' level by transferring Miscellaneous Waste Hold Tank contents to a Clean Waste Receiver Tank to make room to drain S/G 'B' to Miscellaneous Waste (requires jumpering by I&C of SIG Blowdown Monitor RIA-0707); however, this attempt will result in the remaining Miscellaneous Waste Transfer Pump, P-92B, failing due to motor overheating. Alternate drain paths will not be identified.

2. Area surveys will identify affected plant sectors, and access will be restricted/controlled as appropriate.

3. Operators may attempt to regain forced circulation by backfeeding the Main Transformer; this option will not be permitted until after 1145 (0315) to hamper PCS pressure reduction efforts. (Also, the simulator does not currently model backfeed.)

1145 - 1245 (est) (0315 - 0415) (est)

• A.

B.

              'B' Steam Generator level is greater than 100% and is filling the connecting Main Steam piping.
              'B' SIG contents are now highly radioactive with PCS fission products.

C. Players are faced with two choices:

1. Permit steam piping to fill solid and hope for the best.

2. Steam SIG 'B' to cool it and reduce its level to prevent challenging Main Steam safeties.

D. Election of either option of C above will result in a release to the atmosphere (if players permit steam piping to fill solid, either a code safety will open and fail open or an overstressed piping section will yield and fail, depending on how successful players have been at reducing 'B' SIG pressure previously). E. Expected Actions:

1. Players will elect to Steam 'B' Steam Generator as necessary to maintain level indication on scale until such a time as 'B' SIG pressure is below safety

• valve setpoints and then permit steam piping to fill solid. This action permits planned releases that can be coordinated with evacuation and other Protective Action Recommendations and offsite monitoring efforts.

2. Protective Action Recommendations will be revised as appropriate.

3. The release of this pbase of the exercise may be continued as long as necessary to demonstrate exercise objectives.

1245 (est) - 1500 (0415 (est) - 0630) A. Players are provided new plant conditions. Personnel not involved in recovery planning terminate participation and conduct critiques. B. Approximately 8 hours have elapsed from the time of the plant trip. Forced circulation has been regained by backfeeding the Main Transformer and restarting PCP's P-50B and P-50C. Shutdown Cooling is in service, the Pressurizer is filled solid, and PCS cooldown is in progress at 40 degrees fahrenheit/hr. C. 'B' Steam Generator is re-isolated (or steaming to atmosphere slowly if the piping break option was necessary) and is filled solid .

D. Expected Actions:

1. Implement plans for reentry/recovery.

2. Continue to cool down at the maximum permitied rate.

3. Implement appropriate radiological controls for both primary and secondary systems high fission product contents.

4. Consider options to minimize release from the steam line break (if the piping break option was necessary), eg, temporary barriers/enclosures.

1500 + (0630 +) Terminate exercise.

MESSAGE SHEETS

Scenario: PALEX-92 Time: 0800

• Message No: 1 Scenario Time: -0030 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Message For: Operators Simulated Plant Conditions:

See attached Initial Conditions and Data Sheets. Message: Announce following over the Plant Public Address System when directed by the Controller: 11 Attention all personnel. The emergency exercise will commence shortly .. All announcements related to the drill will be preceded by and followed by the statement, 'This is a drill'. 11

• FOR CONTROLLER USE ONLY Controller Notes:

1. 2. 3. Act as off going SS and give turnover to players. Inform Operators that alarms provided are key alarms only. 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 at full power at the end of core life (11.1 GWD/MTU). No B. Technical Specification surveillance activities in progress. The plant will ~mmence coast down shortly, with shutdown for refueling outage scheduled for next weekend. Based on current PCS activity trends, Reactor Engineering anticipates finding approximately 5 leaking fuel assemblies during the refueling (all burnt assemblies are to be inspected during the shuffle). C. Plant radwaste capability is extremely taxed. Both radwaste evaporators and the VRS are currently out of service, and just enough clean waste holdup capacity is available to support operation to the weekend and subsequent shutdown and boration. D. Management expectations as conveyed to operators are. that, due to high system demand created by the unseasonably early warm spring weather, every attempt consistent with safe plant operation shall be made to adhere to the scheduled weekend shutdown and that no testing or evolutions which have the potential to jeopardize this goal are to be authorized (the reason for this admonition is that an attempt to perform turbine valve testing the previous weekend to check out new DEH controls had resulted in an unanticipated derate to 60%) .

• E. Equipment in a degraded mode:

1. Radwaste Evaporator M-59A has been out of service for one month due to non-availability of obsolete parts.

2. Radwaste Evaporator M-59B is out of service to replace "rocked up" recirculation pump discharge-lines.

3. The Volume Reduction System is out of service while repairs are made to the extruder.

4. Miscellaneous Waste Transfer Pump P-92A is tagged out for pump rebuild and motor replacement and is completely disassembled.

5. Letdown Flow Indicator FIC-0202, while in service, is out of calibration and reads approximately 5 gpm too low. A work request has been submitted.

6. Containment Sump Level Indicator LIA-0359 is out of service due to failed meter movement. A replacement meter is on order.

F. Rad waste Systems tank status:

• Clean Waste System T-64A CWRT Level 95%

T-64B CWRT Level 95 % T-64C CWRT Level 56% T-64D CWRT Level 0% Dirty Waste System T-92A Misc Waste Tk Level 97% T-92B Misc Waste Tk Level 98% T-92C Misc Waste Tk Level 75 % T-94A Clean Cone Tk Level 98 % T-96 RBAT Level 10% 15,200ppm T-94B Clean Cone Tk Level 97% T-95A Dirty Cone Tk Level 97% T-95B Dirty Cone Tk Level 98 % G. Existing Alarm Conditions:

1. Annunciator EK-11-60, "Radwaste Panel C-105 off-normal"*

2. Annunciator EK-13-68, "Radwaste Panel C-40 off-normal"

3. Annunciator EK-07-71, "Volume Control Radiation Monitor High Radiation" has just been received. Chemistry has been directed to sample the PCS for activity and is in the process of obtaining the sample.

H. Meteorological Conditions are as follows:

• Unusually warm and dry spring conditions exist, with sustained winds from the southwest.

a. Wind Speed: 2-4 mph

b. Wind Direction: 225 degrees

c. Stability: D/E

d. Ambient Temperature: 80-90 degrees Fahrenheit I. Primary and Secondary Chemistry:

1. Primary System Chemistry (prior to sample in progress)

a. pH: 7.07

b. Boron: 5 ppm

c. Dissolved Oxygen: less than 0.002 ppm

d. Hydrogen: 25 cc/kg

       .. e. Total Beta Gamma Activity: 2.04 µCi/ml

• f.

g. Iodine Dose Equivalent: 0.053 pCi/ml Total PCS Gas Activity: 15.2 µCi/ml*.

h. PCS Xe-133 Specific Isotope Activity: 40.0 µCi/ml

2. Secondary System Chemistry

a. Primary to Secondary Leak Rate: 0.001 gpm

b. Offgas Xe-133: 5.42E-6 pCi/ml

c. Condenser Air In-Leakage: 1 scfm

d. A and B Steam Generator Gross Gamma Activities: Less than 5.6E-6

                µCi/ml J. PCS Leak Rate (most recent results)

1. Identified: 0.08 gpm

• 2.

3. Unidentified: 0.044 gpm Total: 0.124 gpm.

PAI EX 9? Date SEPTEMBER l 1992 Message # l (Page 1) Ti me .l2fill.Q Scenario Time .:.Q.O.lO. Time Jump

• Scenario Time Jiimp Sumps P-7A .Pti. P-7B .s.Ifil P-7C .Pti SW Critical Hdr Press A ll.. B ll.. psig Pumps P-52A .s.Ifil P-528 .Pti P-52C .s.Ifil FPC Pumps P-51A .Pti e Pumps P-9A .D.EE P-9B .D.EE P-41 .D.EE P-518 .D.EE Ccctaicmect Ccclec Becicc Eacs VlA .Pti V2A .Pti V3A .Pti V4A .Pti VlB .Pti V2B .Pti V3B .Pti V4B .Pti CCW Cooler Outlet Temp A ll.. F B lZ... F Containment Spray Pumps P-54A .D.EE P-54B .D.EE P-54C .D.EE HPSI Pumps P-66A .D.EE P-66B .D.EE LPSI Pumps P-67A .D.EE P-67B .D.EE satetv Iciecticc Sucticc Supp]y Train A Train B CV-3057 (SIRW) QPEti CV-3029 (SIRW) tLDS.fl2 CV-3031 (SIRW) QPEti CV-3030 (Sump) tLDS.fl2 1 etdcW11 Chacging Intermediate Press Letdown Temp ll3. F Flow H gpm Letdown Line Temp Zil F Line Temp la! F Letdown Flow 35 gpm Pumps P-55A .Pti P-55B .D.EE P-SSC .D.EE Vclume CcctccJ Tack Temp lD5 F Pressure ZS. psi Level 55  % PCP Control Bleedoff Pressure il psig Shutd0wc Cooling System SOCS from PCS (R) Bl F SOCS to PCS (R) Bl F Quecch Tack Temp lPZ F Pressure :l psig Level .6.3. X Pcimarv Ccc]act system Pressurizer Pressure (R) ZD.5.l psi a PCS Tave (R) Loop 1 (TR-0111) .5.59. Loop 2 (TR-0121) .5.59.

Pressurizer Level (R) LRC-OlOlA .5B. x LRC-OlOlB .5B. x LIA-0102A H x Pzr Htr Amps LCC 15 ill LCC 16 ill PORV PRV-1042B tLDS.fl2 PRV-1043B tLP.S.Ell Block Valve MOV-1042A tLJ2Sfl2 MOV-1043A tu2.S..ED. PCPs P-SOA .Pti P-50B_ .Pti P-50C .Pti P-500 .Pti Reactor Power Level NI-01 lPE+ofi NI-02 '...l.O.E+/-il5 NI-03 !lZE+oZ NI-04 !lZE+oZ Nl-05 lPil NI-06 .!la NI-07 .!la NI-08 1PE+o3 t=ill. AfW System AFW Pump P-8A .D.EE P-8B .D.EE P-8C .D.EE . AFW Pump Amps P-8A ~ P-8C ~ AFW Pump P-8B Steam Pressure ~ psig AFW Disch Press P-8A & P-8B lO P-8C lO psi Secccdacy System MSIV Bypass MOV-0501 tu2.S..ED. MOV-0510 tLJ2Sfl2 MSIV's CV-0501 QPEti CV-0510 QPEti MFP Suction Pressure .3.3S. psig HFP Discharge Pressure A l.CU2! B l.CU2! psi Moisture Separator Drain Tank Level ,5A X Condenser Hotwell Level .6.3. X Atmospheric Dump Valves tu2.S..ED. Condenser Vacuum Z1...5 in Hg. Heater Drain Pump Status P-lOA .Pti P-lOB .Pti Gland Seal Condenser Vacuum l!..Z in Hg. Condensate Pump Status P-2A .Pti P-2B .Pti (Demand Log + Constant, Rod, or Flux/Temp) Gross MW .8lZ Net MW 1l!J. Core Exit Thermocouple Temperature .5B.l..l F Control Rod Position GPl .l3.l GP2 .l3.l GP3 .L'il GP4 .L'il GP5(P) .L'il GP6(A) .l3.l GP7(B) .l3.l

 . k Rods          HOliE      # ~

PAI EX 92 Date SEPJEMRFR 1992 Message # l (Page 2) Time .llfil2.ll Scenario Time .:..l2.ll3.ll Time Jump Scenario Time Jump 1 Level .9.12 % T~939 Level trument Air Pressure tainment Building Pressure

                                           ~
                                                   '"psig
                                           .li2Z psig Condensate Storage Tank Level T-2 Dome Temperature .a.a         F     Humidity ~
                                                                                                                               .al2
                                           .12 G A Compartment                                                             Temperature         Bl        F     Humidity .5!

S/G B Compartment Temperature M F Humidity .5! - SIRW Tank Level WR Containment Pressure (R) Containment Sump Level

                                           .9Z l i psi a"                            Containment Water Level (R)

SI Tank Level (%)

                                           .12 A .sz.
                                                    "               B .4a                         c  .4a
                                                                                                                               .12 D .4a SI Tank Pressure (psig)                A 2.3.3.                    B .zz.a                       c  .2.'i.12               D ZJ!

PANE! K-13 SIAS Alann fill Containment High Pressure Alann fill Containment High Radiation Alann fill Concentrated Boric Acid Tank Levels T53A .9Z...5 % T53B 95.2 % Reactor Vessel DP z.a..z psid PDRV Discharge Temperature .a.a F I. Pzr Safety Valve Discharge Temp (F) RV-1039 .Ba RV-1040 .Ba RV-1041 .Ba PCP Current (Amps) P-50A P-50B .592. P-50C ,,5ga P-50D .5ZZ PCS Flow Pressure Level (cold) !i..l.  % Loop Thot ( F) Loop l Loop 2 .saz. Loop Tcold (F) Loop l Loop 2 .5.3.S Tcold Wide range Loop l Loop 2 ill Subcooling Temp Press llfi psi PCS Prssure WR NR .6.12.0. psia Steam Generator A Steam Generator B (WR) .6.5. % (NR) .6.5.  % (WR) .6.5. % (NR) Z.!ll2 psia Z.!ll2 psia .6.5. " Steam .S..S. PPH Feed .S..S. PPH Steam .S..S. PPH Feed .S..S. PPH Note: Steam and Feed Flow X 1000000 AFW Flow to A S/G From P-BA&B .12 From P-BC .12 AFW Flow to B S/G From P-BA&B .12 From P-BC .12 Condenser Vacuum (R) z.a PCP Seal Leakoff Flow P-50A l..l PPH P-50B l..l PPH P-50C l..l PPH P-50D l..l PPH t.:.12! Diesel Generator Frequency 1-1 .12 1-2 li. 1-C BUS Voltage Z!M Amps 2.B.5 1-D BUS Voltage Z!.fll Amps ill C-l l Bilek C-llA Containment Area Monitors (R/Hr) RIA-1805 ...!lZ.12 RIA-1806 ...illi RIA-1807 ...lZ.12 RIA-1808 ....12.B.Q High Range Containment Monitors (R/Hr) RIA-2321 l RIA-2322 l Containment Hydrogen Concentration (%) AI-2401R .12 AI-2401L .12 Main Steam Line Ganma (cpm) RIA-2324 2.3. RIA-2323 z.s. Stack Monitors RIA-2325 ll2.ll cpm RIA-2326 fill cpm RIA-2327 -2. mr/hr

Sceruµio: *. PALEX-92 Time: 0830

• Message No: 2 PALISADES NUCLEAR PLANT Scenario Time: 0000 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Message For: Chemistry Simulated Plant Conditions:

Same as Initial Conditions Message: PCS activity sample results requested by Control Room indicate 30 uCi/gm Iodine Dose Equivalent I-131.

• FOR CONTROLLER USE ONLY Controller Notes:

Provide backup sample results of this same or less magnitude (at least less than 40

        µCi/gm) at appropriate intervals, until 0945.

Action Expected:

1. Chemistry will notify the *controf Room.

2. Operators will:

a. Request backup samples

b. Refer to ONP-11.1

c. Declare an ALERT. (The real Control Room must sound the siren.)

Scenario: PALEX-92 Time: 0845

• Message No: 3 PALISADES NUCLEAR PLANT Scenario Time: 0()15 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Message For: Operators Simulated Plant Conditions:

Message:

1. See Data Sheets.

2. Annunciator status is unchanged.

• FOR CONTROLLER USE ONLY Controller Notes:

Action Expected: Continue SEP activation .

Date SEPTEMBER 199? Message I .3. (Page 1) Time l2B!5 Scenario Time .lli2l5 Time Jump Scenario Time Jump umps P-7A mt P-78 ilBI P-7C mt SW Critical Hdr Press A Z!.. 8 Z!.. psig umps P-52A Slll'.. P-528 mt P-52C Slll'..

• FPC Pumps P-51A mt
• Pumps P-9A .Q.EE P-98 .Q.EE P-41 .Q.EE P-518 .Q.EE Coctajcmect Coolei:: Becji::c Eacs 0

VlA mt V2A mt V3A mt V4A mt Vl8 mt V28 mt V38 mt V48 mt CCW Cooler Outlet Temp A ZL. F 8 1L F Containment Spray Pumps P-54A .Q.EE P-548 .Q.EE P-54C .Q.EE HPSI Pumps P-66A .Q.EE P-668 .Q.EE LPSI Pumps P-67A .Q.EE P-678 .Q.EE Safety Icjectjoc Suctioc Supply Train A Train 8 CV-3057 (SIRW) .DfEli CV-3029 (SIRW) WlS.EI2 CV-3031 (SIRW) .DfEli CV-3030 (Sump) WlS.EI2 tetdown Chai::ging Intermediate Press Letdown Temp lU F Flow i l gpm Letdown Line Temp Z5l F Line Temp 3.6! F Letdown Fl ow JS gpm Pumps P-55A .Qli P-558 .Q.EE P-55C .Q.EE Vpl 1nne Conti::ol Tank Temp lil5 F Pressure Z5 psi Level .li6 X PCP Control 8leedoff Pressure il psig Sh1Jtdowc Cool; cg System SD~S from PCS (R) al F SOCS to PCS (R) al F Ouecch Tack Temp JJ2Z F Pressure .:l psig Level .6.3.  % Pi::imai::y Coolact System Pressurizer Pressure (R) .wi psi a PCS Tave (R) Loop 1 (TR-0111) .5.59. Loop 2 (TR-0121) s.59. Pressurizer Level (R) LRC-0101A .s.a x LRC-OlOlB .s.a x LIA-0102A i l x Pzr Htr Amps LCC 15 ill LCC 16 lil PORV PRV-1042B WlS.EI2 PRV-1043B WlS.EI2 Block Valve MOV-1042A llQSfI2 MOV-1043A WlS.E.12 PCPs P-50A .Qli P-508 .Qli P-50C .Qli P-500 .Qli Reactor Power.Level Nl-01 !OE+OS NI -Of ....l.llE+/-0.5 Nl-03 9ZE+D2 Nl-04 9ZE+DZ Nl-05 .lQl2 Nl-06 9.6. Nl-07 9.6. NI-08 1Df+Q3 AEW System AFW Pump P-8A .Q.EE P-8B .Q.EE P-8C .QEE AFW Pump Amps P-8A D. P-8C D. AFW Pump P-8B Steam Pressure D. psig AFW Di sch Press P-8A &P-8B lD. P-8C lD. psi Secocdai::y System MSIV Bypass MOV-0501 WlS.EI2 MOV-0510 WlS.E.12 MSIV's CV-0501 QPf1t CV-0510 QPf1t MFP Suction Pressure .3.JS psig MFP Discharge Pressure A lD..12! B lD..12! psi Moisture Separator Drain Tank Level Ji! X Condenser Hotwell Level .6.3. X Atmospheric Dump Valves tL!lS.Ell Condenser Vacuum Zl..5 in Hg. Heater Drain Pump Status P-lOA mt P-lOB .Qli Gland Seal Condenser Vacuum l!..Z in Hg. Condensate Pump Status P-2A mt P-2B .Qli

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

Gross MW .8ll. Net MW ~ Core Exit Thermocouple Temperature .5.a.3...l F ~t"'l Rod '°'ltlon GPl lll GP2 ill GP3 ill GP4 ill GP5(P) ill GP6(A) ill GP7(B) ill ck Rods lilllif I D.

Date SEPTEMBER l 199? Message I .J. (Page 1) Ti me .llB!5. Scenario Time .12.0.l.5 Time Jump Scenario Time Jump SW Sumps P-7A mi . P-78 .ilB1. P-7C .QH SW Critical Hdr Press A lL 8 lL psig Pumps P-52A .ilB1. P-52B mi P-52C .ilB1.

• FPC Pumps P-51A mi e Pumps P-9A .o.E£ P-9B .o.E£ P-41 0.E£ P-51B .o.E£
• Containment Cooler Recjrc Fans VlA mi V2A mi V3A .QH V4A .QH VlB mi V2B mi V3B mi V4B mi CCW Cooler Outlet Temp A LL F B 1L F Containment Spray Pumps P-54A .o.E£ P-54B .o.E£ P-54C 0.E£ HPSI Pumps P-66A .o.E£ P-66B 0.E£ LPSI Pumps P-67A .o.E£ P-678 .o.E£ Safety Iniection S11ction Supply Train A Train B CV-3057 (SIRW) .QfEfi CV-3029 (SIRW) .c.L!lS.Ell CV-3031 (SIRW) .QfEfi CV-3030 (Sump) WlS.fll letdown Charging Intennediate Press Letdown Temp ll3. F Flow ~ gpm Letdown Line Temp lli F Line Temp .18! F Letdown Fl ow .J.5 gpm Pumps P-55A mi P-55B .o.E£ P-55C .o.E£ Vol 1nne Contrpl Tank Temp lil5 F Pressure Zfi psi Level fili  % PCP Control Bleedoff Pressure .il psig Shutdown Cool j ng System SOCS from PCS (R) B.3. F SOCS to PCS (R) B.3. F Oyench Tank
• Pressurizer Pressure (R)

PCS Tave (R) Pressurizer Level (R) Pzr Htr Amps Temp lD2. F

                                             .2.Dfil. psi a Pressure .:.l Primary Cpplant System Loop 1 (TR-0111) .559. Loop 2 (TR-0121) .559.

LRC-OlOlA .sa % LCC 15 ill LRC-OlOlB fill. LCC 16 ill psig Level LIA-0102A ~

                                                                                                                              .li3.    "

PORV PRV-1042B .c.L.C.S.E.12 PRV-1043B WlS.fll Block Valve MOV-1042A illl.S.ED. MOV-1043A WlS.fll PCPs P-50A !lli P-50B !lli P-50C !lli P-50D !lli Reactor Power Level NI-01 ....l.!lE+/-.12.6 NI - 02 .....lllE+/-.0..6. NI-03 9ZE+ll2 NI-04 9ZE+ll2 NI-05 .l.ll.O. NI-06 sa Nl-07 sa NI-08 ICE+CJ

 ~

AF\/ System AFW Pump P-BA QEE P-BB QEE P-BC QEE AFW Pump Amps P-BA D P-BC D AFW Pump P-BB Steam Pressure D psig AFW Disch Press P-BA & P-BB .lil P-BC .lil psi Secondary System MSIV Bypass MOV-0501 illl.S.ED. MOV-0510 WlS.fll MSIV's CV-0501 .QfEfi CV-0510 .QfEfi MFP Suction Pressure .J..:3.5 psig MFP Discharge Pressure A lll..ll! B lll..ll! psi Moisture Separator Drain Tank Level ~ % Condenser Hotl'le 11 Level .li3. % Atmospheric Dump Valves WlS.fll Condenser Vacuum Zl...5. in Hg. Heater Drain Pump Status P-lOA .QH P-lOB !lli Gland Seal Condenser Vacuum 1!..Z in Hg. Condensate Pump Status P-2A mi P-2B !lli (Demand Log + Constant, Rod, or Flux/Temp) Gross MW .lil.Z Net MW 1lJJ. Core Exit Thennocouple Temperature .5al..l. F Control Rod Position GPl lll GP2 lll GP3 lll GP4 lll GP5(P) lll GP6(A) lll GP7(B) lll

~,, Rod* JillllJ:         , ~

Date SEPTEMBER l 1992 Message I l (Page 2) Time .QM5. Scenario Time .llJll5 Time Jump Scenario Time Jump T-81 Level 9.Q % T~939 Level .!9.  % Condensate Storage Tank Level T-2 a.12 rument Air Pressure * * .li2Z. psig ainment Building Pressure .12 psig Dome Temperature Ba F Humidity !S. A Compartment Temperature .az F Humidity .5! B Compartment Temperature .B.4 F Humidity .5! SIRW Tank Level .92. % - WR Containment Pressure (R) .li psia Containment Sump Level .12  % Containment Water Level (R) SI Tank Level (%) A 5Z B !8. c .. SI Tank Pressure (psig) A 2.3.3. B .zza PANE! K-13 SIAS Alarm liC2 Containment High Pressure Alarm liC2 Concentrated Boric Acid Tank Levels T53A az....s. T53B 95.2 Reactor Vessel DP PDRV Discharge Temperature .aa F 2.ll...Z psid Pzr Safety Valve Discharge Temp (F) RV-1039 .aa RV-1D4t PCP Current (Amps) P-50A ill P-508 .592. P-50C PCS Flow ll % Pressure Level (cold) Loop T!iot (F) Loop 1 .ill. Loop 2 .ill. Loop Tcold (F) Loop 1 fil Loop 2 fil Tcold Wide range Loop 1 fil Loop 2 .535 Subcooling Temp .sa F Press ill psi PCS Prssure WR znfil. NR fillll psi a Steam Generator A Steam Genera\ Level (WR) .6.5 % (NR) .6.5  % (WR) .6.5 Press lS.D. psi a lS.D. Flow Steam 5...5 PPH Feed 5...5 PPH Steam 5...5 I Note: Steam and Feed Flow x 100000 AFW Flow to A S/G From P-8A&B .12 From P-8C .12 AFW Flow to B S/G From P-8A&B .12 From P-8C .12 Condenser Vacuum (R) za PCP Seal Leakoff Flow P-50A l...l PPH P-508 l...l PPH P-50C l...l PPH

 ~

Diesel Generator Frequency 1-C BUS 1-D BUS C-11 Back C-llA 1-1 .12 Voltage lli! Voltage Z!8.l. 1-2 .a.. Amps z.as Amps !55 fO

                                                                                                                                     ~co
                                                                                                                                                  ~ot~

Containment Area Monitors (R/Hr) RIA-1805 ...llZ.12 RIA-1806 ....lll.!l tto\\et RIA-1807 ...lZ.12 RIA-1808 ...afil2 coll

                                                                                                                                                    ~\(

High Range Containment Monitors (R/Hr) Containment Hydrogen Concentration (X) Hain Steam Line Ganma (cpm) RIA-2321 AI-2401R RIA-2324 l

                                                                    .12 Z3.

RIA-2322 l AI-2401L .12 RIA-2323 ~ ~c.t\o\\ f. ~ Stack Monitors RIA-2325 l.ll.ll cpm RIA-2326 .6.D. cpm RIA-2327 ...2. mr/hr '2,.

c

• Scenario:

Message No: PALEX-92 4 PALISADES NUCLEAR PLANT Time: 0900 Scenario Time: 0030 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Message For: Operators Simulated Plant Conditions: See Data Sheets Message: Annunciator No. EK-09-54, "Rod Drive Seal Leakoff High Temperature" has just been received .

• FOR CONTROLLER USE ONLY Controller Notes:

Action Expected:

1. Complete SEP activation; communications turnover to TSC.

2. Refer to Alarm Response-Procedure and ONP-23.1.

Date SFPIEMBER 1992 Message I ! (Page 2) Time DS!lil Scenario Time .D.lllQ Time Jump Scenario Time Jump T-81 Level ~ % T~939 Level !a % Condensate Storage Tank Level T-2 B..D.  % trument Air Pressure * .lil2. psig tainment Building Pressure .c. psig Dome Temperature .B.B. F Humidity !5  % A Compartment Temperature .82. F Humidity ~  % B Compartment Temperature .8! F Humidity ~  % SIRW Tank Level .92. % - WR Containment Pressure (R) l l psi a Containment Sump Level .c.  % Containment Water Level (R) .c.  % SI Tank Level (%) A .5Z B ~ c ~ D ~ SI Tank Pressure (psig) A Zll B .2.2.8. c 2.3..C. D 23.! PANFI K-13 SIAS Alarm fill Containment High Pressure Alarm fill Containment High Radiation Alarm fill Concentrated Boric Acid Tank Levels T53A .91....5 % TS3B 95.2 % Reactor Vessel DP 2..0...Z. psid PORV Discharge Temperature .a.a. F Pzr Safety Valve Discharge Temp (F) RV-1039 .a.a. RV-1040 RV-1041 .8.8. PCP Current (Amps) P-SOA .5.Z.5 P-50B fil P-SOC P-50D ill PCS Flow ll % Pressure Level (cold) Loop Thot ( F) Loop 1 .5.82. Loop 2 .5.82. Loop Tcold (F) Loop 1 fil Loop 2 fil Tcold Wide range Loop l fil Loop 2 .5:ili Subcooling Temp fill. F Press 1l.6. psi PCS Prssure WR 2.0.6l NR fillil psi a Steam Generator A Steam Generator B Level (WR) .65 % (NR) .65  % (WR) .65 % (NR) .65  % Press 29..D. psi a 29..D. psi a Flow Steam .5.....5. PPH Feed .5.....5 PPH steam .5.....5. PPH Feed .5.....5. PPH Steam and Feed Flow x 1000000 Note: AFW Flow to A S/G From P-8A&B .c. From P-8C .c. AFW Flow to B S/G From P-8A&B .c. From P-8C .c. Condenser Vacuum (R) za PCP Seal Leakoff Flow P-SOA w. PPH P-5DB w. PPH P-50C w. PPH P-SOD w. PPH

 .t:.:..c..4 Diesel Generator Frequency               1-1 .c.                         1-2 .c.

• 1-C BUS Voltage Z!B! Amps .z.a.s 1-D BUS Voltage .2!Bl Amps ill C-ll Bat:kC-Jl6 Containment Area Monitors (R/Hr) RIA-1805 -ll.2.0. RIA-1806 ...ll.l..a RIA-1807 ..ll.D. RIA-1808 ....aa.c.

High Range Containment Monitors (R/Hr) RIA-2321 l RIA-2322 l Containment Hydrogen Concentration (%) AI-2401R .c. AI-2401L .c. Main Steam Line Ganma (cpm) RIA-2324 2:i RIA-2323 2.5 Stack Monitors RIA-2325 .3..0.0. cpm RIA-2326 .6..Q cpm RIA-2327 ...Z mr/hr

Scenario: .PALEX-92 Time: 0901

• Message No: 5 PALISADES NUCLEAR PLANT Scenario Time: 0031 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Message For: Operators Simulated Plant Conditions:

Message: Annunciator No. EK-13-51, "Containment Sump High Level" Alarm is received .

• FOR CONTROLLER USE ONLY Controller Notes:

Explain to players artificiality of Containment Sump indicated level response. Action Expected:

1. Refer to Alarm Response Procedure and ONP-23.1.

2. Initiate PCS Leakrate Calculation.*

3. Devise strategy to obtain sample of Containment Sump contents .

Scenario: .. PALEX-92 Time: 0915

• Message No: 6 PALISADES NUCLEAR PLANT Scenario Time: 0045 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Message For:
• Operators Simulated Plant Conditions:

Message: See attached Data and Alarm Sheets. FOR .CONTROLLER USE ONLY

• Controller Notes:

Action Expected: Initiate radwaste associated maintenance activities .

Date SEPTEMBER I 1992 Message I .6 (Page 1) Time il9l5 Scenario Time .Qil!5 Time Jump Scenario Time Jump SW Sumps P-7A OH P-78 ilBI P-7C OH SW Critical Hdr Press A 1A.. 8 1A.. psig . : . Pumps P-52A ilBI P-528 OH P-52C Sl.B.l FPC Pumps P-51A OH . e Pumps P-9A m P-98 m P-41 m P-518 fil C:cot'ai omeot C:ccl ec Beci cc Eaos VIA OH V2A OH V3A OH V4A OH Vl8 OH V28 OH V38 OH V48 OH CCW Cooler Outlet Temp A Zl.. F 8 11... F Containment Spray Pumps P-54A fil P-548 fil P-54C QEE HPSI Pumps P-66A fil P-668 QEE LPSI Pumps P-67A fil P-678 fil satetv Ioiectico S11Gtico Supply Train A Train 8 CV-3057 (SIRW) .Q.PfH CV-3029 (SIRW) tulSEl1 CV-3031 (SIRW) .Q.PfH CV-3030 (Sump) tulSEl1 I etdOW!] C:bacgiog Intermediate Press Letdown Temp ill F Flow H gpm Letdown Line Temp Z5l F Line Temp J.BA F Letdown Fl ow .3.S. gpm Pumps P-55A OH P-558 fil P-55C QEE li!cl ume C:cotccl Iaok Temp lll2 F Pressure 2.6 psi Level .6.6  % PCP Control 8leedoff Pressure Al psig SbutclcW!l C:ccliog System SOCS from PCS (R) .a.2 F SOCS to PCS (R) .a.2 F 01ieocb Tack

• Pressurizer Pressure (R)

PCS Tave (R) Pressurizer Level (R) Pzr Htr Amps Temp lQZ F

                                              .z.w. psi a Loop 1 (TR-0111) .s.59. Loop 2 (TR-0121)

LRC-OlOlA .5a X LCC 15 ill Pressure .:.l Pcimacy C:cclaot System LRC-01018 LCC 16 psig Level .6l LIA-0102A H X X PORV PRV-10428 tulSEl1 PRV-1043B Block Valve MOV-1042A tulSEl1 MOV-1043A PCPs P-50A OH P-50B P-50C OH P-500 Reactor Power Level NI-01 !OE+Q6 Nl-02 NI-03 qZE+Q? NI-04 NI-05 .9.9. NI-06 NI-07 SB. NI-08 AFlrl System AFW Pump P-BA m P-BB aEE P-BC m AFW Pump Amps P-BA .0 P-BC .0 AFW Pump P-BB Steam Pressure .O psig AFW Disch Press P-BA & P-BB l.P P-BC l.P psi Seccodacv System MSIV Bypass MOV-0501 tulSEl1 MOV-0510 tulSEl1 MSIV's CV-0501 .Q.PfH CV-0510 .Q.PfH MFP Suction Pressure 33! psig MFP Discharge Pressure A .l.Q.P! B lO.Q! psi Moisture Separator Drain* Tank Level .6! X Condenser Hotwell Level .6l X Atmospheric Dump Valves tulSEl1 Condenser Vacuum Zl...5 in Hg. Heater Drain Pump Status P-lOA OH P-lOB OH Gland Seal Condenser Vacuum l!..Z in Hg. Condensate Pump Status P-2A OH P-2B OH

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

Gross MW .BlZ Net MW ~ Core Exit Thermocouple Temperature .5al..Z. F Control Rod Position GPl lJl. GP2 lJl. GP3 lJl. GP4 lJl. GP5(P) lJl. GP6(A) lJl. GP7(B) lJl. ~** Rod* Jllll!E * ~

Date SEPTEMBER 199? Message I .Ii *(Page 2) Time .!2lU5 Scenario Time .D.lM5 Time Jump Scenario Time Jump T-81 Level ail % T~939 Level !9. % Condensate Storage Tank Level T-2 an rument Air Pressure * .lill psig ainment Building Pressure .D. psig Dome Temperature .Ba F Humidity !5 A Compartment Temperature .az. F Humidity M B Compartment Temperature ~ F Humidity M SIRW Tank Level gz  % - WR Containment Pressure (R) l i psi a Containment Sump Level 10. % Containment Water Level (R) .D. SI Tank Level (%) A .sz. B AB C AB D AB SI Tank Pressure (psig) A ill B z.za c Z.lil D ZJ! PANE! K-13 SIAS Al arm fill Containment High Pressure Alarm fill Containment High Radiation Alarm fill Concentrated Boric Acid Tank Levels T53A Sl...5 % T53B 95.2 % Reactor Vessel DP Z.D...2. psid PORV Discharge Temperature .aa F Pzr Safety Valve Discharge Temp (F) RV-1039 .aa RV-1040 RV-1041 .Ba PCP Current (Amps) P-50A ill P-50B .5Sl P-50C P-500 S1l. PCS Flow ll % Pressure Level (cold) Loop Thot ( F) Loop l .saz Loop 2 .saz Loop Tcold (F) Loop l .5.3.5. Loop 2 .5.3.5. Tcold Wide range Loop l .5.3.5. Loop 2 .5J.li. Subcooling Temp .5a F Press ill psi PCS Prssure WR Z.D.£l NR

• WI psi a Steam Generator A Steam Generator B Level (WR) .6.5 % (NR) .6.5  % (WR) .6.5 % (NR) .6.5  %

Press ill psi a ill psi a Flow Steam s...5 PPH Feed s...5 PPH Steam s...5 PPH Feed s...5 PPH Note: Steam and Feed Flow x 1000000 AFW Flow to A S/G From P-BA&B .D. From P-BC .D. AFW Flow to B S/G From P-8A&B .D. From P-8C .D. Condenser Vacuum (R) Zl PCP Seal Leakoff Flow P-50A w PPH P-50B w PPH P-50C w PPH P-50D w PPH t=Q! Diesel Generator Frequency 1-1 .D. 1-2 il . 1-C BUS Voltage ZAM Amps z.as 1-D BUS Voltage Z!Bl. Amps ill t:-ll Bai:k C-JJA Containment Area Monitors (R/Hr) RIA-1805 .J2Z.O. RIA-1806 .....Dll RIA-1807 -1ll2 RIA-1808 ...nan High Range Containment Monitors (R/Hr) RIA-2321 l RIA-2322 l Containment Hydrogen Concentration (%) Al-2401R .D. Al-2401L .D. Main Steam Line Ganma (cpm) RIA-2324 2.3. RIA-2323 ZS Stack Monitors RIA-2325 .3.lli2 cpm RIA-2326 fill cpm RIA-2327 ..Z. mr/hr

Scenario: * .PALEX-92 Time: 0915 Message No: 6 Scenario Time: 0045 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE ALARM SHEET Alarm Annunc Panel Number Alarm Window Description EK-07 71 Volume Control Radiation Monitor High Radiation EK-09 54 Rod Drive Seal Leakoff High Temperature EK-11 60 Radwaste Panel C-105 Off-Normal EK-13 51 Containment Sump High Level EK-13 68 Radwaste Panel C-40 Off-Normal

Scenario: .PALEX-92 Time: 0930

• Message No: 7 PALISADES NUCLEAR PLANT Scenario Time: 0100 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Message For: Operators Simulated Plant Conditions:

Message:

1. See Data Sheets.

2. Alarm Status is unchanged .

• FOR CONTROLLER USE ONLY Controller Notes:

Action Expected:

Date SEeIE!:IBEB l!!!!Z Message I 1 (Page 1) Ti me .'2!Uil Scenario Time .Qlllil Time Jump Scenario Time Jump t:ila SW Sumps P-7A OH. P-78 .s.I.Bl P-7C OH SW Critical Hdr Press A 1L 81L psig fl"'" P-52A .s.I.Bl P-528 OH P-52C .s.I.Bl FPC Pumps P-51A OH e Pumps P-9A .llEE P-98 .a.EE P-41 .llEE P-518 .llEE Ccctaicmect Coolec Becicc Eacs VlA OH V2A OH V3A OH V4A OH V18 OH V28 OH V38 OH V48 OH CCW Cooler Outlet Temp A ll.. F 8 lZ.. F Containment Spray Pumps P-54A .llEE P-548 .llEE P-54C .llEE HPSI Pumps P-66A .llEE P-668 .llEE LPSI Pumps P-67A .llEE P-678 .llEE Safetv Iciectioc Suctioc Supply Train A Train 8 CV-3057 (SIRW) .Qff!t CV-3029 (SIRW) tulS.Ell CV-3031 (SIRW) .Qff!t CV-3030 (Sump) tulS.Ell l etdQW!! Chanzing Intennediate Press Letdown Temp llJ F Flow .il gpm Letdown Line Temp .Z.SZ F Line Temp 38! F Letdown Flow .15 gpm Pumps P-55A OH P-558 .llEE P-55C .llEE Vol *nne Cont col Iank Temp lD.Z. F Pressure Zfi psi Level ~ X PCP Control Bleedoff Pressure Shutdown *Cool 1cg Systf!ll! SOCS from PCS (R) .B3. F SOCS to PCS (R) .B3. F ouecch Tack

• Pressurizer Pressure (R)

PCS Tave (R) Pressurizer Level (R) Pzr Htr Amps Temp lD.l F zw. psi a Loop 1 (TR-0111) .55ll Loop 2 (TR-0121) LRC-0101A .5a X LCC 15 ill Pressure .:l LRC-01018 LCC 16 psig ec1macy Coolact Systf!ll! Level 5l LIA-0102A .il X X PORV PRV-10428 tulS.Ell PRV-10438 Block Valve MOV-1042A tulS.Ell MOV-1043A tulS.Ell PCPs P-50A OH P-508 P-50C OH P-500 OH Reactor Power Level Nl-01 ]Qf+06 Nl-02 Nl-03 !!ZE+OZ Nl-04 !!ZE+OZ Nl-05 lD..Q NI-06 Nl-07 lla Nl-08 JOE+03 AfW System AFW Pump P-8A .llEE P-88 .llEE P-8C .llEE AFW Pump Amps P-8A D P-8C D AFW Pump P-88 Steam Pressure D psig AFW Disch Press P-8A &P-88 lD. P-8C lD. psi Secondary Systfflll MSIV Bypass MOV-0501 tulS.Ell MOV-0510 tulS.Ell MSIV's CV-0501 .Qff!t CV-0510 .Qff!t MFP Suction Pressure l3.! psig MFP Discharge Pressure A .ll2.ll! B .ll2.ll! psi Moisture Separator Drain Tank Level ~ X Condenser Hotwe 11 Level 5l X Atmospheric Dump Valves

• tulS.Ell Condenser Vacuum 21...S in Hg.

Heater Drain Pump Status P-lOA OH P-108 .D.tt Gland Seal Condenser Vacuum .l!..Z. in Hg. Condensate Pump Status P-2A OH P-28 OH (Demand Log + Constant, Rod, or Flux/Temp) Gross MW BJl. Net MW 11!J. Core Exit Thermocouple Temperature .5.a3...Z F Control Rod Position GPl l3.l GP2 l3.l GP3 l3.l GP4 l3.l GP5(P) l3.l GP6(A) l3.l GP7(B) l3.l

~k Rod*         llllllE     I D

Date SEPTEMBER J 1992 Message I Z (Page 2) Time mw1 Scenario Time .lll.!20 Time Jump Scenario Time Jump T-81 Level .ail X T-939 Level !9. x Condensate Storage Tank Level T-2 .all x rument Air Pressure * .l.llQ psig ainment Building Pressure .a psig Dome Temperature .Ba F Humidity .!S. x A Compartment Temperature Bl F Humidity .5.4 x B Compartment Temperature BA F Humidity .5.4 x SIRW Tank Level - WR Containment Pressure (R)

                                             .az     %

l i psi a Containment Sump Level l.12 x Containment Water Level {R) .a x SI Tank Level (X) A .5l B AB. c AB. D AB. SI Tank Pressure (psig) A Z.13. B .z.z.a. c ill D .z.y PANE! K-13 SIAS Alann fill Containment High Pressure Alann fill Containment High Radiation Alann fill Concentrated Boric Acid Tank Levels T53A gz_s x T53B 95.2  % Reactor Vessel DP 2.0..1 psid PORV Discharge Temperature .Ba F Pzr Safety Valve Discharge Temp (F) RV-1039 .Ba RV-1040 RV-1041 .Ba PCP Current (Amps) P-50A ill P-50B ill P-50C P-50D S1l. PCS Flow 1.4 x Pressure Level (cold) Loop Thot (F) Loop 1 .s.az Loop 2 .s.az Loop Tcold (F) Loop 1 fil Loop 2 fil Tcold Wide range Loop 1 fil Loop 2 .5.3.5 Subcooling Temp 2. F Press ill psi PCS Prssure WR Zil5l NR fil2ll psi a Steam Generator A Steam Generator B Level (WR) .as x (NR) .as x (WR) .as % (NR) .as  % Press Z9.!l psi a Z9.!l psi a Flow Steam .s...s PPH Feed .s...s PPH Steam .s...s PPH Feed .s...s PPH Note: Steam and Feed Flow x 1000000

• AFW Flow to A S/G AFW Flow to B S/G Condenser Vacuum (R)

PCP Seal Leakoff Flow From P-BA&B From P-BA&B P-50A

                                             .a
                                             .a 2l l...l PPH From P-BC From P-BC P-50B
                                                                       .a
                                                                       .a l...l PPH       P-50C    l...l PPH        P-50D   l...l PPH
 .c.:.12!

Diesel Generator Frequency 1-1 .a 1-2 .'2 - 1-C BUS Voltage Z!a! Amps z.a.s 1-D BUS Voltage Z!al Amps ill C-l l Back C-l Ja Containment Area Monitors (R/Hr) RIA-1805 .Jl2.l2 RIA-1806 ..J2.Ul RIA-1807 ....lZ.ll RIA-1808 .J2B.O. High Range Containment Monitors (R/Hr) RIA-2321 l RIA-2322 l Containment Hydrogen Concentration (%) AI-2401R .D. Al-2401L .D. Main Steam Line Ganma (cpm) RIA-2324 2.3. RIA-2323 Z.5 Stack Monitors RIA-2325 3.0.D. cpm RIA-2326 fill cpm RIA-2327 -Z mr/hr

Scenario: *. PALEX-92 Time: 0945

• Message No: 8 PALISADES NUCLEAR PLANT Scenario Time: 0115 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Message For: Operators Simulated Plant Conditions:

Message:

1. See Data Sheets.

2. Alarm status is unchanged .

• FOR CONTROLLER USE ONLY Controller Notes:

Action Expected:

Date SEPTEMBER 1 1992 Message I B. (Page 1) Time .D.9!5 Scenario Time .Ill.LS Time Jump Scenario Time Jump P-7A .IDi P-76 .s.IBl P-7C .IDi SW Critical Hdr Press A Z!... 6 Z!... psig .~s P-52A .sr.a.i . P-9A .QEE P-526 .IDi P-96 .QEE P-52C .s.Ifll P-41 .QEE FPC Pumps P-SlA .IDi P-516 .QEE

• Pumps Containment Cooler ~ecirc fans VlA .IDi V2A .IDi V3A .IDi V4A .IDi *
• V16 .IDi V26 .IDi V36 .IDi V46 .IDi CCW Cooler Outlet Temp A ll.. F 6 11... F Containment Spray Pumps P-54A .QEE P-54B .QEE P-54C .QEE HPSI Pumps P-66A .QEE P-66B .QEE LPSI Pumps P-67A .QEE P-67B .QEE Safety lniectjon Suction Suaply Train A Train B CV-3057 (SIRW) !2fEli CV-3029 (SIRW) .cLO.Sfll CV-3031 (SIRW) !2fEli CV-3030 (Sump) C1JlSfil 1etdown Charging Intermediate Press Letdown Temp lll F Flow A! gpm Letdown Line Temp Z.SZ. F Line Temp la! F Letdown Fl ow JS gpm Pumps P-SSA .IDi P-SSB .QEE P-SSC .QEE Volume Control Tank Temp lna F Pressure .2.5 psi Level ~ X PCP Control Bleedoff Pressure il psig Shutdown Cool j ng System SOCS from PCS (R) B.3. F SOCS to PCS (R) B.3. F Quench Tank
• Pressurizer Pressure (R)

PCS Tave (R) Pressurizer Level (R) Pzr Htr Amps Loop 1 (TR-0111) Temp lPZ. F LRC-OlOlA LCC 15 X psi a Pressure Loop 2 (TR-0121) LRC-01016 LCC 16

                                                                                 .:.1 prjmary Coolant System psig                       Level .53.

LIA-0102A A! X X PORV PRV-10426 PRV-10436 Block Valve MOV-1042A .l:l.!2SEl2 MOV-1043A .l:l.!2SEl2 PCPs P-SOA P-50B P-50C .IDi P-500 .IDi Reactor Power Level NI-01 NI-02. NI-03 9ZE+Q? NI-04 gZE+Q? NI-OS NI-06 NI-07 .9B. Nl-08 JQF+Q3 AfW system AFW Pump P-8A .QEE P-8B .DEE P-8C .DEE AFW Pump Amps P-8A ~ P-8C ~ AFW Pump P-8B Steam Pressure ~ psig AFW Disch Press P-8A & P-8B lO P-8C lO psi Secondary System HSIV Bypass MOV-0501 .l:l.QSfl2 MOV-0510 .cLO.Sfll HSIV's CV-0501 !2fEli CV-0510 !2fEli MFP Suction Pressure .3J! psig MFP Discharge Pressure A .l.0.05 B .l.0.05 psi Moisture Separator Drain Tank Level .6! X Condenser Hotwell Level .6Z % Atmospheric Dump Valves t1.QSfl1 Condenser Vacuum ZLl in Hg. Heater Drain Pump Status P-lOA .IDi P-lOB .IDi Gland Seal Condenser Vacuum ~ in Hg. Condensate Pump Status P-2A .IDi P-2B .IDi (Demand Log + Constant, Rod, or Flux/Temp) 41 . , Gross MW B.ll. Control Rod Position JlllllE , ~ Net MW ZZ.S GP! lll GP2 lll GP3 lll Core Exit Thermocouple Temperature GP4 lll GPS(P) lll GP6(A) lll

                                                                                                                                                      .5B1.Z GP7(B) .lll F

Date SEPTEMBER 1992 Message I .B. . (Page 2) Time .D.9!5 Scenario Time .D.l.l5 Time Jump Scenario Time Jump T-81 Level S.12 % T-939 Level Condensate Storage Tank Level T-2 .za trument Air Pressure

• tainment Building Pressure

                                                !9. %
                                                .l.QZ psig psig                       Dome Temperature .a.a            F     Humidity J5 A Compartment 7 B Compartment           .
                                                .D.

Temperature Temperature

                                                                                                       .B.Z.

M F F Humidity .5! Humidity .5! SIRW Tank Level WR Containment Pressure (R)

                                                .!!Z. %

l i psi a Containment Sump Level lll % Containment Water Level (R) .D.  % SI Tank Level (X) A .5Z. B !B. c !B. D !B. SI Tank Pressure (psig) A Zl3. B .zz.a c ZlO. D ill PANE! K-13 SIAS Alarm .tiO. Containment High Pressure Alarm .tiO. Containment High Radiation Alarm .tiO. Concentrated Boric Acid Tank Levels T53A sz...s  % T53B 95.2 " Reactor Vessel DP a.z psid PORV Discharge Temperature .a.a F Pzr Safety Valve Discharge Temp (F) RV-1039 .a.a RV-1040 RV-1041 .B..B. PCP Current (Amps) P-50A .ill. P-50B .5.92. P-50C P-50D S11. PCS Flow Pressure Level (cold) Loop Thot (F) Loop Tcold (F) Loop 1 Loop 1 Z!

                                                .5.BZ fil
                                                        "      Loop 2 Loop 2
                                                                           .5.BZ fil Tcold Wide range                Loop 1         fil            Loop 2      fil Subcooling                      Temp           .sa     F      Press       ill psi PCS Prssure                     WR             ZQ5l.          NR          filll2 psi a Steam Generator A                                          Steam Generator B Level                           (WR)           ~               (NR)       ~                 (WR)      ~                   (NR)    ~

Press Flow Steam ZS.12 psi a

                                                .5...5 PPH      Feed       .5...5 PPH
                                                                                      "     Steam ZS.12 psi a
                                                                                                       .5...5 PPH
                                                                                                                   "       Feed    .5...5 PPH Note: Steam and Feed Flow x 1000000 AFW Flow to A S/G           From P-8A&B .D.                 From P-8C .D.

AFW Flow to B S/G From P-8A&B .D. From P-8C .D. Condenser Vacuum (R) Zl. PCP Seal Leakoff Flow P-50A w. PPH P-50B w. PPH P-50C w. PPH P-50D w. PPH

 ,C:.Q!

Diesel Generator Frequency 1.:.1 .D. 1-2 -.0.

• 1-C BUS Voltage z.w. Amps z.as.

1-D BUS Voltage .zw. Amps ill r:-11 Back r:-1 JA Containment Area Monitors (R/Hr) RIA-1805 ....D.Z.D. RIA-1806 ....D.lli RIA-1807 ...lZ.ll RIA-1808 ....D..B.O. High Range Containment Monitors (R/Hr) RIA-2321 l RIA-2322 l Containment Hydrogen Concentration (%) AI-2401R .D. AI-2401L .n Main Steam Line Ganma (cpm) RIA-2324 2.3. RIA-2323 Z5 Stack Monitors RIA-2325 .3..D..Q cpm RIA-2326 fill cpm RIA-2327 ...Z mr/hr

Scenario:

• PALEX-92 Time: 0945
• Message No: 8A Scenario Time: 0115 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Message For: Chemistry Simulated Plant Conditions:

Message: Latest PCS activity sample indicates 50 pCi/gm Iodine Dose Equivalent 1-131 (confirmed) .

• FOR CONTROLLER USE ONLY Controller Notes:

Action Expected: TSC will direct plant shutdown at normal rate .

Scenario: PALEX-92 Time: 1000

• Message No: 9 PALISADES NUCLEAR PLANT Scenario Time: 0130 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Message For: Operators Simulated Plant Conditions:

Plant shutdown is in progress at 25%/hr. Message:

1. See Data Sheets.

2. Alarm status is unchanged .

• FOR CONTROLLER USE ONLY Controller Notes:

Action Expected:

Date SEPTEMBER 199? Message # .9. (Page 1) Ti me .lilllil Scenario Time .DJ.:i.Q Time Jump Scenario Time Jump SW Sumps P-7A mt P-7B Sifil'. P-7C mt SW Critical Hdr Press A 1J._ B 1.A... psig Pumps P-52A Sifil'. P-52B mt P-52C Sifil'. FPC Pumps P-51A mt Pumps P-9A .a.EE P-9B .a.EE P-41 .a.EE P-51B .a.EE

• Containment Cppler Recjrc Eans VlA mt V2A mt V3A mt V4A mt VlB mt V2B mt V3B mt V4B mt CCW Cooler Outlet Temp A ZL. F B 1L. F Containment Spray Pumps P-54A .a.EE P-54B .a.EE P-54C .a.EE HPSI Pumps P-66A .a.EE P-66B .a.EE LPSI Pumps P-67A .a.EE P-67B .a.EE Safety Iniectjon Suctjpn Supply Train A Train B CV-3057 (SIRW) .QfEH CV-3029 (SIRW) tLD.SfI2 CV-3031 (SIRW) .QfEH CV-3030 (Sump) tLD.SfI2 I etdpwn Chargjng Intermediate Press Letdown Temp ill F Flow M gpm Letdown Line Temp Z5Z F Line Temp la! F Letdown Flow .3.5. gpm Pumps P-55A mt P-55B .a.EE P-55C .a.EE Vpl 1mie Cpnt rpl Ta pk Temp l.QB. F Pressure 2.6. psi Level .a.6. X PCP Control Bleedoff Pressure il psig Shutdown Cppljng System SOCS fran PCS (R) SJ F SOCS to PCS (R) SJ F Ouench Tank
  • Pressurizer Pressure (R)

PCS Tave (R) Pressurizer Level (R) Pzr Htr Amps Temp lill F 2.llfil. psi a Pressure =l. prjmary Cpplant System Loop l (TR-0111) .55.9. Loop 2 (TR-0121) .55.9. LRC-OlOlA .5.8. x LCC 15 ill LRC-0101B .5.8. x LCC 16 ill psig Level .6.l LIA-0102A M X x PORV PRV-1042B .c.LClS.E.D. PRV-1043B tLD.SfI2 Block Valve MOV-1042A WlSfl2 MOV-1043A tLD.SfI2 PCPs P-50A mt P-50B mt P-50C mt P-500 mt Reactor Power Level NI-01 lDE+llli

• NI-02 . ...lll.E+/-ll5 NI-03 !IZE+llZ NI-04 !IZE+llZ NI-05 l.Q.Q NI-06 !I.a NI-07 !I.a NI-08 1DE+D3

 .c.:.o.l.

Af\,/ System AF\J Pump P-BA .a.EE P-BB .a.EE P-BC .a.EE AF\J Pump Amps P-BA .Q P-BC .Q AF\J Pump P-BB Steam Pressure .Q psig AF\J Disch Press P-BA & P-BB l.Q P-BC l.Q psi Secgndary System MSIV Bypass MOV-0501 tLll.S.Ell MOV-0510 tLD.SfI2 MSIV's CV-0501 .QfEH CV-0510 .QfEH MFP Suction Pressure .3.3A psig MFP Discharge Pressure A .l.12.!l!i B .l.12.!l!i psi Moisture Separator Drain Tank Level .Ii§. X Condenser Hotwell Level !ll X Atmospheric Dump Valves WlSfl2 Condenser Vacuum Z.Z...S in Hg. Heater Drain Pump Status P-lOA mt P-lOB mt Gland Seal Condenser Vacuum .l!..Z. in Hg. Condensate Pump Status P-2A mt P-2B mt (Demand Log + Constant, Rod, or Flux/Temp) Gross MW .llll. Net MW 1.1..!fJ. Core Exit Thermocouple Temperature .5.8.l...3. F Control Rod Position GPl 131 GP2 131 GP3 131 GP4 131 GP5(P) 131 GP6(A) l3.l GP7(B) 131 .,. "°"' lillllf * ~

Date SEPTEMBER 1 1992 Message I S (Page 2) Ti me .llll2Q Scenario Time .lll3D Time Jump Scenario Time Jump T-81 Leve1 fill X T-939 Leve1 A9.  % Condensate Storage Tank Level T-2 Z9. trument Air Pressure* JJ25 psig tainment Building Pressure .a psig Dome Temperature .a.a. F Humidity AS. A Compartment Temperature .82. F Humidity M I B Compartment Temperature a! F Humidity M SIRW Tank Level 92. % - WR Containment Pressure (R) l i psi a Containment Sump Level lQ  % Containment Water Level (R) .a SI Tank Level (%) A ..sz. B ~ c ~ D ~ SI Tank Pressure (psig) A Zll B zz.a c 2.3.0. D ill PANE! K-13 SIAS Alarm li!l Containment High Pressure Alarm li!l Containment High Radiation Alarm li!l Concentrated Boric Acid Tank Levels T53A 9.Z..S. x T53B 95.2 % Reactor Vessel DP 2.12..Z psid PORV Discharge Temperature .a.a. F Pzr Safety Valve Discharge Temp (F) RV-1039 .a.a. RV-1040 RV-1041 .a.a. PCP Current (Amps) P-50A ill P-50B .592. P-50C P-500 S11. PCS Flow ll x Pressure Level (cold) Loop Thot (F) Loop 1 5.82. Loop 2 5.82. Loop Tcold (F) Loop 1 .5.3.5. Loop 2 .5.3.5. Tcold Wide range Loop 1 .5.3.5. Loop 2 ~ Subcooling Temp .sa F Press llS. psi PCS Prssure WR .2.12.61 NR .lilll2 psi a Steam Generator A Steam Generator B Level (WR) .65. x (NR) .65. x (WR) . .65. % (NR) .65. x Press 1.9l psi a 1.9l psi a Flow Steam .5...5 PPH Feed .5...5 PPH Steam .5...5 PPH Feed .5...5 PPH Note: Steam and Feed Flow x 1000000 AFW Fl ow to A S/G From P-8A&B .D. From P-8C .D. AFW Fl ow to B S/G From P-8A&B .D. From P-8C .D. Condenser Vacuum (R) 2l. PCP Seal Leakoff Flow P-50A l...l PPH P-50B l...l PPH P-50C Ll. PPH P-500 Ll. PPH t.:.D! Diesel Generator Frequency 1-1 .D. 1-2 -il - 1-C BUS Voltage z.4a! Amps .z.a5 1-D BUS *Voltage Zill. Amps ill C- J l Bili:k C- J Ja Containment Area Monitors (R/Hr) RIA-1805 ...l2Zil RIA-1806 .J2li RIA-1807 ...ill. RIA-1808 .J2B.ll High Range Containment Monitors (R/Hr) RIA-2321 l RIA-2322 l Containment Hydrogen Concentration (%) Al-2401R .D. Al-2401L .D. Main Steam Line Ganma (cpm) RIA-2324 2l RIA-2323 Z5 Stack Monitors RIA-2325 .3..D..Q cpm RIA-2326 fill cpm RIA-2327 ...Z mr/hr

Scenario: .

• PALEX-92 Time: 1001 Message No: 10 Scenario Time: 0131 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Message For: Operators Simulated Plant Conditions:

Shutdown in progress at 25%/hr. Message: Charging Pumps P-55B and P-55C have started on decreasing pressurizer level. The following alarms have been received: EK-02-05, "Main Steam E-50B RIA-2323 High" EK-02-17, "Main Steam E-50B RIA-2323 Alert" EK-07-61, "Pressurizer Level Hi-Lo"

• FOR CONTROLLER USE ONLY Controller Notes:

Action Expected: Recognize a loss of PCS inventory exists that is greater than Charging Pump capacity and trip the reactor.

Scenario: * *PALEX-92 Time: 1002 Message No: 11 ScenarioTime: 0132 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Message For: Operators Simulated Plant Conditions: Reactor Trip. Message: See Post-Trip ( + 1 minute) Data and Alarm Sheets. "R" Bus is deenergized.

• FOR CONTROLLER USE ONLY Controller Notes:

If asked, trip was either manual or automatic (TM/LP). Action Expected: Carry out EOP-1.0 standard post-trip .ac~ons .

Date Sf P!fMBER 1992 Message I ll (Page 1) Time lililZ Scenario Time .D.l.32. Time Jump Scenario Time Jump t=Oa SW Sumps P-7A mt P-78 .sm P-7C mt SW Critical Hdr Press A a5 BM psig P-52A .silll P-528 mt P-52C .silll FPC Pumps P-51A mt

• e Pumps Pumps P-9A .llEE P-98 .llEE P-41 .llEE P-518 .llEE Contajoment Coolec Becicc Eans VlA mt V2A mt V3A mt V4A .!lli VlB .!lli V2B .!lli V3B .!lli V4B .!lli CCW Cooler Outlet Temp A zn. F B zn F Containment Spray Pumps P-54A .llEE P-546 .llEE P-54C .llEE HPSI Pumps P-66A .llEE P-666 .llEE LPSI Pumps P-67A .llEE P-676 .llEE Safety Ioiectjoo suction Supply Train A Train B CV-3057 (SIRW) QfE?t CV-3029 (SIRW) .c:LilS.ED. CV-3031 (SIRW) QfE?t CV-3030 (Sump) .c:LilS.ED.

1etdowr1 Chacgjog Intermediate Press Letdown Temp ill F Flow .13.l gpm Letdown Line Temp .!Ba F Line Temp .ll9. F Letdown Fl ow .Q gpm Pumps P-55A .!lli P-558 .!lli P-55C .!lli Volunre Cootcol Tack Temp .laa F Pressure ZZ psi Leve1 .6.l X PCP Control Bleedoff Pressure 3.6 psig Shytdowr1 Cooling Syst!!!!! SOCS fran PCS (R) Bl F SOCS to PCS (R) Bl F Quench Tank

• Pressurizer Pressure (R)

PCS Tave (R) Pzr Htr Amps Temp .lilZ F J.m psi a Loop 1 (TR-0111) .53a Loop 2 (TR-0121) .5.lZ Pressurizer Level (R) LRC-0101A Z3. X LCC 15 .Q Pressure =l Pcjmacy Coolant System LRC-01018 LCC 16 .QZ3. " psig Level LIA-0102A JD

                                                                                                                             .6.3. X PORV                         PRV-10428 .c:LilS.ED.             PRV-10436 .c:LilS.ED. Block Valve          MOV-1042A .c:LilS.ED.          MOV-1043A .c:LilS.ED.

PCPs P-50A QEE P-508 .PEE P-50C QEE P-500 QEE Reactor Power Level NI-01 JQF+OS NI-02 1QF+06 NI-03 fi!IE+PO NI-04 fi!IE+QQ NI-05 ...3.9 NI-06 _!Q NI-07 ...43. NI-08 ..Jl AEJJ Syst!!!!! AFW Pump P-8A .!lli P-8B QEE P-8C .PEE AFW Pump Amps P-8A .fi.S. P-8C .Q AFW Pump P-88 Steam Pressure .Q psig AFW Disch Press P-8A &P-88 l.lSl P-8C .9. psi Secoodacy System MSIV Bypass MOV-0501 tLDiED. MOV-0510 .c:LilS.ED. MSIV's CV-0501 QfE?t CV-0510 QfE?t MFP Suction Pressure 2Jl. psig MFP Discharge Pressure A lfiQ B .3.!Z psi Moisture Separator Drain Tank Level Ji X Condenser Hotwell Level ~ X Atmospheric Dump Valves lJ:IB.PI Condenser Vacuum ZB...l in Hg. Heater Drain Pump Status P-lOA .!lli P-lOB .!lli Gland Seal Condenser Vacuum ~ in Hg. Condensate Pump Status P-2A QEE P-28 QEE (Demand Log + Constant, Rod, or Flux/Temp) Gross MW .Q Net MW .:.5. Core Exit Thermocouple Temperature 2U F Control Rod Position GP! .Q GP2 .Q GP3 .Q GP4 .Q GP5(P) .lJl. GP6(A) .Q GP7(6) .Q

 ~k Rod* lillll.E        I Q
                                                                                                                                                                     --------~I

Date SEPTEMBER l 1992 Message I ll (Page 2) Time .lmlZ Scenario Time .ll.l3.Z. Time Jump Scenario Time Jump T-81 Level g.o. % T-939 Level ~  % Condensate Storage Tank Level T-2 19. rument Air Pressure l.l2l psig ainment Building Pressure .0. psig Dome Temperature .as. F Humidity A5 A Compartment Temperature B2. F Humidity ~

  /G B Compartment                                                             Temperature         .a!          F  *Humidity ~

SIRW Tank Level .92. % - WR Containment Pressure (R) l! psi a Containment Sump Level l.D. % Containment Water Level (R) .0. SI Tank Level (%) A .5Z. B !a c !a D !a SI Tank* Pressure (psig) A Zll B ZZli c ZJ.D. D lli PANE! K-13 SIAS Alarm .tiC. Containment High Pressure Alarm .tiC. Containment High Radiation Alarm .tiQ Concentrated Boric Acid Tank Levels T53A .9.Z-5 % T53B 95.2 % Reactor Vessel DP l..J psid PORV Discharge Temperature .as. F Pzr Safety Valve Discharge Temp (F) RV-1039 .as. RV-1040 RV-1041 .aB. PCP Current (Amps) P-50A .0. P-50B .0. P-50C P-50D .0. PCS Flow l.D. % Pressure Level (cold) Loop Thot (F) Loop 1 .5!6. Loop 2 Sil Loop Tcold (F) Loop 1 .53.Q Loop 2 .53.Q Tcold Wide range Loop 1 .53.Q Loop 2 .53.Q Subcooltng Temp .6a F Press lD9. psi PCS Prssure WR lZl6. NR fil20. psi a Steam Generator A Steam Generator B Level (WR) =l % (NR) =l  % (WR) 5  % (NR) 5  % Press Bfifi psi a Bfifi psi a Flow Steam ...z PPH Feed .0. PPH . Steam ...z PPH Feed .0. PPH Note: Steam and Feed Flow x 1000000 AFW Flow to A S/G From P-BA&B ill. From P-8C .0. AFW Flow to B S/G From P-8A&B 165 From P-8C .0. Condenser Vacuum (R) za PCP Seal Leakoff Flow P-50A Wl PPH P-50B Wl PPH P-50C Wl PPH P-50D Wl PPH C:Q! Diesel Generator Frequency 1-1 -l2 1-2 :J2. 1-C BUS Voltage llB2. Amps .16.9. 1-D BUS Voltage Z!al Amps lZl 1:-l l Back 1:-l l! Containment Area Monitors (R/Hr) RIA-1805 ...!Sn RIA-1806 ....lS.O. RIA-1807 ...lfill. RIA-1808 ....lZ.D. High Range Containment Monitors (R/Hr) RIA-2321 l. RIA-2322 l. Containment Hydrogen Concentration (%) AI-2401R .l2 AI-2401L .l2 Main Steam Line Ganma (cpm) RIA-2324 ..l.E+/-.Q.3. RIA-2323 7 8E+03 Stack Monitors RIA-2325 3.llQ cpm RIA-2326 fill cpm RIA-2327 ...Z. mr/hr

Scenario:

• PALEX-92 Time: 1002 Message No: 11 Scenario Time: 0132 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE ALARM SHEET Alarm Annunc Panel Number Alarm Window Description EK-01 01 Turbine Trip EK-01 37 AFAS-FOGG Subsystem Trip EK-01 43. FW Pump PlA Turbine K7A Trip EK-01 49 FW Pump PlB Turbine K7B Trip EK-01 55 Condensate Pump Trip EK-02 05 Main Stea.m E-50B RIA-2323 High EK-02 17 Main Steam E-50B RIA-2323 Alert EK-03 01 Generator Trip EK-03 36 Switchyard ACB Trip EK-05 01 4160V Bus lA Bkr 252-101 Trip EK-05 02 4160V Bus lB Bkr 252-201 Trip EK-05 13 4160V Bus lA and/or lB Undervoltage EK-05 19 4160V Standby Power not Available EK-05 21 2400V Standby Power not Available EK-05 22 Bus Fail to Transfer EK-05 25 Startup Transformers Trip
• EK-07 63 Pressurizer Level CH "A" Lo-Lo

Scenario: *PALEX-92 Time: 1002 Message No: 11 Scenario Time: 0132 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE ALARM SHEET Alarm Annunc Panel Number Alarm Window Description EK-07 64 Pressurizer Level CH "B" Lo-Lo EK-07 71 Volume Control Rad Monitor Hi Radiation EK-09 01 Pri Coolant Pump P-50A Trip EK-09 02 Pri Coolant Pump P-50B Trip EK-09 03 Pri Coolant Pump P-50C Trip EK-09 04 Pri Coolant Pump P-50D Trip EK-09 54 Rod Drive Seal Leakoff Hi Temp EK-09 62 Steam Gen E-50A Lo Level EK-09 64 Steam Gen E-50B Lo Level EK-09 72 Reactor Trip EK-13 51 Containment Sump Hi Level EK-13 64 Gaseous Waste Monitoring Hi Radiation EK-13 65 Process Liq Monitoring Hi Radiation EK-33 05 4160V Bus lF Incoming Bkr 252-301 Trip EK-33 08 4160V Bus lF Undervoltage EK-33 09 4160V Bus lG Incoming Bkr 252-401 Trip

• EK-33 12 4160V Bus lG Undervoltage

Scenario: PALEX-92 . Time: 1002

• Message No: 11 Scenario Time: 0132 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE ALARM SHEET Alarm Annunc

 ~                 Number         Alarm Window Description EK-35             22.            Cooling Tower Pump P-39A Trip EK-35             23             Cooling Tower Pump P-39B Trip

Scenario:

• PALEX-92 Time: 1006
• Message No: 12 PALISADES NUCLEAR PLANT Scenario Time: 0136 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Message For: Operators Simulated Plant Conditions:

Post-Trip Message: Safety injection activation has occurred on low Pressurizer pressure.

• FOR CONTROLLER USE ONLY Controller Notes:

Action Expected: Verify or operate safeguards equipment.

Scenario:

• PALEX-92 Time: 1015 Message No: 13 Scenario Time: 0145 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Message For: Operators Simulated Plant Conditions:

Post-Trip. Message: See Data and Alarm Sheets.

• FOR CONTROLLER USE ONLY Controller Notes:

Action Expected: Commence steaming both S/G's .

Date SEPTEMBER 1 1992 Message I .U (PCl'1e 1) Time lQl5 Scenario Time .lllJ5 Time Jump Scenario Time Jump SW Sumps P-7A mi P-78 mi P-7C mi SW Critical Hdr Press A~ 8 ~ psig Pumps P-52A mi P-528 mi P-52C .QH FPC Pumps P-51A mi Pumps P-9A ilEE P-98 ilEE P-41 .QEE P-518 ilEE Containment Cooler Recjrc Fans VlA .QH V2A mi V3A .QH V4A mi Vl8 .QEE V28 ilEE V38 ilEE V48 ilEE CCW Cooler Outlet Temp A .5l F 8 .5l F Containment Spray Pumps P-54A ilEE P-548 .QEE P-54C .QEE HPSI Pumps P-66A mi P-668 .QH LPSI Pumps P-67A mi P-678 mi Safety Iniectjon Suction Supply Train A Train B CV-3057 (SIRW) .llffli CV-3029 (SIRW) t1.1lSEll CV-3031 (SIRW) !l.eEti CV-3030 (Sump) tLJlSfll 1etdown Chargjng Intermediate Press Letdown Temp ill F Flow ll.1 gpm Letdown Line Temp ill F Line Temp ll.1 F Letdown Flow .a gpm. Pumps P-55A mi P-558 .QH P-55C :Cti Volume ContrpJ Tank Temp .1.12! F Pressure Z0 psi Level .52  % PCP Control Bleedoff Pressure lO. psig Shutdown Cool; ng System SOCS from PCS (R) .8.3. F SOCS to PCS (R) .az. F Ouench Tank

• Pressurizer Pressure (R)

PCS Tave (R) Pressurizer Level (R) Pzr Htr Amps Temp lllZ. F

                                              .llli psi a Loop l (TR-0111) .538 Loop 2 (TR-0121) .5.3.S LRC-OlOlA .a LCC 15 .a Pressure .:l Primary Coolant System LRC-01018 .a LCC 16 .a psig                       Level LIA-0102A l l
                                                                                                                               .6.l   %

PDRV PRV-10428 tul.S.ED. PRV-10438 WlSfil Block Valve MOV-1042A tul.S.ED. MOV-1043A WlSfil PCPs P-50A m P-508 .QEE P-50C m P-500 .QEE Reactor Power Level NI-01 l6E+ll5 NI ..::l.6.E+/-ll5 NI-03 lfiE-ll~ NI-04 ...J.£.E.:..IM NI-05 ~l E-lll NI-06 ..!llf=fil NI-07 fiSE-lll NI-08 ...6.6.E.=.lll t::m. AfW System AFW Pump P-8A .QH P-88 ilEE P-8C ilEE AFW Pump Amps P-8A .6.S P-8C .a AFW Pump P-88 Steam Pressure .a psig AFW Disch Press P-8A & P-88 ll9.l P-8C .9. psi Secondary System MSIV Bypass MOV-0501 t1.1lSEll MOV-0510 tul.S.ED. HSIV's CV-0501 tul.S.El2 CV-0510 tLllS.Ell MFP Suction Pressure z psig MFP Di scbarge Pressure AZ BZ psi Moisture Separator Drain Tank Level .U % Condenser Hotwell Level l2. % Atmospheric Dump Valves lJ::IB.!lI Condenser Vacuum 21..l. in Hg. Heater Drain Pump Status P-lOA ilEE P-108 .QEE Gland Seal Condenser Vacuum .l!..Z in Hg. Condensate Pump Status P-2A ilEE P-28 .QEE (Demand Log + Constant, Rod, or Flux/Temp) Gross MW .'2 Net MW .::l Core Exit Thermocouple Temperature 5il...a F Control Rod Position GPl .0 GP2 .'2 GP3 .'2 GP4 .'2 GP5(P) l3.l GP6(A) .'2 ~P7(B) .'2

 . k Rods li!lHf          I .'2

Date SEPTEMBER J 1992 Message # l3. (Page 2) Time lO.lS. Scenario Time ~ Time Jump Scenario Time Jump T-81 .Level .9.12 % T-939 Level !9. % Condensate Storage Tank Level T-2 1.5. trurnent Air Pressure l!2l. psig tainment Building Pressure .0 psig Dome Temperature .Bl F Hurni di ty .!6.

• A Compartment Temperature .B.3. F Humidity 2 S/G B Compartment Temperature .B.3. F Humidity 2 SIRW Tank Level .9.Z. %

WR Containment Pressure (R) l i psi a Containment Sump Level Containment Water Level (R) .0 SI Tank Level (%) A 2

                                              .li2
                                                      "              B AB.                       c    AB.                        D AB.

SI Tank Pressure (psig) A Zl3. B .21a cm D Z3.! PANE! K-13 SIAS Alarm lli Containment High Pressure Alarm HO. Containment High Radiation Alarm HO. Concentrated Boric Acid Tank Levels T53A T53B 83.0 % Reactor Vessel DP PORV Discharge Temperature

                                                                        .B.3....l 1-.l aa         F "psid Pzr Safety Valve Discharge Temp (F)                         RV-1039    aa                 RV-1040                      RV-1041 Ba PCP Current (Amps)              P-50A        .0              P-50B     .D.                P-50C                        P-50D      .0 PCS Flow                                                     Pressure   Level (cold)

Loop Thot (F) Loop Tcold (F) Loop 1 Loop 1

                                              .3.
                                              .5!3.
                                              .53.3.
                                                      "       Loop 2 Loop 2-
                                                                        .5!3.
                                                                        .sza Tcold Wide range                Loop 1       .sza            Loop 2    .sza Subcooling                      Temp         z.a     F       Press     Z!9. psi PCS Prssure                     WR           lm             NR         fil2l2 psi a Steam Generator A                                        Steam Generator B Level                           (WR)                         (NR)                         (WR)                         (NR)                x Press Flow                            Steam
                                              .:Z
                                              .0
                                              .9.122 psi a PPH     Feed
                                                                        .:Z
                                                                        .D.

PPH Steam

                                                                                                     .4.5 85! psi a
                                                                                                     .D.

PPH Feed

                                                                                                                                   .4.5
                                                                                                                                   .'2      PPH Note: Steam and Feed Flow x 1000000 AFW Flow to A S/G           From P-BA&B lfi9.             From P-BC .D.

AFW Flow to B S/G From P-BA&B m From P-BC .'2 Condenser Vacuum (R) z.a PCP Seal Leakoff Flow P-50A ...9. PPH P-50B ...9. PPH P-50C ...9. PPH P-50D ...9. PPH C:.D.! Diesel Generator Frequency 1-1 .Jl 1-2 ".Jl 1-C BUS Voltage .z.w. Amps .5lM. 1-D BUS Voltage Z!B.Z. Amps .3.9.fi C-ll Bii!t:k C-l!A Containment Area Monitors (R/Hr) RIA-1805 ...55.D. RIA-1806 ...z.s.o. RIA-1807 ...Z.0..0. RIA-1808 ...lfill High Range Containment Monitors (R/Hr) RIA-2321 l RIA-2322 l Containment Hydrogen Concentration (%) AI-2401R .0 AI-2401L .D. Main Steam Line Ganma (cpm) RIA-2324 ..l.E+/-.lll RIA-2323 7 BE+03 Stack Monitors RIA-2325 .l.D..D. cpm RIA-2326 .6.12 cpm RIA-2327 ...Z mr/hr

Scenario: *PALEX-92 Time: 1015 Message No: 13 Scenario Time: 0145 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE ALARM SHEET Alarm Annunc

   ~                  Number         Alarm Window Description EK-01              01             Turbine Trip EK-01              37             AFAS-FOGG Subsystem Trip EK-01              43             FW Pump PIA Turbine K7A Trip EK-01              49             FW Pump PlB Turbine K7B Trip EK-01              55             Condensate Pump Trip EK-02              05             Main Steam E-50B RIA-2323 High

• EK-02 17 Main Steam E-50B RIA-2323 Alert EK-03 01 Generator Trip EK-03 36 Switchyard ACB Trip EK-05 01 4160V Bus IA Bkr 252-101 Trip EK-05 02 4160V Bus lB Bkr 252-201 Trip EK-05 05 2400V Bus lE Bkr 152-302 Trip EK-05 13 4160V Bus lA and/or lB Undervoltage EK-05 17 2400V Bus lE Undervoltage EK-05 19 4160V Standby Power not Available EK-05 20 2400V Bus lE Bkr 152-310 Trip

.EK-05                21             2400V Standby Power not Available

Scenario:

• PALEX-92 Time: 1015 Message No: 13 Scenario Time: 0145 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE ALARM SHEET Alarm Annunc

 ~                   Number         Alarm Window Description EK-05               22             Bus Fail to Transfer EK-05               25             Startup Transformers Trip EK-07               23             Cone Boric Acid Tank Lo Level EK-07               42            Pressurizer Heater Bus Ground/Undervoltage EK-07               63             Pressurizer Level CH "A" Lo-Lo EK-07               64             Pressurizer Level CH "B" Lo-Lo EK-07               71             Volume Control Rad Mon Hi Radiation EK-09               01            Pri Coolant Pump P-SOA Trip EK-09               02             Pri Coolant Pump P-50B Trip EK-09               03             Pri Coolant Pump P-50C Trip EK-09               04            Pri Coolant Pump P-50D Trip EK-09               54             Rod Drive Seal Leakoff Hi Temp EK-09               62             Steam Gen E-SOA Lo Level EK-09               64             Steam Gen E-SOB Lo Level EK-09               72             Reactor Trip

Scenario: *PALEX-92 Time: 1015 Message No: 13 Scenario Time: OI45 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE ALARM SHEET Alarm Annunc Panel Number Alarm Window Description EK-11 20 Low Sub-Cooling Margin EK-11 50 Containment Recirc Fans Trip EK-11 65 Non-Critical Service Water Lo Press EK-I3 42 Safety Inj Initiated EK-I3 5I Containment Sump Hi Level EK-I3 64 Gaseous Waste Monitoring Hi Radiation

• EK-13 65 Process Liq Monitoring Hi Radiation EK-I3 69 Safety Inj Signal Block Permit EK-33 05 4I60V Bus IF Incoming Bkr 252-30I Trip EK-33 08 4I60V Bus IF Undervoltage EK-33 09 4I60V Bus IG Incoming Bkr 252-401 Trip Ek-33 12 4I60V Bus lG Undervoltage EK-35 22 Cooling Tower Pump P-39A Trip EK-35 23 Cooling Tower Pump P-39B Trip

Scenario: *PALEX-92 Time: 1030

• Message No: 14 PALISADES NUCLEAR PLANT Scenario Time: 0200 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Message For: Operators Simulated Plant Conditions:

Message:

1. See Data Sheets.

2. Alarm Status is unchanged .

• FOR CONTROLLER USE ONLY Controller Notes:

Auxiliary Spray CV-2117 is failed in the closed position, although position indication is operable. Action Expected:

1. Terminate Auxiliary Feedwater to SIG 'B'.

2. Cool the PCS to less than 525 degrees fahrenheit using ADV's and AFW to SIG

               'A'.

3. Isolate SIG 'B' .

Date SEPTEMBER 1 199? Message # ll (Page 1) Ti me l.ll.3.0. Scenario Time .QZ!lO. Time Jump Scenario Time Jump SW Sumps P-7A OH

• P-7B OH P-7C OH SW Critical Hdr Press A .99. B .99. psig Pumps P-52A OH P-528 OH P-52C OH FPC Pumps P-51A OH e Pumps P-9A .QEE P-9B .QEE P-41 .QEE P-518 .QEE
• Cpntajnment Cppler Recjrc Fans VlA OH V2A OH V3A OH V4A OH VlB .QEE V2B .QEE V3B .QEE V4B .QEE CCW Cooler Outlet Temp A S.l F B S.l F Containment Spray Pumps P-54A .QEE P-54B .QEE P-54C .QEE HPSI Pumps P-66A OH P-66B OH LPSI Pumps P-67A OH P-67B OH Safety Iniectjgn S11ctjpn Supply Train A Train B CV-3057 (SIRW) .o.e.Eli CV-3029 (SIRW) tl.llSfil CV-3031 (SIRW) .o.e.Eli CV-3030 (Sump) tl.llSfil I etdpwn Chargjng Intermediate Press Letdown Temp llQ F Fl ow J.ll gpm Letdown Line Temp l!a F Line Temp .l6.Q F Letdown Fl ow .a gpm Pumps P-55A OH P-558 .a.ti P-55C OH vol 1nne Cpntrgl Tank Temp .99. F Pressure Zl psi Level .5a " PCP Control Bleedoff Pressure . :U psig Sbutdgwn Cggljng System SOCS from PCS (R) .Bl F SOCS to PCS (R) .az. F Quench Tank
• Pressurizer Pressure (R)

PCS Tave (R) Pressurizer Level (R) Pzr Htr Amps Temp ill F LRC-OlOlA .a LCC 15 .a lZAa psi a Loop l (TR-0111) .s:u Loop 2 (TR-0121) Pressure .=l Primary Cgglant System LRC-01018 LCC 16 psig Level .6.2 . " LIA-0102A l5. " PORV PRV-10428 tl.llSfil PRV-10438 Block Valve MOV-1042A i::J...DSfll MOV-1043A tl.llSfil PCPs P-50A .PEE . P-50B P-50C .PEE P-500 .PEE Reactor Power Level Nl-01 14F+Q2 NI-OZ Nl-03 l4E-07 Nl-04 14E-QZ NI-05 4lf-Q] Nl-06 Nl-07 64E-Ql NI-08 66E-Ql AF\{ System AFW Pump P-8A OH P-8B .PEE P-8C OH AFW Pump Amps P-8A .5a P-8C ~ AFW Pump P-8B Steam Pressure .'2 psig AFW Disch Press P-8A & P-88 l3!l. P-8C l.Z.2.l. psi Secgpdary System MSIV Bypass MOV-0501 tLaS.E.12 MOV-0510 tLPSfll MSIV's CV-0501 tl.llSfil CV-0510 tLPSfll MFP Suction Pressure l5. psig MFP Discharge Pressure A l5. B l5. psi Moisture Separator Drain Tank Level l3. % Condenser Hotwell Level ll Atmospheric Dump Valves Heater Drain Pump Status tl.llSfil P-lOA .PEE P-lOB .PEE Condenser Vacuum Gland Seal Condenser Vacuum

                                                                                                                               .'2    " in Hg.
                                                                                                                               .l!.Z in Hg.

Condensate Pump Status P-2A .PEE P-2B .PEE (Demand Log + Constant, Rod, or Flux/Temp) Gross MW .'2 Net MW .=.3. Core Exit Thermocouple Temperature .5.3.LI. F

 .k Rodo Control Rod Position lllll!E     I Q GPl .'2 GP2 .'2            GP3 D          GP4 .'2       GP5(P) 13.l GP6(A) .'2                GP7(B) .'2

Date SEPTEMBER 1 1992 Message I l i (Page 2) Time ll2lQ Scenario Time .llZ..Q!l Time Jump Scenario Time Jump T-81 Level .9.12 % T~939 Level Condensate Storage Tank Level T-2 Z.l2 trument Air Pressure tainment Building Pressure SI

                                           .l2 "psig psig                     Dome Temperature .Bl             F     Humidity !5

• A Canpartment S/G B Canpartment Temperature Temperature

                                                                                                    .BJ
                                                                                                   .BJ F

F Hurni di ty .5Z. Humidity .5Z.

                                                                                                                                            ""x SIRW Tank Level                           ~         %

WR Containment Pressure (R) l i psi a Containment Sump Level l.l2 % Containment Water Level (R) .l2 SI Tank Level (%) A .5Z. B !6 c .48. D .48. SI Tank Pressure (psig) A Zll B z.za c zzs D .z.3! PANE! K-13 SIAS Alarm IE£ Containment High Pressure Alarm .till Containment High Radiation Alarm .till Concentrated Boric Acid Tank Levels T53A T53B Reactor Vessel DP PDRV Discharge Temperature

                                                                        .6!..Z L.l psid
                                                                        .aa F     "                 64.2 "

Pzr Safety Valve Discharge Temp (F) RV-1039 .aa RV-1040 RV-1D41 .aB PCP Current (Amps) P-50A .l2 P-508 .l2 P-50C P-5DD .l2 PCS Flow

• Pressure Level (cold)

Loop Thot (F) Loop Tcold (F) Loop 1 Loop 1

                                           .2
                                           .531.
                                           .5Z.!
                                                     "        Loop 2 .531.

Loop 2 .5.3.5 Tcold Wide .range Loop 1 .5.3.5 Loop 2 .5.3! Subcooling Temp lS F Press JQg psi PCS Prssure WR lZ!6 NR .6.llO. psi a Steam Generator A Steam Generator B Level (WR) (NR) (WR) Z! (NR) Z! Press Flow Steam 19.

                                           .l2
                                           .9.12.ll psi a PPH     Feed 19.
                                                                        .l2 PPH    Steam
                                                                                                   .9.3a psi a
                                                                                                   .l2 "PPH    Feed       .l2
                                                                                                                                           "  PPH Note:    Steam and Feed Flow x 1000000 AFW Fl ow to A S/G         Fran P-8A&B Z.5Z.              Fran P-8C li.l2 AFW Flow to B S/G          From P-8A&B .l2                From P-8C .l2 Condenser Vacuum (R)                      ~

PCP Seal Leakoff Flow P-50A ...!I. PPH P-508 ...!I. PPH P-50C ...!I. PPH P-50D ...!I. PPH t.:.12! Diesel Generator Frequency 1-1 .J2 1-2 ~- 1-C BUS Voltage Z!6l. Amps ill 1-D BUS Voltage Z!6l. Amps ill i:- Jl B11ck i:- J Ja Containment Area Monitors (R/Hr) RIA-1805 -5.SJl. RIA-1806 -2.S.ll RIA-1807 ...z.ao. RIA-1808 ...l.B.O. High Range Containment Monitors (R/Hr) RIA-2321 l RIA-2322 l Containment Hydrogen Concentration (X) Al-2401R ..23 Al-2401L ..23 Main Steam Line Ganma (cpm) RIA-2324 ..LE+/-ill RIA-2323 7 8f+03 Stack Monitors RIA-2325 .l!li2 cpm RIA-2326 .6.12 cpm RIA-2327 ...Z mr/hr

Scenario:

• PALEX-92 Time: 1045 Message No: 15 Scenario Time: 0215 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Message For: Operators Simulated Plant Conditions:

1. See Data and Alarm Sheets.

2. SIG 'B' has been isolated .

• FOR CONTROLLER USE ONLY Controller Notes:

Alarm list has been reduced to key alarms. Action Expected:

Date SEPTEMBER 1997 Message I l5 (Page 1) T;me lM5 Scenario Time .az.1.5. T;me Jump Scenario Time Jump t:na SW Sumps P-7A .QH P-7B .QH P-7C .QH SW Critical Hdr Press A .99. B .99. psig P-52A .QH P-52B .QH P-52C .QH FPC Pumps P-51A .QH .Pumps Pumps P-9A 12.EE P-9B 12.EE P-41 12.EE P-51B 12.EE Ccataiameat Ccclec Becicc Eaas VlA .QH V2A .QH V3A .QH V4A*.QH VlB 12.EE V2B 12.EE V3B 12.EE V4B 12.EE CCW Cooler Outlet Temp A .5l. F B .5l. F Containment Spray Pumps P-54A 12.EE P-54B 12.EE P-54C .QEE HPSI Pumps P-66A .QH P-66B .QH LPSI Pumps P-67A .QH P-67B .QH Safety Ipjectjnp Sucticn Supply Train A Train B CV-3057 (SIRW) .o.e.Eti CV-3029 (SIRW) tulSfil CV-3031 (SIRW) .o.e.Eti CV-3030 (Sump) tLllS.El2 1etdown Chacgiag Intermediate Press Letdown Temp lll2 F Flow ill. gpm Letdown Line Temp ill F Line Temp J.sn F Letdown Flow .Q gpm Pumps P-55A .QH P-55B .QH P-55C .QH Vo] 1une Coat col Tapk Temp .9l F Pressure ZZ. psi Level .6.l " PCP Control Bleedoff Pressure .U psig Sh1Mcwn Cgpl j pg Systfflll SOCS from PCS (R) .Bl F SOCS to PCS (R) .B.Z F Quench Tack

• Pressurizer Pressure (R)

PCS Tave (R) Pressurizer Level (R) Temp ll2Z. F

                                            .lZ.3l psi a Pressure .:J.

Loop l (TR-0111) .4.6.Q Loop 2 (TR-0121) ill LRC-OlOlA J.Q " psig Pcimacy toolaat Systf'J!J Level .63. LIA-0102A .u Pzr Htr Amps PORV LCC 15 .Q PRV-10428 tLllS.El2 LRC-OlOlB J.Q " LCC 16 .Q PRV-1043B tL.D.S.El1 Block Valve MOV-1042A .o.e.Eti

                                                                                                                                "    MOV-1043A .o.e.Eti PCPs                              P-50A 12.EE                        P-50B 12.EE                                P-50C 12.EE               P-50D .llEf Reactor Power Level               Nl-01 BSE+Ql                       Nl 85E+Ql                              NI-03 B~E-OB              Nl-04 B4E-OB Nl-05 41 F-Dl                      Nl-06 B9E-Ql                               NI-07 ll~E-01             NI-08 66E-Dl AEll system AFW Pump P-BA .llEf P-BB .llEf P-BC .QH                                           AFW Pump Amps                  P-BA .Q                   P-8C .5!

AFW Pump P-BB Steam Pressure .Q psig AFW Disch Press P-8A & P-BB Z P-ac .llfi2 psi secondacy System MSIV Bypass MOV-0501 tL.D.S.E11 MOV-0510 tL.D.S.El1 MSIV's CV-0501 tL.D.S.El1 CV-0510 tLllS.El2 MFP Suction Pressure l5 psig MFP Discharge Pressure A l5 B l5 psi Moisture Separator Drain Tank Level l3. " Condenser Hotwell Level Zil Atmospheric Dump Valves Heater Drain Pump Status Il:lROI P-lOA .llEf P-lOB .llEf Condenser Vacuum Gland Seal Condenser Vacuum D. " in Hg. lA..Z in Hg. Condensate Pump Status P-2A .llEf P-2B .llEf

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

Gross MW .Q Net MW .:.3. Core Exit Thermocouple Temperature ilO...Z F Control Rod Position GPl D. GP2 .Q GP3 .Q GP4 .Q GP5(P) .l3l GP6(A) .Q GP7(B) .Q

~ Rods HOtiE             I .Q

Date SEPTEMBER 1 1992 Message I .15 (Page 2) Time .1M5 Scenario Time .llZlS Time Jump Scenario Time Jump T-81 Level .9.Q % T-939 Level A!l % Condensate Storage Tank Level T-2 .SS trument Air Pressure l.!lS. psig tainment Building Pressure .D. psig Dome Temperature Bf2 F Humidity !.B.

• A Compartment . Temperature .Bl F Humidity ,53 S/G B Compartment Temperature .az. F Humidity .53 SIRW Tank Level .az WR Containment Pressure (R)

Containment Sump Level l! psi a l.D. %

                                                 "                            Containment Water Level (R)                         .D.    %

SI Tank Level (%) A .5Z. B !.B. D !.B. SI Tank Pressure {psig) A 2.ll B Z2l. D 2.ll PANE! K-13 SIAS Alarm IES. Containment High Pressure Alarm ti.D. Containment High Radiation Alarm ti.D. Concentrated Boric Acid Tank Levels T53A 2.6...S % T53B 26.5 % Reactor Vessel DP L2. psid PDRV Discharge Temperature .az F Pzr Safety Valve Discharge Temp (F) RV-1039 .az RV-1040 RV-1041 .az PCP Current (Amps) P-50A .D. P-50B .D. P-50C P-50D .D. PCS Flow z. Pressure Level (cold) Loop Thot (F) Loop Tcold (F) Loop 1 Loop 1 Afili

                                        !.52.
                                                 "         Loop 2 !Sa Loop 2 ill Tcold Wide range             Loop 1    ill               Loop 2 !.B.!

Subcooling Temp l.D.3 F Press ill psi PCS Prssure WR .l2.3Z NR .6.12.D. psi a Steam Generator A Steam Generator B Level (WR) (NR) (WR) (NR) Press Flow Steam

                                        &2 fil psi a" PPH       Feed
                                                                     &2          %

PPH Steam

                                                                                                     .9.S
                                                                                                     .9.B.5 psi a "

PPH Feed

                                                                                                                                 .9.S    %

PPH

                                        .D.                          .D.                             .D.                         .D.

Note: Steam and Feed Flow x 1000000 AFW Flow to A S/G From P-8A&B .D. From P-8C ZlS. AFW Flow to B S/G From P-8A&B .D. From P-8C .D. Condenser Vacuum (R) .D. PCP Seal Leakoff Flow P-50A ...a PPH P-508 ...a PPH P-50C ...a PPH P-50D ...a "PPH Diesel Generator Frequency 1-1 ...D. 1-2 ...o.* 1-C BUS Voltage lliZ, Amps !3B. 1-D BUS Voltage 2.!.B.l Amps i l l C-11 Back C-11 A Containment Area Monitors (R/Hr) RIA-1805 ..ASl2 RIA-1806 ...35.D. RIA-1807 ..z.z.o. RIA-1808 ...l.B.D. High Range Containment Monitors (R/Hr) RIA-2321 l RIA-2322 l Containment Hydrogen Concentration (%) AI-2401R ...3.1 AI-2401L ...3.1 Main Steam Line Ganma (cpm) RIA-2324 .59.E+/-Jl3 RIA-2323 Z ZE+C3 Stack Monitors RIA-2325 lC.O. cpm RIA-2326 fill cpm RIA-2327 ...Z. mr/hr

                . *PALEX-92 Scenario:                                                     Time: 1045 Message No:     15                                     Scenario Time: 0215 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE ALARM SHEET Alarm               Annunc
   ~                   Number         Alarm Window Description EK-02              05             Main Steam E-50B RIA-2323 High EK-02               17            Main Steam E-50B RIA-2323 Alert EK-01               36             Switchyard ACB Trip EK-05               13            4160V Bus lA and/or lB Undervoltage EK-05               17            2400V Bus lE Undervoltage 19            4160V Standby Power not Available

• EK-05 EK-05 21 2400V Standby Power not Available EK-05 22 Bus Fail to Transfer EK-05 25 Startup Transformers Trip EK-07 59 No PCS Protection Channel A EK-09 01 Pri Coolant Pump P-50A Trip EK-09 02 Pri Coolant Pump P-50B Trip EK-09 03 Pri Coolant Pump P-50C Trip EK-09 04 Pri Coolant Pump P-500 Trip EK-09 63 Steam Gen E-50B Hi Level EK-09 72 Reactor Trip 50 Containment Recirc Fans Trip

.EK-11

               *PALEX-92                                         Time: 1045 Scenario:

Message No: 15 Scenario Time: 0215 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE ALARM SHEET Alarm Annunc Panel Number Alarm Window Description EK-11 65 Non-Critical Seivice Water Lo Press EK-13 42 Safety Injection Initiated EK-13 55 SIRW Tank T-58 Hi-Lo Level EK-33 08 4160V Bus lF Undervoltage EK-33 12 4160V Bus lG Undervoltage

                 . PALEX-92 Scenario:                                                                   Time: 1100 Message No:       16                                               Scenario Time: 0230 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Message For:           Operators Simulated Plant Conditions:

Message:

1. See Data Sheets.

2. Annunciator EK-09-61, "Steam Gen E-50B Hi Level," is in due to overfeeding; other Alarm Status is unchanged .

• FOR CONTROLLER USE ONLY Controller Notes:

1. Backfeeding the main transformer to regain forced circulation must not be permitted until 1145.

2. Any attempt to transfer miscellaneous waste to create room to drain S/G 'B' will result in Miscellaneous Waste Tran.sfer Pump P-92B motor overheating and failing.

3. SIS throttling criteria is (marginally) met if players elect this option; it should not significantly enhance the ability to lower PCS pressure.

Action Expected:

Date SEPTEMBER 1992 Message I l6. (Page l) Time ll!lQ Scenario Time .l2Z.3.ll Time Jump Scenario Time Jump SW Sumps P-7A .QH

• P-78 .QH P-7C .QH SW Critical Hdr Press A .!l.9. B .!l.9. psig Pumps P-52A .QH P-528 .QH P-52C .QH FPC Pumps P-51A .QH Pumps P-9A .D.EE P-98 .D.EE P-41 .D.EE P-518 .D.EE
• Containment Cooler Recite Eans VlA .QH V2A .QH V3A .QH V4A .QH VlB .D.EE V2B .D.EE V3B .D.EE V4B .D.EE CCW Cooler Outlet Temp A .5l F B .5l F Containment Spray Pumps P-54A .D.EE P-548 .D.EE P-54C .QEE HPSI Pumps P-66A .QH P-668 .QH LPSI Pumps P-67A .QH P-678 .QH Safety Injection Suction Supply Train A Train B CV-3057 (SIRW) Qfflt CV-3029 (SIRW) t.LO.S.Ell CV-3031 (SIRW) .Df.E1i CV-3030 (Sump) t.LO.S.E11 I etdgwn Cbacgicg Intermediate Press Letdown Temp .1.'19. F Flow ll3. gpm Letdown Line Temp ill F Line Temp .lZa F Letdown Flow D. gpm Pumps P-55A .QH P-558 .QH P-55C .QH

                                                                       ¥alume Caatcal Iack Temp   az    F                   Pressure Z3.          psi             Level 53       x                PCP Control Bleedoff Pressure                  .3.3. psig Sbutdawn Caalicg Syiatem SOCS from PCS (R) .al            F                                            SOCS to PCS (R) .BZ           F Queccb Iack

• Pressurizer Pressure (R)

PCS Tave (R) Pressurizer Level (R) Pzr Htr Amps Temp lPZ F lZil psi a Loop 1 (TR-0111) !5.6. Loop 2 (TR-0121) LRC-OlOlA l6. X LCC 15 D. Pressure .:l LRC-01018 LCC 16 psig Primacy Caalact Syiatem Level .6.1 LIA-0102A lS. X x PORV PRV-10428 t.LO.S.Ell PRV-10438 Block Valve MOV-1042A Qfflt MOV-1043A Qfflt PCPs P-50A .P.EE P-508 P-50C .P.EE P-500 .P.EE

 ,Reactor Power Level                  NI-01 73E+Ql.                      NI-0~                                     NI-03 ZZE-oa                NI-04 ZZE-oa NI-05 41E-01                       NI-06                                     NI-07 BU-Pl                 NI-08 BBE-Pl AFl{ Syiatem AFW Pump P-8A .P.EE P-88 .QEE P-8C .QH                                             AFW Pump Amps                  P-8A D.                      P-8C .5!

AFW Pump P-88 Steam Pressure D. psig AFW Disch Press P-8A & P-88 l P-8C llB.9. psi Secacdacy Syiatem MSIV Bypass MOV-0501 t.LO.S.Ell MOV-0510 .tLOSE.il MSIV's CV-0501 t.1JlS.El2 CV-0510 t.LO.S.Ell MFP Suction Pressure l5 psig MFP Discharge Pressure A l5 8 l5 psi Moisture Separator Drain Tank Level l.3. X Condenser Hotwell Level .fill x Atmospheric Dump Valves IflRDI Condenser Vacuum D. in Hg. Heater Drain Pump Status P-lOA .P.EE P-108 .QEE Gland Seal Condenser Vacuum .lA..Z in Hg. Condensate Pump Status P-2A .P.EE P-28 .D.EE (Demand Log + Constant, Rod, or Flux/Temp) Gross MW D. Net MW =! Core Exit Thennocouple Temperature !55..l F Control Rod Position GPl D. GP2 D. GP3 D. GP4 D. GP5(P) l.3.l GP6(A) D. GP7(B) D.

 -        Ro"'  lllll!.E     I ~

Date SEPTEMBER 1992 Message I lli (Page 2) Time .U.0.0. Scenario Time 1l2Ji1 Time Jump Scenario Time Jump t:ll T-81 Level .9.0. T-939 Level Condensate Storage Tank Level T-2 .sz. ~"""tainment.,,

                   '"""'Pressure Building AS.
                                                     "psig l.lU psig Dome Temperature B..5            F     Humidity AS.

A Compartment I B Compartment

                                              .D.

Temperature Temperature

                                                                                                      .az.
                                                                                                      .az.

F F Humidity .53. Humidity .53. SIRW Tank Level WR Containment Pressure (R) B.6 l l psi a Containment Sump Level Containment Water Level (R) SI Tank Level (") l.D. A .52.

                                                     "               B !8                         c   !8
                                                                                                                                 .D.

D !8 SI Tank Pressure (psig) A m B 2.Zl. c Z2.9. D m ea~EI IH3 SIAS Alarm lli Containment High Pressure Alarm 1iO. Containment High Radiation Alarm 1iO. Concentrated Boric Acid Tank Levels T53A LI T53B 6.8 Reactor Vessel DP PORV Discharge Temperature 2.1. az F "psid " Pzr Safety Valve Discharge Temp (F) RV-1039 az RV-1040 az RV-1041 az PCP Current (Amps) P-50A .D. P-50B .D. P-50C .D. P-500 .D. PCS Flow Pressure Level (cold) JU Loop Thot (F) Loop Tcold (F) Loop 1 Loop 1 2.AM " il8. Loop 2 Loop 2 AM fil Tcold Wide range Loop 1 fil Loop 2 ill Subcooling Temp l.D.Z F Press Z.55 psi PCS Prssure WR lli.l NR .liQO psia Steam Generator A Steam Generator B Level (WR) (NR) (WR) (NR) Press Flow Steam

                                              .91
                                              .D.

Alla psi a PPH Feed

                                                                        .91
                                                                        .D.

PPH Steam

                                                                                                      .9.9.
                                                                                                      .D.
                                                                                                      .a.a! psi a PPH    Feed
                                                                                                                                 .9.9.
                                                                                                                                .D.
                                                                                                                                         " PPH Note: Steam and Feed Flow x 1000000 AFW Flow to A S/G            From P-SA&B .D.              From P-SC ill AFW Flow to B S/G            From P-SA&B .D.              From P-8C .D.

Condenser Vacuum (R) .D. PCP Seal Leakoff Flow P-50A -.B. PPH P-50B -.B. PPH P-50C -.B. PPH P-500 -.B. PPH t:.12.4 Diesel Generator Frequency 1-1 ...a 1-2 *...a-1-C BUS Voltage 2.!82. Amps ill 1-D BUS Voltage Zill. Amps ill C-ll Back C-llA Containment Area Monitors (R/Hr) RIA-1805 -.fi5il RIA-1806 -3.Sil RIA-1807 ...2..2.0. RIA-1808 ....lfill High Range Containment Monitors (R/Hr) RIA-2321 l RIA-2322 l Containment Hydrogen Concentration (%) AI-2401R ...! AI-2401L ...! Main Steam Line Ganma (cpm) RIA-2324 ....fi.B.E.+/-lll RIA-2323 z 6E+Q3 Stack Monitors RIA-2325 .3..0.Q cpm RIA-2326 .6..0. cpm RIA-2327 ...Z mr/hr

Scenario:

• PALEX-92 Time: 1115
• Message No: 17 Scenario Time: 0245 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Message For: Operators Simulated Plant Conditions:

Message:

1. See Data Sheets.

2. Alarm Status is unchanged.

• FOR CONTROLLER USE ONLY Controller Notes:

Action Expected:

Date SEPTEMBER 1 1992 Message # ll (Page 1) Time lll5 Scenario Time .l2Z!5. Time Jump Scenario Time Jump

 .t:.:.QB.

SW Sumps P-7A .QH P-78 . .QH P-7C .QH SW Critical Hdr Press A .9.9. B .9.9. psig P-52A .QH P-528 .QH P-52C .QH FPC Pumps P-51A .QH .Pumps Pumps P-9A .llEE P-98 .llEE P-41 .llEE P-518 .llEE

                                                                                                                                   -~,

Ceataiameat Ceelet Becitc Eaas VIA .QH V2A .QH V3A .QH V4A .QH VlB .llEE V2B .llEE V3B .llEE V4B .llEE CCW Cooler Outlet Temp A .51 F B .5l F Containment Spray Pumps P-54A .llEE P-548 .llEE P-54C .llEE HPSI Pumps P-66A .QH P-668 .QH LPSI Pumps P-67A .QH P-678 .QH Safety Iajectjea Suction Supp]y Train A Train B CV-3057 (SIRW) .Q.Pfft CV-3029 (SIRW) tL.llS.ED. CV-3031 (SIRW) .Q.Pfft CV-3030 (Sump) tL.llS.ED. 1 etdeWTJ

• Chugiag Intermediate Press Letdown Temp SA F Flow lJl gpm Letdown Line Temp SA F Line Temp l.55 F Letdown Fl ow za gpm Pumps P-55A .QH P-558 .QH P-SSC .QH Ve] '!!De Cent tel Tank Temp .85 F Pressure Zfi psi Level .6Z " PCP Control Bleedoff Pressure 35 psig Sh1JtdpWTJ Cea] j DR System SOCS from PCS (R) .BJ F SOCS to PCS (R) al F Queach Tank
• Pressurizer Pressure (R)

PCS Tave (R) Pressurizer Level (R) Pzr Htr Amps Temp .llll F llZ! psia LRC-OlOlA J.B. " LCC 15 D Pressure .=l. Ptimaty Cealant System Loop 1 (TR-0111) !!Z. Loop 2 (TR-0121) !SS. LRC-01018 LCC 16 D J.B. " psig Level M LIA-0102A 35 X PORV PRV-10428 tL.llS.ED. PRV-10438 tL.llS.ED. Block Valve MOV-1042A .Q.Pfft MOV-1043A .Q.Pfft PCPs P-50A .llEE P-508 .llEE P-SOC .llEE P-500 .llEE Reactor Power Level NI-01 Z?E+Ol NI-OZ *Z?E+Ql Nl-03 ZJE-QB Nl-04 71 E-OB Nl-05 SSE-DJ Nl-06 ..A.llE.::.Ql . Nl-07 BSE-01 NI-OB SSE-OJ AE\i system AFW Pump P-BA .llEE P-BB .llEE P-BC .llEE AFW Pump Amps P-BA D P-BC ~ AFW Pump P-BB Steam Pressure 435 psig AFW Disch Press P-BA &P-BB lPl.a P-BC l psi Secendary System MSIV Bypass MOV-0501 tL.llS.ED. MOV-0510 tL.llS.ED. MSIV's CV-0501 tL.llS.ED. CV-0510 tL.llS.ED. MFP Suction Pressure lS. psig MFP Discharge Pressure A lS. B lS. psi Moisture Separator Drain Tank Level .13. " Condenser Hotwell Level .6B. Atmospheric Dump Valves Heater Drain Pump Status IHB.PI P-lOA .llEE P-108 .llEE Condenser Vacuum Gland Seal Condenser Vacuum D " in Hg. l!..2. in Hg. Condensate Pump Status P-2A .llEE P-28 .llEE

                                                                                  .f.lP (Demand Log      +  Constant, Rod, or Flux/Temp)

Gross MW D Net MW .:J Core Exit Thermocouple Temperature !sz...a F Control Rod Position GPl D GP2 D GP3 D GP4 D GPS(P) .l3l GP6(A) D GP7(B) D

. k Rods           JiQfiE     # D

Date SEPTEMBER 1 1992 Message I ll. (Page 2) Time .lll5 Scenario Time ~ Time Jump Scenario Time Jump Condensate Storage Tank Level T-2 e T-81" Level S.O % T-939 Level A.a % 5.6.  % trument Air Pressure li2.3. psig tainment Building Pressure .a psig Dome Temperature a5 F Humidity £2 x A Compartment Temperature .a.z. F Humidity .5A  %

   /G B Compartment                                                       Temperature         .a.z.         F     Humidity .5!       %

SIRW Tank Level fili % WR Containment Pressure (R) l i psi a Containment Sump Level l.a % Containment Water Level (R) .a  % SI Tank Level (%) A .52. B A.a c A.a D A.a SI Tank Pressure (psig) A 2.32. B lli c zzs D 2.3.3. PANE! K-13 SIAS Alarm lli Containment High Pressure Alarm Jill Containment High Radiation Alarm Jill Concentrated Boric Acid Tank Levels T53A .LI! x T53B 6.8  % Reactor Vessel DP z...a psid PORV Discharge Temperature fili F Pzr Safety Valve Discharge Temp (F) RV-1039 fili RV-1040 fili RV-1041 fili PCP Current (Amps) P-50A .a P-50B .a P-5DC .a P-50D .a PCS Flow 2.  % Pressure Level (cold) ~  % Loop Thot (F) Loop 1 !5.11 Loop 2  !.52. . Loop Tcold (F) Tcold Wide range Subcooling PCS Prssure Loop 1 Loop 1 Temp WR m ilQ

                                          .l2..D F ill!

Loop 2 Loop 2 Press NR ilQ ill

                                                                    .B.O.l psi f.D!l psi a Steam Generator A                                 Steam Generator B Level                          (WR)     .!11. %         (NR)      .!11.   %       (WR)      .S.S. x              (NR)     .S.S.    %

Press lli psi a .9.Bl psi a Flow Steam ...l PPH Feed .a PPH Steam .ll PPH Feed .a PPH Note: Steam and Feed Flow x 1000000 AFW Flow to A S/G From P-BA&B 2..52. From P-8C .ll AFW Flow to B S/G From P-8A&B .ll From P-8C .a Condenser Vacuum (R) .a PCP Seal Leakoff Flow P-50A ...a. PPH P-508 ...a. PPH P-5DC ...a. PPH P-500 ...a. PPH

  ~

Diesel Generator Frequency 1-1 ...Q 1-2 -.Jl:- 1-C BUS Voltage 2.A.a.z. Amp.s m 1-D BUS Voltage 2.A.a.z. Amps .19.5 C-l l Bac:k C-l l A Containment Area Monitors (R/Hr) RIA-1805 -.fi5.D RIA-1806 ....3..5..Q RIA-1807 -2.2.ll RIA-1808 ...lB.a High Range Containment Monitors (R/Hr) RIA-2321 l RIA-2322 l Containment Hydrogen Concentration (%) Al-2401R ..Ali Al-2401L ..Ali Main Steam Line Ga111na (cpm) RIA-2324 ...ill+/-.Dl RIA-2323 7 SE+Q3 Stack Monitors RIA-2325 .lD.ll cpm RIA-2326 fill cpm RIA-2327 ...2. mr/hr

• PALEX-92 Scenario: Time: 1130 Message No: 18 Scenario Time: 0300 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Message For: Operators Simulated Plant Conditions:

Message:

1. See Data Sheets.

2. Alarm Status is unchanged .

• FOR CONTROLLER USE ONLY Controller Notes:

Action Expected:

Date SEPTEMBER l 1992 Message I lB. (Page 1) Time .lllil Scenario Time Jl3..0.0. Time Jump Scenario Time Jump

  .t:;;QB.

SW Sumps P-7A mt P-78 mt P-7C mt SW Critical Hdr Press A SS B SS psig .Pumps P-52A mt P-528 mt P-52C mt FPC Pumps P-51A mt Pumps P-9A .PEE P-98 .PEE P-41 .QEE P-518 .QEE Coctaicmect Coolec Becicc Eac~ VlA mt V2A mt V3A mt V4A mt ' VlB .QEE V2B .QEE V3B .PEE V4B .QEE CCW Cooler Outlet Temp A .SO F B fil. F Containment Spray Pumps P-54A .PEE P-548 .PEE P-54C .QEE HPSI Pumps P-66A .PEE P-668 mt LPSI Pumps P-67A mt P-678 mt Safety Icjectioc Suction Supp]y Train A Train B CV-3057 (SIRW) .12.P.Efi CV-3029 (SIRW) tUlSfll CV-3031 (SIRW) .12.P.Efi CV-3030 (Sump) tUlSfll Ietdmm Chacgicg Intermediate Press Letdown Temp fill F Flow lZ.fi gpm Letdown Line Temp fill F Line Temp .l5l F Letdown Fl ow Z5 gpm Pumps P-55A mt P-558 mt P-55C mt Vo] *nne Coat col Tack Temp .B.5. F Pressure !5. psi Level fill  % PCP Control Bleedoff Pressure .53. psig Sh1Itdowc Coo] i cg System SOCS from PCS (R) .8.3. F SOCS to PCS (R) Bl F Quench Tack

• Pressurizer Pressure (R)

PCS Tave (R) Pressurizer Level (R) Pzr Htr Amps Temp J.Ql F Loop 1 (TR-0111) m

                                               .llS.S psi a LRC-OlOlA AZ. %

LCC 15 .0 Pressure Loop 2 (TR-0121) LRC-01018 LCC 16

                                                                                 .:.1 Pclmacy Coolant System psig                       Level .6!

LIA-0102A lB. PORV PRV-10428 tUlSfll PRV-10438 Block Valve MOV-1042A .12.P.Efi MOV-1043A .12.P.Efi PCPs P-50A .PEE P-508 P-SOC .QEE P-500 .QEE Reactor Power Level NI-01 Z?E+Pl. NI Nl-03 ZlE-QR NI-04 71 E-QR NI-05 41 E-01 Nl-06 Nl-07 64E-Ql Nl-08 66E-Pl AEW System AFW Pump P-8A .QEE P-88 .PEE P-8C .PEE AFW Pump Amps P-BA .0 P-8C .0 AFW Pump P-88 Steam Pressure .P psig AFW Disch Press P-8A & P-88 Z!2 P-8C l psi Secocdacy system MSIV Bypass MOV-0501 tUlSfll MOV-0510 tUlSfll MSIV's CV-0501 tUlSfll CV-0510 tUlSfll MFP Suction Pressure 15 psig MFP Discharge Pressure A 15 B 15 psi Moisture Separator Drain Tank Level lJ. % Condenser Hotwell Level .lil % Atmospheric Dump Valves Il:IRPI Condenser Vacuum .P in Hg. Heater Drain Pump Status P-lOA .PEE P-108 .QEE Gland Seal Condenser Vacuum l!..z in Hg. Condensate Pump Status P-2A .QEE P-28 .QEE (Demand Log + Constant, Rod, or Flux/Temp) Gross MW .Q Net MW .=! Core Exit Thermocouple Temperature Al3...5 F Control Rod Position GP! .P GP2 .0 GP3 .0 GP4 .0 GP5(P) l.3.l GP6(A) .0 GP7(B) .0

• Rods liOHE I .0

Date SEPTEMBER 1992 Message I .la (Page 2) Time ll.3..0. Scenario Time .lllQil Time Jump Scenario Ttme Jump T-81 Level .9.12 % T-939 Level il  % Condensate Storage Tank Level T-2 .5Z rument Air Pressure .9.5. psig ainment Building Pressure .l2 psig Dome Temperature M F Humidity .5.12

• A Compartment Temperature .az F Humidity .5!

S/G B Compartment Temperature .Bl F Humidity .5! SIRW Tank Level M  % WR Containment Pressure (R) l i psi a Containment Sump Level l.l2 % Containment Water Level (R) .l2 SI Tank Level (%) A 5Z B !B. t !B. D .4a SI Tank Pressure (psig) A ill B Z21. c .zzg D Z3.'3. PANE! K-13 SIAS Alann I.ES Containment High Pressure Alann HQ Containment High Radiation Alann HQ Concentrated Boric Acid Tank Levels T53A U  % T53B 6.B  % Reactor Vessel DP .Lli psid PORV Discharge Temperature B5 F Pzr Safety Valve Discharge Temp (F) RV-1039 B5 RV-1040 B5 RV-1041 B5 PCP Current (Amps) P-SOA .l2 P-50B .l2 P-50C .l2 P-SOD .l2 PCS Flow l  % Pressure Level (cold) 31..Z  % Loop Thot (F) Loop 1 ill Loop 2 !ll Loop Tcold (F) Loop 1 ill Loop 2 ill Tcold Wide range Loop 1 ill Loop 2 Ail Subcooling Temp ill F Press fill psi PCS Prssure WR ll.55 NR .6!lll psia Steam Generator A Steam Generator B Level (WR) .9Z x (NR) .9Z  % (WR) .SS % (NR) .SS  % Press .zaz psi a ~ psi a Flow Steam ..l. PPH Feed .l2 PPH Steam .D. PPH Feed . PPH

                                                                                                                            .D.

Note: Steam and Feed Flow x 1000000 AFW Flow to A S/G From*P-BA&B .l2 From P-8C .D. AFW Flow to B S/G From P-BA&B .D. From P-8C .D. Condenser Vacuum (R) .D. PCP Seal Leakoff Flow P-50A ...B. PPH P-50B ...B. PPH P-50C ...B. PPH P-50D ...B. PPH t:.ll! Diesel Generator Frequency 1-1 ...D. 1-2 *...a-1-C BUS Voltage Z!.Bl. Amps ila 1-D BUS Voltage ~ Amps .2fil2 C-ll Dack t-llA Containment Area Monitors (R/Hr) RIA-1B05 ...6.5.Q RIA-1806 ...lS.Q RIA-1807 ..1ZD RIA-180B ...lfil2 High Range Containment Monitors (R/Hr) RIA-2321 .1. RIA-2322 l Containment Hydrogen Concentration (%) AI-2401R ...5 Al-2401L ...5 Main Steam Line Ga11111a (cpm) RIA-2324 ...6.Qf+/-Ql RIA-2323 7 4f+03 Stack Monitors RIA-2325 Jfil2 cpm RIA-2326 fill cpm RIA-2327 ..Z mr/hr

Scenario: PALEX-92 Time: 1145

• Message No: 19 Scenario Time: 0315 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Message For: Operators Simulated Plant Conditions:

Message:

1. See Data Sheets.

2. SIG 'B' is offscale high.

• FOR CONTROLLER USE ONLY Controller Notes:

SIG 'B' is essentially solid at this point. An actual simulator malfunction is quite likely from now on due to operation near parameter limits; Control Room Controller must be prepared to revert to hard copy backup data. Action Expected: Permit SIG 'B' to fill, or steam it. In either event, release results .

Date SEPTEMBER l 1992 Message I l i (Page 1) Time .lli5 Scenario Time .ll3l5 Time Jump Scenario Time Jump t.:ila SW Sumps P-7A .llff P-78 .llff P-7C .llff SW Critical Hdr Press A .99. B .99. psig

• P-52A .llff P-528 .llff P-52C .llff FPC Pumps P-51A .llff e Pumps Pumps P-9A JlEE P-98 JlEE P-41 .Q.EE P-518 .Q.EE Ccotaiomeot Ccclet Becitc Eans VlA .llff V2A .llff V3A .llff V4A .llff VlB JlEE V2B JlEE V3B JlEE V4B .Q.EE CCW Cooler Outlet Temp A £2 F B .5l F Containment Spray Pumps P-54A JlEE P-548 .Q.EE P-54C .Q.EE HPSI Pumps P-66A IJlL P-668 .llff LPSI Pumps P-67A .llff P-678 .llff Safety IoiecticD SucticD Supply Train A Train B CV-3057 (SIRW) .Q.P.Ert CV-3029 (SIRW) tLaS.Ell CV-3031 (SIRW) .Q.P.Ert CV-3030 (Sump) tLaS.Ell Letdcwn Chug;ng Intennediate Press Letdown Temp .az. F Flow lZ5 gpm Letdown Line Temp .az. F Line Temp .129. F Letdown Flow Zl gpm Pumps P-55A .llff P-558 .llff P-55C .llff Ve] 'R Ccotml Tank Temp a! F Pressure 5l psi Level az  % PCP Control Bleedoff Pressure .6l psig Sh1Jtdcwn Ccc] i DP Systf'!I!

SOCS from PCS (R) 8.3. F SOCS to PCS (R) Bl F Pueoch Tank

• Pressurizer Pressure (R)

PCS Tave (R) Pressurizer Level (R) Pzr Htr Amps Temp lllZ F

                                                    .99.5 psi a Pressure .:.l Loop 1 (TR-0111) i l l Loop 2 (TR-0121) !0.3.

LRC-OlOlA AZ % LCC 15 D. LRC-01018 AZ % LCC 16 D. psig Ptimaty Ccclaot Systf'!I! Level .6! LIA-0102A 3Z PORV PRV-10428 tLaS.Ell PRV-10438 tLaS.Ell Block Valve MOV-1042A .Q.P.Ert MOV-1043A .Q.P.Ert PCPs P-50A .Q.EE . P-508 .Q.EE P-50C JlEE P-500 JlEE Reactor Power Level NI-01 ZZE+Ol NI ZZE+Pl NI-03 ZIE-Oa NI-04 ZIE-oa NI-05 41E-Ol NI-06 40E-P1 NI-07 li!iE-01 NI-08 lillE-01 AE\I Systf'!I! AFW Pump P-SA QEE P-SB QEE P-SC QEE AFW Pump Amps P-SA D. P-SC D. AFW Pump P-SB Steam Pressure D. psig AFW Disch Press P-SA & P-SB l5 P-SC l psi seccodatv System MSIV Bypass MOV-0501 tLaS.Ell MOV-0510 tLaS.Ell MSIV's CV-0501 tLaS.Ell CV-0510 tLaS.Ell MFP Suction Pressure ll psig MFP Discharge Pressure All B ll psi Moisture Separator Drain Tank Level 13. % Condenser Hotwell Level .Ii.Ii % Atmospheric Dump Valves . IHllilI Condenser Vacuum D. in Hg. Heater Drain Pump Status P-lOA QEE P-108 .Q.EE Gland Seal Condenser Vacuum .l!.2. in Hg. Condensate Pump Status P-2A .Q.EE P-28 QEE

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

Gross MW D. Net MW .:! Core Exit Thennocouple Temperature !ZZ...5. F Control Rod Position GPl D. GP2 D. GP3 D. GP4 D. GP5(P) lll GP6(A) D. GP7(B) D.

. c k Rods         .tilltiE     I D.

Date SEPTEMBER 199? Message I 19. (Page 2) Time .l.li5 Scenario Time .a3.l5 Time Jump Scenario Time Jump T-81 Level .9.D. % T-939 Level !5 % Condensate Storage Tank Level T-2 .5a rument Air Pressure .l.ll.O. psig ainment Building Pressure .D. psig Dome Temperature .a! F Humidity .51. A Compartment _ Temperature .az. F Humidity .5! I B Compartment Temperature .Bl. F Hurni di ty ,5! SIRW Tank Level .a! % WR Containment Pressure (R) l i psi a Containment Sump Level l.D.  % Containment Water Level (R) .D. SI Tank Level (%) A .52. B 411 c 411 D 411 SI Tank Pressure (psig) A 2.31 B Z2l. c .zig D Z3l PANE! K-13 SIAS Alann l'..E.S. Containment High Pressure Alann Jill Containment High Radiation Alann Jill Concentrated Boric Acid Tank Levels T53A LI  % T53B 6.8  % Reactor Vessel DP .a...o. psid PORV Discharge Temperature .as F Pzr Safety Valve Discharge Temp (F) RV-1039 .as RV-1040 .as RV-1041 .as PCP Current (Amps) P-50A .D. P-50B .D. P-50C .D. P-50D .D. PCS Flow 2.  % Pressure Level (cold) 31...5  % Loop Thot (F) Loop l ill Loop 2 ill Loop Tcold (F) Loop 1 !llZ. Loop 2 !12.6. Tcold Wide range Loop 1 !12.6. Loop 2 3.B.D. Subcooling Temp .ll.9. F Press .lifia psi PCS Prssure WR .!l9..6. NR fillil psi a Steam Generator A Steam Generator B Level (WR) ll5 % (NR) SA  % (WR) .l.ll.O. % (NR) .l.ll.O. % Press lli psi a ill psi a Flow Steam ..2. PPH Feed PPH Steam ...5 PPH Feed PPH

                                                                        .D.                                                         .D.

Note: Steam and Feed Flow x 1000000 AFW Flow to A S/G From P-8A&B .D. From P-8C .D. AFW Flow to B S/G From P-8A&B .D. From P-8C .D. Condenser Vacuum (R) .D. PCP Seal Leakoff Flow P-50A ...a PPH P-50B ...a PPH P-50C ...a PPH P-50D ...a PPH t=il! Diesel Generatdr Frequency 1-1 ....D. 1-2 :..0.

• 1-C BUS Voltage 2.4!il Amps ill 1-D BUS Voltage 2.4!i2. Amps 35.D.

C:-ll Back C:-llA Containment Area Monitors (R/Hr) RIA-1805 ...fi.S.12 RIA-1806 ...J5a RIA-1807 ..2.lll RIA-1808 ...lfill High Range Containment Monitors (R/Hr) RIA-2321 l RIA-2322 l Containment Hydrogen Concentration (%) AI-2401R ...5.5 Al-2401L ...5.5 Hain Steam Line Gallllla (cpm) RIA-2324 39 QE+Q3 RIA-2323 42 QF+Q3 Stack Monitors RIA-2325 .3..QQ cpm RIA-2326 .6.0 cpm RIA-2327 ..2. mr/hr

Scenario: *PALEX-92 Time: 1155 Message No: 20 (Contingency) Scenario Time: 0325 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE SHEET Message For: Operators Simulated Plant Conditions: Message: A loud noise of escaping steam is heard coming from the vicinity of the Main Steam Safety Valve discharge stacks .

• FOR CONTROLLER USE ONLY Controller Notes:

Delete this message if Operators have commenced steaming SIG 'B'. Action Expected: Protective action recommendations will Qe revised as appropriate .

Scenario: *PALEX-92 Time: 1200 Message No: 21 Scenario Time: 0330 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE SHEET Message For: Operators Simulated Plant Conditions: Steaming SIG 'B'. Message:

1. See Oat.a Sheets.

2. Alarm Status is unchanged .

• FOR CONTROLLER USE ONLY Controller Notes:

Cooling SIG 'B' has only a momentary effect on SIG 'B' pressure due to the existance of the tube rupture; SIG 'B' pressure is essentially controlled by PCS pressure. Action Expected: _ SIG 'B' will be steamed (or will steam) in conjunction with throttled safety injection flow to reduce PCS pressure and resultant primary to secondary dP .

Date SEPTEMBER 1 1992 Message I Zl (Page l) Ti me .lZl2.0. Scenario Time !lllil Time Jump Scenario Time Jump

 !:=lla SW Sumps            P-7A .a.ti           P-7B .a.ti                P-7C .a.ti                 SW Critical Hdr Press                 A~                                B~       psig

.Pumps P-52A .a.ti P-52B .a.ti P-52C .a.ti FPC Pumps P-SlA .a.ti Pumps P-9A .D.EE P-9B .D.EE P-41 .D.EE P-SlB .D.EE Coctaj!llllect Coolet Becjtc Eacs VlA .a.ti V2A .a.ti V3A .a.ti V4A .a.ti Vl8 .D.EE V28 .D.EE V38 .D.EE V4B .D.EE CCW Cooler Outlet Temp A .512 F B Sl F Containment Spray Pumps P-54A .D.EE P-54B .D.EE P-54C .D.EE HPSI Pumps P-66A .D.EE P-668 .a.ti LPSI Pumps P-67A .a.ti P-678 .a.ti Safety lcjectioD Suctjoc Supply Train A Train 8 CV-3057 (SIRW) .ae.Eft CV-3029 (SIRW) .cLa.S.Ell CV-3031 (SIRW) .ae.Eft CV-3030 (Sump) .cLa.S.Ell I etd 0wn Cbntg1ng Intennediate Press Letdown Temp .az. F Flow .lZ5 gpm Letdown Line Temp .az. F Line Temp lZS F Letdown Fl ow Zl gpm Pumps P-SSA .ll.ti P-558 .a.ti P-SSC .a.ti Volume Cocttol Tack Temp M F Pressure .5.3. psi Level .az  % PCP Control 8leedoff Pressure .61 psi g ShutdoWI! Cool i cg Systt:m SOCS from PCS (R) a3. F SOCS to PCS (R) .Bl F Quecch Tack

• Pressurizer Pressure (R)

PCS Tave (R) Pressurizer Level (R) Pzr Htr Amps Temp lDZ F Sfil2 psi a Loop 1 (TR-0111) ill Loop 2 (TR-0121) l9.Q LRC-OlOlA !!l % LCC 15 .D. Pressure .:l. Ptimaty Coolact System LRC-OlOlB !!l % LCC 16 .ll psig Level l i LIA-0102A 35 PORV PRV-10428 ilP.S.ED. PRV-10438 .cLa.S.Ell Block Valve MOV-1042A .aeEtt MOV-1043A .aeEtt PCPs P-SOA .D.EE P-508 .D.EE P-SOC .D.EE P-500 .D.EE Reactor Power Level NI-01 Z?F+O! NI ZZE+OJ NI-03 ZIF-08 NI-04 ZIE-QB NI-OS 41 E-01 NI-06 ..!llE=.Jll. NI-07 65F-Q! NI-08 66E-OJ AN System AFW Pump P-8A .D.EE P-88 .D.EE P-8C .QEE AFW Pump Amps P-8A .D. P-8C .D. AFW Pump P-88 Steam Pressure .D. psig AFW Disch Press P-8A &P-88 l.6. P-8C l psi SecocdatY System MSIV Bypass MOV-0501 .cLa.S.Ell MOV-0510 .cLa.S.Ell MSIV's CV-0501 .cJJ2S.E12 CV-0510 .cLa.S.Ell MFP Suction Pressure 15 psig MFP Discharge Pressure A 15 8 15 psi Moisture Separator Drain Tank Level l3. % Condenser Hotwell Level .6fi  % Atmospheric Dump Valves IHB.D.I Condenser Vacuum .D. in Hg. Heater Drain Pump Status P-lOA .QEE P-108 .QEE Gland Seal Condenser Vacuum .l!..Z. in Hg. Condensate Pump Status P-2A .QEE P-28 .QEE (Demand Log + Constant, Rod, or Flux/Temp) Gross MW .D. Net MW .=! Core Exit Thennocouple Temperature m F Control Rod Position GPl .D. GP2 .D. GP3 .D. GP4 .D. GPS(P) l3.l GP6(A) .D. GP7(B) .D. . k Rods lil2fiE I .D.

Date SEPTEMBER l 1992 Message I Zl (Page 2) Ti me J.Z..Qil Scenario Time .l233!l Time Jump Scenario Time Jump T-81 Level .9.0. % T~939 Level !fi % Condensate Storage Tank Level T-2 .5Z trument Air Pressure l.W2 psig tainment Building Pressure .0 psig Dome Temperature .a! F Humidity Sl

• A Compartment Temperature Sl F Humidity .5!

S/G B Canpartment Temperature .al F Humidity .5! SIRW Tank Level Sl % WR Containment Pressure (R) l i psi a Containment Sump Level 1.0  % Containment Water Level (R) .0 SI Tank Level (%} A .5? B Ja c Ja D Ja SI Tank Pressure (psig) A m B 22.l. cm D Zl3. PANE!  !(-) 3 SIAS Alarm IES Containment High Pressure Alarm till Containment High Radiation Alarm till Concentrated Boric Acid Tank Levels T53A LI  % T53B 6.8  % Reactor Vessel DP .a..n psid PDRV Discharge Temperature .as F Pzr Safety Valve Discharge Temp (F) RV-1039 .a5 RV-1040 .as RV-1041 .as PCP Current (Amps) P-50A P-508 .0 P-50C .0 P-50D .0 PCS Flow Pressure Level (cold) 35  % Loop Thot (F) Loop 1 Loop 2 fil Loop Tcold (F) Loop l Loop 2 m Tcold Wide range Loop 1 Loop 2 Jil Subcooling Temp Press .6fil2 psi PCS Prssure WR NR .6Qil psia Steam Generator A Steam Generator B Level (WR) .SS % (NR) .SS  % (WR) inn % (NR) inn  % Press 2.5.12 psi a .IW2 psi a Flow Steam ~ PPH Feed PPH Steam ....5 PPH Feed PPH

                                                                      .0                                                  .12 Note: Steam and Feed Flow x 1000000 AFW Flow to A S/G            Fran P-8A&B .12             Fran P-8C .12 AFW Flow to B S/G            Fran P-8A&B .12             Fran P-8C .12 Condenser Vacuum (R)                        .12 PCP Seal Leakoff Flow           P-50A      ..Ji    PPH    P-508     ..Ji     PPH     P-50C      ..Ji    PPH     P-50D   ..Ji    PPH t::.124 Diesel Generator Frequency           1-1 ...Q                  1-2 :...o-1-C BUS                         Voltage ZJal.                Amps ill 1-D BUS                         Voltage Z!Sl                 Amps ..3.fill r:-11 Back r:-11 A Containment Area Monitors (R/Hr)                          RIA-1805 ...55.Q             RIA-1806 ....3.5.Q RIA-1807 ..zza               RIA-1808 ...lfil2 High Range Containment Monitors (R/Hr)                   RIA-2321 l                   RIA-2322 l Containment Hydrogen Concentration (%)                   Al-2401R ...sa               Al-2401L ...sa Main Steam Line Gamna (cpm)                               RIA-2324 39 DE+Q3            RIA-2323 42 QF+Q3 Stack Monitors          RIA-2325 lllil         cpm     RIA-2326 fill           cpm RIA-2327      ~         mr/hr

Scenario: .PALEX-92 Time: 1215

• Message No: 22 PALISADES NUCLEAR PLANT Scenario Time: 0345 EMERGENCY PREPAREDNESS EXERCISE MESSAGE SHEET Mes.sage For: Operators Simulated Plant Conditions:

Steaming S/G 'B'. Mes.sage:

1. See Data Sheets.

2. Alarm Status is unchanged .

• FOR CONTROLLER USE ONLY Controller Notes:

Action Expected:

Date SEPTEMBER 1992 Message # .zz (Page 1) Ti me .lZ.l.S. Scenario Time .ll3!S Time Jump Scenario Time Jump SW Sumps P-7A .Q!i . P-78 .Q!i P-7C .Q!i SW Critical Hdr Press A .9.9. 8 .9.9. psig Pumps P-52A .Q!i P-528 .Q!i P-52C .Q!i FPC Pumps P-SlA .Q!i e Pumps P-9A .QEE P-98 .QEE P-41 .a.EE P-518 .QEE Coctaicmi:=ct Coolet Becitc Eac5 VlA .Q!i V2A .Q!i V3A .Q!i V4A .Q!i V18 .a.EE V28 .a.EE V38 .QEE V48 .a.EE CCW Cooler Outlet Temp A .5.12 F 8 .51 F Containment Spray Pumps P-54A .QEE P-54B .a.EE P-54C .a.EE HPSI Pumps P-66A .QEE P-66B .Q!i LPSI Pumps P-67A .Q!i P-67B .Q!i Safety Iciectioc Sucticc Sypp]y Train A Train B CV-3057 (SIRW) .Qffti CV-3P29 (SIRW) tL.llS.f.D. CV-3031 (SIRW) .Qffti CV-3030 (Sump) tL.llS.f.D. 1etdowt1 Chanticg Intennediate Press Letdown Temp .az. F Flow .lZ5 gpm Letdown Line Temp .az. F Line Temp lZ9 F Letdown Fl ow za gpm Pumps P-5SA .Q!i P-558 .Q!i P-SSC .Q!i Vol '!IDe Cocttol Tack Temp .a! F Pressure Sl psi Level fil X PCP Control Bleedoff Pressure .6.l psi g Sh1Jtdowt1 C00 li cg System SOCS from PCS (R) .8.3. F SOCS to PCS (R) Bl F Puecch Tonk

• Pressurizer Pressure (R)

PCS Tave (R) Pressurizer Level (R) Pzr Htr Amps Temp .lil? F

                                                   .9fil2 psi a Loop 1 (TR-0111) .41.Q Loop 2 (TR-0121)

LRC-OlOlA Ja X LCC 15 .D. Pressure :.l PtimatY Coolant Sy5tem LRC-OlOlB LCC 16 psig Level .6! LIA-0102A Jl X x PORV PRV-1042B CL!lS£l2 PRV-1043B Block Valve MOV-1042A .Qffti MOV-1043A .Qffti PCPs P-SOA .QEE P-SOB P-SOC .a.EE P-500 .a.EE Reactor Power Level NI-01 Z?E+OJ" ' NI-02 NI-03 ZlE-OB NI-04 ZlE-OB NI-OS 4lf-Ql NI-06 NI-07 !iSE-01 NI-08 !iliE-01 AE\l System AFW Pump P-8A .QEE P-8B .QEE P-BC .QEE AFW Pump Amps P-BA .D. P-8C .D. AFW Pump P-8B Steam Pressure .D. psig AFW Disch Press P-BA g P-8B l.6 P-8C l psi SecocdatY System MSIV Bypass MOV-0501 CL!lS£l2 MOV-0510 CL!lS£l2 MSIV's CV-0501 CL!lS£l2 CV-0510 CL!lS£l2 MFP Suction Pressure lS psig MFP Discharge Pressure A lS B lS psi Moisture Separator Drain Tank Level lJ X Condenser Hotwell Level .65 X Atmospheric Dump Valves IliBDI Condenser Vacuum .D. in Hg. Heater Drain Pump Status P-lOA .QEE P-lOB .QEE Gland Seal Condenser Vacuum lJ..Z in Hg. Condensate Pump Status P-2A .QEE P-2B .a.EE (Demand Log + Constant, Rod, or Flux/Temp) Gross MW .D. Net MW .=! Core Exit Thennocouple Temperature ill F Control Rod Position GPl .D. GP2 .D. GP3 .D. GP4 .D. GPS(P) .lJ1 GP6(A) .D. GP7(B) .D.

 . k Rods liQHE             # .D.

Date SEPTEMBER l 1992 Message I zz. (Page 2) Time .l2l.5 Scenario Time .123!5. Time Jump Scenario T.ime Jump T-81 Level ~ % T~939 Level ~  % Condensate Storage Tank Level T-2 .5.fi rument Air Pressure .lilil psig ainment Building Pressure !l psig Dome Temperature BA F Hurni di ty .51

• A Canpartment Temperature Bl F Hurni di ty .5!

S/G B Compartment Temperature Sl F Hurni di ty .5! SIRW Tank Level .B.12 x WR Containment Pressure (R) .li psi a Containment Sump Level l!l  % Containment Water Level (R) !l SI Tank Level (X) A .5Z. B AB C AB D AB SI Tank Pressure (psig) A m B ZZl c Z2.9 D Z3l PANE! !S'.-13 SIAS Alarm I.ES. Containment High Pressure Alarm tiO. Containment High Radiation Alarm tiO. Concentrated Boric Acid Tank Levels T53A LI  % T53B 6.8 x Reactor Vessel DP .a.a psid PORV Discharge Temperature .a5 F Pzr Safety Valve Discharge Temp (F) RV-1039 a5 RV-1040 a5 RV-1041 a5 PCP Current (Amps) P-SOA !l P-SOB !l P-50C !l P-50D !l PCS Flow z. x Pressure Level (cold) 33.....  % Loop Thot (F) Loop 1 m Loop 2 !128. Loop Tcold (F) Loop 1 !Ill. Loop 2 lB8 Tcold Wide range Loop 1 .41ll2 Loop 2 .3..6Z Subcooling Temp .12.!l F Press san psi PCS Prssure WR .9fil2 NR .6.llil psi a Steam Generator A Steam Generator B Level (WR) 9.3. x (NR) 9.3. x (WR) .lilil x (NR) .lilil x Press 2.3.Q psi a l9!l psi a Flow Steam ...z. PPH Feed !l PPH Steam ...5 PPH Feed !l PPH Note: Steam and Feed Flow x 1000000 AFW Fl ow to A S/G From P-8A&B !l From P-8C !l AFW Flow to B S/G From P-8A&B !l From P-8C !l Condenser Vacuum (R) !l PCP Seal Leakoff Flow P-SOA ...a , PPH P-SOB ...a PPH P-SOC ...a PPH P-50D ...a PPH Diesel Generator Frequency 1-1 ...D. 1-2 *...o.. 1-C BUS Voltage liSl Amps ill 1-D BUS Voltage li.aZ Amps ..3.6.Q C-11 e11 ck c-11A Containment Area Monitors (R/Hr) RIA-1805 ...6.S.12 RIA-1806 ...3.50 RIA-1807 ..1.Z!l RIA-1808 ...l.B.12 High Range Containment Monitors (R/Hr) RIA-2321 1 RIA-2322 l Containment Hydrogen Concentration (%) AI-2401R ...53. AI-2401L ...53. Main Steam Line Gamna (cpm) RIA-2324 39 OF+03 RIA-2323 42 OE+03 Stack Monitors RIA-2325 .3..12.Q cpm RIA-2326 fill cpm RIA-2327 ...Z. mr/hr

Scenario: .PALEX-92 Time: 1230

• Message No: 23 PALISADES NUCLEAR PLANT Scenario Time: 0400 EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Message For: Operators Simulated Plant Conditions:

Steaming SIG 'B'. Message:

1. See Data Sheets.

2. Alarm Status is unchanged.

• FOR CONTROLLER USE ONLY Controller Notes:

This message and the subsequent 1245 message and data may be omitted at the descretion of the Lead Controller if exercise objectives have been demonstrated. Action Expected:

Date SEl!IEt!BEB l99Z Message I ZJ. (Page 1) Ti me .lZJ.!l Scenario Time .Q!ilil Time Jump Scenario Time Jump t=ila SW Sumps P-7A mt .. P-7B mt P-7C mt SW Critical Hdr Press A~ B~ psig P-52A mt P-52B mt P-52C mt FPC Pumps P-51A mt .Pumps Pumps P-9A .a.EE P-9B .a.EE P-41 .a.EE P-51B .a.EE Coctajcmect Coolec Becjcc Eacs VlA mt V2A mt V3A mt V4A mt

• VlB .a.EE V2B .a.EE V3B .a.EE V4B .a.EE CCW Cooler Outlet Temp A £2 F B .51. F Containment Spray Pumps P-54A .a.EE P-54B .a.EE P-54C .a.EE HPSI Pumps P-66A .a.EE P-66B mt LPSI Pumps P-67A mt P-67B mt Safety Iciectjpn Suctjpc Supply Train A Train B CV-3057 (SIRW) .QfEli CV-3029 (SIRW) CU2Sf[1 CV-3031 (SIRW) .QfEli CV-3030 (Sump) CU2Sf[1 Letdowr1
• Chacgjcg Intermediate Press Letdown Temp .az. F Flow lZ.fi gpm Letdown Line Temp .az. F Line Temp ~ F Letdown Flow ZJ. gpm Pumps P-55A mt P-55B mt P-55C mt vol rune Cont col lank Temp 84 F Pressure .53 ps1 Level az X PCP Control Bleedoff Pressure .6l psig Sh1Jtdowr1 Cool i cg Systf!!D SOCS fran PCS. (R) al F SOCS to PCS (R) 81. F Quecch lack
• Pressurizer Pressure (R)

PCS Tave (R) Pressurizer Level (R) Pzr Htr Amps Temp lll4 F

                                             .9!D. psi a Loop 1 (TR-0111) !125. Loop 2 (TR-0121)

LRC-OlOlA Jfi X LCC 15 D Pressure .:l LRC-OlOlB LCC 16 psig l!cjmacv Coolact System Level M LIA-0102A 31. X X PORV PRV-1042B tl.PiEll PRV-1043B Block Valve MOV-1042A .QfEli MOV-1043A .QfEli PCPs P-50A .P.EE P-50B P-50C .P.EE P-500 .P.EE Reactor Power Level NI-01 Z2E+01

• NI NI-03 ZJE-08 Nl-04 ZlE-OB NI-05 41 E-01 NI-06 NI-07 SSE-Pl NI-08 SSF-01 AFW Pump P-8A .P.EE P-8B .P.EE P-8C .P.EE AFW Pump Amps P-8A D P-8C D AFW Pump P-8B Steam Pressure D psig AFW Disch Press P-8A & P-8B l6. P-8C Z psi Secocdarv System MSIV Bypass MOV-0501 tl.PiEll MOV-0510 tl.PiEll MSIV's CV-0501 tl.PiEll CV-0510 tl.PiEll MFP Suction Pressure l.5 psig MFP Discharge Pressure A l.5 B l.5 psi Moisture Separator Drain Tank Level J.3 X Condenser Hotwell Level .6.6 x Atmospheric Dump Valves IliB.PI Condenser Vacuum D in Hg.

Heater Drain Pump Status P-lOA .P.EE P-lOB .P.EE Gland Seal Condenser Vacuum l!.Z in Hg. Condensate Pump Status P-2A .P.EE P-2B .P.EE (Demand Log + Constant, Rod, or Flux/Temp) Gross MW D Net MW .:! Core Exit Thennocouple Temperature Jl6. F Control Rod Position GPl D GP2 D GP3 D GP4 D GP5(P) l3.l GP6(A) D GP7(B) D

-        Rod* JlllJiE    ID

Date SEPTEMBER 1 1992 Message I Z.l (Page 2) Ti me .l.Z3.l2 Scenario Time .l2A.l2!l Time Jump Scenario Time Jump T-81 Level Bil X T-939 Level Ali x Condensate Storage Tank Level T-2 .SS. x trument Air Pressure l!lQ psig tainment Building Pressure .l2 psig Dome Temperature a! F Humidity .51. x

• A Compartment Temperature .B2. F Humidity .5! x S/6 B Compartment Temperature Bl F Humidity .5! x SIRW Tank Level za x WR Containment Pressure (R) l i psia Containment Sump Level l.l2 x Containment Water Level (R) .l2 x SI Tank Level (X) A .5Z B !B. c !B. D !B.

SI Tank Pressure (psig) A Z3Z B ZZl c z.za D Zl3. PANE! K-13 SIAS Alarm I.ES Containment High Pressure Alarm tiC2 Containment High Radiation Alarm tiC2 Concentrated Boric Acid Tank Levels T53A u x T53B 6.8 x Reactor Vessel DP .B....ll psid PORV Discharge Temperature B5 F Pzr Safety Valve Discharge Temp (F) RV-1039 B5 RV-1040 B5 RV-1041 B5 PCP Current (AmpsJ P-50A .l2 P-50B .l2 P-50C .l2 P-50D .l2 PCS Flow z. x Pressure Level (cold) 31- x Loop Thot (F) Loop 1 .w. Loop 2 !.!23. Loop Tcold (F) Loop 1 :m Loop 2 .3.al Tcold Wide range Loop 1 J.!15 Loop 2 ill Subcool1ng Temp ill F Press .6QO psi PCS Prssure WR .9!12 NR fillQ psi a Steam Generator A Steam Gene*rator B Level (WR) Sl x (NR) Sl x (WR) l!lll x (NR) l!lll x Press 2.l.l2 psi a lZ.l2 psi a Flow Steam ..z. PPH Feed .l2 PPH Steam ...s PPH Feed .l2 PPH Note: Steam and Feed Flow x 1000000 AFW Flow to A S/G From P-BA&B .l2 From P-BC .l2 AFW Flow to B S/G From P-BA&B .l2 From P-BC .l2 Condenser Vacuum (R) .l2 PCP Seal Leakoff Flow P-50A ...a PPH P-50B ...a PPH P-50C ...B. PPH P-50D ...B. PPH Diesel Generator Frequency 1-1 ...a 1-2 -...a-1-C BUS Voltage 2.!B.l. Amps ill 1-D BUS Voltage lliz. Amps Jfill C-11 Rack C-llA Containment Area Monitors (R/Hr) RIA-1805 ...6.SD RIA-1806 ...lS.l2 RIA-1807 ..1Zil RIA-1808 ..J.ail High Range Containment Monitors (R/Hr) RIA-2321 l RIA-2322 l Containment Hydrogen Concentration (%) AI-2401R ....62 AI-2401L ....62 Main Steam Line Garnna (cpm) RIA-2324 39 DE+D3 RIA-2323 ~2 DE+D3 Stack Monitors RIA-2325 lO.l2 cpm RIA-2326 .6.l2 cpm RIA-2327 ..Z. mr/hr

Scenario: * .PALEX-92 Time: 1245 Message No: 24 Scenario Time: 0415 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE SHEET M~ge For: Operators Simulated Plant Conditions: Steaming SIG 'B'. M~ge:

1. See Data Sheets.

2. Alarm Status is unchanged .

• FOR CONTROLLER USE ONLY Controller Notes:

Action Expected:

Date SEeIEMBEB l!l!lZ Message # ZA (Page 1) Time ~ Scenario Time ~ Time Jump Scenario Time Jump

 .c.::aa SW Sumps            P-7A .[2fi.      P-78 .[2fi             P-7C .[2fi              SW Critical Hdr Press             A .SS                        B .SS   psig P-52A !lli       P-528 !lli             P-52C !lli              FPC Pumps                    P-51A !lli

.Pumps Pumps P-9A !LEE P-98 !LEE P-41 !LEE P-518 !LEE CcoiajomeDI Ccclet Becjtc Eans VlA !lli V2A !lli V3A !lli V4A !lli VlB !LEE V2B !LEE V3B !LEE V4B !LEE CCW Cooler Outlet Temp A . SD F B .51 F Containment Spray Pumps P-54A .Q.EE P-548 !LEE P-54C !LEE HPSI Pumps P-66A .Q.EE P-668 !lli LPSI Pumps P-67A !lli P-678 !lli Safeh Iniedjno SuciicD Supply Train A Train B CV-3057 (SIRW) .ae.Ef:L CV-3029 (SIRW) .cLllSfl2 CV-3031 (SIRW) .ae.Ef:L CV-3030 (Sump) .cLllSfl2 I eidown Charging Intermediate Press Letdown Temp .az. F Flow ill gpm Letdown Line Temp .az. F Line Temp lZJi F Letdown Flow .z:i gpm Pumps P-55A !lli P-558 !lli P-55C !lli Yclume Ccoirc] Iaok Temp a! F Pressure S:i psi Level .az  % PCP Control Bleedoff Pressure .lil psig Sh11idcW11 Cea] i og Systcw SOCS from PCS (R) Bl F SOCS to PCS (R) .Bl F Q11ench lank

• Pressurizer Pressure (R)

PCS Tave (R) Pressurizer Level (R) Pzr Htr Amps Temp lPZ. F LRC-OlOlA 3! % LCC 15 .P

                                                .!l2.P psi a Loop l (TR-0111) !Oil Loop 2 (TR-0121)

Pressure .:.1. LRC-01018 LCC 16 psig etimaty Cgc]aDI Sysiem Level LIA-0102A ~ M X X PORV PRV-10428 .cLllSfl2 PRV-10438 Block Valve MOV-1042A .ae.Et:L MOV-1043A PCPs P-SOA .Q.EE P-508 P-SOC .Q.EE P-500 Reactor Power Level NI-01 ZZE+Ol. NI-02" NI-03 Z]E-QB NI-04 NI-OS 41E-Ol NI-06 NI-07 65F-Ql NI-08 AE\{ Sysiem AFW Pump P-8A .Q.EE P-88 .Q.EE P-8C .Q.EE AFW Pump Amps P-8A .0 P-8C .0 AFW Pump P-88 Steam Pressure .P psig AFW Disch Press P-8A & P-88 1.6. P-8C l psi Secanduy System MSIV Bypass MOV-0501 .cLllSfl2 MOV-0510 .cLllSfl2 MSIV's CV-0501 .cLllSfl2 CV-0510 .cLllSfl2 MFP Suction Pressure l5 psig MFP Discharge Pressure A l5 B l5 psi Moisture Separator Drain Tank Level .1.2 % Condenser Hotwell Level .fifi X Atmospheric Dump Valves ll:iRPI Condenser Vacuum .P in Hg. Heater Drain Pump Status P-lOA .Q.EE P-108 !LEE Gland Seal Condenser Vacuum l!..2. in Hg. Condensate Pump Status P-2A .Q.EE P-28 !l.E£ (Demand Log + Constant, Rod, or Flux/Temp) ti Gross MW .Q Net MW =A Core Exit Thermocouple Temperature ill F Control Rod Position GPl .P GP2 .P GP3 .0 GP4 .0 GPS(P) .lJl. GP6(A) .0 GP7(B) .0 Rod* Ollllf ID

Date SEPTEMBER 1992 Message I 2J (Page 2) Time lZ!5. Scenario Time .ll!l.5 Time Jump Scenario Time Jump T-81 Level .9.Q % T-939 Level Afi % Condensate Storage Tank Level T-2 .5..5. trument Air Pressure .lili2 psig tainment Building Pressure D psig Dome Temperature .a! F Humidity fil.. A Compartment Temperature .az. F Humidity .5! I B Compartment Temperature .Bl F Humidity .5! SIRW Tank Level 1.6. % WR Containment Pressure (R) l l psi a Containment Sump Level 1.0  % Containment Water Level (R) .a SI Tank Level (%) A .5.2. B A.a C AH D AH SI *Tank Pressure (psig) A ill B 21l c lli D lli PANF! K-13 SIAS Alarm lli Containment High Pressure Alarm till Containment High Radiation Alarm till Concentrated Boric Acid Tank Levels T53A LI % T53B 6.8 % Reactor Vessel DP lW2 psid PORV Discharge Temperature .8.5 F Pzr Safety Valve Discharge Temp (F) RV-1039 .8.5 RV-104D .8.5 RV-1041 .8.5 PCP Current (Amps) P-5DA .a P-50B .a P-50C .a P-50D .c. PCS Flow .z % Pressure Level (cold) =li- % Loop Thot (F) Loop 1 A.ll9. Loop 2 JSB. Loop Tcold (F) Loop 1 m Loop 2 ill Tcold Wide range Loop 1 3.9.Q Loop 2 :i.52. Subcooling Temp ill F Press .6fill. psi PCS Prssure WR .s.z.a NR ~ psi a Steam Generator A Steam Generator B Level (WR) il % (NR) il  % (WR) .lili2 % (NR) .lili2 % Press 2lO. psi a 15.a psi a Flow Steam ....z PPH Feed .a PPH Steam ....5. PPH Feed .c. PPH Note: Steam and Feed Flow x lOOOOOD AFW Flow to A S/G From P-8A&B .a From P-8C .a AFW Flow to B S/G From P-8A&B .a From P-8C .a Condenser Vacuum (R) .a PCP Seal Leakoff Flow P-50A ...a PPH P-50B ...a PPH P-50C ...a PPH P-5DD ...a PPH t=Jl! Diesel Generator Frequency 1-1 ...n 1-2 -..a-1-C BUS Voltage 2J.Bl Amps ill 1-D BUS Voltage ZJ.az. Amps :ifill r:-ll Back r:-llA Containment Area Monitors (R/Hr) RIA-1805 ....6.5..0. RIA-18D6 ...3.fill RIA-1807 ....zz.a RIA-1808 ...lB.D High Range Containment Monitors (R/Hr) RIA-2321 l RIA-2322 l Containment Hydrogen Concentration (%) AI-2401R ..ll AI-2401L ..ll Main Steam Line Ganma (cpm) RIA-2324 39 OF+03 RIA-2323 42 OE+03 Stack Monitors RIA-2325 3.D.D cpm RIA-2326 fill cpm RIA-2327 ....Z mr/hr

• Scenario:

Message No:

                   .PALEX-92 25 PALISADES NQCLEAR PLANT Time:. 1300est Scenario Time: 0430est EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM Message For:            Site Emergency Director Simulated Plant Conditions:

Time Jump to new plant conditions. Message: Approximately 8 hours have elapsed from the time of the plant trip. Forced circulation has been regained by backfeeding the Main Transformer and restarting PCP's P-SOB and P-SOC. shutdown Cooling is in service, the Pressurizer is filled solid, and PCS cooldown is in progress at 40 degrees fahrenheit/hr.

        'B' Steam Generator is re-isolated (or steaming to atmosphere slowly if the piping break option was necessary) and is filled solid .

• 'R' Bus remains deenergized.

FOR CONTROLLER USE ONLY Controller Notes: Plant player participation begins to en~. Commence critiques. Selected Managers will participate in recovery planning. Action Expected: Recovery Planning begins .

Date SEPTEMBER l 1992 Message I ZS. (Page 1) Time Ufil2 Scenario Time ~ Time.Jump -Scenario Time Jump

• ~s VlA mi P-7A mi P-52A mi P-9A .PEE V2A mi P-7B mi P-52B mi P-9B .PEE V3A mi V4A mi P-7C .sraY P-52C .sraY P-41 .PEE C0 ntajnrnent C001er SW Critical Hdr Press FPt Pumps Recjrc fans VlB mi A fill P-SlA mi P-SlB .PEE V2B mi V3B mi Bl l V4B mi psig CCW Cooler Outlet Temp A l! F B ZS. F Containment Spray Pumps P-54A .PEE P-54B .PEE P-54C QEE HPSI Pumps P-66A .PEE P-66B .PEE LPSI Pumps P-67A mi P-67B QEE Safety Injectj 0 n Suctj 0n Supply Train A Train B CV-3057 (SIRW) ilPEli CV-3029 (SIRW) tLD.S.El2 CV-3031 (SIRW) .D.eEli CV-3030 (Sump) t1JlS.E.l2 Letdown Charging Intermediate Press Letdown Temp ill F Flow .8.3. gpm Letdown Line Temp fil F Line Temp lZZ. F Letdown Fl ow mi gpm Pumps P-SSA mi P-SSB mi P-SSC QEE Vol 1nne C0 ntr0 1 Tank Temp 35 F Pressure .S.O. psi Level .B.3.  % PCP Control Bleedoff Pressure .SZ. psig Shutdown C001 j ng System SOCS fran PCS (R) .2.SJ2 F SOCS to PCS (R) .2.1B. F
• Quench Tank Temp M F Pressure A psig Level z.a  %

Primary C00 lant System Pressurizer Pressure (R) m psi a PCS Tave (R) Loop l (TR-0111) .2.SJ2 Loop 2 (TR-0121) .2.Sfi Pressurizer Level (R) LRC-OlOlA li2l1 % LRC-DlOlB lPll % LIA-0102A 35  % Pzr Htr Amps LCC 15 .0 LCC 16 .0 PORV PRV-1042B .cLOSfl2 PRV-1043B t1JlS.E.l2 Block Valve MOV-1042A .D.eEli MOV-1043A ilPEli PCPs P-SOA .PEE

• P-SDB llfi. P-SDC mi P-SOD .PEE Reactor Power Level NI-01 72E+01* NI Z?E+Ql NI-03 Zlf-06 NI-04 71 F-06 NI-OS 41E-Ol NI-06 .ill.:.Ol NI-07 65F-QJ NI-08 43f-Ql AfW System AFW Pump P-8A .PEE P-8B .PEE P-8C .PEE AFW Pump Amps P-8A .0 P-8C .0 AFW Pump P-8B Steam Pressure .0 psig AFW Disch Press P-8A & P-8B .15 P-8C l psi Secondary System MSIV Bypass MOV-0501 t1JlS.E.l2 MOV-0510 J:l.PSfll MSIV's CV-0501 .cLOSfl2 CV-0510 J:l.PSfll MFP Suction Pressure lS psig MFP Discharge Pressure A lS B lS psi Moisture Separator Drain Tank Level l l % Condenser Hotwell Level ~  %

Atmospheric Dump Valves J:l.PSfll Condenser Vacuum .0 in Hg. Heater Drain Pump Status P-lDA .PEE P-lDB .PEE Gland Seal Condenser Vacuum .l!..1 in Hg. Condensate Pump Status P-2A .PEE P-2B .PEE (Demand Log + Constant, Rod, or Flux/Temp) Gross MW .Q Net MW =A Core Exit Thermocouple Temperature ~ F ol Rod Position GPl .0 GP2 .0 GP3 .0 GP4 .0 GPS(P)_ .lJl GP6(A) .0 GP7(B) .0 Rods lillfiE I .0

Date SEPTEMBER 1992 Message I 2.5 (Page 2) Time Uil!l Scenario Time ~ Time Jump Scenario Time Jump Level SD % T-939 Level !6. % Condensate Storage Tank Level T-2 .5.D.  % rument Air Pressure .lill2 psig ainment Building Pressure D. psig Dome Temperature M F Humidity .5l  % A Canpartment Temperature .az. F Humidity .5!  % S/G B Canpartment Temperature .Bl F Humidity .5!  % - SIRW Tank Level 20. % WR Containment Pressure (R) l! psi a Containment Sump Level 10. % Containment Water Level (R) D.  % SI Tank Level (%) A .sz. B !B. c !B. D J.B. SI Tank Pressure (psig) A 2.31 B 21Z c m D Z3l PANE! K-13 SIAS Alarm ~ Containment High Pressure Alarm .till Containment High Radiation Alarm .till

 .c.:.l2.

Concentrated Boric Acid Tank Levels T53A LI % T53B 6.8 % Reactor Vessel DP .12..l psid PORV Discharge Temperature .as F Pzr Safety Valve Discharge Temp (F) RV-1039 .as RV-1040 .as RV-1041 .as PCP Current (Amps) P-50A D. P-50B ill. P-50C ill P-500 D. PCS Flow Al % Pressure Level (cold) ~  % Loop Thot (F) Loop l 2.5.6 Loop 2 2.5.6 Loop Tcold (F) Loop 1 ill Loop 2 2.5.6 Tcold Wide range Loop l 2.5.6 Loop 2 2.5.6 Subcooling Temp l!9 F Press Z.3.l psi PCS Prssure WR m NR m psi a Steam Generator A Steam Generator B Level (WR) .as % (NR) .as  % (WR) .lill2 % (NR) .lill2 % Press ~ psi a A.5 psi a Steam ..1. PPH Feed D. PPH Steam ..s PPH Feed D. PPH Note: Steam and Feed Flow x 1000000 AFW Flow to A S/G From P-8A&B D. From P-8C D. AFW Flow to B S/G From P-8A&B D. From P-8C D. Condenser Vacuum (R) D. PCP Seal Leakoff Flow P-50A ..J PPH P-508 ..J' PPH P-50C PPH P-50D PPH Diesel Generator Frequency 1-1 .a 1-2 ...!i 1-C BUS Voltage .2!B.l. Amps ill 1-D BUS Voltage Z!B.Z Amps Jfill C-11 Back C-11 A Containment Area Monitors (R/Hr) RIA-1805 -6.5.0. RIA-1806 ...lS.D. RIA-1807 ...z.z.o. RIA-1808 ....lfill. High Range Containment Monitors (R/Hr) RIA-2321 l RIA-2322 l Containment Hydrogen Concentration (%) AI-2401R ..J.j, AI-2401L ..J.j, Main Steam Line Ga11111a (cpm) RIA-2324 39 OF+03 RIA-2323 42 OF+03 Stack Monitors RIA-2325 .lilil cpm RIA-2326 fill cpm RIA-2327 ..1. mr/hr

Date SEPTEMBER 1992 Message I 2.5. (Page 2) Time l3..l2.0. Scenario Time .ll!3.l2 Time Jump Scenario Time Jump T-81 Level .9.0. X T.-939 Level Ali x Condensate Storage Tank Level T-2 .5.l2 x trument Air Pressure

• lQll psig tainment Building Pressure .l2 psig Dome Temperature .a! F Humidity .51 x A Canpartment Temperature az F Humidity .5! x 7 B Canpartment Temperature .Bl F Humidity .5! x SIRW Tank Level 20. x

- WR Containment Pressure (R) l i psi a Containment Sump Level l.l2 % Containment Water Level (R) .l2  % SI Tank Level (X) A .5Z. B !B. c !B. D !B. SI Tank Pressure (psig) A ZJZ. B ill c .z.za D z:u PANE! K-13 SIAS Alarm @. Containment High Pressure Alarm .tiO. Containment High Radiation Alarm .tiO. C=l2 Concentrated Boric Acid Tank Levels T53A LI x T53B 6.8 % Reactor Vessel DP lZ...Z psid PDRV Discharge Temperature .as. F Pzr Safety Valve Discharge Temp (F) RV-1039 .as. RV-1040 .as. RV-1041 .as. PCP Current (Amps) P-50A .l2 P-50B lil P-50C ill. P-500 .0. PCS Flow  !.3. % Pressure Level (cold) ~  % Loop Thot (F*) Loop 1 2.5..6. Loop 2 2.5..6. Loop Tcold (F) Loop 1 z.s.s Loop 2 2.5..6. Tcold Wide range Loop 1 2.5..6. Loop 2 2.5..6. Subcooling Temp ill F Press ill psi PCS Prssure WR ill NR ill psi a Steam Generator A Steam Generator B Level (WR) .as. x (NR) .as. x (WR) lQll x (NR) lQll x Press 3.S. psi a AS psi a Flow Steam ..z PPH Feed .l2 PPH Steam ...5 PPH Feed .0. PPH Note: Steam and Feed Flow x 1000000 AFW Flow to A S/G From P-8A&B .l2 From P-8C .0. AFW Flow to B S/G From P-8A&B .0. From P-8C .0. Condenser Vacuum (R) .l2 PCP Seal Leakoff Flow P-50A -! PPH P-50B -! PPH P-50C -! PPH P-50D -! PPH Diesel Generator Frequency 1-1 ...l2 1-2 -...a 1-C BUS Voltage Z!B.l. Amps ASl. 1-D BUS Voltage .2.!.6.2 Amps .3..6.l2 C-ll Back C-JJA Containment Area Monitors (R/Hr) RIA-1805 ...fi.5.0. RIA-1806 ..3.S..l2 RIA-1807 ...z.z.o. RIA-1808 ...l.fill High Range Containment Monitors (R/Hr) RIA-2321 l RIA-2322 l Containment Hydrogen Concentration (X) Al-2401R _u Al-2401L _u Main Steam Line Ganma (cpm) RIA-2324 39 Of +03 RIA-2323 42 OE+03 Stack Monitors RIA-2325 .3..0..0. cpm RIA-2326 .fi.O. cpm RIA-2327 ..Z mr/hr

• .Scenario:

Message No: PALBX-92 25 Time: l 300est Scenario Time: 0430est

                                        ~AD~           NllQLEAR PLAJYt Y l'REPAREDJ.'iEs EXERCISE ALARM Alarm
         ~                       Annunc HEET Numb~

BK-02 17 BK-03 36 Main Steam E-son RIA-2323 Alen EK-05 Switchyard ACB Trip 19 BK-05 21 416()y Standby Power not AVaiJabJe BK-05 22 2400V Standby Power not A VailabJe BK-05 Bus Fail to Transfer 25 BK-og 63 Startup Transformers Trip BK-09 72 Steam Gen B-50B Hi Level BK-13 Reactor Trip 55

                                         - 'SIRW Tank T-58 Hi-Lo Level

Date SEPTEMBER l 1992 Message I 25 (Page 1) Time .l.ll5 Scenario Time .ll!i5 Time Jump Scenario Time Jump t.:il5 SW Sumps P-7A mi. P-78 mi P-7C .ilBl SW Critical Hdr Press A .an 8 19. psig P-52A mi p:...525 mi P-52C .ilBl FPC Pumps P-51A mi

• e Pumps Pumps P-9A .QEE P-98 QEE P-41 .QEE P-518 .QEE Ccctajcmect Coolet Becjtc Eacs VlA mi V2A mi V3A mi V4A mi Vl8 mi V28 mi V38 mi V48 mi CCW Cooler Outlet Temp A ll F B 15 F Containment Spray Pumps P-54A .QEE P-548 .QEE P-54C .QEE HPSI Pumps P-66A QEE P-668 .QEE LPSI Pumps P-67A mi P-678 .QEE Safety lcjecticn Sucticc Supp])'

Train A Train 8 CV-3057 (SIRW) !2f.Eti CV-3029 (SIRW) tulSfll CV-3031 (SIRW) !2f.Eti CV-3030 (Sump) CJJ2S.El2 1etdrnm Charging Intermediate Press Letdown Temp lll F Flow .a.3. gpm Letdown Line Temp ill F Line Temp lZZ F Letdown Flow .6.9. gpm Pumps P-55A mi P-558 mi P-55C .QEE Ve] 1nne Ccctto] Tack Temp as F Pressure Sil psi Level .a.3. X PCP Control 8leedoff Pressure .5Z psig Shutdown Cooling System SOCS from PCS (R) lli F SOCS to PCS (R) Zila F Q11ecch Tank

• Pressurizer Pressure (R)

PCS Tave (R) Pressurizer Level (R) Pzr Htr Amps Temp .8! F 2.62. psi a Loop 1 (TR-0111) lli Loop 2 (TR-0121) ill LRC-0101A lilD. X LCC 15 .0 Pressure ! Ptimaty Coc]ant System LRC-01018 LCC 16 .0l.Pil " psig Level LIA-0102A z.a as X PORV PRV-10428 tl.QSfll PRV-10438 CJJ2S.El2 Block Valve MOV-1042A !2f.Eti MOV-1043A !2f.Eti PCPs P-50A QEE P-508 mi P-50C mi P-500 .QEE Reactor Power Level Nl-01 72E+Ol NI-02 -Z?E+Ol NI-03 ZlE-011 NI-04 ZlE-oa NI-05 41 E-01 Nl-06 -!SE=ill. NI-07 liSE-Pl NI-08 !13E-Pl AE\I System AFW Pump P-8A .QEE P-88 QEE P-8C QEE AFW Pump Amps P-8A .0 P-8C .0 AFW Pump P-88 Steam Pressure .P psig AFW Disch Press P-8A & P-88 15 P-8C l psi Secondary System MSIV Bypass MOV-0501 .cJJ2S.Ell MOV-0510 .c:.tJlSfil MSIV's CV-0501 tl.QSfll CV-0510 CJJ2S.El2 MFP Suction Pressure 15 psig MFP Discharge Pressure A 15 B 15 psi Moisture Separator Drain Tank Level .1.1 X Condenser Hotwell Level .6.6. X Atmospheric Dump Valves CLnSfl2 Condenser Vacuum .P in Hg. Heater Drain Pump Status P-lOA QEE P-lOB .QEE Gland Seal Condenser Vacuum .1J..Z in Hg. Condensate Pump Status P-2A .QEE P-28 .QEE (Demand Log + Constant, Rod, or Flux/Temp) Gross MW .Q Net MW .:! Core Exit Thermocouple Temperature z.sz. F Control Rod Position GPl .P GP2 .0 GP3 .0 GP4 .0 GP5(P) .lll. GP6(A) .0 GP7(B) .0 411' Rod* JlllllE I ~

Date SEPTEMBER l 1992 Message I Zfi (Page 2) nme .l3.lS. Scenario Time ~ .* Time Jump Scenario Time Jump T-81 Level .!U2 % T-939 Level Condensate Storage Tank Level T-2 trument Air Pressure

• tainment Building Pressure

                                         !6.
                                         .l.Wl psig psig                       Dome Temperature .B!            F
                                                                                                                             .5.D.

Hurni di ty .51.

                                         .12 A Compartment                                                         Temperature         Bl          F    Humidity .5!

7 B Compartment Temperature al F Humidity .5! SIRW Tank Level - WR Containment Pressure (R) Containment Sump Level l.Q lD l i psi a Containment Water Level (R) SI Tank Level (%) A .5Z.

                                                "               B  ~                       c   ~

SI Tank Pressure (psig) A 2.31 B Z2l. c .z..zg PANE! K-13 SIAS Alann ~ Containment High Pressure Alann HQ Containment High Radiation Alann HQ Concentrated Boric Acid Tank Levels T53A LI T53B Reactor Vessel DP PORV Discharge Temperature

                                                                   .lZ..l psid
                                                                   .as F      "                6.8          "

Pzr Safety Valve Discharge Temp (F) RV-1D39 .as RV-1040 RV-1041 .B.5 PCP Current (Amps) P-50A .12 P-50B m. P-50C P-50D .12 PCS Flow Pressure Level (cold) Loop Thot (F) Loop Tcold (F) Loop 1 Loop 1 il U6 Z!5

                                                "       Loop 2 U6 Loop 2 U6 Tcold Wide range              Loop 1    U6             Loop 2 U6 Subcooling                    Temp      li9. F          Press     Zll psi PCS Prssure                   WR        m.             NR         2.62. psi a Steam Generator A                                    Steam Generator B Level                         (WR)      .as             (NR)      .as               (WR)                        (NR)

Press Flow Steam 35 psi a

                                         ...z PPH        Feed      .12 PPH    Steam
                                                                                               .l.Wl
                                                                                              !5 psi a
                                                                                               ...5 PPH
                                                                                                          "      Feed
                                                                                                                            .l.Wl
                                                                                                                            .12
                                                                                                                                    "  PPH Note: Steam and Feed Flow x 1000000 AFW Flow to A S/G         From P-8A&B   .12         From P-8C     .12 AFW Flow to B S/G         From P-8A&B   .12          From P-8C    .12 Condenser Vacuum (R)                    .12 PCP Seal Leakoff Flow         P-50A     ...!   PPH      P-50B     ...!      PPH     P-50C     ...!       PPH    P-50D      ...!       PPH Diesel Generator Frequency         1-1 ...n                  1-2 :...12-1-C BUS                       Voltage 2.fil                Amps ill 1-D BUS                       Voltage liaz                 Amps .3.fill C-11 Back C-JlA Containment Area Monitors (R/Hr)                      RIA-1805    ...5.5.12          RIA-1806     ...J.5.D.

RIA-1807 ...zzn RIA-1808 ...lilil High Range Containment Monitors (R/Hr) RIA-2321 l RIA-2322 l Containment Hydrogen Concentration (%) AI-2401R ..lB. Al-2401L ..lB. Main Steam Line Ganma (cpm) RIA-2324 39 CE+D3 RIA-2323 ~2 CE+D3 Stack Monitors RIA-2325 3.l2D cpm RIA-2326 fill cpm RIA-2327 ...Z mr/hr

CFMS OPERATIONS DATA

SHAVPALI TSC

• S T AT US P AGE *PALEX 92 Time 0800 Scenario Time -0030 Message # ! 140 Time Jump - Scenario Time Jump - -

C-13 C-12 PCP Curreiit""'{Amps) Condensate Storage Tank Level T-2 80  % P-50A 575 P-50B 592 Instrument Air Pressure 102 psig P-50C ~ P-50D r;f7 (15) Containment Building Pressure 0-- psig (6) PCS Flow (16) S/G A Compartment Temperature n2 F (3) Thot (F) Loop I 582 F S/G A COMPARTMENT Humidity 'Sl  % Loop 2 ~ F (16) S/G B Compartment Temperature 8' F (2) Tcold (F) Loop IA '5!5 F S/G B Humidity 'Sl  % Loop 2A '5!5 F

• (16) Dome Temperature an F Loop IB '5!5 F (11) SIRW Tank Level M  % Loop 2B '5!5 F (15) WR Containment Pressure (R) T4 psi a (5) Subcooling '5Ef" F 716* PSIA (14) Containment Sump Level 0  % (7) PCS WR Pressure (R) 2061 PSI~

(14) Containment Water Level (R) 0 ,3 (7) PCS NR Pressure (R) . bOO"" PSIA (22) SI Tank Level (%) (30) S/G A LEVEL WR 6s- % A 52 B 48 c 48 D 48 (30) S/G A LEVEL (R) 65 % SI Tan"k"Pressure-"Tpsig) (30) S/G A PRESS 790 psia A 233 B 228 c 230 D 234 S/G A STM FLW (R) 'S:"5 Xl0**6 PPH

,(21) SIAS Alarm                   -NO                                  S/G A FD FLW (R)         'S:"5 Xl0**6 PPH (30) S/G B LEVEL WR           6s- %

C-12 (30) S/G B LEVEL (R) 65 %' (30) S/G B PRESS 790 psia

• Concentrated Boric Acid Tank Levels S/G B STM FLW (R) 'S:"5 Xl0**6 PPH T53A 97.5  % S/G B FD FLW (R) '5:5 Xl0**6 PPH T53B ~  %

Reactor Vessel DP ~ psid PANEL K-13 (12) PORV Discharge Temperature an-- F (13) Pzr Safety Valve Discharge Tem~(F) (20) CONTAINMENT HIGH PRESS RV-1039 88 F NO RV-1040 an F RV-1041 an F (20) Containment High Radiation NO

SHAVPALI PALEX 92 TSC

• S T AT US P AGE
• Time 0800 Scenario Time -0030 Message # ! 141 Time Jump Scenario Time Jump C-01 C-04 MFP Suction Pressure 335 psig (32) D/G Freq
• 1-1 0 1-2 0 MFP A Discharge Pressure T004 psig (32) 1-C BUS VOLTS 2484 Amps285 MFP B Discharge Pressure TOOil psig (32) 1-D BUS VOLTS 248I Amps455 AFW Pump P-8C Amperes . 0-- AMPS AFW Discharge Pressure P-8C To psig C-11 BACK C-llA AFW Pump P-8A Amperes 0 AMPS AFW Pump P-88 Steam Pressure O psig (17) Containment Area Monitors AFW Discharge Pressure P-8A & P-8B To psig RIA-1805 .020 R/Hr Moisture SEP Drain Tank Level 64 % RIA-1806 :or9 R/Hr Condensor Hotwell Level 6j  % RIA-1807 -:120 R/Hr Condensor Vacuum 27.5 in Hg. RIA-1808 :0S0 R/Hr Gland Seal Condensor Vacuum T4.2 in Hg. (17) High Range ContaTniiient Monitors Atmospheric Dump Valves ITOSED RIA-2321 1 R/Hr AFW Pump P-8A OFF P-8B OFF P-8C OFF RIA-2322 T R/Hr

.Heater Drain Pump-       P-lOA Off" P-lOB Ofr                    (19) Containment Hydrogen Concentration

. Condensate Pump P-2A ON P-2B ON Al-2401R 0  % AI-2401L 0  % C-11 (30) Main Steam Line ~amma RIA-2324 23 CPM (31) AFW FLOW TO SGA RIA-2323 ~ CPM FROM P8A, B 0 From P-8C 0 gpm (31) AFW FLOW TO ~GB EQUIPMENT STATUS: FROM P-8A&B 0 From P-8C 0 gpm Condenser Vacuum (R) "2"8 IN HG. 1. SIGNIFICANT EQUIP OUTAGES PCP A Leak-off Flow (R) r.1 (INOPERABLE EQUIPMENT) PCP B Leak-off Flow (R) r.T 2. SURVEILLANCE DUE/PROGRESS PCP C Leak-off Flow (R) r.T 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off Flow (R) r.T OR OUTAGES

SHAVPALI PALEX 92 TSC

• S T AT US P AGE
• Time 0800 Scenario Time -0030 Message # ! 142
• Time Jump ~ Scenario Time Jump - -

C-08 C-02 SW Pumps P-7A ON P-78 ST8Y P-7C ON (10) VCT Temp 106 F CCW Pumps P-52A 'ST8Y P-528 ~ P-52C 'ST8Y (10) VCT Pressure ~ psi FPC Pumps P-51A ~ P-518 Off (10) VCT Level 66 % PCP Control 8leedoff Pressure 41 psig CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow 35 gpm (26) Charging Flow 44 gpm VIA ON V2A ON V3A ON V4A ON (9) Quench Tank Temp 102 F VlB ON V28 ON V38 ON V48 ON (9) Quench TANK Pressure :Y- psig (9) Quench TANK Level bj  % C-03 (7) Pressurizer Pressure (R) 2061 psia

                                              '                    (8) PZR Level (R)      LT0102A         ~ %

(23) HPSI Pumps P-66A OFF P-668 OFF LT0103 44.I % (25) LPSI Pumps P-67A TIFF' P-678 OFf (12) PORV PRV-1042A CLOSED 10438 'CIITSED

 * (18) Containment Spray Pumps-                                  (12) BLOCK MOV-1042A CLOSED 1043A CLOSED P-54A OFF P-548 OFF P-54C OFF                           CHARGING PUMPS (27) HPSIA, LPSIA:--SPRAY A SUCTION                                          P55A ON P55B OFF P55C OFF CV-3057 (SIRWT)         CV-3030 (Sump)            (6) PCPS     P50A ON P50B 00- P50C ~ P50D ON OPEN                    CLOSED                       PZR HTR AMPS --LC15 141-- LCC 16*141 (1) PCS TAVE (R) LOOPl--rTR-0111) '559 F LOOP2 (TR-0121) '559 F C-02                                     (25) REACTOR POWER LEVEL Nil .10E+06 cps Nl3 .97E+02 % NI7 98             %

Intermediate Press Letdown Temp 113 F NI2 .IOE+06 cps NI4 .97E+02 % NIB :TOE+03  % Charging Line Temperature JM F NI-05 IOO  % Nl-09 Letdown Line Temp ffi F Nl-06 98""  % Nl-10 SOCS from PCS {R) 83 F SOCS to PCS (R) BJ F PIP (DEMAND LOG+CONSTANT~OD, OR FLUX/TEMP) Gross MW 817 Net MW 7T5 (28) Control Rod PositTOrl GPI 131GP2 131 GP3 131 GP4 131 GP6(A) 11IGP7(B) l1I Stuck R'OcfS NONE <optional># O Core Exit Temp ~83.IF

SHAVPALl Time 0845 TSC Scenario Time 0015 S T AT US P AG E Message # ~ 140 PALEX 92 Time Jump - - Scenario Time Jump - - C-13 C-12 PCP Curre~Amps) Condensate Storage Tank Level T-2 80 % P-50A 575 P-50B 592 Instrument Air Pressure 1152 psig P-50C m P-50D ID (15) Containment Building Pressure er- psig (6) PCS Flow (16) S/G A Compartment Temperature ~2 F (3) Thot (F) Loop 1 582 F S/G A COMPARTMENT Humidity 'Sil  % Loop 2 w F (16) S/G B Compartment Temperature 'Bil F (2) Tcold (F) Loop IA m F S/G B Humidity '5iJ  % Loop 2A m F (16) Dome Temperature BS F Loop IB m F (11) SIRW Tank Level M  % Loop 2B m F (15) WR Containment Pressure (R) 14 psi a (5) Subcooling -"58 F 716 PSIA (14) Containment Sump Level 0  % (7) PCS WR Pressure (R) '2061 PSIA (14) Containment Water Level (R) 0 3 (7) PCS NR Pressure (R) bOO PSIA (22) SI Tank Level (%) (30) S/G A LEVEL WR 6s- % A 52 B 48 c 48 D 48 (30) S/G A LEVEL (R) b5 %

     .SI Tan'KPressure(psig)                                       (30) S/G A PRESS             790 psi a A 233      B 228      c 230        D 234                      S/G A STM FLW (R)       n XI0**6    PPH (21) SIAS Al arm                        NO                               S/G A FD FLW (R)        n Xl0**6    PPH (30) S/G B LEVEL WR          6s- %

C-12 (30) S/G B LEVEL (R) b5 %* (30) S/G B PRESS 790 psia

    *Concentrated Boric Acid Tank Levels                                S/G B STM FLW (R)      n Xl0**6     PPH T53A                       97.5     %                        S/G B FD FLW (R)       n Xl0**6     PPH T53B                       95'":2   %

Reactor Vessel DP 20,1 psid PANEL K-13 (12) PORV Discharge Temperature SS-- F (13) Pzr Safety Valve Discharge Temj:)(F) (20) CONTAINMENT HIGH PRESS RV-1039 88 F NO RV-1040 'SS F RV-1041 BS F (20) Containment High Radiation NO

SHAVPALl PALEX 92 TSC

• S T AT US P AGE
• Time 0845 Scenario Time 0015. Message # ~ 141 Time Jump - - Scenario Time Jump - -

C-01 C-04 MFP Suction Pressure 335 psig (32) D/G Freq 1-1 0 1-2 0 MFP A Discharge Pressure 1004 psig (32) 1-C BUS VOLTS 2484 Amps285 MFP B Discharge Pressure T004 psig (32) 1-D BUS VOLTS 248I Amps455 AFW Pump P-8C Amperes 0---- AMPS AFW Discharge Pressure P-8C To psig C-11 BACK C-llA AFW Pump P-8A Amperes .0 AMPS AFW Pump P-8B Steam Pressure TI psig (17) Containment Area Monitors

~FW Discharge Pressure P-8A & P-8B            To      psig                RIA-1805          .020        R/Hr Moisture SEP Drain Tank Level                 64 %                        RIA-1806         -:-oI9       R/Hr Condensor Hotwell Level                       Ol %                        RIA-1807         :T20         R/Hr Condensor Vacuum                            , 27.5 in Hg.                 RIA-1808         -:0S0        R/Hr Gland Seal Condensor Vacuum                   T4.2 in Hg.           (17) High Range Conta1Jlilient Monitors Atmospheric Dump Valves                       IT'USED                     RIA-2321         1            R/Hr AFW Pump       P-8A OFF    P-8B  OFF    P-8C  OFF                         RIA-2322         I            R/Hr Heater Drain Pump-        P-lOA Ofr P-108 mf"                       (19) Containment Hydrogen Concentration Conden~ate Pump            P-2A OR      P-2B OR                           AI-2401R         0          %

AI-2401L 0  % C-11 (30) Main Steam Line ~amma RIA-2324 23 CPM

'(31) AFW FLOW TO SGA                                                      RIA-2323        25         CPM FROM P8A, B 0               From P-8C O      gpm (31) AFW FLOW TO ~GB                                               EQUIPMENT STATUS:

FROM P-8A&B 0 From P-8C 0 gpm Condensor Vacuum (R) 28 IN HG. 1. SIGNIFICANT EQUIP OUTAGES PCP A Leak-off Flow (R) r.1 (INOPERABLE EQUIPMENT) PCP B Leak-off Flow (R) r.T 2. SURVEILLANCE DUE/PROGRESS PCP C Leak-off Flow {R} r.T 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off Flow (R) r.T OR OUTAGES

SHAVPALI PALEX 92 TSC

• S T AT US P AGE
• Time 0845 Scenario Time 0015 Message # ~ 142

 *Time Jump -                Scenario Time Jump -

C-08 C-02 SW Pumps P-7A ON P-78 STBY P-7C ON (10) VCT Temp 106 F CCW Pumps P-52A 'STBY P-528 ~ P-52C 'STBY (10) VCT Pressure 2b psi FPC Pumps P-51A ~ P-518 OFF (10) VCT Level 65 % PCP Control Bleedoff Pressure lf psig CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow !5 gpm (26) Charging Flow 44 gpm VIA ON V2A ON V3A ON V4A ON (9) Quench Tank Temp 102 F VIB OR V2B UR V3B UR V4B UR (9) Quench TANK Pressure T psig (9) Quench TANK Level b3 % C-03 (7) Pressurizer Pressure (R) 2061 psia

                                              '                   (8) PZR Level (R)       LT0102A         44%

(23) HPSI Pumps P-66A OFF P-668 OFF LT0103 44.1 %

. (25) LPSI Pumps         P-67A ITT P-678 OFT                    (12) PORV     PRV-1042A CLOSED 10438 CLOSED
 *( 18) Containment Spray Pumps                                  (12) BLOCK MOV-1042A CLOSED 1043A CLOSED P-54A OFF P-548 OFF P-54C OFF                          CHARGING PUMPS (27) HPSIA, LPSIA~PRAY A SUCTION                                             P55A ON P55B OFF P55C OFF CV-3057 (SIRWT)        CV-3030 (Sump)            (6) PCPS     P50A OR P50B cm- P50C cm- P50D ON OPEN                  CLOSED                       PZR HTR AMPS ---LC15 141--- LCC 16 *141 (1) PCS TAVE (R) LOOPl"""{TR-0111) "5"59 F LOOP2 (TR-0121) !59 F C-02                                     (25) REACTOR POWER LEVEL Nil .10E+06 cps NI3 .97E+02 % NI7 98              %

Intermediate Press Letdown Temp 113 F NI2 .lOE+06 cps NI4 .97E+02 % NIB :TOE+03  % Charging Line Temperature !Bil F NI-05 lOO  % Nl-09 Letdown Line Temp 25I F Nl-06 98  % Nl-10 SOCS from PCS (R) M"" F SOCS to PCS (R) 'Bl F PIP (DEMAND LOG+CONSTANT-;--ROD, OR FLUX/TEMP) Gross MW 817 Net MW 775 (28) Control Rod PositlOii GPl 131GP2 131 GP3 131 GP4 131 GP6(A) I!IGP7(B) I!I Stuck Rods 'RUNE <optional># 0 Core Exit Temp ~83.lF

SHAVPALl TSC

• S T AT US P AGE
• PALEX 92 Time 0900 Scenario Time 0030 Message # ~ 140 Time Jump - - Scenario Time Jump - -

C-13 C-12 PCP Curreilf"1Amps) Condensate Storage Tank Level T-2 80 % P-50A 575 P-508 592* Instrument Air Pressure 1TI2 psig P-50C -m P-50D ID (15) Containment Building Pressure ~ psig (6) PCS Flow (16) S/G A Compartment Temperature ~2 F (3) Thot (F) Loop 1 582 F S/G A COMPARTMENT Humidity '51  % Loop 2 w F (16) S/G B Compartment Temperature Bil F (2) Tcold (F) Loop IA m F S/G B Humidity '51  % Loop 2A m F (16) Dome Temperature ~ F Loop 18 m F .(II) SIRW Tank Level 92  % Loop 28 m F (15) WR Containment Pressure {R) T'l psia (5) Subcooling ~ F 716 PSIA (14) Containment Sump Level 0-  % (7) PCS WR Pressure (R} 2061 PSIA (14) Containment Water Level {R) O  % (7) PCS NR Pressure (R) 600 PSIA (22) SI Tank Level (%) - (30) S/G A LEVEL WR w % A 52 B 48 C 48 D 48 (30) S/G A LEVEL {R) 65 % SI Tan~Pressure---Cpsig) (30) S/G A PRESS 790 ps*i a A 233 B 228 C 230 D 234 S/G A STM FLW (R) n Xl0**6 PPH (21) SIAS Alarm - NO S/G A FD FLW {R) n Xl0**6 PPH (30) S/G B LEVEL WR . w % C-12 (30) S/G B LEVEL (R) 65 %* (30) S/G B PRESS 790 psi a Concentrated Boric Acid Tank Levels S/G B STM FLW {R) n Xl0**6 PPH T53A 97.5  % *s/G B FD FLW (R) n X10**6 PPH T53B ~  % Reactor Vessel DP 20:1 psid PANEL K-13 (12) PORV Discharge Temperature ~ F (13) Pzr Safety Valve Discharge Temj)"(F) (20) CONTAINMENT HIGH PRESS RV-1039 88 F NO RV-1040 'S'S F RV-1041 ~ F (20) Containment High Radiation NO

SHAVPALI PALEX 92

                                              .TSC

• S T AT US P AGE
• Time 0900 Scenario Time 0030 Message # .1 141 Time Jump - - Scenario Time Jump - -

C-01 C-04 MFP Suction Pressure 335 psig (32) D/G Freq 1-1 0 1-2 0 MFP A Discharge Pressure T004 psig (32) 1-C BUS VOLTS 2484 Amps285 MFP B Discharge Pressure 1004 psig (32) 1-D BUS VOLTS 248f Amps455

.AFW Pump P-8C Amperes                           0- AMPS AFW Discharge Pressure P-8C                     To     psig                       C-11 BACK C-llA AFW Pump P-8A Amperes                         . O AMPS AFW Pump P-8B Steam Pressure                    o psig               (17) Containment Area Monitors AFW Dfscharge Pressure P-8A & P-8B             To     psig                 RIA-1805         .020       R/Hr Moisture SEP Drain Tank Level                  64 %                        RIA-1806        :or9        R/Hr Condenser Hotwell Level                        63 %                        RlA-1807        -:120       R/Hr Condenser Vacuum                            . 27. 5 in Hg.                 RIA-1808        :0S0        R/Hr Gland Seal Condenser Vacuum                    T4.2 in Hg.          (17) High Range Contaliiiiient Monitors Atmospheric Dump Valves                        UoS"ED                      RIA-2321        1           R/Hr AFW Pump       P-8A OFF     P-8B OFF     P-8C OFF                          RIA-2322        I           R/Hr Heater Drain Pump-         P-lOA OW P-IOB OW                        (19) Containment Hydrogen Concentration Conden,sate Pump            P-2A UR      P-28 OR                           AI-2401R        0         %

AI-2401L 0  % C-11 (30) Main Steam Line ~amma RIA-2324 23 CPM (31) AFW FLOW TO SGA RIA-2323 25 CPM FROM P8A, B 0 From P-8C O gpm (31) AFW FLOW TO SGB EQUIPMENT STATUS:

 '       FROM P-8A&B 0                From P-8C 0     gpm Condenser Vacuum (R)                    '2'8 IN HG.          1. SIGNIFICANT EQUIP OUTAGES PCP A Leak-off Flow (R)                 r.1                       (INOPERABLE EQUIPMENT)

PCP B Leak-off Flow (R) r.T 2. SURVEILLANCE DUE/PROGRESS PCP C Leak-off Flow (R) r.T 3. ABNORMAL ELECTRICAL LINEUPS

• PCP D Leak-off Fl ow (R) r.T OR OUTAGES

SHAVPALI PALEX 92 TSC

• S T AT US P AG E
• Time 0900 Scenario Time 0030 Message # .1 142 Time *-Jump - Scenario Time Jump -

C-08 C-02 SW Pumps P-7A ON P-78 STBY P-7C ON (10) VCT Temp 106 F CCW Pumps P-52A nBY P-528 00--- P-52C nBY (10) VCT Pressure ~ psi FPC Pumps P-51A 00--- P-518 OFF (10) VCT Level 60 % PCP Control Bleedoff Pressure 4I psig CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow !5 gpm (26) Charging Flow 44 gpm VIA ON V2A ON V3A ON V4A ON (9) Quench Tank Temp 102 F VIB TIN V2B UN V3B UN V4B UN (9) Quench TANK Pressure  :-Y- psig (9) Quench TANK Level bl % C-03 (7) Pressurizer Pressure (R) 2061 psia (8) PZR Level (R) LT0102A ~ % (23) HPSI Pumps P-66A OFF P-668 OFF LT0103 44.1 % (25) LPSI Pumps P-67A OfT P-678 OFf (12) PORV PRV-1042A CLOSED 10438 troSED

 * (18) Containment Spray Pumps-                                   (12) BLOCK MOV-1042A CLOSED 1043A CLOSED P-54A OFF P-548 OFF P-54C OFF                           CHARGING PUMPS (27) HPSIA, LPSIA~PRAY A SUCTION                                                P55A ON P55B OFF P55C OFF CV-3057 (SIRWT)        CV-3030 (Sump)            (6) PCPS       PSOA UN PSOB Off" PSOC Off" PSOD ON OPEN                  CLOSED                        PZR HTR AMPS ---LC15 141--- LCC 16.141 (1) PCS TAVE (R) LOOPI"lTR-0111} '5"59 F LOOP2 (TR-0121) '5"59 F C-02                                     (25) REACTOR POWER LEVEL Nil .IOE+06 cps Nl3 .97E+02 % Nl7 98               %

Intermediate Press Letdown Temp 113 F Nl2 .lOE+06 cps Nl4 .97E+02 % NIB :TOE+03  % Charging Line Temperature m F Nl-05 lOO  % Nl-09 letdown line Temp IB F Nl-06 98""  % Nl-10 SOCS from PCS (R) 'Sr F SOCS to PCS (R) nl F PIP (DEMAND LOG+CONSTANT~OD, OR FLUX/TEMP) Gross MW 817 Net MW 775 (28) Control Rod PositTOii GPI 131GP2 131 GP3 131 . GP4 131 GP6(A) l!IGP7(B) TlI Stuck Rods NONE <optional># 0 Core Exit Temp ~83.lF

SHAVPALI Time 0915 T S C S T AT US Scenario Time 0045 P AGE

• PALEX 92 Message # .§. 140 Time Jump Scenario Time Jump - -

C-13 C-12 PCP Currenr-{Amps) Condensate Storage Tank Level T-2 80 % P-50A 575 P-50B 592 Instrument Air Pressure 102 psig P-50C ~ P-50D rJl7 (15) Containment Building Pressure O psig (6) PCS Flow (16) S/G A Compartment Temperature ~2 F (3) Thot (F) Loop 1 582 F S/G A COMPARTMENT Humidity "54 % Loop 2 W F (16) S/G B Compartment Temperature Bil F (2) Tcold (F) Loop IA m F S/G B Hurni di ty "54 % Loop 2A m F '(16) Dome Temperature BS F Loop lB m F (11) SIRW Tank Level ~  % Loop 28 m F '(15) WR Containment Pressure (R) 14 psia (5) Subcooling ~ F 715 PSIA (14) Containment Sump Level 10  % (7) PCS WR Pressure (R) 2061 PSIA (14) Containment Water Level (R) 0-  % (7) PCS NR Pressure (R) 600 PSIA (2Z) SI Tank Level (%) - (30) S/G A LEVEL WR W% A 52 B 48 C 48 D 48 (30) S/G A LEVEL (R) 65 % SI Tan~Pressure~psig) (30) S/G A PRESS 790 psia A 233 B 228 C 230 D 234 S/G A STM FLW (R) '5":"5 Xl0**6 PPH (21) SIAS Alarm - NO S/G A FD FLW (R) '5'":""5 Xl0**6 PPH (30) S/G B LEVEL WR W% C-12 (30) S/G B LEVEL (R) 65 %* (30) S/G B PRESS 790 psia Concentrated Boric Acid Tank Levels S/G B STM FLW (R) '5'":""5 Xl0**6 PPH T53A 97.5  % S/G B FD FLW (R) '5'":""5 Xl0**6 PPH T53B ~  % Reactor Vessel DP 20':'1 psid PANEL K-13 (12) PORV Discharge Temperature SS-- F (13) Pzr Safety Valve Discharge TemP-(F) (20) CONTAINMENT HIGH PRESS RV-1039 88 F NO RV-1040 BS F RV-1041 BS F (20) Containment High Radiation NO

SHAVPALI PALEX 92 TSC

• S T AT US P AGE
• Time 0915 Scenario Time 0045 Message # ~ 141 Time Jump - - Scenario Time Jump - -

C-01 C-04 MFP Suction Pressure 334 psig (32) D/G Freq 1-1 0 1-2 0 MFP A Discharge Pressure T004 psig (32) 1-C BUS VOLTS 2484 Amps285 MFP B Discharge Pressure T004 psig (32) 1-D BUS VOLTS 248T Ampsif55 AFW Pump P-8C Amperes 0--- AMPS AFW Discharge Pressure P-8C Io psig C-11 BACK C-llA 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 Io psig RIA-1805 .020 R/Hr Moisture SEP Drain Tank Level b4 % RIA-1806 -:o19 R/Hr C~ndensor Hotwell Level 6l % RIA-1807 :120 R/Hr Condenser Vacuum . 27. 5 in Hg. RIA-1808 :0S0 R/Hr Gland Seal Condenser Vacuum lU in Hg. (17) High Range ContaTnilient Monitors Atmospheric Dump Valves IT'O'SED RIA-2321 1 R/Hr AFW Pump P-8A OFF P-88 OFF P-8C OFF RIA-2322 I R/Hr Heater Drain Pump- P-lOA 'Off" P-lOB 'ITfr (19) Containment Hydrogen Concentration Condensate Pump P-2A OR P-2B OR AI-2401R 0  % AI-2401L 0  % C-11 (30) Main Steam Line ~amma RIA-2324 23 CPM (31) AFW FLOW TO SGA RIA-2323 25 CPM FROM P8A, B 0 From P-8C 0 gpm (31) AFW FLOW TO ~GB EQUIPMENT STATUS: FROM P-8A&B 0 From P-8C 0 gpm Condenser Vacuum (R) 27 IN HG. 1. SIGNIFICANT EQUIP OUTAGES PCP A Leak-off Flow (R) r.1 (INOPERABLE EQUIPMENT) PCP B Leak-off 'Flow (R) CT 2. SURVEILLANCE DUE/PROGRESS PCP C Leak-off Flow (R) CT 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off Flow (R) CT OR OUTAGES

SHAVPALI PALEX 92 TSC

• S T AT US P AGE
• Time 0915 Scenario Time 0045 Message # ~ 142 Time Jump- Scenario Time Jump -

C-08 C-02 SW Pumps P-7A ON P-78 STBY P-7C ON (10) VCT Temp 107 F CCW Pumps P-52A 'STBV P-528 UW-- P-52C 'ST8V (10) VCT Pressure lo- psi FPC Pumps P-51A rrrr- P-518 Of'F (10) VCT Level 'SO % PCP Control 8leedoff Pressure 4I psig CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow !5 gpm (26) Charging Flow 44 gpm VIA ON V2A ON V3A ON V4A ON (9) Quench Tank Temp 102 F VIB OR V2B UR V3B OR V48 OR (9) Quench TANK Pressure :i- psig (9) Quench TANK Level b3 % C-03 (7) Pressurizer Pr~ssure (R) 2061 psia (8) PZR Level (R) LT0102A ~ % (23) HPSI Pumps P-66A OFF P-668 OFF LT0103 44 .1 %

 * (25)- LPSI Pumps         P-67A ITT P-678 ITT                    (12) PORV     PRV-1042A CLOSED 10438 CIOSED
 '(18) Containment Spray Pumps-                                    (12) BLOCK MOV-1042A CLOSED 1043A CLOSED P-54A OFF P-548 OFF P-54C OFF                            CHARGING PUMPS (27) HPSIA, LPSIA-;--sPRAY A SUCTION                                          P55A ON P55B OFF P55C OFF CV-3057 (SIRWT)          CV-3030 (Sump)            (6) PCPS     P50A OR P50B Off" P50C Off" P50D ON OPEN                     CLOSED                       PZR HTR AMPS ---LC15 141--- LCC 16*141 (1) PCS TAVE (R) LOOPI-rlR-0111) '5'59 F LOOP2 (TR-0121) '5"59 F C-02                                     (25) REACTOR POWER LEVEL Nil .IOE+06 cps NI3 .97E+02 % NI7 98               %

Intermediate Press letdown Temp 113 F NI2 .10E+06 cps NI4 .97E+02 % NIB :TOE+03  % Charging Line Temperature !Bil F Nl-05 99  % Nl-09 Letdown Line Temp ID F Nl-06 9B'  % Nl-10 SDCS from PCS (R) nJ F SDCS to PCS (R) n3" F PIP (DEMAND LOG+CONSTANT-;-"ROD, OR FLUX/TEMP) Gross MW 817 Net MW 7T6, (28) Control Rod PositlOii GPI 131GP2 131 GP3 131 GP4 131 GP6(A) 1JIGP7(8) l1I Stuck Rods NONE <optional># 0 Core Exit Temp ~83.2F

SHAVPALI Time 0930 TSC Scenario Time 0100 S T AT US P AG E Message # I 140 PALEX 92 Time Jump - - Scenario Time Jump - - C-13 C-12 PCP Curreilf"1Amps) Condensate Storage Tank Level T-2 BO % P-50A *575 P-508 592 Instrument Air Pressure TOO psig P-50C "599 P-500 !77 (15) Containment Building Pressure 0-- psig (6) PCS Flow (16) S/G A Compartment Temperature g2 F (3) Thot. (F) Loop 1 582 F S/G A COMPARTMENT Humidity '54  % Loop 2 ill F (16) S/G B Compartment Temperature 84 F (2) Tcold (F) Loop IA ill F S/G B Humidity '54 gs

                                             %                                       Loop 2A     m F (16) Dome Temperature                         F                                       Loop 18     m F (11) SIRW Tank Level                  92      %                                       Loop 28     m F (15) WR Containment Pressure (R)      14      psi a                   (5) Subcooling              "5"a- F 715   PSIA (14} Containment Sump Level           IO      %                       (7) PCS WR Pressure (R) °2061 PSIA (14) Containment Water Level (R}      0
                                     -       3                       (7) PCS NR Pressure (R) 600 PSIA (22} SI Tank Level (%)                                               (30) S/G A LEVEL WR          °6"b"%

A 52 B 4B c 4B D 4B (30) S/G A LEVEL (R} ~  % SI Tan~Pressure-""Tpsig} (30} S/G A PRESS 790 psia A 233 B 228 c 230 D 234 S/G A STM FLW (R} "S:"5 Xl0**6 PPH (21} SIAS Alarm NO S/G A FD FLW (R) D Xl0**6 PPH (30) S/G B LEVEL WR bs- % C-12 (30) S/G B LEVEL (R) ~  %* (30) S/G B PRESS 790 psia Concentrated Boric Acid Tank Levels S/G B STM FLW (R} "S:"5 Xl0**6 PPH T53A 97 .5  % S/G B FD FLW (R} D Xl0**6 PPH T53B '9'5:2 3 Reactor Vessel DP 21f.2 psid

• PANEL K-13 (12) PORV Discharge Temperature gs-- F (13) Pzr Safety Valve Discharge Temj)"(F) (20) CONTAINMENT HIGH PRESS RV-1039 BB F NO RV-1040 gg F RV-1041 gg F (20) Containment High Radiation NO

SHAVPALI PALEX 92 TSC

• S T A T US P AGE
• Time 0930 Scenario Time 0100 Message # J_ 141 Time Jump - - Scenario Time Jump - -

C-01 C-04 MFP Suction Pressure 334 psig (32) D/G Freq 1-1 0 1-2 0 MFP A Discharge Pressure 1004 psig (32) 1-C BUS VOLTS 2484 Amps285 MFP B Discharge Pressure TOCM psig (32) 1-D BUS VOLTS 248T AmpsifS'S AFW Pump P-8C Amperes 0- AMPS AFW Discharge Pressure P-8C . To psig C-11 BACK C-llA AFW Pump P-8A Amperes 0 AMPS AFW Pump P-8B Steam Pressure O psig (17) Containment Area Monitors AFW Discharge Pressure P-8A & P-8B To psig . RIA-1805 .020 R/Hr Moisture SEP Drain Tank Level 64  % RIA-1806 ~ R/Hr Condensor Hotwell Level 6l % RIA-1807 -:120 R/Hr Condensor Vacuum

• 27. 5 in Hg. RIA-1808 :0S0 R/Hr Gland Seal Condensor Vacuum ~- in Hg. (17) High Range Conta"'liliii'ent Monitors Atmospheric Dump Valves ~ED RIA-2321 1 R/Hr AFW Pump P-8A OFF P-8B OFF P-8C OFF RIA-2322 T R/Hr Heater Drain Pump- P-lOA Off" P-lOB Off" (19) Containment Hydrogen Concentration Condensate Pump P-2A OR P-2B OR AI-2401R 0  %

Al-2401L 0  % C-11 (30) Main Steam Line Gamma RIA-2324 23 CPM (31) AFW FLOW TO SGA RIA-2323 25 CPM FROM P8A, B 0 From P-8C 0 gpm (31) AFW FLOW TO ~GB EQUIPMENT STATUS: FROM P-BA&B 0 From P-8C 0 gpm Condensor Vacuum (R) "'l..7 IN HG. 1. SIGNIFICANT EQUIP OUTAGES PCP A Leak-off Flow (R) r.1 (INOPERABLE EQUIPMENT) PCP B Leak-off Flow (R) CT 2. SURVEILLANCE DUE/PROGRESS PCP C Leak-off Flow (R) CT 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off Flow (R) CT OR OUTAGES

SHAVPALI PALEX 92 TSC

• S T AT US P AGE
• Time 0930 Scenario Time 0100 Message # I 142

  *Time Jump -                 Scenario Time Jump -

C-08 C-02 SW Pumps P-7A ON P-78 ST8Y P-7C ON (10) VCT Temp 107 F CCW Pumps P-52A ST8V P-528 on-- P-52C 'Sl8Y (10) VCT Pressure lo- psi FPC Pumps P-51A OW-- P-518 Of'F (10) VCT Level ~  % PCP Control 8leedoff Pressure 4I psig CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow !S gpm (26) Charging Flow 44 gpm VIA ON V2A ON V3A ON V4A ON (9) Quench Tank Temp 102 F Vl8 UR V28 UR V38 OR V48 UR (9) Quench TANK Pressure -:-Y- psig (9) Quench TANK Level bl % C-03 (7) Pressurizer Pressure (R) 2061 psia

                                                 '                  (8) PZR level (R)       LT0102A          ~ %

(23) HPSI Pumps P-66A OFF P-668 OFF l TO 103 44. 1 % (25) LPSI Pumps P-67A 0Ft P-678 UFt (12) PORV PRV-1042A CLOSED 10438 'CIOSEO (18) Containment Spray Pumps- (12) BLOCK MOV-1042A CLOSED 1043A CLOSED

        .      P-54A OFF P-548 OFF P-54C OFF                             CHARGING PUMPS (27) HPSIA, LPSIA-;-""S'PRAY A SUCTION                                          P55A ON P55B OFF P55C OFF
   .             CV-3057 (SIRWT)          CV-3030 (Sump)            (6) PCPS      P50A OR P50B OW- P50C 'On- P500 ON OPEN                    CLOSED                        PZR HTR AMPS ~LC15 141~ LCC 16*141 (1) PCS TAVE (R) LOOPI--rTR-0111) !59 F LOOP2 (TR-0121) 'S'S9 F C-02                                     (25) REACTOR POWER LEVEL Nil .IOE+06 cps NI3 .97E+02 % NI7 98                %

Intermediate Press Letdown Temp 113 F NI2 .IOE+06 cps NI4 .97E+02 % NIB :TOE+03  % Charging Line Temperature l8il F Nl-05 loo  % NI-09 Letdown Line Temp '2M F Nl-06 98  % Nl-10 SOCS from PCS (R) IJr F

 .SOCS to PCS (R)                              'Sl   F                                    PIP (DEMAND LOG+CONSTANT~OO, OR FLUX/TEMP)

Gross MW 817

• Net MW 775 (28) Control Rod PositTOrl GPI 131GP2 131 GP3 131 GP4 131 GP6(A) T!IGP7(B) T!I Stuck Rods NORE <optional># 0 Core Exit Temp ~83.2F

SHAVPAU T SC

• S T AT U S P AGE
• PALEX 92 Time 0945 Scenario Time 0115 Message # !! 140 Time Jump - - Scenario Time Jump - -

C-13 C-12 PCP Curreiif:1Amps) Condensate Storage Tank level T-2 79 % P-50A 575 P-50B 592 Instrument Air Pressure 102 psig P-50C m P-50D.ID (15) Containment Building Pressure ~ psig (6) PCS Flow (16) S/G A Compartment Temperature ~2 F (3) Thot (F) loop_ I 582 F S/G A COMPARTMENT Humidity '54  % Loop 2 w F (16) S/G B Compartment Temperature ~ F (2) Tcold (F) *Loop IA m F S/G B Humidity '54  % loop 2A m F (16) Dome Temperature ~ F Loop IB m F (11) SIRW Tank Level ~  % loop 2B m F (15) WR Containment *Pressure {R) n psia (5) Subcooling w- F 715 PSIA (14) Containment Sump Level TO  % (7) PCS WR Pressure (R) 2061 PSIA (14) Containment Water Level (R} 0-- ~ (7) PCS NR Pressure (R) 600 PSIA (22) SI Tank Level (%) - (30) S/G A LEVEL WR w % A 52 B 48 C 48 D 48 (30) S/G A LEVEL (R) b5 % SI Tan"K"Pressure----C-psig) (30) S/G A PRESS No psi a A 233 B 228 C 230 D 234 S/G A STM FLW (R) n Xl0**6 PPH . (21 ) SI AS Al arm NO S/G A FD FLW (R) n Xl0**6 PPH (30) S/G B LEVEL WR ~ % C-12 (30) S/G B LEVEL (R) b5 %' (30) S/G B PRESS No psi a Concentrated Boric Acid Tank Levels S/G B STM FLW (R) n Xl0**6 PPH T53A 97 .5  % S/G B FD FLW (R) n Xl0**6 PPH T53B ~  % Reactor Vessel DP '20:1 psid PANEL K-13 (12) .PORV Discharge Temperature ~ F (13) Pzr Safety Valve Discharge TemP-(F) (20) CONTAINMENT HIGH PRESS RV-1039 88 F NO RV-1040 ng F RV-1041 ng F (20) Containment High Radiation NO

SHAVPALI PALEX 92 T S C S T AT US P AGE

• Time 0945 Scenario Time 0115 Message # !! 141

*Time Jump - -          Scenario Time Jump - -

C-01 C-04 MFP Suction Pressure 334 psig (32) D/G Freq 1-1 0 1-2 0 MFP A Discharge Pressure 1005 psig (32) 1-C BUS VOLTS 2484 Amps285 MFP B Discharge Pressure T005 psig (32) 1-D BUS VOLTS 248T Amps45'5 AFW Pump P-8C Amperes er- AMPS AFW Discharge Pressure P-8C . To psig C-11 BACK C-llA AFW Pump P-8A Amperes 0 AMPS AFW .Pump P-8B Steam Pressure o psig (17) Containment Area Monitors AFW Discharge Pressure P-8A & P-8B To psig RIA-1805 .020 R/Hr Moisture SEP Drain Tank Level 64 % RIA-1806 :oJg R/Hr Condensor Hotwell Level b2 % RIA-1807 :r20 R/Hr tondensor Vacuum . 27. 5 in Hg. RIA-1808 :0S0 R/Hr Gland Seal Condensor Vacuum ~ in Hg. (17) High Range ContaTniiient Monitors Atmospheric Dump Valves ~ED RIA-2321 1 R/Hr AFW Pump P-8A OFF P-8B OFF P-8C OFF RIA-2322 T R/Hr Heater Drain Pump- P-lOA 01f" P-lOB 01f" (19) Containment Hydrogen Concentration Condensate Pump P-2A OR P-2B OR AI-2401R 0  % Al-2401L 0  % C-11 (30) Main Steam Line ~amma RIA-2324 23 CPM (31) AFW FLOW TO SGA RIA-2323 2'5 CPM FROM P8A, B 0 From P-8C 0 gpm (31) AFW FLOW TO ~GB EQUIPMENT STATUS: FROM P-8A&B 0 From P-8C 0 gpm Condensor Vacuum (R) 27 IN HG. 1. SIGNIFICANT EQUIP OUTAGES PCP A Leak-off Flow (R) r.1 (INOPERABLE EQUIPMENT) PCP B Leak-off Flow (R) r.r 2. SURVEILLANCE DUE/PROGRESS PCP C Leak-off Flow (R) r.r 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off Flow (R) r.r OR OUTAGES

SHAVPALl PALEX 92 TSC

• S T AT US P AGE
• Time 0945 Scenario Time 0115 Message # !! 142

  'Time Jump -              Scenario Time Jump -

C-08 C-02 SW Pumps P-7A ON P-78 ST8V P-7C ON (10) VCT Temp 108 F CCW Pumps P-52A 'ST8V P-528 ~ P-52C 'ST8V (10) VCT Pressure ~ psi FPC.Pumps P-51A ~ P-518 MF (10) VCT Level b'b % PCP Control 8leedoff Pressure 4I psig CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow !S gpm (26) Charging Flow 44 gpm VIA ON V2A ON V3A ON V4A ON (9) Quench Tank Temp 102 F Vl8 OR V28 UN V38 OR V48 UN (9) Quench TANK Pressure ':'I""" psig (9) Quench TANK Level 6l % C-03 (7) Pressurizer Pressure (R) 2061 psia (8) PZR Level (R) l T0102A ~ % (23) HPSI Pumps P-66A OFF P-668 OFF LT0103 44.1 % (25) LPSI Pumps P-67A OFF' P-678 orF' (12) PORV PRV-1042A CLOSED 10438 ctoS'ED (18) .Containment Spray Pumps- (12) BLOCK MOV-1042A CLOSED 1043A CLOSED P-54A OFF P-548 OFF P-54C OFF CHARGING PUMPS (27) HPSIA, LPSIA:-SPRAV A SUCTION P55A ON P55B OFF P55C OF.F

  .             CV-3057 (SIRWT)        CV-3030 (Sump)            (6) PCPS      P50A OR P508 orr- P50C Tin- P50D ON OPEN                   CLOSED                       PZR HTR AMPS --LC15 141-- LCC 16.Till (1) PCS TAVE (R) LOOPI-rTR-0111) '5'59 F LOOP2 (TR-0121) 559 F C-02                                     (25) REACTOR POWER LEVEL Nil .IOE+06 cps NI3 .97E+02 % NI7 98                  %

Intermediate Press letdown Temp 113 F NI2 .IOE+06 cps NI4 .97E+02 % NIB :TOE+03  % Charging Line Temperature m F NI-05 too  % Nl-09 Letdown Line Temp ill F Nl-06 '9"8"  % NI-10 SOCS from PCS (R) nJ" F SOCS to PCS (R) 'Sl F PIP (DEMAND LOG+CONSTANT-;-°'ROD, OR FLUX/TEMP) Gross MW 817 Net MW 77S (28) Control Rod PositTOrl GPI 131GP2 131 GP3 131 GP4 131 GP6(A) l!IGP7(8) l!I Stuck Rods NORE <optional># O Core Exit Temp ~83.2F

SHAVPALl

• T S C S T AT US P AG E
• PALEX 92 Time 1000 Scenario Time 0130 Message # 2 140 Time Jump - - Scenario Time Jump - -

C-13 C-12 PCP Curre~Amps) Condensate Storage Tank Level T-2 79  % P-50A 575 P-50B 592 Instrument Air Pressure 105 psig P-50C '599 P-500 "577 (15) Containment Building Pressure ~ psig (6) PCS Flow - (16) S/G A Compartment Temperature ~2 F (3) That (F) Loop 1 582 F S/G A COMPARTMENT Humidity '5lT  % Loop 2 W F (16) S/G B Compartment Temperature 84 F (2) Tcold (F) Loop IA ill F S/G B Humidity '5lT  % Loop 2A ill F (16) Dome Temperature ~ F Loop IB ill F

.(11) SIRW Tank Level                    92        %                            .         Loop 2B     ill F (15) WR Containment Pressure (R) 14               psi a                   (5) Subcooling             'SB""" F 715   PSIA (14} Containment Sump Level             TO        %                       (7) PCS WR Pressure (R) 2061 PSIA (14) Containment Water Level (R) 0               ,3                       (7) PCS NR Pressure (R) bOO PSIA (22) SI Tank Level (%)                                                   (30) S/G A LEVEL WR         w %

A 52 B 48 c 48 D 48 (30) S/G A LEVEL (R) 65 % SI Tan"l<"Pressure--'(psig) (30) S/G A PRESS 791 psia A 233 B 228 c 230 D 234 S/G A STM FLW (R) '5':-5 Xl0**6 PPH (21) ~IAS Alarm -NO S/G A FD FLW (R) '5':-5 Xl0**6 PPH (30) S/G B LEVEL WR W% C-12 (30) S/G B LEVEL (R) 65 %* (30) S/G B PRESS 791 psia Concentrated Boric Acid Tank Levels S/G B STM FLW (R) '5':-5 Xl0**6 PPH T53A 97.5  % S/G B FD FLW (R) '5':-5 Xl0**6 PPH T53B 95":""2'  % Reactor Vessel DP "20:2 psid PANEL K-13 (12) PORY Discharge Temperature SS-- F . ( 13) Pzr Safety Valve Discharge TemP-(F) (20) CONTAINMENT HIGH PRESS RV-1039 88 F NO RY-1040 ~ F RV-1041 ~ F (20) Containment High Radiation NO

SHAVPALI PALEX 92 TS C

• S T AT US P AGE
• Time 1000 Scenario Time 0130 Message # .2 141

*Time Jump - -           Scenario Time Jump - -

C-01 C-04 MFP Suction Pressure 334 psig (32) D/G Freq 1-1 0 1-2 0 MFP A Discharge Pressure 1005 psig (32) 1-C BUS VOLTS 2484 Amps285 MFP B Discharge Pressure TifOS psig (32) 1-D BUS VOLTS 2481' Amps455' AFW Pump P-8C Amperes 0-- AMPS AFW Discharge Pressure P-8C To psig C-11 BACK C-llA AFW Pump P-8A Amperes 0 AMPS AFW Pump P-88 Steam Pressure O psig (17) Containment Area Monitors AFW Discharge Pressure P-8A & P-88 To psig RIA-1805 .020 R/Hr Moisture SEP Drain Tank Level 6il 3 RIA-1806 :oT9 R/Hr Condensor Hotwell Level ~ 3 RIA-1807 :T20 R/Hr tondensor Vacuum . 27. 5 in Hg. RIA-1808 :0S0 R/Hr Gland Seal Condensor Vacuum T4.2 in Hg. (17) High Range Conta"'fil'ilient Monitors. Atmospheric Dump Valves ITOSED RIA-2321 1 R/Hr AFW Pump P-8A OFF P-88 OFF P-8C OFF RIA-2322 T R/Hr Heater Drain Pump- P-lOA Off" P-108 Off" (19) Containment Hydrogen Concentration Condensate Pump P-2A cm P-28 cm AI-2401R 0 3 Al-240ll O 3 C-11 (30) Main Steam Line Gamma RIA-2324 23 CPM (31) AFW FLOW TO SGA RIA-2323 25 CPM FROM P8A, B 0 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) 27 IN HG. 1. SIGNIFICANT EQUIP OUTAGES PCP A leak-off Flow (R) r.1 (INOPERABLE EQUIPMENT) PCP B leak-off Flow (R) TI 2. SURVEILLANCE DUE/PROGRESS PCP C Leak-off Flow (R) TI 3. ABNORMAL ELECTRICAL LINEUPS PCP D leak-off Flow (R) TI OR OUTAGES

SHAVPALI PALEX 92 TSC

• S T AT US P AGE
• Time 1000 Scenario Time 0130 Message # .2 142 Time Jump - Scenario Time Jump -

C-08 C-02 SW Pumps P-7A ON P-78 STBY P-7C ON (10) VCT Temp 108 F CCW Pumps P-52A 'STBY P-528 'On-- P-52C 'STBY (10) VCT Pressure 2b" psi FPC Pumps P-51A 'On-- P-518 OFF (10) VCT Level 6b % PCP Control Bleedoff Pressure

• 4T psig CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow JS gpm (26) Charging Flow 44 gpm VIA ON V2A ON V3A ON V4A ON (9) Quench Tank Temp 102 F VIB OR V2B OR V3B OR V4B OR (9) Quench TANK Pressure  :-Y- psig (9) Quench TANK Level b3' %

C-03 (7) Pressurizer Pressure (R) 2061 psia

                                             '                   (8) PZR Level (R)       LT0102A         ~ %

(23) HPSI Pumps P-66A OFF P-668 OFF LT0103 44.1 % (25) LPSI Pumps P-67A 0Fr P-678 OFF (12) PORV PRV-1042A CLOSED 10438 'CTO'SEO (18) Containment Spray Pumps- (12) BLOCK MOV-1042A CLOSED 1043A CLOSED P-54A OFF P-548 OFF P-54C OFF CHARGING PUMPS (27) HPSIA, LPSIA~PRAY A SUCTION P55A ON P55B OFF P55C OFF CV-3057 (SIRWT) CV-3030 (Sump) (6) PCPS P50A OR P50B TI'fr PSOC Off" P50D ON OPEN CLOSED PZR HTR AMPS ~LC15 141~ LCC 16*141 (1) PCS TAVE (R) LOOPI"liR-0111) 'S'59 F LOOP2 (TR-0121) ~ F C-02 (25) REACTOR POWER LEVEL Nil .IOE+06 cps NI3 .97E+02 % NI7 98  % Intermediate Press Letdown Temp 113 F NI2 .lOE+06 cps NI4 .97E+02 % NIB :TOE+03  % Charging Line Temperature !S1 F Nl-05 lOO  % Nl-09 Letdown Line Temp lli F Nl-06 ~  % Nl-10 SOCS from PCS (R) 'Sr F SOCS to PCS (R) 'Sl F PIP (DEMAND LOG+CONSTANT-;-llOD, OR FLUX/TEMP) Gross MW 817 Net MW 7T5 (28) Control Rod Positl'Ci'il GPI 131GP2 131 GP3 131 GP4 131 GP6(A) 11IGP7(B) l1I Stuck Rods NORE <optional># 0 Core Exit Temp - ~83.3F

SHAVPALI TSC

• S T AT US P AGE
• PALEX 92 Time 1002 Scenario Time 0132 Message # .!! 140 Time Jump - - Scenario Time Jump - -

C-13 C-12 PCP Curre~Amps) Condensate Storage Tank Level T-2 79 % P-50A 0 P-50B 0 Instrument Air Pressure TIH psig P-50C -0 P-50D 0 (15) Containment Building Pressure 0- psig (6) PCS Flow (16) S/G A Compartment Temperature ~2 F (3) Thot (F) Loop I 546 F S/G A COMPARTMENT Humidity ~  % Loop 2 m F (16) S/G B Compartment Temperature 84 F (2) Tcold (F) Loop IA m F S/G B Humidity ~  % Loop 2A m F (16) Dome Temperature fIB F Loop lB m F .(11) SIRW Tank Level '92  % Loop 2B m F (15) WR Containment Pressure (R) R psi a (5) Subcooling b9 F 709 PSIA (14) Containment Sump Level IO  % (7) PCS WR Pressure (R) 1716 PSIA (14) Containment Water Level (R) 0  % (7) PCS NR Pressure (R) 600 PSIA (22) SI Tank Level (%) (30) S/G A LEVEL WR :j  % A 52 B 48 c 48 D 48 (30) S/G A LEVEL (R) -:j % SI Tanl<"Pressure~psig) (30) S/G A PRESS Bb6 psi a A 233 B 228 c 230 D 234 S/G A STM FLW (R) T Xl0**6 PPH (21) SIAS Alarm NO S/G A FD FLW (R) 0 Xl0**6 PPH (30) S/G B LEVEL WR b  % C-12 (30) S/G B LEVEL (R) b  %* (30) S/G B PRESS 866 psi a Concentrated Boric Acid Tank Levels S/G B STM FLW (R) T Xl0**6 PPH T53A 97.5  % S/G B FD FLW (R) 0 Xl0**6 PPH T53B 95":2  % Reactor Vessel DP T-:r- psid PANEL K-13 (12) PORV Discharge Temperature ~ F (13) Pzr Safety Valve Discharge TemP-(F) (20) CONTAINMENT HIGH PRESS RV-1039 88 F NO RV-1040 n'S f RV-1041 n'S F (20) Containment High Radiation NO

SHAVPAll PALEX 92 TSC

• S T AT US P AGE
• Time 1002 Scenario Time 0132 Message #  !! 141 Ti me Ji.Imp - - Scenario Time Jump - -

C-01 C-04 MFP Suction Pressure 277 psig (32) D/G Freq 1-1 .0 1-2 .0 MFP A Discharge Preisure 360 psig * (32) 1-C BUS VOLTS 2482 A~ps1b9 MFP B Discharge Pressure m psig (32) 1-D BUS VOLTS 2'48l Amps'321 AFW Pump P-8C Amperes O AMPS AFW Discharge Pressure P-8C 9 psig C-11 BACK C-llA AFW Pump P-8A Amperes "SS AMPS AFW Pump P-8B Steam Pressure o psig (17) Containment Area Monitors AFW Discharge Pressure P-8A & P-8B 1193 psig RIA-1805 .450 R/Hr Moisture SEP Drain Tank Level ~% . RIA-1806 :150 R/Hr Condensor Hotwell Level bb % RIA-1807 :TbO R/Hr Condensor Vacuum , 28.1 in Hg. RIA-1808 :120 R/Hr Gland Seal Condensor Vacuum 14.2 in Hg. (17) High Range ContaTnilient Monitors

*Atmospheric Dump Valves                        TRmlT                      RIA-2321          1          R/Hr AFW Pump         P-8A ON     P-8B OFF    P-8C nrt                         RIA-2322         T           R/Hr
*Heater Drain Pump--        P-lOA Ulr P-lOB Ulr                      (19) Containment Hydrogen Concentration Condensate Pump              P-2A otF    P-2B otF                         AI-2401R          0        %

Al-2401L U  % C-11 (30) Main Steam Line ~amma RIA-2324 .7E+03 CPM (31) AFW FLOW TO SGA RIA-2323 7.8E+03 CPM FROM P8A, B 169 From P-8C 0 gpm (31) AFW FLOW TO 'SGB EQUIPMENT STATUS: FROM P-8A&B 166 From P-8C 0 gpm Condensor Vacuum (R) '28 IN HG. 1. SIGNIFICANT EQUIP OUTAGES PCP A Leak-off Flow (R) r.o (INOPERABLE EQUIPMENT) PCP B Leak-off Flow (R) r:o 2. SURVEILLANCE DUE/PROGRESS PCP C Leak-off Flow (R) r:o 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off Flow (R) r:o OR OUTAGES

SHAVPALI PALEX 92 TS C

• S T AT US P AGE
• Time 1002 Scenario Time 0132 Message # !! 142 Time Jump - - Scenario Time Jump - -

C-08 C-02 SW Pumps P-7A ON P-78 ST8Y P-7C ON (10) VCT Temp 108 F CCW Pumps P-52A ST8V P-528 ~ P-52C ST8V (10) VCT .Pressure 22 psi FPC Pumps P-51A ~ P-518 OFF (10) VCT Level 6I % PCP Control 8leedoff Pressure jS psig CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow o gpm (26) Charging Flow T33 gpm VIA ON V2A ON V3A ON V4A ON (9) Quench Tank Temp Tif2 F VIB ON V28 OR V3B ON V48 OR (9) Quench TANK Pressure :r psig (9) Quench TANK Level b3 % C-03 (7) Pressurizer Pressure (R) T716 psia

                                              '                   (8) PZR Level (R)      LT0102A         j'() %

(23) HPSI Pumps P-66A OFF P-668 OFF LT0103 29.5 % (25) LPSI Pumps P-67A OFF P-678 0Ft (12) PORV PRV-1042A CLOSED 10438 CLOSED (18) Containment Spray Pumps- (12) BLOCK MOV-1042A CLOSED 1043A CLOSED P-54A OFF P-548 OFF P-54C OFF CHARGING PUMPS (27) HPSIA, LPSIA-;-5PRAY A SUCTION P55A ON P55B ON P55C ON CV-3057 (SIRWT) CV-3030 (Sump) (6) PCPS P50A OFF P50B OfF P50C OfF P50D OFF OPEN CLOSED PZR HTR AMPS LC15 0 -LCC

• 16* 0 (1) PCS TAVE (R) LOOPl-(TR-0111) ~38 F LOOP2 (TR-0121) '537 F C-02 (25) REACTOR POWER LEVEL Nil .10E+06 cps Nl3 .69E+OO % NI7 .43  %

Intermediate Press Letdown Temp 114 F NI2 .lOE+06 cps NI4 .69E+OO % NIB :TI"  % Charging Line Temperature ill F Nl-05 .39  % NI-09 Letdown Line Temp l8n F Nl-06 :40  % NI-10 SOCS from PCS (R) -gr F SOCS to PCS (R) 'Sl F PIP (DEMAND LOG+CONSTANT-;-ROD, OR FLUX/TEMP) Gross MW 0 Net MW ~5 (28) Control Rod PositTOn GPl 0 GP2 0 GP3 0 GP4 0 GP6(A) O GP7(8) O

• Stuck Rods NONE <optional># 0 Core Exit Temp ~ ~44.9F

SHAVPALI TSC

• S T AT US P AGE
• PALEX 92 Time 1015 Scenario Time 0145 Message # ll 140, Time Jump Scenario Time Jump - -

C-13 C-12 PCP Curre~Amps)

• Condensate Storage Tank Level T-2 75  % P-50A 0 P-SOB 0 Instrument Air Pressure TOI psig P-50C 0 P-500 "O (15) Containment Building Pressure 0-- psig (6) PCS Flow (16) S/G A Compartment Temperature ~3 F (3) Thot (F) Loop 1 543 F S/G A COMPARTMENT Humidity '52 3 Loop 2 m F (16) S/G B Compartment Temperature 83 F (2) Tcold (F) Loop IA m F S/G B Humidity '52  % Loop 2A m F (16) Dome Temperature 87 F Loop lB m F (11) SIRW Tank Level ~ 3 Loop 2B m F (15) WR Containment Pressure (R) 14 psia (5) Subcooling 28 F 249 PSIA (14) Containment Sump Level 1li 3 * (7) PCS WR Pressure (R) 1232 PSIA (14) Containment Water Level (R) 0-  % (7) PCS NR Pressure (R) bOO PSIA (22) SI Tank Level (%) (30) S/G A LEVEL WR T  %

A 52 B 48 C 48 0 48 (30) S/G A LEVEL (R) :z  % SI Tanl<"Pressure-"f psig) (30) S/G A PRESS 907 psi a

       , A 233        B 228       C 229       D 234                      S/G A STM FLW (R)      0    Xl0**6 PPH (21) SIAS Alarm                        YES                             S/G A FD FLW (R)       0    Xl0**6 PPH (30) S/G B LEVEL WR         45   %

C-12 (30) S/G B LEVEL (R) 45  %* (30) S/G B PRESS Bb4 psi a Concentrated Boric Acid Tank Levels S/G B STM FLW (R) 0 Xl0**6 PPH T53A 83 .1  % S/G B FD FLW (R) 0 Xl0**6 PPH T53B 8!:0  % Reactor Vessel OP r:-r- psid PANEL K-13

* (12) PORY Discharge Temperature       ~        F
* (I3) Pzr Safety Valve Discharge Temj)"(F)                         (20) CONTAINMENT HIGH PRESS RV-1039                     88       F                                              NO RV-1040                     ng       F RV-1041                     ng       F                  (20) Containment High Radiation NO

SHAVPALl PALEX 92 TSC

• S T AT US P AGE Time 1015 Scenario Time 0145 Message # g 141 Time Jump Scenario Time Jump - -

C-01 C-04 MFP Suction Pressure 2 psig (32) D/G Freq 1-1 .0 1-2 .0 MFP A Discharge Pressure ~ psig (32) 1-C BUS VOLTS '2481 Amps'504 MFP B Discharge Pressure ~ psig (32) 1-D BUS VOLTS ~ AmpsJ9b AFW Pump P-8C Amperes 0 AMPS AFW Discharge Pressure P-8C . ~ psig C-11 BACK C-llA AFW Pump P-8A Amperes o5 AMPS AFW Pump P-8B Steam Pressure o psig (17) Containment Area Monitors AFW Discharge Pressure P-8A & P-8B 1191 psig RIA-1805 .550 R/Hr Moisture SEP Drain Tank Level U-3 RIA-1806 :2"50 R/Hr Condensor Hotwell Level n 3 RIA-1807 -:200 R/Hr Condensor Vacuum . 27. 7 in Hg. RIA-1808 -:160 R/Hr Gland Seal Condensor Vacuum T4.2 in Hg. (17) High Range Conta"'lil'iilent Monitors Atmospheric Dump Valves TRlmT RIA-2321 1 R/Hr AFW Pump P-8A ON P-8B OFF P-8C ott RIA-2322 I R/Hr 'Heater Drain Pump-- P-lOA arr P-lOB art (19) Containment Hydrogen Concentration Condensate Pump P-2A 'OFF P-28 arr AI-2401R 0 3 Al-2401L TI 3 C-11 (30) Main Steam Line ~amma RIA-2324 .7Et03 CPM (31) AFW FLOW TO SGA RIA-2323 7.8E+03 CPM FROM P8A, B 169 From P-8C 0 gpm (31) AFW FLOW TO 'SGS EQUIPMENT STATUS: FROM P-8A&B 166 From P-8C 0 gpm Condensor Vacuum (R) ~8 IN HG. 1. SIGNIFICANT EQUIP OUTAGES PCP A Leak-off Flow (R) -:-"§ (INOPERABLE EQUIPMENT) PCP B Leak-off Flow (R) -:-"§ 2. SURVEILLANCE DUE/PROGRESS PCP C Leak-off Flow (R) -:-"§ 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off Flow (R) -:-"§ OR OUTAGES

SHAVPALl PALEX 92 TSC

• S T AT US P AGE
• Time IOI5 Scenario Time OI45 Message # ll I42

 . Time Jump -                 Scenario Time Jump -

C-08 C-02

  .SW Pumps      P-7A ON       P-78 ON     P-7C ON                 (IO) VCT Temp                              104 F CCW Pumps P-52A OR        P-528 OR     P-52C OR                 (IO) VCT Pressure                         2cr psi FPC Pumps P-5IA OR        P-518 OFF                             (10) VCT Level                            "57 %

PCP Control 8leedoff Pressure !O psig CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow 0- gpm (26) Charging Flow T33 gpm VIA ON V2A ON V3A ON V4A ON (9) Quench Tank Temp ~ F VI8 OF'F V28 OFF V38 OF'F V48 otF (9) Quench TANK Pressure  :-Y- psig (9) Quench TANK Level b'J % C-03 (7) Pressurizer Pressure (R) 1232 psia (8) PZR Level (R) LTOI02A ~ % (23) HPSI Pumps P-66A ON P-668 ON LTOI03 12.7 % (25) LPSI Pumps P-67A OR P-678 OR (I2) PORV PRV-I042A CLOSED I043B ctOS'ED (I8) Containment Spray Pumps~ (I2) BLOCK MOV-1042A CLOSED 1043A CLOSED

  .             P-54A OFF P-548 OFF P-54C OFF                            CHARGING PUMPS
 * (27)  HPSIA, LPSIA:SPRAY A SUCTION                                             P55A ON P55B ON P55C ON
.                 CV-3057 (SIRWT)         CV-3030 (Sump)             (6) PCPS     P50A OF'F PSOB otF .psoc OF'F PSOD OFF OPEN                   CLOSED                        PZR HTR AMPS LC15 0 -LCC 16*0 (1) PCS TAVE (R) LOOPI-(TR-0111) ~38 F LOOP2 (TR-012I) '535 F C-02                                     (25) REACTOR POWER LEVEL Nil .16E+05 cps Nl3 .16E-04 % NI7 .65E-Ol          %
   .lnte~mediate  Press Letdown Temp           114  F                 NI2 .16E+05 cps Nl4 .16E-04 % NIB .66E-Ol          %

Charging Line Temperature ill F Nl-05 .41E-Ol % Nl-09 Letdown line Temp ID F Nl-06 .40E-Ol % NI-IO SOCS from PCS (R) 'Sr F SOCS to PCS (R) M F PIP (DEMAND LOG+CONSTANT-;-"ROD, OR FLUX/TEMP) Gross MW 0 Net MW ~3 (28) Control Rod Position GPI 0 GP2 0 GP3 0 GP4 0 GP6(A) TI GP7(8) TI Stuck Rods NONE <optional># o Core Exit Temp ~43.3F

SHAVPALI TSC S T AT US P AGE

• PALEX 92 Time 1030 Scenario Time 0200 Message # 14 140 Time Jump - - Scenario Time Jump - -

C-13 C-12 PCP Currenf"l'Amps) Condensate* Storage Tank level T-2 70  % P-50A 0 P-50B 0 Instrument Air Pressure "g7 psig P-50C -0 P-50D O (15) Containment Building Pressure 0- psig (6) PCS Flow (16) S/G A Compartment Temperature 83 F (3) Thot (F) loop 1 537 F

S/G A COMPARTMENT Humidity 'S2  % loop 2 m F (16) S/G B Compartment Temperature 'SJ F (2) Tcold (F) Loop IA m F S/G B Humidity 'S2  % Loop 2A m F (16) Dome Temperature 87 F Loop 18 m F (11) SIRW Tank Level 9f  % Loop 2B m F (15) WR Containment Pressure (R) 14 psia (5) Subcooling rs- F 309 PSIA (14) Containment Sump level TO  % (7) PCS WR Pressure (R) TI4B PSIA (14) Containment Water Level (R) 0-  % (7) PCS NR Pressure (R) 600 PSIA (22) SI Tank Level (%) - (30) S/G A LEVEL WR T9  %

A 52 B 48 C 48 D 48 (30) S/G A LEVEL (R) 19  % SI Tan~Pressure--Cpsig) (30) S/G A PRESS 900 psi a

      , A 233       B 228     C 229       D 234                     S/G A STM FLW (R)       0   Xl0**6 PPH (21) SIAS Alarm                      YES                            S/G A FD FLW (R)        0   Xl0**6 PPH (30) S/G B LEVEL WR          74  %

C-12 (30) S/G B LEVEL (R) 74  %* (30) S/G B PRESS 938 psi a Concentrated Boric Acid Tank Levels S/G B STM FLW (R) 0 Xl0**6 PPH T53A 64.2  % S/G B FD FLW (R) 0 Xl0**6 PPH T53B 04:1  % Reactor Vessel DP ~ psid PANEL K-13 (12) PORV Discharge Temperature Ba- F (13) Pzr Safety Valve Discharge Temj)"(F) (20) CONTAINMENT HIGH PRESS RV-1039 88 F NO RV-1040 88 F RV-1041 88 F (20) Containment High Radiation NO

SHAVPALI PALEX 92 TSC

• S T AT US P AGE
• Time 1030 Scenario Time 0200 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 .0 MFP A Discharge Pressure T5 psig (32) 1-C BUS VOLTS 2481 Amps495 MFP

• B Discharge Pressure T5 psig (32) 1-D BUS VOLTS 248I Amps'if42 AFW Pump P-8C Amperes 48 AMPS AFW Discharge Pressure P-8C 1221 psig C-11 BACK C-llA AFW Pump P-8A Amperes ~ AMPS AFW Pump P-8B Steam Pressure O psig (17) Containment Area Monitors AFW Discharge Pressure P-8A & P-8B T341 psig RIA-1805 . 550 R/Hr Moisture SEP Drain Tank Level n-% RIA-1806 :250 R/Hr Condensor Hotwell level TI  % RIA-1807 -:200 R/Hr Condensor Vacuum . 0 in Hg. RIA-1808 :TSO R/Hr Gland Seal Condensor Vacuum 14. 2 in Hg. (17) High Range Conta"'filiiient Monitors Atmospheric Dump Valves CI'OSED RIA-2321 1 R/Hr AFW Pump P-8A ON P-8B OFF P-8C ON RIA-2322 T R/Hr Heater Drain Pump- P-lOA arr P-lOB otF (19) Containment Hydrogen Concentration Condensate Pump P-2A OFT P-2B arr AI-2401R .23  %

AI-240ll :2l  % C-11 (30) Main Steam line Gamma RIA-2324 .7E+03 CPM (31)' AFW FLOW TO SGA RIA-2323 7.8E+03 CPM FROM P8A, B 252 From P-8C 140 gpm (31) AFW FLOW TO 'SGS EQUIPMENT STATUS: FROM P-8A&B 0 From P-8C 0 gpm Condensor Vacuum (R) Ci IN HG. 1. SIGNIFICANT EQUIP OUTAGES PCP A Leak-off Flow (R) :9

-g (INOPERABLE EQUIPMENT)

PCP B leak-off Flow (R) 2. SURVEILLANCE DUE/PROGRESS PCP C Leak-off Flow (R)  :-g 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off Flow (R)  :-g OR OUTAGES

SHAVPALl PALEX 92 TSC

• S T AT US P AGE
• Time 1030 Scenario Time 0200 Message # 14 142

 . Time Jump -                Scenario Time Jump -

C-08 C-02 SW Pumps P-7A ON P-7B ON P-7C ON (10) VCT Temp 99 F CCW Pumps P-52A TIR P-528 ON P-52C UR (IO) VCT Pressure II psi FPC Pumps P-51A TIR P-518 'OrF (10) VCT Level '58 % PCP Control Bleedoff Pressure JI psig CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow () gpm (26) Charging Flow T33 gpm VlA ON V2A ON V3A ON V4A ON (9) Quench Tank Temp T02' F VlB OF'F V2B UFF V3B OF'F V4B 'OrF (9) Quench TANK Pressure  :-r- psig (9) Quench TANK Level 6l % C-03 (7) Pressurizer Pressure (R) 1248 psia (8) PZR Level (R) LT0102A Ts--% (23) HPSI Pumps P-66A ON P-668 ON LT0103 T5.4 % (25) LPSI Pumps P-67A OR P-678 UN (12) PORV PRV-1042A CLOSED 10438 CI'OSED (18) Containment Spray Pumps--- (12) BLOCK MOV-1042A CLOSED 1043A CLOSED P-54A OFF P-548 OFF P-54C OFF CHARGING PUMPS (27) HPSIA, LPSIA:-""SPRAY A SUCTION P55A ON . P55B ON P55C ON

.               CV-3057 (SIRWT)          CV-3030 (Sump)             (6) PCPS     PSOA 'OrF PSOB OF'F P50C OF'F PSOD OFF OPEN                     CLOSED                        PZR HTR AMPS LC15 0 -LCC 16*0 (I) PCS TAVE (R) LOOPI-(TR-0111) ~31 F LOOP2 (TR-0121) '53b F C-02                                     (25) REACTOR POWER LEVEL Nil .14E+02 cps Nl3 .14E-07 % NI7 .64E-Ol          %

Intermediate Press Letdown Temp 110 F NI2 .14E+02 cps NI4 .14E-07 % NIB .66E-Ol  % Charging Line Temperature 160 F NI-05 .41E-Ol % Nl-09 Letdown line Temp Tim F NI-06 .20E-Ol % Nl-10 SOCS from PCS (R) 'SJ F SOCS to PCS (R) ~ F

• PIP (DEMAND LOG+CONSTANT-;-'ROD, OR FLUX/TEMP)

Gross MW O Net MW ~3 (28) Control Rod PositTOn GPI 0 GP2 0 GP3 0 GP4 0 GP6(A) TI GP7(B) TI Stuck Rods NONE <optional># o Core Exit Temp ~38.3F

SHAVPALI Time 1045 Scenario Time 0215 TSC

• S T AT US P AGE Message # 15 140 PALEX 92 Time Jump - - Scenarfo Time Jump - -

C-13 C-12 PCP Curreilf"1Amps) Condensate Storage Tank Level T-2 59 % P-50A 0 P-50B 0 Instrument Air Pressure T05 psig P-50C O P-50D 0 (15) Containment Building Pressure 0-- psig (6) PCS Flow - (16) S/G A Compartment Temperature ~3 F (3) Thot (F) Loop 1 468 F S/G A COMPARTMENT Humidity "5J  % Loop 2 ill F (16) S/G B Compartment Temperature ~ F (2) Tcold (F) Loop lA ill F S/G B Humidity "5J 3 Loop 2A ID F (16) Dome Temperature 8b F Loop 1B ill F (11) SIRW Tank Level 87  % Loop 28 ID F (15) WR Containment Pressure (R) 14 psia (5) Subcooling TOl F 732 PSIA (14) Containment Sump Level TO  % (7) PCS WR Pressure (R) ill7 PSIA

 '(14) Containment Water Level (R)     O        %                     (7) PCS NR Pressure (R) 600      PSIA (22) SI Tank Level (%)               -                             (30) S/G A LEVEL WR          80   %

A 52 B 48 C 48 D 48 (30) S/G A LEVEL (R) 80  % SI Tan"l<"Pressure~psig) (30) S/G A PRESS 426 psia A 233 B 227 C 229 D 233 S/G A STM FLW (R) 0 X10**6 PPH (21) SIAS Alarm - YES S/G A FD FLW (R) 0 Xl0**6 PPH (30) S/G B LEVEL WR 95  % C-12 (30) S/G B LEVEL (R) 95  %* (30) S/G B PRESS 985 psia Concentrated Boric Acid Tank Levels S/G B STM FLW (R) 0 X10**6 PPH T53A 26.5  % S/G B FD FLW (R) O X10**6 PPH T53B 20':"'5  % Reactor Vessel DP r-:r- psid PANEL K-13 (12) PORV Discharge Temperature ~ F (13) Pzr Safety Valve Discharge Tem~(F) (20) CONTAINMENT HIGH PRESS RV-1039 87 F NO RV-1040 lf1 F RV-1041 lf1 F (20) Containment High Radiation NO

SHAVPALl. PALEX 92 TSC

• S T AT US P AGE
• Time 1045 Scenario Time 0215 Message # ~ 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 TS psig (32) 1-C BUS VOLTS °2182 Amps4J8 MFP

• B Discharge Pressure TS psig (32) 1-D BUS VOLTS 2481 *Amps4il9 AFW Pump P-8C Amperes '5'l AMPS AFW Discharge Pressure P-8C . TI69 psig C-11 BACK C-llA AFW Pump P-8A Amperes 0-- AMPS AFW Pump P-8B Steam Pressure o psig (17) Containment Area Monitors AFW Discharge Pressure P-8A & P-8B 7 psig RIA-1805 .650 R/Hr Moisture SEP Drain Tank Level 13  % RIA-1806 :350 R/Hr Condensor Hotwell Level 70  % RIA-1807 :220 R/Hr Condensor Vacuum , O in Hg. RIA-1808 -:180 R/Hr Gland Seal Condensor Vacuum 14. 2 in Hg. (17) High Range Contal"iliiient Monitors Atmospheric Dump Valves THlmT RIA-2321 1 R/Hr AFW Pump P-8A OFF P-8B OFF P-8C m- RIA-2322 l R/Hr Heater Drain Pump- P-lOA OFF P- lOB 'O"F'F (19) Containment Hydrogen Concentration Condensate Pump P-2A OFF P-2B OFF Al-2401R .33  %

AI-2401L -:-Jj  % C-11 (30) Main Steam Line Gamma RIA-2324 .69E+03 CPM (31)* AFW FLOW TO SGA RIA-2323 7.7E+03 CPM FROM P8A, B 0 From P-8C 215 gpm (31) AFW FLOW TO ~GB 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) :8 (INOPERABLE EQUIPMENT) PCP B Leak-off Flow (R)  :"B 2. SURVEILLANCE DUE/PROGRESS PCP C Leak-off Flow (R)  :"B 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off Flow (R)  :"B OR OUTAGES

SHAVPALI PALEX 92 TSC

• S T AT US P AGE
• Time 1045 Scenario Time 0215 Message # li 142 Time Jump Scenario Time Jump ~

C-08 C-02 SW Pumps P-7A ON P-78 ON P-7C ON (10) VCT Temp 91 F CCW Pumps P-52A OR P-528 OR P-52C OR (10) VCT Pressure 22 psi FPC Pumps P-51A OR P-518 OFF (10) VCT Level bl % PCP Control 8leedoff Pressure !2 psig

• CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow 0- gpm (26) Charging Flow 133 gpm VIA ON V2A ON V3A ON V4A ON (9) Quench Tank Temp 102 F V18 OF'F V28 OF'F V3B TIFF V48 OFF (9) Quench TANK Pressure -:-Y- psig (9) Quench TANK Level 63 %

C-03 (7) Pressurizer Pressure (R) T237 psia (8) PZR Level (R) LT0102A ~ % {23) HPSI Pumps P-66A ON P-668 ON LT0103 3I.6 % (25) LPSI Pumps P-67A OR P-678 OR (12) PORV PRV-1042A CLOSED 10438 Cl]j'SED (18) Containment Spray Pumps~ (12) BLOCK MOV-1042A OPEN 1043A OPEN P-54A OFF P-548 OFF P-54C OFF CHARGING PUMPS (27) HPSIA, LPSIA:--SPRAV A SUCTION P55A ON P55B ON P55C ON CV-3057 (SIRWT) CV-3030 (Sump) (6) PCPS P50A OFF P508 TIFF P50C OfF P50D OFF OPEN CLOSED PZR HTR AMPS --rc15 0 ---LCC 16*~ (1) PCS TAVE (R) LOOPl-(TR-0111) 460 F LOOP2 (TR-0121) 477 F C-02 (25) REACTOR POWER LEVEL Nil .85E+Ol cps Nl3 .84E-08 % NI7 .64E-Ol  %

 , Intermediate Press Letdown Temp             110  F                NI2 .85E+Ol cps NI4 .84E-08 % NIB .66E-Ol         %

Charging Line Temperature TbO F Nl-05 .41E-Ol % Nl-09 Letdown Line Temp ill F Nl-06 .89E-Ol % Nl-10 SOCS from PCS (R) 83 F

 *socs to PCS (R)                             1J2   F                                    PIP (DEMAND LOG+CONSTANT~OD, OR FLUX/TEMP)

Gross MW 0 Net MW 73 (28) Control Rod PositlOn

                                                                        ~Pl    0 GP2      0     GP3 0      GP4 0 GP6(A) 0 GP7(B) 0 Stuck Rods        NONE     <optional># o Core Exit Temp ~                        470.7F

SHAVPALI Time 1100 TSC Scenario Time 0230 S T AT US P AGE Message # 16 140 PALEX 92 Time Jump - - Scenario Time Jump - - C-13 C-12 PCP Curreiif"1Amps) Condensate Storage Tank Level T-2 57 % P-50A 0 P-50B 0 Instrument Air Pressure 103 psig P-SOC -0 P-50D O (15) Containment Building Pressure 0-- psig (6) PCS Flow (16) S/G A Compartment Temperature n2 F (3) Thot (F) Loop I 464 F S/G A COMPARTMENT Humidity 'Sl % Loop 2 m F (16) S/G B Compartment Temperature ~ F (2) Tcold (F) Loop IA m F S/G B Humidity 'Sl  % Loop 2A m F

   . (16) Dome Temperature                     BS    F                                     Loop IB      m   F (11) SIRW Tank Level                      8b    %                                     Loop 2B      m   F (15) WR Containment Pressure (R)          Iil   psia                  (5) Subcooling              107  F 755 PSIA (14) Containment Sump Level               TO    %                     (7) PCS WR Pressure (R) illl     PSIA (14) (:ontainment Water Level (R)         o    ,%                     (7) PCS NR Pressure (R) 600      PSIA (22) SI Tank Level (%)                                               (30) S/G A LEVEL WR           gr  %

A 52 B 48 C 48 D 48 (30) S/G A LEVEL (R) 9f  % SI Tanl<"Pressure-rpsig) (30) S/G A PRESS 408 psi a A 233 B 227 C 229 D 233 S/G A STM FLW (R) 0 Xl0**6 PPH (21) SIAS Alarm YES S/G A FD FLW (R) 0 Xl0**6 PPH (30) S/G B LEVEL WR 99  % C-12 (30) S/G B LEVEL (R) ~  %* (30) S/G B PRESS 984 psi a Concentrated Boric Acid Tank Levels S/G B STM FLW (R) 0 Xl0**6 PPH T53A 6.8 S/G B FD FLW (R) T53B 6:-s

                                                      %                                                -0   Xl0**6 PPH Reactor Vessel DP                   7":7    psid                              PANEL K-13 (12) PORV Discharge Temperature           1!r-    F (13) Pzr Safety Valve Discharge Tem'j)"(F)                           (20) CONTAINMENT HIGH PRESS RV-1039                        87      F                                                NO RV-1040                        'S7     F RV-1041                        'S7     F                  (20) Containment High Radiation NO

SHAVPALI PALEX 92 TSC

• S T AT US P AG E
• Time 1100 Scenario Time 0230 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 .0 MFP A Discharge Pressure T5 psig (32) 1-C BUS VOLTS 2482 Amps4l7 MFP B Discharge Pressure T5 psig (32) 1-D BUS VOLTS 2481 Amps449 AFW Pump P-8C Amperes '5il AMPS AFW Discharge Pressure P-8C IT69

• psig C-11 BACK C-llA AFW Pump P-8A Amperes AMPS

'AFW Pump P-8B Steam Pressure                 TI    psig           (17) Containment Area Monitors AFW Discharge Pressure P-8A & P-8B           7      psig                RIA-1805         .650        R/Hr Moisture SEP Drain Tank Level                T3 %                       RIA-1806        :1'50        R/Hr Condensor Hotwell Level                      69 %                       RIA-1807        :220         R/Hr Condensor Vacuum                             0       in Hg.             RIA-1808        :180         R/Hr Gland Seal Condensor Vacuum                  14. 2   in Hg.       (17) High. Range ContaTiiilient Monitors Atmospheric Dump Valves                      TRlmT                      RIA-2321         1           R/Hr AFW Pump       P-8A OFF    P-8B OFF     P-8C ~                          RIA-2322        T            R/Hr Heater Drain Pump-        P-lOA ITT P-IOB otF                     (19) Containment Hydrogen Concentration Condensate Pump            P-2A ITT     P-28 OIT                        AI-2401R         .4        %

AI-2401L :il  % C-11 (30) Main Steam Line Gamma RIA-2324 .68E+03 CPM (31) AFW FLOW TO SGA RIA-2323 7.6E+03 CPM FROM P8A, B 0 From P-8C 215 gpm (31) AFW FLOW TO ~GB EQUIPMENT STATUS: FROM P-8A&B 0 From P-8C O gpm Condensor Vacuum (R) TI IN HG. 1. SIGNIFICANT EQUIP OUTAGES PCP A Leak-off Flow (R) :8 {INOPERABLE EQUIPMENT) PCP B Leak-off Flow (R) :s 2. SURVEILLANCE DUE/PROGRESS PCP C Leak-off Flow (R) :s 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off Flow (R) :s OR OUTAGES

SHAVPALl PALEX 92 TSC

• S T AT US P AG E
• Time 1100 Scenario Time 0230 Message # 16 142 Time Jump - Scenario Time Jump -

C-08 C-02 SW Pumps P-7A ON P-78 ON P-7C ON (10) VCT Temp 87 F CCW Pumps P-52A OR P-528 OR P-52C ON (10) VCT Pressure TI psi FPC Pumps P-51A OR P-518 OFF (10) VCT Level . bl % PCP Control Bleedoff Pressure TI psig

 *CONTAINMENT COOLER RECIRC FANS                                  (26) Letdown Flow                          O gpm (26) Charging Flow                         T33 gpm VIA ON      V2A ON       V3A ON     V4A ON                     (9) Quench Tank Temp                     102" F VIB OFF     V2B OFF      V3B MF     V4B OFF                    (9) Quench TANK Pressure                 :r psig
                                                                  * (9) Quench TANK Level                    bl %

C-03 (7) Pressurizer Pressure (R) 1241 psia (8) PZR Level (R) LT0102A ~% (23) HPSI Pumps P-66A ON P-668 ON LT0103 '34.6 % (25) LPSI Pumps P-67A ON P-678 ON (12) PORV PRV-1042A CLOSED 10438 CC:OSED (18) Containment Spray Pumps (12) BLOCK MOV-1042A OPEN 1043A OPEN P-54A OFF P-548 OFF P-54C OFF CHARGING PUMPS (27) HPSIA, LPSIA~PRAV A SUCTION P55A ON P55B ON P55C ON

         '       CV-3057 (SIRWT)         CV-3030 (Sump)             (6) PCPS     P50A OFF P50B OFF P50C OFF P500 OFF OPEN                   CLOSED                        PZR HTR AMPS LC15 0 -LCC 16*0 (1) PCS TAVE (R) LOOPI-(TR-0111) 156 F LOOP2 (TR-0121) 47I F C-02                                      (25) REACTOR POWER LEVEL Nil .73E+Ol cps Nl3 .72E-08 % NI7 .64E-Ol           %
  *Intermediate Press Letdown Temp            109 F                  NI2 .73E+Ol cps NI4 .72E-08 % NIB .66E-Ol           %

Charging Line Temperature

• ill F NI-05 .41E-Ol % Nl-09 Letdown Line Temp ill F NI-06 .64E-Ol % NI-10

  .SOCS from PCS (R)                         nr   F SOCS to PCS (R)                           M F                                         PIP (DEMAND LOG+CONSTANT-;---ROD, OR _FLUX/TEMP)

Gross MW 0 Net MW ~4 (28) Control Rod PositlOn GPl 0 GP2 0 GP3 0 GP4 0 GP6(A) n GP7(B) n Stuck Rods NONE <optional># 0 Core Exit Temp l66.7F

SHAVPALI Time 1115 TSC Scenario Time 0245 S T AT US P AGE Message # !I 140 PALEX 92 Time Jump Scenario Time Jump - - C-13 C-12 PCP Currenr-{Amps) Condensate Storage Tank Level T-2 56  % P-50A 0 P-50B 0 Instrument Air Pressure 103 psig P-SOC 0 P-50D O (15) Containment Building Pressure O psig (6) PCS Flow - (16) S/G A Compartment Temperature 132 f (3) Thot (F) Loop 1 450 F S/G A COMPARTMENT Humidity "5Ll 3 Loop 2 452 F (16) S/G B Compartment Temperature ~ F (2) Tcold (F) Loop IA ill F S/G B Humidity "5il 3 Loop 2A m F (16) Dome Temperature 85 F Loop lB m F (11) SIRW Tank Level HS 3 Loop 2B m F (15) WR Containment Pressure (R} Til psia (5) Subcooling m F 801 PSIA (14) Containment Sump Level TO  % (7) PCS WR Pressure (R) ill4 PSIA .(14) Containment Water Level (R) 0  % (7) PCS NR Pressure (R} 600 PSIA (22) SI Tank Level (%) - (30} S/G A LEVEL WR 91  % A 52 B 48 C 48 D 48 (30} S/G A LEVEL (R) 97  % SI Tan"k"Pressure~psig) (30) S/G A PRESS jtf6 psia A 232 B 227 C 229 D 233 S/G A STM FLW (R) T Xl0**6 PPH (21) SIAS Alarm - YES S/G A FD FLW (R) 0 Xl0**6 PPH (30) S/G B LEVEL WR 99  % C-12 (30) S/G B LEVEL (R) gg  %* (30) S/G B PRESS 983 psi a Concentrated Boric Acid Tank Levels S/G B STM FLW (R) 0 Xl0**6 PPH T53A 6.8 3 S/G B FD FLW (R) 0 Xl0**6 PPH T53B b:B  % - Reactor Vessel DP /:-s psid PANEL K-13 (12) PORV Discharge Temperature ~ F (13} Pzr Safety Valve Discharge Temj)"(F) (20) CONTAINMENT HIGH PRESS RV-1039 86 F NO RV-1040 as F RV-1041 as F (20) Containment High Radiation NO

SHAVPALI PALEX 92 I TSC

• S T AT US P AGE
• Time 1115 Scenario Time 0245 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 .0 MFP A Discharge Pressure T5 psig (32) 1-C BUS VOLTS 2482 Amps439 MFP 8 Discharge Pressure T5 psig (32) 1-D BUS VOLTS ~ Amps!9b AFW Pump P-8C Amperes '5'4 AMPS AFW Discharge Pressure P-BC I psig C-11 BACK C-llA AFW Pump P-8A Amperes 0 AMPS

'AFW Pump P-88 Steam Pressure               235 psig              (17) Containment Area Monito~s
 ~FW Discharge Pressure P-BA & P-88         TOTS psig                    RIA-1805         .650        R/Hr Moisture SEP Drain Tank Level              rr--- %                      RIA-1806        :350         R/Hr Condensor Hotwell Level                    68 %                         RIA-1807        :220         R/Hr Condensor Vacuum                         . O        in Hg.              RIA-1808        :180         R/Hr Gland Seal Condensor Vacuum                14. 2 in Hg.          (17) High Range Conta"lrlrilent Monitors Atmospheric Dump Valves                    TRlmT                        RIA-2321        1            R/Hr AFW Pump     P-8A OFF     P-88 OFF    P-8C nrt                          RIA-2322        T            R/Hr Heater Drain Pump-       P-lOA ITT P-108 OFF                     (19) Containment Hydrogen Concentration Condensate Pump           P-2A ITT    P-28 OFF                          AI-2401R         .46       %

AI-2401L :4b  % C-11 (30) Main Steam Line Gamma RIA-2324 .67E+03 CPM (31) AFW FLOW TO SGA RIA-2323 7.5E+03 CPM FROM P8A, 8 252 From P-8C O gpm (31) AFW FLOW TO 'SGS 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) :a (INOPERABLE EQUIPMENT) PCP 8 Leak-off Flow (R) ~ 2. SURVEILLANCE DUE/PROGRESS PCP C Leak-off Flow (R) ~ 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off Flow (R) ~ OR OUTAGES

SHAVPALI PALEX 92 TSC

• S T AT US P AGE
• Time 1115 Scenario Time 0245 Message # 17 *142 Time Jump - Scenario Time Jump C-08 C-02 SW Pumps P-7A ON P-78 ON P-7C ON (10) VCT Temp 85 F CCW Pumps P-52A UR P-528 UR P-52C UR (10) VCT Pressure 2b psi FPC Pumps P-51A UR P-518 OFF (10) VCT Level 67 3 PCP Control Bleedoff Pressure !S psig CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow 213 gpm (26) Charging Flow 113 gpm VIA ON V2A ON V3A ON V4A ON (9) Quench Tank Temp ~ F VIB TitF V2B TitF V3B OFF V48 TitF (9) Quench TANK Pressure :i-- psig (9) Quench TANK Level bil %

C-03 (7) Pressurizer Pressure (R) 1224 psia (8) PZR. Level (R) LT0102A ~ % (23) HPSI Pumps P-66A ON P-668 ON LT0103 !5.4 % (25) .LPSI Pumps P-67A UR P-678 UR (12) PORV PRV-1042A CLOSED

• 10438 C[()'SED (18) Containment Spray Pumps (12) BLOCK MOV-1042A OPEN 1043A OPEN P-54A OFF P-548 OFF P-54C OFF CHARGING PUMPS (27) HPSIA, LPSIA~PRAY A SUCTION P55A ON P558 ON P55C ON CV-3057 (SIRWT) CV-3030 (Sump) (6) PCPS PSOA OFF PSOB TIFF PSOC OFF P50D OFF OPEN CLOSED PZR HTR AMPS ---rc1s 0 ~LCC 16*~

(1) PCS TAVE (R) LOOPI-(TR-0111) 442 F LOOP2 (TR-0121) 459 F C-02 (25) REACTOR POWER LEVEL Nil .72E+Ol cps NI3 .71E-08 % NI7 .89E-Ol  % Intermediate Press Letdown Temp 94 F NI2 .72E+Ol cps NI4 .71E-08 % NIB .66E-Ol  % Charging Line Temperature BS F NI-05 .65E-Ol % Nl-09 Letdown Line Temp '94 F Nl-06 .40E-Ol % Nl-10 SOCS from PCS (R) Bl F SOCS to PCS (R) ITT F PIP {DEMAND LOG+CONSTANT-;-""ROD, OR FLUX/TEMP) Gross MW O Net MW ~4 (28) Control Rod PositTOn GPI 0 GP2 0 GP3 0 GP4 0 GP6(A) 0 GP7(8) 0 Stuck Rods NONE <optional># O Core Exit Temp ~ 452.9F

SHAVPALI TSC

• S T AT US P AGE
• PALEX 92 Time 1130 Scenario Time 0300 Message # 18 140 Ti me Ju.mp - - Scenario Time Jump - -

C-13 C-12 PCP Currenr-{Amps) Condensate Storage Tank Level T-2 57 3 P-50A 0 P-508 0 Instrument Air Pressure 95 psig P-50C 0 P-50D O (15) Containment Building Pressure 0 psig (6) PCS Flow (16) S/G A Compartment Temperature ~2 F (3) Thot (F) Loop I 430 F

  . S/G A COMPARTMENT Humidity       'Sil  3                                        Loop 2      m    F (16) S/G B Compartment Temperature     BI    F                         (2) Tcold (F) Loop IA      m    F S/G 8 Humidity                   'Sil  %                                        Loop 2A     m    F
'(16) Dome Temperature                  84    F                                        Loop 18     m    F (11) SIRW Tank Level                    84    3                                        Loop 28     m    F (15) WR Containment Pressure (R)       14    psia                      (5) Subcooling             m    F 811 PSIA

( 14) Containment Sump Level TO 3 -, (7) PCS WR Pressure (R) ms PSIA

• (14) Containment Water Level (R) O .3 (7) PCS NR Pressure (R} 600 PSIA (22} SI Tank Level (%) - (30) S/G A LEVEL WR 91  %

A 52 8 48 C 48 D 48 (30) S/G A LEVEL (R) 97  % SI Tan"K""Pressure--ipsig) (30} S/G A PRESS 287 psi a A 232 B 227 C 229 D 233 S/G A STM FLW (R} T Xl0**6 PPH (21) SIAS Alarm - YES S/G A FD FLW (R) 0 Xl0**6 PPH (30) S/G 8 LEVEL WR 99  % C-12 (30) S/G 8 LEVEL (R) 99  %' (30) S/G 8 PRESS 944 psi a Concentrated Boric Acid Tank Levels S/G 8 STM FLW (R) 0 Xl0**6 PPH T53A 6.8 3 S/G 8 FD FLW (R) 0 Xl0**6 PPH T53B b:8 3 Reactor Vessel DP r:-g psid PANEL K-13 (12) PORV Discharge Temperature ~ F (13) Pzr Safety Valve Discharge Tem~(F) (20) CONTAINMENT HIGH PRESS RV-1039 86 F NO RV-1040 BG F RV-1041 BG F (20) Containment High Radiation NO

i I I SHAVPALl PALEX 92 TSC

• S T AT US P AGE
• Time 1130 Scenario Time 0300 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 .0 MFP A Discharge Pressure B psig (32) 1-C BUS VOLTS 2481 Amps4il2 MFP B Discharge Pressure B psig (32) 1-D BUS VOLTS 2482 Amps~ AFW Pump P-8C Amperes 0 AMPS AFW Discharge Pressure P-8C 7 psig C-11 BACK C-llA AFW Pump P-8A Amperes 0 AMPS AFW Pump P-88 Steam Pressure O psig (17) Containment Area Monitors AFW Discharge Pressure P-8A & P-88 247 psig RIA-1805 .650 R/Hr Moisture SEP Drain Tank Level T3 % RIA-1806 -:150 R/Hr Condensor Hotwell Level 67 % RIA-1807 -:220 R/Hr Condensor Vacuum , 0 in Hg. RIA-1808 . -:-r80 R/Hr Gland Seal Condensor Vacuum 14.2 in Hg. (17) High Range Contaliliiient Monitors Atmospheric Dump Valves THlmT RIA-2321 1 R/Hr AFW Pump P-8A OFF P-88 OFF P-8C 0Ft RIA-2322 I R/Hr Heater Drain Pump- P-lOA ITT P-108 ITT (19) Containment Hydrogen Concentration Condensate Pump P-2A ITT P-28 ITT Al-2401R .5  % Al-2401L :S  % C-11 (30) Main Steam Line 'Gamma RIA-2324 .66E+03 CPM (31) AFW FLOW TO SGA RIA-2323 7.4E+03 CPM FROM P8A, B 0 From P-8C 0 gpm (31) AFW FLOW TO ~GB 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) :s 2. SURVEILLANCE DUE/PROGRESS PCP C Leak-off Flow (R) :s 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off Flow (R) :s OR OUTAGES

SHAVPALl PALEX 92 TSC

• S T AT US P AGE
• Time 1130 Scenario Time 0300 Message # 18 142 Time Jump Scenario Time Jump ~

C-08 C-02 SW Pumps P-7A ON P-78 ON P-7C ON (10) VCT Temp 85 F CCW Pumps P-52A OR P-528 OR P-52C OR (10) VCT Pressure 45 psi FPC Pumps P-51A OR P-518 otf (10) VCT Level 80 % PCP Control Bleedoff Pressure '5J psig CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow 20 gpm (26) Charging Flow 126 gpm VIA ON V2A ON V3A ON V4A ON (9) Quench Tank Temp 102 F .

• VIB otf V2B otF V3B otF V4B otF (9) Quench TANK Pressure :i- psig (9) Quench TANK Level bil %

C-03 (7) Pressurizer Pressure (R) TT55 psia (8) PZR Level (R) LT0102A ~ % (23) HPSI Pumps P-66A OFF P-668 ON LT0103 !7.7 % (25)*LPSI Pumps P-67A OW- P-678 ON '(12) PORV PRV-1042A CLOSED 10438 ctITS'Eo (18) Containment Spray Pumps~ (12) BLOCK MOV-1042A OPEN 1043A OPEN

        ,     P-54A OFF P-548 OFF P-54C OFF                            CHARGING PUMPS (27) HPSIA, LPSIA~PRAY A SUCTION                                              P55A ON P55B ON P55C ON CV-3057 (SIRWT)         CV-3030 (Sump)             (6) PCPS     P50A otF P50B OF'F P50C otF P500 OFF OPEN                    CLOSED                        PZR HTR AMPS LC15 0 -LCC 16*0 (1) PCS TAVE (R) LOOPI-(TR-0111) 423 F LOOP2 (TR-0121) 438 F C-02                                      (25) REACTOR POWER LEVEL Nil .72E+Ol cps NI3 .71E-08 % NI7 .64E-Ol         %

Intermediate Press Letdown Temp 90 F NI2 .72E+OI cps NI4 .71E-08 % NIB .66E-OI  % Charging Line Temperature Bl F Nl-05 .41E-OI % NI-09 Letdown Line Temp '90 F Nl-06 .64E-OI % NI-10 SOCS from PCS (R) 'Sl F SOCS to PCS (R) 'ST F PIP (DEMAND LOG+CONSTANT:---ROD, OR FLUX/TEMP) Gross MW 0 Net MW ~4 (28) Control Rod PositTOn GPI 0 GP2 0 GP3 0 GP4 0 GP6(A) TI GP7(B) TI Stuck Rods NONE <optional># o Core Exit Temp ~ 433.SF

SHAVPALI TSC

• S T AT US P AGE

                                                                                                          **PALEX 92 Time 1145                 Scenario Time 0315              Message # 19                 140 Time Jump                   Scenario Time Jump - -

C-13 C-12 PCP Curreiif'"1Amps) Condensate Storage Tank Level T-2 58 P-SOA 0 P-50B 0 Instrument Air Pressure TOO P-50C TI P-50D TI (15) Containment Building Pressure 0-- (6) PCS Flow (16) S/G A Compartment Temperature n2 (3) Thot (F) Loop I 425 F S/G A COMPARTMENT Humidity 'Sil  % Loop 2 427 F (16) S/G B Compartment Temperature BI F (2) Tcold (F) Loop IA 407 F S/G B Humidity 'Sil  % Loop 2A 40b F

• (16) Dome Temperature 'Sil F Loop IB 407 F (11) SIRW Tank Level 'Sil  % Loop 2B 40b F (15) WR Containment Pressure (R) 11 psi a (5) Subcooling rrg F 668 PSIA (14) Containment Sump Level Jo  % (7) PCS WR Pressure (R) 990 PSI~

(14). Containment Water Level (R) TI .% (7) PCS NR Pressure (R) 600 PSIA (22) SI Tank Level (%) - (30) S/G A LEVEL WR gs-  % A 52 B 48 C 48 D 48 (30) S/G A LEVEL (R) ~  % SI Tan~Pressure-Cpsig) (30) S/G A PRESS '2"51 psia A 232 B 227 C 229 D 233 S/G A STM FLW (R) ~ Xl0**6 PPH (21) SIAS Alarm YES S/G A FD FLW (R) 0- Xl0**6 PPH (30) S/G B LEVEL WR Too  % C-12 (30) S/G B LEVEL (R) TOO  %* (30) S/G B PRESS 9il6 psia Concentrated Boric Acid Tank Levels S/G B STM FLW (R) :S- Xl0**6 PPH T53A 6.8  % S/G B FD FLW (R) 0- Xl0**6 PPH T53B ~  % Reactor Vessel DP n:O' psid PANEL K-13 (12) PORV Discharge Temperature n5'""" F (13) Pzr Safety Valve Discharge TemP-(F) (20) CONTAINMENT HIGH PRESS RV-1039 85 F NO RV-1040 'S'S F RV-1041 'S'S F (20) Containment High Radiation NO

SHAVPALl PALEX 92 TSC

• S T AT US P AG E
• Time 1145 Scenario Time 0315 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 .0 MFP A Discharge Pressure TS psig (32) 1-C BUS VOLTS 2481 Ampsif51 MFP B Discharge Pressure TS psig (32) 1-D BUS VOLTS 2if8'2 Ampslb'O AFW Pump P-8C Amperes 0 AMPS AFW Discharge Pressure P-8C 7 psig C-11 BACK C-llA AFW Pump P-8A Amperes 0 AMPS AFW Pump P-8B Steam Pressure 0 psig (17) Containment Area Monitors AFW Discharge Pressure P-8A & P-8B 16 psig RIA-1805 .650 R/Hr Moisture SEP Drain Tank Level TI % RlA-1806 :350 R/Hr Condensor Hotwell Level 'Sb % RIA-1807 -:220 R/Hr Condensor Vacuum 0 in Hg. RIA-1808 :TSO R/Hr Gland Seal Condenser Vacuum 14. 2 in Hg. (17) High Range Conta"'filiiient Monitors Atmospheric Dump Valves TmmT RIA-2321 1 R/Hr AFW Pump P-8A OFF P-8B OFF P-8C Ott RIA-2322 l R/Hr Heater Drain Pump- P-lOA ?ITT' P-lOB ?ITT' (19) Containment Hydrogen Concentration

*condensate Pump             P-2A ?ITT'   P-2B ITT                       Al-2401R          . 55        %

AI-240ll -:-S"5  % C-11 (30) Main Steam line Gamma RIA-2324 39.0E+03CPM

 '(31) AFW FLOW TO SGA                                                    RIA-2323         42.0E+03CPM FROM P8A, B 0                From P-8C 0    gpm (31) AFW FLOW TO ~GB                                             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) :a (INOPERABLE EQUIPMENT) PCP B leak-off Flow (R) :s 2. SURVEILLANCE DUE/PROGRESS

• PCP C leak-off Flow (R) :s 3. ABNORMAL ELECTRICAL LINEUPS PCP D leak-off Flow (R) :s OR OUTAGES

SHAVPALI PALEX 92 TSC

• S T AT US P AGE
• Time 1145 Scenario Time 0315 Message # 19 142 Time Jump - Scenario Time Jump -

C-08 C-02 SW Pumps P-7A ON P-78 ON P-7C ON (10) VCT Temp 84 F CCW Pumps P-52A OR P-528 OR P-52C OR (10) VCT Pressure 'SJ psi FPC Pumps P-51A OR P-518 otF (10) VCT Level 87 % PCP Control Bleedoff Pressure bl psig CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow 2l gpm (26) Charging Flow 126 gpm VIA ON V2A ON V3A ON V4A ON (9) Quench Tank Temp ~ F Vl8 OFF V2B OFF V38 OFF V48 OFF (9) Quench TANK Pressure :i- psig (9) Quench TANK Level 64 % C-03 (7) Pressurizer Pressure (R) 996 psia

                                               '                   (8) PZR Level (R)       LT0102A         ~ %

(23) HPSI Pumps P-66A Of/ P-668 ON LT0103 j7,5 % (25) LPSI Pumps P-67A ~ P-678 ON (12) PORV PRV-1042A CLOSED 10438 CCOSED

 * (18) Containment Spray Pumps~                                  (12) BLOCK MOV-1042A OPEN          1043A OPEN P-54A OFF P-548 OFF P-54C OFF                           CHARGING PUMPS (27) HPSIA, LPSIA~PRAY A SUCTION                                             P55A ON P558 ON P55C ON CV-3057 (SIRWT)         CV-3030 (Sump)            (6) PCPS     PSOA OFF PSOB OFF PSOC OFF PSOD OFF OPEN                   CLOSED                       PZR HTR AMPS LC15 0 -LCC 16*0 (1) PCS TAVE (R)    LOOPI-(TR-0111) 416 F LOOP2 (TR-0121) 40'l F C-02                                     (25) REACTOR POWER LEVEL Nil .72E+Ol cps Nl3 .71E-08 % NI7 .65E-Ol          %

Intermediate Press Letdown Temp 82 F NI2 .72E+Ol cps NI4 .71E-08 % NIB .66E-Ol  % Charging Line Temperature Il9 F NI-05 .41E-Ol % Nl-09 Letdown Line Temp 82 F Nl-06 .40E-Ol % Nl-10 SOCS from PCS (R) 'S'3' F SOCS to PCS (R) iIT F PIP (DEMAND LOG+CONSTANT:-ROD, OR FLUX/TEMP) Gross MW O Net MW ~4 * (28) Control Rod PositTOn GPI 0 GP2 0 GP3 0 GP4 0 GP6(A) TI GP7(8) TI Stuck Rods NONE <optional># o Core Exit Temp 427.SF

SHAVPALI Time 1200 TSC Scenario Time 0330 S T AT US P AG E Message # £! 140 PALEX 92 Time Jump Scenario Time Jump - - C-13 C-12 PCP Curre'iltl'Amps) Condensate Storage Tank Level T-2 57  % P-50A 0 P-508 0 Instrument Air Pressure TOO psig P-50C -0 P-50D 0 (15) Containment Building Pressure 0-- psig (6) PCS Flow (16) S/G A Compartment Temperature li2 F (3) Thot (F) Loop 1 424 F S/G A COMPARTMENT Humidity '54  % Loop 2 m F (16) S/G B Compartment Temperature Bf F (2) Tcold (F) Loop IA 40b F S/G B Humidity '54  % Loop 2A m F (16) Dome Temperature 84 F Loop lB m F (11) SIRW Tank Level ~  % Loop 2B 3ti>1 F (15) WR Containment Pressure (R} Til psia (5) Subcooling m F 660 PSIA (14} Containment Sump Level 10  % (7) PCS WR Pressure (R) 980 PSIA (14} Containment Water Level {R} 0  % (7) PCS NR Pressure (R) 600 PSIA (22} SI Tank Level (%) - (30) S/G A LEVEL WR gs-  % A 52 B 48 C 48 D 48 (30) S/G A LEVEL (R) 95  %

     .SI Tan"K"Pressure--rpsig)                                  (30) S/G A PRESS             250    psi a A 232      B 227      C 229      D 233                      S/G A STM FLW (R)       T      X10**6 PPH (21} SIAS Alarm                    -    YES                            S/G A FD FLW (R}        0      Xl0**6 PPH (30) S/G B LEVEL WR          Too    %

C-12 (30) S/G B LEVEL (R) 100  %' {30) S/G B PRESS 810 psi a

• Concentrated Boric Acid Tank Levels S/G B STM FLW (R) T Xl0**6 PPH

       ,. T53A                        6.8   %                        S/G B FD FLW (R)        0      X10**6 PPH T53B                       0:8    %

Reactor Vessel DP S:O psid PANEL K-13 (12) PORV Discharge Temperature ~ F (13) Pzr Safety Valve Discharge Temj:)(F) (20) CONTAINMENT HIGH PRESS RV-1039 85 F NO RV-1040 tiS F RV-1041 tiS F (20) Containment High Radiation NO

SHAVPALl PALEX 92 TSC

• S T AT US P AGE
• Time 1200 Scenario Time 0330 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 .0 MFP A Discharge Pressure TS psig (32) 1-C BUS VOLTS 2481 Amps451 MFP B Discharge Pressure TS psig (32) 1-D BUS VOLTS ~ Amps'j6(j AFW Pump P-8C Amperes 0 AMPS

• AFW Discharge Pressure P-8C 7 psig C-11 BACK C-llA AFW Pump P-8A Amperes 0 AMPS AFW Pump P-8B Steam Pressure 0 psig (17) Containment Area Monitors

.AFW Discharge Pressure P-8A & P-8B            16     psig                RIA-1805         .650         R/Hr Moisture SEP Drain Tank Level                 TI %                       RIA-1806        -:350         R/Hr Conderrsor Hotwe 11 Level                     6S %                       RIA-1807        :220          R/Hr Condensor Vacuum                           ,()        in Hg .            RIA-1808        :180          R/Hr Gland Seal Condensor Vacuum                 . 14.2    in Hg.       (17) High Range Contal"'niiient Monitors Atmospheric Dump Valves                       THlWT                      RIA-2321        1             R/Hr AFW Pump     P-8A OFF       P-88 OFF    P-8C 0Fr                         RIA-2322        1             R/Hr Heater Drain Pump-         P-lOA 0IT P-lOB OFT                     (19) Containment Hydrogen Concentration Condensate Pump             P-2A 0IT    P-2B 0IT                         AI-2401R         . 59       %

AI-2401L  :"59  % C-11 (30) Main Steam Line Gamma RIA-2324 39.0E+03CPM . (31) AFW FLOW TO SGA RIA-2323 42.0E+03CPM FROM P8A, B 0 From P-8C O gpm (31) AFW FLOW TO ~GB EQUIPMENT STATUS: FROM P-8A&B 0 From P-8C O 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) -:-s 2. SURVEILLANCE DUE/PROGRESS PCP C Leak-off Flow (R) -:-s 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off Flow (R) -:-s OR OUTAGES

SHAVPALI PALEX 92 TSC ** S T AT US P AGE

• Time 1200 Scenario Time 0330 Message # ll 142 Time Jump - Scenario Time Jump . -

C-08 C-02 SW Pumps P-7A ON P-78 ON P-7C ON (10) VCT Temp 84 F CCW Pumps P-52A UR P-528 OR P-52C UR (10) VCT Pressure "5l psi FPC Pumps P-51A OR P-518 OFF (10) VCT Level "H7 % PCP Control Bleedoff Pressure bl psig CONTAINMENT COOLER RECIRC FANS (26) letdown Flow 2l gpm (26) Charging Flow 126 gpm

• VIA ON V2A ON V3A ON V4A ON (9) Quench Tank Temp ~ F VIB OFF V2B OFF V3B OFF V4B OFF (9) Quench TANK Pressure -:r- psig (9) Quench TANK Level 04 %

C-03 (7) Pressurizer Pressure (R) 980 psia

                                              '                    (8) PZR level (R)         l T0102A          W %

(23) HPSI Pumps P-66A OFF P-668 ON LT0103 35 % (25) LPSI Pumps P-67A "Ur:r- P-678 ON (12) PORV PRV-1042A CLOSED 10438 trOSED

* (18) Containment Spray Pumps~                                   (12) BLOCK MOV-1042A OPEN              1043A OPEN P-54A OFF P-548 OFF P-54C OFF                            CHARGING PUMPS (27) HPSIA, LPSIA~PRAY A SUCTION                                              P55A ON P558 ON P55C ON CV-3057 (SIRWT)          CV-3030 (Sump)            (6) PCPS     P50A OFF P508 TIFF P50C TIFF P50D OFF OPEN                     CLOSED                       PZR HTR AMPS LC15 0 -LCC 16*0 (1) PCS TAVE (R) LOOPl-(TR-0111) 415 F LOOP2 (TR-0121) 390 F C-02                                      (25) REACTOR POWER LEVEL             .

Nil .72E+Ol cps NI3 .71E-08 % NI7 .65E-Ol  % Intermediate Press letdown Temp 82 F NI2 .72E+Ol cps NI4 .71E-08 % NIB .66E-Ol  % Charging Line Temperature 129 F NI-05 .41E-Ol % NI-09 Letdown line Temp 82 F NI-06 .40E-Ol % NI-10 SOCS from PCS (R) Bl F SOCS to PCS (R) Bl F PIP (DEMAND LOG+CONSTANT-;-"'°ROD, OR FLUX/TEMP) Gross MW 0 Net MW ~4 (28) Control Rod Positl'On

• GPl 0 GP2 0 GP3 0 GP4 0 GP6(A) O GP7(8) 0 Stuck Rods . NONE <optional># o Core Exit Temp - 426 F

SHAVPALl Time 1215 TSC Scenario Time 0345 S T AT US P AGE Message # 22 140 PALEX 92 Time Jump Scenario Time Jump - - C-13 C-12 PCP Curreiif"1Amps) Condensate Storage Tank Level T-2 56  % P-50A 0 P-50B 0 Instrument Air Pressure TOO psig P-50C 0 P-50D o (15) Containment Building Pressure 0-- psig (6) PCS Flow (16) S/G A Compartment Temperature 82 F (3) Thot (F) Loop 1 419 F S/G A COMPARTMENT Humidity '54  % Loop 2 408 F (16) S/G B Compartment Temperature BT F (2) Tcold (F) Loop IA 401 F S/G B Humidity '54  % Loop 2A m F (16) Dome Temperature 84 F Loop IB 400 F .( 11) SIRW Tank Level 80  % Loop 2B ~ F (15) WR Containment Pressure (R) Iil psia (5) Subcooling 120 F 580 PSIA (14) Containment Sump Level 10  % (7) PCS WR Pressure (R) 9bO PSIA (14) Containment Water Level (R) O  % (7) PCS NR Pressure (R) 600 PSIA (22) SI Tank Level (%) (30) S/G A LEVEL WR gr  % A 52 B 48 C 48 D 48 (30) S/G A LEVEL (R) 91  % SI Tan~Pressure--Cpsig) (30) S/G A PRESS no psi a A 232 B 227 C 229 D 233 S/G A STM FLW (R) T Xl0**6 PPH (21) SIAS Alarm - YES S/G A FD FLW (R) 0 Xl0**6 PPH (30) S/G B LEVEL WR Too  % C-12 (30) S/G B LEVEL (R) TOO  %* (30) S/G B PRESS 790 psi a Concentrated Boric Acid Tank Levels S/G B STM FLW (R) T Xl0**6 PPH T53A 6.8  % S/G B FD FLW (R) 0 Xl0**6 PPH T53B 0:S  % - Reactor Vessel DP 1f.O psid PANEL K-13 (12) PORV Discharge Temperature SS- F (13) Pzr Safety Valve Discharge TemP-(F) (20) CONTAINMENT HIGH PRESS RV-1039 85 F NO RV-1040 8'5 F RV-1041 8'5 F (20) Containment High Radiation NO

SHAVPALI T S C S T AT US . P AG E PALEX 92 Time 1215 Scenario Time 0345 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 .0 MFP A Discharge Pressure T5 psig (32) 1-C BUS VOLTS 2481 Amps'ifSl MFP B Discharge Pressure T5 psig (32) 1-D BUS VOLTS ~ Ampsli)Q AFW Pump P-8C Amperes 0 AMPS AFW Discharge Pressure P-8C 7 psig C-11 BACK C-llA AFW Pump P-8A Amperes 0 AMPS

• AFW Pump P-8B Steam Pressure 0 psig (17) Containment Area Monitors AFW Discharge Pressure P-8A & P-8B T6 psig RIA-1805 .650 R/Hr Moisture SEP Drain Tank Level TI % RIA-1806 :3'50 R/Hr Condensor Hotwell Level bb % RIA-1807 :220 R/Hr Condensor Vacuum O in Hg. RIA-1808 :180 R/Hr Gland Seal Condensor Vacuum T4. 2 in Hg. (17) High Range ContaTniiient Monitors Atmospheric Dump Valves TmmT RIA-2321 1 R/Hr AFW Pump P-8A OFF P-8B OFF P-8C art
• RIA-2322 T R/Hr Heater Drain Pump- P-lOA Off' P-lOB ITT (19) Containment Hydrogen Concentration Condensate Pump P-2A Off' P-2B Off' AI-2401R .63  %

AI-2401L -:6'l  % C-11 (30) Main Steam Line Gamma RIA-2324 39.0E+03CPM (31) AFW FLOW TO SGA RIA-2323 42.0E+03CPM FROM PBA, B 0 From P-8C 0 gpm (31) AFW FLOW TO SGB EQUIPMENT STATUS: FROM P-8A&B 0 From P-8C O gpm Condensor Vacuum (R) TI IN HG. 1. SIGNIFICANT EQUIP OUTAGES PCP A Leak-off Flow (R) :a (INOPERABLE EQUIPMENT) PCP B Leak-off Flow (R) -:-s 2. SURVEILLANCE DUE/PROGRESS PCP C Leak-off Flow (R) -:-s 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off Flow (R) -:-s OR OUTAGES

SHAVPAll PALEX 92 TSC

• S T AT US P AG E
• Time 1215 Scenario Time 0345 Message # 22 142 Time Jump - Scenario Time Jump -

C-08 C-02 SW Pumps P-7A ON P-78 ON P-7C ON (10) VCT Temp 84 F CCW Pumps P-52A UN P-528 OR P-52C UN (10) VCT Pressure 'SJ psi FPC Pumps P-51A UN P-518 MF (10) VCT Level 87 % PCP Control Bleedoff Pressure bl psig CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow 21 gpm (26) Charging Flow 126 gpm VIA ON V2A ON V3A ON V4A ON (9) Quench Tank Temp 102' F VIB otF V2B OFF V3B MF V4B OFF (9) Quench TANK Pressure T psig (9) Quench TANK Level ~  % C-03 (7) Pressurizer Pressure (R) %0 psia

                                               .                     (8) PZR Level (R)      LT0102A         33 TI . %

(23) H~SI Pumps P-66A OFF P-668 ON LT0103

 .(25) LPSI Pumps           P-67A 0Jr P-678 OR                    (12) PORV       PRV-1042A CLOSED    10438 'CLOSED (18) Containment Spray Pumps--                                 (12) BLOCK MOV-1042A OPEN           1043A  OPEN P-54A OFF P-548 OFF P-54C OFF                             CHARGING PUMPS (27) HPSIA, ~PSIA-;--s-PRAY A SUCTION                                          P55A ON P55B ON P55C ON
         .       CV-3057 (SIRWT)         CV-3030 (Sump)              (6) PCPS     PSOA OFF PSOB OFF PSOC OFF PSOD OFF OPEN                   CLOSED                   . PZR HTR AMPS ---rc15 0 ---LCC 16*~

(I) PCS TAVE (R) LOOPI-(TR-0111) 410 F LOOP2 (TR-0121) l85 F C-02 (25) REACTOR POWER LEVEL Nil .72E+Ol cps NI3 .71E-08 % Nl7 .65E-Ol  % Intermediate Press Letdown Temp 82 F NI2 .72E+Ol cps NI4 .71E-OB % NIB .66E-Ol  % Charging Line Temperature 119 F NI-05 .41E-Ol % Nl-09 Letdown Line Temp n2 F NI-06 .40E-Ol % Nl-10 SOCS from PCS (R) Bl F SOCS to PCS (R) 'ST F PIP (DEMAND LOG+CONSTANT-;-R:OD, OR FLUX/TEMP) Gross MW 0 Net MW ~4 (28) *control Rod PositTOn GPl -0 GP2 0 GP3 0 GP4 0 GP6(A) 0 GP7(B) O Stuck Rods NONE <optional># 0 Core Exit Temp 421 F

SHAVPALI Time 1230 TSC Scenario Time 0400 S T AT US P AG E Message # 23 PALEX 92 140 Time Jump - - Scenario Time Jump - - C-13 C-12 PCP Curreilf"1Amps) Condensate Storage Tank Level T-2 55 % P-50A 0 P-50B 0 Instrument Air Pressure Tllo psig P-50C TI P-50D TI (15) Containment Building Pressure n-- psig (6) PCS Flow (16) S/G A Compartment Temperature ~2 F (3) Thot (F) Loop 1 414 F

 . S/G A COMPARTMENT Humidity        ~     %                                     Loop 2      403" F (16) S/G B Compartment Temperature   Bf    F                     (2) Tcold (F) Loop IA       m    F S/G B Humidity                  '54   %                                     Loop 2A     w    F (16) Dome Temperature                ~     F                                     Loop IB     w    F

.(11) SIRW Tank Level iS  % Loop 2B m F (15) WR Containment Pressure (R) 14 psia (5) Subcooling m F 600 PSIA (14) Containment Sump Level TO  % (7) PCS WR Pressure (R) m PSIA (14) Containment Water Level (R) O  % (7) PCS NR Pressure (R) 600 PSIA (22) SI Tank Level (%) (30) S/G A LEVEL WR 92  % A 52 B 48 C 48 D 48 (30) S/G ~ LEVEL (R) ~  % SI Tan~Pressure-C-psig) (30) S/G A PRESS Ilo psi a A 232 B 227 C 229 D 233 S/G A STM FLW (R) T Xl0**6 PPH (21) SIAS Alarm YES S/G A FD FLW (R) *o Xl0**6 PPH (30) S/G B LEVEL WR Too  % C-12 (30) S/G B LEVEL (R) TOO  %* (30) S/G B PRESS 770 psi a Concentrated Boric Acid Tank Levels S/G B STM FLW (R) T Xl0**6 PPH T53A 6.8  % S/G B FD FLW (R) 0 Xl0**6 PPH T53B 0:S  % Reactor Vessel DP S:O psid PANEL K-13 (12) PORV Discharge Temperature SS- F (13) Pzr Safety Valve Discharge Tem~(F) (20) CONTAINMENT HIGH PRESS RV-1039 85 F NO RV-1040 lJ'5 F RV-1041 lJ'5 F (20) Containment High Radiation NO

SHAVPALI PALEX 92 TSC

• S T AT US P AGE
• Time 1230 Scenario Time 0400 .

Message # -23 141 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 TS psig (32) 1-C BUS VOLTS 2481 Amps451 MFP B Discharge Pressure TS psig (32) 1-D BUS VOLTS 2482 Amps360 AFW Pump P-8C Amperes 0 AMPS AFW Discharge Pressure P-8C 7 psig C-11 BACK C-llA AFW Pump P-8A Amperes 0 AMPS AFW Pump P-88 Steam Pressure 0 psig (17) Containment Area Monitors AFW Discharge Pressure P-8A & P-88 T6 psig RIA-1805 .650 R/Hr Moisture SEP Drain Tank Level n % RIA-1806 :J50 R/Hr Condenser Hotwell Level 6b % RIA-1807 -:-220 R/Hr Condenser Vacuum .er in Hg. RIA-1808 -:180 R/Hr Gland Seal Condenser Vacuum T4.2 in Hg. (17) High Range Conta"'filiiient Monitors Atmospheric Dump Valves TmmT RIA-2321 1 R/Hr AFW Pump P-8A OFF P-88 OFF P-8C OF't RIA-2322 I R/Hr Heater Drain Pump- P*-IOA orF' P-IOB ITT (19) Containment Hydrogen Concentration Condensate Pump P-2A ITT P-2B ITT AI-2401R .67  % AI-2401L -:67  % C-11 (30) Main Steam Line Gamma RIA-2324 39.0E+03CPM (31) AFW FLOW TO SGA RIA-2323 42.0E+03CPM FROM P8A, B 0 From P-8C O gpm (31) AFW FLOW TO ~GB EQUIPMENT STATUS: FROM P-8A&B 0 From P-8C O gpm Condenser Vacuum (R) 0 IN HG. 1. SIGNIFICANT EQUIP OUTAGES PCP A Leak-off Flow (R) :a

g (INOPERABLE EQUIPMENT)

PCP B Leak-off Flow (R) 2. SURVEILLANCE DUE/PROGRESS PCP C Leak-off Flow (R) :g 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off Flow (R) :g OR OUTAGES

SHAVPAll PALEX 92 TSC

• S T AT US P AGE
• Time 1230 Scenario Time 0400 .Message # 23 142 Time Jump - Scenario Time Jump -

C-08 C-02 SW Pumps P-7A ON P-78 ON P-7C ON (10) VCT Temp 84 F CCW Pumps P-52A OR P-528 OR P-52C OR (10) VCT Pressur*e 'SJ psi FPC Pumps P-51A OR P-518 OFF (10) VCT Level 87 % PCP Control 8leedoff Pressure 6I psig CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow 2l gpm (26) Charging Flow 126 gpm VIA ON V2A ON V3A ON V4A ON (9) Quench Tank Temp ~ F Vl8 OFF V28 OFF V38 otF V48 OFF (9) Quench TANK Pressure -:Y- psig (9) Quench TANK Level 6il % C-03 (7) Pressurizer Pressure (R) 9ilo psia

                                               '                   (8) PZR Level (R)        LT0102A         Jr- %

(23) HPSI Pumps P-66A OFF P-668 ON l T0103 3T %

 .(25) LPSI Pumps          P-67A fir P-678 OR                     (12) PORV     PRV-1042A CLOSED 10438 ~ED
. (18) Containment Spray Pumps--                                  (12) BLOCK MOV-1042A OPEN           1043A OPEN P-54A OFF P-548 OFF P-54C OFF                           CHARGING PUMPS (27) HPSIA, LPSIA-;-5PRAY A SUCTION                                          P55A ON P558 ON P55C ON CV-3057 (SIRWT)         CV-3030 (Sump)            (6) PCPS     P50A OFF P508 Off PSOC otF PSOD OFF OPEN                    CLOSED                       PZR HTR AMPS LC15 0 -LCC 16*0 (1) PCS TAVE (R) LOOPI-(TR-0111) 405 F LOOP2 (TR-0121) 380 F C-02                                     (25) REACTOR POWER LEVEL Nil .72E+Ol cps Nl3 .71E-08 % Nl7 .6SE-Ol          %

Intermediate Press Letdown Temp 82 F Nl2 .72E+OI cps Nl4 .71E-08 % NIB .66E-Ol  % Charging Line Temperature Il9 F Nl-05 .41E-Ol % Nl-09 Letdown Line Temp n2 F Nl-06 .40E-Ol % Nl-10 SOCS from PCS (R) nl F SOCS to PCS (R) 'B"I F PIP (DEMAND LOG+CO~STANT-;""'ROD, OR FLUX/TEMP) Gross MW

• 0 Net MW 74 (28) Control Rod PositTOn GPI 0 GP2 0 GP3 0 GP4 0 GP6(A) O GP7(8) O Stuck Rods NONE <optional># O Core Exit Temp - 416 F

SHAVPALI Time I245 TSC Scenario Time 04I5 S T AT US P AGE Message # 24 I40 PALEX 92

.Time Jump - -              Scenario Time Jump - -

C-13 C-12 PCP Curreiif"1Amps) Condensate Storage Tank Level T-2 55 % P-50A 0 P-50B 0 Instrument Air Pressure TOO psig P-50C -0 P-50D O

*(I5) Containment Building Pressure    0-- psig                     (6) PCS Flow (I6) S/G A Compartment Temperature    ~2      F                    (3) Thot (F) Loop I          409   F S/G A COMPARTMENT Humidity      'S'il %                                      Loop 2      m      F (I6) S/G B Compartment Temperature    Bf F                         (2) Tcold (F) Loop IA       m      F S/G B Humidity                  'S'il %                                      loop 2A     m      F (I6) Dome Temperature                 84 F                                         loop IB     !9o    F (II) SIRW Tank Level                  7b %                                         Loop 28      35..1 F (I5) WR Containment Pressure (R)      14 psia                      (5) Subcooling              m      F 660 PSIA (I4) Containment Sump Level           10      %                    (7) PCS WR Pressure (R) 920        PSIA (I4) Containment Water Level (R)      0       %                    (7) PCS NR Pressure (R) 6(j(j      PSIA (22) SI Tank Level (%)                -                           (30) S/G A LEVEL WR          m-     %

A 52 B 48 C 48 D 48 (30) S/G A LEVEL (R) 91  % SI Tan"l<"Pressure-rpsig) (30) S/G A PRESS no psi a A 232 B 227 C 229 D 233 S/G A STM FLW (R) T XI0**6 PPH . (2I) SIAS Alarm - YES S/G A FD FLW (R) *0 XI0**6 PPH (30) S/G B LEVEL WR Too  % C-12 (30) S/G B LEVEL (R) TOO  %* (30) S/G B PRESS """SO psi a Concentrated Boric Acid Tank Levels S/G B STM FLW (R) T XI0**6 PPH T53A 6.8  % S/G B FD FLW (R) 0 XI0**6 PPH T53B b:'iJ  % Reactor Vessel DP lf.O' psid PANEL K-13 (I2) PORV Discharge Temperature 85'""" F (13) Pzr Safety Valve Discharge Temp(F) (20) CONTAINMENT HIGH PRESS RV-I039 85 F NO RV-I040 gs F RV-I04I gs F (20) Containment High Radiation NO

SHAVPALI PALEX 92 TSC

• S T AT US P AG E *

       *Time 1245              Scenario Time 0415               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 .0 MFP A Discharge Pressure TS psig (32) 1-C BUS VOLTS 2481 Amps451 MFP 8 Discharge Pressure TS psig (32) 1-D BUS VOLTS 2482 Amps!SO AFW Pump P-8C Amperes 0 AMPS AFW Discharge Pressure P-8C 7

                                            . ()

psig C-11 BACK C- llA

• AFW Pump P-8A Amperes AMPS AFW Pump P-8B Steam Pressure () psig (17) Containment Area Monitors AFW Discharge Pressure P-8A & P-88 T6 psig RIA-1805 .650 R/Hr Moisture SEP Drain Tank Level TI % RIA-1806 -:150 R/Hr Condensor Hotwell Level bb % RIA-1807 :220 R/Hr Condensor Vacuum . 0 in Hg. RIA-1808 .180 R/Hr Gland Seal Condensor Vacuum 14. 2 in Hg. (17) High Range ContaTniiient Monitors Atmospheric Dump Valves TmmT RIA-2321 1 R/Hr

. AFW Pump P-8A OFF P-8B OFF P-8C art RIA-2322 T R/Hr Heater. Drain Pump- P-lOA OFT P-108 OFT (19) Containment Hydrogen Concentration Condensate Pump P-2A OFT P-28 OFT AI-2401R . 71  % Al-2401L :7T  % C-11 (30) Main Steam Line Gamma RIA-2324 39.0E+03CPM (31) AFW FLOW TO SGA RIA-2323 42.0E+03CPM FROM P8A, B 0 From P-8C 0 gpm (31) AFW FLOW TO ~GB EQUIPMENT STATUS: FROM P-8A&8 0 From P-8C 0 gpm Condensor Vacuum (R) 0 IN HG. 1. SIGNIFICANT EQUIP OUTAGES PCP A Leak-off Flow (R) :8 (INOPERABLE EQUIPMENT) PCP B Leak-off Flow (R)  :-s 2. SURVEILLANCE DUE/PROGRESS PCP C Leak-off Flow (R)  :-s 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off Flow (R)  :-s OR OUTAGES

SHAVPAll PALEX 92 TSC

• S T AT US P AGE
• Time 1245 Scenario Time 0415 Message # 24 142

  *Time Jump -                Scenario Time Jump -

C-08 C-02 SW Pumps P-7A ON P-78 ON P-7C ON (10) VCT Temp 84 F CCW Pumps P-52A OR P-528 OR P-52C OR (10) VCT Pressure 'SJ psi FPC Pumps P-51A OR P-518 OF'F (10) VCT Level 87 % PCP Control Bleedoff Pressure 6T psig CONTAINMENT COOLER RECIRC FANS (26) letdown Flow 2l gpm (26) Charging Flow T26 gpm VIA ON V2A ON V3A ON V4A ON (9) Quench Tank Temp 102 F VlB OF"F V2B otF V3B OFF V4B otf (9) Quench TANK Pressure  :-Y- psig (9) Quench TANK Level ~  % C-03 (7) Pressurizer Pressure (R) 920 psia (8) PZR level (R) LT0102A ~ % (23) HPSI Pumps P-66A OFF P-668 ON LT0103 3:"l:)  % (25) LPSI Pumps P-67A 'Ofir P-678 OR (12) PORV PRV-1042A CLOSED 10438 CIO"SED (18) Containment Spray Pumps-- (12) BLOCK MOV-1042A OPEN 1043A OPEN P-54A OFF P-548 OFF P-54C OFF CHARGING PUMPS

 .(27) HPSIA; LPSIA-;-""SPRAY A SUCTION                                          P55A ON P55B ON P55C ON CV-3057 (SIRWT)          CV-3030 (Sump)            (6) PCPS      P50A OfF P50B otF P50C OFF P50D OFF OPEN                     CLOSED                        PZR HTR AMPS ---rc15 0 ~LCC 16 .cr-( 1) PCS TAVE (R) LOOPl-(TR-0111) 400 F LOOP2 (TR-0121) 315 F C-02                                     (25) REACTOR POWER LEVEL Nil .72E+Ol cps NI3 .71E-08 % NI7 .65E-Ol           %

Intermediate Press letdown Temp 82 F NI2 .72E+Ol cps NI4 .71E-08 % NIB .66E-Ol  % Charging Line Temperature T2'9 F Nl-05 .41E-Ol % NI-09 Letdown Line Temp 82 F Nl-06 .40E-Ol % NI~lO sacs from PCS (R) 1Jl F sacs to PCS (R) BT F PIP (DEMAND LOG+CONSTANT:---ROD, OR FLUX/TEMP) Gross MW O Net MW ~4 (28) Control Rod PositTOn GPl 0 GP2 . 0 GP3 0 GP4 0 GP6(A) TI GP7(B) TI Stuck Rods NONE <optional># O Core Exit Temp 411 F

SHAVPALI Time 1300 TSC Scenario Time 0430 S T AT US P AGE Message # 25 PALEX 92 I40 Time Jump - - Scenario Time Jump - - C-13 C-12 PCP Curreiif"1Amps) Condensate Storage Tank Level T-2 50  % P-50A 0 P-50B 743 Instrument Air Pressure TOO psig P-50C 75I P-50D 0

 '(I5) Containment Building Pressure    O       psig                  (6) PCS Flow                    -

(I6) S/G A Compartment Temperature 82 F (3) Thot (F) Loop I 256 F S/G A COMPARTMENT Hurni di ty '51 . % Loop 2 '2"50 F (I6) S/G B Compartment Temperature BI F (2) Tcold (F) Loop IA 255 F S/G B Humidity '51  % Loop 2A '2"50 F (I6) Dome Temperature 84 F Loop IB 255 F (II) SIRW Tank Level 70  % Loop 2B 25b F (I5) WR Containment Pressure (R) T4 psia (5) Subcooling 149 F 231 PSIA (I4) Containment Sump Level TO  % (7) PCS WR Pressure (R) 202' PSI~ (I4) Containment Water Level (R} 0- 3 (7) PCS NR Pressure (R) 202' PSIA (22) SI Tank Level (%) - (30) S/G A LEVEL WR SS- % A 52 B 48 C 48 D 48 (30) S/G A LEVEL (R) 85 % SI Tan"k"Pressure~psig) (30) S/G A PRESS j5 psia A 232 B 227 C 229 D 233 S/G A STM FLW (R) :2 XI0**6 PPH . (2I) SIAS Ala rm ..tJ.Q S/G A FD FLW (R) 0- XI0**6 PPH (30) S/G B LEVEL WR Too % C-12 (30) S/G B LEVEL (R) TOO %* (30) S/G B PRESS ifs- psia Concentrated Boric Acid Tank Levels S/G B STM FLW (R)  :"5 XI0**6 PPH T53A 6.8  % S/G B FD FLW (R) 0- XI0**6 PPH T53B 0':"8  % Reactor Vessel DP 12:"7 psid PANEL K-13 (I2) PORV Discharge Temperature SS-- F (13) Pzr Safety Valve Discharge TemP-(F) (20) CONTAINMENT HIGH PRESS RV-1039 85 F NO RV-1040 BS' F RV-1041 BS' F (20) Containment High Radiation NO

SHAVPALI PALEX 92 TSC

• S T AT US P AGE
• Time 1300 Scenario Time 0430 Message # 25 141

. Ti me 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 T5 psig (32) 1-C BUS VOLTS 2481 Amps451 MFP B Discharge Pressure T5 psig (32) 1-D BUS VOLTS 2482 Amps360 AFW Pump P-8C Amperes 0 AMPS AFW Discharge Pressure P-8C 7 psig C-11 BACK C-llA AFW Pump P-8A Amperes .0 AMPS AFW Pump P-8B Steam Pressure O psig (17) Containment Area Monitors AFW Discharge Pressure P-8A & P-88 T6 psig RIA-1805 .650 R/Hr Moisture SEP Drain Tank Level TI % RIA-1806 :J!O R/Hr Condensor Hotwell Level 66 % RIA-1807 :220 R/Hr Condensor Vacuum 0 in Hg. RIA-1808 :IBO R/Hr Gland Seal Condensor Vacuum 14. 2 in Hg. (17) High Range Conta-:rnilient Monitors Atmospheric Dump Valves CTO"SED RIA-2321 1 R/Hr

*AFW Pump      P-8A OFF     P-88 OFF    P-8C OFF                          RIA-2322        l            R/Hr Heater Drain Pump-       P-IOA OFT P-108 OFT                      (19) Containment Hydrogen Concentration Condensate Pump            P-2A OFT    P-2B OFT                          AI-2401R         .74       %

AI-2401L :7il  % C-11 (30) Main Steam Line Gamma RIA-2324 39.0E+03CPM (31) AFW FLOW TO SGA RIA-2323 42.0E+03CPM FROM P8A, B 0 From P-8C 0 gpm (JI) AFW FLOW TO ~GB 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)  :-4 (INOPERABLE EQUIPMENT) PCP B Leak-off Flow (R) :if 2. SURVEILLANCE DUE/PROGRESS PCP C Leak-off Flow (R) :if 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off Flow (R) :if OR OUTAGES

SHAVPALl PALEX 92 TSC

• S T AT US P AGE
• Time 1300 Scenario Time 0430 Message # 25 142 Time Jump - Scenario Time Jump C-08 C-02 SW Pumps P-7A ON P-78 ON P-7C STBV (10) VCT Temp 95 F CCW Pumps P-52A UR P-528 UR P-52C 'STBY (10) VCT Pressure '50 psi FPC Pumps P-51A UR P-518 OFF (10) VCT Level Bl %

PCP Control Bleedoff Pressure !2 psig CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow ~ gpm (26) Charging Flow Bl gpm VIA ON V2A ON V3A ON V4A ON (9) Quench Tank Temp 84 F VlB UR V2B UR V3B UR V4B UR (9) Quench TANK Pressure ;r- psig (9) Quench TANK Level 78 % C-03 (7) Pressurizer Pressure (R) 262 psia (8) PZR Level (R) LT0102A 95'""" % (23) HPSI Pumps P-66A -OFF P-668 OFF LT0103 9S". % (25) LPSI Pumps P-67A O"fr P-678 UF'F (12) PORV PRV-1042A CLOSED 10438 ~ED (18) Containment Spray Pumps--- (12) BLOCK MOV-1042A OPEN 1043A OPEN P-54A OFF P-548 OFF P-54C OFF CHARGING PUMPS (27) HPSIA, LPSIA-;-""'SPRAV A SUCTION P55A ON P55B ON P55C OFF CV-3057 (SIRWT) CV-3030 (Sump) (6) PCPS P50A UFF P50B UR P50C OW- P500 OFF

• OPEN CLOSED PZR HTR AMPS ---rc15 0 --- LCC 16 er (1) PCS TAVE (R) LOOPI-(TR-0111) ~56 F

                                                                           .            LOOP2 (TR-0121) "2"5b F C-02                                     (25) REACTOR POWER LEVEL Nil .72E+Ol cps NI3 .71E-08 % NI7 .65E-Ol %

Intermediate Press Letdown Temp 111 F NI2 .72E+Ol cps NI4 .71E-08 % NIB .43E-Ol % Charging Line Temperature ill F Nl-05 .41E-Ol % NI-09 Letdown Line Temp ill F NI-06 .45E-Ol % Nl-10 SOCS from PCS (R) BO F SOCS to PCS (R) fil F PIP (DEMAND LOG+CONSTANT~OD, OR FLUX/TEMP) Gross MW 0 Net MW 74 (28) Control Rod PositTOn GPl 0 GP2 0 GP3 0 GP4 0 GP6(A) n GP7(B) n Stuck Rods NONE <optional># o Core Exit Temp ~63.6F

SHAVPALI Time 1315 TSC Scenario Time 0445 S T AT US P AGE Message # 26 140

                                                                                                          *PALEX 92 Time Jump                  Scenario Time Jump - -

C-13 C-12 PCP Curreilfl"Amps) Condensate Storage Tank Level T-2 50  % P-50A 0 P-508 743 Instrument Air Pressure TOO psig P-50C 751 P-50D 0--- (15) Containment Building Pressure cr- psig (6) PCS Flow (16) S/G A Compartment Temperature 82 F (3) That (F) Loop I 246 F S/G A COMPARTMENT Humidity 'S4  % Loop 2 240 F

• (16) S/G B Compartment Temperature BI F (2) Tcold (F) Loop IA 245 F S/G B Humidity 'S4  % Loop 2A 240 F (16) Dome Temperature 84 F Loop IB 245 F (11) SIRW Tank Level 70  % Loop 28 24b F

*(15) WR Containment Pressure (R)      14       psi a                (5) Subcooling             Tifg F 231    PSIA (14) Containment Sump Level           TO       %                    (7) PCS WR Pressure (R) ill PSI~

(14) Containment Water level (R) 0- ,% (7) PCS NR Pressure. (R) ill PSIA (22) SI Tank Level (%) (30) S/G A LEVEL WR SS- % A 52 B 48 c 48 D 48 (30) S/G A LEVEL (R) 85 % SI Tan~Pressure-i-psig) (30) S/G A PRESS 35 psia A 232 B 227 C 229 D 233 S/G A STM FLW (R) :2 Xl0**6 PPH (21) SIAS Ala rm - No: S/G A FD FLW (R) 0- Xl0**6 PPH (30) S/G B LEVEL WR Too % C-12 (30) S/G B LEVEL (R) TOO %* (30) S/G B PRESS 4s- psia Concentrated Boric Acid Tank Levels S/G B STM FLW (R) -:-5 Xl0**6 PPH T53A 6.8  % S/G B FD FLW (R) 0- Xl0**6 PPH T53B 0:-S  % Reactor Vessel DP 1'2:'"7 psid PANEL K-13 (12) PORV Discharge Temperature SS-- F (13) Pzr Safety Valve Discharge Temj)"(F) (20) CONTAINMENT HIGH PRESS RV-1039 85 F NO RV-1040 'S'S F RV-1041 HS F (20) Containment High Radiation NO

SHAVPAll PALEX 92 TSC

• S T AT US P AGE
• Time 1315 Scenario Time 0445 Message # 26 141 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 TS psig (32) 1-C BUS VOLTS '2481 Amps451 MFP B Discharge Pressure TS psig (32) 1-D BUS VOLTS ~ Amps3b0 AFW Pump P-8C Amperes 0 AMPS AFW Discharge Pressure P-8C 7 psig C-11 BACK C-llA AFW Pump P-8A Amperes 0 AMPS AFW Pump P-8B Steam Pressure o psig (17) Containment Area Monitors AFW Discharge Pressure P-8A & P-88 T6 psig RIA-1805 .650 R/Hr Moisture SEP Drain Tank Level TI  % RIA-1806 :350 R/Hr Condensor Hotwell Level 66  % RIA-1807 -:-220 R/Hr

*Condensor Vacuum                           O        in Hg.              RIA-1808        -:180         R/Hr Gland Seal Condensor Vacuum                T4.2 in Hg.           (17) High Range Conta"l'"niiient Monitors Atmospheric Dump Valves                    ctTISED                      RIA-2321        1             R/Hr

-AFW Pump P-8A OFF P-8B OFF P-8C OFF RIA-2322 T R/Hr Heater Drain Pump- P-lOA OFT P-lOB ITT (19) Containment*Hydrogen Concentration Condensate Pump P-2A OFT P-2B ITT AI-2401R . 78  % AI-240ll -:-7S  % C-11 (30) Main Steam line Gamma RIA-2324 39.0E+03CPM (31) AFW FLOW TO SGA RIA-2323

• 42.0E+03CPM FROM P8A, B 0 From P-8C 0 gpm (31) AFW FLOW TO ~GB 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)  :-4 (INOPERABLE EQUIPMENT) PCP B leak-off Flow (R)  :-if 2. SURVEILLANCE DUE/PROGRESS PCP C leak-off Flow (R)  :-if 3. ABNORMAL ELECTRICAL LINEUPS PCP D leak-off Flow (R)  :-if OR OUTAGES

SHAVPALI PALEX 92 TSC

• S T A T US P AGE
• Time 1315 Scenario Time 0445 Message # 26 142 Time Jump - Scenario Time Jump -

C-08 C-02 SW Pumps P-7A ON P-78 ON P-7C STBY (10) VCT Temp 95 F CCW Pumps P-52A OR P-528 OR P-52C STBY (10) VCT Pressure 'SCJ psi FPC Pumps P-51A OR P-518 otF (10) VCT.Level n"l % PCP Control Bleedoff Pressure 'S'2' psig CONTAlNMENT COOLER RECIRC FANS (26) Letdown Flow 69 gpm (26) Charging Flow nJ gpm VIA ON V2A ON V3A ON V4A ON (9) Quench Tank Temp ~ F VlB OR . V2B OR V3B OR V4B OR (9) Quench TANK Pressure ~ psig (9) Quench TANK level 78 % C-03 (7) Pressurizer Pressure {R) 202 psia (8) PZR Level {R) LT0102A 95""" % . (23) HPSI Pumps P-66A OFF P-668 OFF LT0103 9S" % (25) LPSI Pumps P-67A ~ P-678 'O'FT (12) PORV PRV-1042A CLOSED 10438 t'IOSED (18) Containment Spray Pumps-- (12) BLOCK MOV-1042A OPEN 1043A OPEN P-54A OFF P-548 OFF P-54C OFF CHARGING PUMPS (27) HPSIA, LPSIA~PRAY A SUCTION P55A ON P55B ON P55C OFF CV-3057 (SIRWT) CV-3030 (Sump) (6) PCPS P50A OFF P50B OR P50C ~ P500 OFF OPEN CLOSED PZR HTR AMPS ---rc15 0 -- LCC }6.tr (1) PCS TAVE (R) LOOPl-{TR-0111) !46 F LOOP2 (TR-0121) !4b F C-02 (25) REACTOR POWER LEVEL Nil .72E+Ol cps Nl3 .71E-08 % NI7 .65E-Ol  % Intermediate Press Letdown Temp 111 F Nl2 .72E+Ol cps NI4 .71E-08 % NIB .43E-Ol  % Charging Line Temperature ill F Nl-05 .41E-Ol % NI-09 Letdown Line Temp ill F Nl-06 .45E-Ol % NI-10 SOCS from PCS (R) m F SOCS to PCS (R) ~ F PIP {DEMAND LOG+CONSTANT-;-R:OD, OR FLUX/TEMP) Gross MW 0 Net MW ~4 (28) Control Rod PositTOn GPI 0 GP2 0 GP3 0 GP4 0 GP6{A) 0 GP7{B) 0 . Stuck Rods NONE <optional># O Core Exit Temp !52 F

CFMS RAD DATA

SCCHRRIO llHC: - 00 ~ 0 RHDIULOGICRL I

                                                                **                ' I\

Rill***2327 llHC: 0800 fUCL HRHDLIHG RRCRS DHtkUP SI RCIC RIR-2318 ._._o>E....Jo ....S--'-'-._ _ CPH

• • LIQUID' RROIAllOH

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    . 00         CPH RIA-1005               , oi...o             Rl'llR          CIJHll OIT r.ns RHO UHSIC DISCHG                                                                     --

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                                                                                                    *(( SC  RAO
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                                            ----1'r----- Rl'llR                             --~

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 *r*n1LCO fU[L                                                                              '--"

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 *OCCROC OCPCHOCHI                                                                         S[P SOU111 OH CR SUllCH                                                                              7-313            (), -JL      tlR/llR PUSl1 I.OH

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   *CoHPOHCHf COOLIHG UAICR 0915                                                                    tUHIROL RO,. RAO              2310 (fY        CPH                                                          HOH         f2

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   *Occnoc OCPCHOCHI                                                             SCP SOUlll OH CR SUlltH PU511 IUH                                                                     2313              ().1L      tlRl'HR

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     *COHPOHCHJ COOLIHG unr~R 09;.ft>             cm                                                      tUHIROL R HOH         f.
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     ---.*-...::11~.:;..:0=0__ CPH RIR-1805         0~020         Rl'HR            conn orr       GAS RllOUHSIC OIStHG                                                            ~

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                                                                       ~-                               / iJ. l-crtt 1019                                                                        0631 81'0        [Pft ds/a,t1
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   *H.1 HIHG BRSIH                                                              -
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            .:l 3!    [Ptt HRIH SICRM B 2323                                                           Slr HORlll is=         CPH                                                     !;709             0. eP HRl'llR
   *DCCRDC OCPCHOCHI                                                           SCP SOUlll I   OH CR SUllCH                                                                7-31 3            (), 1L   tlR/llR PUSl1 IOH

SCCHRRIO I IHC: fl//j-: RQOIULDGICHL

• RIR-*232f; Rill**-2327 ta. 0

                                                                                                          --=--"-*_z..__

t. M~ 11Hc: D!'/L URCkUP SIRCK .S fUCL HAHDLIHG RRCRS RHl-2~18 0 0 Crt1

    *~lbUIO        RRDIRllOH HOHllORS                 HOH 1. OOS              HRl'HR                      RI R-231 9 -~0.=....:0::;;....;;::S____ Cf>l1 HUH Z    00.$           HR.IHR
     *CoHPOHCHI COOLIHG URICR 0915                                                                             CUHIROL RO~ RAD                     2310 I   f"1?      CPH                                                        HOH        f) * /                  HR lllR SCRUICC URICR 0033 <eoo CUHIAltlttCHl ISOLRllOH             -

CPH l).oi-o RIR-1005 R.tllR conn nrr r.ns RHO unstc DISCHG -- 1019 RIR-1806 ().111/ Rl'HR 0631 ~ .).._-Z.- Crt1 RIA-1807 . IJ. / '-0 Rl'HR *Rno unsrc PLCHl.11 SIH GCH OUJUDOUH 0707

                 -~

{-#0 CPH RIA-1808 11. oro R.IHR -,. 110, lt,o Cl1tt Hi RAH&C I R.lllR

      *HIHIHG DRSIH 111 RllHGC R L

I Rl'llR

                                                                                                     *CCSC RRU
                                                                                                                              /).0.

1323 11/IJ CM1

                 />:0            CPH 1.
      *rnILCD fU[L ozozn
          *      . 10         Clttt    l-60U L        '.
                                                              ,()

DIRIY URSIC DRAIH lAHKS

                                                                       *1.                    'I
                                                                                              ~
                                                                                                     *UCSC RAD It/I Rm unsrc urn1 1/-oo      f:rt1 Hn1*n SICIW1 R 2321                 l-60C L             ,.0       %              -...                                       l<

1) CPH 51// f.PN 2323 srr HORIH

.I [Pt1  !;709 Q,;_P HR.tllR

      *nrcnoc OCPCHDCHI                                                                      SCP SOUllf OH CR SUllCH                                                                           7-ll l            (), fL           tlRlllR PUSlllUH

SCCHARIO llHC: 0110 RDDIDLO&ICDL *

                                                                      .. II\

RIR-*232fj Ri n-- 2321

                                                                                                         "()
                                                                                              --=---o.;;..._._i,_,_ M~

crA um:kUP SIRC:IC ruct HRHDLIHG RRCRS Rll1-2:U8 00.S cm

   *~JQUID      RROIRllOH MOHUORS            HOH 1 . 00$           HR.lllR                    RI R-231 9 __t>..;:....;O;....;;:S........_ _ trt1 HUH Z    00.S         HR,,HR
    *CDMPOHCHJ COOLIHG
             '.P6 I .

tUHIROL RO~ RAD 2310 UAJCR CPM HOH f) * / HR/HR StRUICC URJ[R 0033 CUHIAIRtCHI ISOLRllOH

    -----~--

C,oo CPM O. () 'l,O . R/llR RIR-1005 conn orr 1ms RllO UllSIC OISCHG ll111J RIR-1806 tJ.011 R/HR -- 0631 £..,~. Crt1 RIR-1007 *O*l2'0 R.tHR *RnD uns1c l'l[Hll1 SI H GCH BUJUOOUH o101 ~wo cm RIR-1808 IP* ()J'O R.lllR -- ltOP l/,o C:l'tt Hi RRHGC L I R/llR *CCSC RAU

     *HIHIHG DRSIH 1323                     Ill RllHGC R           I        R/llR              -
                                                                                  ~

1110 /J.O . trt1

              /J-0       CPM
                                                                                         *UCSC RRD
     *rntLCD ruct                DIRlV URSlC DRAIN 1RHKS                           ~

0202n

               .I 0      C:Pt1   l-60U l      I .  ~D          ~                 RH
                                                                                   -IJ um;rc It/I UCHI 1/-oo       f:rt1
                                                                              ~

HRIH SICnt1 R 2321 2--) tPM 1-60[ l 6"()

1. 51-// l~ l:Pl1 HRIH s~ 0 z:~ Slr HORlll

                                                                                 !i709            (), >:,l' HR/HR
     *OCCRO[ OCPCHDCHI                                                           SlP SOUlll DH CR SUllCH PUSll IOH      .

2313 (). 6JL t1R1HR

SCCHRRIO I IHC: llHC:

                                  .IJ.l!/J,_

f 0/ ~, RHOIULOGICRL

                                                                        *         '~

RI H*** 2 32fi __,__ _lo.::;.__0_ _ C* Rill*-2327 0° t. MRlH UACICUP 51 ff[IC rucL HRHOLIHG RRCRS Rlfl-2::110 _....,lo~oL.:s=----__ crtt

       'tIQUID RRDIRllOH
               .ffOHllORS                    HOH I     QQ.$        HRl'llR                RIH-2319         _.:...;bO::.....;::S~-- Crtl HUH Z     00.$        HR,,HR
         *Cot1POHCHI COOLIHG URICR     NC/('            CPH tUff fROL R HOH          ~*

O" RAO 2310 HR/llR SCRUICC UntCR COHIRIHHCHI ISOLRIJOH I _0_0_33__,.t,"'-o=-=-o__ cm

                                                                 ~-

I I RIR-1005 R/llR nrr RflO UHSIC DISCHG 1019 RIR-1006 l~ R/HR -- cuHH 0631 r.ns _ ___.,,....i=-=-~-- CPl1 RIA-1007 I \00 Rl'HR *Rno unsr C l'l[Hllt SIH GCH BUJUDOUH ... i 01~1 ~fo [Pl1 RIR-1808 ll-0 Rl'llR

                                                                                     --    If OP
                                                                                                                          /t,O      Cl'tt Hi RRHGC   L            l    Rl'llR                    *((5 C   RAU
          *H.1 HIHG BRSIH                                                                  --
                                                                                            ~

1323 Ill RllHGC R I Rl'llR 11/D /J.0 . CM1

                   /J-0            CPH
          *rn1 Leo run, 0202A        711
                         * * *     [PH DIRIV I-GOU l unstc I.
                                                                 ,/)

DRRIH IRHkS

                                                                                            ~
                                                                                                     *UC SC RRD It/I RHI UflSf C UCHI 1/-oo      1: rt1 HOJH    Sf Cntt    A 2321             1-60[ l          l"Q       %           --             Sri/                   1<      [1'11
                       '1vO        CPl1 ttAIH SICRt B           232~                                                     Slr HORf 11 1--too           CPl1                                                    6709               o.;,'I HR/HR
          *DCCHOC OCPCHOCHI                                                                SCP SOUlll I    UH CR SUI I CH                                                                   7-ll l              (), ~L     tlR.tHR PUSlllOH

t-a*. c~I RIR-*23Zfj SCCHRRIO l IHC: 0 2.UO RRDIULOGICRL "

                                                                            "       Rill . *2327          o.z..

llHC: /0 J0 rUCL HRHDLIHG RRCRS URCkUP SIRf.lk' RIR-2318 ooS. CPH "tIQUIO RROIRllOH HOHllORS HOH 1. oos HR.lllR RIR-2319 oos CPH MOH Z 00.S HR-'llR

   *COHPOHCHT COOLIHG URICR 0915                                                                       tUHIROL RO" RAO            2310 CPH                                                         HOH          f2 *      ,   HR.lllR SCRUICC URICR COHIRiHMCHl ISOLRllOH 0033    C.oo         CPH RIR-1005         o. sso         R/llR RllO UHSIC OISCHG lll19                          RIR-1806          O.L~          R.IHR      -  -

coHn nr*r Gns 0631 -

                                                                                                               ~

Crtt Ii-<<.;> CPl1 '

                                                   *o. ~o RIR-1807                        R.IHR             *Rno uns1c f'LCHlfl SIH GCH OUJUOOUH 0707         fp                RIR-1808          o. lc.o       R.lllR
                                                                              ~

ltOf /t,o [1'11

        . .;ll          CPH Hi RRHGC    L           I       Rl'llR                      11((5[  RRU
   *MIKIHG'DRSIH 1323                          Ill RllHGC R          I      _ R.lllR
                                                                                     --""                     /).0 . trt1 I
             /J-0       CPH 1110 DIRlY URSIC DRRIH lRHICS                          ...     *UCSC RRD
   *rn1Lco rucL 020ZR"°7 ? 7 .

l-60U L .. £0 *1. ~IJ It/I 1/-oo trtt

• CPtl Rn um;1c urHr HRIH SICfW1 R 2321 1-60£ L ,-0  % ~

      . "'f.oo CPl1                                                                            Sri/              l<'    tf'H Mn.IH ~Oe           232~

Slr HORlll [Pl1 6709 (), >:P HR.tllR

   *nccnoc OCPCHDCHI I   OH CR SUllCH                                                                     SCP SOUlll PUSlt lUH                                                                        7-ll l            (), ~L tlR.tllR

SCCHRRIO llt1C: QJ,,../ ~ 11Hc= 1o~r RROIULOGICRL

• j ~

Rln*-*2321; Rill***2327 __,___:.__'-_O__ t

• MRlH UACkUP SI HCIC rucL HRHDLIHG RRCRS Rlll-2:118 _ _,om<...:llo.._.S.=....*_ _ crtt

'tl~UIO RHDIRllOH HOHllORS HOH I. ODS HR/HR RIR-2319 ~-=b;...;O::;,_;;;:S::;....._ _ Crt1 HUH 2 00.$ HRl'HR URICR 0/915

                ,0
*CotlPOHCHI COOLIHG CPtt CUHIROL RO" RRO HOH        ~*

2310 ttR/llR StRUICC URICR tOHIRIHttCHI ISOLRllOH _0_03_3__,,,(,r:...o=-=o__ crtt RIR-1005 o . .r~ R/llR cnHn nrr r.ns RllU UllSIC DISCHG RIR-1806 o. ~S1>. R/HR 1019 06:U _ ___,g.,....~-=Q__

             ...            CPl1 RIR-1807         o.z..*o     R.IHR               *Rno unsr C t*L£Hll1 SI t1 GCH DUftJUOUH RIR-1800          O.IC.O     Rl'llR
                                                                          .......                                        /(,O     Cl'tt 0707 ;+/ S-O               CPM                                                    If OP
 *HIHIHG DRSIH 1323 Hi RRHGC L Ill RllHGC R         I I    R/llR R.lllR
                                                                                           *((5 C 1110 RAU
                                                                                                                       /).0 .      Crt1
 -----'-~......;:0,.,____ CP11
 *f'RILCD rucL ozozn???
             *     * **     CPtt    1-60U L       I*
                                                     ,/)

DIRIY URSIC ORAIH.iAHKS

                                                              *1.
                                                                                    ~
                                                                                           *UC SC RAD
                                                                                    "' J ,,,,

Rm um;1 C UCHI 1/-oo 1:m HllIH SICIW1 A 2321

          ~C2               CPtt 1-601: L         'O        1.                           51-//                            I~    t.Pl1 HRIH SICntt D             232~                                                    Slr HORlll
       ~                    CPl1                                                   !i709              Q, >:.,l' HR/llR
 *OCCRUC OCPCHOCHI                                                                 SCP SOUlll UH CR SUllCH                                                                      7.31 l              (),'SL            tlR/llR PUSlllOH

r-*** Rlll-*232fj _ 0 c H RRDIOLOGICAL Rill**-2327 . ~. 1.- MRlH SCCHRRIO IIHC: 11ttc: LIOD ruct HHHDLIHG HRCHS DRCkUP SIHCk Rll1-2:tl0 oo.s.* CPH

• ~IQUIO RRDIRTIOH HOHllORS HOH 1. oos HRl'HR RIR-2319 _ boS CPH HUH Z 00.S HRl'HR

*COl1POHCHJ COOLIHG URI CR ,,,~         CPH                                                   CUHIROL RO" RAD         2310 HOH        /2*         HRl'llR StRUICC iJAJCR COHIAIHHCHT ISOLRJIOH           ,..

0033 C..oo CPH RIA-1005 I.lo~- Rl'llR cnHn nrr rms RllD unstc OISCHG lll19 RIR-1806 O* 1$1l Rl'HR

                                                                      --  0631               - ~ro-         CPH 81-0         CPH RIA-1807 D *. z,.~o    Rl'HR            *Rno uns1c l'LCHl11 SIH GCH OUJUDOUH 0707  2,,/Of)       CPH RIR-1800         0.110         Rl'llR       -~

ltOf /(,o Cl'tt Hi RRHGC L l Rl'llR

*HIHIHG DRSIH 1323                     111. RllHGC R          I     _ Rl'llR
                                                                           --     *CCSC RAU
                                                                                                /J.O .
        /'90        [Ptf 1110                       trt1 DIRIV UASIC DRAIH IAHkS                               *UCSC RAD
*f"RILCO rucL                                                              ~

0202'?.  ?? . [1'11 l-60U L ~/) *1. ~IJ It/I 1/-oo 1:m I* RH UflSIC UCHI

                                                                      ~

HRIH SICIW1 A 2321 "fO CPH 1-60[ L l"O  % Sri/ l~ tPl1 HAIH SICIW1 0 2323 Slr HORlll

     ??:@           CPH                                                   !i709          (),e,1/ HRl'llR
*OCCROC OCPCHOCHI                                                         SCP SOUllt UH CR SUllCH PUSll IOH                                                                 7-31 l         (), ~L  tlRl'llR

SCCHHRIO llHC: ,QZ, llHC: ///$'

                               'If RHOIULOGICRL

• II\

RIH-*232f; _._ _ Rill ..*2327 {p_o_ _ [ *

                                                                                                               '* 'Z..                 MRIH URCkUP SI RCIC rucL HRHDLIHG RRCRS                            RIH-2:110 _ _,O..__.O...._.S.=......_ _ cPt1

• ~tQUID RADIRllOH

      *HOHllORS                    HOH I. OOS             HR.lllR                     RIR-2319        _t>.:.....;O:......;;:S::--..--- CPH HUH 2    00.$          HRl'llR
*COHPOHCHI COOLIHG URICR 0915
           /,0           CPH CUftlROL R HOH         ~*

or RAD 2310 HRl'llR SCRUICC UHICR 0 03 3 COHIRIR1CHI ISOLRllOH _ _ _ _C.__..o'--"o__ cr11 RIR-1005 IJ *. (,~ Rl'llR cuHn nrr GAS RUD UHSIC OISCHG 1tl1CJ RIR-1006 Q!'I~ R.tHR 0631 (, ,s-'.b. CPl1 RIR-1007 o. z..z_.o R.tHR *Rno uns1 C f'LCHll1 SI H GCH DUJUOOUH t!J. lt'O 0707 4 RIR-1008 Rl'llR If OP

                                                                                                                          //,O          Cl'tt eo""o            cm        Hi RRHGC   l               I   Rl'llR                       *((S C RAU
 *HIHIHG BRSIH 111 RHHGC R             I     Rl'llR
                                                                                                                        /J.O .           Crt1 1323

____l ... .J-__,0,.___ CPH 1110

 *r*nr Leo rucL 0202~~?.

[ftt1 I-GOU l '.

                                                         ,/)

DIRIY URSIC ORRIH IRHkS

                                                                  ~
                                                                                                *UC SC RRD It/I Rftl um;r C UCHI 1/-oo tm nn~H   tt-iJ R         2321          1-60[ l            ,.()
                                                                  %                              5t//

___.I._< __ tPl1 CPH HRIH:!'!Rtl D 2323 Slr HORlll

     . 1::l/!.0          CPH                                                           !i70CJ            (),J-,P HRl'llR
  *OCCHOC OCPCHOCHI                                                                    SCP SOUlll OH. CR SUllCH                                                                        7-313              (), ~L           tlRl'llR PUSll lOH

SCCHRRld. llHC:

                .llHC:
                       ~(1()
                        //JO RADIULOGICRL

• II\

R1n-*232fi Rill ..*2327 __._,(poc:;....__o___ er* _(). 2- MRlH UACkUP SI ff[k rucL HAHDLIHG ARCAS Rlfl-2310 _ _.:OIE...llOILS=......_ _ cPtt . *~tQUID RRDIAllOH

        .HOHllORS             HOH I     OOS          HR.tflR                      RIR-2319         ~-=t>~O:...;;:S:.......__ CPH HUH 2     00.$         HRl'HR
  *CottPOHCHf COOLIHG UAICR    ll'6         CPH CUHf ROL R HOH          f..

or RRO 2310 HRl'llR SCRUICC UAICR 0033 ~ COHIAIHHCHI ISOLRllOH __. ..;:i~c..o=o__ cm o. t . ¢ R/llR RIR-1005 cnHn orr RllD UHSIC DISCHG 1019 RIR-1806 D. 3 j"'t) R.tllR

                                                                         --       0631 GAS
                                                                                                             *     ~*         Crtt
       .*. 8 1-(,:)     CPl1 12* z,z.o   R.tHR RIR-1007                                            *Rno unsr C l'LCHll1 SIH GCH OUJUDOUH                                                       ....-..

0707 RIR-1800 "* 180 R.lllR 1101 /(,O Cl'tt

           £(10         CPH Hi RANGE    L             I     R/llR
                                                                                   .-       *CCS C RAU
   *HIKIHG BASIH                                                                   1-..

I 3Z3 Ill RllHGC R I Rl'llR 11/IJ /J.0 . CM1

            /J-0        CPl1
                                                                                            *UC SC RHO
   *f'RILCD rucL                 DIRIY UASI[ DRAIH tRHKS                            --'

OZOZAt??. I-GOU L ~/) ~ It/I 1/-oo r:rH RIH Ufl!jf C UCHf tf'li I' HAIH SICntt R 2321

             '11<2 CPl1 1-GOC L           I"()

r. .._

Sri/ f< CPl1 HAIH SICntt B 232:i Slr HORlll 2~ CPl1 !i709 f),;,_P HRl'llR

   *OCCADC OCPCHOCHI                                                               SCP SOUlll OH CR SUI ICH                                                                   7-ll 3               (), ~L tlRl'llR PUSlllOH

RI n*-*232f; ___._ _ f.P_O___ t r H .

                            ,,,_          RADIOLOGICAL               ..   "

R i 11*** 2 327 _ _;,*_;::()::-.:-...~....;;.__-- MR' H SCCHARIO 1 IHC:  !!,11 S_ ttHc: l/Yf: UACkUP SIRCk rucL HRHDLIHO AREAS R1 n-z:11 8 ___----lolE-lloL.S=---_ _ cm "tlQUID RRUIAIIOH HOHllORS HOH I OOS HR.IHR RI n-231 9 -~b.:....::O=S~-- cm HOH 2 00.$ HR.IHR

*COl1POHCHI COOLIHG UAICR 0}15                                                                     CUHIROL         RO~         RAD          2310
      * /"-0         CPH                                                       HOH            /2 * /               . HR l'llR SCRUICC UAICR CUHIRIR1CHI ISOLAllOH            -

_0_0_33~"~=..:::oo__ cm o. "S"P. RIR-1005 Rl'llR cnHH orr r.ns RHO UllSJ[. DISCHG RIA-1806 e.J~ R.IHR

                                                                            ~

06:11 C,.@* Crt1 1019 li-Q CPH RIA-1807

o. 2- z.u R.IHR *RAD uns1c PLCHll1 SIM GCH OUJUDWH 0707 RIR-1800 O.li'~ R.IHR -

110? l(,o Cl'tt uro cm Hi RAH&C L I R.tllR *CCSC RAU

                                                                                 ~
 *HIKIHG DASIH                                                                   ~

1323 Ill RftHGC R - I R.tllR 1110 /J.O CM1 _ __.../)--=~O~- CPH

                                                                                            *UCSC RAD
 *f"RILCD ruct                      DIRlY URSIC DRAIH IAHKS                       ~

0202A ~  ?'?. Clttt l-60U l - .. £D *1.

                                                                            ~

Rn~,J um;rc " urHr 1/-oo t:rt1

                                                     ~{)

HAIH Sl!IW1 A 2321 1-60[ l 1. Sri/ l~ f:Pl1 t.roo cm HRIH Sl~ptt 0 232~ Slr HORIH

   .    ?'fOf         CPH                                                       6709                   (), J,..P HRl'llR
 *OCCRDC DCPCHDCHI                                                              SCP SOUlll UH CR SUllCH                                                                   7-ll~                   (), fL           tlRl'llR POSll IUH

           **                              RRDIULOGICRL H

RIH-*2321; '0 Ri ll**2327 _ __:_tJ_._'L__ er. . MRm' SCCHRRIO IIHC: J!.}J 0 11HC: /1AO rUCL HRHOLIHG RRCRS DRCkUP SIRCIC

    *~1uu10      RAOIRllOH R1n-2:u e            o o.S             CPtt ttOHllORS            HOH I '    oo.S        HRl'llR                     RI R-2 31 9 __t>=....;:o::;.-=:s:.--__ CPH ttUH 2     00.$        HRl'HR
      *COHPOHCHI CODLIHG URICR 0915                                                                     CUHIROL RO~ RAO                2310
    .           /,0      CPtt HOH         /2 * /            HR/llR SCRUICC URICR oo33    C.oo       cm COHIAIHHCHI ISOLRllOH            ...

I' . RIR-1005 o~c.~u Rl'llR nrr ROD UHSIC OJSCHG 11119 RIR-1806 o. JP. Rl'HR

                                                                               --   CIJHll
                                                                                   'Ofill GAS l.Pn>        Crtt 8'10       CPtt RIA-1807
                                                   'o. zz..o    R.IHR
                                                                                                           ~

SI H Gett DUIJOOUH 0707 2-0f'O RIR-1800 Q, / 5'.Q_ Rl'llR

                                                                              ..-   *Rno URSI[ l'l[Hll1 l/,o      [1'11 CPtt                                                       ltOf Hi RRH&C L               I    Rl'HR                        *((5[ RAU
      *ttlHIHG DASIH Ill RllHGC R           I      Rl'llR 1323
               /)-Q 11/D                /J.O        trt1 CPtt unstc                                             *UCSC RHO
      *rnrtco ruct                  DIRIV         DRAIH IRHKS                        _.....

0202A  ??? : [fttf 1-60U L I, £0  % -,J' ,,,, RH um; I c U(ff I 1/-oo t:lttt HRiH SICIW1 A 2321 1-60£ i. ,.()

                                                                %               ~

Sri/ l~ f:Pl1

           "" 000      tPtt 2323                                                        SLr HORlll CPtt                                                       !i709              (),;.'/ HRl'llR
      *OCCRDC OCPCHDCHI                                                             SCP SOUlll I      OH CR SUllCH PUSll IOH 231]               I), 1L tlR/llR

SCCHRRIO. llHC: .f)j__~ llHC: /~/~ RAOIULOGICHL

                                                        *         ~~           n--

RI 2 32fi Rill*--2327

                                                                                         --=----":'f"-.--':=--- cjp rucL  HHHOLIHO HRCHS                           bHCkUP SI RC:IC Rtn-z:u 8 _..,'!loE,..mEoc...:;S~.--CPH

• ~tQUIO RRDIAllOH HOH1tORS HOH 1 00$ HRl'llR RIR-2319 __.:::C>;,,.,:O::._;:S=----- trt1 HUH 2 00,S HR.lllR

*COHPDHCHI COOLIHG UAICR   O't         CPH                                                    CUHIROL RO(tt RAO
                                                                                       ~* I 2310 SCRUICC UAICR HOH
                                                                                          ------*-        HR.tllR 0033                            tOHIHIHttCHI ISOLHllOH l.eoo       CPH o~ ~("o.

RIH-1005 R.lllR RHO unstc OISCHG ,.., - c11H11 nrr r;ns RIR-1806 tJ. 1 J () Rl'HR -

     *. 8 .,.Q lll19                                                                      0631                   . I ffJ!J.            cm CPH RIA-1807        o. ., £0       Rl'HR           *Rno    uns1 C l'LCHllt 5111   GCH DUnJOOUH

().I lo ,. 0707 Z..10 0 cm RIA-1808 IUllR - 1101 /l,0 Cl'tt Hi RAH&C L I Rl'llR

*HIHIHG DASIH 1323                       HI RHHGC R           I         Rl'llR           --      *C[S C RHO 11/IJ                /).0 .           tM1
----4l....~._O=--   cm DIRIY unstc DRAIH IRHKS                                *UC SC RHO
*f'ffllCO fUCL OZOZA??? .
                                                                            ~
                                                                             -      It/I                 1/-oo
         *.

• CPl1 l-60U l I* 5"D *1. Rltll UHSI C U£HI t:PH HAIH JHCOO A 2321 1-601: l ,.0  % - t<

1'l lt!o cm Sr// tPH ttAI.~ SICffl B 2323 VU l6t> cm Slr HORlll

                                                                           !i709            0,;,_P       HR.tllR
*occnuc OCPCHOCHI                                                          SCP SOUlll UH CR SUltCH PUSlllOH                                                                   7-ll.l            ()

• f L tlR.tllR

SCCHRRIO I IHC: 1 IHC:

                              ~p-
                              /).io RRDIOLOGICRL

• a RIR-*232fi ___...._ _,~()_ _ C , .

Rill***2327 -"--......_IJ_._z.._ MR'nf URCkUP SI Rf.IC rucL HRHOLIHO RRCRS Rin-z:u 8 _ _:OIE....llolL.S=......_ _ cPH

• ~1~UIO RROIAllOH HOHi i ORS HOH I. 00$ HR/HR RIR-2319 ~..::::b;....o;;_;;;S..____ cm HUH 2 00.$ HR.IHR

*CoHPOHCHf COOLIHG UAICR 0915 "0                  CPH CUHIROL R HOH or 12..

RAD I 2310 HRl'llR SCRUICC URICR COH1Rltl1CHl ISOLAllOH _o_o3_3_(,-=Q""-"0'-- CPH RIR-1005 (). (,,('0 Rl'llR c11Hn nrr r.ns RflO unstc OJSCHG IJ. i ff! Hl19

--1~1'-=~'-- CPH RIR-1806 RIR-1807           f)<<  z,z,,o RIHR R.IHR 0631
                                                                                                              -----                Cl'tt SIH GCH BUJUOOUH 0707 /,// O                  CPH RIR-1800           tJ. 1 to    R/llR    -

I~

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 *HIHIHG DASIH                                                                        --

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*COl1POHCHJ COOLIHG                                                                                                              I

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*rntLCO f"UCL                                                                                    ~

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RAD MONITOR DATA

R~I 2.4 kV CONTROL'D ACCESS PERS CONT PURGE OUTSIDE CRTL RM OLD SPENT EAST RH SERV CONTROL SWITCH* LAB CONTROL AIRLOCK UNIT RU DEHIN CRTL RM MAIN EAST TURB LUNCH FUEL SAFEGRDS CORRIDOR AREA GEAR CORRIDOR STATION OUTSIDE RH NORTH RH FOOF CORRIDOR ENTRANCE OP FLOOR ROCJol POOL RH 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 TIHE 2300 2301 2302 2303 2304 2305 2306 2307 2308 2309 2310 2311 2312 2313

=========================================================================================================================================================

08:00 AH 7 0.8 0.8 0.9 0.2 0.16 oos 0.4 0.2 0.1 0.4 0.4 0.52 08:15 AH 7 0.8 0.8 0.9 0.2 0.16 oos 0.4 0.2 0.1 0.4 0.4 0.52 08:30 AH 7 0.8 0.8 0.9 0.2 0.16 oos 0.4 0.2 0.1 0.4 0.4 0.52 08:45 AH 7 0.8 0.8 0.9 0.2 0.16 oos 0.4 0.2 0.1 0.4 0.4 0.52 09:00 AM 7 0.8 0.8 0.9 0.2 40 oos 0.4 0.2 0.1 0.4 0.4 0.52 09: 15 AH 1 0.8 0.8 0.9 0.2 40 oos 0.4 0.2 0.1 0.4 0.4 0.52 09:30 AH 1 0.8 0.8 0.9 0.2 40 oos 0.4 0.2 0.1 0.4 0.4 0.52 09:45 AH 1 0.8 0.8 .o.9 0.2 80 oos 0.4 0.2 0.1 0.4 0.4 0.52 10:00 AH 1 1 0.8 0.9 0.2 80 oos 0.4 0.2 0.1 1 0.4 0.52 10:15 AH 1 2.1 0.8 0.9 0.2 80 oos 0.4 2 0.2 7 0.4 0.52 10:30 AH 1 2.1 0.8 0.9 0.2 80 oos 0.4 2 0.2 3 0.4 0.52 10:45 AH 1 0.9 0.8 0.9 0.2 80 oos 0.4 2 0.2 0.4 0.52 11:00 AH 1 0.9 0.8 0.9 0.2 80 oos 0.4 2 0.2 0.4 0.52 11 :15 AH 1 0.9 0.8 0.9 0.2 80 oos 0.4 2 0.2 0.4 0.52 11:30 AH 1 0.9 0.8 0.9 0.2 80 oos 0.4 2 0.2 0.4 0.52 11:45 AM 1 0.9 0.8 0.9 0.2 80 oos 0.4 2 0.2 0.4 0.52 12:00 PH 1 0.9 0.8 0.9 0.2 80 oos 0.4 3 0.2 40 0.4 0.52 12:15 PH 1 0.9 0.8 0.9 0.2 80 oos 0.4 3 0.2 30 0.4 0.52 12:30 PH 1 0.9 0.8 0.9 0.2 80 oos 0.4 3 0.2 20 0.4 0.52 12:45 PH 1 0.9 0.8 0.9 0.2 80 oos 0.4 3 0.2 10 0.4 0.52 01:00 PH 1 0.9 0.8 0.9 0.2 80 oos 0.4 3 0.2 1 0.4 0.52 01:15 PH 1 0.9 0.8 0.9 0.2 80 oos 0.4 3 0.2 0.4 0.52 01:30 PH 1 0.9 0.8 0.9 0.2 80 oos 0.4 3 0.2 0.4 0.52 01:45 PH 1 0.9 0.8 0.9 0.2 80 oos 0.4 3 0.2 0.4 0.52 02:00 PH 1 0.9 0.8 0.9 0.2 80 oos 0.4 3 0.2 0.4 0.52 02:15 PH 1 0.9 0.8 0.9 0.2 80 oos 0.4 3 0.2 0.4 0.52 02:30 PH 1 0.9 0.8 0.9 0.2 80 oos 0.4 3 0.2 0.4 0.52

EVAP RY CONTROL'D RY RY SPENT FUEL EXHAUST RY FUEL DE CON CONTROL DECAY LAB PACKAGING PACKAGING POOL FAN ADDITION HANDLING ROOM EVAP A EVAP B PANEL TANKS CORRIDOR AREA NO AREA YEST CRITICALITY DUCT VENT RH VENT Ra/h  !!a/h l!a/h  !!a/h  !!a/h ~/h Ra/h  !!a/h  !!a/h  !!a/h cpm cpm TIME 5701 5702 5703 5704 5705 5706 5707 5708 5709 5710 5711 5712 E:::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::::: 08:00 AH 0.3 0.35 18 0.03 0.2 0.9 0.1 0.13 0.28 oos 15 18 08:15 AH 0.3 0.35 18 0.03 0.2 0.9 0.1 0.13 0.28 oos 15 18 08:30 AH 0.3 0.35 18 0.03 0.2 0.9 0.1 0.13 0.28 oos 15 18 08:45 AH 0.3 0.35 18 0.03 0.2 0.9 0.1 0.13 0.28 oos 15 18 09:QO AH 0.3 0.35 18 0.03 0.2 0.9 0.1 0.13 0.28 oos 15 18 09:15 AH 0.3 0.35 18 0.03 0.2 0.9 0.1 0.13 0.28 oos 15 18 09:30 AM 0.3 0.35 18 0.03 0.2 0.9 0.1 0.13 0.28 oos 15 18 09:45 AM 0.3 0.35 18 0.03 .0.2 0.9 0.1 0.13 0.28 oos 15 18 10:00 AH 0.3 0.35 18 0.03 0.2 0.9 0.1 0.13 0.28 oos 15 18 10:15 AH 0.3 0.35 18 0.03 0.2 0.9 0.1 0.13 0.28 oos 15 18 10:30 AM 0.3 0.35 18 0.03 0.2 0.9 0.1 0.13 0.28 oos 15 18 10:45 AM 0.3 0.35 18 0.03 0.2 0.9 0.1 0.13 0.28 oos 15 18 11:00 AM 0.3 0.35 18 0.03 0.2 0.9 0.1 0.13 0.28 oos 15 18 11:15 AH 0.3 0.35 18 0.03 0.2 0.9 0.1 0.13 0.28 oos 15 18 11:30 AM 0.3 0.35 18 0.03 0.2 0.9 0.1 0.13 0.28 oos 15 18 11:45 AH 0.3 0.35 18 0.03 0.2 0.9 0.1 0.13 0.28 oos 15 18 12:'00 PH 0.3 0.35 18 0.03 0.2 0.9 0.1 0.13 0.28 oos 15 18 12:15 PM 0.3 0.35 18 0.03 0.2 0.9 0.1 0.13 0.28 oos 15 18 12:30 PH 0.3 0.35 18 0.03 0.2 0.9 0.1 0.13 0.28 oos 15 18 12:45 PM 0.3 0.35 18 0.03 0.2 0.9 0.1 0.13 0.28 oos 15 18 01:00 PM 0.3 0.35 18 0.03 0.2 0.9 0.1 '0.13 0.28 oos 15 18 01:15 PH 0.3 0.35 18 0.03 0.2 0.9 0.1 0.13 0.28 oos 15 18 01 :30 PH 0.3 0.35 18 0.03 0.2 0.9 0.1 0.13 0.28 oos 15 18 01 :45 PH 0.3 0.35 18 0.03 0.2 0.9 0.1 0.13 0.28 oos 15 18 02:00 PH 0.3 0.35 18 0.03 0.2 0.9 0.1 0.13 0.28 oos 15 18 02:15 PH 0.3 0.35 18 0.03 0.2 0.9 0.1 0.13 0.28 oos 15 18 02:30,PM 0.3 0.35 18 0.03 0.2 0.9 0.1 0.13 0.28 oos 15 18

AIRLOCK 590' INSIDE CONT CONT CONT CONT AIR RM CONT RAD MON RAD MON RAD MON RAD MON

                ~/h        ~/h        ~/h        ~/h        ~/h        ~/h TIME      2314       2315       1805       1806       1807       1808

=================================================================

08:00 AM 3.1 2.7 20 19 120 80 08:15 AM 3.1 2.7 20 19 120 80 08:30 AM 3.1 2.7 20 19 120 80 08:45 AM 3.1 2.7 20 19 120 80 09:00 AM 3.1 2.7 20 19 120 80 09:15 AM 3.1 2.7 20 19 120 80 09:30 AM 3.1 2.7 20 19 120 80 09:45 AM 3.1 2.7 20 19 ,120 80 10:00 AM 3.1 2.7 20 19 120 80 10: 15 AM 3.1 250 450 150 160 120 10:30 AM 3.1 350 550 250 200 160 10:45 AM 3.1 350 550 250 200 160 11:00 AM 3.1 450 650 350 220 180 11:15 AM 3.1 450 650 350 220 180 11:30 AM 3.1 450 650 350 220 180 11:45 AM 3.1 450 650 350 220 180 12:00 PM 3.1 450 650 350 220 180 12: 15 PM 3.1 450 650 350 220 180 12:30 PM 3.1 450 650 350 220 180 12:45 PM 3.1 450 650 350 220 180 01:00 PM 3.1 450 650 350 220 180 01:15 PM 3.1 450 650 350 220 180 01 :30 PM 3.1 450 650 350 220 180 01:45 PM 3.1 450 650 350 220 180 02:00 PM 3.1 450 650 350 220 180 02:15 PM 3.1 450 650 350 220 180 02:30 PM 3.1 450 650 350 220 180

I* SERVICE STEAM COMPONENT CIRC LIQUID TURB

                   \IATER GENERATOR   COOLING      \IATER         R\I     BLDG DISCHARGE BLO\IDO\IN     \IATER DISCHARGE    MONITOR       SUMP cpn       cpn        cpn        cpn        cpn       cpn 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 08:30 AM 600 1410 150 120 870 150 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 2090 245 120 870 150 10:30 AM 600 2130 160 120 870 150 10:45 AM 600 2150 160 120 870 150 11:00 AM 600 2100 160 120 870 150 11:15 AM 600 2090 160 120 870 150 11:30 AM 600 2110 160 120 870 150 11 :45 AM 600 2080 160 120 870 150 12:00 PM 600 2080 160 120 870 150 12:15 PM 600 2100 160 120 870 150 12:30 PM 600 2110 160 120 870 150 12:45 PM 600 2100 160 120 870 150 01:00 PM 600 2090 160 120 870 150 01:15 PM 600 2110 160 120 870 150 01:30 PM 600 2080 160 120 870 150 01:45 PM 600 2080 160 120 870 150 02:00 PM 600 2100 160 120 870 150 02:15 PM 600 2110 160 120 870 150 02:30 PM 600 2080 160 120 870 150

STACK GAS STACK GAS EAST YEST CONT BLDG WASTE BLOWDOYN GROSS SINGLE RY 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

==================================================================================================

08:00 ;AM. oos oos 160 120 400 3900 <1DO 122 400 08:15 AM oos oos 160 120 400 3900 <100 122 400 08:30 AM oos oos 160 120 400 3900 <100 122 400 08:45 AM oos oos 160 120 400 3900 <100 122 400 09:00 AM oos oos 160 120 400 3900 <100 122 400 09:15.AM oos oos 160 120 400 3900 <100 122 400 09:30.AM oos oos 160 120 400 3900 <100 122 400 09:45 AM oos oos 160 120 400 3900 <100 122 400 oos ' 10:00 AM oos 160 120 400 3900 <100 122 400 10:15 AM oos oos 160 120 400 . 3900 <100 650 1500 10:30 AM oos oos 160 120 400 3900 <100 550 1350 10:45 AM oos oos 160 120 400 3900 <100 650 1400 11:00 AM oos oos 160 120 400 3900 <100 750 1350 11:15 AM oos oos 160 120 400 3900 <100 650 1300 11:30 AM oos oos 160 120 400 3900 <100 550 1400 11:45 AM oos oos 160 120 400 3900 <100 650 1450 12:00 PM oos oos 160 120 400 3900 <100 1500- 1500 12:15 PM oos oos 160 120 400 3900 <100 1500 1500 12:30 PM oos oos 160 120 400 3900 <100 1500 1500 12:45 PM oos oos 160 120 400 3900 <100 1500 1500 01 :00 PM oos oos 160 120 400 3900 <100 1500 1500 01 :15 PM oos oos 160 120 400 3900 <100 1500 1500 01 :30 PM oos oos 160 120 400 3900 <100 1500 1500 01:45 PM oos oos 160 120 400 3900 <100 1500 1500 02:00 PM oos oos 160 120 400 3900 <100 1500 1500 02:15 PM oos oos 160 120 400 3900 <100 1500 1500 02:30 PM oos oos 160 120 400 3900 <100 1500 1500

IODINE/ NORMAL HIGH MAIN MAIN CONT CONT FAILED HIGH RANGE

• PART NOBLE GAS RANGE STEAM STEAM HIGH HIGH FUEL EFFLUENT GAS EFF EFFLUENT NOBLE GAS GAMMA B GAMMA A RANGE RANGE MONITOR MONITOR cpn cpn ldt/h cpn cpn R/h R/h rit/h TIME 2325 2326 2327 . 2322

                                                                                                "                    .(' ~ c..\--~&.
                                                                                                                                     ...ea..~ ,* Yl ~

2323 2324 2321 0202 (RAD GUN) - C.OV"'

==================================================================================================

08:00 AM 300 60 0.2 25 23 10 BKG 08:15 AM 300 *60 0.2 25 23 10 BKG 08:30 AM 300 60 0.2 25 23 10 BKG 08:45 AM 300 60 0.2 25 23 10 BKG 09:0.0 AM 300 60 0.2 25 23 10 BKG 09:15 AM 300 60 0.2 25 23 10 BKG 09:30 AM 300 60 0.2 25 23 10 BKG 09:45 AM 300 60 0.2 25 23 10 BKG 10:00 AM 300 60 0.2 25 23 10 BKG 10: 15 AM 300 60 0.2 7800 700 OFF 5 10:30 AM 300 60 0.2 7800 700 SCALE 5 10:.45 AM 300 60 0.2 7800 700 HIGH 5 11:00 AM 300 60 0.2 7700 690 0.1 11:15 AM 300 60 0.2 7600 680 0.1 11:30 AM 300 60 0.2 7500 610 0.1 11:45 AM 300 60 0.2 7400 660 0.1 12:00 PM 300 60 0.2 . 420000 39000 275 12:15 PM 300 60 0.2 420000 39000 275 12:30 PM 300 60 0.2 420000 39000 275 12:45 PM 300 60 0.2 420000 39000 275 01:00 PM 300 60 0.2 420000 39000 275 01:15 PM 300 60 0.2 420000 39000 275 01:30 PM 300 60 0.2 420000 39000 275 01:45 PM 300 60 0.2 420000 39000 275 02:00 PM 300 60 0.2 420000 39000 275 02:15 PM 300 60 0.2 420000 39000 275 02:30 PM 300 60 0.2 420000 39000 275

INPLANT RAD DATA I

AUX/TURBINE ONSITE DATA NOTES

1. CONTAMINATION LEVELS FOR THE ENTRANCE HALLWAY TO SIRW SHOULD BE MULTIPLIED BY A FACTOR OF 10 EACH TIME THE DOOR IS OPENED.

THE FIRST TIME THE DOOR IS OPENED THE CONTAMINATION LEVEL WILL BE 1000 CPM.

2. RIA MONITORS ARE AS FOUND EXCEPT WHERE NOTED IN THE SCENARIO.

3. IF PERSONNEL WANT TO CLIMB THE LADDER ON THE 625' CCW ROOF THE FOLLOWING APPLIES:

1005-1055 HRS - UNSAFE, NO CLIMBING 1056-1155 HRS - ALLOW CLIMBING, SEE MAPS FOR CONTAMINATION 1156-1255 HRS - UNSAFE, NO CLIMBING

4. FOR THE NSSS PANEL SAMPLING (NSSS SX), THE DOSE RATES ARE DEPENDENT ON THE SX VALVES BEING OPENED OR CLOSED. SEE MAPS FOR DOSE RATES.

5. FOR THE FILTERED WASTE MONITOR TANKS (FWMT) AND CHEM LAUNDRY DRAIN TANKS (CLOT) THE DOSE RATES ARE CONTINGENT ON FILLING THE TANKS WITH THE EXCESS WATER FOR THE CONTAINMENT LEAK *

        \.  .

Rad Levels Contaminat:i,on 3A s Foun d

N PLANT RADIATION DATA ALL FIGURES ARE mR/HR UNL~s~; :-3PEC IF I ED OTHERWISE 3CENAP. fC' TIME: -_QOJ.Q~.z.2 __ _

TIME: 57-o' . --*- ._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __.:.__ _ _ _ _ _ _ _ ___JL___ _ _:___ _ _ __J

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Rad Levels --; Conta.minatiox:_) As found

N PLANT RADIATION DATA co****** N*** co*****

ALL FIGURES ARE mR/HR UNLESS SPECIFIED OTHERWISE S\.ENARIO TIME: -~QlQ:-~1~~--- ~c;o .. TIME:

.~N ALL PL/.tADIATION DATA FIGURES ARE mR/HR UNLESS SPECIFIED OTHERWISE

1 CENA E [ 0 T I ME : - j)_}QQ::_O_!_Q~-~

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T I ME : Rad Levels ~As found. Contamination Level$)

                                               ~--------
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t, .. rJ 0 IN PLANT RADIATION DATA ALL FIGURES ARE mR/HR UNLESS SPECIFIED OTHERWISE SCENARIO TIME: -0300-0100 Rad Levels * ~ As found Contamination LevelSJ TIME: 0800-0930 PAUeaD11e "-A*T

N PLA-ADIATION DATA

~LL FI~S ARE mR/HR UNLESS SPECIFIED OTHERWISE

'i\.ENAE IO '!' IME:

            '!' I ME :
                           -:_QQ3_fl=.QlQ.Q_ __

_.Q6..QP.:.Q2.3_Q.._._ Rad Levels Contamination Levels 5As found

                       . 'h-_flt=-==============:::::::::J            

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J

• 0 Li~_,__ ____,

====1

• Rad Levels - NSSS Panel when Sx Line

                                                            !4 c::=:::::J    a a                                                       Open

c::==J c::::J 0

0 i 4 Note: Prior to opening Sx pts - As found 15 mR/HR in hood when Sx flush begins 250 mR/HR GA NSSS when Sx is collected 2.5R/HR Contact with 500 ml Sx bottle

N PLANT RADIATION DATA ALL FIGURES ARE mR/HR UNLE~S SPECIFIED OTHERWISE Sr.EN AR IO TIME: -0030-0100 Contamination Levels - As found TI ME : 0800-0930 Rad Levels: Depend on NSSS Sx pt being open or closed.

See above note.

                                                                                                                         c"ji,*j;j*~1wt*anu*e*1*1,1nan1n1r-----1
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                                              ...... I        ~..... '
                                           ******~*-            \I \I                m::m m::m I

I I I I I m::m m::m I J a =====.J c:* _:N PLANT RADIATION DATA ALL FIGURES ARE mR/HR UNLESS SPECIFIEI? OTHERWISE

      ~1CENARIO           TIME:         - 003 0-01-.0"'-'0,.___             Rad Levels TIME:             0800-0930                       Contamination    Levels~ As found

                                                  *z.~u
                          ~I=--=-* I)                   ([=--=*IP

~~a~~~-~ -

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                          *-'(' ............. ~

N PLANT RADIATION DATA ALL FIGURES ARE mR/HR UNLESS ~3PECIFIED OTHERWISE

JCENAP.[ 1) TIME: -0030-0100 Rad Levels Contamination Levels 3 As found TI ME: 0800-0930

2~11.

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(I .... D.... I) IN PLANT RADIATION DATA ALL FIGURES ARE mR/HR UNLESS SPECIFIED OTHERWISE C~Rll l'OftR COllPIUIY SCENARIO TIME: -0030-0100 Rad Levels "";> As found PAU9ADl8 Pt.AllT TIME: 0800-0930 Contamination LevelsJ

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M PLANT RADIATION DATA Rad Levels Contaminat io 3As found ALL FIGURES ARE mR/HR UNLESS SP~CIFIED OTHERWISE

"i ! :EN AF: r!) T I ME : -Q_O..J_Q=Q.1!_?] ___ _

TIME: _O~_Q9_-:_J:?2z __._ -*** * - - - - * - - - - - - - - - - - - - - - - . . . . : . . __ _ _ _ _ _ _ _ _ _ _i___ ___::_:___ _ __J 57-o'

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N PLANT RADIATION DATA co**--** H*** co*****

ALL FIGURES ARE mR/HR UNLESS SPECIFIED OTHERWISE SCENARIO TIME: Rad Levels . ' ) ____________ Contamination Levels? As found*'

                                                                                                                                           '5"'10 -            _,

TIME: 09JO~Q2_1!;;____ _

~CE NAE I0 1' IMF.: Q]QQ_Q]~

          "!'!ME:   0930-0945 Contamination Levels_; As found Rad Levels t

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I] IN PLANT RADIATION DATA ALL FIGURES ARE mR/HR UNLESS SPECIFIED OTHERWISE SCENARIO TIME: 0100-0115 TI ME: ~0~9_3=0-_.0"""'9'"""'"4..,_5_ _ Contamination Levels Rad Levels J As found

~N

.~~-.L PLA~'"' RADIATION DATA F I . S ARE mR/HR IJNLEs::; :-3PECIFIED OTH!:t~RWISE.

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                                                                                                                                         *o*OO**NI ii.o*M*lil I*

1CENAEIO TIME: OJ00-0115 T I HE : 0930-094 5 Contamination Levels~

As found Rad Levels lj_1 __

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                                                           .a.               a a c::::::J               Contamination Levels - As .found 0

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                                                              ~
                                                              ~
                  ~N     PLANT RADIATION DATA ALL FIGURES ARE mR/HR UNLESS SPECIFIED OTHERWISE
                ~"Jr.ENAP.IO        TIME:

TIME: 0930-0945

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l I cn:m cn:m I I I I cn:m cn:m I Dc*=====i _:N PLANT RADIATION DATA ALL FIGURES ARE mR/HR UNLESS SPECIFIED OTHERWISE

"JCENAR IO 1' IME

OJ 00-011 5 Rad Levels  ? As found PALl*AD** PlA*T Contaminations Levels ,)

TIME: 0930-094.5...._

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N PLANT RADIATION DATA ALL FIGURES ARE mR/HR UNLESS SPECIFIED OTHERWISE

JCENAP.£ 1) TIME: 0100-0115 Rad Levels ~A s f oun d Contamination Levels TIME: 0930-0945 P&UUMePt. ... I

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                   ~N PLANT RADIATION DATA ALL FIGURES ARE mR/HR UNLESS SPECIFIED OTHERWISE                                            C~M   POftll COllPAMY
                 .SCENARIO TIME:          0100-0115                      Contamination Levels TIME:        0930-0945                      Rad Levels                 ~ As found PAUSAD!I l'LAMT

Rad Levels - As found

N PLANT RADIATION DATA ALL FIGURES ARE mR/HR IJNLES~3 :~PF.CIFIED OTHERWISE

            ;JCEtMP.ro '!'IME: -0030-0425 TIME:     0800-1255

. -*** . _____________________;____ 57-o'

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                                                                                             --:zr--------
                                                                                             ~ote: If water is moved to treated filtered monitor tanks, chem laundry drain tanks,
                                                                                          ..        the dose rates will rise for noted areas .
                                                           ~N PLANT RADIATION DATA                                                             CO**u.*** *****co*****

ALL FIGURES ARE mR/HR UNLESS SPRCIFIED OTHERWISE

                                                          ~lr.ENARIO TIME: 0115-0130           Contamination Levels:?         ~*                 ~'io-Rad Levels          .5 As found   ~~~~~~~.&.-~~~~~~~~~__1
                                                                     '!'I HE : 094 5-1000

\LL

~t:ENAE RADIATION DATA ARE mR/HR UNLESS C') TT MF.:       *-0115-0130
                                    --~----....;. __

-~PEC IF I ED OTHERWISE ---r c:= ---bl _

                                                                                                               ~: _J l~          ~

l

                     *:rME:       0945-1000 Rad Levels Contamination Levels_:)
                                                                 ~ As found                     I;. I ~ 'oAo..
                              .~e     -----cf
                            'I . ***- - -----------.J
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                                              \

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D a rJ CLDT is filled IN PLANT RADIATION DATA ALL FIGURES ARE mR/HR UNLESS SPECIFIED OTHERWISE Contamination Levels.? SCENARIO TIME: . <E-!~:.~12~---- Rad Levels _sAs found TIME: 0945-1000

                                                                                        *au**H* "-***

u,oz.'

CN PLAtJ'" RADlATION DATA *

 ~~

.. .. L F I . S ARE mR/HR IJNLES~; :3PECIFIED OTHERWISE

1CENAE[0 TIME

_0115-0130

             '!' I HE :   094 5-1000 Contamination ~                      As found Rad Levels                  .....)

11_1._fl=-==========~ D a ._._ ....... _ I> ***_............ . _.:;*,*.=-..;.~~~~~ ~-~~~~~

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              ~ ..... ~ ~! ....:.:~=-=: ~~---:--_

N PLANT RADIATION DATA C**ev.1*1 ***** CO***llt

\LL FIGURES ARE mR/HR IJNLESS :~PF.CIFIED OTHERWISE

                                                                                                                         **u***** *u**'

1CENARIO TIME: 0130-0135 Contrunination Levels] >t' As found Rad Levels TIME: 1000-1005

.-\LL RADIATION DATA lt:ENAE l 1) 'f I HF.: ARE mR/HR UNL[S3 ~:.PF.CI Fl ED OTHERWISE 0130-0135 Rad Levels

                                                                                 *    -:fl.
                                                                             ~ As found                                _Q                     ~~*___J lI;** I Contamination Level .                                         I~                        .

1000-1005

                                                                                                                                       ~IQ~Q
                                                    '~"--- ,...._
                              ,f . -

11 *- ----- --------

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I I I\ , 0 is filled IN PLANT RADIATION DATA ALL FIGURES ARE mR/HR UNLESS SPECIFIED OTHERWISE SCENARIO TIME: -913.P-0~13~5~ Contamination :;:; As found T I ME: 1000-1005 Rad Levels :J u,oz_'

~M    l-'LAt-1*** HADIATION DATA                                               *

.~~JL F l . S ARE mR/HR !JNLES~3 ~3FECIFIED OTHERWISE

"if'.ENAElO TIME: 0130-0135 Contamination :J As T IHE: 1000-1005 Rad Levels __)

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• c::=::l c:::J Contamination Levels - As found 0

0

                                                                ~
                                                                ~
                            ~N   PLANT RADIATION DATA ALL FIGURES ARE mR/HR UNLESS SPECIFIED OTHERWISE Sf:ENAEIO TIME:                                                                                              PALllADll PlA*f TIME:

• I r-==::::~.HIC AC* tiiimiif==t"J====t:r=,

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25 mR/!Ll. 5.0,000 cpm smearable on roof /gravel _:N PLANT RADIATION DATA ALL FIGURES ARE mR/HR UNLESS SPECIFIED OTHERWISE PAU8AD** PLA*T

 ;)CENAR IO 1' IME:                  0130-0135 TIME:            1000-1005

---

~.

1-1

              *'IDIRll --

N PLANT RADIATION DATA

      .;\LL FIGURES ARE mR/HR UNLESS SPECIFIED OTHERWISE 3 CENA P. [ ~) 1' I ME : -9.!JQ::..01-Ji__ _

TIME: 1000-1005 PAUUMe"-UI

                               -Z?-11.

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          !N PLANT RADIATION DATA ALL FIGURES ARE mR/HR UNLESS SPECIFIED OTHERWISE SCENARIO TIME:   0130-0135         Unsafe to climb ladder -

Steam, contamin a;ion Levels PAUIADf9 Pl.AMT TIME: 1000-1005

Rad Levels - As found

N PLANT RADIATION DATA

\LL FIGURES ARE mR/HR IJNLES:3 :-3PEC IF I ED OTHERWISE

3 CE tM P. f !) '!'I ME : - .Q_QJ_Q_-_.9_~g_2_ __ _

TIME: _2~Q.~~~22_ __,_ 57-o' _L_ _ _ _ _ _ _ ____,

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• -* ... ~ ~..... ~ ~~ ...:==:.: ~~-~---

                                                                                  *-:-r--- -**   .                                    -               :_~--
                                                                                  °*Note:    If water is moved to treated filtered monitor tanks, chem laundry drain tanks,
                                                                                                                                      *--~   -
                                                                                                                                      ~~!~!-'-
                                                                                                                                             ....n .........
                                                                                                                                                                 -  -~ .

the dose rates will rise for noted areas

                                                   ~N   PLANT RADIATION DATA                                                                 CO*IUl81** ***** co*****

\LL FIGURES ARE mR/HR UNLESS :3PECIFIED OTHERWISE

)r.ENARIO TIME: 0145-0325 Contamination Levels.) As found*' '5"9o -

                                                              '!' IHE: 1015-1155 Rad Levels            _5

~N PLJ.ADIATION DATA ALL  FIGU~ES

.iCENAE £0 TTME: ARE mR/HR 0145-0325 UNL~SS SPECIFIED OTHERWISE Rad Levels s * --r. c~- ---~ l~----J l';"' l Qa"~

                 *n ME : __.l....,O,_l""'-5-~l=l=-5.....,5,___ Contamination As found

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a a rJ 0 CLDT is filled IN PLANT RADIATION DATA ALL FIGURES ARE mR/HR UNLESS SPECIFIED OTHERWISE SCENARIO TIME: 0145-0325 Contamination ;>As found Rad Levels _) TIME: 1015-1155 (Doz_'

~M  PLA-ADIATION DATA

.:\LL F I - S ARE mR/HR IJNLJ!:S~3 :3PECIFIED OTHERWISE

'iCENAEIO TIME: 0145-0325 Contamination) As found Rad Levels _)

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                              ~N    PLANT RADIATION DATA ALL FIGURES ARE mR/HR UNLfi;SS SPEC.IFIED OTHERWISE                                                                                   ca**u*t** *a*t* ca****'
                             ~)f:ENAE ['.")          TIME:         0145-0322_                  Contamination Levels - As found
                                                                                                                                                                        **u*aaa* *t.**'

TIME: 1015-1155

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                                                                                                         -1*1**1*CY 50 mR/HR   2 mR/Hr (1015)     (1055) 50,000 cpm   210,000 cpm smearable (1015)       (1055)

_:N PLANT RADIATION DATA ALL FIGURES ARE mR/HR UNLESS SPECIFIED OTHERWISE

  ~)CENARIO            TIME:   0145- 032,:j               Decrease Rad Levels as time approaches 1055.                     PAL18ADl8 PlA*f Increase Contamination Levels as time approaches 1055.

TIME: 1015-1155

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                           ":_jT . . . . -                   L------___JI -

N PLANT RADIATION DATA ALL FIGURES ARE mR/HR UNL~SS SPECIFIED OTHERWISE

JCENAP. [ 1.) T IHE: .Ql~-=_Q32_?___ _

TIME: 1015:-1155

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

P&UUMeft.Uf

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ii-- l 1au1***** **-- ll. ****-** L l _____l_L _ _c C::::::::J (I .... D IN PLANT RADIATION DATA ALL FIGURES ARE mR/HR UNLESS SPECIFIED OTHERWISE C~M POWl!lt COWAllY SCENARIO TIME: 0145-0325 Unsafe to climb ladder to 649 1 PAU9AD1a Pl.ANY TIME: 1015-1155

\.. .

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N PLANT RADIATION DATA ALL FIGURES ARE mR/HR UNL[S3 SPECIFIED OTH~RWISE

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                                                                                                                                            .~~!'!!--     -=~--

iM~ .. __ monitor tanks, chem laundry drain tanks, the dose rates will rise for noted areas

N PLANT RADIATION DATA c***.,.*** *****co*****

ALL FIGURES ARE mR/HR UNLESS SP~CIFIED OTHERWISE Contamination Levels:? As found~ 1

)CENARIO TIHE: 0325-0425 '=><to -

Rad Levels _) TIME: 1155-1255

~t!            ADIATION DATA

.*\LL FIGURES ARE mR/HR !JNLlrn:; ~:.PF.CIFIED OTHERWISE

                                                                 --r
                                                                          ---bl                      *

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• As found Ra d Leve1 s TIME: 1155-1255 PAU*AN* Pt.A*f

;tr   PLAN'" RADIATION DATA                                                       *

.~LL F l . S ARE mR/HR UNLESS :OPECIFIED OTHERWISE

1!"'.ENAP.IO TIME: 0325-0425 Contamination "?As found

               '!' IHE:    1155-1255                      Rad Levels     ,)
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                                                      .:*4 Note: 1155 Rad Levels are listed.

time approaches 1255 . Decrease rad levels as

N PLANT RADIATION DATA ALL FIGURES ARE mR/HR' UNLESS SPECIFIED OTHERWISE

                  ~-;r.ENAP. IO       'l'IME:      0325-0425                           Contamination Levels - As found TIME:       1155-1255

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_IN PLANT RADIATION DATA ALL FIGURES ARE mR/HR UNLESS SPECIFIED OTHERWISE

    ~1CENAP.IO TIME:     0325-0425 TIME:    1155-1255
                        ----.-..-~---**-

N PLANT RADIATION DATA

       .:\LL FIGURES ARE mR/HR UNLESS               ~-3PECIFIED OTHERWISE

1!:ENAP. F.' 1' IME: .Ql~..:-..Q!!.?.5___ _

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                !N PLANT RADIATION DATA ALL FIGURES ARE mR/HR UNLESS SPECIFIED OTHERWISE                            C_....MI POftll COWAllY SCENARIO TIME:        0325-0425                       Unsafe to climb ladder PAUIADl9 PUllT "TIME:      1155-1255

ONSITE RAD DATA

• ONSITE RADIATION DATA PLUME RADIATION LEVELS AND AIR SAMPLE DATA ONLY APPLY TO THE DOWNWIND SECTORS. DUE TO BUILDING WAKE EFFECTS, SWIRLING OF THE PLUME, AND EFFECTIVE STACK HEIGHT FROM THE STEAM DUMPS THE PLUME DOES NOT TOUCH DOWN UNTIL BEYOND THE PROTECTED AREA FENCE.

THREE INCH AND THREE FOOT GROUND SURVEY DATA AND GROUND FRISK DATA ONLY APPLY TO AREAS OVER WHICH THE PLUME HAS TRAVELED. THIS DATA CAN NOT BE MEASURED UNTIL AFTER THE RELEASE HAS STOPPED BECAUSE OF THE DOSE RATES FROM THE PLUME. IF A GROUND SMEAR IS TAKEN MULTIPLY THE GROUND FRISK DATA BY FOUR FOR GROUND SMEAR RESULTS IN CPM/100 SQ CM. AIR SAMPLE DATA IS GIVEN AS CPM/1000 FOR A 1 MINUTE - 2 CUBIC FOOT SAMPLE. THE DATA IS FOR IODINE. DIVIDE BY 10 FOR THE PARTICULATE. THE PLUME DATA IS FOR A WINDOW CLOSED READING. MULTIPLY BY 10 FOR THE WINDOW OPEN READING *

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,J J*a,~I I ~~ . ~* 1.1*i **' ISi -ir:-- *'i...4 ---- * ,,*i' ta**. ih::'..*- - ~= .-.~:>' *)i~l)* *. GROUND FRISK DATA (CPM/1000) SCCHRRIO T.lHC: 01 fcJ _.,. TIHC: / '8: oo -'!> 8owlh Romd ~,~~-' ' PALISADES NUCLEAR PLANT EMEROENCY ONBITE MONITORING MAP . -~ - *-**** LAKE /**---- MICHIGAN --------- *-4'*--- Demlnerallrer Ouilding Warehouse Warehouse I Support Building Security Build Ing <fill J [(iUR[5 lH MR/HR> r,r.rHnRtn TIHr~_oQ.Oo- OIJIJ 11m:= ..~.rJo - 1*: .. \ \ \ \ '\ \ -- /~-- ~ I I I I I / / ,,,/ ,,/:.~ / ,, *' ,,,.*, ... ,<:~!\~~'..I,':'...;*"" -- ;r ~r; ,........r~.. \ \ ' \ \. \ \ / / '\ \ \ NNll \ NW ' \ \ \ ' ' ~... ~ ' ' .... cf' WNW WSW !JHSI TE 3 IH 6ROUHD__Jj_U_RU[_y_QJHJJ <nLL rIGURE5 IH MR/llR> " " ' " SCEHnRfO TIME:~9
• O~J 0 I
I ., ~* I I I \ -- PALISADES NUCLEAR PLANT *Y I I \ \ \ \ EMERGENCY ONSITE MONITORING MAP LAKE -*--**-~---- MICHIGAN _.:.-----~ --- --. r:----_ _ _.-- ---.....i L-J Rad. Waste Cask Slorage l -#-*ff-fl___.._...,_.1'""V"') .._, ___. flt . Tutblne BuRding Demheralzer Duitdilg 0 Warehouse 0 I Wa~se I Q Support Building Securl ty Build lng ott~1J_t._J_UL~Rmm.1J su'Rucv on1n <fill. F lliUR[S IH MR/llR> r,r.r.HRRIIJ TJM[~~r-ov.t' 1 nn: 'llJ.15'-'lfll' \ \ --/~-~ / / / :.~ 'r* \ / '*' L,/ / \ ,*,;~.. ,*,.~ \ I  ; ,<::-;._;*.:.":l'*~t""i*,,,.: \ I \ \ -- >-<*. ----~ \. \ ,,,"" "\ \ ' ,,,"' \ \ \ '\ \ / / \ \ '\ NW \ \ \ NNW ~ \ \ \ ..... ..... \ \ ..,. ..... ..... ~ WNW ... $J" \ WSW 3*~*v;,:*  !)HSI T £. 3 I H GROUHD S_URY[cY DA !_fl ,.f_.,

-;; <ALL r1GURES IH MR/llR>

(* f.* *~. SCEHARIO TIM[:Qfff _. d'1'f' ~ 1JM£of.~l.~-/I~ F-\~~ ~ - * 'j PALISADES NUCLEAR PLANT \ \ ~HlriO 1 w---s§o EMERGENCY ONSITE MONITORING MAP II ' ' . I - ..- * . .,,..~ . ..- - LAKE MICHIGAN Demlneraber Ouitding . TUfblne Bulding Warehouse 0 I Wa~s* I 0 Support Bulldlng Securlty Bulld Ing '(fill f IGUR[S IH MR/HR> m:rHRRtn TJMr.~-~ J_l*O-" 1 rm: ~~-;!_O -9 \ \ \ \ \ \ \ \ \ \ \. \ \ \ \ \ \ \ \ \ ' \ \ Ni \ \ \ NNI \ \ \ \ SI ~ 'q" ' cf, INI ISi OHSIT£ 3 IH GROUHO SURYEV on1n <nLL r1GUR£S IH MR/llR> SC£HRRIO TIME:: l)S,fO ~ TIM[:_~!!~p -=J' \ PALISADES NUCLEAR PLANT \ \ \ EMERGENCY ONSITE MONITORING MAP LAKE .......-.-,..-*------- . _____ -- /---- IHIGAN - -------~-* ~---- Rad. Waste '-~-ill*--~~~*** s..... ~------__..-- ~t ~lake Dem~erallrer Dulldilg Turbine Building Warehouse I Warehouse I Support Building Securl ty Dul ldlng Q~Sll~ 3 rt GR!ly_~p_sURUCV DATA <JILL fIGURlS IH MRl'llR> StCHARill JIM[: t)()U0 - tf'), 10 ilMC:~_~Jd ~ /0.'0 0 \ \ '\ \ \ \ NNW \ \ NW WNW WSW OHSITE 3 fl GROUHO SURUEV ORTA fl, <ALL rIGURES IH MRl'ltR> ~.., ~ ~ Sl:lHARIO TIME:~O- f)I) 0 1 IM[:~B!o * /C):f>O \ PALISADES NUCLEAR PLANT \ \ \ \ EMERGENCY ONSITE MONITORING MAP \ LAKE ,...----------- -- /"-- ---*-------- ---- ----======:::::::====~==------- - -------~  ::---=:::::::: ____ Rad. Waste Cask Storage l ~,._...~~~ ~.~*"'V"l....,, __ _.._~,s-11-1 ~t Demlneralrer Building Warehouse I Warehouse I" Support Building Security Building .<JILL r11mRlS IH MIUllR> .!l((HRRIU I IM[:J)!!l.r* 0~~ HM£:_!.f{r * /~'1'-r * \ \ \ \ - -- -------~ \ \ \ \ '\ \ \ NNI '\ NW WNW ... w WSW OHSIT£ 3 rT GROUHO SURU£V ORTA <ALL rIGURES IH MR/HR> S[EHARIO TIMr:6/4/r- *J1,,- 1 IMr:_lj_:_/ /" - 11,tr- \ PALISADES NUCLEAR PLANT \ \ EMERGENCY ONSITE MONITORING MAP \ \ \
• LAKE
/"---- ------ -- . - - ---- * ---...;.-----~ -* ~--- Rad.Waste -*-fl-*-...,-.._.,_;*** SO.age ~---'l- ~t Demlnerallzer Building Warehouse 0 I Warehouse I -Z/ t) Support Building Security Bui Id lng <ftlL rumRL5 IH MIUllR> !1C£HRRill I IM[:_O_J_)* __,, 11 M[: !_~~~~ -9 '\ \ NNI \ NI INI ..... WSW OHSITE 3 rT GROUHD SURUEV QATR <ALL rIGURES IH MR/HR> SCENARIO TIME: /) ~)0 __,") PALISADES NUCLEAR PLANT EMERGENCY ONSITE MONITORING MAP OFFSITE RAD DATA
• OFFSITE RADIATION DATA THE FOLLOWING PAGES CONTAIN THE DATA FOR PLUME DOSE RATE DATA, THREE INCH AND THREE FOOT GROUND SURVEY DATA, GROUND FRISK DATA, AND AIR SAMPLE DATA *
• PLUME DATA THE DATA PRESENTED IS FOR THE WINDOW CLOSED READING.
10 TO DERIVE THE WINDOW OPEN READING
• MULTIPLY BY
.* .....urrent Who I e Bod~ n9e Rate ( mRem/hr )
• 12.0 SEGMENT NO* 1
\O~lt;" N TINE: 0 HR 15 NIH ISOPLETH SCALE* *5000 lf}#. Y))i*:.:.R-~.p...=:.,~ 5.000 50.00 ~ 500.0 11'1111111 e MAP SCALE IH MILES -12.e 12.e Sth 12th )3th "ti ~ ..... 16th CR-380 'O .c ~ (1\ ....... 24th co .c. (I) l(D 26th .c .... .c. +' ~ In ..... 28th 30th '-'------------~------"*-----------....JI----------- . *...:urrent Who I e Body D-e Rate ( mRem/hr )
• 12.0 SEGMENT N01 2
/O,'JO TIME: 0 HR 30 MIN ISOPLETH SCALE*
• 5000 '.?~.'?_.~W:j~-::;_.¥-~)i-.'),,io 5.000 *******************************
50.00 ~ 500. 0 111111111 0 MAP SCALE IH MILES -12.0 12.0 Sth 12th )3th "'O f.2 16th v I

c CR-380 "CJ I "I- cEi .....l:.

(1\ ...... 24th (.0 .l:. m (D 26th .s:. .r:. (.0 ihI"- 20th 30th ttrrent Whole Body DoA9Rate <mRem/hr) ~ 12.0 SEGMENT NO: 3 /o: 4/S-N TIME: 0HR 45 NIH ISOPLETH SCALE* *5000E-01 ;;~*~*~w:./-:)1-~/-:;) .5000 111!111 lll!lll!ll19!!91!! s.000 ~~a 50.00 11111111 0 MAP SCALE IH MILES I -12.e e 12.0. Sth 12th >3th "'O ~I I 16th .c ~ ~ v I i::::: CR-300 ~I .c '1.. / .J I I I 24th (1\ <O . .c Q) w I 26-th ~1 I I I .I:. IQ I I I 2Sih 30th &urrent Whole Bod!:) n& Rate (mRem/hr)
• 12.0 SEGMENT NO 1 4
/ / : 00 N TIME: I HR 0 MIN ISOPLETH SCALE* *5000E-10 =i~."ft.-Y:.i-~-'+~)1-.::.,~ .5000E-09  :::::::::::::::::::::::::::::::

-:::::::::::::::x:::-::: .

*5000E-08 ~ .5000E-07 lm8111 MAP SCALE IH MILES I -12.0 0 12.0 ~jurrent Whole Bod~ D.titd Rate (mRem/hr) *~ 12.0 SEGMENT NO 1 5 ~':oo N TINE: 1 HR 15 NIH ISOPLETH SCALE* *5000E-10 '{':if..Y);i*:}\./')_i; .5000E-09 .5000E-08 ~~ .5000E-07 lllllld e MAP SCALE IH MILES -12.0 12.0 .-urrent Wh6 I e Body n& Rate ( mRem/hr )
• 12.0 SEGMENT NO 1 6
//."/S-N TIME: 1 HR 30 MIH ISOPLETH SCALE: *5000E-10  :;~."?.5.r;,,:.1-:;)1-.,'.?--':./.; .5000E-09  ::x::~:::.:::H::H::x:::.a::: .5000E-08 ~ .5000E-07 11111111 0 MAP SCALE IH MILES -12.0 12.0 . .urrent Who I e Bod!J n& Rate ( mRem/hr )
• 12.0 SEGMENT NO 1 7
//:~D N TIME: 1 HR 45 MIH ISOPLETH SCALE1 .5000E-10 .5000E-09  :::::::::::::::::::::::::::::::

-:::r.:::-::::-:::=-::::c:: .

*5000E-08 ~~~ .5000E-07 11111'.\ll.ll
• 0 MAP SCALE IH MILES
-12.0 12.0 .urrent Who I e Body n& Rate ( mRem/hr )
• 12.0 SEGMENT NO: 9
//:4'S-TIHE: 2HR 0 MIH ISOPLETH SCALE1
• 5000E-10 lf)#_.y;;/-:)~-~-F-':.i;
.5000E-09 .5000E-08 i;z;.J(~ .5000E-07 111111111 0 MAP SCALE IN MILES -12.0 12.0 aurrent Whole Bod!:J n& Rate <mRem/hr) I 12.0 SEGMENT NO: 9 /~: oa N TIME: 2 HR 15 MIH ISOPLETH SCALE1 50
• 00 =J~Y-~'.!i)./*:)_.¥-~.F.'}1 500.0 *******************************

~::~::x:::.:::;;::x:::

5000. ~ .5000E+05 dRlllll 0 MAP SCALE IH MILES -12.0 12.0 0th 12th )3th 'lJ ~ 16th v_. I

c CR-380 "C .c

~ +" O't ...... 24th (.0 .r. Q) (D 26th .c .J: +' +' Je an ..... 20-th 30th ...urrent Who I e Body D.-e Rate ( mRem/hr )
• 12.0 SEGMENT NO: 10
/J.: I~ N TIME: 2 HR 30 MIH ISOPLETH SCALE: 50
• 00 =?~.~.y::,:+:)J.~.~~')!
500.0  ::HH:iHHH:iHHHHHH::: 5000. ~ .5000E+05 llllllB 0 MAP SCALE IH MILES -12.e 12.0 Sth 12th )3th "tJ ~ 16th CR-380 'tJ .c. ~ .... 0\ ...... 24th (1) .....c. (J) (1) 26th J: .c. fe In I'- 28th 30th aurrent Who I e Bod~ n& Rate ( mRem/hr )
• 12.0 SEGMENT NO: 11
/.} :~S N TINE: 2HR 45 MIH ISOPLETH SCALE1  ;:::~:~:::.;.::.;,l::.:.:,::,.:.: 50 .* 00 *.:.*.**.*~**:.,:,:*~... ..._.,: ...,;,:. 500.0 5000. ~
• 5000E +05 111111111 NAP SCALE IH NILES I
-12.0 0 12.0 4+0 -.J 4+8~ UI ..... O') .+ .+ J "3' 4+9Z (J) Q) J (1) tJ) ll+~z: -.J .+ ~ "::T a. 0 4+91 .,a.w -.J 4+ei 4+8 tl.urrent Whole Bod~ ni:tl:. Rate (mRem/hr) ~ 12.0 SEGMENT NO: 12 /3.'00 N TINE: 3HR 0 MIH ISOPLETH SCALE* ~:~:~::,:,:.::.:.;_::.:..:,.::.;..: 50.00 *,::.**:..:.**.:.:..""'"'...:.""!.*:* ..;,:* 500.0 5000. ~
• 5000E +05 111111111 MAP SCALE IH MILES
-12.0 12.0 9th 12th 0 )3th "'O t. f2 16th CR-380 1J .s::. ~ +' 0\ 24th (.0 .s::. +" 00 w 26-th .c .J:. +' (.0 +' ..... In ...... 28-th 30th .urrent Who I e Body DA Rate ( mRem/hr )
• 12.0 SEGHEHT HO* 13
/3  :~~ N TINE: 3 HR 15 MIH ISOPLETH SCALE* 50
• 00  :;~-~-Y;,,4:)i*~-~!.i-.)
500.0  :::-::::t:::-::::-::::-::::-::::t::. 5000. ~
• 5000E +05 111111111 0
MAP SCALE IH MILES -12.0 12.0
• Sth
. 12th )3th 2646 16th .c

t. '

'Ito CR-300 24th 26th - .....J:. . Ill 20-th - - 30th* tlurrent Whole Bod~ nJa:. Rate <mRem/hr) tt 12.0 SEGMENT NO: 14 13:~0 N TIME: 3HR 30 MIH ISOPLETH SCALE: ~:~:~::.:..:_::.:.:.,::.;.:_::.:.: 50.00 *.:,:.**.-.:.**.:.;:*"..:."""':.*.r* ....:,:* 500.0  ::::::::::::::::::::::::;::::::

-::::-::::-::::0::::-::::-::::-:::.

5000. ~ .5000E+05 1181111 0 MAP SCALE IH MILES -12.0 12.0 0 Sth 12th )3th "O c5> 3480 ..... 16th .c. \fl-o* t...... .... 'lit

c I

CR-380 ~I .c Zif} / II I I '- ....0\ 24th. U) £. (I) (.0 I 26th ~1 I I J .t:. +' IQ I I I 29th 30th
• AIR SAMPLE DATA AIR SAMPLE DATA IS FOR A 1 MINUTE - 2 CUBIC FOOT SAMPLE. MULTIPLY THE APPROPRIATE VALUE BY THE NUMBER OF MINUTES SAMPLED TO ARRIVE AT THE CORRECT CPM READING. THE DATA PRESENTED IS FOR IODINE. DIVIDE BY 10 FOR THE PARTICULATE DATA.
EXAMPLE: 2.5 MINUTE SAMPLE 300 CPM/1000 VALUE AT LOCATION = 750 CPM/1000 OR 750,000 CPM IODINE 75,000 CPM PARTICULATE IF VALUE WOULD BE OFFSCALE HIGH GIVE THE RESULT AS "OFFSCALE HIGH". AIR SAMPLE DATA IS ALSO PROVIDED IN MR/H IF DETECTABLE. PROVIDE THIS DATA ONLY IS REQUESTED
• 12.0
'ob I e A i r Sa mp I e F i I a... Data <cpm )
• SEGMENT NO: 1 10:1~
N TIME: 0 HR 15 MIH ISOPLETH SCALE:

50. 00 ~;Y.',~J.j~.f=);

500
• 0 HillfRlW'tfDRm .
• 5000E+05 lltlll!tl 0
MAP SCALE IH MILES -12.0 12.0 9th 12th "'O (") I""" 16th ..c +" I""" 8'- v ... . . I

c CR-380 0

"'O .c cG r-- +" (1\ 24th <D .t:. +" m w 26-th .c .c ~ . <D +" r- IO I"- 28-th 30th
• 1ob I e A i r Samp I e F i I 12~0 a-. Data ( c:pm )
• SEGMENT NO: 2 10:30 N TIME:* 0HR 30 MIH ISOPLETH SCALE:
50
• 00 'f~.'f..}'(),:'=',)!*~./_j; 500.0 ~
';_"'"f:."'".F..IJ. '£ '~~'J. 5000 * .l.""/....../...i::'/7..i:~;.-
• 5000E +05 B:lll\M e
NAP SCALE IH MILES -12.0 12.0 I I I 0th I 12th )3th 16th I . v I i::: CR-380 "O J: N c: ...... (J\ ~ 24th (£) .r:. .p co (0 26-th .c ...... .r:. .p (£) In ("'- 28-th 30th . . iob I e A i r Sa mp I e F i I -..... Data 12.0 <c:pm )
• SEGMENT NO: 3
/O : &/S-N TIME: 0 HR 45 MIH ISOPLETH SCALE1 50
• 00 'i~."?.-Yj{;+~./!--J 500. 0 lllBB!Ufl~
.5000E+05 0 MAP SCALE IH MILES -12.0 12.0 9th 12th )3th "'O L ...............................................a...£...6~.& .. &...~ -r tf ,t: I .c ~ I"- m " ~, I*.!~~ l"-f )]I rr it 0 ..-4 I CR-380 r if/ I \ I I *-** ---1 ttttf3l - *- - -- - - ~I J: +" fJ\ 24th (0 .. .c m w I 26th .I ~1 I l1*111u*1 -- .c +" ~ IQ I I I 28th 30th ' I - m *  ; ****.-***********-******************************************** .. ***********************************"***** ...................n ............****************
• 1'ob I e A i r Samp I e F i I .... Data ( cpm )
12.0 SEGMENT NO: 4 11:00 TIME: 1 HR 0 MIH ISOPLETH SCALE: 50
• 00 '{"?,.~'-!()J*<.<F-~i~
500.0 5000. ~y~
• 5000E +05 llllllH'ilil 0
MAP SCALE IH MILES -12.e 12.0 9th 12th )3th "'O ~ 16th CR-390 0 "O N c: .., J: O'o r-- 24th (.0 .c. .p co w 26-th ..,.t:. (.0 ...,.c. ..... In r-- 28-th 30th ,._..._ _ _ _ _ _ _ _ _ _ _...-:::------...11...........-*********************************************-****-**********************----*** ************************ **************************** 12.0 lob le Air Sample Fi 1-r Data (c:pm) SEGMENT NO: 5 11:1r N TINE: 1 HR 15 MIH ISOPLETH SCALE1 50 .00 =i~P-~~~/-:)~-~-P-':/.; 500.0 lll!Imll~ 5000 * ~/&Z,;0!-. .5000E+05 11111111 0 MAP SCALE IH MILES -12.0 12.0 0th 12th )3th 1J 0 '- (V) 16th .c. ..... 0 0 v I

E: CR-380 0

1J c: .c: N fJ\ 24th (0 """ L. m (D 26th .t:. L. +' (0 +' In ..... 28th 30th 9 iob I e 12.0 A i r Samp I e F i I -9..-. Data ( c:pm ) SEGMENT NO 1 S 11: 30 N TIME: I HR 30 MIH ISOPLETH SCALE*

50. 00 =i~."'?.-Y:).ii-~.¥~.F->

500.0 5000. ~~ .5000E+05 nmama*al 0 MAP SCALE IH MILES -12.0 12.0 8th 0 12th )3th .948 2 "O 0 L 0 6 M ..... 16th .c ~ ..... .502 ("'- 0 0 CR-380 ,,c .c ~ N O'o 0 I"- 24th (0 .....t:.m (0 26-th .I:. . ..c (0 ~ ...... In I"'- 20-th 30th *job I e A i r Samp I e F i I .... Data <c:pm ) ... 12.0 SEGMENT NO 1 7 l/:~- N TIHE: 1 HR 45 MIN ISOPLETH SCALE:

5. 000  :.f~.'f..}!i);_/*:)\./J-_j; 50.00 ~-

500.0 ~.Z,Za0. 5000
• lllllfitll 0
MAP SCALE IH MILES -12.e 12.0 ---****-*--*--***-******---*----***-*---*--****-**.------~----~------ ..... 4+0 4~0:Z: ....... UI ..... ~ O> ':I ..... "3' 4+9Z (J) Q) .+ ':I (1) ....... 4+~z: '° .+ ':I ~

0. .

08-~3 :I .....I ~ 0 ....

r 4+91

.,a. (.a.) L 0 z z;* s 4+ei 4-4-'l 0 0 4+0 tt job I e 12.0 A i r Sa mp I e F i I - Data ( cpm ) SEGMENT NO 1 9 I ).:t>O N TINE: 2 HR 0 NIH ISOPLETH SCALE* 5
• 000 '{.'?..5-f)j-!*~~-;.;.~.F-);
50.00 500.0 ~,z;. 5000. lllllltil 0 MAP SCALE IH MILES -12.0 12.0 103rd .c + co CD "C .c .c N c + + (S) CS) I"- Base Line CD 0 .c. + v CD .085 0 8th 0 12th .£.:
• 72)th +-
([) If) "'O 0 .c L (Y) I"- CR-380 IO CD "C c .c 24th 0\ M-43 .c .c +' co r-- £. (S) 26th c.o ..... .c. ..... v (D ..-4 1-------'1------------11--....---...~-------...... CD v c.o I 28th ....... I: 30-th ~lob le Air Sample Fi l~r Data (cpm) 12.0 SEGMENT NO 1 9 1;.:1J' N TIME: 2HR 15 NIH ISOPLETH SCALE* 50
• 00  ;;~p.~'.!Ci*,)!-~./-1-.'Ji 500.0 1111ClB!ttl!WIOOBM!
5000. ~z,'~ .5000E+05 NAP SCALE IH NILES -12.0 12.0 103rd s::. + CD CD 1J c N I'- Base Line ./ 0th ......... 12th .c 16th + CD IO "O .c (V) + ..... CR-380 In CD "C c .c + 24th 0\ N-43 .t::. .c +' +' .c CS) 26th 00 r-- + .c v CD (D v (D 'l"'4 I . CD I'- I: 28th 30th I . . . loble Air Sample Fi 1-tt~ Data (cpm) 12.0 SEGMENT NO: 10 12,.: J 0 N TIME: 2HR 30 MIH ISOPLETH SCALE* 50.00 500.0 5000 *
• 5000E+05 11111111 0
MAP SCALE IH MILES -12.0 12.0 103rd .I:. to CD .I:. .c co Base Line (S.l co ./ 8th 12th 16th ....CD.c IO .' . . -,, "O (") .c . .. . . ..... CR-380 IO w "C .I:. c ...... N 24th en H-43 .I:. .£:. (S) 26th 00 r-- £. .c v CD (() v ..... ..-t CD (.0 I ..... J: 28th 30th -job I e A i r Samp I e F i I .-,.... Data ( cpm ) 12.0 SEGMENT HO: 11 1;:'/r TIME: 2 HR 45 MIH ISOPLETH SCALE: 50.00 500.0 DtllBimltWJ 5000 * ~aZ<<&~
• 5000E +05 11111111 0
NAP SCALE IH NILES -12.0 12.0 103rd .c. + c.o CD Base- Line-0th 12th £. 16th + m If) "O £. L ('I) CR-380 + . . ...... IO CD "tJ J: c +" N 24th 0\ M-43 0 £. .c +' +' .c .c (0 CS) v I

c 26th 28th co CD r-(J) ....

v CD 30th . . iob I e A i r Samp I e F i I 12.0 -f" Data ( cpm ) SEGMENT N01 12 11.*.-o N TIME: 3 HR 0 HIN ISOPLETH SCALE: 50
• 00 '!}'~.~'V)/-:)-:-~./--J 500.0 lff!llllWfliiWll9Ill
• 5000E +05 1111111111.
e MAP SCALE IN MILES -12.0 12.0 103rd .c + CD CD 'O c N Base Line .c v CD 8th 12th L. 16th +- co IO "'O L. L ('I) CR-380 +- a ..... lO w 'O c .c N + 24th (J'o H-43 .J:. .J:. 26th +' 00 r- .c cs:i +' .c v CD (.0 v U) 9-4 I w ..... I: 28th 30-th. 9.ob I e A i r Samp I e F i I -~ Data ( cpm ) 12.0 SEGHEHT HO: 13 IJ ! tr-N TIHE: 3HR 15 NIH ISOPLETH SCALE* 50.00 500.0 5000
• w;z.z,z;,;~~
.5000E+05 llltBIBI HAP SCALE IH MILES -12.0 12.0 103rd .c:. + CO CO Base Line ~ 8-th 12th .r. 16-th ..... .. - 00 If) ... 0 "'O .r. L (Y) ..... .. - t- CR-380 lO lO "C c .c 24th 0\ M-43 .c:. .c:. .J:. (S) v ...-4 26th co 1-------1-..:~------:~~--t--r~----- CD +' t-CD ...~.c:. (0 I t- ~ 28th 30-th -1ob I e A i r Samp I e F i I -...... Data ( cpm ) 12.0 SEGMENT NO* 14 l'J:Jo N TIME: 3HR 30 MIH ISOPLETH SCALE: 50.00 500.0 5000.. ~W.Wa* .5000E+05 m1a1111 0 MAP SCALE IH NILES -12.0 12.0 103rd .c. + co co "O c .£:. .... *I .c. + N m (S) .. I"'- Base- Line- CD ....v.£:. (() , ~ ..... 8th 12th 16th ....m £ If) "O £ L (Y) CR-380 In ...... I"- co "C .c c .... 24th 0\ M-43 £ 26th .£:. co ....t- £ .c CS> vw-4 CD (D .... v ....(0 I co ..... :c 28th 30th 12.0 iob I e A i r Samp I e F i I -f' Data ( mR/hr ) SEGMENT HO: 1 /0!/j" N TINE: 0 HR 15 MIH ISOPLETH SCALE*
• 5000E-02 ii}if_.y:;_,4:)1<.F-');
.5000E-01 .s000 ~z,m;~ 5.000 11111111 0 MAP SCALE IH MILES. -12.0 12.0 ---*---**-***** **--*-- -*------*-*--*-----*--****-***-**-*-*---********-**..------~------------.. 4.\-0 4.\-8~ ...... UI -.I ..... CJ) ..+ J J 4+9Z m Q) 1 J O') ........ 4-l-tl "'.....J ° t-J

J

a. 0 4+8

12.0 ;ob I e A i r Samp I e F i I -~ Data ( mR/hr ) SEGMENT NO: 2 10:3 u N TIME: 0 HR 30 NIH ISOPLETH SCALE*
• 5000E-02 =i~Y-Y))i*:.:.-~~-~~-')./i
.5000E-01 .5000 ~1!@.~

5. 000 1111111*

MAP SCALE IH MILES -12.0 12.0 8th 12th )3th "C ~. I 16th .I:. it:I""' ....vI l: CR-380 .c 0 I I \. ~I 24th (J'o <.O . .c +" co (D I . 26-th ~1 I I I I .c +' IQ I I I 28-th 30th ' I - * **--****-------*-*-----*---*-*-*-*--*----"--**--**--"'*--*---*--- e1ob I e A i r Samp I e F i I --~ Data <mR/hr )
• 12.0 SEGMENT NO 1 3
/0: yr-- N. TIME: 0 HR 45 HIN ISOPLETH SCALE*
• 5000E-02 ~~.'?-..Y:)J~:)~~)!-_').,*
.5000E-01 .5000 ~m%:!'.i!':

5. 000 111111111

• 0 MAP SCALE IH MILES
-12.0 12.0 8th 12th ~ M ~ 16th £. +- ~ ~ v ..-4 I

c CR-380 0

"C £. 0 ~ +- fJ\ I"'- 24th (.I) ..c (X) (D 26th .c ..... ..c (.I) +' ....... In I"'- 28th 30th
• jOb I e A i r Samp I e F i I ...... Data ( mR/hr )
12.0 SEGMENT NO 1 4 11: .0 TIME: 1 HR 0 MIH ISOPLETH SCALE 1
• 5000E-02 'f~.':fi..5-f);./:).1<.Fj~
.5000E-01 11991!111Wl1B!m!lt! *5000 W.1'/Z,Z.,.Z-0. 5.000 11111111 0 HAP SCALE IH HILES -12.0 12.0 4+0 ..,,J 4-l-SZ ~ ';j' at J 4+9Z (1) m .+ J (1) ...... 4+PZ: '°.....

J"

~ c. 4.\-91 4-1-Zl 4..\-S ~lob le Air Sample Fi,....._ Data (mR/hr) 12.0 SEGMENT N01 _;, 11: /.f N TIME: 1 HR 15 MIH ISOPLETH SCALE:
• 5000E-10 =!~.":!f.}!i).:.i'~/-1*~./A'}o
.5000E-09 .5000E-08 'f!Z'1:9JP')!§!~
• 5000E-07 lillllllliiillill 0 "?\-UV\')' *\~ \'DD
=:l:+/-+/-=~-+-~~**-1 °b \~i'6~~~b TO ~E'AD . 1=11-TE R b~-ri-\ ~~ "'~' ~. ~Y\+~I 5~~e."\ M:~ MAP SCALE IH MILES I -12.0 0 12.0 e12.0 1ob I e A i r Samp I e F i I a.. Data ( mR/hr )
• SEGMENT NO 1 6 II :Jo N TIME: 1 HR 30 MIH ISOPLETH SCALE:
*5000E-10  ;;~-~-~w:.:.t+~'-~;~./1-.':.,'; .5000E-09 .5000E-08 ~IP.Ybf~
• 5000E-07 IJlll!IBliil!illlll 0
MAP SCALE IH MILES -12.0 12.0 12.0 iob I e A i r Samp I e F i I -fr Data ( mR/hr )
• SEGMENT NO 1 7 11.* 11.r N TIME: 1 HR 45 MIH ISOPLETH SCALE*
• 5000E-10 =i~.'?..}!:'j.:;_.<i-~.F->
.5000E-09 lllE!IMl9!DI! .5000E-08 ~~;y~~
• 5000E-07 11111111
• 0 MAP SCALE IH MILES
-12.0 12.0 . . job le Air Sample Fi l~r Data (mR/hr) 12.0 SEGMENT NO: 0 /.;i.: oO N TIME: 2 HR 0 MIH ISOPLETH SCALE* *5000E-10 =.r~.'fa.-~W::i-:.:_R-~./i--); .5000E-09 .5000E-08 ~ .5000E-07 llllllill* 0 MAP SCALE IH MILES -12.0 12.0 ~lob le Air Sample Fi I_,~ Data <mR/hr) 12.0 SEGMENT HO: 9 ,-,,:1r N TINE: 2 HR 15 NIH ISOPLETH SCALE:
• 5000E-02 '-i~.'?..'Yj~)\)i-.';);
.5000E-01 ~ . *5000 ~}:~f-0. 5.000 lllfililll 0 MAP SCALE IH MILES -12.0 12.0 103rd £ + CD CD Base Line 8th 12th £. +- 16th 00 IO "O £. ('I) +- t- CR-380 IO . CD 'tJ c .c N 24th 0\ M-43 £. £. ..... ..... .J:. (S) 26th co t-(.Q ..... .J:. v . CD v ..... ....-1 CD (0 I 28th t- I: 30th ~job le Air Sample Fi I...... Data <mR/hr) 12.0 SEGMENT NO* 10 1:>-=10 N TIME: 2HR 30 MIH ISOPLETH SCALE:
• 5000E-01  ;;~p.y:)i-1-:;_.\/1=.>*
• 5000 mmMetlllleMm 5.000 '.~..Y.1:§1*-
50.00 11111111 0 MAP SCALE IH MILES -12.0 12.0 103rd .c + co co "O .c c + N ,..... ts) Base- Line- c.o 8th 12th .c. +" 16th (X) If) ,,l.. .c. (V) +" ....... CR-380 IO CD "C .t:. 0 c +" 24th CJ\ M-43 .t:. s:. ...§ .t:. CS) v 26th co CD t-(D .....t:.v (.0 .,.;J I co ....... I: 28th 30th 12.9 job I e A i r Samp I e F i I - r Data ( mR/hr ) SEGMENT NO* 11 /.).:'(S-N TINE: 2HR 45 MIH ISOPLETH SCALE*
• 5000E-01  :;~y.y;;,<.i!-~./-i--'~;;
.5000 ~ 50~00 111111111 0 MAP SCALE IH MILES -12.0 12.0 103rd Base Line 8th 12th .....cco 16th If) 'O .c L (Y) .... ..... CR-380 IO CD 'O .s:::. N c ..... 24th CJ\ M-43 .r:. .... .s:::. co .... ..c § ..c CS) v 26th CD t-(() ....v (0 I CD ....... I: 28th 30th ~ioble Air Sample Fi 1.ttr Data (mR/hr) 12.0 SEGMENT NO: .12 1~:oa N TINE: 3HR 0 HIN ISOPLETH SCALE*
• 5000E-01 {'!f..Y,')-;;.JJ.~.~¥-.'};
.5000 ~ 5.000 ~z;.z~ 50 a00 llJtl'll'lll 0 NAP SCALE IH NILES -12.0 12.0 103rd "O c N ..... Base Line 8th .. 12th .£:. +- 16th Q) If) 0 "O .£:. L +- (Y) ..... CR-380 If) CD "IJ c .c N +- 24th (J'o H-43 .I:. .I:. +" +- .t::. (ti 26th co t- +- .J: v CD CD v -+' CD <O I ..... I: 28th 30-th e 1ob I e 12.0 A i r Samp I e F i I .ttr Data ( mR/hr ) SEGMENT NO: 13 /J;/t' TINE: 3 HR 15 MIH ISOPLETH SCALE:
• 5000E-01 lf}'~*~'*i:i)ji-~'..'*:./i-.J
.5000 I~ 50.00 0 MAP SCALE IH NILES -12.0 12.0 103rd .c + co co 'tJ c N ...... Base- Line-8th 12th ..c. +- 16th 00 If) 'tJ .c L +- (I') ...... CR-380 IO CD "O c .c N +- 24th (J'o H-43 .c .c +' +- .r:. ~ .r:. CS) v 26th 00 CD CD .... <O I (D ...... :c: 28th 30th **ob I e A i r Samp I e F i I 12.0 a-. Data <mR/hr )
• SEGMENT N01 14 N TINE: 3 HR/J:
30'" MIH ISOPLETH SCALE* .5000E-01 =i~P-Y,'.f:;_i-j~');
• 5000 IBl!lm001 5
• 000  :?WZ..Y./.Z~b.
50.00 0 MAP SCALE IH MILES -12.0 12.0 103rd .s: +- c.o CD Base- Line-I:. +' v c.o 8th 12th .£. +- 16th Q) IO "O .£. L +- ('I) I"'- CR-380 IO CD "C c .s: +- 24th (J\ H-43 ~ .£. +' +' .c.
• ~ CS) 26th co r- -fJ'
• ~ .c. v c.o CD v
-fJ' .... (.0 (0 I 28th I"'- I: 30th
• GROUND FRISK DATA IF A GROUND SMEAR IS TAKEN MULTIPLY THE APPROPRIATE GROUND FRISK NUMBER BY FOUR TO GIVE CPM/100 SQ CM .
~round 12.0 FrisK Data (c~)
• SEGMENT HO: 1 1tJ ~ IS' N TIME: 0 HR 15 MIH ISOPLETH SCALE:
• 5000 '{?..:,W~',==<'.=\.'.!</-1 5.000 mlltl!RM!Il!IMm 0
-12.0 12.0 - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ J 8th 12th )3th "'O ~ r-- 16th v I i: CR-380
• 'U N
c: r-- 24th J: 0\ (0 .r. +' (X) (0 26th .t:. U) J: +' Ill "" r-- 20-th 30th ~round Frisk Data <c'9) 12.0 SEGMENT NO: 2 N TIME: 10: ""o 0HR 30 MIH ISOPLETH SCALE* . 5.000 50.00 500.0 ~~ 5000. 11111111 0 NAP SCALE IH NILES -12.0 12.0 Sth 12th )3th "O M ..... 16th .c I""- ..... v I I:: CR-380 0 u .c c: ..... N Q'e I""- 24th (1) .c +' (D (0 26th .c. .t:. -fJ (1) ..... If) I""- 28th I"- 30th .*-round Fr i sk Data ( 12.0 elf) ** SEGMENT NO: 3. 1a: 'If" N. TINE: 0HR 45 NIH ISOPLETH SCALE: 5
• 000 =ry.y,:,>~)\)':.)i 50.00 ~
500.0  !.1!'19Z11~!'*' 5000. 111111111 0 MAP SCALE IH MILES -12.0 12.0 0th 12th )3th 16th CR-390 'tJ J: c: +" N C1'o I"- 24th (1) .c +' m w 26th .c ..... .c (I) .... In ....... 28th I"- .......,___________ 30th around Frisk Data 12.0 <c#ft) ** SEGMENT HO: 4 II: .,o TIME: 1 HR 0 MiH ISOPLETH SCALE: 5 *000 . :;~y.y;;_/-)\.~'J:.j; 50.00 500.0 ~Z~!~ 5000. 11111111 0 MAP SCALE IH MILES -12.0 12.0 Sth 12th )3th "O ..... 16th 0 CR-380 0 'tJ .c ~ +" ."'"" 24th Q\ (1) .c t itO 0 26th s:. .I:. +' (1) +' Ill ..... 20th 30th r . ~round FrisK Data <elf) 12.0 SEGMENT NO: 5 11:1r N TIME: l HR 15 NIH ISOPLETH SCALE* 5
• 000 '{'?.Y::/-:)!*~-F-J 50.00 500.0 ~Z?QY./.&a.
5000. 111111111 e MAP SCALE IH MILES I -12.e e 12.e 9th 12th )3th j
• I~ HI 1 /0 "tJ
~, llt:l~I!~ .075 0 ~J fY* J v ..-t 0 1':1_ I CR-380 0 - ~-- 7161 I ( 0 ~I .c +" O"t 24th U) * £. +" co w I 26th ~1 I I -**n * ,J..... I £. +' IQ I I I 29-th 30th ' I -
• IL--*-----***-**--*****-******-*--*--**-**-******--*----*---***"-***---*--*-**-"**---**----
~round Frisk Data <c6f) 12.0 SEGMENT N01 6 II: 1iJ N TIME: 1 HR 30 MIH ISOPLETH SCALE*  ;..,=::.,:..:::~::.,:.;.::..:.:,::~::.:..: 5.000 *.:,.*.**.*.:.**.:.::*"'..:."'":.'.:""":.;:* 50.00 500.0 ~~~ 5000. 111111111 MAP SCALE IH MILES I -12.0 0 12.0 8th lllllll,)3th 12th "O J; I"- 16th 0 v I

c CR-380 0

'O .c 0 N c: ....O'o ..... 24th U) .t::. (D w 26-th 28-th 30th '-&----...::------=------...II---*----**-*--*-*--**--**--*-**--**--**---------** *--*---*-- . .round Fr i sk Data ( c.lf) 12.0 SEGMENT HO: 7 II :q.r' N TIME: 1 HR 45 MIH ISOPLETH SCALE* 5
• 000  :?~.'f.-Y);/*~-~~-F-':./.;
50.00 500.0 ~bX:-0. 5000. * ******* 0 MAP SCALE IH MILES -12.0 12.0 0 8th 0 12th )3th .059 1J 0 (V) ..... 16th I .c. 0 +' ..... v .0 ..... I ~ CR-380 0 0 'tJ .c c +' N 0-. I"- 24th <D ....m.J:. w 26-th .c CD .J:. +' ..... In I'- 28th 30th tl;round FrisK Data <ctJt) 12.0 ,,.:oo SEGMENT HO 1 9 N TINE: 2 HR 0 NIH ISOPLETH SCALE1 5
• 000 '{'?,.y:;_;.~.¥~./i*-'.i~
s0.00 **eatte 5000
• 1111111&1 0
MAP SCALE IH MILES -12.0 12.0 Sth 0 12th )3th "'O .085 '- (V) r- 16th .121 .c 0 r-r- 0 CR-300 .c ~I 24th (1\ U) * .c m CD I 26th .,Jrwr . ~1 I I ** A I .c. IQ I I I 28-th , _30th ~round FrisK Data <cit) 12~0 N SEGMENT NO: TINE: ,,:,r 2 HR 15 MIH 9 ISOPLETH SCALE: 5
• 000  :.?~.x.Y:.:,,:-1.:.:,.:~-~-F-'J 50.00 500.0 ~~.if-:
5000. llllllmt NAP SCALE IH MILES I -12.0 0 12.0 103rd .c + c.o c.o Base Line .J::. +' v c.o 0 8th .055 0 12th £. +- (0 In 0 0~ (Y) £. +- I"- CR-380 lO w "C c .c 0 24th CJ\ N-43 .£:. s:::. +' +' CS) 26th 00 f'- s:. ..... v ~ CD CD (0 I 28th I"- :c 30th *uround FrisK Data (c~) 12.0 SEGMENT HO: 10 I.).: Jib N TIME: 2 HR 30 MIN ISOPLETH. SCALE* 50
• 00 'f~.'?.-Y:.:i*:))i*~-~~-':./*
500.0 mmll!Mlt919001! 5000. !Z1W~
• 5000E +05 11111111 0
MAP SCALE IH MILES I -12.0 0 12.0 103rd £ CD CD 0 "O .c £ c: ...... ...... N CS) (S) I"- Base- Line- CD 0 .c. +' v CD .022 8th .055 0 12th ..c +- co 0 16th In "O 0 ..c L +- (Y) I"- CR-380 In CD 0 "C .c c ....... N 24th (J\ H-43 .c .c co ,.... .c .c CS) v 26th . co (() .... v (0 .-I I CD ....... :c 28th 30-th ~round Frisk Data <c#f) 12.0 SEGMENT NO: 11 /l.: c/J" , TIME: 2 HR 45 MIH ISOPLETH SCALE* 50
• 00 =i;p.y;~4:)..\.F-':./;
500 .0 OJ!RB".mB 5000 * ~D.m:~fl~
• 5000E +05 111111111 0
MAP SCALE IH MILES -12.0 12.0 103rd .I:. + ((I ((I "'O .l:. .I:. cEi +- + CS) ~ I"- Base- Line- CD 0 .021 .t:. +- v CD .077 9th 12th .079 £. + c.o 16th If) 'U £. L (V) + I"- CR-380 lO w "'O c .c N 24th (J'lo H-43 .J:. £. +- +' .t:. ~ .c. (S) v 26th 00 CD I"- CD .... v CD .-4 I w I"- l: 28th 30th ~round 12.0 Frisk Data <c6') ** SEGMENT NO: 12. 11:,.. N TINE: 3 HR 0 MIH ISOPLETH SCALE* 50
• 00  ;;~y.y:;/-,)~~)!-.j-;
500.0 lll!lelllB~ 5000. ~Y/.Y.~
• 5000E +05 llHtllM\i!'I 0
MAP SCALE IH MILES -12.0 12.0 *uround FrisK Data 12.0 <c~)
• SEGMENT N01 13 13 :11" N TINE: 31-tR 15 MIH ISOPLETH SCALE*
50.00 500.0 5000. ~}%~)!-: .5000E+05 1111'.ltlll
• e MAP SCALE IH MILES
-12.0 12.0 103rd J:. + c.o CD "O J:. J:. *c ...... + N cs:i (S.l r- Base- Line- c.o 0 £. v c.o ... 028 8th .. 053 12th .c 16th 00 LO ,, .c (Y) + ~ CR-380 . IO CD "C J: c + 24th er. *N-43 J:. s:. ..... ..... s:. ~ m 26th . co r- ..... .c v co (() v (.0 r- ~ I I: 28th CD 30th . uround FrisK Data 12.0 (cJ"") SEGMENT N01 14 l'J :10 N TIME: 3 HR 30 MIN ISOPLETH SCALE: 50
• 00 '.f~.'?_}::.f;;_/;*:;,.i!-~./--J 500 .0 matat!WWW 5000. ~19Z~
• 5000E +05 lllllllltl 0
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WSI FORECAST The information presented on the following page provides the Palisades meteorological forecast that is available through the Weather Services International (WSI) service. The first forecast should be provided to the players if they access WSI and request a weather forecast prior to 10:00 AM. The second forecast should be provided anytime afte~ 10:00 AM . METEOROLOGICAL FORECAST DATA
• AVAILABLE BEFORE 10:00 AM ON 9/1/92 INTERPOI.ATED MOS FOR PAL(4219N,8619W) USING ORD,SBN,GRR:
DY/HR 01/06 01/12 01/18 02/00 02/06 02/12 02/18 02/00 GMT DY/HR 01/01 01/07 01/13 01/19 02/01 02/07 02/13 02/19 EST WIND-MP 2210 2108 2310 1810 1915 2003 2403 1205 CLDS-.1 10 10 10 7 3 7 5 9 HGT-FT 1000 1850 1900 3750 5150 4700 4250 5500 PAS E D D E F E D D AVAILABLE AFTER 10:00 AM ON 9/1/92 INTERPOIATED MOS FOR PAL(4219N,8619W) USING ORD,SBN,GRR: DY/HR 01/18 02/00 02/06 02/12 02/18 03/00 03/06 03/12 GMT DY/HR 01/13 01/19 02/01 02/07 02/13 02/19 03/01 03/07 EST WIND-MP 2210 1915 2009 2007 2310 2004 1803 1505 CLDS-.1 10 10 10 10 10 7 2 0 HGT-FT 1000 1850 1900 3750 5150 4700 4250 5500 PAS E -. D F E E c D D WSI HOURLY :MET DATA The information presented on the following page provides hourly National
• Weather Service data available through the Weather Services I~ternational (WSI) service. This information should only be provided to the players if they access the WSI system and request hourly meteorological data for Benton Harbor and/or Muskegon. If the Players do not access the YSI system and request this data then the data should not be given to the players .
NATIONAL WEATHER SERVICE DATA WSI SYSTEM Observations for 8AM(01Z) 1-SEP-92 Station Name Wind PS Benton harbor, MI 2301 E Muskegon, MI 2202 E Observations for 9AM(02Z) l-SEP-92 Station Name Wind PS Benton harbor, MI 2301 E Muskegon, MI 2201 E Observations for 10AM(03Z) l-SEP-92 Station Name Wind PS Benton harbor, MI 2202 D Muskegon, MI 2203 D Observations for 11AM(04Z) l-SEP-92 Station Name Wind PS Benton harbor, MI 2203 D Muskegon, MI 2202 D
• Observations for 12AM(OSZ)
Station Name *Benton harbor, MI Muskegon, MI l-SEP-92 Wind 2204 2303 PS D D Observations for 1PM(06Z) l-SEP-92 Station Name Wind PS Benton harbor, MI 2202 D Muskegon, MI 2203 D Observations for 2PM(07Z) l-SEP-92 Station Name Wind PS Benton harbor, MI 2202 E Muskegon, MI 2302 E Observations for 3PM(08Z) l-SEP-92 Station Name Wind PS Benton harbor, MI 2302 E Muskegon, MI 2401 E ONSITE MET TOWER The meteorological data presented on the following page provides the primary
• meteorological data for PALEX-92. This data should be provided by controllers whenever, the players access the onsite meteorological monitoring system from either the Control Room, Technical Support Center, or Emergency Operations Facility. This data should only be provided to the-players if they actually go through the process of accessing and displaying data from the onsite meteorological monitoring system .
PARAMETER TEMP STAB DT WSlO WDlO SIGl WS60 WD60 SIG6
• UNITS __ c PASO _£_ MPH DEG DEG MPH DEG DEG 09/01/92 08:00 19.8 E 1.72 3.03 126 13.2 8.01 132 0.9 09/01/92 08:15 21.0 E 1.53 3.05 127 14.4 3.7 -136 10.8 09/01/92 08:30 22.9 E 1.14 3.72 134 15.3 4.13 140 8.6 09/01/92 08:45 23.l D .75 3.64 142 16.7 4.06 153 7.6 09/01/92 09:00 23.6 D -.87 3.07 153 17.2 4.01 162 0.9 09/01/92 09:15 24.0 D -1.78 2.05 187 4.4 3.25 192 11.8 09/01/92 09:30 25.7 D -1.74 2.02 210 15.3 4.13 222 7.6 09/01/92 09:45 26.3 D -1.75 2.14 220 16.7 4.06 238 8.9 09/01/92 10:00 27.5 D -2.39 2.02 221 27.5 3.13 242 13.9 09/01/92 10:15 28.0 D -2.41 2.00 225 27.1 3.03 243 12.0 09/01/92 10:30 28.4 D -2.53 2.50 224 27.9 3.43 242 12.4 09/01/92 10:45 28.8 D -2.56 2.90 226 28.7 3.93 244 13.7
• 09 /01/92 11: 00 30.3 D -1.72 3.10 227 29.3 3.23 244 15.6 09/01/92 11:15 31.4 D -1.68 3.30 227 23.9 3.93 244 13.0 09/01/92 11:30 32.6 E -1.36 3.70 226 25.2 4.34 243 10.8 09/01/92 11:45 32.4 E -1~62 3.50 227 23.0 4,27 244 11.7 09/01/92 12:00 32.2 D -1.36 3.80 228 21.6 4.47 245 10.9 09/01/92 12:15 32.2 D -1.11 3.90 229 22.2 4.57 246 10.9 09/01/92 12:30 31.4 D -.48 3.80 227 22.0 4.47 244 10.5 09/01/92 12:45 30.3 E .21 3.80 225 20.2 3.93 244 9.2 09/01/92 13:00 28.8 D 1.03 3.20 226 21.3 3.23 244 9.1 09/01/92 13:15 25.5 D 1.68 2.70 225 19.9. 3.03 240 7.6 09/01/92 13:30 26.2 D 1.99 2.50 224 20.0 2.98 237 8.6 09/01/92 13:45 23.5 E 1.22 4.09 217 24.3 4.9 222 15.0 09/01/92 14:00 23.8 D 1.23 4.20 216. . 21.3 3.23 221 9.1
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