Text

1993 Palisades Emergency Exercise Scenario.
	ML18059A523
Person / Time
Site:	Palisades
Issue date:	11/18/1993
From:	; CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	;
Shared Package
ML18059A522	List: ML18059A521; ML18059A523;
References
	NUDOCS 9312020078
	Download: ML18059A523 (432)
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ATTACHMENT Consumers Power Company Palisades Plant Docket 50-255 1993 PALISADES EMERGENCY EXERCISE SCENARIO

November 18, 1993

PALEX-93

TABLE OF CONTENTS SCOPE AND OBJECTIVES EXERCISE CONDUCT EXERCISE ORGANIZATION CONTROLLER ORGANIZATION EXERCISE DATA AND MESSAGES CRITIQUES EVALUATOR CHECKLISTS EXERCISE DATA SEQUENCE OF EVENTS NARRATIVE

SUMMARY

MEDICAL SPECIFICS

MAINTENANCE ACTIVITIES MESSAGE SHEETS CFMS OPERATIONS DATA CFMS RADIATION DATA RAD MONITOR DATA INPLANT RADIATION DATA ONSITE RAD DATA CFMS METEOROLOGICAL DATA WSI FORECAST WSI HOURLY METEOROLOGICAL DATA ONSITE MET TOWER

SCOPE AND OBJECTIVES

PALEX-93 SCOPE AND OBJECTIVES

SCOPE PALEX-93 is designed to meet exercise requirements specified in 10 CFR 50, Appendix E, Section IV.F. PALEX-93 is a utility only exercise and will not include the participation of local governments. State personnel will participate only to the extent of answering phones and supplying information on simulated offsite actions. The Joint Public Information Center will not 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 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.

personnel in accordance with procedures.

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

d. Monitor, track and document radiation exposure to maintenance, operations, and moriitoring 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. Update status boards at least every 30 minutes.

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

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

5. Direction and Control,

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

b. Coordinate maintenance activities.

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

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, field team progress, and offsite actions as appropriate.

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

k. Demonstrate reentry and recovery in accordance with procedures.

6. Exercise Control

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

b. Accurately assess performance of exercise players and controllers.

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. Each CPCo Controller/Evaluator must submit a completed, signed Evaluator Checklist at the conclusion of the exercise. NRC evaluators will also be present for the exercise.

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

Controller/Evaluators are authorized to modify scenario data as judged appropriate.

Howeve:r, 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/Evaluator 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 assigned to each Emergency Response Facility and is responsible for addressing Player inquiries, conducting a post exercise critique, and collecting completed Evaluator Checklists following the exercise.

Controller/Evaluators will refer all Player inquiries to the Lead Controller if possible.

If the Lead Controller is not able to answer the question, it should be referred to the Exercise Coordinator .

EXERCISE DATA AND MESSAGES

Messages and data to drive .Player actions are contained in Section 3, Exercise Data.

Refer to the Table of Contents for headings.

It is each Controller/Evaluator's responsibility to be fully familiar with the scenario package and ensure that only appropriate information is provided to Players. 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 that the Player was prompted.

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.

CONTROL ROOM EVALUATOR CHECKLIST

1. ASSESSMENT AND CLASSIFICATION OVERALL: MET NOT MET

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

MET MET/PROBLEM NOT MET N/A EXPLANATION:

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

MET MET/PROBLEM NOT MET N/A EXPLANATION:

PAGE 1 OF 7

2. COMMUNICATIONS l

OVERALL: MET NOT MET

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

MET MET/PROBLEM NOT MET N/A EXPLANATION:

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

MET MET/PROBLEM NOT MET N/A EXPLANATION:

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

MET MET/PROBLEM NOT MET N/A EXPLANATION:

PAGE 2 OF 7

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

MET MET/PROBLEM NOT MET N/A

EXPLANATION:

3. RADIOLOGICAL ASSESSMENT AND CONTROL OVERALL: MET NOT MET

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

MET MET/PROBLEM NOT MET N/A EXPLANATION:

PAGE 3 OF 7

4. EMERGENCY RESPONSE FACILITIES OVERALL: MET NOT MET

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

MET MET/PROBLEM NOT MET N/A EXPLANATION:

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

MET MET/PROBLEM NOT MET N/A EXPLANATION:

e. Track and prioritize status of key inplant jobs.

MET MET/PROBLEM NOT MET N/A EXPLANATION:

PAGE 4 OF 7

5. DIRECTION AND CONTROL OVERALL: MET NOT MET

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

MET MET/PROBLEM EXPI.ANATION:

NOT MET N/A

b. Coordinate maintenance activities.

MET MET/PROBLEM NOT MET N/A EXPI.ANATION:

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

MET MET/PROBLEM NOT MET N/A EXPI.ANATION:

PAGE 5 OF 7

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

MET l'IBT/PROBLEM NOT MET N/A

EXPLANATION:

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

MET MET/PROBLEM NOT MET N/A EXPLANATION:

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

MET MET/PROBLEM NOT MET N/A EXPLANATION:

PAGE 6 OF 7

6. EXERCISE CONTROL OVERALL: MET NOT MET

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

MET MET/PROBLEM EXPLANATION:

NOT MET N/A

b. Accurately assess performance of exercise players and controllers.

MET MET/PROBLEM NOT MET N/A EXPLANATION:

c. Adequacy of scenario data.

MET MET/PROBLEM NOT MET N/A EXPLANATION:

Name:

PAGE 7 OF 7 Date:

TSC EVALUATOR CHECKLIST

1. ASSESSMENT CLASSIFICATION

.AND OVERALL: MET NOT MET

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

MET MET/PROBLEM NOT MET N/A EXPLANATION:

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

MET MET/PROBLEM NOT MET N/A EXPLANATION:

PAGE 1 OF 8

2. COMMUNICATIONS OVERALL: MET NOT MET

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

MET MET/PROBLEM NOT MET N/A EXPLANATION:

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

MET MET/PROBLEM NOT MET N/A EXPLANATION:

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

MET MET/PROBLEM NOT MET N/A EXPLANATION:

PAGE 2 OF 8

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

MET .MET/PROBLEM NOT MET N/A

EXPI.ANATION:

3. RADIOLOGICAL ASSESSMENT AND CONTROL OVERALL: MET NOT MET

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

MET MET/PROBLEM NOT MET N/A EXPLANATION:

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

MET MET/PROBLEM NOT MET N/A EXPLANATION:

PAGE 3 OF 8

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

MET .MET/PROBLEM NOT MET N/A

EXPLANATION:

f. Identify appropriate protective action recommendations.

MET MET/PROBLEM NOT MET N/A

EXPLANATION:

PAGE 40F 8

4. EMERGENCY RESPONSE FACILITIES OVERALL: MET NOT MET

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

MET MET/PROBLEM NOT MET N/A EXPLANATION:

c. Update status boards at least every 30 minutes.

MET MET/PROBLEM NOT MET N/A EXPLANATION:

e. Track and prioritize status of key inplant jobs.

MET MET/PROBLEM NOT MET N/A EXPLANATION:

PAGE 5 OF 8

5. DIRECTION AND CONTROL OVERALL: MET NOT MET

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

MET MET/PROBLEM NOT MET N/A EXPLANATION:

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

MET MET/PROBLEM NOT MET N/A EXPLANATION:

d. Dispatch field teams in accordance with procedures.

MET MET/PROBLEM NOT MET N/A EXPLANATION:

e. Direct and monitor field team actions.

MET MET/PROBLEM NOT MET N/A

PAGE 6 OF 8

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

MET . .MET/PROBLEM NOT MET N/A

EXPLANATION:

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

MET MET/PROBLEM NOT MET. N/A EXPLANATION:

h. Brief Emergency Response Facility staffs approximately every 30

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

MET MET/PROBLEM EXPLANATION:

NOT MET N/A

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

MET MET/PROBLEM NOT MET N/A EXPLANATION:

PAGE 7 OF 8

.d

6. EXERCISE CONTROL OVERALL: MET NOT MET

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

MET MET/PROBLEM EXPLANATION:

NOT MET N/A

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

c. Adequacy of scenario data.

MET MET/PROBLEM NOT MET N/A EXPLANATION:

Name:

PAGE 8 OF 8 Date:

OSC EVALUATOR CHECKLIST

2. COMMUNICATIONS OVERALL: MET NOT MET

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

MET MET/PROBLEM NOT MET N/A EXPLANATION:

3. RADIOLOGICAL ASSESSMENT AND CONTROL OVERALL: MET NOT MET

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

MET MET/PROB~EM NOT MET N/A EXPLANATION:

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

MET MET/PROBLEM NOT MET N/A EXPLANATION:

PAGE 1 OF 5

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

MET ..MET/PROBLEM NOT MET N/A

EXPLANATION:

4. EMERGENCY RESPONSE FACILITIES OVERALL: MET NOT MET

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

MET MET/PROBLEM NOT MET N/A EXPLANATION:

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

PAGE 2 OF 5

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

MET . .MET/PROBLEM NOT MET N/A

EXPLANATION:

e. Track and prioritize status of key inplant jobs.

MET MET/PROBLEM NOT MET N/A EXPLANATION:

5. DIRECTION AND CONTROL OVERALL: MET NOT MET

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

MET MET/PROBLEM NOT MET N/A EXPLANATION:

PAGE 3 OF 5

b. Coordinate maintenance activities.

MET MET/PROBLEM NOT MET N/A

EXPLANATION:

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

MET MET/PROBLEM NOT MET N/A EXPLANATION:

d. Dispatch field teams in accordance with procedures.

MET MET/PROBLEM NOT MET N/A

EXPLANATION:

e. Direct and monitor field team actions.

MET MET/PROBLEM NOT MET N/A EXPLANATION:

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

MET MET/PROBLEM NOT MET N/A EXPLANATION:

PAGE 4 OF 5

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

MET 'MET/PROBLEM NOT MET N/A EXPLANATION:

6. EXERCISE CONTROL OVERALL: MET NOT MET

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

MET MET/PROBLEM NOT MET N/A EXPLANATION:

b. Accurately assess performance of exercise players and controllers.

MET MET/PROBLEM EXPLANATION:

NOT MET N/A

c. Adequacy of scenario data.

I MET MET/PROBLEM NOT MET N/A EXPLANATION: _

Name:

PAGE 5 OF 5 Date:

RMT EVALUATOR CHECKLIST

2. COMMUNICATIONS

OVERALL:

d.

MET NOT MET Provide updates between appropriate Emergency Response Facilities at least every 30 minutes.

MET MET/PROBLEM NOT MET N/A EXPLANATION:

3. RADIOLOGICAL ASSESSMENT AND CONTROL

OVERALL:

a.

MET NOT MET Collect radiological survey data.

MET MET/PROBLEM NOT MET N/A EXPLANATION:

PAGE 1 OF 3

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

MET l1ET/PROBLEM NOT MET N/A

EXPLANATION:

g. Perform environmental monitoring in accordance with procedures.

MET MET/PROBLEM NOT MET N/A EXPLANATION:

5. DIRECTION AND CONTROL OVERALL: MET NOT MET

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

MET MET/PROBLEM NOT MET N/A EXPLANATION:

PAGE 2 OF 3

6. EXERCISE CONTROL OVERALL: MET NOT MET

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

MET MET/PROBLEM EXPLANATION:

NOT MET N/A

b. Accurately assess performance of exercise players and controllers.

MET MET/PROBLEM NOT MET N/A EXPLANATION:

c. Adequacy of scenario data.

MET MET/PROBLEM NOT MET N/A EXPLANATION:

PAGE 3 OF 3 Name: Date:

EOF EVALUATOR CHECKLIST

1. ASSESSMENT.:AND CLASSIFICATION

OVERALL:

a.

MET NOT MET Assess conditions which warrant classification within fifteen minutes of being provided those conditions.

MET MET/PROBLEM NOT MET N/A EXPLANATION:

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

MET MET/PROBLEM NOT MET N/A

EXPLANATION:

2. COMMUNICATIONS OVERALL: MET NOT MET

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

MET MET/PROBLEM NOT MET N/A EXPLANATION:

PAGE 1 OF 8

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

MET 1'1ET/PROBLEM NOT MET N/A

EXPLANATION:

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

MET MET/PROBLEM NOT MET N/A EXPl.ANATION:

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

MET MET/PROBLEM NOT MET N/A EXPLANATION:

PAGE 2 OF 8

3. RADIOLOGICAL ASSESSMENT AND CONTROL OVERALL: MET NOT MET

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

MET MET/PROBLEM EXPLANATION:

NOT MET N/A

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

MET MET/PROBLEM NOT MET N/A EXPLANATION:

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

MET MET/PROBLEM NOT MET N/A EXPLANATION:

PAGE 3 OF 8

f. Identify appropriate protective action recommendations.

MET MET/PROBLEM NOT MET N/A EXPLANATION:

g. Perform environmental monitoring in accordance with procedures.

MET MET/PROBLEM NOT MET N/A EXPLANATION:

PAGE 4 OF 8

4. EMERGENCY RESPONSE FACILITIES OVERALL: MET NOT MET

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

MET MET/PROBLEM EXPLANATION:

NOT MET N/A

c. Update status boards at least every 30 minutes.

MET MET/PROBLEM NOT MET N/A EXPLANATION:

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

MET MET/PROBLEM NOT MET N/A EXPLANATION:

PAGE 5 OF 8

5. DIRECTION AND CONTROL OVERALL: MET NOT MET

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

MET MET/PROBLEM EXPLANATION:

NOT MET N/A

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

MET MET/PROBLEM NOT MET N/A EXPLANATION:

e. Direct and monitor field team actions.

MET MET/PROBLEM NOT MET N/A EXPLANATION:

PAGE 6 OF 8

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

MET .MET/PROBLEM NOT MET N/A

EXPLANATION:

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

MET MET/PROBLEM NOT MET N/A EXPLANATION:

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

MET MET/PROBLEM NOT MET N/A EXPLANATION:

PAGE 7 OF 8

6. EXERCISE CONTROL OVERALL: MET NOT MET

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

MET MET/PROBLEM NOT MET N/A EXPI.ANATION:

b. Accurately assess performance of exercise players and controllers.

MET MET/PROBLEM NOT MET N/A EXPI.ANATION:

c. Adequacy of scenario data.

MET MET/PROBLEM NOT MET N/A EXPI.ANATION:

Name:

PAGE 8 of 8 Date:

SEQUENCE OF EVENTS

SCENARIO

SUMMARY

PALEX-93 involves a fuel handling accident with personnel injuries. A release to the environment occurs.

The Control Room simulator will be used and run in real time mode, although its usefulness and the ability to simulate the postulated conditions in the Fuel Pool Area is extremely limited. Reactor plant conditions will remain relatively static throughout the exercise. Backup plant conditions data sheets have been prepared and will be used if needed.

SEQUENCE OF EVENTS:

-0030/0800 Initial conditions are provided to players:

The plant is in Cold Shutdown at the end of core life. Preparations for refueling are in progress. Fuel handling operations in the Spent Fuel Pool are in progress.

Equipment degraded/out of service:

Safeguards Transformer 1-1

Spent Fuel Pool Cooling Pump P-51A Normal shutdown alarms are annunciated.

A severe storm warning has been issued and a tornado watch is in effect.

0000/0830 The exercise begins when a lightning strike disables Station Power Transformer 1-2. Shutdown Cooling is briefly lost, Spent Fuel Pool cooling is lost and the Spent Fuel Handling Machine, with a spent fuel bundle in the mast, is disabled.

0015/0845 A tornado destroys the Spent Fuel Handling Area and spreads debris along the north-south access road leading to Lake Michigan.

Two operators are injured and rendered unconscious. The Fuel Pool begins to leak into the south Tilt Pit. An "ALERT' or hia=her should be declared.

0030/0900 The damaged fuel bundle continues to uncover. Debris washes into gutters and catch basins leading to Lake Michigan.

0045/0915 Site Emergency Plan activation complete. Search and rescue operations commence.

0100/0930 Site Emergency Plan classification should be upgraded to "SITE AREA EMERGENCY" or hia=her.

0130/1000 Fuel Pool losses to Tilt Pit are overcome by Fire Water addition to Spent Fuel Pool and the damaged fuel bundle is re-submerged. The injured operators are located and evacuated.

0223/1053 The Fuel Pool is refilled. The injured operators are transported to South Haven Community Hospital. Contamination retention/capture efforts are underway on the site perimeter.

0230/1100 Fuel Pool cooling is restored, resulting in high radiation areas being

0300/1130 created in the Spent Fuel Pool Heat Exchanger Room and adjacent areas of the Auxiliary Building.

The damaged fuel bundle is secured to the Spent Fuel Handling Machine.

0400/1230 Cleanup planning is completed. The Site Emergency Plan classification should be downgraded to "ALERT'.

0400 +/1230 + Recovery planning begins. Players not involved in recovery planning begin critiques.

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

NARRATIVE

SUMMARY

NARRATIVE

SUMMARY

0800 (-0030)

A. The plant is in Cold Shutdown at the end of core life. Preparations for refueling are in progress. The reactor has been shutdown for 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months .

The Primary Coolant System is pressurized to 250 psia; Primary Coolant Pumps P-50B and P-50C are in service for Primary Coolant System source term reduction.

B. The Equipment Hatch and both doors of the Personnel Lock are open.

Work in Containment is in progress to support Reactor Vessel Head removal in approximately 6 days. The South Tilt Pit Gate is installed and the south Tilt Pit is empty; the Fuel Transfer Tube Flange is installed.

C. Fuel handling operations in the Spent Fuel Pool are in progress to accommodate a full core off-load in support of Reactor Vessel beltline inspections. One Control Operator and an Auxiliary Operator "lifeguard" are using the Spent Fuel Handling Machine to move various spent fuel bundles to different storage locations as directed by Reactor Engineering.

At present, bundle L-015 is being moved from Spent Fuel Pool location 0-13 to location 1-15*

D. Equipment in a degraded mode:

1. . Safeguards Transformer 1-1 is out of service to repair a recurrent nitrogen leak. MOD 24Fl is open and red tagged. 2400VAC busses are being fed from Station Power Transformer 1-2 via Main Transformer backfeed.

2. Spent Fuel Pool Cooling Pump P-51A is disassembled with rebuild in progress to support the upcoming core off-load. P-51B is in service for Spent Fuel Pool cooling.

E. Many normal shutdown alarms are annunciated.

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

- a -~----**-

PALISADES SHUTDOWN SAFETY EQUIPM AVAIL.ABILITY Effective-- Tiirough c:r

1' Spedal Instructions:

KEEP SOC RETURN TEMPERAnJRES COMFORTABLY ABOVE 70-F CSOP* 1 AND OOP-14) eom 'TRAINS OF soc ARE OPERABLE. TiiE S/Q'S ARE NOT NEEDED TO MErr GOP-14 REQUIREMENTS Shiftly SiO level verification is llCll requiJm to be logged in SH0-1 ID meet C.OP-14 n:quiremc:nts.

PCS Over-p~ssure Protection is being provided by both ctwmels of LTOP

'i' Decay Heat Removal requirements: i=fcmd in xmcz a:mn Shutdown Cooling Train 'A' defined in GOP-14 Aaacll. s coi0 1-2> OPERABLE LPSI P-67A CCW PUMP P-52B. SWS PUMP P-7A CCW HX E-54A SOC HX E-60A LPSI INJ M0-3012 / FI-031 IA M0-3014 / FI--0313A EK-1161/1162 LPSI Pumu Press and inu Alllmll Shutdown Cooling Train 'B' defw:d in GOP-14 Aaacn. s CD!G 1-1> OPERABLE LPSI P-67B CCW PUMP P-52A SWS PUMP p.7B CCW HX E-548 SOC HX E""60B LPSI INJ M0-3008 / FI-0307A M0-3010 I FI--OJOIJA EK-116111162 LPSI P1111111 Pn:u and lriD Almn.L.

PCS Loop 1 ( 'A' SIG and P-50B ) AVAn.ABLE PCS Loop 2 ( 'B' SIG and P-50C) AVAll.ABLE 1' CVCS Boric Acid Tech Spec 3.2 and GOP-14 Inventory Addition Pathways (Both required J; I. T-53'A' level ~118" @94.!~) and [BJ 11.500 ID 15.000 ppmevP-56A, M0-2140, P-SSA AND B -

CBOmCHGPUMPSREQUIRED), tbroughnonnalCharging -2111 and CV-2113orCV-2115 -

2. SIRWT with level ~O.,~C!:l720 ppm. CV-3057 g.mwn ID P-66A HPSI pump and .

discbarge mrough REDUND RPSI header through M 3064 (Pllh available wi!bin 30 mmwa>

1' PCS normal makeup Inventory Addition Pathway: SIR.WT, P-55A or B, normal charging Ma LcYd RJU. AND SCUD

'i' PCS Level Band: FlJLL AND SOLID to FlJLL AND SOLID Mill LcYd RJU. AND SOLID e PCS Level Indication Requirements: UA-0102A AND U-0103A when PCS ~28' 6" Ma Temp. tlrf 1' PCS Temperanuc Band: _____10_0_0_F_____ to _____s_o_°F.______

Min Temp. '709F

'i PCS Temperawre Indication Requirements: CETs # 2 <H-2). # 16 <R-8) and TR-0351 1' Electric Power Requirements: Diesel 1-2 C and D Buses on STATION PWR AND STARTIJP power available 1' SFP Exhaust Fan I Charcoal Filter: V-88 AND VF-66 OPERABLE (1111& mmd with Eqaip Hach Coad)

Baed en lni&ial PCS Tcnrpmmre or 130 *F

e Containment Qosure Time Frame: 40 MINUTES Bued an Minimum PCS LeYel or Full mt Solid Based on~ days ~tuaor lbmdown MECHANICAL MAINTENANCE 1' Equipment Hatch Qosure Responsibility:

Notify: SEEOUIYUST 181 NOTE: Adherence ID all of the equipment conditions specified will ensure that me risk of jeopardizing the safe shutdown condition of the plant is minimized.. Additional equipment may also be available, these flow paths meet the requiremems and suppon the schedule. This equipment should not be degraded without Operations Scheduling approval.

.ttJ:tA vi' *LDAli?A Im 1 avauao1e wnn1n jU minutes 1 Suction Reaaor Sump tbmugb CV- 3029 Path I Pump HPSI P-66-A

TRAIN 2 REDUNDANTHPSI Discharge REDUNDANT HPSI tbrougb M0-3064

Path 2 Suction Pump Discharge Suction Reactor Sump through LPSI P-67-A CV- 3029 and M0-3198 Normal SDC through M0-3012 and M0-3014 Reactor Sump through CV- 3029 Path J Pump HPSI P-66-A Discharge REDUNDANT HPSI Hot Leg Injection through M0-3082 Suction LPSI through M0-3015 and M0-3016 Path 4 Pump LPSI P-67-A Discharge Normal SOC. both Heat Exchangers. M0-3012 and M0-3014 INOPERABLE CONTAINMENT PENETRATIONS For planned maintenance REMEMBER 'IHAT OPERATIONS PENETRATIONS MUST Al.SO BE a:>NTROLLED BY mE SHIFI' SUPERVISOR MZ-42 PMW TO QUENCH TK MAY BE OPEN TO SUPPLY PMW TO THE CONTAINMENI',

CV-OlSS CAN BE a.DSED TO ISOLATE IF NEEDED.

MZ-10 SERVICE AIR MAY BE OPEN TO SUPPLY AIR TO THE CONTAINMENT AS REQUE.STED.

MV- CA-122 CAN BE Q.OSED TO ISOLATE IF NEEDED.

MZ-50 EQUIPMENT HATCH HATCH IS OPEN. MECHANICAL MAIN'IENANCE WILL BE STATIONED AT Li*

NEAR 1BE RATai 24 HOURS A DAY WHEN OPEN. THEY NE.ED 20 ?r<<NU'IT.:S C..OSE THE RA.Tai AFTER NOTIFICATION. ~ M1Nt1ra CONl"AINMEN'T Cl.OSURE1IMEA.UDWS OPERA.TORS 10 MINUIESTORECOONIZELOSS OF SOC. H

~TO NOTIFY MA.INT. AND av.It TEMPORARY LINES. AND 20 MOOJTES T*

a.DSE 11IE HA.Tal.

MZ-19 PERSONNEL AIR LOCK WE WILL BE AlJ.QWING THE DW0-13 TIME FRAME TO EXPIRE. THE DOOR JN'l'.ERLOCIC IS DEFEATED TO AU.OW Born DOORS TO BE OPEN TO ESTA.BUSH REFUELINCi VENIU.ATION LINE-UP. AT AU. TIMES EACH DOOi SHOULD BE CAPABLE OF BEING O.OSED. NO TEMPORARY LINES SHOULD RUN 1HROUGH nm DOORS. -

CONTAINMENT PURGE CONTAlNMENf PURGE CARD HAS BEEN ISSUED, CONTAINMENT PURGE ~1 BE PERFORMED AS NEEDED. ONCE nm PURGE CARD IS CLOSED OUT A Nt ONE IS NEEDED BEFORE RES~G PURGE.

OPERATIONS SUPERINTENDENT WAIVERS OF GOP-14 REQUIREMENTS NONE

NIA OPSSUPERtNTLNDENT

r AL~A.U!!.~ ~nu i..uv n 1.,. i.'lM .c.. J. 1 A.li.'lA .~i.'li.'l.C..i.'li.'l1n.c..i .. .i Any ~o

mswas ro Ille que:Slicms will have circmnmnccs jdmrific:ri on Ille Shurdown Safciy EqWpment Availabilii:y Shem. Havmt ~

c:onciicions not salisfied is expecr"" A ieview of the no IDS\Wft, cammems. and swus sheets will pmvids1level of ~g t.o .~

cmreru risk level. A copy of this will be aaai::bcd co the SS and the Qwage Mmager's Copy of the i:;~a'it jailabilir:y Shecu. .

. IA,\,,.'= ..

~ :w CORE HEAT REMOVAL

_ , L PCS Tcmpemure is less than 120-F?

_ , L Two Shmdown Cooling pumps are Operable?

_ , L Two Slwrdown Cooling iraiDS an: Operable?

_ , L SDC Aow is ~.000 gallons perminwe?

_ L _ Two Core Ent Thermocouples an: Openble?

/~":"' Q.;

- V'

- Both SFP Cooling Pumps are available?

-- ...... PCS makeup is available >"Boil Off me"'? P-.5.5A AND P-.5.5B DCaied until 6/14193. aiu:rthcn only one pw

-- - t/ SDC

...... All F~

Insaumenwion is Protection Operable?

sys1am m Operable?

...... 2 Instrument comprmon are Operable?

-- Air REACTIVITY CONTROL .

At least two Pumped Barie Acid flow palhs (diesel blcbd-up) ro the PCS are Operable?

PCS [BJ is> 3~,. CSD szr Refueling boron c:onccrun.tion? PCS ~G [BJ of 1.720 PPM 2 Source Range Nuclear Inmumems m Operable?

No Core alrcnlions are in prosrm?

No Fuel moves in SFP are in progrea?

_L No Comml Rod Drive testing is in progress?

_L Primary Makeup Wala' ID PCS is cmmon ragged closed? MV-CVC-2162 s!osp:I.

ELECTRICAL AVAILABil.JTY

- .L AI lcm one Dielel Cimmrar is opmble?

- .L AI least 2 Off-Sile poMr man:a me opcnble?

- .L AI leut 3 Pre!emd AC Ima me opcnble?

- .L Both IC md 10 bases me meqized7

.L - No Eleczrical special reain1 is planned?

- L Swirchylld Power supply is Sllble?

L _ All DC Bmes me opmble? ED--01 Blllav DUcharp 1e11 will be mnm wia PCS <I 30L PCS INVENTORY t/ PCS full and inw:t szr is elevlUon of lowest opc:ning idemilied?

- L PCS Jevel is above 628' S"?

- L PCS level is above 623" O" {ndaced invcmary)?

- L PCS level above ii 618' O" C2S'< boe/Cald leg cznrmine)?

_ .L 2 Comaimnau Sump Jeve1 inm1lmenu me available?

- L Two PCS leYel hiiam m operable?

_ L All flow pldll far beayY lold requir=naus are available?

- L Elevuiaa of Jowat PCS apming is idcmified?

- _.!:.. OOP-14POVeming~aesatisfied?

CONTAINMENT INTEGRITY 40 minute Containment Comre Tune for loss of SOC

- .L Comaimnml Imqrii:y i i

JZr camrolled IAW GOP-14?

_ L CamaiDmcnt is opm wilh abilii:y to close within specified time?

_ .L 1-10 penmaaam are open wbidl can be closed wilhin lime limits'>.__ _ _ _ _ _ _ _ _ _ _ _ _ _ __

- .L Comaimnem Colure pammel m identified and available?

- L No penemtiam open which cm not be closed wilhin time limits? - - - - - - - - - - - - - - - - -

Al icaR one door dosed CE.quip fflu:h. Hau:ll Covm. Roll-up Doc

- .L SFP Cmcoal Filtc:n are available?

- .L Air locb 1re clmed szr capable of being closed?

2!l!.,. 2!l!.,.

~ ..!!l!...

.!!!!.... ..!!l!...

IF PCS IS IN REDUCED INVENTORY Tmie spent in niduced inYmrory minimized?

Only scheduled 1C1Un1 and m.aimmanc:e in progras?

No Elec:aical Power supply c:hmges planned?

. OPERA11UN~ Ci.c.NJ:.KAL uu lAU.C. ll'4rv.ru.vJ.rtiiv1"4 PLEASE REVIEWTBE F.QlJIPMENT SfA1t1S SllEE'l'S SIDFll.y AA1> BE AWAJlE OF CHANGING PLANT co:r.l>mONS. . PU.AS SHARE ANY COMMENl'S OR CONCERNS wrm SIEVE- CONTROL ROOM AND SS BAVE THE ONLY omCAL COPIF.5 nm DA'IE.5101HE 151' OF1HE ENmY DEPICT'1HE U.TEST CHAHCiE TO 1HE ASSOCIATED ENl'RY.

Filling out Ourage Critique comment sheets as conditions wmam and when they are fiuh in your mind is the easiest md*most effcaive way to effect change in the fumre.. The SE's are maintaining a book of commcms.

All Operations personnel are encouraged to summit and review the comments frequently.

Keep Iodine removal fan/sin service as R.adPro requests. Keep at least one VHX-3 or4 fan on to rec:in: Com 3.i*

All PCS makeup sbould be from the SIRWT which will keep PCS (B] above REFOUT cone of 1.720 PPM Work Order bas disabled SIS on PCS Low Pressure SIS will still occur on High Cont Pressure and manual.

We arc cleaning up the PCS below the milllmum activity level to minimize exposure and take advantage of the ext time the polar crane delay has caused. With the PCP's safeguards n::iom should clean up even fanher.

GOP-9 S.l Ensure the Controlled Bleed-off Flow Control Valves are closed prior to depres.mrizing the PCS co prevent back flow from the VCT into the PCP seals.

Secondary Side Lay-up per FWS0-1 is in progress using FWP Air. after humidity drops we will secure this line-ui SOP-I 7.1.S.e We closed and caution tagged i?MW makeup to the PCS MV-CVC-2162 when cooling down before going on SDC. This ensures unwanu:d dilution on SDC docs not occur. Maintain this closed.

The first PCS drain will be to *647' O" through Letdown system to allow P'ZR manway and tool access flanges to be removed. After CRD's are uncoupled the m:xt drain will be through two Cold Leg drains to Mid-Loop for Head removal and SIG nozzle dams. This drain is slow at *12 GPM and is amtrolled from the Corurol Room.

All PCS drains should go to T-64'A' CWRT. We will top off SIR WT prior to cavity fill with this water early next.

week. We will also need to send 2 more feet of SFP water to the SIRwr over the next week.

While on SDC maimainSDC flow>2810GPM. Ifwcdmp below this Tech Spec 3.10.lc and SOP 3 applies. w. ,

need 2 Charging pumps electrically cmmected for PCS makeup palhs. .*-

OOP-9 AU I 3.8 During Cooldown <32S"F wc placed the I.PSI Pump RAS trip switches to defeat. This emures an unplanned RAS does not secure SDC. SOP-3 7.3.8 i enswcs they arc enabled during hcamp.

Do not vent any of the SIT's but the pressure can decay away, keep at least SO# in each boale.

When the Equipment balch is open eilher the aack alley hatches or the roll-up door must be closed CV-1212 Service Air isnlarim is Temp Mod blocked open to minllni7.C loss of breathing air in the Containmeru.

Especially after the imerioc:k is defeared on the PclSCIDld Air Lock doors wc should establish and maintain the Refueling Venrilarioo lineup. 1bis has shown to be the least contaminating air flow path to the SFP area.

The acoustic monitors for the PORV's are removed to support Pressurizer dome insulation removal. We will be removing the damagm jnsldarioo in the shed before we remove the Pzr Manway and insEall new insulation at the end of the omage. While the PORV's arc needed we must keep the do~ temp TE-0106 operable.

Please keep T-2 Omd Srmage Tank level low wort~ a preferred *5090 level, we will need this level to be low later this mcnb to drain bodl S/G's to it for seamdary side inspection and sludge lancing.

During l&C calibrariDD of the data logger use the CFMS indication for CET indication. Note the designated incorcs have one decimal point for ease of idcmification.

.r Starting Monday the Shift Manager will run the 0815 meetings during the outage. a shift contact is needed and will provide Ops swus and report concerns back to the shifts.

a- An 1830 outage management meeting is held in the Tech Suppon Center daily, please have an SE.SS.or OSS aner each night. Shift Manager will run the meeting

<l) Our safety director needs to be notified (within 2 hrs) about any work groups injury on site which requires off site crcaunent. -*- -* . . . . ---

2

G. Met~rological conditions are as follows:

1. It is hot and humid with moderate to strong winds from the southwest; the sky over the lake has turned black and heavy rainfall .

appears imminent. A severe storm warning has been received from Murray and Trettel predicting high winds and thunderstorms, effective from 0830 to 1100 today. A tornado watch is in effect.

a. Wind speed: 18 mph

b. Wind direction: 226°

c. Stability: A

d. Ambient temperature: 85°F H. Primary chemistry conditions:

1. pH: 4.87

2. Boron: 1945 ppm

3. Total beta gamma activity: 0.173 pci/ml

4. Iodine dose equivalent: 7.52E-4 pci/ml 0830-0845 (0000-0015)

A. The exercise begins when a lightning strike disables Station Power Transformer 1-2. Bus lD fails to fast transfer to Startup Transformer 1-2 due to a fault in the synch check circuit; all other 2400VAC and 4160VAC bosses successfully transfer to startup power. Diesel Generator 1-2 cranks but does not start due to sediment blockage in the fuel supply line.

B. The inservice Shutdown Cooling Pump, P-67A,loses power and stops.

C. The Spent Fuel Handling Machine, with bundle L-015 in its mast, stops in transit to Spent Fuel Pool location 1-5 at Spent Fuel Pool location L-10 (in front of the south Tilt Pit gate).

D. The inservice Spent Fuel Pool Cooling Pump, P-51B, loses power and stops*

E. Expected actions:

1. Operators will respond to the loss of Shutdown Cooling Pump P-67A *

by invoking ONP-17, "Loss of Shutdown Cooling." The alternate Shutdown Cooling Pump, P-67B, will be started to restore Shutdown Cooling and Charging Pump P-55C will be started to restore Charging Flow and PCS pressure.

2. Operators will respond to the loss of Bus lD and the failure of Diesel Generator 1-2 to load by invoking ONP-2.1, "Loss of AC Power."

Operators will manually energize Bus lD from startup power to restore SFP cooling and the Spent Fuel Handling Machine.

3. If the operators attempt to manually position the Spent Fuel Handling Machine, a hoist brake malfunction will impede their progress.

0845-0900 (0015-0030)

A. A powerful tornado descends on the southwest comer of the Turbine Building and proceeds northeast. Portions of the Turbine Building roof

B.

are tom off; the aluminum Safety Injection and Refueling Water Tank explodes and its contents are carried skyward by the vortex.

The siding and roof of the Fuel Handling Building are ripped away as the operators inside dive for cover. A volume of 60,000 gallons of the contents of the Spent Fuel Pool (approximately 10 feet of level reduction) blasts upwards into the funnel cloud and is carried off, exposing approximately 2 feet of bundle L-015 in the mast of the Spent Fuel Handling Machine.

Whirling debris and jagged pieces of metal lacerate the mast and hoist box, damaging several peripheral fuel pins which spill a portion of their contents; the mast and hoist box remain attached to the Spent Fuel Handling Machine by cables. The nitrogen-inflated seal around the south Tilt Pit gate succumbs to the heavy buffeting and tears; the remaining contents of the Spent Fuel Pool commences leaking into the empty south Tilt Pit and Transfer Tube at 400 gallons ( -1 inch of Spent Fuel Pool level reduction) per minute.

c. The tornado destroys the_ Heating and Ventilation Equipment Room, still proceeding northeast, when inexplicably it drops its burden of roofing, siding, sheet metal, Safety Injection Refueling Water Tank and Spent Fuel Pool water, HVAC equipment, and miscellaneous debris on the north-south access road leading to Lake Michigan and ascends back to the overhanging cloud bank.

D. The entire episode has lasted approximately 10 seconds. In the demolished Spent Fuel Pool area, radiation monitors are off-scale high due to radiation fields of hundreds of Rem per hour caused by the exposed and damaged fuel bundle dangling from the Spent Fuel Handling Machine which continues to further uncover as the remaining contents of the Spent Fuel Pool leaks into the Tilt Pit. Outside, astonished workers in the Support Building and Security personnel view the debris strewn along the north-south access road.

E. The two operators at the Spent Fuel Pool are covered by debris in the ruined Heating and Ventilation Equipment Room, unconscious and heavily contaminated but alive. Their location shields them from most of the direct effects of the hanging fuel bundle.

F. Expected actions:

1. The Shift Supervisor will assume the Site Emergency Director position and:

a. An Iii ALERT* will be declared under "Natural Phenomenon -

Tornado Striking Facility" unless it is immediately evident to players that major damage to spent fuel in the Fuel Handling Building has probably occurred. In this event, the declaration of

a *sJTE AREA EMERGENCY* would be appropriate.

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 Operations Support Center and Technical Support Center; 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.

2. The Control Room will implement ONP 11.2, "Fuel Handling Accident" and dispatch operators, security personnel and Health Physics to survey the damage and ascertain the status of the two operators known to have been in the Fuel Pool area

0900-0930 (0030-0100)

A.

B.

Activation of the Site Emergency Plan continues.

Personnel previously dispatched report on the damage observed to the Spent Fuel Pool and surrounding area, the high radiation fields in the Spent Fuel Pool area and the contamination and debris present on the north-south access road. Observers at the Spent Fuel Pool receive high radiation doses during their initial assessment and decide that the intense radiation field created by the hanging fuel bundle prevents entry into the area. The two operators are not located.

C. Heavy rain following passage of the tornado caused the smaller and lighter debris on the access road to be carried by the stormwater towards curbside catch basins and the storm sewer outfall/trash rack near the corner of the perimeter fence. Use of real-time meteorological data begins at 0900 (0030). The squall line that the thunderstorms and tornado were associated with extends from Grand Rapids to Kalamazoo to Elkhart, Indiana by 0930 (0100) and is moving rapidly east.

D. The remaining contents of the Spent Fuel Pool continue to leak to the south Tilt Pit at -400 gallons per minute. Over one foot more of bundle L-015 has now been exposed, and Fuel Pool radiation levels have increased

E.

exponentially.

Expected actions:

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

2. Complete site accountability and commence search and rescue operations for the missing operators.

3. Upgrade the Site Emergency Classification to "SITE AREA EMERGENCY" based on "Major Damage to Irradiated Fuel in the Fuel Handling Building" and commence evacuation of unnecessary personnel. A classification of "GENERAL EMERGENCY" due to loss of fission product barriers is also acceptable.

4. Operators will respond to the continued loss of Fuel Pool inventory by manually valving in Fire Water makeup in the Spent Fuel Pool Heat Exchanger Room to provide makeup, cooling and shielding.

Radiation levels in that room, although higher than normal, are not excessive since the operable Spent Fuel Pool Cooling Pump, P-51B, if recovered following the initiating loss of power event, will have tripped due to the low water level in the Fuel Pool.

S. Men and materials will be designated to dike outfall points to Lake

- Michigan to prevent the un-monitored releases*

0930-1053 (0100-0223)

A. Spent Fuel Pool level recovers at approximately 2 inches per minute from the addition of Fire Water and radiation levels decrease accordingly, although leakage into the south Tilt Pit continues unabated.

Approximately 40,000 gallons will be required to fill the south Tilt Pit and Transfer Tube, and approximately 60,000 gallons will be required to recover Spent Fuel Pool level.

B. Expected actions:

1. Search and rescue teams, authorized to receive emergency lifesaving radiation exposure amounts, will enter the Spent Fuel Pool area and rescue the two unconscious operators. The operators will be transported, heavily contaminated, to South Haven Community Hospital for the treatment of head wounds and internal injuries.

2. Rainwater containing debris may be dammed and/or filtered prior to reaching Lake Michigan; massive amounts of sand and drying agents

3.

may be required to absorb the liquid and prevent the contamination from going airborne.

The damaged Spent Fuel Handling Machine mast and hoist box containing the remains of bundle L-015 will be re-submerged and Fuel Pool level will be recovered, with intermittent makeup necessary until Fuel Pool and Tiit Pit levels are equalized.

4. As Spent Fuel Pool radiation levels decrease, strategies will be formulated to:

a. Capture the damaged Spent Fuel Handling Machine mast and hoist box containing bundle L-015 to prevent their falling into the Fuel Pool.

b. Increase Spent Fuel Pool boron concentration from recycled boric acid to compensate for the dilution caused by the addition of Fire Water.

c. Restore Spent Fuel Pool cooling in an orderly fashion .

1053-1130 (0223-0300)

A.

B.

Plant personnel accompanying the injured operators to South Haven Community Hospital report that their conditions are serious but not life threatening; decontamination efforts are ongoing.

The extent of exterior contamination has been determined; it is also apparent that, despite all efforts, at least some of the runoff has reached Lake Michigan.

C. Operators have restored Spent Fuel Pool cooling, creating high radiation areas in the Spent Fuel Pool Heat Exchanger Room and adjacent areas of the Auxiliary Building. Efforts are ongoing to capture the damaged Spent Fuel Handling Machine equipment and fuel bundle and increase Spent Fuel Pool boron concentration.

D. Expected actions:

1. The contaminated area will be quarantined and posted. Local officials will be apprised of the immediate danger to water supplies and beach activities.

2. Plant and Emergency Operations Facility personnel will commence

planning for a full scale cleanup of the area, including repairs to the Spent F~el Handling Machine and safe storage of bundle L-015, repairs to and enclosure of the Fuel Pool and south Tilt Pit, earth excavation, storage and disposal, waterborne contamination control and long term monitoring.

3. Repairs to the alternate Spent Fuel Pool Cooling Pump, P-SlA, now located in a high radiation area, will be expedited to provide a backup means of Fuel Pool cooling should the inservice pump fail.

1130-1230 (0300-0400)

A. The Spent Fuel Handling Machine mast and hoist box containing bundle L-015 have been secured to the Spent Fuel Handling Machine by additional cabling. Recycled boric acid has been added to the Spent Fuel Pool.

B. Curious boaters and onlookers begin to gather on the beach and near the shoreline.

C. Exp~ted actions:

1.

2.

Cleanup planning will be completed, including contacting vendors and determining expected arrival times. Earthmoving and capture activities will commence.

Effective crowd control practices will keep onlookers at a safe distance.

3. The Site Emergency Plan classification will be downgraded to an "ALERT'.

1230 + (0400 +)

The exercise will be terminated for plant personnel when long term cleanup and monitoring planning have been successfully demonstrated and recovery planning has begun*

~----------- ---------~--

MEDICAL SPECIFICS

PALEX *93 MEDICAL PORTION .

Palex Time 0015 Medical Time 0000 Two operators are injured by tornado damaging SFP Auxiliary Building. Both are rendered unconscious.

0045 0030 Search and rescue initiated

0130 0115 Injured operators are located and evacuated

0223 0208 Operators transported to SHCH

This timeline should be shortened significantly. I would expect that once the victims are discovered they would be leaving site no longer than 30 minutes from time of discovery. (This would be very slow).

MEDICAL DRILL Goal: The goal of the 1993 PALEX/Medical Drill is to adequately demonstrate Palisades ability to respond to a contaminated injured person utilizing site, off-site (amb~lance) and hospital resources .

Objectives: I. *Recognize the need for and initiate search and rescue (and possible medical treatment) within 30 minutes of the initiating incident in accordance with EI-12.3, "Search and Rescue Team Responsibilities".

2. Demonstrate proper response of site personnel during an Alert or Higher Classification to a Medical Emergency (Operations, Health Physics and EMT's) in accordance with EI-14, "Medical Care/Treatment of Contaminated, Injured Personnel".

3. Demonstrate proper request, response and necessary interfacing of off-site agency assistance (ambulance) needed during a radiological emergency in accordance with EI-14, "Medical Care/Treatment of Contaminated, Injured Personnel".

4. Demonstrate proper notification to hospital personnel of contaminated injury in accordance with El-2.1, "Emergency Actions/Notifications/Responsibilities", El-3, "Cormnunications and Notifications", El-14, "Medical Care/Treatment of Contaminated, Injured Personnel".

5. Demonstrate proper interfacing necessary to treat a

contaminated injury between hospital and Site. (Health Physics) personnel in accordance with EI-14, "Medical Care/Treatment of Contaminated, Injured Personnel".

6. Search and Rescue personnel demonstrate proper techniques of 1ocat i ng, .i dent i fyi ng, survey; ng and treating missing individuals in accordance with EI-12.3, "Search and Rescue Team Responsibilities". *

7.

8.

Search and Rescue personnel demonstrate proper communication necessary to request additional resources .*

(EMTs, Hps, etc.} for both on-site and off-site (ambulances} assistance.

Medical personnel (both on-site and off-site} demonstrate necessary communication skills to effectively and efficiently manage the medical emergencies following these principals:

A. Medical care of personnel comes First.

8. Minimize addftional harm to the injured and rescuers from the radiological hazards (and other hazards}

present.

C. Minimize the spread of contamination following the ALARA concept.

SCENARIO .

Tornado strikes Auxiliary Building (SFP} during fuel moves. One Control Operator and one Auxiliary Operator (Lifeguard} are injured*. Additionally,

contamination is spread throughout the SFP area via SFP water .

Victim #1: Laceration~to forehead with bleeding, unconscious, bruising to the ribs with 1-2 rib fractures. Victim regains consciousness, complains of severe chest pains due to the fractured ribs.

Victim will be soaked with SFP water and rain coming in through opening in roof. Victim will be shocky, but will stabilize out after oxygen, IV and packaging.

Victim #2: Multiple extremity fractures. Initially victim will be unconscious. Victim will have fractures to an upper arm and multiple fractures of one lower leg. Victim will be shocky, but will stabilize out after oxygen, splinting, IV and packaging.

Victim will be soaked in SFP water and rain coming in through opening in roof.

Victim #1 :*

Injuries: Laceration to forehead with bleeding, simulate with moulage.

1-2 rib ~ractures, ~imul~te with m6ulage (de~p bruising 1n area of fracture). Unconscious for first 15 minutes.

Dress: Full set of Anti-Cs, with scrubs and modesty clothing (shorts and T~shirt) .

Contamination Levels:

Varying levels of contamination will exist over.their entire body with localized hot particles {Coleman Lantern Mantels).

Vitals: Initially: Unconscious-Responds (purposefully) to painful stimuli Airway-Intact with GAG reflex Breathing-Spontaneously shallow at 24 per min.

Pulse-Present basically weak at 140 per min .

B/P-70/50

Subsequent vitals will change only based on treatment applied.

RESPONSE/VITALS Victim #1 TREATMENT APPLIED LEVEL OF CONSCIOUSNESS Pressure bandage-Forehead Conscious: Responds slowly to Stabilize head/neck verbal commands Oxygen applied minimal 8 liters/min. Respirations: 20/shallow Pulse: 140/min weak B/P: 70/50

-Lung Sounds: Slightly diminished in area of bruising

Fully immobilized on back board without elevating lower extremities (Trendelenburg position)

Fully immobilized on back board No significant change Conscious: Responds slowly to with elevation of lower extremities verbal commands (Trendelenburg position) Respirations: 20/min weak Pulse: 120/min weak B/P: 80/60 Lung Sounds: No change IV started by ambulance EMTs Conscious: No change Normal saline wide open Respirations: No change

(>IOOcc/min) Pulse: 100/mi n B/P: 90/60 Lung Sounds: No change 2nd. IV started or M.A.S.T. Conscious: No change applied & inflated with Respirations: No change 1st. IV Pulse: 90/min B/P: 100/80 Lung Sounds: No change

Varhtions Legs elevated prior to Same as fully immobilized on immobilizing on.back board back board with lower extremities elevated M.A.S.T. applied and inflated Same as First IV prior to IV PROCEDURE PERFORMED RESULTS Initially Background SFP Area readings >300 ccpm Open Window R0-2/R0-2A reveals 1-2 particles 1000 mrem/hr.

Remove Clothing Background SFP Area readings >300 ccpm D.W. R0-2 No detectable particles

~Access Control/Ambulance 10,000-100,000 ccpm by frisking over entire body, 1-2 particles detectable up to 5 mrem/hr.

Tape Lift Particles ~Particles removed Washing/Rinsing ~Hos pi ta 1-Conta.mi nation levels

decrease with rinsing. 2-3 rinsings/hair washing remove all detectable contamination.

Collection container 5,000 ccpm up to, but no higher than 2 mrem/hr.

Victim #2 Injuries: Unconscious; Closed upper arm fracture simulated by moulage (bruising of area) pain, tenderness and inability to move arm; Multiple fractures of one leg-Femur (closed) and

Tibia/Fibula (open). Some bleeding from Tibia/Fibula fract11re.

Dress: Scrubs with modesty clothing CT-shirt/shorts).

Contamination Varying levels of contamination will exist over entire Levels: body with localized hot particles (Coleman Lantern Mantels).

Vitals: Initiallv: Unconscious-But responds purposefully to painful st.imul i Airway-Intact with GAG reflex Breathing-Spontaneously at 22 per min.

Pulse-Weak-Radially at 120 per min.

B/P-80/60

Subsequent vitals will change only with treatment applied.

Victim #2 TREATMENT APPLIED LEVEL OF CONSCIOUSNESS Pressure bandage-Leg Wound Conscious: Responds slowly to Stabilize head/neck verbal commands Respirations: 20/min Pulse: 120/min B/P: 80/60 Lung Sounds: Clear Bilaterally All fractures splinted Conscious: No change Back Boarded Respirations: 18/min Oxygen applied at least -Pulse: 120/min, no change 8 liter/min. B/P: 80/60; no change M.A.S.T. applied or 1st

Conscious: No change IV started or Treudenlenburg Respirations: No change position ' Pulse: 100/min B/P: 90/60, no change 2nd. IV or .!st and M.A.S.T. Conscious: No change or M.A.S.T. and Treudenlenburg Respirations: No change position Pulse: 90/min B/P: 100/60 PROCEDURE PERFORMED RESULTS Initially Background SFP Area readings >300 ccpm Open Window R0-2/R0-2A reveals 1-2 particles 1000 mrem/hr.

- Remove --Clothing - -- - --

Background:

-sFP Area -readings >300

ccpm D.W. R0-2 No detectable particles

~Access Control/Ambulance 10,000-100,000 ccpm by frisking over entire body, 1-2 particles detectable up to 5 mr~m/hr.

Tape Lift Particles ~Particles removed

Washing/Rinsing ~Hospital-Contamination levels decrease with rinsing. 2-3 rinsings/hair washing remove all detectable contamination .

Collection container 5,000 ccpm up to, but no higher than 2 mrem/hr.

EXPECTED ACTIONS/RESULTS

1. Control Room initiates Search & Rescue through OSC for SFP Area due to loss of communication with operators.

Key- 2. All Site EMT's if paged by Control Room, respond to OSC for direction.

3. When victims found, they are properly identified, assessed for injuries, area surveyed (Radiologically) Control Room/OSC notified and additional resources requested as needed.

4. Hospital is notified of Contaminated Injured Personnel with recommendation to set-up to receive contaminated injured.

5. Ambulances are requested properly through Van Buren County (911} multiple

-ambulances requested.

6. Ambulance personnel informed of contamination and instructed to don appropriate protective clothing *

7.

8.

9.

Transfer of patients performed smoothly and efficiently.

Core of patients medical status taken presentence over decontamination.

Techniques demonstrated by all personnel to maintain the spread of contamination ALARA (control is not lost} .

MAINTENANCE ACTIVITIES

PA-L~t-cr-3 MAINTENANCE ACTIVITIES

Equipment: P-S/11 Alternate Power? _ ___.;.#_()_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Location of Equipment: .....S.._1='........ ...............R.....11_.._._s

.P___._H....X

____'f_()_.._E_..l_FV._._ _ _ _ _ _ __

ExtentofTroubleshooting: AltJAlf. ,;

co,vltAJVc /i't=BV!t.IJ oe fV/'1P ParametersforTesting/Troubleshooting:___.41 __0.....N........

E________~

WfJIJ'7. 91: /?fPtf/fifl' /J(l{Ull( SCFAIA~lfJ Estimated Time of Repair: *Al/A Scenario Time:

ToolsNeeded: SidAJCJAR/J TOOLS Fdl? trf:P'41~ l/F f:'O{)l/JS 911/fXLTPVMP Equipment/Replacement Parts: S'7AAJM~/J ~OVl/JS pVttP ,ffM/R P~~TS From Stock: /!1PFLl E~. ,

~ECH .S/Ml OIL S/?tfL.I, Cl/ .Or&:r.r. 0 -fUAICS Procure:

Anti-CsNeeded:'------------~lJ...-fi,__S~*--~-------------------------

Simulation:

Equipment/Parts:_~y-~_s ______________________~

Tools: YES Eauipment Status Indication:

(For Drill/Exercise)

Necessarv Controller Information:

(Message Sheet needed? Yes No )

MAINTENANCE ACTIVITIES

Equipment:

Alternate Power?

Location of Equipment:

f/-/f=

S.Pf?AJT FUE!l J/A&l.Jt.INC IV O

.......:;~;;.__-----------------~

6" ~9" S' ~ P AIC Ell

~AC!f/AJE Extent of Troubleshooting: perey11rur lft?tv -ro ClfPTP~F r1- /Cf"STIMI~

,,, rllt:'L A .r.rE'1ftBL.Y r/et?IJf Flf(,t. IPF ,t:(,,l/B7#6'".l /N~ s ,DG>P7 rvn. P~-' f'f1)/9Jf~6 Parameters for Testing/Troubleshooting: - - - - - - - - - - - - AHF.f Estimated Time of Repair:

1/5 1'11N Scenario Time:

Equipment/ReplacementParts: ---~/1/-~-A/~~;;.___ _ _ _ _ _ _ _ _ ____

From Stock: -----------------------~

Procure:

Anti-cs Needed:.

Simulation:

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

Equipment/Parts: ____~y_e __s __________________~

Tools:

Equipment Status Indication:

(For Drill/Exercise)

Necessary Controller Information:

(Message Sheet needed? Yes No )

MESSAGE SHEETS

Scenario: PALEX-93 Time: 0800 Message No: I

scenario Time: -0030

PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: All Plant Personnel Simulated Plant Conditions:

See attached Initial Conditions and Data Sheets Message: .

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

FOR CONTROLLER USE ONLY Controller Notes:

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

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

3. Answer questions as appropriate.

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

Action expected:

Players should familiarize themselves with data provided .

INITIAL CONDITIONS 0800 (-0030)

A. The plant is in Cold Shutdown at the end of core life. Preparations for refueling are in progress. The reactor has been shutdown for 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months . The PCS is pressurized to 250 psia; PCPs P-508 and P-SOC are in service for PCS source term reduction.

B. The Equipment Hatch and both doors of the Personnel Lock are open.

Work in Containment is in progress to Support Reactor Vessel head removal in approximately 6 days. The south Tilt Pit Gate is installed and the south Tilt Pit is empty; the Fuel Transfer Tube flange is installed.

C. Fuel handling operations in the Spent Fuel Pool are in progress to accomodate a full core offload in support of Reactor Vessel beltline inspections. One Control Operator and an Auxiliary Operator "lifeguard" are using the Spent Fuel Handling Machine to move various spent fuel bundles to different storage locations as directed by Reactor Engineering. At present, bundle L-015 is being moved from SFP location 0-13 to location 1-15.

D. Equipment in a degraded mode:

1. Safeguards Transformer 1-1 is out of service to repair a recurrant nitrogen leak. MOD 24Fl is open and red tagged.

2400VAC Susses are being fed from Station Power Transformer 1-2 via Main Transformer backfeed .

E.

2. Spent Fuel Pool Cooling Pump P-51A is dissassembled with rebuild in progress to support the upcoming core offload.

P-518 is in service for SFP cooling.

Many normal shutdown alarms are annunciated.

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

- w.

PALISADES SHUTDOWN SAFETY EQUIPM AVAILABILITY

1' Special Instructions:

KEEP SOC RETURN TEMPERATIJRES COMFORTABLY ABOVE 70"F (SOP-1 AND OOP-14)

Bora TRAINS OF SDC ARE OPERABLE. raE SJQ*s ARE NOT NEEDED TO MEET GOP-14 REQUIREMENTS Shiftly SIG level verificalion is not ~ ro be logged in SH0-1 ro meet C.OP-14 n=quirmiena.

PCS Over-prcsswe Proteetion is being provided by both channels of LTOP 1' Decay Heat Removal requirements: pretem:d in sc:Mce min Shutdown Cooling Train 'A' defmedinGOP-14Aaach..5 (DICil-2) OPERABLE LPSI P-67A CCW PUMP P-SlB SWS PUMP p.7A CCW HX E-54A SDC HX E-60A LPSI 'fNJ M0-3012 / FI-031 IA -M0-3014 I FI-0313A EK-1161/1162 IJ>SI Pumii Pn:ss and tnii Alzmu Shutdown Cooling Train 'B' defmed in GOP-14 AU&ch. .s CD/G 1-n OPERABLE LPSI P-67B CCW PUMP P-SlA SWS PUMP P-7B CCW HX E-54B SDC HX E--60B LPSI 'fNJ M0-3008 / FI-0307A M0-3010 I FI-0309A EK -1161/1162 LPSI P1111111 Press and !riv Al~;;~**

PCS Loop 1 ( 'A' SIG and P-50B ) AVAILABLE PCS Loop 2 ( 'B' SIG and P-50C ) AVAD..ABLE 1' CVCS Boric Acid Tech Spec 3.2 and GOP-14 Inventory Addition Pathways (Both required :

1. T-53'A' level 2!118" @94.!~> and [BJ 11,500 to lS.(XX) oomcVP-S6A, M0-2140, P-SSA AND B (BOTHCHGPUMPSRE.QUIRED), tbrougbnmma1CW1ilil -2111 and CV-2113orCV-2115"

2. S~W1' with level~°" and~~l 720 ppm. CV-30S7 discharge du'ougb RED~ APsl header through M g.*wn 3064 to P-66A HPSI pump and (Pm IYlilable wilhin 30 mm~.-,,

1' PCS nonnal makeup Inventory Addition Pathway: SIR.WI", P-55A or B, normal charging _, . __

- Mal.nd RJLLANDSOUi'

'i PCS Level Band: FULL AND SOLID to FULL AND SOLID MiD LcYel RJLL AND soLm 1' PCS Level Indication Requirements: UA-0102A AND U-Ol03A when PCS 2!628' 6" MR Temp. JEF

'i' PCS Temperatme Band: ____1_0_0°_F_____ to ___s_o~0_F_____

Min Temp. '7rF 1' PCS Tempemure Indication Requirements: CETs # 2 <H-2), # 16 <R-8) and TR-0351

'i' Electtic Power Requirements: DieseJ 1*2 c and D Buses on STATION PWR AND STARTUP power available .

'i' SFP Exhaust Fan I Charcoal Filter:

Bum an Inilial PCS Tanpcnmre or 130 *r

'i' Containment Closure Time Frame: 40 MINurES Bum an Minimmn PCS ~ or Full and Solid Bued on i, days afler iu=or lllmrdown

'i' Equipment Hat.ch Closure Responsibility: MECHANICAL MAINTENANCE

Notify: SEE DUIY UST PhoneExL #

NOTE: Adherence m all of the equipment amditions specified will ensure ~ the risk of jeopardizing the safe shutdo~

condition of the plant is minimized. Additional equipment may also be available, these flow paths meet the ~mcms and support the schedule. This equipment should not be degraded without Operations Scheduling approval.

181

t1ftA V X LUAU I! A 1 Ub:I 1 ava11ao1e w1tn1n jU minutes 1 Suction Rcacmr Sump through CV-3029 Path 1 Pump HPSI P-66-A TRAIN 2 REDUNDANT HPSI Discharge REDUNDANT HPSI thiougb M0-3064

Suction Reactor sum2 through CV-3029 and M0-3198 Path 2 Pump LPSI P-67-A Discharge Normal SDC through M0-3012 and M0-3014 Suction Reactor Sump through CV-3029 Path 3 Pump HPSI P-66-A Discharge REDUNDANT HPSI Hot Le& lniection throu~ M0-3082 Suction LPSI through M0-3015 and M0-3016 Path 4 Pump LPSI P-67-A Discharge Normal SOC. both Heat Exchangers. M0-3012 and M0-3014 INOPERABLE CONTAINMENT PENETRATIONS For planned maintenance REMEMBER 1HAT OPERATIONS PENETRATIONS MUST ALSO BE CX>NTROLIJID BY THE SHIFT SUPERVISOR MZ-42 PMW TO QUENCH TK MAYBE OPENTO SUPPLY PMWTO THE COm'AINMENr.

CV-01.55 CAN BE CLOSED TO ISOLATE IF NEEDED.

MZ-10 SERVICE AIR MAY BE OPEN TO SUPPLY AIR TO THE CONTAINMENT AS REQUESm:

MV- CA-122 CAN BE C.OSED TO ISOLATE IF NEEDED.

MZ-50 EQUIPMENT HATCH HATal IS OPEN. MECHANICAL MAINTENANCE WILL BE STATIONED A 1 'JI NEAR 'l'BE HATal 24 HOURS A DAY WHEN OPEN. nmY NEED 20 MINU 1 ; ;,:

O.OSE 11IE HATCI AFl'ER NO'IlFICATION. ~ MINl1l'E CONl'AINMENI' .

C.OSURE11MEALLOWS OPEtATORS JO MINt1I'ES TO REaXiNIZE LOSS OF SD! I (

MINtna TO NO'l1FY MAOO'. AND Cl.EAR 'IEMPORARY LINES. AND 20 MINtm- ' ,.,

a.osE nlE HATCX MZ-19 PERSONNEL AIR LOCK WE Will. BE ALLOWING THE DW0-13 TIME FRAME TO EXPIRE. THE ooc *.

JNI:ERL()CKIS DEFEATED TO AU.OW B01H DOORS TO BE OPEN TO ESTABUSHREFUELINO VENJ'ILATIONLINE-UP. AT All TIMES EACH OOdi SHOULD BE CAPABLE OF BEING *a.osED. NO TEMPORARY LINES SHOUID RUN nmouoa nm DOORS. -

CONTAINMENT PURGE CONTAINMENT PURGE CARD HAS BEEN ISSUED. CONTAINMENT PURGE i>1 BE PERFORMED AS NEEDED. ONCE !HE PURGE CARD IS CLOSED OUT A NE ONE IS NEEDED BEFORE RESUMING PURGE.

OPERATIO NS SUPERINTENDENT WAIVERS OF GOP-14 REQUIREMENTS NONE

NIA OP88UPER.tNT.ENDENT

rAL~Alie~ ~nu1uun1 .. ..:li'll".Cd. 1 ~A .~..'.l..'.l.C....'.l..'.lJ.n.c..1 .. .1 Any ~o* answe:n w rbe quesz:icms will have cln:UJnsrmces idmrificrl on die Sluwiown Safety Equjpmem Availability Shem. HA\rQ'.lg !

conditions not samtied is expecrert A review of !he no answcn. commems. and swus slleecS will provict.1lnel of undamDl:img to u cumm risk level. A copy of lbis will be aniched w !he SS md lhe.OWage Mmager's Copy of du: ~~o'it 'jail&bility Sheet£.

/

~m

/),\,,.\...

ScW11 ler Dai

_L

_L

-L

_L

~~ CORE HEAT REMOVAL PCS Tempsamre is less lhan 120'"F?

Two Shurdown Cooling pmnps are Opeiable?

Two Shurdown Cooling iraiDs are Operable?

SDC Flow is ~.000 gallons F minme?

Two Core &it Thamocouples are Operable?

/ /' Commems Bolh SFP Cooling Pumps are available?

-- v PCS malceup is available > "Boil Off rate"? P-SSA AND P*SSB needed umil 6/14193. afierlhen only one plll'.

v

--- - v SOC Insuumenwion is Opcnble?

All FR Protection systrms are Operable?

v 2 Instrument Air compn:ssors are Opcnble?

REACTIVITY CONTROL At least two Pumped Barie Acid flow palhs (diacl t.cUd-up) ro !he PCS are Operable?

PCS [BJ is> 3.5CJi CSD i1r Refueling boron con.cc:ruration? PCS O?REFUEUNG [BJ of 1.720 PPM 2 Source Range Nuclear lnmumc:ms are Opmble?

No Core alla'lticms are in progrm?

No Fuel moves in SFP min progia1?

No Comrol Rod Drive &esting is in progress?

Primary Makeup Warer IO PCS ii caulian ragged closed? MV-CVC-2162 closed.

ELECTRICAL AVAILABilJTY

_L At leut one Diael Gcncmar is apenble?

_L At least 2 Off-Sire power mmca are opcnble?

_L At least 3 Prefemd AC baa me opcnhle?

L- _

r/ Bolh l C and 10 bma m e:nc:qjzed7 No Elec:lrical special lelling is plamled?

-- v v Swilehylrd Power supply is stable?

All DC Bmcs 1n: apenble?

PCS INVENTORY

- L PCS full md inrac:t m: is eievadon of Jowmi opening idemified?

- L PCS level ii above 628' S"?

- L PCS levd is above 623' O'" (reduced invenrory)?

- .Jl. PCS level above ii 618' O'" (2..5"< hac/COld leg c:mtr::rline)?

_ L 2 Qmt1inmem Sump leYcl inmmncms are available?

- L. Two PCS lc'lel imuumam m opmble?

- L All flow palhs for heavy laid requimnems are available?

- L Elevuiaa of lows PCS opening is idcmifled?

- ..!!._ OOP-14 PCS Vcmmg reqmrana111 are satisfied?

CONTAINMENT INTEGRITY 40 minute Containment Cosure Tune for loss of SD<..::

- L Camaimncm .lmegrity inet JI[ comrolled IA W OOP-147

- L Camainment ii opm wilh ability ro cloa within specified time?

- L I-IO penmadom areapm whicllcan be closed willUn time limits'---------------~-

- L Contaimnem Closure pmmme1 are identified and available?

- L No pe:nmatiam open whicb cm not be closed wi1hin time limits? - - - - - - - - - - - - - - - - -

- L SFP Cmcoal Filu:n are avlilable? Al lcaa one door clmed (Equip Hach. Hau:il Cavm. Roll-1111 Doc

- L Air loda are clmcd m: ClpAble of being closed?

IF PCS IS IN REDUCED INVENTORY

.!!!!.. ..!!!!.. T"nne spent in reduced invenrory minimized?

..!!!!.. ..!!!!... Only scheduled testing and maintmance in progress?

..!!!!... ..!!!!... No Elearical Powel' supply changes pl11111cd?

0 PERATlUN~ li.tiNJ:::J<.AL u u J. A u.c. 11~ rv ru.v.l.J"\. J. i u 1-.

PLEASE REVIEW TSE EQUIPMENT Sl'A1t1S SBEE1S SBIFILY Ahl> BE AWAU OF CHANGING PI.A.Yr CO~l>mONS. PLEA:

SILUlE ANY COMMEN'IS OR CONCERNS wrm S1'EVF. CONl'JlOL ROOM AND SS BA VE THE ONLy omCIAL COPIES 111E DA1E3 TO THE LEFTOF'IJIE EHIRY DEPICT THE l.Ata'I' CHANGE TO 1llE ASSOCIA'IED amtY.

Filling out Omage Critique commem sbecls as conditions wammt and when they arc fresh in your mind is the easiest and most effective way to effect change in the fumrc. The SE's arc maintaining a book of commems*

All Operations personnel are encouraged to summit and review the comments frequently.

Keep Iodine removal fan/s in service as RadPm requests. Keep at lean one VHX-3 or 4 fan on to reciit: Com air.

All PCS makeup should be from the SIRWI' which will keep PCS [B] above REFOur cone of 1,720 PPM.

Woric Order has disabled SIS on PCS Low Pressure SIS will still occur on High Com Pressure and manual.

We arc cleaning up the PCS below the minimum activity level to minimize exposure and take advaruage of the ext time the polar crane delay has caused. With the PCP's safeguards room should clean up even fanher.

GOP-9 s.1 Ensure the Comrollcd Bleed-off Flow Comrol Valves are closed prior to depressurizing the PCS to prevent back flow from the VCT into the PCP seals.

Secondary Side Lay-up per FWS0-1 is in progress using FWP Air, after humidity drops we will secure this line-u; SOP-I 7.1.S.e We closed and caution tagged PMW makeup to the PCS MV-CVC-2162 when cooling down before going on SDC. This ensures unwamed dilution on SDC does not occur. Maintain this closed.

The first PCS drain will be to *647' O" through Letdown system to allow P'ZR manway and tool access flanges to be removed. After CRD's are uncoupled the next drain will be through two Cold Leg drains to Mid-Loop for Head removal and SIG nozzle dams. 1bis drain is slow at *12 GPM and is conttolled from the CODII'Ol Room.

All PCS drains sboold goto T-64'A' CWRT. We will top off SIRWTpriorto cavity fill with this warerearly next week.. We will also need to send 2 more feet of SFP water to the SIRwr over the next week.

While on SDC maimain SDC flow >2810 GPM. If we drop below this Tech Spec 3.10.lc and SOP 3 applies. \Ve need 2 Charging ~ eleca:ically connected for PCS makeup paibs.

GOP-9 An I 3.8 During CoOldown <32S°F we placed the IJ>SI Pump RAS trip switches to defeat. This ensures an unplanned RAS does not secme SDC. SOP-3 7.3.8 i emures they are enabled during hcatup.

Do not vcm any of the SITs but the presswe can decay away, keep at least SO# in each bottle.

When the Equipment harch is open either the aack alley hatches or the roll-up door must be closed CV-1212 Service Air isoJaricm is Temp Mod blocked open to minimize loss of breathing air in the Containment.

Especially after tbe imerloc:k is defeared on d1e PelSOD11d Air Lock doors we should establish and maintain the Refueling Vemilaricm lineup. 'Ibis has shown to be the lean contaminating air flow path to the SFP area.

The acoustic mmitms for the PORV's are removed to support Pressurizer dome insulation removal. We will be removing the damaged jm:nlarim in the shed before we remove the Pzr Manway and install new insulation at the end of the outage. While the PORV's arc needed we must keep the downstream temp TE-0106 operable.

Please keep T-2 Cmd Storage Tank level low wodc toWards a preferred a50% level, we will need this level to be low 1arer this mmlb to drain bocb S/G's to it for secondary side inspection and sludge lancing.

During I&C calibmicm of 1be data logger use the o=MS indication for CET indication. Note the designated incores have one decimal point for ease of jdc:nri fication.

B Starting Monday the Shift Manager will run the 0815 meetings during the outage, a shift contact is needed and will provide Ops swus and report concerns back to the shifts.

B An 1830 outage managemmt meeting is held in the Tech Support Center daily, please have an SE.SS.or OSS atter each night. Shift Manager will run the meeting

(l.) Our safety dilcctor needs to be notified (within 2 his) about any wodc groups injury on site which requires off site treaDDCDL -*- .. . .. ---

G. Met~rological conditions are as follows: *

1. It is hot and humid with moderate to strong winds from the southwest; the sky over the lake has turned black and heavy rainfall.

appears imminent. A severe storm warning has been received from Murray and Trettel predicting high winds and thunderstorms, effective from 0830 to 1100 today. A tornado watch is in effect.

a. Wind speed: 18 mph

b. Wind direction: 226°

c. Stability: A

d. Ambient temperature: SST H. Primary chemistry conditions:

1. pH: 4.87

2. Boron: 1945 ppm 3.

Total beta gamma activity: 0.173 uci/ml

4. Iodine dose equivalent: 7.52E-4 uci/ml

Date OCTOBER 26. 1993 Message # 1 (Page 1) Time 0800 Scenario Time -0030 Time J~ - - Scenario Time J~ - -

C-08 SW P-7A ON P-78 ON P-7C STBY SW Critical Hdr Press A 76. B 75. psig S~

CC\I p~ P-52A ON P-52B ON P-52C Sffi FPC P~ P-51A OFF Fire P~ P-9A OFF P-9B OFF P-41 OFF P-51B ON Containment Cooler Recirc Fans V1A .Qff. V2A .Qff. V3A Q!! V4A Q!! V1B .Qff. V2B .Qff. V3B Qt! V4B Q!!

c-03 CCW Cooler Outlet T~ A 54. F B 55. F Containment Spray P~ P-54A OFF P-54B OFF P-54C OFF HPSI P~ P-66A OFF P-668 OFF LPSI P~ P-67A Qt! P-678 OFF Safety Injection Suction Supply Train A Train B CV-3057 CSIRW) CLOSED CV-3029 (SIRW) CLOSED CV-3031 (SIRW) CLOSED CV-3030 CS~) CLOSED Letdown Chara ins Intermediate Press Letdown T~ 85. F Flow 46. gpm Letdown Line T~ 84. F Line Teq> 99. F Letdown Flow 47. gpm P~ P-55A ON P-55B Qf.E P-55C OFF Volume Control Tank Teq> 85. F Pressure ~ psi Level 90. PCP Control Bleedoff Pressure 150 psig Shutdown Coolina System SDCS from PCS CR) ill F SDCS to PCS CR) 70. F Quench Tank Tellfl 102 F Pressure .:l.:. psig Level 65. %

Primary Coolant System Pressurizer Pressure CR) 244. psi a PCS Tave CR) Loop 1 CTR-0111) 115 Loop 2 CTR-0121) 115 Pressurizer Level CR> LRC-0101A 100 " LRC-0101B 100 LIA-0102A 97 Pzr Htr AfT4)S PORV LCC 15 o.

PRV-1042B CLOSED LCC 16 o. "

PRV-1043B CLOSED Block Valve MOV-1042A OPEN

" MOV-1043A OPEN PCPs P-50A ~ P-50B ~ P-50C ~ P-50D OFf" Reactor Power Level NI-01 TsE+o2 NI-02 :1'8E+02 NI-03 .82E-08 NI-04 .80E-08 NI-05 .12E-07 NI-06 .11E-07 NI-07 .12E-07 NI-08 *12E-07 C-01 AFW System AFW P~ P-8A OFF P-8B OFF P-8C OFF AFW P~ AfT4)S P-8A o. P-8C o.

AFW P~ P-8B Steam Pressure 0. psig AFW Disch Press P-8A &'P-8B 18. P-8C 18. psi Secondary System MSIV Bypass MOV-0501 ~ MOV-0510 CLOSED MSIV's CV-0501 CLOSED CV-0510 CLOSED MFP Suction Pressure 11:. psig MFP Discharge Pressure A~ B 15. psi Moisture Separator Drain Tank Level 26. % Condenser Hotwell Level 70. %

Atmospheric D~ Valves ~ Condenser Vacuum :0- in Hg.

Heater Drain P~ Status P-10A .Qff. P-10B Q.E.E Gland Seal Condenser Vacuum 14.2 in Hg.

Condensate P~ Status P-2A OFF P-28 Q.E.E (Demand Log + Constant, Rod, or Flux/Teq>)

Gross MW O. Net MW -3. Core Exit Thermocouple Temperature 115.3 F Control Rod Position GP1 0:- GP2 2.:_ GP3 2.:_ GP4 ,:.Q GP5CP) 1.:. GP6CA) 2.:_ GP7CB) O.

Stuck Rods .!!Q!!E. # Q -

Date OCTOBER 26. 1993 Message # 1 (Page 2) Time 0800 Scenario Time -0030 Time J~ Scenario Time J~ - -

C-13 T-81 Level 90. X T-9~9 Level 93. % Condensate Storage Tank Level T-2 89. x Instrument A"i"r"Pressure 95. psig Containnent Building Pressure -5. psig Dcme T~reture 103 F Hunidity 28. x S/G A Coq:>artment T~rature m F Hunidity 30. %

S/G B Coq:>artment Teq:>erature 92. F Hunidity 30 x SIRW Tank Level 98. x WR Contairment Pressure CR) iO psi a Contairment s....., Level 585 % Contairment Water Level CR) !!.:. %

SI Tank Level CX> A 40. B 39. c 39. D 39.

SI Tank Pressure Cpsig) A 150 B 151 c 151 D 152 PANEL K-13 SIAS Alarm NO Containment High Pressure Alarm ~ Contairment High Radiation Alarm NO Concentrated Boric Acid Tank Levels T53A 100. % T53B 10.6 %

Reactor Vessel DP 16.9 psid PORV Discharge T~rature TI1 F Pzr Safety Valve Discharge T~ CF> RV-1039 126 RV-1040 141 RV-1041 176 PCP Current (Aq:>ll) P-50A o. P-50B 668 P-50C 678 P-SOD 0.

PCS Flow 34. % Pressure LeVel (cold) 96.7 %

Loop Thot CF> Loop 1 TIS Loop 2 115 Loop Tcold CF) Loop 1 114 Loop 2 TIS

rcold Wide range Loop 1 TIS Loop 2 'ITT Subcooling T~ 283 F Press 242 psi PCS Prssure WR 244. NR 244. psi a Steam Generator A Steam Generator B Level CWR) 2Q.:. :t: CNR) 90. x CWR) 87. % CNR) 87. x Press 1. psi a 13. psis Flow Steam .0 PPH Feed .O PPH Steam .O PPH Feed ....Q PPH Note: Steam and Feed Flow )( 1000000 C-11 AFW Flow to A S/G From P-8A&B o. From P-8C o.

AFW Flow to B S/G From P-8A&B 0: From P-8C o.

Condenser Vacuun CR) 0:

PCP Seal Leakoff Flow P-50A 1.0 PPH P-50B .hQ PPH P-50C .hQ PPH P-500 .hQ PPH C-04 Diesel Generator Frequency 1-1 .o 1-2 .0 1-C BUS Voltage 2447 Amps 365 1-D BUS Voltage 2455 Amps 291 C-11 Back C-11A Contairment Area Monitors CR/Hr) RIA-1805 .2E-01 RIA-1806 .2E-01 RIA-1807 -.2-- RIA-1808 .8E-01 High Range Contairment Monitors CR/Hr) RIA-2321 :-ie-01 RIA-2322 :1E-OT Contairment Hydrogen Concentration (%) AI-2401R -0.-- AI-2401L -0.--

Main Steam Line Ganma Ccpm) RIA-2324 .3E+02 RIA-2323 .2E+02 Stack Monitors RIA-2325 ???? cpm RIA-2326 ....Q cpm RIA-2327 ....Q mr/hr

PALEX-93 TIME: ({)@() MESSAGE No: _j_

SCENARIO TIME: -a2.30

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SCENARIO TIME: -t2aJtJ

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PALEX-93 TIME: ~J~ t) . MESSAGE No: I SCENARIO TIME: -tJ(Jc.30

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SCENARIO TIME: - oa3CJ

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Scenario: PALEX-93 Time: 0832 Message No: 2

Scenario Time: 0002

Message For: Operators PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM s;mulated Plant Condit;ons:

Loss of Bus ID Message:

See attached Data and Alarm Sheets. Bus ID is deenergized; D/G 1-2 has tripped on overcrank .

FOR CONTROLLER USE ONLY Controller Notes:

Action expected:

I. Operators will invoke ONP-17, "Loss of Shutdown Cooling" and start P-678 to restore Shutdown Cooling.

2. Operators will invoke ONP-2.1, "Loss of AC Power" to repower Bus ID .

Date OCTOBER 26, 1993 Message # f (Page 1) Time 0832 Scenario Time 0002 Time Junp - - Scenario Time Junp - -

C-08 SW S~ P-7A OFF P-78 ON P-7C OFF SW Critieal Hdr Press A 46. 8 46 psig ccw P-51A OFF p~ P-52A ON"'" P-528 OFF P-52C ST8Y FPC P~

Fire P~ P-9A OFF P-98 OFF P-41 OFF P-518 OFF Contairment Cooler Recirc Fans V1A OFF V2A Qll V3A Qll V4A Q!! V18 Qll V28 Qll V3B Q!! V4B Q!

C-03 CCW Cooler outlet T~ A 46. F B 46. F Contairment Spray P~ P-54A OFF P-54B OFF P-54C OFF HPSI P~ P-66A OFF P-66B OFF LPSI P~ P-67A Qll P-678 Qff Safety Injection Suction Supply Train A Train B CV-3057 (SIRW) CLOSED CV-3029 (SIRW) £bQiEQ. CV-3031 (SIRW) ~ CV-3030 (Sunp) £bQiEQ.

Letdown Chars ins Intermediate Press Letdown T~ 113 F Flow 2.:. gpm Letdown Line Teirp 118 F Line T~ 99. F Letdown Flow 23. gpm P~ P-55A Qff P-55B OFF P-55C OFF Volume Control Tank Teirp 85. F Pressure 38. psi Level 94. x PCP Control Bleedoff Pressure 150 psig Shutdown Cool ins System SOCS from PCS (R) 94. F SOCS to PCS (R) 88. F Quench Tank

Pressurizer Pressure CR)

PCS Tave (R)

Pressurizer Level CR>

Pzr Htr ~

T~ 102 F 240. psi a Pressure Loop 1 CTR-0111) 120 Loop 2 (TR-0121) 120 LRC-0101A 100 x LCC 15 0:-

.:1.:. psig Primar:r: Coolant System LRC-0101B 100 %

LCC 16 0:-

Level 65.

LIA-0102A 97.

X x

PORV PRV-1042B CLOSED PRV-1043B CLOSED Block Valve MOV-1042A OPEN MOV-1043A OPEN PCPs P-50A OFF P-50B ~ P-50C ON P-500 OFF Reactor Power Level Nl-01 :18E+02 Nl-02 :18E+02 Nl-03 :82E-08 Nl-04 .80E-08 NI-05 .12E-07 Nl-06 .11E-07 Nl-07 .12E-07 Nl-08 .12E-07 C-01 AFW System AFW Punp P-8A Qll P-8B OFF P-8C OFF AFW Punp ~ P-8A 0. P-8C o.

AFW Punp P-8B Steam Pressure 0. psig AFW Disch Press P-SA & P-8B 18. P-8C 18. psi Secondary System MSIV Bypass MOV-0501 ~ MOV-0510 CLOSED MSIV's CV-0501 CLOSED CV-0510 CLOSED MFP Suction Pressure 12..:. psig MFP Discharge Pressure A~ B 15. psi Moisture Separator Drain Tank Level 26. % Condenser Hotwell Level 70. X Atmospheric Dunp Valves £bQiEQ. Condenser VacU1J11 :0- in Hg.

Heater Drain Punp Status P*10A Qff P-10B OFF Gland Seal Condenser Vacuun 14.2 in Hg.

Condensate Punp Status P-2A OFF P-2B Qff (Demand Log + Constant, Rod, or Flux/Ten.,)

Gross MW 0. Net MW 0. Core Exit Thermocouple Temperature 119.9 F Control Rod POsition GP1 D:" GP2 2.:_ GP3 Q.:. GP4 ,:.Q GP5(P) 1:. GP6(A) 2.:_ GP7(B) O.

Stuck Rods .!!Q!!g # Q -

Date OCTOBER 26. 1993 Message # ~ (Page 2) Time 0832 Scenario Time 0002 Time J~ - - Scenario Time J~ - -

&:Q T-81 Level 90. % T-939 Level 93. % Condensate* Storage Tank Level T-2 89. %

lnstrunent ATr""Pressure . 103 psig Contairment Building Pressure -5

psig Dome T~rature 103 F Hunidity 29. %

S/G A C~rtment T~rature 102 F Hunidity 30. %

S/G B C°""8rtment T~rature 93. F Hunidity 30. %

SIRW Tank Level 98. %

WR Contairment Pressure CR) ~ psi a Contairment S~ Level 585 % Contairment Water Level (R) Q... %

SI Tank Level (%) A 40. B 39. c 39. D 39.

SI Tank Pressure (psig) A 149 B 149 c 150 D ill PANEL K-13 SIAS Alarm NO Contairment High Pressure Alarm NO Contairment High Radiation Alarm NO Concentrated Boric Acid Tank Levels T53A 100. % T53B 10.6 %

Reactor Vessel DP 16.6 psid PORV Discharge T~rature 112 F Pzr Safety Valve Discharge T~ CF) RV-1039 126 RV-1040 141 RV-1041 176 PCP Current (~S) P-50A 0. P*50B 667 P-50C 678 P-50D O.

PCS Flow 35. % Pressure Level (cold) 96.8 Loop Thot CF) Loop 1 120 Loop 2 120 Loop Tcold CF) Loop 1 120 Loop 2 119 Tcold Wide range Loop 1 TI9 Loop 2 120 Subcooling T~ 2n F Press 238 psi PCS Prssure WR 240. NR 240. psia Steam Generator A Steam Generator B Level CWR) 90. % (NR) 90. % (WR) 87. % CNR) 87. %

Press 1:- psi a 13. psia Flow Steam .o PPH Feed .0 PPH Steam .0 PPH Feed ~ PPH Note: Steam and Feed Flow x 1000000 C-11 AFW Flow to A S/G From P-8A&B o. From P-8C 0.

AFW Flow to B S/G From P*SA&B ii: From P-8C 0.

Condenser Vacuun CR) ii:

PCP Seal Leakoff Flow P-50A 1.0 PPH P-50B bQ PPH P*50C bQ PPH P*50D bQ PPH C-04 Diesel Generator Frequency 1-1 60. 1-2 .o 1-C BUS Voltage 2442 Amps 407 1-D BUS Voltage 0. Amps 0.

C-11 Back C-11A Contairment Area Monitors CR/Hr) RIA-1805 .2E*01 RIA-1806 .2E*01 RIA-1807 -.2-- RIA-1808 .8E-01 High Range Contairment Monitors CR/Hr) RIA-2321 :1°E-01 RIA-2322 .1E-01 Contairment Hydrogen Concentration (%) AI-2401R -0.-- AI-2401L -0.--

Main Steam Line GaRllla Ccpm) RIA-2324 .3E+02 RIA-2323 .2E+02 Stack Monitors RIA-2325 1ill cpm RIA-2326 ~ cpm RIA-2327 ~ mr/hr

PALEX-93 TIME: t&,f.:J;z_ MESSAGE No:

SCENARIO TIME: 1'9(21!/,2-

ANNUNCIATOR DISPLAYS K-01

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MESSAGE No:

SCENARIO TIME: 1Jt2t2,L

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PALEX-93 TIME: -MESSAGE No:

SCENARIO TIME:

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P.ALEX-93 TIME:

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f}t2t);l-MESSAGE No:

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PALEX-93 TIME: tQJ'3 ,L MESSAGE No:

SCENARIO TIME: p()tJ,;l-

ANNUNCIATOR DISPLAYS K-21

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Scenario: PALEX-93 Time: 0833 Message No: 3 Scenario Time: 0003

PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Control Room Operators Simulated Plant Conditions:

Loss of Buss ID Message:

Shutdown Cooling Pump P-678 is running with total Shutdown Cooling flow approximately 3000 gpm; see Data and Alarm Sheets .

FOR CONTROLLER USE ONLY Controller Notes:

Action expected:

Date OCTOBER 26. 1993 Message # ~ (Page 1) Time 0833 Scenario Time 0003 Time J~ - - Scenario Time J~ - -

C-08 SW S~ P-7A OFF P-78 ON P-7C OFF SW Critical Hdr Press A 46. B 46. psig ccw P-52A ON p~ P-528 OFF P-52C ST8Y FPC P~ P-51A OFF Fire P~ P-9A OFF P-98 OFF P-41 OFF P-518 OFF Contairment Cooler Recirc Fans V1A OFF V2A OFF V3A OFF V4A ON V1B OFF V28 Qff. V3B ON V4B ON CCW Cooler Outlet Teq:> A 47. F 8 47. F Contairment Spray P~ P-54A OFF P-548 OFF P-54C OFF HPSI P~ P-66A OFF P-668 OFF LPSI P~ P-67A OFF P-678 ON Safety Injection Suction Supply Train A Train B CV-3057 (SIRW) CLOSED CV-3029 (SIRW) CLOSED CV-3031 (SIRW) CLOSED CV-3030 (S~) CLOSED Letdown Charging Intermediate Press Letdown Teq:> 108 F Flow 40. gpm Letdown Line Teq:> ill F Line Teq:> 103 F Letdown Flow 6. gpm P~s P-55A Qff. P-55B OFF P-55C Q!!

Volune Control Tank Teq:> 85. F Pressure 38. psi Level 94. x PCP Control Bleedoff Pressure 150 psig Shutdown Cooling System SOCS from PCS (R) 120 F SOCS to PCS (R) 70. F Quench Tank

Pressurizer Pressure (R)

PCS Tave CR)

Pressurizer Level CR)

Pzr Htr Alrps Teq:> 102 F 235. psi a Pressure .:.b. psig Primary Coolant System Loop 1 (TR-0111) 119 Loop 2 (TR-0121) 119 LRC-0101A 100 x LCC 15 0:-

LRC-01018 100 x LCC 16 0:-

Level LIA-0102A 97.

65. X x

PORV PRV-10428 CLOSED PRV-1043B CLOSED Block Valve MOV-1042A OPEN MOV-1043A OPEN PCPs P-50A ~ P-508 ~ P-50C i5N P-500 OFF Reactor Power Level NI-01 :TiiE+02 NI-02 :1°8E+02 NI-03 :8'2E-08 NI-04 .80E-08 NI-05 .12E-07 NI-06 .11E-07 NI-07 .12E-07 NI-08 .12E-07 C-01 AFW System AFW P~ P-8A OFF P-88 OFF P-8C OFF AFW P~ Alrps P-8A 0. P-8C o.

AFW P~ P-88 Steam Pressure 0. psig AFW Disch Press P-8A & P-88 18. P-8C 18. psi Secondary System MSIV Bypass MOV-0501 CLOSED MOV-0510 CLOSED MSIV's CV-0501 CLOSED CV-0510 CLOSED MFP Suction Pressure 12..:. psig MFP Discharge Pressure A~ 8 15. psi Moisture Separator Drain Tank Level 26. X Condenser Hotwell Level 70. X Atmospheric D~ Valves CLOSED Condenser Vacuum :C- in Hg.

Heater Drain P~ Status P-10A OFF P-108 OFF Gland Seal Condenser Vacuum 14.2 in Hg.

Condensate P~ Status P-2A OFF P-28 QEf.

(Demand Log + Constant, Rod, or Flux/Teq:>)

Gross MW 0. Net MW 0. Core Exit Thermocouple Teq:>erature 119.9 F Control Rod Position GP1 0. GP2 Q:. GP3 Q:. GP4 .J! GP5(P) 1..:. GP6(A) Q:. GP7(B) 0.

Stuck Rods .!!Q!!E. # Q

Date OCTOBER 26. 1993 Message # ~ (Page 2) Time 0833 Scenario Time 0003 Time J~ - - Scenario Time J~ - -

£.:ll

93. Condensate Storage Tank Level T-2 89.

T-81 Level 90. X T-939 Level Instrument AirPressure : "

95. psig "

Containnent Building Pressure -5. psig Dome 103 F Humidity 29.

S/G A COlll>Brtment T~rature T~rature 102 F

93. F Humidity 30.

Humidity 30.

SIG B COlll>Brtment SIRW Tank Level WR Containnent Pressure CR) 98.

~ psi a" T~rature Containnent S~ Level 585 Containnent Water Level CR) Q:.

SI Tank Level CX> A 40.

" B 39. c 39. D 39.

SI Tank Pressure Cpsig) A 149 B 149 c 149 D 151 PANEL K-13 SIAS Alarm NO Containnent High Pressure Alarm !Q Containnent High Radiation Alarm .No Concentrated Boric Acid Tank Levels T53A 100. T53B Reactor Vessel DP PORV Discharge T~rature 16.8 psid 112 F

" 10.6 "

Pzr Safety Valve Discharge T~ CF) RV-1039 127 RV-1040 142 RV-1041 1n PCP Current (~) P-50A 0. P-50B W P-50C 678 P-50D O.

PCS Flow 34. Pressure Level (cold)

Loop Thot CF)

Loop Tcold CF)

Loop 1 Loop 1 120 119

" Loop 2 Loop 2 120 ffii 96.9 "

Tcold Wide range Loop 1 120 Loop 2 TI9 Subcool ing T~ 275 F Press 233 psi PCS Prssure WR 235. NR 235. psi a Steam Generator A Steam Generator B Level (WR) 90. CNR) 90. CNR) 87.

Press "

~ psi a " (WR) 87. "

13. psia "PPH e

Flow Steam .0 PPH Feed .O PPH Steam .O PPH Feed ,:..Q Note: St'i!""am and Feed Flow x 1000000

£:11 AFW Flow to A S/G From P-8A&B o. From P-8C o.

AFW Flow to B S/G From P-8A&B 0. From P-8C o.

Condenser Vacuun CR) 0.

PCP Seal Leakoff Flow P-50A 1.0 PPH P-50B b.Q PPH P-50C b.Q PPH P-50D b.Q PPH C-04 Diesel Generator Frequency ,_, 60. 1-2 .o 1-C BUS Voltage 2433 Amps 494 1-D BUS Voltage 0. Amps 0.

C-11 Back C-11A Containnent Area Monitors CR/Hr) RIA-1805 .2E-01 RIA-1806 .2E-01 RIA-1807 -.2-- RIA-1808 .8E-01 High Range Containnent Monitors CR/Hr) RIA-2321 :i'E-01 RIA-2322 :1E-iii Containnent Hydrogen Concentration CX> Al-2401R -0.-- Al-2401L -0.--

Main Steam Line Ganma Ccpm) RIA-2324 .3E+02 RIA-2323 .2E+02 Stack Monitors RIA-2325 ???? cpm RIA-2326 ,:..Q cpm RIA-2327 ,:..Q mr/hr

PALEX-93 TIME: t2fd'3 MESSAGE No:

SCENARIO TIME: 1212<23

ANNUNCIATOR DISPLAYS K-01

- 1 **** 2 **** 3 **** 4 **** 5 **** 6 **** 7 **** 8 **** 9 *** 10 *** 11 *** 12 ***

1 ON

ON

+ ON

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PALEX-93 TIME: MESSAGE No:

SCENARIO TIME:

K-ANNUNCIATOR DISPLAYS 1 ON 01 ****

ON z **** ..3

- - - - 4

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- - - - ~*************************************~~w~*******

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PALEX-93 TIME: MESSAGE No:

SCENARIO TIME:

ANNUNCIATOR DISPLAYS K-06A

.;.:..:: * ....:**......*.;*;/:..:* . . . .* .....* ..

. **:\;.;* 1\;;*~ .\z ;~.~~

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1

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PALEX-93 TIME: ~f,3.3 MESSAGE No:

SCENARIO TIME : tJC):J..3

ANNUNCIATOR DISPLAYS K-07

- 1

- 1

- - - ~2

- - - 3 **** 4 **** 5 **** 6 **** 7 ****

*... ON e **** 9 *** 10 *** 11 *** 12 ***

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- - - - ~*-*****************************************

2 "'*

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K-09

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PALEX-93 TIME: MESSAGE No:

SCENilIO TIME:

ANNUNCIATOR DISPLAYS

- '1 **** 2 **** ~ **** 4 **** 5 **** 6 **** 7 **** 6 **** 9 '*** 1C *** 11 *** 12 ***

1 * * * ... * * * * * * *

* * *

ON * * * * *

ON *

- - - - w********w**~*****~***~*****T***~***~********w***************~**~***

2 * * * *

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- - - - www**************************************

3 * ... * * * ... * * * * *

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H * * * * * * * * * * *

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6 ON *

ON ... .,, * * *

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K-13

- 1 **** 2 **** 3 **** 4 **** 5 **** 6 **** 7 ****

s **** 9 *** 10 *** 11 *** 12 *** 13 -~~

1

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2 ON

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PALEX-93 TIME: Crfd3. MESSAGE No:

SCENARIO TIME: t2CJCJ3

ANNUNCIATOR DISPLAYS K-21

'* I*i1 +*.~*~,:2.:**.*.* ****

.: **<:::: *: ..::::::.:~--

.: ;.:tt:r,~;;;;;rr*:

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4 K-22

- 1 **** 2 **** 3 **** 4 **** 5 ***

1

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4 * .* ON 01\

PALEX-93 TIME: tJf'd3. MESSAGE No:

SCENARIO TIME: ~(JtJ.;3'

ANNUNCIATOR DISPLAYS

- -1 **** :2 ***** 3 ***** 4 ****

... s **** 6 **** 8 **** 9 *** 10 ***

1 * * * * * * * * *

.2 . .

3

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K9'.34

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1

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K-35

- 1 **** 2 **** 3 **** ~ **** s **** e **** 7 ***

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Scenario: PALEX-93 Time: 0835 Message No: 4 Scenario Time: 0005

PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Control Room Operators s;mulated Plant Cond;t;ons:

Loss of Bus ID Message:

The Spent Fuel Handling Machine, with bundle L-015 in its mast, has lost power at SFP location L-10 (in front of the south Tilt Pit gate). Also, lack of circulation ind*icates that the SFP Cooling Pump has tripped .

FOR CONTROLLER USE ONLY Controller Notes:

1. Message should be phoned into the Control Room by the simulator console operator to simulate the operators in the SFP area.

2. If the SFP operators are directed to manually position the SFHM, the Control Room should be advised (again, by phone) that movement is difficult as the hoist brake appears to be engaged.

Act;on expected:

Operators will manually energize Bus ID from Startup power or crosstie Load Centers 11 and 12 to restore SFP Cooling and the SFHM .

Scenario: PALEX-93 Time: 0844 Message No: 5 Scenario Time: OOI4

PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Control Room Operators Simulated Plant Conditions:

Reenergization of Bus ID Message:

Bus ID has been reenergized by Startup Power. See Data and Alarm Sheets *

FOR CONTROLLER USE ONLY Controller Notes:

I. If the less likely option of crosstieing LCCs II and I2 was selected, then verbally provide appropriate confirmation of restoration of power to SFP cooling and the SFHM at this time.

Action expected:

I. Resume fuel handling operations.

2. Start additional Service Water and CCW Pumps as necessary to stabilize PCS temperature when Buss ID is reenergized and restore normal Charging lineup .

Date OCTOBER 26. 1993 Message # 2 (Page 1) Time 0844 Scenario Time 0014 Time J....., -- Scenario Time J.....,

~

SW S.....,s P-7A OFF P-78 ON P-7C OFF SW Critical Hdr Press A 46. 8 46. psig P-528 OFF P-52C SrBY FPC P.....,s P-51A OFF CCW P.....,s P-52A ON"'"

Fire P.....,s P-9A OFF P-98 OFF P-41 OFF P-518 OFF Contairment Cooler Recirc Fans V1A QEf. V2A QEf. V3A QEf. V4A Qt! V18 QEf. V28 .QEf. V38 Qt! V48 Qt!

CCW Cooler Outlet T~ A 52. F 8 52. F Contairment Spray P.....,s P-54A OFF P-548 OFF P-54C OFF HPSI P.....,s P-66A OFF P-668 OFF LPSI P.....,s P-67A QEf. P-678 ON Safety Injection Suction Supply Train A Train B CV-3057 (SIRW) CLOSED CV-3029 (SIRW) ~ CV-3031 (SIRW) ~ CV-3030 cs.....,) CLOSED Letdown Charging Intermediate Press Letdown T~ 98. F Flow !Q.:. gpm Letdown Line T~ 105 F Line T~ 21.:. F Letdown Flow 32. gpm P.....,s P-55A OFF P-55B OFF P-55C Qt!

Volune Control Tank T~ 85. F Pressure 38. psi Level 94. PCP Control Bleedoff Pressure 150 psioi Shutdown Cooli!'.!S System SOCS from PCS (R) ill F SOCS to PCS (R) ~ F Quench Tank

Pressurizer Pressure (R)

PCS Tave (R)

Pressurizer Level CR>

T~ 102 F 249. psis Pressure Loop 1 (TR-0111) 119 Loop 2 (TR-0121) 119 LRC-0101A 100 " LRC-0101B 100

.:l:. psig Primary Coolant System Level LIA-0102A

~

2l.:.

X Pzr Htr ~

PORV LCC 15 o.

PRV-1042B ~

LCC 16 ~ "

PRV-1043B CLOSED Block Valve MOV-1042A OPEN

" MOV-1043A OPEN PCPs P-50A OFF P-50B ~ P-50C ON'" P-500 Of'F Reactor Power Level Nl-01 :18E+02 Nl-02 :1"8E+02 Nl-03 :82E-08 Nl-04 .80E-08 Nl-05 .12E-07 Nl-06 .11E-07 Nl-07 .12E-07 Nl-08 .12E-07

~

AFW System AFW P....., P-8A OFF P-8B .Q.E.E P-8C OFF AFW P....., A8')S P-8A 0. P-8C 0.

AFW P....., P-88 Steam Pressure 0. psig AFW Disch Press P-8A & P-8B 18. P-8C 18. p5i Secondary System MSIV Bypass MOV-0501 CLOSED MOV-0510 CLOSED MSIV's CV-0501 CLOSED CV-0510 CLOSED MFP Suction Pressure .1i:. psig MFP Discharge Pressure A ;s:--- B 15. psi Moisture Separator Drain Tank Level 26. X Condenser Hotwell Level 7ii:' X Atmospheric o....., Valves CLOSED Condenser Vacuum :0 in Hg.

Heater Drain P....., Status -P-10A OFF -P-108 .Q.E.E Gland Seal Condenser Vacuum-- 14.2 in Hg-.

Condensate P....., Status P-2A OFF P-28 Q.EI (Demand Log + Constant, Rod, or Flux/T~)

Gross MW O. Net MW O. Core Exit Thermocouple T~rature 120.0 F Control Rod POsition GP1 0:- GP2 Q.:. GP3 Q.:. GP4 .:,Q GP5CP) 1.:, GP6(A) Q.:. GP7(B) O.

Stuck Rods NONE # Q -

Date OCTOBER 26. 1993 Message # ~ (Page 2> Time 0844 Scenario Time 0014 Time Juip Scenario Time Juip - -

&.:.Y Condensate* Storage Tank Level T-2 89.

T-81 Level 90. X T-939 Level lnstrunent Air"Pressure ,.

93. "

100 psig "

-s. psig Dome 102 F Humidity 29.

Containnent Building Pressure T~rature S/G A C~rtment T~rature 102 F Humidity 30.

S/G B C~rtment T~rature 93. F Humidity ~

SIRW Tank Level 98. "

WR Containnent Pressure CR) 9."'" psis Containnent Suip Level Containnent Water Level CR)

SI Tank Level CX>

585 "

A 40. B 39. c 39.

2..:.

D 39.

SI Tank Pressure (psig) A 149 B 149 c 149 D 150 PANEL K-13 SIAS Alarm .!!Q Containnent High Pressure Alarm NO Containnent High Radiation Alarm NO Concentrated Boric Acid Tank Levels T53A iOO. T53B Reactor Vessel DP PORV Discharge T~rature

n 112 F "psid 10.6 "

Pzr Safety Valve Discharge T~ CF) RV-1039 m RV-1040 142 RV-1041 177 PCP Current (Amps) P-50A o. P-50B Mr P-50C 678 P-500 O.

PCS Flow 34. Pressure Level (cold)

Loop Thot (F)

Loop Tcold CF)

Loop 1 Loop 1 120 119

" Loop 2 Loop 2 120 120 96.6 "

Tcold Wide range Loop 1 120 Loop 2 119 Subcool ing T~ 281 F Press 247 psi PCS Prssure WR 249. NR 249. psi a Steam Generator A Steam Generator B Level 90. CNR) 90. (WR) CNR) 87.

Press Flow (WR)

Steam .0 PPH

- psi a Feed .0 PPH

" Steam

87. "

13. psis

.0 PPH Feed ...Q "PPH Note: Steam and Feed Flow x 1000000 C-11 AFW Flow to A S/G From P-8A&B o. From P-8C o.

AFW Flow to B S/G From P-8A&B ii: From P-8C o.

Condenser VacU\111 CR) ii:

PCP Seal Leakoff Flow P-50A 1.0 PPH P-50B !.:.Q. PPH P-50C !.:.Q. PPH P-500 !.:.Q. PPH c-04 Diesel Generator Frequency 1-1 60. 1-2 .o 1-C BUS Voltage 2433 Arrps 494 1-D BUS Voltage 2482 Arrps 45.

C-11 Back C-11A Containnent Area Monitors CR/Hr) RIA-1805 .2E-01 RIA-1806 .2E-01 RIA-1807 -.2-- RIA-1808 .8E-01 High Range Containnent Monitors CR/Hr> RIA-2321 :i'E-01 RIA-2322 .1E-01 Containnent Hydrogen Concentration CX> Al-2401R -0.-- Al-2401L -0.--

Main Steam Line Garrma Ccpm) RIA-2324 .3E+02 RIA-2323 .2E+02 Stack Monitors RIA-2325 1ill cpm RIA-2326 ...Q cpm RIA-2327 ...Q mr/hr

PALEX-93 TIME: ?JJ?f~ MESSAGE No:

SCENARIO TIME: LJc)/f'

ANNUNCIATOR DISPLAYS K-01

- 1 **** 2 **** 3 **** 4 ****

1 ON

~ **** 6 **** 7 **** s **** 9 *** 10

ON

ON 11 *** 12 ***

* * " ON * * *

.....;..........~****************************"********************************************

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SCENAllIO TIME: tJO/'(

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PALEX-93 TIME: ~)'¢~* MESSAGE No:

SCENARIO TIME~1

ANNUNCIATOR DISPLAYS K-C6A

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PALEX-93 TIME: Nl/'i *MESSAGE No:

SCENAR.IO TIME: t20/t./

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TIME: ~fff/ MESSAGE No: .::)

PALEX-93 SCENARIO TIME: 6t?/¢'

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PALEX-93 TIME: ?Jcft/g MESSAGE No: s-SCENARIO TIME: CJO tf

ANNUNCIATOR DISPLAYS K-21

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PALEX-93 TIME: MESSAGE No:

SCENARIO TIME:

ANNUNCIATOR DISPLAYS

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Scenario: PALEX-93 Time: 0845 Message No: b Scenario Time: 0015 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Control Room Operators Simulated Plant Conditions:

Tornado striking Auxiliary 8uilding\SFP Message:

A tornado has just destroyed the Safety Injection and Refueling Water Tank and the Spent Fuel Pool enclosure. Safety Injection Tank levels and pressures are in alarm; the Control Room is experienting heavy buffeting and negative atmospheric pressure. Plant Area Monitoring High Radiation Alarm EK-13 annunciator no.66 is in alarm due to SFP Area Monitor RIA-2313 being upscale high. The following HVAC Fans have tripped:

V-7 V-67 V-69 V-8A V-68A V-70A V-88 V-688 V-708 Control Room HVAC is operating normally. See attached Alarm and Data Sheets .

FOR CONTROLLER USE ONLY Controller Notes:

1. If questioned, the alternate SFP Area Monitor RIA-5709 is failed low, i.e.

is non-functional; SIRWT level indicators LIA-0331 and LIA-0332a are failed low; and SIRWT temperature indicators TIA-0328 and TIA-0332 are failed high.

SFP instruments LS-0924, TIA-0925 and TIA-0926 have been destroyed and their respective alarms are not functioning.

Action expected:

1. Declare an "ALERT" based on "Natural Phenomenon - Tornado Striking Facility" or a "SITE AREA EMERGENCY" based on "Fission Product Barriers -

Major Damage to Irradiated Fuel in Containment or Fuel Handling Building" (the real Control Room must sound the siren).

2. Operators will implement ONP 11.2, "Fuel Handling Accident" and dispatch personnel to locate/evacuate personnel in the SFP area.

Date OCTOBER 26. 1993 Message # §. (Page 1) Time 0845 Scenario Time 0015 Time Juip - - Scenario Time Juip - -

£.:!!§ SW S~ P-7A ON P-78 ON P-7C STBY SW Critical Hdr Press A 46. B 46. .psig ccw P-52A ON P-528 ON P-52C STBY FPC P~ P-51A OFF p~

Fire P~ P-9A OFF P-98 OFF P-41 OFF P-518 OFF Containment Cooler Recirc Fans V1A OFF V2A OFF V3A Q.E.f. V4A ON V1B Q.E.f. V2B OFF V3B ON V4B ON C-03 CCW Cooler outlet Teap A 52. F B 52. F Containment Spray P~ P-54A OFF P-548 OFF P-54C OFF HPSI P~ P-66A OFF P-668 OFF LPSI P~ P-67A Q.E.f. P-678 ON Safety Injection Suction Supply Train A Train B CV-3057 CSIRW) ~ CV-3029 CSIRW) ~ CV-3031 CSIRW) ~ CV-3030 (Sutp) ~

Letdown chars ins Intermediate Press Letdown Teap 98. F Flow 40. gpm Letdown Line leap 105 F Line Teap 21.:. F Letdown Flow . 32. gpm Puips P-55A ON P-55B OFF P-55C OFF VollJlle Control Tank leap 85. F Pressure 38. psi Level 94. x PCP Control Bleedoff Pressure 150 psfg Shutdown Cool ins System SDCS from PCS CR) ,gQ F SDCS to PCS CR) ~ F Quench Tank

Pressurizer Pressure CR)

PCS Tave CR)

Pressurizer Level (R)

Pzr Htr ~

Tefl1) 102_ F 249. psi a Pressure Loop 1 CTR-0111) 119 Loop 2 CTR-0121) 119 LRC-0101A 100 x LCC 15 Q."'

LRC-0101B 100 x LCC 16 o.

.:l:. psig Primary Coolant System Level 65.

LIA-0102A .2Z:. x X

PORV PRV-1042B CLOSED PRV-1043B 9:Qfil Block Valve MOV-1042A OPEN MOV-1043A OPEN PCPs P-50A OFF P-50B ON P-50C ON P-SOD OFF Reactor Power Level NI-01 :18E+02 NI-02 :1'8E+02 NI-03 .82E-08 NI-04 .80E-0&

NI-05 .12E-07 NI-06 .11E-07 NI-07 .12E-07 NI-08 .12E-O('

c-01 AFW System AFW Putp P-8A OFF P-88 OFF P-8C OFF AFW Puip ~ P-8A 2.:, P-8C O.

AFW Putp P-88 Steam Pressure 0. psig AFW Disch Press P-SA & P-88 ~ P-8C 18. ;pui Secondary System MSIV Bypass MOV-0501 ~ MOV-0510 CLOSED MSIV's CV-0501 CLOSED CV-0510 CLOSED MFP Suction Pressure .1i:. psig MFP Discharge Pressure A~ 8 15. p$i Moisture Separator Drain Tank Level 26. X Condenser Hotwell Level 70:- X Atmospheric Duip Valves ~ Condenser Vacuum :0 in Hg.

Heater Drain Puip Status - - P-10A Q.E.f. P-108 OFF- - Gland-seat Condenser-vacuum-

f4.2 in lie~

Condensate Puip Status P-2A OFF P-28 Q.E.f.

(Demand Log + Constant, Rod, or Flux/leap)

Gross MW 0. Net MW 0. Core Exit Thermocouple Temperature R!h.Q 'F Control Rod Position GP1 0:- GP2 2.:, GP3 2.:, GP4 ..:,Q GP5CP) 1..:. GP6CA) 2.:, GP7(B) 2.:,

Stuck Rods NONE # Q -

Date OCTOBER 26, 1993 Message # ~ (Page 2) Time 0845 Scenario Time 0015 Time J111p - - Scenario Time J111p

&.:ll T-81 Level 90. X T-939 Level 93. x Condensate* Storage Tank Level T-2 89. x lnstrunent AlrPressure . 100 psig Containnent Building Pressure -5

psig Dome T~rature 102 F Hunidity 29. x S/G A Coq:>artment T~rature 102 F Hunidity 30. x S/G B Coq:>artment T~rature 93. F Hunidity 30. x SIRIJ Tank Level o. x IJR Contairment Pressure CR> 9. psi a Conteirment S111p Level 585 x Contairment IJater Level CR) .!l.:. x SI Tank Level <X> A 40. B 39. c 39. D 39.

SI Tank Pressure Cpsig) A 149 B 149 c 149 D 150 PANEL K-13 SIAS Alarm .!!Q Contairment High Pressure Alarm .!!Q Contairment High Radiation Alarm .!!Q Concentrated Boric Acid Tank Levels T53A *100. x T53B 10.6 x Reactor Vessel DP 16.8 psid PORV Discharge T~rature 112 F Pzr Safety Valve Discharge T~ CF> RV-1039 127 RV-1040 142 RV-1041 177 PCP Current (Allps) P-50A o. P-50B 667 P-50C 678 P-500 O.

PCS Flow 34. x Pressure Level (cold) 96.6 Loop Thot CF) Loop 1 120 Loop 2 120 Loop Tcold CF> Loop 1 m Loop 2 120 Tcold IJide range Loop 1 120 Loop 2 ill Subcool ing T~ 281 F Press 247 psi PCS Prssure IJR 249. NR 249. psia Steam Generator A Steam Generator B Level (IJR) ~ x (NR) ~ x (IJR) 87. x CNR) 87. x Press 1. psi a 13. psia Flow Steam .o PPH Feed .0 PPH Steam .0 PPH Feed .:..2 PPH Note: Steam and Feed Flow x 1000000

~

AFIJ Flow to A S/G From P-SA&B o. From P-8C 0.

AFIJ Flow to B S/G From P-SA&B D." From P-8C 0.

Condenser Vacuun (R) D."

PCP Seal Leakoff Flow P-50A 1.0 PPH P-50B 1.:..2 PPH P-50C 1.:..2 PPH P-500 1.:..2 PPH

£:..!!!

Diesel Generator Frequency 1-1 60. 1-2 .o 1-C BUS Voltage 2433 Amps 494 1-D BUS Voltage 2482 Amps 45.

C-11 Back C-11A Contairment Area Monitors CR/Hr) RIA-1805 .2E-01 RIA-1806 .2E-01 RIA-1807 -.2-- RIA-1808 :ae:o; High Range Contairment Monitors CR/Hr) RIA-2321 :i"E-01 RIA-2322 .1E-01 Contairment Hydrogen Concentration CX> AI-2401R -0.-- AI-2401L -0.--

Main Steam Line Ganma Ccpm) RIA-2324 .3E+02 RIA-2323 .2E+02 Stack Monitors RIA-2325 ???? cpm RIA-2326 .:..2 cpm RIA-2327 .:..2 mr/hr

PALEX-93 TIME: IJPf.?' MESSAGE No:

SCENARIO TIME: t'JO/S

ANNUNCIATOR DISPLAYS K-01

- 1 **** 2 **** 3 **** 4 **** 5 **** 6 **** 7 **** 8 **** 9 *** 10 *** 11 *** 12 ***

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PALEX-93 TIME: ?Jft/:S:,,..,.. MESSAGE No:

SCENARIO TIME: ao/..:>

K-03 ANNUNCIATOR DISPLAYS 1 ON

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PALEX-93 TIME: &It!? MESSAGE No: --'--

SCE~IO TIME: tJtJJ.S-

ANNUNCIATOR DISPLAYS K-u6A 1 ****** ... **** 3 **** 4 ***

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PALEX-93 TIME: /Jf1/-_3 MESSAGE No:

SCENARIO TIME~._,--

ANNUNCIATOR DISPLAYS K-*

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PALEX-93 TIME: /P,ft/-5' MESSAGE No:

SCENARIO TIME: dtfl.£'

ANNUNCIATOR DISPLAYS K-11

- - - 3 **** 4 **** *5 **** 6 **** 7 **** 8 **** 9 *** 10 *** 11 *** 12 ....

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P.ALEX-93 TIME: tfJ?~S MESSAGE No:

SCElWlIO TIME: ~i£

ANNUNCIATOR DISPLAYS K-21

- - 1** '**** 2 **** 3 "**** 4 **** '.5 ***

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PALEX-93 TIME: tJf~ MESSAGE No:

SCENil.10 TIME: ()t2J,5"

ANNUNCIATOR DISPLAYS

- 1 **** 2 **** .3 **** 4 **** 5 **** 6 **** 7 **** **** 9 *** 10 ***

1

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Scenario No: PALEX-93 Time: 0845 Message No: * '6A Scenario Time: 0015

PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Containment HP Technician Simulated Plant Conditions:

Tornado striking Auxiliary Building/Spent Fuel Pool Message:

The Containment HP Technician hears a loud roaring sound and then crashing noises from the direction of the equipment hatch. Upon investigation he discovers:

1) The equipment hatch is blocked with debris

2) Daylight and rain can be seen through the debris pile

3) Alarms are sounding in the SFP area, and

4) He cannot hear or see the Operators who were in the SFP handling machine.

FOR CONTROLLER USE ONLY

Controller Notes:

Action Expected:

Scenario No: PALEX-93 Time: 0845 Scenario Time: 0015 Message No: *'6B PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: CAS and SAS Operators Simulated Plant Conditions:

Message:

CAS and SAS alarm panels receive**the following alarms:

84, 85, 97, 98, 1, 4 intrusion and tamper alarms, alarms will not clear; 86a, 86e, 93, 94, 95, 96, 99, 100, 101 intrusion alarms, alarms clear, some re-alarm and clear.

Doors 162, 163, 164, 166, 306, 144; 163 and 164 will not clear.

CAS and SAS have no coverage of PA from cameras 2, 14, 15, 16, or 23 .

CCTV coverage from other cameras indicate debris, siding, bags.; etc, in alarm zones 84, 85, a~d 1.

sheet metal It appears that fence, E-Field and Microwave damaged in southwest corner of PA and east side of PA along zone 85.

FOR CONTROLLER USE ONLY

\

Controller Notes:

Once security personnel have determined appropriate compensatory measures and applicable reportability, if any, compensatory measures may be simulated since recovery will be long term.

Action expected:

Security will determine how to respond to and compensate for alarms and damaged equipment .

Scenario No: PALEX-93 Time: 0850 Message No: ** 6C Scenario Time: 0035 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Messaqe For: Response Officer to Doors 144, 166 and 164 Simulated Plant Conditions:

Messaqe:

1. Upon response to Doors 144 and 166, the doors and area are found secure.

2. Upon response to Door 164, the door has been ripped from hinges. A hole in the roof allows rain to enter the Spent Fuel Pool Area. Radiation monitors are alarming.

FOR CONTROLLER USE ONLY controller Notes:

Information for 11 2 11 to be given to officer upon arrival at Doors 166 and 144.

Action Expected:

Notify CAS of findings, and follow directions from CAS and HP

Scenario No: PALEX-93 Time: 0850 Message No:

6D Scenario Time: 0035 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Patrol Officer - North End of Protected Area Simulated Plant conditions:

Message:

(Upon arrival of player) Debris in Zones 84 and 85.

Microwave heads damaged by debris. Zone 1 fence north of support building damaged (holes in wire mesh).

FOR CONTROLLER USE ONLY controller Notes:

Message given to officer when "damage should be in view."

Action Expected:

Report findings to CAS and wait for further instructions .

Scenario No: PALEX-93 Time: 0850 Message No: 6E Scenario Time: 0035 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Security Officers - South End of Protected Area Simulated Plant Conditions:

Message:

(Upon arrival of Player) Large hole is in the Southwest corner of the Protected Area fence. South end of Zone 7 and West half of Zone 98 missing due to tornado striking area.

CCTVs 14, 15, 16 and 23 along with the south end of the turbine building - roof is severely damaged.

FOR CONTROLLER USE ONLY controller Rotes:

Action Expected:

Contact CAS of findings in the area and follow proper compensatory measures. Await further instruction from CAS

Scenario: PALEX-93 Time: 0900 Message No: *"'J Scenario Time: 0030 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Control Room Operators Simulated Plant Conditions:

post-tornado Message:

See Data and Alarm Sheets .

FOR CONTROLLER USE ONLY Controller Notes:

Action expected:

I. Continue SEP activation.

2. Place Control Room HVAC in "Emergency" mode and seal any open penetrations in the CR/TSC envelope .

Date OCTOBER 26, 1993 Message # l (Page 1) Time 0900 Scenario Time 0030 Time J~ - - Scenario Time J~ - -

c-08 SW S~ P-7A ON P-78 ON P-7C . STBY SW Criti.cal Hdr Press A 46. B 46. psig ccw p~ P-52A ON P-52B ON P-52C STBY FPC P~ P-51A OFF Fire P~ P-9A Qff P-9B OFF P-41 QEf P-51B OFF Containment Cooler Recirc Fans V1A OFF V2A OFF V3A OFF V4A Qt! V1B QEf V2B QE.E V3B ON V4B Qt!

C-03 CCW Cooler Outlet T~ A 52. F B 52. F Containment Spray P~ P-54A OFF P-54B OFF P-54C OFF HPSI P~ P-66A OFF P-66B OFF LPSI P~ P-67A QE.E P-678 ON Safety Injection Suction Supply Train A Train B CV-3057 (SIRW) CLOSED CV-3029 CSIRW) ~ CV-3031 CSIRW) CLOSED CV-3030 CS~) CLOSED Letdown Charging Intermediate Press Letdown T~ 98. F Flow 40. gpm Letdown Line T~ 105 F Line T~ ~ F Letdown Flow 32. gpm P~ P-55A Q!! P-55B OFF P-55C OFF Volume Control Tank T~ 85. F Pressure 38. psi Level 94. x PCP Control Bleedoff Pressure 150 psi9 Shutdown Cool ins System SOCS from PCS CR) 120 F SOCS to PCS (R) 73. F Quench Tank

Pressurizer Pressure CR)

PCS Tave CR)

Pressurizer Level CR>

Pzr Htr ~

T~ 102 F 249. psia Pressure .:b. psig Primary Coolant System Loop 1 (TR-0111) 119 Loop 2 CTR-0121) 119 LRC-0101A 100 x LCC 15 ii:'"'""

LRC-0101B 100 x LCC 16 o.

Level 65.

LIA-0102A 97.

x x

PORV PRV-1042B CLOSED PRV-1043B ~ Block Valve MOV-1042A OPEN MOV-1043A OPEN PCPs P-50A ~ P-50B ON P-50C CiN P-500 OFF Reactor Power Level NI-01 :i8E+02 Nl-02 :18E+02 NI-03 .82E-08 Nl-04 .80E-08 NI-05 .12E-07 NI-06 .11E-07 NI-07 .12E-07 Nl-08 .12E-07 C-01 AFW System AFW P~ P-8A OFF P-88 Qff. P-8C OFF AFW P~~ P-8A 0. P-8C 0.

AFW P~ P-88 Steam Pressure 0. psig AFW Disch Press P-BA & P-8B 18. P-8C 18. psi Secondary System MSIV Bypass MOV-0501 ~ MOV-0510 CLOSED MSIV's CV-0501 CLOSED CV-0510 CLOSED MFP Suction Pressure 12.:. psig MFP Discharge Pressure A ;s:---- B 15. psi Moisture Separator Drain Tank Level 26. X Condenser Hotwell Level 70. X Atmospheric D~ Valves ~ Condenser Vacuum ~ in Hg.

Heater Drain P~ Status P-10A OFF P-10B QEf Gland Seal Condenser Vacuum 14.2 in Hg.

Condensate P~ Status P-2A OFF P-28 QEf (Demand Log + Constant, Rod, or Flux/T~)

Gross MW 0. Net MW o. Core Exit Thermocouple Temperature 120.0 F Control Rod Position GP1 ii:" GP2 Q.:. GP3 Q.:. GP4 .:,Q GPSCP) ~ GP6(A) Q... GP7(8) O.

Stuck Rods ~ # Q -

Date OCTOBER 26, 1993 Message # Z (Page 2) Time 0900 Scenario Time 0030 Time J~ - - Scenario Time J~ - -

£.:.ll

93. Condensate-Storage Tank Level T-2 89.

T-81 Level 90. X T-939 Level Jnstri.nent Air"Pressure . "

100 psig "

-5. psig Dome Tenperature 102 F H1m1idity 29.

Ccntairment Building Pressure S/G A COlllHlrtment Teq:>erature 102 F Hunidity 30.

S/G B COlllHlrtment Teq:>erature 93. F Hunidity 30.

SJRW Tank Level* 0.

WR Containment Pressure (R) 585

9. psi a Containment Water Level (R)

Containment S~ Level

SI Tank Level (X) A 40.

" B 39. c 39.

D 39.

SI Tank Pressure (psig) A 149 B 149 c 149 D 150 PANEL IC-13 SIAS Alarm NO Containment High Pressure Alarm !!Q Containment High Radiation Alarm !!Q Concentrated Boric Acid Tank Levels T53A 100. T53B Reactor Vessel DP PORV Discharge Teq:>erature 112 F 16.8 psid 10.6 "

Pzr Safety Valve Discharge T~ (F) RV-1039 127 RV-1040 142 RV-1041 177 PCP Current (Amps) P*50A 0. P*50B 667 P-50C 678 P-500 O.

PCS Flow 34. Pressure Level <cold)

Loop Thot (F)

Loop Tcold (F)

Loop 1 Loop 1 120 119

" Loop 2 120 Loop 2 120 96.6 "

Tcold Wide range Loop 1 120 Loop 2 TI9 Subcooling T~ 281 F Press 247 psi PCS Prssure WR 249. NR 249. psi a Steam Generator A Steam Generator B Level 90. (NR) 90. 87. % (NR) 87.

Press Flow (WR)

Steam .0 PPH

'f:"'" psi a Feed .O PPH

" (WR)

Steam

13. psia

.0 PPH Feed .:!

"PPH Note: Steam and Feed Flow x 1000000 C-11 AFW Flow to A S/G From P-SA&B 0. From P-8c.!!..:.

AFW Flow to B S/G From P-8A&B 0: From P-8C .!!..:.

Condenser vacuun (R) 0:

PCP Seal Leakoff Flow P-50A 1.0 PPH P-50B 1.:.Q PPH P*50C 1.:.Q PPH P-500 1.:.Q PPH C-04 Diesel Generator Frequency 1-1 60. 1-2 .o 1-C BUS Voltage 2433 Amps 494 1-D BUS Voltage 2482 Amps 45.

C-11 Back C-11A Containment Area Monitors CR/Hr) RIA-1805 .2E-01 RIA-1806 .2E-01 RIA-1807 -.2-- RIA-1808 .8E-01 High Range Containment Monitors (R/Hr) RIA-2321 :i'E-01 RIA-2322 .1E-01 Containment Hydrogen Concentration (%) AI-2401R -0.-- AI-2401L -0.--

Main Steam Line Ganma (cpm) RIA-2324 .3E+02 RIA-2323 .2E+02 Stack Monitors RIA-2325 ???? cpm RIA-2326 .:! cpm RIA-2327 .:,Q mr/hr

PALEX-93 TIME: ~{) MESSAGE No:

SCENARIO TIME: mao

ANNUNCIATOR DISPLAYS K-01

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PALEX-93 TIME: .MESSAGE No:

SCENARIO TIME:

. *:~. .. . .. .

K-J3 ANNUNCIATOR DISPLAYS

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PALEX-93 TIME: tJ'f/J~ MESSAGE No:

SCENARIO TIME: /AfO

ANNUNCIATOR DISPLAYS K-06A

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PALEX-93 TIME: ~~~ MESSAGE No: _:z_

SCENARIO TIME: /tl0.3P

ANNUNCIATOR DISPLAYS

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PALEX-93 TIME: t!J~CJ MESSAGE No:

SCENARIO TIME: @c3CJ

ANNUNCIATOR DISPLAYS K-11

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PALEX-93 TIME: t!Jft1tJ MESSAGE No:

SCEbh\RIO TIME: 4JC3tJ

ANNUNCIATOR DISPLAYS K-21

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PALEX-93 TIME: MESSAGE No:

SCENARIO TIME:

ANNUNCIATOR DISPLAYS 5

- 1 **** *2 **** 3 **** 4 **** **** 0 **** **** 9 *** 10 ***

1 * * * * * * * *

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Scenario: PALEX-93 Time: 0905 Message No: 8 Scenario Time: 0035 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Auxiliary Operator(s) dispatched to SFP area.

Simulated Plant Conditions: Post Tornado Message:

Initial damage assessment of SFP area:

1. High radiation levels at entrance to SFP.

2. Roof and walls of SFP enclosure are demolished, Equipment Hatch is plugged with debris, much debris in and around SFP.

3. SFP appears to be approximately 10 feet low and is continuing to fall; the sound of rushing water can be heard.

4. SFHM mast is exposed and is dangling from the machine by cables.

5. No sign of the operators known to have been in the area.

Additionally, your electronic dosimetry is alarming.

FOR CONTROLLER USE ONLY Controller Notes:

1. Message may be delayed slightly i f it takes longer than anticipated to transit from the simulator control room to the plant.

2. Due to the physical distances involved, once the AOs are dispatched from the simulator they will have to take all future direction from the control room by phone (ie, no "body double").

Action Expected:

1. Phone in report to simulator control room (2219/2238/2239).

2. Report to OSC and Health Physics for assessment of dose received.

3. Again report by phone to simulator control room when available for assignment .

Date OCTOBER 26. 1993 Message # § (Page 1> Time 0905 Scenario Time 0035 Time J~ - - Scenario Time J~ - -

C-08 Sil S~ P*7A ON P-78 ON P-7C STBY Sil Critical Hdr Press A 46. B 46. psig P-52A ON P-528 ON P-52C STBY FPC P~ P*51A OF"f" CCII P~

Fire P~ P-9A OFF P*9B OFF P-41 OFF P-518 OFF

. Contairrnent Cooler Reci re Fans V1A Q.Ef V2A OFF V3A OFF V4A Q!! V1B OFF V2B Q.Ef V3B ON V4B ON C-03 CCII Cooler Outlet T~ A 52. F B 52. F Containment Spray P~ P*54A OFF P-548 OFF" P-54C OFF HPSI P~ P*66A OFF P-668 OFF LPSI P~ P*67A Q.Ef P-678 Q!!

Safety Injection Suction Supply Train A Train B CV-3057 (SIRll) CLOSED CV-3029 (SIRll) CLOSED CV-3031 (SIRll) ~ CV-3030 CS~) ~

Letdown Charging Intermediate Press Letdown T~ 98. F Flow 40. gpm Letdown Line T~ 105 F Line T~ 91. F Letdown Flow 32. gpm p~ P-55A ON P-558 Q.Ef P-55C Qff Volune Control Tank T~ 85. F Pressure 38. psi Level 94. PCP Control Bleedoff Pressure 150 psig Shutdown Cooling System SOCS from PCS CR) 120 F SOCS to PCS CR) 73. F Quench Tank

Pressurizer Pressure CR)

PCS Tave (R)

Pressurizer Level CR)

Pzr Htr Amps T~ 102 F 249. psia LRC*0101A 100 X u:c 15 0.-

Pressure .:1.:. psig Primary Coolant System Loop 1 CTR-0111) 11£ Loop 2 CTR-0121) 119 LRC*0101B 100 "

LCC 16 a.-

Level 65.

LIA-0102A 97.

PORV PRV-10428 CLOSED PRV-10438 CLOSED Block Valve MOV-1042A ~ MOV*1043A ~

PCPs P-50A ~ P-508 ON P-50C ON P-500 OFF Reactor Power Level Nl-01 :18E+02 Nl-02 :18E+02 Nl-03 .82E-08 Nl-04 .80E-08 Nl-05

12E*07 NI *06 .11E*07 Nl-07 .12E-07 Nl-08 .:EE:QI AFll System AFll P~ P-8A OFF P-88 OFF P*8C OFF AFll P~ Amps P*8A O. P*8C O.

AFll P~ P-88 Steam Pressure 0. psig AFll Disch Press P-8A & P-88 18. P*8C 18. psi Secondary System MSIV Bypass MOV-0501 ~ MOV-0510 CLOSED MSIV's CV-0501 CLOSED CV-0510 CLOSED MFP Suction Pressure 12.:. psig MFP Discharge Pressure A ;s:--- B 15. .psi Moisture Separator Drain Tank Level 26. X Condenser Hotwell Level 70. X Atmospheric D~ Valves ~ Condenser Vacuun :0- in Hg.

Heater Drain P~ Status P-10A OFF P-108 Qff Gland Seal Condenser Vacuiin 14.2 in Hg.

Condensate .P~ Status P-2A OFF P-2B Qff (Demand Log + Constant, Rod, or Flux/T~)

Gross Mil 0. Net Mil O. Core Exit Thermocouple T~rature 120.0 F Control Rod Position GP1 0:- GP2 Q.:. GP3 Q.:. GP4 .:,Q GP5(P) 1..:. GP6(A) Q.:. GP7CB) O.

Stuck Rods ~ # Q -

Date OCTOBER 26. 1993 Message # § (Page 2> Time 0905 Scenario Time 0035 Time J....., -- Scenario Time J....., --

£:ll T-81 Level 90. X T-939 Level 93. x Condensate* Storage Tank Level T-2 89. x lnstrunent AfrPressure .* 100 psig Containnent Building Pressure -5

ps"ig Dame T~rature 102 F Hunidity 29. x S/G A COll'p8rtment T~rature 102 F Hunidity 30. x S/G B COll'p8rtment T~rature 93. F Hunidity 30. x SIRW Tank Level 0. x WR Contairment Pressure CR) 9. psi a Containnent s....., Level 585 x Contairment Water Level CR) .Q.:. x SI Tank Level CX> A 40. B 39. c 39. D ~

SI Tank Pressure Cpsig) A 149 B 149 c 149 D 150 PANEL K-13 SIAS Alarm NO Contairment High Pressure Alarm NO Contairment High Radiation Alarm !!Q c-12 Concentrated Boric Acid Tank Levels T53A *100. x T53B 10.6 x Reactor Vessel DP 16.8 psid PORV Discharge T~rature Pzr Safety Valve Discharge Teq> CF) RV-1039 127 m F RV-1040 142 RV-1041 1n PCP Current CA111>S> P*SOA 0. P*SOB W P*SOC 678 P-SOD o.

PCS Flow 34. x Pressure Level (cold) 96.6 x Loop Thot (F) Loop 1 120 Loop 2 120 Loop Tcold (F) Loop 1 119 Loop 2 120 Tcold Wide range Loop 1 120 Loop 2 m Subcooling Teq> 281 F Press 247 psi PCS Prssure WR 249. NR 249. psi a Steam Generator A Steam Generator B Level (WR) 90. x CNR) 90. x (WR) 87. x (NR) 87. x Press ;:-- psi a 13. psis Flow Steam .0 PPH Feed .o PPH Steam .O PPH Feed .:.!! PPH Note: Steam and Feed Flow x 1000000 c-11 AFW Flow to A S/G From P*SA&B o. From P-8c o.

AFW Flow to B S/G From P*8A&B D.' From P-8C o.

Condenser Vacuun (R) D.'

PCP Seal Leakoff Flow P-SOA 1.0 PPH P-508 !:Q PPH P*SOC !:Q PPH P*50D !:Q PPH C-04 Diesel Generator Frequency 1-1 60. 1-2 .o 1-C BUS Voltage 2433 ~ 494 1-D BUS Voltage 2482 ~ 45.

C-11 Back C*11A Contairment Area Monitors (R/Hr) RIA-1805 .2E*01 RIA-1806 .2E*01 RIA-1807 .2 RIA-1808 .8E*01 High Range Contairment Monitors CR/Hr> RIA-2321 .1E*01 RIA-2322 .1E*01 Contairment Hydrogen Concentration <X> Al-2401R -0.-- Al*2401L -0.--

Main Steam Line Ganma ccpm) RIA-2324 .3E+02 RIA-2323 .2E+02 Stack Monitors RIA-2325 ???? cpm RIA-2326 .:.!! cpm RIA-2327 ,:,Q mr/hr

PALEX-93 TIME: tJVf"'

SCENARIO TIME:@3~

MESSAGE No: L

ANNUNCIATOR DISPLAYS K-01

- 1 **** 2 **** 3 **** 4 **** 5 **** 6 **** 7 **** ! **** 9 *** 10 *** 11 *** 12 ~**

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PALEX-93 SCENARIO TIME:

TIME: tP~- __...,--

f2t}i::D MESSAGE No: L

.ANNUNCIATOR DISPLAYS

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PALEX-93 TIME: tJY~ MESSAGE No:

SCENARIO TIME: t?t1~

ANNUNCIATOR DISPLAYS K-G6A 1 **** ... **** 3 **** 4 ***

1

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PALEX-93 TIME: tJ~ MESSAGE No:

SCENARIO TIME: /1tJdS

ANNUNCIATOR DISPLAYS K-17

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PALEX-93 MESSAGE No:

ANNUNCIATOR DISPLAYS K-11

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PALEX-93 TIME: f?t10~ MESSAGE No: J?

/2123.S-SCENARIO TIME:

ANNUNCIATOR DISPLAYS K-21

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PALEX-93 TIME: ~._5' MESSAGE No:

M3f SCENARIO TIME:

ANNUNCIATOR DISPLAYS

- 1 **** 2 **** 3 **** 4 **** 5 **** 0 **** 7 **** ~ **** 9 *** 10 ***

1 * * * * * * * *

2.

- - - - ?~******************************************

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Scenario: PALEX-93 Time: 0915 Message No: / ,.

Scenario Time: 0045 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Control Room Operators s;mulated Plant Cond;t;ons:

Message:

See Alarm and Data Sheets

FOR CONTROLLER USE ONLY Controller Notes:

Action expected:

I. Complete SEP activation; communications turnover to TSC.

2. Upon receipt of report of low SFP level, operators will line up to make up to the SFP from Firewater per SOP 27 with TSC concurrence .

Date OCTOBER 26, 1993 Message # 2 (Page 1> Time 0915 Scenario Time 0045 Time J~-- Scenario Time J~ - -

C-08 SW SUJ1)5 P-7A ON P-78 ON P-7C STBY SW Criti*cal Hdr Press A 46. B 46. psig .

CCW PUJ1:>5 P-52A ON P-528 ON P-52C SrBY FPC PUJ1)5 P-51A OFF Fire PUJ1:>5 P-9A OFF P-98 OFF P-41 OFF P-518 OFF Contairment Cooler Recirc Fans V1A QE.E V2A OFF V3A OFF V4A ON V1B QE.E V2B OFF V3B ON V4B ON C-03 CCW Cooler outlet Temp A 52. F B 52. F Containnent Spray PUJ1:>5 P-54A OFF P-548 OFF P-54C OFF HPSI PUJ1)5 P-66A OFF P-668 OFF LPSI P~ P-67A OFF P-678 Q!!

Safety Injection Suction Supply Train A Train B CV-3057 (SIRW) ~ CV-3029 CSIRW) ~ CV-3031 (SIRW) CLOSED CV-3030 (S~) ~

Letdown Chars ins Intermediate Press Letdown Temp 98. F Flow !Q.:. gpm Letdown Line Temp 105 F Line Temp 21..:. F Letdown Flow 32. gpm PUJ1:>5 P-55A Q!! P-558 QE.E P-SSC QE.E Volune Control Tank Temp ~ F Pressure 38. psi Level 94. x PCP Control Bleedoff Pressure 150 psig Shutdown Cool ins System SOCS from PCS (R) 120 F SOCS to PCS (R) 73. F Quench Tank

Pressurizer Pressure CR>

PCS Tave CR)

Pressurizer Level CR>

Pzr Htr A""5 Temp 102 F 249. psi a Pressure .:k. psig Primary Coolant Loop 1 CTR-0111) 119 Loop 2 CTR-0121) 119 LRC-0101A 100 x LCC 15 0:-

LRC-01018 100 x LCC 16 0:-

S~tem Level LIA-0102A 97.

~ X x

PORV PRV-10428 CLOSED PRV-10438 CLOSED Block Valve MOV-1042A OPEN MOV-1043A OPEN PCPs P-SOA OFF P-508 ~ P-SOC ON P-SOD OFF Reactor Power Level Nl-01 :1iE+02 Nl-02 :i°8E+02 Nl-03 :8'2E-08 Nl-04 .80E-08 NI-OS .12E-07 Nl-06 .11E-07 Nl-07 .12E-07 Nl-08 .12E-07

£:Q1 AFW System AFW P~ P-8A OFF P-88 OFF P-8C OFF AFW P~ A8'>$ P*8A 0. P-8C 0.

AFW P~ P-88 Steam Pressure 0. psig AFW Disch Press P*8A & P-88 18. P*8C 18. psi Secondary System MSIV Bypass MOV-0501 CLOSED MOV-0510 CLOSED MSIV's CV-0501 CLOSED CV-0510 CLOSED MFP Suction Pressure .1i:, psig MFP Discharge Pressure A~ 8 15. psi Moisture Separator Drain Tank Level 26. X Condenser Hotwell Level 70. X Atmospheric D~ Valves CLOSED Condenser Vacuum :0 in Hg.

Heater Drain P~ Status -p-1QA*QE.E P~108 Q.EI. --Gland Seal Condenser Vacuum* 14.2 - in Hg. --

Condensate P~ Status P*2A OFF P-28 OFF (Demand Log + Constant, Rod, or Flux/Temp)

Gross MW 0. Net MW 0. Core Exit Thermocouple Temperature 120.0 F Control Rod Pcisition GP1 0. GP2 .!!..:. GP3 .!!..:. GP4 .:.,Q. GPS(P) 1.:. GP6CA) .Q.:. GP7(8) 0.

Stuck Rods ~ # Q -

Date OCTOBER 26, 1993 Message # f (Page 2> Time 0915 Scenario Time 0045 Time J~ - - Scenario Time J~ - -

.£:.ll T-81 Level 90. X T-939 Level 93. x Condensate Storage Tank Level T-2 89.

Instrunent Air""Pressure 1ciO psig "

Contairment Building Pressure -5. psig Dome 102 F Hunidity 29.

S/G A C°""8rtment S/G B C°""8rtment T~rature T~rature T~rature 102 F

93. F Hunidity 30.

Hunidity 30.

"xx SIRW Tank Level o. x WR Contairment Pressure CR> 9. psi a Contairment S~ Level 585 x Contairment Water Level CR) Q.:. x SI Tank Level CX> A 40. B 39. c 39. D 39.

SI Tank Pressure (psig) A 149 B 149 c 149 D 150 PANEL K-13 SIAS Alarm NO Contairment High Pressure Alarm NO Contairment High Radiation Alarm NO concentrated Boric Acid Tank Levels T53A . 100. x T53B 10.6 x Reactor Vessel DP 16.8 psid PORV Discharge T~rature Pzr Safety Valve Discharge Tenp CF) RV-1039 127 m F RV-1040 142 RV-1041 177 PCP current C.Aq:>s> P*50A o. P-50B 667 P-50C 678 P-500 O.

PCS Flow 34. x Pressure Level (cold) 96.6 x Loop Thot CF> Loop 1 120 Loop 2 120 Loop Tcold CF> Loop 1 119 Loop 2 120 Tcold Wide range Loop 1 120 Loop 2 TI9 Subcool ing Tenp 281 F Press 247 psi PCS Prssure WR 249. NR 249. psi a Steam Generator A Steam Generator B Level CWR> 90. x CNR) 90. x (WR) 87. x CNR) 87. x Press ;:- psi a 13. psia Flow Steam .o PPH Feed .O PPH Steam .0 PPH Feed .:.!! PPH Note: Steam and Feed Flow x 1000000 C-11 AFW Flow to A S/G From P-8A&B o. From P-8C o.

AFW Flow to B S/G From P-8A&B a: From P-8C 0.

Condenser vacut.111 CR) Q."

PCP Seal Leakoff Flow P-50A 1.0 PPH P-508 .1.J! PPH P*50C .1.J! PPH P*50D .1.J! PPH c-o4 Diesel Generator Frequency 1-1 60. 1-2 .o 1-C BUS Voltage 2433 Aq>s 494 1-D BUS Voltage 2482 Aq>s 45.

C-11 Back C-11A Containnent Area Monitors CR/Hr) RIA-1805 .2E*01 RIA-1806 .2E-01 RIA-1807 -.2-- RIA-1808 .8E-01 High Range Containnent Monitors CR/Hr) RIA-2321 :1E-01 RIA-2322 .1E*01 Containnent Hydrogen Concentration CX) Al-2401R -0.-- Al-2401L -0.--

Main Steam Line GaRlllB (cpm) RIA-2324 .3E+02 RIA-2323 .2E+02 Stack Monitors RIA-2325 1111 cpm RIA-2326 ~ cpm RIA-2327 .:,Q mr/hr

PALEX-93 TIME: t?l/6- MESSAGE No:

SCENARIO TIME: ,&tJt/5 ANNUNCIATOR DISPLAYS K-01

- 1 **** z **** 3 **** 4 **** **** 6 **** 7 ****

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PALEX-93 ' TIME: t!/f/5" MESSAGE No:

SCENARIO TIME: @~

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K-03 ANNUNCIATOR DISPLAYS 1 ON

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PALEX-93 TIME: &Vf" MESSAGE No:

SCEN:ARIO TIME: @#'..£

ANNUNCIATOR DISPLAYS K-Ci6A 1 **** ' **** 3 **** 4 ***

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PALEX-93 TIME: '2f/.5* MESSAGE No:

SCENARIO TIME:M"fl'6

- ANNUNCIATOR DISPLAYS

- 1 **** .2 **** 3 **** 4 ..... 5 "*** *":> **** 7 **** 8 **** 9 *** 10 *** 11 *** 12 ***

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PALEX-93 TIME: t!f# MESSAGE No:

SCENARIO TIME: f2CJf£

ANNUNCIATOR DISPLAYS K-11

- 1 ***** -2 **** 3 **** 4 **** s **** c **** **** e **** 9 *** 1 o *** 11 *** 12 ***

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PALEX-93 TIME: CJtf/f MESSAGE No: L SCENARIO TIME: @"l/.P

ANNUNCIATOR DISPLAYS K-21

- 1 **"** 2 **** 3 **** ...

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PALEX-93 TIME: t?'f/.5 / /' MESSAGE No:

SCENARIO TIME: faf0

** 1 **** 2 **** 3 **** 4 ****

ANNUNCIATOR DISPLAYS 5 **** 6 **** 7 **** **** 9 *** 10 ***'

1 * * * * * * * * * *

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Scenario: PALEX-93 Time: 0930 Message No: I0

Scenario Time: 0100

PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Control Room Operators Simulated Plant Conditions:

Message:

See attached Data and Alarm sheets. Electric Fire Pump P-9A is running due to SFP fill efforts *

*FOR CONTROLLER USE ONLY Controller Notes:

Control room controller needs to remember to have simulator personnel start P-9A at this point.

Action expected:

1. Commence search and rescue operations.

2. Upgrade SEP classification, if not done previously, to Site Area Emergency or higher.

3 ~ Co111mence debris _capture/r_etent ion effprts ._

Date OCTOBER 26, 1993 Message # 10 (Page 1> Time 0930 Scenario Time 0100 Time JUf4:> - - Scenario Time JUf4:> - -

C-08 SW SUf4:>5 P-7A ON P-78 ON P-7C STBY SW Critical Hdr Press A 46. B 46. psig CCW PUf4:>5 P-52A ON P-528 ON P*52C STBY FPC PU1'4'5 P*51A OFF Fire PUf4:>5 P-9A ON P-98 OFF P-41 OFF P-518 OFF Contairment Cooler Recirc Fens V1A 2f! V2A 2f! V3A 2f! V4A .Q?! V1B OFF V2B OFF V3B .Q?! V4B .Q?!

~

CCW Cooler Outlet T~ A 52. F B 52. F Conteirment Spray PUf4:>5 P-54A OFF P-548 OFF P-54C OFF HPSI PUf4:>5 P-66A OFF P-668 OFF LPSI PUf4:>5 P-67A 2f! P-678 .Q?!

Safety Injection Suction Supply Train A Train B CV-3057 (SIRW) CLOSED CV-3029 (SIRW) CLOSED CV-3031 (SIRW) CLOSED CV-3030 (SUf4:>) CLOSED Letdown Charging Intermediate Press Letdown T~ 98. F Flow 40. gpm Letdown Line T~ iOs F Line T~ 91. F Letdown Flow 32. gpm PUf4:>5 P-55A ON P-558 OFF P-55C QEf Volume Control Tank T~ 85. F Pressure 38. psi Level 94. x PCP Control Bleedoff Pressure 150 ps;f!

Shutdown Cooling System SOCS from PCS (R) 120 F SOCS to PCS (R) 73. F Quench Tank

Pressurizer Pressure CR>

PCS Tave (R)

Pressurizer Level (R)

T~ 102 F 249. psie Pressure Loop 1 (TR-0111) 119 Loop 2 (TR-0121) 119 LRC-0101A 100 x

.:1.:. psig Primary Coolant System LRC-01018 100 x Level 65.

LIA-0102A 97.

X x

Pzr Htr Aq>s LCC 15 0. LCC 16 0.

PORV PRV-10428 CLOSED PRV-10438 CLOSED Block Valve MOV-1042A OPEN MOV-1043A OPEN PCPs P-50A OFF P-508 ~ P-50C ON P-500 OFF Reactor Power Level NI-01 TBE+02 NI-02 :18E+02 NI-03 "Ji2E-08 NI-04 .80E-08 NI-05 .12E-07 NI-06 .11E-07 NI-07 .12E-07 NI-08 .12E-07 C-01 AFW System AFW PUf4:> P-8A OFF P-88 OFF P-8C OFF AFW PUf4:> A8'>S P-8A 0. P-8C 0.

AFW PUf4:> P-88 Steam Pressure 0. psig AFW Disch Press P-8A & P-88 18. P-BC 18. :psi Secondary System MSIV Bypass MOV-0501 CLOSED MOV-0510 CLOSED MSIV 1 s CV-0501 CLOSED CV-0510 CLOSED MFP Suction Pressure 12:. psig MFP Discharge Pressure A ;s:--- B 15. -psi Moisture Separator Drain Tank Level 26. X Conclenser Hotwell Level 70. X Atmospheric 0Uf4:> Valves CLOSED Condenser Vacuum :0- in Hg.

Heeter Drain PUf4:> Status -- -P* 10A QEf -- P-108 QEf Glend Seal tondenser Vacuum - 14.2- -in Hg.

Condensete Pump Status P-2A OFF P-28 QEf (Demand Log + Constant, Rod, or Flux/T~)

Gross MW O. Net MW 0. Core Exit Thermocouple T~reture 120.0 -F Control Rod Position GP1 0:- GP2 Q.:. GP3 Q.:. GP4 ..:..2 GP5(P) 1.:. GP6(A) Q.:. GP7(B) 0.

Stuck Rods NONE # .Q -

Date OCTOBER 26, 1993 Message # !Q (Page 2) Time 0930 Scenario Time 0100 Time J~ - - Scenario Time J~ - -

C-13 T-81 Level 90. X T-939 Level 93. x Condensate Storage Tank Level T-2 89. x lnstrunent AirPressure .

100 psig Contairvnent Building Pressure -5

psig Dome T~rature 102 F Hi.nidity 29. x S/G A C~rtment T~rature 102 F Hi.nidity 30. x S/G B C~rtment T~rature 93. F Hi.nidity 30. x SIRW Tank Level o. x WR Contairment Pressure CR) 9. psi a Contairvnent S~ Level 585 x Contairvnent Water Level CR> 2..:. x SI Tank Level (X) A 40. 8 39. c 39. D 39.

SI Tank Pressure (psig) A 149 B 149 c 149 D 150 PANEL K-13 SIAS Alarm .!!Q Contairvnent High Pressure Alarm .!!Q Contairvnent High Radiation Alarm .!!Q Concentrated Boric Acid Tank Levels T53A . 100. x T538 10.6 x Reactor Vessel DP 16.8 psid PORV Discharge T~rature m F Pzr Safety Valve Discharge T~ CF) RV-1039 127 RV-1040 142 RV-1041 1n PCP Current (Allps) P-50A 0. P-508 667 P-50C 678 P-50D 0.

PCS Flow 34. x Pressure Level (cold) 96.6 x Loop Thot CF) Loop 1 120 Loop 2 120 Loop Tcold CF) Loop 1 119 Loop 2 120 Tcold Wide range Loop 1 120 Loop 2 119 Subcooling T~ 281 F Press 247 psi PCS Prssure WR 249. NR 249. psi a Steam Generator A Steam Generator 8 Level (WR) 90. x CNR) 90. x (WR) 87. x CNR) 87. x Press 1:- psi a 13. psia Flow Steam .0 PPH Feed .0 PPH Steam .0 PPH Feed .:.Q PPH Note: Steam and Feed Flow x 1000000 C-11 AFW Flow to A S/G From P-8A&8 o. From P-8C o.

AFW Flow to B S/G From P-8A&8 0: From P*8C 0.

Condenser Vacui.n CR) 0:

PCP Seal Leakoff Flow P-50A 1.0 PPH P-508 1.:.Q PPH P-50C 1.:.Q PPH P-50D 1.:.Q PPH C-04 Diesel Generator Frequency 1-1 60. 1-2 .0 1-C BUS Voltage 2433 Anps 494 1-D BUS Voltage 2482 Amps 45.

C-11 Back C-11A Contairvnent Area Monitors CR/Hr) RIA-1805 .2E-01 RIA-1806 .2E*01 RIA-1807 -.2-- RIA-1808 .8E-01 High Range Contairvnent Monitors CR/Hr) RIA-2321 :1°E-01 RIA-2322 .1E*01 Contairvnent Hydrogen Concentration (%) Al-2401R -0.- Al-2401L -0.--

Main Steam Line Ganma (cpm) RIA-2324 .3E+02 RIA-2323 .2E+02 Stack Monitors RIA-2325 ???? cpm RIA-2326 .J! cpm RIA-2327 .J! mr/hr

PALEX-93 TIME: tf?tj'dtJ MESSAGE No:

SCENARIO TIME: (2/(?tJ

. *=~*..

ANNUNCIATOR DISPLAYS K-01

- 1 **** z **** 3 **** 4 **** * **** 6 **** 7 **** ! **** 9 *** 10 *** 11 *** 12 ***

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PALEX-93 TIME: f}fc.3 C) . MESSAGE No:

SCENARIO TIME: t1/I /t?tJ

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PALEX-93 TIME: t?fdtJ MESSAGE No:

SCENARIO TIME: C/Z'?J

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PALEX-93 TIME: tJ?d~ . MESSAGE No: _l!!_

SCENARIO TIME: tJ/IJt/

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PALEX-93 TIME: {Jf30 MESSAGE No:

SCENARIO TIME: 0/.0?J

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Scenario: PALEX-93 Time: 0945 Message No: II Scenario Time: 0115

PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Control Room Operators Simulated Plant Conditions:

Message: .

SFP level is recovering at approximately 2 inches per minute. See attached Data And Alarm Sheets .

FOR CONTROLLER USE ONLY Controller Notes:

Action expected:

Develope strategy to increase SFP boron to compensate for dillution from Fire Water .

,--------------------------------------------------------~--

Date OCTOBER 26, 1993 Message # 11 (Page 1> Time 0945 Scenario Time 0115 Time J~ - - Scenario Time J~ - -

c-08 SW S~ P-7A ON P-78 ON P*7C STBY SW Criti.cal Hdr Press A 46. B 46. psig ccw P-52A ON .* P-52B ON P*52C STBY FPC P~ P-51A OFF p~

Fire P~ P*9A ON P*9B OFF P-41 OFF P-51B OFF Contail'lllent cooler Recirc Fans V1A Q.E.f. V2A OFF V3A OFF V4A ON V1B OFF V2B Q.E.f. V38 Q!l. V4B ON CCW Cooler Outlet Teq:> A 52. F B 52. F Contail'lllent Spray P~ P-54A OFF P-54B OFF P*54C OFF HPSI P~ P-66A OFF P-66B OFF LPSI P~ P-67A Q.E.f. P-678 ON Safety Injection Suction Supply Train A Train 8 CV-3057 (SIRW) ~ CV*3029 (SIRW) CLOSED' CV-3031 CSIRW) ~ CV-3030 CS~) CLOSED Letdown Chars ins Intermediate Press Letdown Teq:> 98. F Flow 40. gpm Letdown Line Teq:> 105 F Line Teq:> 21:. F Letdown Flow 32. gpm P~ P-55A ON P-558 Q.E.f. P-55C OFF Volume Control Tank Teq:> 85. F Pressure 38. psi Level 94. x PCP Control 8leedoff Pressure 150 psig Shutdown Cool ins System SDCS from PCS CR) 120 F SDCS to PCS CR) 73. F Quench Tank

Pressurizer Pressure CR>

PCS Tave CR)

Pressurizer Level CR)

Pzr Htr A8'>S Teq:> 102 F 249. psi a Pressure Loop 1 CTR-0111) 119 Loop 2 CTR*0121) 119 LRC-0101A 100 x LCC 15 a:-

.:b. psig Primary Coolant System LRC-01018 100 x LCC 16 a:-

Level 65. X LIA*0102A 97. x PORV PRV-1042B CLOSED PRV-1043B CLOSED Block Valve MOV*1042A OPEN MOV-1043A Qffil!

PCPs P-50A OF'F'" P-50B ON P-50C ON P-50D OFF Reactor Power Level NI-01 :18E+02 Nl-02 :1'8E+02 Nl-03 .82E-08 Nl-04 .80E-08 Nl-05 *12E-07 Nl-06 .11E-07 Nl-07 .12E-07 Nl-08 .12E-07 C-01 AFW system AFW P~ P-8A OFF P-88 OFF P-8C OFF AFW P~ Amps P-8A O. P-8C O.

AFW P~ P-88 Steam Pressure 0. psig AFW Disch Press P-BA & P-88 18. P-8C 18. psi Secondary System MSIV Bypass MOV-0501 CLOSED MOV-0510 CLOSED MSIV's CV-0501 CLOSED CV-0510 CLOSED MFP Suction Pressure - - 12..:. psig MFP Discharge Pressure A ~ 8 15. psi Moisture Separator Drain Tank Level 26. X Condenser Hotwell Level 70. %

Atmospheric D~ Valves CLOSED Condenser Vacuum :0- in Hg.

Heater Drain P~ Status P-10A OFF P-108 OFF Gland Seal Condenser Vacuum 14.2 in Hg.

Condensate P~ Status P-2A OFF P-28 QE.f (Demand Log + Constant, Rod, or Flux/Teq:>)

Gross MW 0. Net MW 0. Core Exit Thermocouple Temperature 120.0 F Control Rod Position GP1 0:- GP2 Q.,, GP3 Q.,, GP4 .J!. GP5CP) 1..:. GP6CA) Q.,, GP7(B) O.

Stuck Rods NONE # Q -

Date OCTOBER 26, 1993 Message # 11 (Page 2) Time 0945 Scenario Time 0115 Time J~-- Scenario Time J~ - -

T-81 Level 90. X T-939 Level 93. % Condensate Storage Tank Level T-2 89.

Jnstrunent AirPressure .

100 psig Containment Building Pressure -5. psig Dome TE!fl1)erature 102 F Hunidity 29.

S/G A COll'pllrtment S/G B COll'pllrtment Teft1>erature TE!fl1)erature 102 F

93. F Hunidity 30.

Hunidity 30.

SJRW Tank Level WR Containment Pressure CR) o.

9.' psi a Containment S~ Level 585 Containment Water Level CR>

SJ Tank Level CX> A 40.

" B 39. c 39.

D 39.

SJ Tank Pressure Cpsig) A 149 B 149 c 149 D 150 PANEL K-13 SIAS Alarm NO Containment High Pressure Alarm NO Containment High Radiation Alarm NO C-12 Concentrated Boric Acid Tank Levels T53A 100. T53B 10.6 Reactor Vessel DP PORV Discharge TE!fl1)erature 112 F 16.8 psid "

Pzr Safety Valve Discharge T~ CF) RV-1039 127 RV-1040 142 RV-1041 177 PCP Current (~) P-50A o. P-508 667 P-50C 678 P-50D o.

PCS Flow 34. Pressure LeVel (cold> 96.6 Loop Thot (F)

Loop Tcold (F)

Loop 1 Loop 1 120 ill

" Loop 2 120 Loop 2 120 Tcold Wide range Loop 1 120 Loop 2 119 Subcooling T~ 281 F Press 247 psi PCS Prssure WR 249. NR 249. psi a Steam Generator A Steam Generator B Level (WR) 90. (NR) 90. (WR) (NR) 87.

Press Flow Steam

- psi a

.o PPH Feed

.0 PPH Steam

87. "

13. psia

.0 PPH Feed ,:.Q "PPH Note: Steam and Feed Flow x iiiooooo c-11 AFW Flow to A S/G From P-8A&B o. From P-8C 0.

AFW Flow to B S/G From P-8A&B 0. From P-8C o.

Condenser Vacuun CR> 0.

PCP Seal Leakoff Flow P-50A 1.0 PPH P-508 hQ PPH P-50C hQ PPH P-500 hQ PPH C-04 Diesel Generator Frequency 1-1 60. 1-2 .0 1-C BUS Voltage 2433 Al"'5 494 1-D BUS Voltage 2482 Al"'5 45.

C*11 Back C-11A Containment Area Monitors CR/Hr) RIA-1805 .2E-01 RIA-1806 .2E-01 RIA*1807 -.2-- RIA-1808 .8E*01 High Range Containment Monitors CR/Hr) RIA-2321 :1E*01 RIA*2322 *1E-01 Containment Hydrogen Concentration (%) Al-2401R -0.-- Al-2401L -0.--

Main Steam Line Ganma Ccpm) RIA-2324 .3E+02 RIA-2323 .2E+02 Stack Monitors RIA*2325 1111. cpm RIA*2326 ,:.Q cpm RIA-2327 ,:.Q mr/hr

PALEX-93 TIME: C/(~ MESSAGE No: -1L SCENARIO TIME: a/)£

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PALEX-93 TIME: ~£ MESSAGE No: _Ji_

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PALEX-93 TIME: MESSAGE No:

SCENAllIO TIME:

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PALEX-93 TIME: . @1? MESSAGE No:

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PALEX-93 MESSAGE No:

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PALEX-93 TIME: t!JtfV-- MESSAGE No:

SCERARIO TIME: CJ//£

ANNUNCIATOR DISPLAYS

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PALEX-93 TIME:

SCENARIO TIME:O///° t?':fy- MESSAGE No:

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Scenario: PALEX-93 Time: 1000 Message No: /;i._

Scenario Time: 0130

PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Control Room Operators Simulated Plant Conditions:

Message:

SFP level continues to recover at approximately 2 inches per minute. See attached Alarm and Data Sheets .

FOR CONTROLLER USE ONLY Controller Notes:

Action expected:

Date OCTOBER 26, 1993 Message # 12 (Page 1) Time 1000 Scenario Time 0130 Time J~ - - Scenario Time J~ - -

£.:fil!

SW S~ P-7A ON P-78 ON P-7C STBY SW Critical Hdr Press A 46. B 46. psig ccw P-52A ON P-528 ON P-52C STiiY FPC P~ P-51A OFF p~

Fire P~ P-9A ON P-98 OFF P-41 OFF P-518 OFF Containment Cooler Recirc Fans V1A Qll V2A Qll V3A OFF V4A ~ V1B Qll V2B Qll V3B Q!l. V4B ON C-03 CCW Cooler Outlet T~ A 52. F B 52. F Containment Spray P~ P-54A OFF P-548 OFF P-54C OFF HPSI P~ P-66A OFF P-668 OFF LPSI Pl.Jli>S P-67A .Q.Ef. P-678 ~

Safety Injection Suction Supply Train A Train B CV-3057 CSIRW) ~ CV-3029 CSIRW) CLOSED CV-3031 CSIRW) CLOSED CV-3030 CS~) ~

Letdown Chars ins Intermediate Press Letdown T~ 98. F Flow 40. gpn Letdown Line T~ 105 F Line T~ 21.:. F Letdown Flow 32. gpn P~ P-55A ~ P-558 Qll P-55C Qll Volune Control Tank T~ 85. F Pressure 38. psi Level 94. x PCP Control Bleedoff Pressure 150 psig Shutdown Cool ins system SOCS from PCS CR) 120 F SOCS to PCS CR) 73. F Quench Tank

Pressurizer Pressure CR)

PCS Tave (R)

Pressurizer Level CR)

Pzr Htr A""8 T~ 102 F 249. psia Pressure .:b. psig Prima:cv Coolant System Loop 1 CTR-0111) 119 Loop 2 (TR-0121) 119 LRC-0101A 100 x LCC 15 0:-

LRC-01018 100 x LCC 16 0:-

Level 65.

LIA-0102A 97.

X x

PORV PRV-10428 CLOSED PRV-10438 CLOSED Block Valve MOV-1042A OPEN MOV-1043A ~

PCPs P-50A ~ P-508 ON P-50C ON P-500 OFF Reactor Power Level Nl-01 :18E+02 Nl-02 :1°8E+02 Nl-03 .82E-08 NI-04 .80E-08 NI-05 .12E-07 NI-06 .11E-07 NI-07 .12E-07 NI-08 .12E-07 c-01 AFW System AFW Pl.Jll> P-8A OFF P-88 OFF P-8C OFF AFW p~ ~s P-8A 0. P-8C O.

AFW Pl.Jll> P-88 Steam Pressure 0. psig AFW Disch Press P-8A & P-88 18. P-8C 18. psi Secondary System MSIV Bypass MOV-0501 CLOSED MOV-0510 ~ MSIV's CV-0501 CLOSED CV-0510 CLOSED MFP Suction Pressure 12..:.. psig MFP Discharge Pressure A 15':""""""""" B 15. psi Moisture Separator Drain Tank Level 26. X Condenser Hotwell Level 70. X Atmospheric DI.Ill> Valves CLOSED Condenser Vacul.111 :0- in Hg.

Heater Drain Pl.Jll> Status P-10A Qll P-108 Qf.E Gland Seal Condenser Vacul.111 14.2 in Hg.

Condensate Pl.Jll> Status P-2A OFF P-28 Qf.E (Demand Log + Constant, Rod, or Flux/T~>

Gross MW 0. Net MW 0. Core Exit Thermocouple T~rature 120.0 F Control Rod Position GP1 ii:" GP2 .!!.:, GP3 .!!.:, GP4 _,_Q GP5(P) 1..:. GP6(A) .!!.:, GP7(B) O.

Stuck Rods !!Q!!E. # Q -

Date OCTOBER 26, 1993 Message # 12 CPage 2) Time 1000 Scenario Time 0130 Time JUJ1) Scenarfo Time JUJ1) - -

T-81 Level 90. X T-939 Level 93. " Condensate Storage Tank Level T-2 lnstrunent Air""Pressure .

100 psig Containment Building Pressure -5. psig Dome Tefl1)erature 102 F H1i11idity 29.

S/G A C~rtment S/G B C~rtment Tefl1)erature Tefl1)erature 102 F

93. F H1i11idity 30.

H1i11idity 30.

SIR" Tank Level WR Contairment Pressure CR>

0.

9. psia Contairment SUJ1> Level Contairment "ater Level CR) !h SI Tank Level CX>

585 "

A 40. B 39. c 39. D 39.

SI Tank Pressure Cpsig) A 149 B 149 c 149 D 150 PANEL K-13 SIAS Alarm NO Contairment High Pressure Alarm .!!Q Containment High Radiation Alarm NO Concentrated Boric Acid Tank Levels T53A 100. " T53B 10.6 "

Reactor Vessel DP 16.8 psid PORV Discharge Tefl1)erature 112 F Pzr Safety Valve Discharge T~ CF) RV-1039 127 RV-1040 142 RV-1041 177 PCP Current (Alrps) P-50A o. P-508 667 P-50C 678 P-500 0.

PCS Flow 34. " Pressure Level (cold) 96.6 Loop Thot CF> Loop 1 120 Loop 2 120 Loop Tcold (F) Loop 1 m Loop 2 120 Tcold "ide range Loop 1 120 Loop 2 119 Subcooling T~ 281 F Press 247 psi PCS Prssure WR 249. NR 249. psis Steam Generator A Steam Generator B Level 90. CNR) 90. CNR) 87.

Press Flow (WR)

Steam .o PPH"

~ psi a Feed .0 PPH

" (WR)

Steam

87. "

13. psis

.0 PPH Feed .:.,Q PPH Note: Steam and Feed Flow x iOooooo f:.11 AF" Flow to A S/G From P-8A&B

0. From P-8C 0.

AF" Flow to B S/G From P-8A&B Q.' From P-8C o.

Condenser Vacu1i11 CR) Q.'

PCP Seal Leakoff Flow P-50A 1.0 PPH P-508 Ll! PPH P-50C Ll! PPH P-500 Ll! PPH C-04 Diesel Generator Frequency 1-1 60. 1-2 .o 1-C BUS Voltage 2433 Amps 494 1-D BUS Voltage 2482 Amps 45.

C-11 Back C-11A Contairment Area Monitors CR/Hr) RIA-1805 .2E-01 RIA-1806 .2E-01 RIA-1807 -.2-- RIA-1808 .8E-01 High Range Contairment Monitors CR/Hr) RIA-2321 :1°E-01 RIA-2322 .1E-01 Contairment Hydrogen Concentration (X) AI-2401R -0.-- AI-2401L -0.--

Main Steam Line Ga11111a (cpm) RIA-2324 .3E+02 RIA-2323 .2E+02 Stack Monitors RIA-2325 1111. cpm RIA-2326 .:.,Q cpm RIA-2327 .:.,Q mr/hr

PALEX-93 TIME: JIJ(JO MESSAGE No:

SCENARIO TIME:' C/d?J

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Scenario: PALEX-93 Time: 1015 Message No: I3 Scenario Time: 0145

PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Control Room Operators Simulated Plant Conditions:

Message:

SFP level continues to recover at approximately 2 inches per minute. See attached Alarm and Data Sheets .

FOR CONTROLLER USE ONLY Controller Notes:

Action expected:

As SFP radiation levels decrease, develope strategies to:

1. Capture the damaged SFHM mast and hoist box containing the fuel bundle.

2. Restore SFP cooling in an orderly fashion .

Date OCTOBER 26, 1993 Message # 13 (Page 1) Time 1015 Scenario Time D145 Time J~ - - Scenario Time J~ - -

~

SIJS~ P*7A ON P-78 ON P*7C STBY Slol Critical Hdr Press A 46. B 46. psig P*52C SriiY P-51A OFF CCIJ P~ P-52A ON P-528 ON FPC P~

Fire P~ P*9A ON P-98 OFF P-41 OFF P-518 OFF

containment Cooler Recirc Fans V1A QE.E. V2A QE.E. V3A QE.E. V4A Qt! V1B QE.E. V2B QE.E. V3B Qt! V4B .Qt!

C-D3 CCIJ Cooler Outlet T~ A 52. F B 52. F Containment Spray P~ P*54A OFF P-548 OFF P-54C OFF HPSI P~ P-66A OFF P-668 OFF LPSI P~ P*67A OFF P-678 ON Safety Injection Suction Supply Train A Train B CV-3057 (SIRIJ) CLOSED CV-3029 (SIRIJ) CLOSED CV-3031 (SIRW) CLOSED CV-3030 CS~) £!:Q§EQ Letdown Chars ins Intermediate Press Letdown T~ 98. F Flow 40. gpm Letdown Line T~ 105 F Line T~ 21.:. F Letdown Flow 32. gpm P~ P-55A ON P-558 QE.E. P*55C QE.E.

Voll.Ille Control Tank T~ 85. F Pressure 38. psi Level 94. PCP Control Bleedoff Pressure 150 psig Shutdown Cool ins System SOCS from PCS CR) 12D F SOCS to PCS (R) 73. F Quench Tank

Pressurizer Pressure (R)

PCS Tave CR)

Pressurizer Level CR)

T~ 102 f 249. psi a Pressure :b. psig Primary Coolant System Loop 1 CTR-0111) 119 Loop 2 (TR-0121) 119 LRC-01D1A 100 " LRC-01018 100 Level LIA-0102A &.

65. X Pzr Htr Aq>S PORV LCC 15 0:-

PRV-10428 CLOSED LCC 16 0:- "

PRV-10438 CLOSED Block Valve MOV-1042A Qffil!

" MOV-1043A OPEN PCPs P-5DA OFF P-508 ~ P-50C ON P-500 OFF Reactor Power Level NI *01 :18E+02 NI-02 :i'8E+02 NI-03 .82E-08 NI-04 .SOE-OB NI-05 .12E-07 NI-06 .11E-07 NI-07 .12E-07 NI-08 .12E-07 C-01 AFIJ System AFIJ P~ P-8A OFF P-88 QE.E. P*8C OFF AFIJ Pl.Jl1) Amps P*8A 0. P*8C 0.

AFIJ P~ P-88 Steam Pressure 0. psig AFIJ Disch Press P-8A & P-88 18. P*8C 18. psi Secondary System MSIV Bypass MOV-0501 £!:Q§EQ MOV-0510 CLOSED MSIV's CV-0501 CLOSED CV-0510 CLOSED MFP Suction Pressure .1i:. psig MFP Discharge Pressure A~ B 15. psi Moisture Separator Drain Tank Level 26. X Condenser Hotwell Level 70. X Atmospheric D~ Valves ~ Condenser Vacuum :0 in Hg.

Heater Drain P~ Status- -- -- P--10A-*OFF - P-108* QE.E.** - Gland* Seal Condenser* vacuum*** *14.-2*

in Hg. -

Condensate P~ Status P-2A OFF P-28 OFF (Demand Log + Constant, Rod, or Flux/T~>

Gross Mlol 0. Net Mlol D. Core Exit Thermocouple Temperature 12D.D F Control Rod Position GP1 D. GP2 Q.:. GP3 Q.:. GP4 .:,Q GP5(P) 1:. GP6(A) Q.:. GP7(8) D.

Stuck Rods !!QHE # Q

Date OCTOBER 26. 1993 Message # 13 (Page 2> Time 1015 Scenario Time 0145 Time J~ - - Scenario Time J~ - -

£:ll T-81 Level 90. X T-939 Level 93. x Condensate Storage Tank Level T-2 !l2.:. x 100 psig Jnstrunent AirPressure .

Contail'lllent Building Pressure -5

psig Dome Teq>erature 102 F H1.111idity 29. x S/G A COll1)8rtment Teq>erature 102 F H1.111idity 30. x S/G B COll1)8rtment Teq>erature 93. F H1.111idity 30. x SIRW Tank Level o. x WR Contail'lllent Pressure CR> 9. psi a Contail'lllent S~ Level 585 x Contail'lllent Water Level (R) !k. x SI Tank Level (X) A 40. B 39. c 39. D 39.

SI Tank Pressure (psig) A 149 B 149 c 149 D 150 PANEL K-13 SIAS Alarm !!Q Contail'lllent High Pressure Alarm !!Q Contail'lllent High Radiation Alarm NO Concentrated Boric Acid Tank Levels T53A 100. x T53B 10.6 x Reactor Vessel DP ~ psid PORV Discharge T~rature 112 F Pzr Safety Valve Discharge T~ CF> RV-1039 127 RV-1040 142 RV-1041 177 PCP Current (Amps) P-SOA o. P-SOB 667 P-SOC 678 P-500 O.

PCS Flow 34. x Pressure LeVel <cold) 96.6 Loop Thot <F> Loop 1 120 Loop 2 gQ Loop Tcold (F) Loop 1 119 Loop 2 120 Tcold Wide range Loop 1 120 Loop 2 119 Subcooling T~ 281 F Press 247 psi PCS Prssure WR 249. NR ~ *psia Steam Generator A Steam Generator B Level (WR) 90. x CNR) 90. x (WR) 87. x (NR) 87. x Press ;:- psi a 13. psia Flow Steam .0 PPH Feed .O PPH Steam .0 PPH Feed ~ PPH Note: steam and Feed Flow x 1000000 C-11 AFW Flow to A S/G From P-8A&B o. From P*8C 0.

AFW Flow to B S/G From P*8A&B 0: From P-8C 0.

Condenser VacU\111 (R) 0:

PCP Seal Lealcoff Flow

P-SOA 1.0 PPH P*SOB !:..Q PPH P-SOC !:..Q PPH P-SOD !:..Q PPH C-04 Diesel Generator Frequency 1-1 60. 1-2 .0 1*C BUS Voltage 2433 Amps 494 1-D BUS Voltage 2482 Amps 45.

C*11 Back C-11A Contail'lllent Area Monitors CR/Hr) RIA*1805 .2E-01 RIA-1806 .2E-01 RIA-1807 -.2-- RIA-1808 .8E-01 High Range Contail'lllent Monitors (R/Hr> RIA-2321 :i"E-01 RIA-2322 .1E-01 Contail'lllent Hydrogen Concentration <X> AI*2401R -0.-- AI-2401L -0.--

Main Steam Line Ganma (cpm) RIA*2324 .3E+02 RIA-2323 .2E+02 Stacie Monitors RIA-2325 ???? cpm RIA*2326 .& cpm RIA*2327 _& mr/hr

TIME:

/tJ/.5 . MESSAGE No:

PAI..EX-93 SCENARIO TIME: 6V"i/'~

** 1 **** z ****

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SCENARIO TIME: tO/"f/.£

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PALEX-93 TIME: /~/f MESSAGE No:

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PALEX-93 TIME: MESSAGE No: /.J SCENARIO TIME:

ANNUNCIATOR DISPLAYS K-21

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PALEX-93 TIME: /?)/._5" . MESSAGE No: /3 t?/¥.?

SCENARIO TIME:

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Scenario: PALEX-93 Time: 1030 Message No: /7' Scenario Time: 0200

PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Control Room Operators Simulated Plant Conditions:

Message:

SFP level continues to recover at aoproximately 2 inches per minute. See Aalrm and Data Sheets. *

FOR CONTROLLER USE ONLY Controller Notes:

Action expected:

Date OCTOBER 26, 1993 Message # 14 (Page 1) Time 1030 Scenario Time 0200 Time J~ - - Scenario Time J~ - -

£:.Q§ SW S~ P-7A ON P-78 ON P-7C STBY SW Critical Hdr Press A 46. B 46. psig ccw P-52A ON P-52B ON P-52C STBY FPC P~ P-51A Ci'Ff" p~

Fire P~ P-9A ON P-9B OFF P-41 OFF P-51B OFF Containment Cooler Recirc Fans V1A Q.Ef V2A OFF V3A Q.Ef V4A Qt!. V1B Q.Ef V2B OFF V3B ON V4B Qt!.

CCW Cooler outlet T~ A 52. F B 52. F containment Spray P~ P-54A Ci'Ff" P-54B Ci'Ff" P-54C OFF HPSI P~ P-66A OFF P-66B OFF LPSI P~ P-67A OFF P-678 ON Safety Injection Suction Supply Train A Train B CV-3057 CSIRW) CLOSED CV-3029 CSIRW) ~ CV-3031 CSIRW) CLOSED CV-3030 CS~) CLOSED Letdown Chars ins Intermediate Press Letdown T~ 98. F Flow 40. gpm Letdown Line T~ 105 F Line T~ ~ F Letdown Flow 32. gpm P~ P-55A Qt!. P-558 OFF P-55C OFF Volume Control Tank T~ 85. F Pressure 38. psi Level 94. PCP Control Bleedoff Pressure 150 psig Shutdown Cool ins System SOCS from PCS CR) 120 F SOCS to PCS CR) 73. F Quench Tank

Pressurizer Pressure CR>

PCS Tave CR>

Pressurizer Level CR)

T~ m F 249. psi a Pressure .:l:. psig Primary Coolant System Loop 1 CTR-0111) 119 Loop 2 CTR-0121) 119 LRC-0101A 100 x LRC-0101B 100 Level LIA-0102A 97.

65. X Pzr Htr ~

PORV LCC 15 0.-

PRV-1042B CLOSED LCC 16 0.- "

PRV-1043B CLOSED Block Valve MOV-1042A OPEN

" MOV-1043A OPEN PCPs P-50A ii'FF" P-508 ON P-50C ON P-500 OFF"""

Reactor Power Level Nl-01 :l8E+02 Nl-02 :1"8E+02 Nl-03 .82E-08 Nl-04 .80E-08 Nl-05 .12E-07 Nl-06 .11E-07 Nl-07 .12E-07 Nl-08 .12E-07 C-01 AFW System AFW P~ P-8A OFF P-8B Q..Ef P-8C OFF AFW P~ ~ P-8A 0. P-8C 0.

AFW P~ P-8B Steam Pressure 0. psig AFW Disch Press P-8A & P-8B 18. P-8C 18. psi Secondary System MSIV Bypass MOV-0501 CLOSED MOV-0510 CLOSED MSIV's CV-0501 CLOSED CV-0510 CLOSED MFP Suction Pressure - - 1.h psig MFP Discharge Pressure A~ B 15. psi Moisture Separator Drain Tank Level 26. X Condenser Hotwell Level 70. X Atmospheric D~ Valves CLOSED Condenser Vacuum :0 in Hg.

Heater Drain P~ Status P-10A OFF P-10B OFF Gland Seal Condenser Vacuum 14.2 in Hg.

Condensate P~ Status P-2A OFF P-2B Q..Ef (Demand Log + Constant, Rod, or Flux/T~)

Gross MW 0. Net MW 0. Core Exit Thermocouple Teq:>erature 120.0 F Control Rod Position GP1 O. GP2 ,!h GP3 ,!h GP4 ..:.,Q GP5(P) .!:. GP6CA) ,!h GP7(B) O.

Stuck Rods NONE # Q

Date OCTOBER 26. 1993 Message # 14 (Page 2) Time ~ Scenario Time 0200 Time J~ Scenario Time J~ - -

C-13 T-81 Level 90. X T-939 Level 93. x Condensate Storage Tank Level T-2 89. x lnstrunent Air"Pressure ,. 100 psig Contairment Building Pressure -5

psig Dome T~rature 102 F HllRidity 29. x S/G A C~rtment T~reture 102 F HllRidity 30. x SIG B C~rtment T~reture 93. F HllRidity 30. x SIRW Tank Level o. x llR Conteirment Pressure CR) 9. psi a Contairment S~ Level 585 x Conteirment Water Level CR> ~ x SI Tank Level CX> A 40. B 39. c 39. D 39.

SI Tank Pressure Cpsig) A 149 B 149 c 149 D 150 PANEL K-13 SIAS Alarm NO Conteirment High Pressure Alarm !!Q Conteirment High Radiation Alarm NO Concentrated Boric Acid Tank Levels T53A

100. x T53B 10.6 x Reactor Vessel DP 16.8 psid PORV Discharge T~rature 112 F Pzr Safety Valve Discharge T~ CF> RV-1039 127 RV-1040 142 RV-1041 177 PCP Current (~) P-50A 0. P-50B 667 P-50C 678 P-500 0.

PCS Flow 34. x Pressure Level <cold) 96.6 Loop Thot CF) Loop 1 120 Loop 2 120 Loop Tcold (F) Loop 1 119 Loop 2 120 Tcold Wide range Loop 1 120 Loop 2 ill Subcool ing T~ 281 F Press 247 psi PCS Prssure WR 249. NR 249. psia Steam Generator A Steam Generator B Level CWR) 90. x (NR) 90. x (llR) 87. x CNR) 87. x Press ;-:- psi a 13. psie Flow Steam .o PPH Feed .0 PPH Steam .0 PPH Feed ...Q PPH Note: Steam and Feed Flow x 1000000 C-11 AFW Flow to A S/G From P-8A&B 0. From P-8C 0.

AFW Flow to B S/G From P-8A&B 0. From P-8C 0.

Condenser VacullR CR) 0.

PCP Seal Leekoff Flow P-50A 1.0 PPH P-50B 1:.Q PPH P-50C 1:.Q PPH P-500 1:.Q PPH C-04 Diesel Generator Frequency 1-1 60. 1-2 .0 1-C BUS Voltage 2433 Amps 494 1-D BUS Voltage 2482 Amps 45.

C-11 Back C-11A Conteirment Area Monitors CR/Hr) RIA-1805 .2E-01 RIA-1806 .2E-01 RIA-1807 -.2-- RIA-1808 .8E-01 High Range Contairment Monitors CR/Hr) RIA-2321 :-i"E-01 RIA-2322 .1E-01 Conteirment Hydrogen Concentration CX> Al-2401R -0.-- AI-2401L -0.--

Mein Steam Line Ganma Ccpm) RIA-2324 .3E+02 RIA-2323 .2E+02 Steck Monitors RIA-2325 1111 cpm RIA-2326 ...Q cpm RIA-2327 ...Q mr/hr

PALEX-93 TIME: /tJcJtJ MESSAGE No:

?J.2.610 SCENARIO TIME:

ANNUNCIATOR DISPLAYS K-01

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PALEX-93 TIME: /030 MESSAGE No:

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PALEX-93 TIME: /{)30 MESSAGE No:

SCEEAB.IO TIME: &e??JO

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PALEX-93 TIME: MESSAGE No:

SCENARIO TIME:

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PALEX-93 TIME: . /tJd t) MESSAGE No:

SCENAB.IO TIME: Pd@

ANNUNCIATOR DISPLAYS K-11

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PALEX-93 TIME: /tJ.3{) MESSAGE No:

SCENARIO TIME: &;ltJO I

ANNUNCIATOR DISPLAYS K-21

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PALEX-93 TIME: /4,3ZJ MESSAGE No:

SCENARIO TIME: f2;??0

ANNUNCIATOR DISPLAYS

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Scenario: PALEX-93 Time: 1045 Message No: Io

scenario Time: 0215

PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Control Room Operators Simulated Plant Conditions:

Message:

The SFP has been refilled to above the SFP Cooling Pumps_suction connection (645'). See attached Alarm and Data Sheets .

FOR CONTROLLER USE ONLY Controller Notes:

High radiation levels will occur in the SFP Heat Exchanger Room and adjacent areas of the Auxiliary Building when SFP Cooling Pump P-518 is started.

Action expected:

Place SFP on recirc per SOP 27 .

Date OCTOBER 26, 1993 Message# 15 (Page 1) Time 1045 Scenario Time 0215 Time J~ - - Scenario Time J~ - -

C-08 SW Surps P-7A ON P-78 ON P*7C STBY SW Critical Hdr Press A 46. B 46. psig rnv CCW Purps P-52A ON P-52B ON P-52C FPC Purps P-51A OFF Fire Purps P-9A ON P-9B OFF P-41 OFF P*51B OFF Contairwnent Cooler Recirc Fans V1A .Qll V2A OFF V3A OFF V4A Q!! V1B .Qll V2B .Qll V3B .Qt! V4B ON CCW Cooler OUtlet T~ A 52. F B 52. F Contairment Spray Purps P*54A OFF P-54B OFF P-54C OFF HPSI Pl.lll>S P-66A OFF P*66B OFF LPSI Purps P-67A OFF P-678 Q!!

Safety Injection Suction Supply Train A Train B CV-3057 CSIRW) CLOSED CV-3029 (SIRW) CLOSED CV-3031 CSIRW) CLOSED CV-3030 CS~) CLOSED Letdown Charging Intermediate Press Letdown T~ 98. F Flow 40. gpm Letdown Line T~ 105 F Line T~ 21.:. F Letdown Flow 32. gpm Purps P-55A .Qt! P-55B OFF P-55C OFF Volume Control Tank T~ 85. F Pressure 38. psi Level 94. % PCP Control Bleedoff Pressure 150 p-~ig Shutdown Cooling Sr!tem socs from PCS (R) 120 F SOCS to PCS CR) 73. F Quench Tank T~ 102 F Pressure :.?..:. psig Level 65. X Primary Coolant System Pressurizer Pressure CR> 249. psia PCS Tave CR) Loop 1 CTR-0111) 119 Loop 2 CTR-0121) 119 Pressurizer Level CR> LRC-0101A 100 x LRC*0101B 100 x LIA-0102A 97. x Pzr Htr Aq>S LCC 15 0. LCC 16 0.

PORV PRV-1042B CLOSED PRV*1043B CLOSED Block Valve MOV-1042A OPEN MOV-1043A QeE!!.

PCPs P*50A ~ P-50B ON P*50C ON" P-500 OFF Reactor Power Level NI-01 :i8E+02 NI-02 :18E+02 NI-03 .82E*08 NI-04 .80E-08 NI-05 .12E-07 NI-06 .11E*07 NI-07 .12E-07 NI-08 .12E*07 C-01 AFW System AFW P~ P-8A OFF P-88 OFF P-8C OFF AFW P~ Afl1)S P-8A 0. P-8C 0.

AFW P~ P-8B Steam Pressure 0. psig AFW Disch Press P-8A & P-88 18. P*BC 18. psi Secondary System MSIV Bypass MOV-0501 CLOSED MOV-0510 CLOSED MSIV's CV-0501 CLOSED CV-0510 CLOSED MFP Suction Pressure ~ psig MFP Discharge Pressure A 15:'""""""" B 15. psi Moisture Separator Drain Tank Level 26. X Condenser Hotwell Level 70. %

Atmospheric D~ Valves ~ Condenser Vacuum :0- in Hg.

Heater Drain P~ Status P-10A OFF P-108 OFF Gland Seal Condenser Vacuum 14.2 in Hg.

Condensate P~ Status P-2A OFF P-2B .Qll (Demand Log + Constant, Rod, or Flux/T~)

Gross MW O. Net MW 0. Core Exit Thermocouple Temperature 120.0 F Control Rod Position GP1 0:- GP2 ~ GP3 ~ GP4 ..:,Q GP5(P) 1.:. GP6(A) ~ GP7CB) O*

Stuck Rods NONE # Q -

Date OCTOBER 26, 1993 Message # 15 <Page 2> Time 1045 Scenario Time 0215 Time JUJ1) Scenario Time Juq> - -

T-81 Level 90. X T-939 Level 93. x Condensate Storage Tank Level T-2 89. x lnstrunent ATr'Pressure " 100 psig Contairment Building Pressure -5. psig Dome Terrperature 102 F Hunidity 29. x S/G A COllJISrtment Terrperature 102 F Hunidity 30. x S/G B COllJISrtment Terrperature 93. F Hunidity 30. %

SIRW Tank Level 0. %

WR Containment Pressure CR> 9. psi a Containment SUJ1:> Level 585 % Containment Water Level (R) .2..:. x SI Tank Level (%) A 40. B 39. c 39. D 39.

SI Tank Pressure (psig) A 149 B 149 c 149 D 150 PANEL K-13 SIAS Alarm NO Containment High Pressure Alarm NO Containment High Radiation Alarm !!Q Concentrated Boric Acid Tank Levels T53A . 100. x T53B 10.6 %

Reactor Vessel DP 16.8 psid PORV Discharge Terrperature 112 F Pzr Safety Valve Discharge Tefll> (F) RV-1039 ffi RV-1040 142 RV-1041 177 PCP Current <"""5> P*50A 0. P*50B 667 P-50C 678 P-500 0.

PCS Flow 34. % Pressure Level (cold> 96.6 Loop Thot (F) Loop 1 120 Loop 2 120 Loop Tcold (F) Loop 1 119 Loop 2 120 Tcold Wide range Loop 1 120 Loop 2 119 Subcool ing Tetrp 281 F Press 247 psi PCS Prssure WR 249. NR 249. psis Steam Generator A Steam Generator B Level (WR) 90. x (NR) 90. % (WR) 87. % CNR) 87. %

Press ;:- psi a 13. psia Flow Steam .0 PPH Feed .0 PPH Steam .0 PPH Feed .:! PPH Note: Steam and Feed Flow x 1000000 C-11 AFW Flow to A S/G From P-8A&B o. From P-8C o.

AFW Flow to B S/G From P-8A&B Q." From P-8C 0.

Condenser Vacuun (R) Q."

PCP Seal Leakoff Flow P-50A 1.0 PPH P-50B !:.Q PPH P-50C !:.Q PPH P-500 !:.Q PPH C-04 Diesel Generator Frequency 1-1 60. 1-2 .0 1-C BUS Voltage 2433 ~ 494 1-D BUS Voltage 2482 A8'>S 45.

C-11 Back C-11A Containment Area Monitors (R/Hr) RIA-1805 .2E-01 RIA-1806 .2E-01 RIA-1807 -.2-- RIA-1808 .8E-01 High Range Containment Monitors CR/Hr) RIA-2321 :i'E-01 RIA-2322 .1E-01 Containment Hydrogen Concentration (%) Al-2401R -0.-- Al-2401L -o_--

Main Steam Line Ganma (cpm) RIA-2324 .3E+02 RIA-2323 .2E+02 Stack Monitors RIA-2325 ???? cpm RIA-2326 .:! cpm RIA-2327 .:,Q mr/hr

PALEX-93 TIME: /tJI/?' MESSAGE No:

SCENARIO TIME: tfZ,Z/S

ANNUNCIATOR DISPLAYS K-01

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SCENARIO TIME:

K-03 ANNUNCIATOR DISPLAYS

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PALEX-93 TIME: /(Jif ~

MESSAGE No:

SCENARIO TIME: t26/~

ANNUNCIATOR DISPLAYS K-C6A

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PALEX-93 TIME: MESSAGE No:

SCENARIO TIME:

ANNUNCIATOR DISPLAYS K-i7

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PALEX-93 TIME: /tJ(/:? MESSAGE No:

SCENARIO TIME: &e2;i£:

ANNUNCIATOR DISPLAYS K-11

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PALEX-93 TIME: @ef MESSAGE No: JS-SCENARIO TIME: a;./~

ANNUNCIATOR DISPLAYS K-21

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PALEX-93 TIME: /tJff? MESSAGE No:

SCENARIO TIME: ~

** 1 **** 2 **** 3 **** 4 **** 5 ****

ANNUNCIATOR DISPLAYS 6 **** 7 **** ~ **** 9 *** 10 ***

1 * * * * * * * * *

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Scenario: PALEX-93 Time: 1053 Message No: I~

.* Scenario Time: 0223

PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Control Room Operators Simulated Plant Cond;t;ons:

Message:

SFP Cooling Pump P-518 has been started and appears to be operating normally .

FOR CONTROLLER USE ONLY Controller Notes:

Action expected:

Expedite repairs to the alternate pump P-SIA .

Date OCTOBER 26, 1993 Message # 16 (Page 1) Time 1053 Scenario Time 0223 Time Jurp - - Scenario Time Jurp - -

c-08 SW S~ P-7A ON P-78 ON P-7C STBY SW Critical Hdr Press A 46. B 46. psi!J ccw P-52A ON P-52B ON P-52C STBY FPC P~ P-51A OFF p~

Fire P~ P-9A ON P-98 OFF P-41 OFF P-51B OFF Contairrnent Cooler Recirc Fans V1A OFF V2A Q.E.E. V3A Q.E.E. V4A Qt! V1B Q.E.E. V2B Q.E.E. V3B ON V4B ON C-03 CCW Cooler Outlet Teq> A 52. F B 52. F Contairrnent Spray P~ P-54A OFF P-54B OFF P-54C OFF HPSI P~ P-66A OFF P-66B OFF LPSI P~ P-67A OFF P-678 Q!!

Safety Injection Suction Supply Train A Train B CV-3057 CSIRW) CLOSED CV-3029 CSIRW) CLOSED CV-3031 CSIRW) CLOSED CV-3030 CSurp) ~

Letdown Chars ins Intermediate Press Letdown Teq> 98. F Flow 40. gpm Letdown Line Teq> 105 F Line Teq> ~ F Letdown Flow 32. gpm P~ P-55A Q!! P-55B OFF P-55C Q.E.E.

Vol1111e Control Tank Teq> 85. F Pressure 38. psi Level 94. x PCP Control Bleedoff Pressure 150 psis Shutdown Cool ins system SOCS from PCS CR) 120 F SOCS to PCS CR> 73. F Quench Tank

Pressurizer Pressure CR)

PCS Tave CR>

Pressurizer Level CR>

Pzr Htr Aq:>s Teq> 102 .F 249. psi a Pressure .:b psig Primary Coolant System Loop 1 CTR-0111) 119 Loop 2 CTR-0121) 119 LRC-0101A 100 x LCC 15 0:-

LRC-0101B 100 x LCC 16 0:-

Level 65.

LIA-0102A 97.

X x

PORV PRV-1042B CLOSED PRV-1043B CLOSED Block Valve MOV-1042A OPEN MOV-1043A OPEN PCPs P-50A OFF P-50B ON P-50C ON P-500 OFF Reactor Power Level NI-01 :l8E+02 Nl-02 :-f8E+02 Nl-03 .82E-08 Nl-04 .80E-08 Nl-05 .12E-07 Nl-06 .11E-07 NI-07 .12E-07 Nl-08 *12E-07 C-01 AFW System AFW Purp P-8A Q.E.E. P-8B OFF P-8C OFF AFW P~ ~ P-8A 0. P-8C o.

AFW Purp P-8B Steam Pressure o. psig AFW Disch Press P-8A & P-8B 18. P-8C 18. psi Secondary System MSIV Bypass MOV-0501 ~ MOV-0510 CLOSED MSIV's CV-0501 CLOSED CV-0510 CLOSED MFP Suction Pressure .12.:. psig MFP Discharge Pressure A~ B 15. psi Moisture Separator Drain Tank Level 26. X Condenser Hotwell Level 70. X Atmospheric Durp Valves CLOSED Condenser Vacuun :0 in Hg.

Heater Drain Purp Status P-10A OFF P-10B OFF Gland Seal Condenser Vacu1.111 14.2 in Hg.

Condensate Purp Status P-2A OFF P-2B OFF (Demand Log + Constant, Rod, or Flux/T~)

Gross MW O. Net MW 0. Core Exit Thermocouple T~rature 120.0 Control Rod Position GP1 D:' GP2 9-:_ GP3 .Q.:. GP4 .,:.Q. GP5CP) .!.:. GP6CA) .Q.:. GP7CB) 0.

Stuck Rods NONE # .Q -

Date OCTOBER 26, 1993 Message # 16 (Page 2) Time 1053 Scenario Time 0223 Time J~ Scenario Time J~ - -

£:ll T-81 Level 90. X T-939 Level 93. x Condensate Storage Tank Level T-2 89. x 100 psig lnstrunent AlrPressure :

Contairment Building Pressure -5

psig Dome T~rature 102 F Hunidity 29. x S/G A C011p8rtment T~rature 102 F Hunidity 30. x SIG B C011p8rtment T~rature 93. F Hunidity 30. x SJRll Tank Level 0.

llR Contairment Pressure CR)

Contairment S~ Level 585 "x

9. psi a Contairment !later Level CR) .Q.:. x SI Tank Level CX> A 40. B 39. c 39. D 39.

SI Tank Pressure Cpsig) A 149 B 149 c 149 D 150 PANEL K-13 SIAS Alarm .!l.Q Contairment High Pressure Alarm .!l.Q Containment High Radiation Alarm NO Concentrated Boric Acid Tank Levels T53A 100. x T53B 10.6 x Reactor Vessel DP 16.8 psid PORV Discharge T~rature m F Pzr Safety Valve Discharge T~ CF> RV-1039 127 RV-1040 142 RV-1041 177 PCP Current (Amps) P-50A o. P*50B 667 P-50C 678 P-500 O.

PCS Flow 34. x Pressure Level (cold) 96.6 "

Loop Thot CF> Loop 1 120 Loop 2 120 Loop Tcold (F) Loop 1 119 Loop 2 120 Tcold llide range Loop 1 120 Loop 2 119 Subcool ing T~ 281 F Press 247 psi PCS Prssure llR 249. NR 249. psi a Steam Generator A Steam Generator B Level (llR) 90. x (NR) 2Q.:. x 87. x (NR) 87.

"PPH (llR)

Press 1:- psi a 13. psis Flow Steam .o PPH Feed .0 PPH Steam .0 PPH Feed ,:.Q Note: Steam and Feed Flow x 1000000 C-11 AFll Flow to A S/G From P*8A&B o. From P*8C o.

AFll Flow to B S/G From P-8A&B Q.' From P-8C o.

Condenser Vacuun CR) Q.'

PCP Seal Leakoff Flow P-50A 1.0 PPH P-50B !:.Q PPH P-50C !:.Q PPH P-50D !:.Q PPH C-04 Diesel Generator Frequency 1-1 60. 1-2 .0 1-C BUS Voltage 2433 Amps 494 1-D BUS Voltage 2482 Amps 45.

C-11 Back C-11A Contairment Area Monitors CR/Hr) RJA-1805 .2E-01 RIA-1806 .2E-01 RIA-1807 -.2-- RIA-1808 .SE-01 High Range Contairment Monitors CR/Hr) RIA-2321 :-:iE-01 RIA-2322 :l'E-01 Contairment Hydrogen Concentration CX> AI-2401R -0.-- AI-2401L -0.--

Main Steam Line Ganma Ccpm) RIA-2324 .3E+02 RIA-2323 .2E+02 Stack Monitors RIA-2325 ???? cpm RIA-2326 ,:.Q cpm RIA-2327 ,:.Q mr/hr

PALEX-93 TIME: Ja£:! MESSAGE No:

SCENARIO TIME:' azg3

ANNUNCIATOR DISPLAYS K-01

- 1 **** 2 **** 3 **** 4 **** ~ **** 6 **** 7 **** g **** 9 *** 10 *** 11 *** 12 ***

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PALEX-93 TIME: /053' MESSAGE No:

SCENARIO TIME: @:23

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PALEX-93 TIME: MESSAGE No:

SCENARIO TIME:

ANNUNCIATOR DISPLAYS K-G6A 1 **** ' **** 3 **** 4 ***

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PALEX-93 TIME: ~.53 MESSAGE No:

SCENARIO TIME: ?7:;,z.z.3

ANNUNCIATOR DISPLAYS

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PALEX-93 TIME: /tJS.3 MESSAGE No: ~

SCENARIO TIME: 6!>>3

ANNUNCIATOR DISPLAYS 1(-11

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PALEX-93 TIME: /!)5'0 MESSAGE No: /6 SCENARIO TIME: ?J~...3

ANNUNCIATOR DISPLAYS K-21

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PALEX-93 TIME: /t)S.3 MESSAGE No:

SCENARIO TIME: !¥2 ;(,3

ANNUNCIATOR DISPIAYS

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Scenario: PALEX-93 Time: 1100 Message No: 11

scenario Time: 0230

PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Control Room Operators Simulated Plant Conditions:

Message:

See attached Alarm and Data Sheets .

FOR CONTROLLER USE ONLY Controller Notes:

Action expected:

Continue efforts to capture the damaged SFHM equipment and increase SFP boron concentration .

Date OCTOBER 26. 1993 Message # 17 (Page 1) Time 1100 Scenario Time 0230 Time J.....,-- Scenario Time J....., --

c-08 SW S~ P-7A ON P-78 ON P-7C. ST8Y SW Critical Hdr Press A 46. 8 46. psig ccw p~ P-52A ON P-528 ON P-52C SrBv FPC P~ P-51A O'F'f Fire P~ P-9A ON P-98 OFF P-41 OFF P-518 ON Containment Cooler Recirc Fans V1A OFF V2A OFF V3A Qff V4A Qt! V18 OFF V28 Qff V3B Qt! V4B ON CCW Cooler OUtlet T~ A 52. F 8 52. F Containnent Spray P~ P-54A O'F'f P-548 O'F'f P-54C OFF HPSI P~ P-66A OFF P-668 OFF LPSI P~ P-67A OFF P-678 ON Safety Injection Suction Supply Train A Train B CV-3057 (SIRW) ~ CV-3029 (SIRW) ~ CV-3031 (SIRW) ~ CV-3030 cs.....,) ~

Letdown Chars ins Intermediate Press Letdown Tefl1) 98. F Flow ~ gpm Letdown Line Tefl1) 105 F Line T~ 2.L, F Letdown Flow 32. gpm P~ P-55A Qt! P-55B Qff P-55C OFF Volume Control Tank T~ 85. F Pressure 38. psi Level 94. x PCP Control Bleedoff Pressure 150 psig Shutdown Cool ins system SOCS from PCS (R) lli F SOCS to PCS CR) 73. F Quench Tank

Pressurizer Pressure (R)

PCS Tave CR)

Pressurizer Level CR>

Pzr Htr Aq>s T~ .1,!g F

~ psia Pressure .:k. psig Primary Coolant System Loop 1 CTR-0111) ~ Loop 2 (TR-0121) 119 LRC-0101A 100 x LCC 15 0:-

LRC-0101B 100 x LCC 16 0:-

Level 65.

LJA-0102A &.

X x

PORV PRV-1042B CLOSED PRV-1043B CLOSED Block Valve MOV-1042A Qru MOV-1043A Qffil!

PCPs P-50A ~ P-50B ON P-50C ON P-500 OFF Reactor Power Level NI-01 :18E+02 NI-02 :18E+02 NI-03 .82E-08 NI-04 .80E-08 NI-05 .:.l1E:Ql NI-06 .11E-07 NI-07 *12E-07 NI-08 .12E-07 C-01 AFW System AFW P....., P-8A OFF P-8B OFF P-8C OFF AFW P....., Amps P-8A 0. P-8C 0.

AFW P....., P-8B Steam Pressure O. psig AFW Disch Press P-SA & P-8B 18. P-8C 18. psi Secondary System MSIV Bypass MOV-0501 ~ MOV-0510 CLOSED MSIV's CV-0501 CLOSED CV-0510 CLOSED MFP Suction Pressure 12.:. psig MFP Discharge Pressure A~ B 15. psi Moisture Separator Drain Tank Level 26. X Condenser Hotwell Level 70. X Atmospheric o....., Valves ~

Heater Drain P~ *status - - *p-*10A* OFF

P-10B-OFF Co~ns.er_ Vac.L!U!_ __ -* _ . _ _ _.o . __ . in Hg *. _

Grand Seal Condenser Vacuum 14.2 in Hg.

Condensate P....., Status P-2A Qff P-2B Q.Ef (Demand Log + Constant, Rod, or Flux/T~)

Gross MW 0. Net MW 0. Core Exit Thermocouple T~rature 120.0 F Control Rod Position GP1 ii:" GP2 Q:, GP3 Q:, GP4 ..:,Q GP5(P) 1..:. GP6(A) .Q.:, GP7CB) 0.

Stuck Rods NONE # Q -

Date OCTOBER 26. 1993 Message # 17 (Page 2) Time 1100 Scenario Time 0230 Time J~ - - Scenario Time J~ - -

&:.Y T-81 Level 90. X T-939 Level 93. x Condensate Storage Tank Level T-2 89. x lnstrinent AirPressure .

100 psig Containnent Building Pressure -5. psig Dome T~rature 102 F Hunidity 29. x S/G A C~rtment T~rature 102 F Hunidity 30. x S/G B C~rtment T~rature 93. F Hunidity 30. x SIRW Tank Level o. x WR Containnent Pressure CR> 9. psi a Containment S~ Level 585 x Containnent Water Level CR> Q.:. x SI Tank Level (%) A 40. B 39. c 39. D 39.

SI Tank Pressure Cpsig) A 149 B 149 c 149 D 150 PANEL K-13 SIAS Alarm !!Q Contairrnent High Pressure Alarm NO Containnent High Radiation Alarm NO

~

Concentrated Boric Acid Tank Levels T53A 100. x T53B 10.6 x Reactor Vessel DP 16.8 psid PORV Discharge T~rature Pzr Safety Valve Discharge Teq:> CF) RV-1039 127 m F RV-1040 142 RV-1041 177 PCP Current (Amps) P-50A o. P-50B 667 P-50C 678 P-50D 0.

PCS Flow 34. x Pressure Level (cold) 96.6 x Loop Thot (f) Loop 1 120 Loop 2 120 Loop Tcold (F) Loop 1 m Loop 2 120 Tcold Wide range Loop 1 120 Loop 2 TI9 Subcool ing Teq:> 281 F Press 247 psi PCS Prssure WR 249. NR 249. psia Steam Generator A Steam Generator B Level (WR) 90. x CNR) 90. x (WR) 87. x CNR) 87. x Press 1:"- psia 13. psia Flow Steam .o PPH Feed .0 PPH Steam .0 PPH Feed .:,Q PPH Note: Steam and Feed Flow x 1000000 C-11 AFW Flow to A S/G From P-BA&B o. From P-8C o.

AFW Flow to B S/G From P-8A&B 0. From P-8C 0.

Condenser Vacuun CR) 0.

PCP Seal Lealcoff Flow P-50A 1.0 PPH P-50B 1.:.Q PPH P-50C 1.:.Q PPH P-500 1.:.Q PPH C-04 Diesel Generator Frequency 1*1 60. 1-2 .0 1-C BUS Voltage 2433 Amps 494 1-D BUS Voltage 2482 Amps 45.

C-11 Back C-11A Containnent Area Monitors CR/Hr) RIA-1805 .2E*01 RIA-1806 .2E-01 RIA-1807 -.2-- RIA-1808 .8E-01 High Range Containnent Monitors CR/Hr) RIA*2321 :i'E-01 RIA-2322 .1E-01 Containnent Hydrogen Concentration CX> Al-2401R -o_-- Al-2401 L -0.--

Main Steam Line Ganma (cpm) RIA-2324 .3E+02 RIA*2323 .2E+02 Stacie Monitors RIA-2325 1111. cpm RIA-2326 .:,Q cpm RIA-2327 .:,Q mr/hr

PALEX-93 TIME: l,/()O MESSAGE No:

SCENARIO TIME: r 42,30

ANNUNCIATOR DISPLAYS K-01

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PALEX-93 TIME: /)CJO MESSAGE No:

SCENARIO TIME: 6'230 ANNUNCIATOR DISPLAYS

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PALEX-93 TIME: MESSAGE No:

SCENARIO TIME:

ANNUNCIATOR DISPLAYS K-G6A

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PALEX-93 TIME: MESSAGE No:

SCENARIO TIME:

ANNUNCIATOR DISPLAYS

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PALEX-93 TIME: MESSAGE No:

SCENARIO TIME:

ANNUNCIATOR DISPLAYS

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PALEX-93 TIME: J/PJ 0

MESSAGE No: _L2_

SC~IO TIME: tf),;¢30

ANNUNCIATOR DISPLAYS K-21 1 **** 2 **** 3 **** 4 **** 5 ***

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PALEX-93 TIME: )/~() MESSAGE No:

SCENARIO TIME: r t),230

ANNUNCIATOR DISPLAYS

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Scenario: PALEX-93 Time: 1115 Message No: !/'

.* Scenario Time: 0245

PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Control Room Operators Simulated Plant Conditions:

Message:

See attached Alarm and Data Sheets .

FOR CONTROLLER USE ONLY Controller Notes:

Action expected:

Date OCTOBER 26, 1993 Message # 18 (Page 1) Time 1115 Scenario Time 0245 Time J~ - - Scenario Time J~ -

c-08 SW S~ P-7A ON P-7B ON P-7C ST8Y SW Criti-cal Hdr Press A 46. 8 46. .,**14. ~

P-52A ON P-528 ON P-52C STeY P-51A OFF ccw p~ FPC P~

Fire P~ P-9A ON P-98 OFF P-41 OFF P-518 ON Containnent Cooler Recirc Fans V1A .QE.E. V2A OFF V3A .QE.E. V4A Q!! V18 OFF V2B OFF V3B Q!! V4B ON C-03 ccw Cooler Outlet T~ A 52. F 8 52. F Containnent Spray P~ P-54A OFF P-548 OFF P-54C OFF HPSI P~ P-66A OFF P-668 OFF LPSI P~ P-67A OFF P-678 Q!!

Safety Injection Suction Supply Train A Train B CV-3057 (SIRW) ~ CV-3029 (SIRW) CLOSED CV-3031 CSIRW) CLOSED CV-3030 (S~) CLOSED Letdown Chars ins Intermediate Press Letdown T~ 98. F Flow 40. gprn Letdown Line T~ 105 F Line T~ ~ F Letdown Flow 32. gprn P~ P-55A Q!! P-55B OFF P-55C OFF Volune Control Tank

85. F Pressure 38. psi Level 94. PCP Control Bleedoff Pressure 150 . psig T~

Shutdown Cool ins system SOCS from PCS (R) 120 F SOCS to PCS (R) 73. F Quench Tank

Pressurizer Pressure CR)

PCS Tave (R)

Pressurizer Level CR)

T~ 102 F 249. psi a Pressure .:1.:. psig Primary Coolant System Loop 1 CTR-0111) 119 Loop 2 CTR-0121) 119 LRC-0101A 100 " LRC-0101B 100 Level 65.

LIA-0102A 97.

X Pzr Htr ~

PORV LCC 15 0.

PRV-1042B CLOSED LCC 16 0. "

PRV-1043B CLOSED Block Valve MOV-1042A OPEN

" MOV-1043A OPEN PCPs P-50A ~ P-50B. ON P-50C ON P-50D OFF Reactor Power Level Nl-01 T8E+02 Nl-02 :i'8E+02 NI-03 "Ji2E-08 Nl-04 .80E-08 NI-05

12E-07 Nl-06 .11E-07 NI-07 .12E-07 NI-08 .12E-07 C-01 AFW System AFW P~ P-8A .QE.E. P-8B OFF P-8C OFF AFW P~~ P-8A 0. P-8C 0.

AFW P~ P-8B Steam Pressure 0. psig AFW Disch Press P-BA & P-8B 18. P-8C 18. psi Secondary System MSIV Bypass MOV-0501 ~ MOV-0510 CLOSED MSIV's CV-0501 CLOSED CV-0510 CLOSED MFP Suction Pressure 12.:. psig MFP Discharge Pressure A TS:""""""' B 15. psi Moisture Separator Drain Tank Level 26. X Condenser Hotwell Level 70. X Atmospher-ic D~-Valves ________ CLOSED _______ _ _ __ Condenser_ Vacul.111 _ _ __ __ __ _ __ _'])__ in_Hg. __ --- _ ___ _ __

Heater Drain P~ Status P-10A .QE.E. P-10B OFF Gland Seal Condenser Vacul.111 14.2 in Hg.

Condensate P~ Status P-2A OFF P-2B lli (Demand Log + Constant, Rod, or Flux/T~)

Gross MW 0. Net MW 0. Core Exit Thermocouple Temperature 120.0 F Control Rod Pos'iti on GP1 0. GP2 ~ GP3 ~ GP4 ..:,Q GP5(P) 1.:. GP6(A) ~ GP7(B) 0.

Stuck Rods NONE # Q -

l_ __

Date OCTOBER 26, 1993 Message # 18 (Page 2) Time 1115 Scenario Time 0245 Time J~ - - Scenario Time J~ - -

£:ll T-81 Level 90. X T-939 Level 93. Condensate Storage Tank Level T-2 89.

lnstrunent AirPressure . * "

100 psig "

Containment Building Pressure -5

psig Dome Teq>erature 102 F Hunidity 29.

S/G A Coq:>artment S/G B Coq:>artment T~rature 102 F

93. F Hunidity 30.

Hunidity 30.

"x SIRW Tank Level WR Containment Pressure (R)

0. %

9.' psia T~rature Containment S~ Level 585 Containment Water Level CR) Q..

SI Tank Level CX> A 40.

" B 39. c 39. D 39.

SI Tank Pressure Cpsig) A 149 B 149 c 149 D 150 PANEL K-13 SIAS Alarm NO Containment High Pressure Alarm ~ Containment High Radiation Alarm NO Concentrated Boric Acid Tank Levels T53A . 100. " T53B 10.6 x Reactor Vessel DP 16.8 psid PORV Discharge Teq:>erature 112 F Pzr Safety Valve Discharge T~ CF> RV-1039 127 RV-1040 142 RV-1041 1IT PCP Current (Alrps) P-50A o. P-50B 667 P-50C 678 P-500 O.

PCS Flow 34. x Pressure Level (cold) 96.6 Loop Thot (F) Loop 1 120 Loop 2 120 Loop Tcold CF) Loop 1 119 Loop 2 120 Tcold Wide range Loop 1 120 Loop 2 119 Subcooling T~ 281 F Press 247 psi PCS Prssure WR 249. NR 249. psis Steam Generator A Steam Generator B Level (WR) 90. CNR) 90. x CW) 87. x CNR) 87. x Press Flow Steam

~ psia

.0 PPH

" Feed .O PPH Steam

13. psia

.0 PPH Feed ...Q PPH Note: Steam and Feed Flow x 1000000

£.:..11 AFW Flow to A S/G From P-8A&B 0. From P-8c 0.

AFW Flow to B S/G From P-8A&B Q." From P-8c 0.

Condenser Vacuun CR> Q."

PCP Seal Leakoff Flow P-50A 1.0 PPH P-50B !.:Q PPH P-50C 1...Q PPH P-50D 1...Q PPH C-04 Diesel Generator Frequency 1-1 60. 1-2 .0 1-C BUS Voltage 2433 Amps 494 1-D BUS Voltage 2482 Amps 45.

C-11 Back C-11A Containment Area Monitors CR/Hr) RIA-1805 .2E-01 RIA-1806 .2E-01 RIA-1807 -.2-- RIA-1808 .8E-01 High Range Containment Monitors CR/Hr) RIA-2321 :i'E-01 RIA-2322 .1E-01 Containment Hydrogen Concentration CX) AI-2401R -0.-- AI-2401L -0.--

Main Steam Line Ganlll8 (cpm) RIA-2324 .3E+02 RIA-2323 .2E+02 Stack Monitors RIA-2325 ???? cpm RIA-2326 ...Q cpm RIA-2327 ...Q mr/hr

PALEX-93 TIME: Jll,5' MESSAGE No:

SCENARIO TIME: &.2V?"

I ANNUNCIATOR DISPLAYS K-01

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PALEX-93 TIME: ///_5" ,,./ MESSAGE No:

SCENARIO TIME: <?.2f?

K-03 ANNUNCIATOR DISPLAYS 1 ON

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PALEX-93 TIME: MESSAGE No:

SCENARIO TIME:

ANNUNCIATOR DISPLAYS K-Ci6A

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PALEX-93 MESSAGE No:

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PALEX-93 TIME: MESSAGE No:

SCENARIO TIME:

ANNUNCIATOR DISPLAYS K-11

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PALEX-93 SCE~IO TIME:

TIME:

1!!£?L_,-_ z:...~

MESSAGE No: J£..

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PALEX-93 SCENARIO TIME:

TIME: ///£//--

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MESSAGE No:

ANNUNCIATOR DISPLAYS

- . 1 ****

2 **** 3 **** 4 **** 5 **** 6 **** 7 ****

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Scenario No: PALEX-93 Time: 1130 Message No: D Scenario Time: 0300 PAUSADES NUCLEAR. PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Control Room Operators Simulated Plant Conditions:

Message:

See attached Alarm and Data Sheets*

FOR CONTROLLER USE ONLY Controller Notes:

Action Expected:

Date OCTOBER 26. 1993 Message # 19 (Page 1> Time 1130 Scenario Time 0300 Time J~ - - Scenario Time J~ - -

C-08 SW S~ P-7A ON P-78 ON P-7C STBY SIJ Critical Hdr Press A 46. B 46. psig ccw P-52A ON P-52B ON P-52C STBY FPC P~ P-51A OFF p~

Fire P~ P-9A ON P-98 OFF P-41 OFF P-51B ON Contairment Cooler Recirc Fans V1A Q.Ef. V2A Q.Ef. V3A OFF V4A ON V1B OFF V2B Q.Ef. V3B ON V4B Q!!

c-03 CCII Cooler Outlet T~ A 52. F B 52. F containment Spray P~ P-54A OFF P-54B OFF P-54C OFF HPSI P~ P-66A OFF P-66B OFF LPSI P~ P-67A Q.Ef. P-678 Q!!

Safety Injection Suction Supply Train A Train B CV-3057 CSIRIJ) ~ CV-3029 (SIRIJ) CLOSED CV-3031 (SIRIJ) CLOSED CV-3030 (S1.f11:>) CLOSED Letdown Char9ins Intermediate Press Letdown T~ 98. F Flow 40. gpm Letdown Line T~ 105 F Line T~ ~ F Letdown Flow 32. gpm P~ P-55A ON P-558 OFF P-55C OFF Volume Control Tank T~ 85. F Pressure 38. psi Level 94. x PCP Control 8leedoff Pressure 150 psig Shutdown Cool ins System SOCS from PCS CR) 120 F SOCS to PCS CR) 73. F Quench Tank

Pressurizer Pressure CR>

PCS Tave CR)

Pressurizer Level CR)

Pzr Htr Amps T~ 102 F 249. psi a Pressure :l.:. psig Primary Coolant System Loop 1 CTR-0111) 119 Loop 2 CTR-0121) 119 LRC-0101A 100 x LCC 15 0.-

LRC-01018 100 x LCC 16 0:-

Level 65.

LIA-0102A 97.

X x

PORV PRV-10428 CLOSED PRV-1043B CLOSED Block Valve MOV-1042A OPEN MOV-1043A OPEN PCPs P-50A ~ P-50B ON P-50C ~ P-500 O'fF Reactor Power Level Nl-01 TBE+02 Nl-02 :1"8E+02 Nl-03 :82E-08 Nl-04 .80E-08 Nl-05 .12E-07 Nl-06 .11E-07 Nl-07 .12E-07 Nl-08 .12E-07 C-01 AFIJ System AFIJ P~ P-8A OFF P-8B OFF P-8C OFF AFW P~ Amps P-BA O. P-8C 0.

AFIJ P~ P-88 Steam Pressure 0. psig AFW Disch Press P-8A & P-88 18. P-8C 18. psi Secondary System MSIV Bypass MOV-0501 CLOSED MOV-0510 CLOSED MSIV's CV-0501 CLOSED CV-0510 CLOSED MFP Suction Pressure .12.:. psig MFP Discharge Pressure A~ B 15. psi Moisture Separator Drain Tank Level 26. X Condenser Hotwell Level 70: X Atmospheric D~ Valves CLOSED Condenser Vacuum :0 in Hg.

Heater Drain P~ Status P-10A OFF P-108 Qf£ Gland Seal Condenser Vacuum 14.2 in Hg.

Condensate P~ Status P-2A OFF P-28 Qf£ (Demand Log + Constant, Rod, or Flux/Temp)

Gross MIJ 0. Net MIJ 0. Core Exit Thermocouple T~rature 120.0 F Control Rod Position GP1 0:- GP2 Q.:. GP3 Q.:. GP4 ..:.Q GP5(P) !.:. GP6(A) Q.:. GP7(8) O.

Stuck Rods ~ # Q -

Date OCTOBER 26. 1993 Message # 19 (Page 2> Time 1130 Scenario Time 0300 Time J~ - - Scenario Time J~ - -

£.:Y T-81 Level 90. X T-939 Level 93. x Condensate Storage Tank Level T-2 89. x lnstrunent ATr"'Pressure . 100 psig Containment Building Pressure -5

psig Dome T~rature 102 F HLnidity 29. x S/G A C~rtment T~rature 102 F HLnidity 30. x S/G B C~rtment T~rature 93. F HLnidity 30. x SIRW Tank Level 0. %

WR Containment Pressure (R) 9. psi a Containment S~ Level 585 x Containment Water Level CR> .!!..:. x SI Tank Level (X) A 40. B 39. c 39. D 39.

SI Tank Pressure Cpsig) A 149 B 149 c 149 D 150 PANEL K-13 SIAS Alarm NO Containment High Pressure Alarm !!Q Containment High Radiation Alarm .NO Concentrated Boric Acid Tank Levels T53A

100. x T53B 10.6 %

Reactor Vessel DP 16.8 psid PORV Discharge T~rature w F Pzr Safety Valve Discharge T~ CF) RV-1039 127 RV-1040 142 RV-1041 177 PCP Current (Amps) P*50A 0. P-50B 667 P-SOC 678 P-SOD 0.

PCS Flow 34. x Pressure Level (cold) 96.6 %

Loop Thot CF> Loop 1 120 Loop 2 120 Loop Tcold (f) Loop 1 ill Loop 2 120 Tcold Wide range Loop 1 120 Loop 2 119 Subcooling T~ 281 F Press 247 psi PCS Prssure WR 249. NR 249. psi a Steam Generator A Steam Generator B Level CWR) 90. x CNR) 90. x (WR) 87. x CNR) 87. %

Press ;:- psi a 13. psia Flow Steam .0 PPH Feed .0 PPH Steam .0 PPH Feed ...Q PPH Note: Steam and Feed Flow x 1000000 C-11 AFW Flow to A S/G From P-8A&B o. From P-8C 0.

AFW Flow to B S/G From P-SA&B 0: From P-8C O.*

Condenser VacuLn CR> 0:

PCP Seal Leakoff Flow P-50A 1.0 PPH P-508 .!:.Q PPH P-50C .!:.Q PPH P-500 .!:.Q PPH c-04 Diesel Generator Frequency 1-1 60. 1-2 .0 1-C BUS Voltage 2433 An.,s 494 1-D BUS Voltage 2482 Amps 45.

C-11 Back C-11A Containment Area Monitors CR/Hr) RIA-1805 .2E-01 RIA-1806 .2E-01 RIA*1807 -.2-- RIA-1808 .8E-01 High Range Containment Monitors CR/Hr) RIA*2321 :i'E-01 RIA*2322 .1E-01 Containment Hydrogen Concentration (%) Al *2401R -0.-- AI-2401L -o_--

Main Steam Line Ganma (cpm) RIA*2324 .3E+02 RIA*2323 .2E+02 Stack Monitors RIA-2325 1111 cpm RIA-2326 ...Q cpm RIA-2327 ...Q mr/hr

PALEX-93 TIME: MESSAGE No:

SCENARIO TIME:

ANNUNCIATOR DISPLAYS K-01

- 1 **** 2 **** 3 **** 4 **** **** 6 **** 7 **** e **** 9 *** 10 *** 11 *** 12 ***

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Scenario No: PALEX-93 Time: 1200 Message No: 2o Scenario Time: 0315 PAUSADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Control Room Operators Simulated Plant Conditions:

Message:

See attached Alarm and Data Sheets*

FOR CONTROLLER USE ONLY Controller Notes:

Date OCTOBER 26, 1993 Message # 20 (Page 1) Time 1145 Scenario Time 0315 Time J~ - - Scenario Time J~ - -

c-08 SW S~ P-7A ON P-78 ON P-7C STBY SW Critii:al Hdr Press A 46. B~ psig ccw p~ P-52A ON P-52B ON P-52C STeY FPC P~ P-51A OFF Fire P~ P-9A ON P-98 OFF P-41 OFF P-51B ON Containnent Cooler Recirc Fans V1A QEf V2A QEf V3A QEf V4A ON V1B QEf V2B QEf V3B Q!! V4B Q!!

CCW Cooler Outlet Teq> A 52. F B 52. F Containnent Spray P~ P-54A OFF P-54B OFF P-54C OFF HPSI P~ P-66A OFF P-668 OFF LPSI P~ P-67A OFF P-678 ON Safety Injection Suction Supply Train A Train B CV-3057 (SIRW) CLOSED CV-3029 (SIRW) CLOSED CV-3031 (SIRW) CLOSED CV-3030 (S~) CLOSED Letdown Chars ins Intermediate Press Letdown Teq> 98. F Flow 40. gpm Letdown Line Teq> 105 F Line Teq> 91. F Letdown Flow 32. gpm P~ P-SSA ON P-SSB OFF P-SSC OFF Volune Control Tank Teq> 85*. F Pressure 38. psi Level 94. x PCP Control Bleedoff Pressure 150 psig Shutdown Coolins system SOCS fran PCS CR) 120 F SOCS to PCS CR) ~ F Quench Tank

Pressurizer Pressure CR)

PCS Tave CR)

Teq> 102. F 249. psi a Pressure ~ psig Primary Coolant System Loop 1 CTR-0111) 119 Loop 2 (TR-0121) 119 Pressurizer Level CR>

Pzr Htr An.,s LRC-0101A 100 x LCC 15 0.-

LRC-0101B TOO x LCC 16 0.-

Level 65. X LIA-0102A 97. x PORV PRV-1042B CLOSED PRV-1043B CLOSED Block Valve MOV-1042A OPEN MOV-1043A QfE!!

PCPs P-SOA OFF P-SOB ON P-SOC ON P-SOD OFF Reactor Power Level Nl-01 :1iiE+02 Nl-02 :18E+02 Nl-03 .82E-08 Nl-04 .80E-08 NI-OS .12E*07 Nl-06 .11E*07 Nl-07 .12E-07 Nl-08 .12E-07 C-01 AFW System AFW P~ P-SA OFF P-8B OFF P-8C OFF AFW P~ An.,s P-8A 0. P-8C 0.

AFW P~ P-8B Steam Pressure o. psig AFW Disch Press P-SA & P-8B 18. P-8C 18. psi Secondary System MSJV Bypass MOV-0501 CLOSED MOV-0510 CLOSED MSIV's CV-0501 CLOSED CV-0510 CLOSED MFP Suction Pressure .1i:. psig MFP Discharge Pressure A ;s:-- B 15. psi Moisture Separator Drain Tank Level 26. X Condenser Hotwell Level =;Q." X

_Atmospheri.c_D~ Valves .. -~- .. .. Condenser ..Vacuum -* :0- in-Hg *.

Heater Drain P~ Status P-10A Qf.E. P-10B QE.E. Gland*Seal Condenser Vacuum 14.2 in Hg.

Condensate P~ Status P*2A OFF P-2B QE.E.

(Demand Log + Constant, Rod, or Flux/Teq>)

Gross MW 0. Net MW O. Core Exit Thermocouple Teq>erature 120.0 F Control Rod Position GP1 Cl. GP2 Q=. GP3 Q=. GP4 ~ GPS(P) !:. GP6(A) Q=. GP7(B) 0.

Stuck Rods NONE # Q -

Date OCTOBER 26, 1993 Message # 20 (Page 2) Time 1145 Scenario Time 0315 Time J~ - - Scenario Time J~ - -

£.:Y Condensate* Storage Tank Level T-2 89.

T-81 Level .2Q.,:, " T-939 Level lnstrunent Air Pressure .

93.

100 psig "

-5. psig Dome T~rature 102 F Hunidity 29.

Contairrnent Building Pressure SIG A Compartment Tenperature Tenperature 102 F

93. F Hunidity 30.

Hunidity 30.

SIG B Compartment SIRW Tank Level WR Containment Pressure CR>

o.

9. psi a Contairment Water Level CR>

Containment S~ Level SI Tank Level <">

585 A 40.

" B 39. c 39.

.Q.:.

D 39.

SI Tank Pressure (psig) A 149 B 149 c 149 D 150 PANEL K-13 SIAS Alann .!!Q Contairment High Pressure Alann .!!Q Containment High Radiation Alarm NO Concentrated Boric Acid Tank Levels T53A 100. " T53B 10.6 x Reactor Vessel DP 16.8 psid PORV Discharge T~rature 112 F Pzr Safety Valve Discharge T~ CF> RV-1039 127 RV-1040 142 RV-1041 1n PCP Current (~) P-50A 0. P-50B W P-50C 678 P-500 O.

PCS Flow 34. " Pressure Level (cold) 96.6 Loop Thot (F) Loop 1 120 Loop 2 120 Loop Tcold (F) Loop 1 119 Loop 2 120 Tcold Wide range Loop 1 120 Loop 2 119 Subeool ing Tetll> 281 F Press 247 psi PCS Prssure WR 249. NR 249. psia Steam Generator A Steam Generator B Level CWR) CNR) 90. CWR) (NR) §I:.

Press Flow Steam 90.

- psis

.0 PPH Feed .O PPH

" Steam

87. "

13. psia

.0 PPH Feed .J!

"PPH Note: Ste11111 and Feed Flow x 1000000

c-11 AFW Flow to A S/G AFW Flow to B S/G Condenser Vacuun (R)

PCP Seal Leakoff Flow From P-8A&B From P-8A&B P-50A o.

a:-

o.

.bQ PPH From P-8C o.

From P-8C 0.

P-50B .bQ PPH P*50C 1.:Q PPH P-500 .bQ PPH

£.:!!!

Diesel Generator Frequency 1-1 60. 1-2 .0 1-C BUS Voltage 2433 Amps 494 1-D BUS Voltage 2482 Amps 45.

C-11 Back C-11A Contairment Area Monitors CR/Hr) RIA-1805 .2E-01 RIA-1806 .2E-01 RIA*1807 -.2-- RIA-1808 .8E-01 High Range Contairment Monitors CR/Hr) RIA-2321 :lE-01 RIA*2322 :1E-Oi' Contairment Hydrogen Concentration CX> AI-2401R -0.-- Al-2401L -0.--

Main Steam Line Gal!lllB Ccpm) RIA*2324 .3E+02 RIA-2323 .2E+02 Stack Monitors RIA-2325 ???? cpm RIA-2326 .& cpm RIA-2327 .:,Q mr/hr

PALEX-93 TIME: MESSAGE No:

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Office of Administration Items of Interest Week Ending November 26, 1993 Significant FOIA Requests Received by the NRC For 4-Day Period of November 19

- November 24. 1993 Request for copies of the transcript, meeting minutes and written comments obtained from the Advisory Committee on Medical Use of Isotopes meeting held November 1-2, 1993. (Hal Siegel, Hybritech Incorporated, FOIA-93-612)

Request for records regarding the final Table S-3 and the Draft Environmental Statements and Regulatory Guides. (Michaela Noble, FOIA-93-613)

NOVEMBER 26, 1993 ENCLOSURE F

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Office of Personnel Items of Interest Week Ending November 26, 1993 Courses Offered for SES and Supervisory Development Program Participants From November 15-19, 1993, participants in the SES Candidate Development Program and the NRC Supervisory Development Program attended two special courses: a two-day EEO for Managers and Supervisors course and a three-day Personnel Management Practices course, which included a half-day workshop on the President's National Performance Review.

Arrivals KHANNA, Meena MATERIALS ENGINEER (PFT) NRR Departures MILLER, Isabelle REACTOR SYSTEMS ENGINEER (PFT) NRR MONREAL, Lynn OFFICE AUTOMATION ASSISTANT (OPFT) RIV ROVACK, Michael REACTOR INSPECTOR (PFT) RV

NOVEMBER 26, 1993 ENCLOSURE I

PALEX-93 TIME: //~ MESSAGE No:

SCENARIO TIME: ~~

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Scenario No: PALEX-93 Time: 12~

Message No: 21 Scenario Time: 0330 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Control Room Operators Simulated Plant Conditions:

Message:

See attached Alarm and Data Sheets.

FOR CONTROLLER USE ONLY Controller Notes:

Action Expected:

Date OCTOBER 26, 1993 Message # 21 (Page 1) Time 1200 Scenario Time 0330 Time J~ - - Scenario Time J~ - -

£:ill!

SW S~ P-7A ON P-78 ON P-7C STBY SW Critical Hdr Press A 46. B 46. psig P-52C M P-51A OFF CCW P~s P-52A ON P-52B ON FPC P~

Fire P~ P-9A ON P-98 OFF P-41 OFF P-518 ON Contairment Cooler Recirc Fans V1A .Q.Ef V2A OFF V3A OFF V4A ON V1B Q.E.E. V2B Q.E.E. V3B ON V4B Q!!.

CCW Cooler Outlet T~ A 52. F B 52. F Contairment Spray P~ P-54A OFF P-548 OFF P-54C OFF HPSI P~ P-66A OFF P*668 OFF LPSI P~ P-67A .Q.Ef P-678 Q!!

Safety Injection Suction Supply Train A Train B CV-3057 (SIRW) CLOSED CV-3029 (SIRW) CLOSED CV*3031 (SIRW) CLOSED CV-3030 (S~) CLOSED Charging Flow 40. gpm Line T~ ~ F P~ P-55A ON P-55B OFF P-55C OFF PCP Control Bleedoff Pressure 150 psig SOCS to PCS (R) 73. F Level 65. X Pressurizer Pressure (R) 249. psi a PCS Tave CR) Loop 1 CTR-0111) 119 Loop 2 (TR*0121) 119 Pressurizer Level (R) LRC-0101A 100 x LRC-01018 100 x LIA-0102A 97. %

Pzr Htr Arrps LCC 15 0:- LCC 16 0:-

PORV PRV-1042B CLOSED PRV-1043B CLOSED Block Valve MOV-1042A Qffili MOV-1043A OPEN PCPs P-50A ~ P-508 ON P-50C ON P-500 OFF Reactor Power Level Nl-01 TBE+02 Nl-02 :18E+02 NJ-03 .82E-08 Nl-04 .80E-08 NJ-05 .12E-07 Nl-06 .11E-07 NJ-07

12E-07 Nl-08 .12E-07 C-01 AFW System AFW P~ P*8A OFF P-8B OFF P-8C OFF AFW P~ All'pS P-8A 0. P-8C o.

AFW P~ P-88 Steam Pressui=e"" 0. psig AFW Disch Press P-8A & P-88 18. P-8C 18. psi Secondary System MSIV Bypass MOV-0501 CLOSED MOV*0510 CLOSED MSIV's CV-0501 CLOSED CV-0510 CLOSED MFP Suction Pressure 12..:. psig MFP Discharge Pressure A ;s:--- B 15. psi Moisture Separator Drain Tank Level 26. X Condenser Hotwell Level 70. X Atmospheri c-D~- Valves ClOSED- - Condenser-Vacuum --- .0 - in Hg.--- --

Heater Drain P~ Status P-10A OFF P*108 Q.E.E Gland Seal Condenser Vacuum 14.2 in Hg.

Condensate P~ Status P*2A OFF P-28 OFF (Demand Log + Constant, Rod, or Flux/Temp)

Gross MW 0. Net MW O. Core Exit Thermocouple Temperature 120.0 F Control Rod Position GP1 0. GP2 Q.:. GP3 Q.:. GP4 .:,Q GP5CP) 1..:.. GP6(A) Q.:. GP7CB) O.

Stuck Rods NONE # Q

Date OCTOBER 26, 1993 Message # 21 (Page 2) Time 1200 Scenario Time 0330 Time J.._., -- Scenario Time J.._., --

£:ll T-81 Level 90. X T-939 Level 93. x Condensate Storage Tank Level T-2 89. x Instrument A"fr'""Pressure 100 psig Containment Building Pressure -5. psig Dome T~rature 102 F Hunidity 29. x S/G A C~rtment T~rature 102 F Hllllidity 30. x S/G B C~rtment T~rature 93. F Hllllidity 30. x SIRW Tank Level 0. x WR Containment Pressure CR) 9. psia Containment s....., Level 585 x. Containment Water Level CR> Q.:. x SI Tank Level CX> A 40. B 39. c 39. D 39.

SI Tank Pressure Cpsig) A 149 B 149 c 149 D 150 PANEL K-13 SIAS Alarm ~ Containment High Pressure Alarm !!.Q Containment High Radiation Alarm ~

Concentrated Boric Acid Tank Levels T53A

100. x T53B 10.6 %

Reactor Vessel DP 16.8 psid PORV Discharge T~rature m F Pzr Safety Valve Discharge TeQ1) CF> RV-1039 127 RV-1040 142 RV-1041 177 PCP Current (~) P-SOA o. P-50B 667 P*50C 678 P*SOD 0.

PCS Flow 34. x Pressure Level <cold) 96.6 %

Loop Thot CF) Loop 1 120 Loop 2 120 Loop Tcold CF> Loop 1 TI9 Loop 2 120 Tcold Wide range Loop 1 120 Loop 2 119 Subcool ing T~ 281 F Press 247 psi PCS Prssure WR 249. NR 249. psi a Steam Generator A Steam Generator B Level (WR) 90. x CNR> 90. x (WR) 87. x CNR) §L. x Press ;:- psia 13. psia Flow Steam .0 PPH Feed .0 PPH Steam .0 PPH Feed .:,Q PPH Note: Steam and Feed Flow x 1000000 c-11 AFW Flow to A S/G From P*BA&B o. From P-8C o.

AFW Flow to B S/G From P*BA&B D." From P*8C 0.

Condenser Vacullll CR> D."

PCP Seal Leakoff Flow P-SOA 1.0 PPH P-50B .LQ PPH P*50C .LQ PPH P-50D .LQ PPH C-04 Diesel Generator Frequency 1-1 60. 1-2 .o 1-C BUS Voltage 2433 ~ 494 1-D BUS Voltage 2482 ~ 45.

C-11 Back C-11A Containment Area Monitors CR/Hr) RIA-1805 .2E-01 RIA-1806 .2E-01 RIA-1807 -.2-- RIA-1808 .8E-01 High Range Containment Monitors CR/Hr) RIA-2321 :l'E-01 RIA-2322 .1E-01 Containment Hydrogen Concentration (%) AI-2401R -0.-- Al-2401L -0.--

Main Steam Line Galllll8 (cpm) RIA-2324 .3E+02 RIA-2323 .2E+02 Stacie Monitors RIA-2325 1111 cpm RIA-2326 ,:..Q cpm RIA-2327 ,:..Q mr/hr

- - - - - ~- - ---~-----

~----

PALEX-93 TIME: µoo MESSAGE No: ;2./

SCENARIO TIME: 4Zt30

ANNUNCIATOR DISPLAYS

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SCENARIO TIME: t?..:330

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PALEX-93 TIME: MESSAGE No:

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ANNUNCIATOR DISPLAYS K-*1

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PALEX-93 TIME: MESSAGE No:

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ANNUNCIATOR DISPLAYS 1(-11

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PALEX-93 TIME: j;l{)tJ MESSAGE No: o2/

SCENARIO TIME:.- lfJ..330

ANNUNCIATOR DISPLAYS K-21

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PALEX-93 TIME: /;lCJO MESSAGE No: ;z,j SCENARIO TIME: o33o

ANNUNCIATOR DISPLAYS

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Scenario No: PALEX-93 Time: W5'

Message No: 22 Scenario Time: 0345 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Control Room Operators Simulated Plant Conditions:

Message:

See attached Alarm and Data Sheets.

FOR CONTROLLER USE ONLY Controller Notes:

Action Expected:

Date OCTOBER 26. 1993 Message# 22 (Page 1) Time 1215 Scenario Time 0345 Time J~ - - Scenario Time J~

~

SW S~ P*7A ON P-78 ON P*7C STBY SW Critical Hdr Press A 46. B 46. psig ccw P-52C ruv P-5,A OFF p~ P*52A ON P*52B ON FPC P~

Fire P~ P*9A .Q!t P-98 OFF P-41 OFF P*51B ON Contair111ent Cooler Recirc Fans V1A OFF V2A Qf.E V3A Qf.E V4A Qt! V1B OFF V2B Qf.E V3B .Q!t V4B Qt!

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CCW Cooler Outlet Teq:> A 52. F B 52. F Contair111ent Spray P~ P-54A OFF P-548 OFF P*54C OFF HPSJ P~ P*66A OFF P-668 OFF LPSI P~ P-67A Qf.E P-678 ON Safety Injection Suction Supply Train A Train B CV-3057 (SIRW) ~ CV-3029 CSIRW) ~ CV-3031 (SIRW) ~ CV-3030 CS~) CLOSED Letdown Charging Interniecliate Press Letdown Teq::i 98. F Flow 40. gpm Letdown Line Teq:> 105 F Line Teq:> 21..:.. F Letdown Flow 32. gpm P~ P*55A ON P*55B OFF P*55C .Q.Ef Volume Control Tank Teq:> 85. F Pressure 38. psi Level ~ x PCP Control Bleedoff Pressure 150 psi(;

Shutdown Cooling System SDCS from PCS CR) 120 F SOCS to PCS (R) Zl:. F Quench Tank

Pressurizer Pressure CR>

PCS Tave CR>

Pressurizer Level CR)

Pzr Htr Aq>s Teq:> 102 F 249. psia LRC*0101A 100 x LCC 15 0.-

Pressure .:b. psig Primary Coolant System Loop 1 CTR-0111) 119 Loop 2 CTR-0121) 119 LRC-01018 100 x LCC 16 0.-

Level 65.

LIA-0102A 97.

x x

PORV PRV-1042B CLOSED PRV-10438 CLOSED Block Valve MOV*1042A QfE!! MOV*1043A Qefil!

PCPs P*50A OFF P-508 ON P*50C ON P-500 OFF Reactor Power Level Nl-01 :i8E+02 Nl-02 :l8E+02 Nl-03 .82E*08 Nl-04 .80E-08 Nl-05 .12E*07 Nl-06 .11E-07 Nl-07 .12E*07 Nl-08 .12E-07 c-01 AFW system AFW P~ P-8A OFF P-88 Qff. P-8C OFF AFW P~ Amps P-8A 0. P-8C 0.

AFW P~ P-8B Steam Pressure O. psig AFW Disch Press P-8A & P-88 18. P*8C 18. psi Secondary System MSIV Bypass MOV-0501 CLOSED MOV-0510 CLOSED MSIV's CV-0501 CLOSED CV-0510 CLOSED MFP Suction Pressure ~ psig MFP Discharge Pressure A ;s:--- B 15. psi Moisture Separator Drain Tank Level 26. X Condenser Hotwell Level 70. X Atmospheric D~ Valves CLOSED Condenser Vacuum .:,Q in~H~g_._ _

___ -~-Heater.-Drai n-P~-Status----P--1 OA- OFF--- -P-1 OB-OFF- ------Gland- Sea l-condens*er-vac~~-- fn Hg.

Condensate P~ Status P-2A OFF P-2B Qff.

(Demand Log + Constant, Rod, or Flux/Teq:>)

Gross MW 0. Net MW 0. Core Exit Thermocouple Temperature 120.0 F Control Rod POsition GP1 0. GP2 .!!..:. GP3 .!!..:. GP4 ~ GP5(P) 1.:. GP6(A) f!.:. GP7(B) 0.

Stuck Rods NONE # Q

Date OCTOBER 26. 1993 Message # 22 (Page 2) Time 1215 Scenario Time 0345 Time J~ - - Scenario Time J~ - -

C-13 T-81 Level 90. X T-939 Level 93. x Condensate Storage Tank Level T-2 §2.. x 100 psig Instrunent Air'Pressure .

Containment Building Pressure -5. psig Dome T~rature 102 F Hunidity 29. x S/G A C~rtment T~rature 102 F Hunidity 30. x S/G B C~rtment T~rature 93. F Hunidity 30. x SIRW Tank Level 0. x WR Containment Pressure CR) 9. psi a Containment S~ Level 585 x Containment Water Level CR) 2.:. x SI Tank Level CX> A 40. B 39. c 39. D 39.

SI Tank Pressure (psig) A 149 B 149 c 149 D 150 PANEL K-13 SIAS Alarm NO Containment High Pressure Alarm !!Q Containment High Radiation Alarm NO Concentrated Boric Acid Tank Levels T53A . 100. x T53B 10.6 x Reactor Vessel DP 16.8 psid PORV Discharge T~rature 112 F Pzr Safety Valve Discharge T~ CF> RV-1039 127 RV-1040 142 RV-1041 177 PCP Current CA111>s> P-50A 0. P-50B 667 P-SOC 678 P-5DD 0.

PCS Flow 34. x Pressure Level (cold) 96.6 Loop Thot CF) Loop 1 12o Loop 2 llQ Loop Tcold (F) Loop 1 'ii9 Loop 2 120 Tcold Wide range Loop 1 12o Loop 2 lli Subcool ing Teq> 281 F Press 247 psi PCS Prssure WR 249. NR 249. psia Steam Generator A Steam Generator B Level (WR) 90. x (NR) .22.:. x (WR) 87. x (NR) 87. x Press ;:- psi a 13. psia Flow Steam .o PPH Feed .o PPH Steam .0 PPH Feed .:,Q PPH Note: Steam and Feed Flow x 1000000 C-11 AFW Flow to A S/G From P-8A&B 0. From P-BC o.

. AFW Flow to B S/G From P-8A&B Q.' From P-BC o.

Condenser Vacuun CR) Q.'

PCP Seal Leakoff Flow P-SOA 1.0 PPH P-SOB 1.:.Q PPH P-SOC 1.:.Q PPH P*SDD 1.:.Q PPH C-04 Diesel Generator Frequency 1-1 60. 1-2 .o 1-C BUS Voltage 2433 Aq>S 494 1-D BUS Voltage 2482 Aq>S 45.

C-11 Back C-11A Containment Area Monitors CR/Hr) RIA*1805 .2E-01 RIA-1806 .2E-01 RIA*1807 -.2-- RIA-1808 :8E:o1 High Range Containment Monitors CR/Hr) RIA-2321 :i"E-01

-0.--

RIA-2322 :1E=01 Containment Hydrogen Concentration <X> Al-2401R AI-2401L -0.--

Main Steam Line Gamma Ccpm) RIA-2324 .3E+02 RIA*2323 .2E+02 Stack Monitors RIA-2325 1111 cpm RIA*2326 .:,Q cpm RIA-2327 .:,Q mr/hr

~-- - - - - - - - - - -- - - - - - - - - - - --- - - - - - - - - -- - - - - - - - - - - - - ----

PALEX-93 TIME: MESSAGE No:

SCENARIO TIME:

ANNUNCIATOR DISPLAYS K-01

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PALEX-93 TIME: I .;ij.5" MESSAGE No:

SCENARIO TIME: @'-/.?'

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PALEX-93 TIME: )e2.J.S- MESSAGE No:

SCENARIO TIME: 6Jc3'~

ANNUNCIATOR DISPLAYS K-C6A

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PALEX-93 TIME: MESSAGE No:

SCENARIO TIME:

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P.ALEX-93 TIME: MESSAGE No:

SCENARIO TIME:

ANNUNCIATOR DISPLAYS 1(-11

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PALEX-93 TIME: /ql)_5" - MESSAGE No:

SCENARIO TIME: &,37{?

ANNUNCIATOR DISPLAYS K-21

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Scenario No: PALEX-93 Time: 1230 Message No: 23 Scenario Time: 0400 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Control Room Operators Simulated Plant Conditions:

Message:

See attached Alarm and Data Sheets.

FOR CONTROLLER USE ONLY Controller Notes:

Action Expected:

Date OCTOBER 26. 1993 Message # 23 (Page 1) Time 1230 Scenario Time 0400 Time Juq> - - Scenario Time Juq> - -

c-os SW Suq>s P-7A ON P-78 ON P*7C STBY SW Critical Hdr Press A 46. B 46. psig P-528 ON P*52C STBY CCW Puq>s P*52A ON FPC Puq>s P*51A OFF Fire Puq>s P*9A 2!!. P-98 OFF P-41 OFF P-518 ON Contail"lllent Cooler Recirc Fans V1A QEf. V2A QEf. V3A QEf. V4A Qt! V1B QEf. V2B QEf. V3B Qt! V4B Qt!

CCW Cooler Outlet T~ A 52. F B 52. F Containment Spray Puq>s P*54A OFF P-548 OFF P*54C OFF HPSI Puq>s P*66A OFF P-668 OFF LPSI Puq>s P-67A QEf. P-678 ON Safety Injection Suction Supply Train A Train B CV-3057 (SIRW) CLOSED CV-3029 (SIRW) CLOSED CV-3031 (SIRW) ~ CV-3030 (Suq>) CLOSED Letdown Chars ins Intermediate Press Letdown T~ 98. F Flow 40. gpm Letdown Line T~ 105 F Line T~ 21:. F Letdown Flow 32. gpm Puq>s P*55A ON P-558 OFF P*55C OFF Volune Control Tank T~ 85. F Pressure 38. psi Level 94. x PCP Control Bleedoff Pressure 150 psig Shutdown coolins system SOCS from PCS (R) 120 F SOCS to PCS (R) 73. F Quench Tank

Pressurizer Pressure CR>

PCS Tave CR>

Pressurizer Level CR)

Pzr Htr A8')S T~ 102 F 249. psia Pressure ~ psig Primary Coolant System Loop 1 (TR-0111) 119 Loop 2 CTR-0121) 119 LRC*0101A 100 x LCC 15 Q."'"

LRC-01018 100 x LCC 16 Q."'"

Level 65.

LIA*0102A 97.

X x

PORV PRV-10428 CLOSED PRV-10438 CLOSED Block Valve MOV-1042A OPEN MOV-1043A OPEN PCPs P-50A OFF P-508 ON P*50C ON P-500 OFF Reactor Power Level NI-01 :i8E+02 NI-02 :i"8E+02 NI-03 :ii2E-08 NI-04 .80E-08 NI-05 .12E-07 NI-06 .11E-07 NI-07 .12E*07 NI-08 .12E-07 C-01 AFW System AFW Puq> P-8A OFF P-88 OFF P-8C OFF AFW Puq> ~ P-8A 0. P*8C 0.

AFW Puq> P-88 Steam Pressure 0. psig AFW Disch Press P-8A & P-88 18. P-8C 18. psi Secondary System MSIV Bypass MOV-0501 ~ MOV-0510 CLOSED MSIV's CV-0501 CLOSED CV-0510 CLOSED MFP Suction Pressure ~ psig MFP Discharge Pressure A~ B 15. psi Moisture Separator Drain Tank Level 26. X Condenser Hotwell Level 70. X Atmospheric Duq> Valves CLOSED Condenser Vacuun :0 in Hg.

-- -- ---Heater- Drai n-Puq>-Status---P-1 DA- Qff.- --P-1 OB-Qff. - - ------Gland-Seal-Condenser-Vacuun--14--;2-- - in-Hg-.----------

Condensate Puq> Status P-2A OFF P-28 OFF (Demand Log + Constant, Rod, or Flux/T~)

Gross MW O. Net MW 0. Core Exit Thermocouple Temperature 120.0 F Control Rod POsition GP1 0. GP2 .!1.:. GP3 .!1.:. GP4 .:,Q GP5(P) l.:. GP6(A) .!1.:. GP7(8) O.

Stuck Rods ~ # Q

Date OCTOBER 26. 1993 Message # 23 (Page 2) Time 1230 Scenario Time 0400 Time J~ - - Scenario Time J~ - -

C-13 T-81 Level 90. X T-939 Level 93. x Condensate Storage Tank Level T-2 89. x lnstri.nent AirPressure ,

100 psig Containnent Building Pressure -5

psig Dome T~rature 102 F Hi.nidity 29. x S/G A Coq:>artment T~rature 102 F Hi.nidity 30. x S/G B Coq:>artment T~rature 93. F Hi.nidity 30. x SIRW Tanlc Level 0. x WR Containnent Pressure CR) 9. psi a Containnent S~ Level 585 x Containnent Water Level CR) !!:. x SI Tank Level CX> A 40. B 39. c 39. D 39.

SI Tank Pressure Cpsig) A 149 B 149 c 149 D 150 PANEL K-13 SIAS Alarm NO Containnent High Pressure Alarm NO Containnent High Radiation Alarm !!Q Concentrated Boric Acid Tank Levels T53A 1QQ..:. x T53B 10.6 x Reactor Vessel DP 16.8 psid PORV Discharge T~rature 112 F Pzr Safety Valve Discharge T~ CF> RV-1039 127 RV-1040 142 RV-1041 177 PCP Current (Alrps) P-50A 0. P*50B 667 P*50C 678 P-50D 0.

PCS Flow 34. x Pressure LeVel (cold) 96.6 x Loop Thot (F) Loop 1 120 Loop 2 120 Loop Tcold CF) Loop 1 119 Loop 2 120 Tcold Wide range Loop 1 12o Loop 2 'IT9 Subcooling T~ 281 F Press w psi PCS Prssure WR 249. NR 249. psia Steam Generator A Steam Generator B Level CWR) 90. x CNR) 90. x (WR) 87. x CNR) 87. x Press ;-:-- psi a 13. psis Flow Steam .0 PPH Feed .0 PPH Steam .0 PPH Feed ,:.Q PPH Note: Steam and Feed Flow x 1000000

£.:1!

AFW Flow to A S/G From P*8A&B o. From P*8C o.

AFW Flow to B S/G From P*8A&B 0: From P-8C 0.

Condenser Vacui.n CR) 0:

PCP Seal Lealcoff Flow P*50A 1.0 PPH P*50B kQ PPH P-50C kQ PPH P*50D kQ PPH Diesel Generator Frequency 1-1 60. 1-2 .0 1-C BUS Voltage 2433 Amps 494 1-D BUS Voltage 2482 Amps 45.

C-11 Baclc C*11A Contairvnent Area Monitors CR/Hr) RIA-1805 .2E-01 RIA-1806 .2E-01 RIA-1807 -.2-- RIA-1808 .8E*01 High Range Contairvnent Monitors CR/Hr) RIA-2321 :i"E-01 RIA-2322 .1E-01 Containnent Hydrogen Concentration CX> AI-2401R -0.-- AI*2401L -0.--

Hain Steam Line Ganina Ccpm> RIA-2324 .3E+02 RIA-2323 .2E+02 Stacie Monitors RIA-2325 1111. cpm RIA-2326 ,:.Q cpm RIA-2327 ,:.Q mr/hr

~-- -- - ---- - - - - - - - -- - - - - ----- - - - - - - - - - - -- --~------------------- -

PALEX-93 TIME: /~O MESSAGE No:

SCE~O TIME:foO

ANNUNCIATOR DISPLAYS K-01

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PALEX-93 TIME: h230 MESSAGE No:

6?@0 SCEN'ARIO TIME:

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SCENARIO TIME:

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PALEX-93 TIME: /.:Z30 MESSAGE No:

SCENAAIO TIME: tJ fC 0

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PALEX-93 TIME: /.:?.,30 MESSAGE No:

SCE?WUO TIME: (2 ~(20

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PALEX-93 TIME: MESSAGE No:

SCENARIO TIME:

ANNUNCIATOR DISPLAYS K-21

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PALEX-93 TIME: /;l.3 O MESSAGE No:

SCENARIO TIME: t??t'PV

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Scenario No: PALEX-93 Time: 1245 +24 hrs Message No:

24 Scenario Time: 0415 +24 hrs PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE FORM Message For: Site Emergency Director and EOF Director Simulated Plant Conditions:

See attached assessment sheet.

Message:

Begin Recovery Planning Plant personnel involved in Recovery Planning report to the EOF for Recovery Discussions at 2:00 pm.

FOR CONTROLLER USE ONLY

Controller Notes:

If Environmental vegetation, milk, and water samples have not been obtained (simulated discussions) then DELETE Item #4 from RAD Data on Recovery Sheet before giving to players. This should have taken place and if not an item on the critique.

Have Players break for lunch - 1/2 hour maximum.

All Players participate in Facility Critique (may perform facility critique while eating lunch).

Plant personnel for recovery will travel to the EOF for Recovery Planning Discussions.

Action Expected:

Rad Data for ~a-entry/Recovery

1.

2.

The bulk material from the tornado has been picked up or secured.

Dose Rates are all less than 1 mR/HR.

There is still loose and fixed contamination on the access road inside the Protected Area ranging from 100 to 10,000 cpm.

3. There has been no identified hot spots of contamination outside the Protected Area. Monitoring Teams are still checking surrounding environs. The environmental TLDs and Air Samples have been pulled with no activity identified by plant equipment but they have been sent offsite for evaluation.

4. Environmental vegetation, milk, and water samples have been obtained and are being readied for shipment.

General Data

1. Work is continuing on covering the Spent Fuel Pool and SIRW Tank with temporary coverings.

2. Security is manning the breaches in the Protected Area fencing 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months a day *

3. General debris clean-up and site evaluation is on going.

4. Procedure changes and Facility repair/changes are being evaluated.

-------------- ~--------

CFMS OPERATIONS DATA

SHAVPALl T S C S T A T U S PAGE

PALEX 93 Time 0800 Scenario Time -0030 Message # 1 Time Jump Scenario Time Jump

--- 140 I C-13 c-12 i

I .PCP Current (Amps)

Condensate Storage Tank Level T-2 89. o.

Instrument Air P~essure 95. '

psig P-50A P-50C 678 P-508 668 P-50D o.

( 15) Containment Ileuilding Pressure -5. psig (6) PCS Flow

( 16) S/G A Compar tment Temperature 1

101 F (3) Thot (F) Loop 1 115 F S/G A COMPARTMENT Humidity 30.

I Loop 2 115 F

( 16) S/G B Compar tment Temperature 1

92. F (2) Tcold (F) Loop lA 114 F S/G B Humidi~ty 30 Loop 2A 115 F

( 16) Dome TemperaIture 1

103 F Loop 18 115 F

( 11) SIRW Tank Le:vel 98.

(15) WR Containmelnt Pressure (R)

(14) Containment ~ump Level 10 '

psia (5) Subcooling Loop 28 114 F 283 F 242 PSIA*.

585 (14) Containment Water Level (R) i (22) SI Tank Level (%)

o. (7)

(7)

PCS WR Pressure (R) 244. PSIA PCS NR Pressure (R) 244. PSIA (30) S/G A LEVEL WR 90.

I A 40. I B 39. c 39. D 39. (30) S/G A LEVEL (R) 90.

SI Tank Pres~ure (psig) (30) S/G A PRESS 1. psia A 150 B 151 c 151 D 152 S/G A STM FLW (R) .o Xl0**6 PPH (21) SIAS Alarm l NO S/G A FD FLW (R) .o Xl0**6 PPH (30) S/G B LEVEL WR 87.

I c-12 (30) S/G B LEVEL (R) 87.

I (30) S/G B PRESS 13. psia Concentrated! Boric Acid Tank Levels T53A S/G B STM FLW (R) .o Xl0**6 PPH 100. .o Xl0**6 T53B i 10.6 ' S/G B FD FLW (R) PPH I

Reactor Vessel DP I

(12) PORV Discharge Temperature 16.9 '

paid PANEL IC-13 111 F (13) Pzr Safety Valve Discharge Temp (F) (20) CONTAINMENT HIGH PRESS I

RV-1039, 126 F NO RV-1040 I 141 F RV-1041' 176 F (20) Containment High Radiation NO

SHAVPALl PALEX 93 T S C S T A T U S PAGE Time 0800 Scenario Time -0030 Message # 1 141 Time Jump Scenario Time Jump I

. I c-01 C-04 I

MFP suction Pressure 15. psig (32) D/G Freq 1-1 .o 1-2 .o I

MFP A Discharge ~ressure 15. psig (32) 1-C BUS VOLTS 2447 Amps365 MFP B Discharge Pressure 15. psig (32) 1-D BUS VOLTS 2455 Amps291 I

AFW Pump P-8C Amp~res o. AMPS .

AFW Discharge Pre,sure P-SC 18. psig C-11 BACK C-llA AFW Pump P-8A Amperes I

o. AMPS AFW Pump P-8B Stec:un Pressure o. psig (17) Containment Area Monitors AFW Discharge Pre~sure P-8A & P-8B 18. psig RIA-1805 .2E-01 R/Hr Moisture SEP Drain Tank Level 26. RIA-1806 .2E-01 R/Hr Condenser Hotwe11ILevel Condensor Vacuum

I 70.

.o

in Hg.

RIA-1807 RIA-1808

.2

.8E-Ol R/Hr R/Hr Gland Seal Condenser Vacuum 14.2 in Hg. (17) High Range Containment Monitors Atmospheric Dump yalves CLOSED RIA-2321 .lE-01 R/Hr AFW Pump P-SA OFF P-8B OFF P-8C OFF RIA-2322 .lE-01 R/Hr Heater Drain Pump! P-lOA OFF P-lOB OFF (19) Containment Hydrogen Concentration Condensate Pump I P-2A OFF P-2B OFF AI-2401R o.

AI-2401L o. '

c-11 (30) Main Steam Line Gamma '

I RIA-2324 .3E+02 CPM (31) AFW FLOW TO SGAI RIA-2323 .2E+02 CPM FROM P8A, B (!). From P-8C o. gpm (31) AFW FLOW TO ~GB EQUIPMENT STATUS:

FROM P-8A&B Q. From P-8C o. gpm Condenser VaeuumI (R) o. IN HG. 1. SIGNIFICANT EQUIP OUTAGES PCP A Leak-off Flow (R) 1.0 (INOPERABLE EQUIPMENT)

PCP B Leak-off Flow (R) 1.0 2. SURVEILLANCE DUE/PROGRESS I

PCP c Leak-off I Flow (R) 1.0 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off Flow (R) 1.0 OR OUTAGES i

I I

SHAVPALl PALEX 9J T S C S T A T U S P A G E Time OBOO scenario Time -0030 Message # 1 142 Time Jump Scenario Time Jump C-08 c-02 SW Pumps P-7A ON P-78 ON P-7C STBY (10) VCT Temp 85. F ccw Pumps P-52A ON P-528 ON P-52C STBY (10) VCT Pressure 3B. psi FPC Pumps P-SlA OFF P-518 ON (10) VCT Level 90.

PCP Control Bleedoff Pressure '

150 psig CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow 47. gpm (26) Charging Flow 46. gpm VlA OFF V2A OFF V3A ON V4A ON (9) Quench Tank Temp 102 F VlB OFF V2B OFF V3B ON V4B ON (9) Quench TANK Pressure -2. psig (9) Quench TANK Level 65.

C-03 (7) Pressurizer Pressure (R) '

244. psia (8) PZR Level (R) LT0102A 97 (23) HPSI Pumps P-66A OFF P-668 OFF LT0103 96.7 '

(25) LPSI Pumps P-67A ON P-678 OFF (12) PORV PRV-1042A CLOSED 10438 CLOSED' (lB) 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 P5SB OFF PSSC OFF CV-3Q57 (SIRWT) CV-3030 (Sump) (6) PCPS P50A OFF PSOB ON PSOC ON PSOD OFF CLOSED CLOSED PZR HTR AMPS LC15 O. LCC 16 O.

(1) PCS TAVE (R) LOOP! (TR-0111) 115 F LOOP2 (TR-0121) 115 F c-02 (25) REACTOR POWER LEVEL Nil .18E+02 cps NI3 .82E-08 NI7 .12E-07 Intermediate Press Letdown Temp BS. F NI2 .18E+02 cps NI4 .BOE-OB ' NIB .12E-07 '

Charging Line Temperature 99. F NI-05 .12E-07 ' NI-09 '

Letdown Line Temp 84.

115 F

F NI-06

llE-07 NI-10 SCCS from PCS (R)

SCCS to PCS (R) 70. F PIP (DEMAND LOG+CONSTANT, ROD, OR FLUX/TEMP)

Gross MW o.

Net* MW -3.

(28) Control Rod Position GPl O. GP2 O. GP3 O. GP4 .O GP6(A) .Q..:_ GP7(B) O.

Stuck Rods NONE <optional># 0 Core Exit Temp 115.3F

SHAVPALl T S C S T A T U S PAGE

PALEX 9, Time 0832 Scenario Time 0002 Message # ~ 140 Time Jump Scenario Time Jump C-13 c-12 i PCP Current (Amps)

I I

89. P-50A O. P-50B 667 Condensate Storage Tank Level T-2 I

Instrument Air Pr~ssure 103 '

psig (6)

P-50C PCS Flow 678 P-SOD O.

(15) Containment Building Pressure -5. psig (16) S/G A Compar~ment Temperature 102 F (3) Thot (F) Loop 1 120 F

30. Loop 2 120 F S/G A COMPARTMENT Humidity I

(16) S/G B Compartment Temperature I

93.

30.

F (2) Tcold (F) Loop lA Loop 2A 120 F 119 F S/G B Humidii;-Y (16) Dome TemperatureI 103. 'F Loop lB 119 F

( 11) SIRW Tank Leyel 98. Loop 2B 120 F (15) WR Containme~t Pressure (R) 9. 'psia (5) Subcooling 277 F 238 PSIA *

(14) Containment $ump Level 585 (7) PCS WR Pressure (R) 240. PSIA (14) Containment Water I

Level (R) o. (7)

(30)

PCS NR Pressure (R) 240. PSIA S/G A LEVEL WR (22) SI Tank Level (\) 90. '

A 40. I B 39. c 39. D 39. (30) S/G A LEVEL (R) 90. '

-- I -- psia SI Tank Pres~ure (psig) (30) S/G A PRESS 1.

A 149 ! B 149 c 150 D 151 S/G A STM FLW (R) .o Xl0**6 PPH (21) SIAS Alarm , NO S/G A FD FLW (R) .o Xl0**6 pp~

87.

I c-12 (30)

(30)

S/G B LEVEL WR S/G B LEVEL (R) 87. %'

I (30) S/G B PRESS 13. psia Concentrated! Boric Acid Tank Levels S/G B STM FLW (R) .o Xl0**6 PPH I

100. S/G B FD FLW (R) .o Xl0**6 PPH T53A i 10.6 '

T53B Reactor Vessel DP 16.6 'paid PANEL K-13 (12) PORV Discharbe Temperature 112 F I

(13) Pzr Safety Valve Discharge Temp (F) (20) CONTAINMENT HIGH PRESS 1

RV-1039! 126 F NO RV-1040' 141 F RV-1041 176 F (20) Containment High Radiation NO

SHAVPALl PALEX 9.3 I T S C S T A T U S P A G E I

Time 0832 I Scenario Time 0002 Message # 2 141 Time Jump Scenario Time Jump II I c-01 c-04 I

MFP Suction Pressure 15. psig (32) D/G Freq 1-1 60. 1-2 .o I

MFP A Discharge Pressure 15. psig (32) 1-C BUS VOLTS 2442 Amps407 I

MFP B Discharge lressure 15. psig (32) 1-D BUS VOLTS o. Amps!!!_

AFW Pump P-8C Amperes I

o. AMPS AFW Discharge Pressure P-8C 18. psig C-11 BACK C-llA I

AFW Pump P-8A Amp~res o. AMPS AFW Pump P-8B Ste~m Pressure I

o. psig (17) Containment Area Monitors AFW Discharge ~re~sure P-8A & P-8B 18. psig RIA-1805 .2E-01 R/Hr Moisture SEP Draitj Tank Level 26. RIA-1806 .2E-01 R/Hr Condensor Hotwell !Level 70. RIA-1807 .2 R/Hr Condenser Vacuum .o in Hg. RIA-1808 .8E-01 R/Hr Gland Seal Condenser Vacuum 14.2 in Hg. (17) High Range Containment Monitors Atmospheric Dump ~alves CLOSED RIA-2321 .lE-01 R/Hr AFW Pump P-8A OFF P-8B OFF P-8C OFF RIA-2322 .lE-01 R/Hr Heater Drain Pump_!__ P-lOA OFF P-lOB OFF (19) Containment Hydrogen Concentration i P-2A OFF P-2B OFF AI-2401R o.

Condensate Pump C-11 AI-2401L o.

(30) Main Steam Line Gamma RIA-2324 .3E+02 CPM (31) AFW FLOW TO ~GA RIA-2323 ~2E+02 CPM FROM P8A, B O. From P-8C 0. gpm (31) AFW FLOW TO SGB . EQUIPMENT STATUS:

I FROM P-8A&B O. From P-8C 0. gpm Condensor Vaquum (R) o. IN HG. 1. SIGNIFICANT EQUIP OUTAGES PCP A Leak-o~f Flow (R) 1.0 (INOPERABLE EQUIPMENT)

PCP B Leak-o~f Flow (R) 1.0 2. SURVEILLANCE DUE/PROGRESS PCP C Leak-off I Flow (R) 1.0 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-o~f Flow (R) 1.0 OR OUTAGES I

SHAVPALl PALEX 9.J T S C S T A T U S P A G E Time 0832 scenario Time 0002 Message # 2 142 Time Jump Scenario Time Jump C-08 c-02 SW Pumps P-7A OFF P-7B ON P-7C OFF (10) VCT Temp as. F ccw Pumps P-52A ON P-528 OFF P-52C STBY (10) VCT Pressure 38. psi FPC Pumps P-51A OFF P-518 OFF (10) VCT Level 94.

PCP Control Bleedoff Pressure 150 '

psig CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow 23. gpm (26) Charging Flow o. gpm VlA OFF V2A OFF V3A OFF V4A ON (9) Quench Tank Temp 102 F VlB OFF V2B OFF V3B ON V4B ON (9) Quench TANK Pressure -2. psig (9) Quench TANK Level 65.

C-03 (7) Pressurizer Pressure (R) '

240. psia (8) PZR Level (R). LT0102A 97.

(23) HPSI Pumps P-66A OFF P-668 OFF LT0103 96.8

(25) LPSI Pumps P-67A OFF P-678 OFF (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, LPSIA, SPRAY A SUCTION PSSA OFF P558 OFF PSSC OFF CV-3057 (SIRWT) cv-3030 (Sump) (6) PCPS P50A OFF P50B ON P50C ON P50D OFF CLOSED CLOSED PZR HTR AMPS LClS O. LCC 16 O.

(1) PCS TAVE (R) LOOPl (TR-0111) 120 F LOOP2 (TR-0121) 120 F C-02 ( 2 5 ) REACTOR POWER LEVEL Nil .18E+02 cps NI3 .82E-08 NI7 .12E-07 Intermediate Pres~ Letdown Temp 113 F NI2 .18E+02 cps NI4 .BOE-08 ' NIB .12E-07 '

Charging Line Temperature 99. F NI-05 .12E-07 ' NI-09 '

Letdown Line Temp 118 94.

F F

NI-06 .llE-07 NI-10 socs from PCS (R)

SOCS to PCS (R) 88. F PIP (DEMAND LOG+CONSTANT, ROD, OR FLUX/TEMP)

Gross MW O.

Net MW O.

(28) Control Rod Position GPl O. GP2 O. GP3 O. GP4 .0 GP6(A) Q.=._ GP7(B) O.

Stuck Rods NONE <optional># 0 Core Exit Temp 119.9F

SHAVPALl T S C S T A T U S PAGE

PALEX 93 Time 0833 scenario Time 0003 Message # 3 140 Time Jump Scenario Time Jump i C-13 c-12 I PCP Current (Amps)

I Condensate Storage Tank Level T-2 89. :P-50A o. P-50B 667 Instrument Air PrJssure I

95. '

psig P-50C 678 P-50D O.

(15) Containment Building Pressure -5. psig (6) PCS Flow (16) S/G A Comparfment I

Temperature 102 F (3) Thot (F) Loop 1 120 F S/G A COMPARTMENT Humidity 30. Loop 2 120 F I

(16) S/G B Compartment Temperature 93. 'F (2) Tcold (F) Loop lA 119 F S/G B Humidity 30. Loop 2A 120 F I

(16) Dome Temperature 103 'F Loop lB 120 F (11) SIRW Tank LeJel 98. Loop 2B 119 F (15) WR Containme~t Pressure (R) 9. '

psia (5) Subcooling 275 F 233 PSIA-.

(14) Containment ~ump Level 585 (7) PCS WR Pressure (R) 235. PSIA (14) Containment ~ater Level (R) o. (7) PCS NR P~essure (R) 235. PSIA (22) SI Tank Level (%) (30) S/G A LEVEL WR 90.

A 40.

I i B 39.

SI Tank Pres~ure (psig)

C 39. D 39. (30)

(30)

S/G A LEVEL (R)

S/G A PRESS 90.

1.

psi a A 149 ! B 149 C 149 D 151 S/G A STM FLW (R) .o Xl0**6 PPH (21) SIAS Alarm NO S/G A FD Jt'LW (R) .o Xl0**6 PPH (30) S/G B LEVEL WR 87.

c-12 (30) S/G B LEVEL (R) 87. '

(30) S/G B PRESS '

13. psia Concentrated Boric Acid Tank Levels S/G B STM FLW (R) .o Xl0**6 PPH T53A 100. S/G B FD FLW (R) .o Xl0**6 T53B I 10.6 PPH Reactor Vessel DP 16.8 paid PAHEL lt-13 I

(12) PORV Discharge Temperature 112 F I

(13) Pzr Safety V'lve Discharge Temp (F) (20) CONTAINMENT HIGH PRESS RV-1039: 127 F NO RV-1040; 142 F 1

RV-1041 177 F (20) Containment High Radiation NO

SHAVPALl PALEX 93 T S C S T A T U S PAGE Time 0833 Scenario Time 0003 Message # ~ 141 Time Jump Scenario Time Jump c-01 C-04 i

MFP Suction Press~re 15. psig (32) D/G Freq 1-1 60. 1-2 .o I

MFP A Discharge ~ressure 15. psig (32) 1-C BUS VOLTS 2433 Amps494 MFP B Discharge Pressure I

15. psig (32) 1-D BUS VOLTS o. Amps.Q.:_

AFW Pump P-8C Amp~res o. AMPS.

AFW Discharge Pre~sure P-8C 18. psig C-11 BACK C-llA AFW Pump P-8A Amp~res o. AMPS AFW Pump P-8B Stearn Pressure o. psig (17) Containment Area Monitors AFW Discharge Pre~sure P-8A & P-8B 18. psig RIA-1805 .2E-Ol R/Hr Moisture SEP Drain Tank Level 26. % RIA-1806 .2E-01 R/Hr Condenser HotwelliLevel 70. % RIA-1807 .2 R/Hr Condenser Vacuum ' *o in Hg

RIA-1808 .8E-Ol R/Hr Gland Seal condenser Vacuum 14.2 in Hg. (17) High Range* Containment Monitors I

Atmospheric Dump Valves CLOSED RIA-2321 .lE-01 R/Hr I

AFW Pump P-8A OFF P-8B OFF P-8C OFF RIA-2322 .lE-01 R/Hr Heater Drain Pump-i~ P-lOA OFF P-lOB OFF (19) Containment Hydrogen concentration Condensate Pump 1 P-2A OFF P-2B OFF AI-2401R o. %

I AI-2401L o. %

c-11 (30) Main Steam Line Gamma II RIA-2324 .3E+02 CPM (31) AFW FLOW TO SGA RIA-2323 ~2E+02 CPM I

FROM P8A, B o. From P-8C O. gpm (31) AFW FLOW TO SGB EQUIPMENT STATUS:

FROM P-8A&B O. From P-8C O. gpm Condenser Vacuum (R)

I

o. IN HG. 1. SIGNIFICANT EQUIP OUTAGES PCP A Leak-off Flow (R) 1.0 (INOPERABLE EQUIPMENT)

PCP B Leak-off I Flow (R) 1.0 2. SURVEILLANCE DUE/PROGRESS PCP C Leak-off I Flow (R) 1.0 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off' Flow (R) 1.0 OR OUTAGES

SHAVPALl PALEX 9.3 T S C S T A T U S PAGE Time 0833 Scenario Time 0003 Message # 3 142 Time Jump Scenario Time Jump c-oa c-02 SW Pumps P-7A OFF P-78 ON P-7C OFF (10) VCT Temp 85. F CCW Pumps P-52A ON P-528 OFF P-52C ST8Y (10) VCT Pressure 38. psi FPC Pumps P-51A OFF P-518 OFF (10) VCT Level 94.

PCP Control 8leedoff Pressure '

150 peig CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow 6. gpm (26) Charging Flow 40. gpm VlA OFF V2A eFF V3A OFF V4A ON (9) Quench Tank Temp 102 F Vl8 OFF V2B OFF V3B ON V48 ON (9) Quench TANK Pressure -2. peig (9) Quench TANK Level 65.

C-03 (7) Pressurizer Pressure (R) '

235. peia (8) PZR Level (R) LT0102A 97.

(23) HPSI Pumps P-66A OFF P-668 OFF LT0103 96.9 '

(25) LPSI Pumps P-67A OFF P-678 ON (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, LPSIA~ SPRAY A SUCTION P55A OFF P55B OFF P55C ON CV-3057 (SIRWT) CV-3030 (Sump) (6) PCPS P50A OFF P50B ON P50C ON P50D OFF CLOSED CLOSED PZR HTR AMPS LC15 O. LCC 16 O.

(1) PCS TAVE (R) LOOPl (TR-0111) 119 F LOOP2 (TR-0121) 119 F c-02 (25) REACTOR POWER LEVEL Nil .18E+02 cps NI3 .82E-08 NI7 .12E-07 Intermediate Pree~ Letdown Temp 108 F NI2 .18E+02 cps NI4 .BOE-08 ' NIB .12E-07 '

Charging Line Tem~erature 103 117 F

F NI-05 .12E-07 NI-09 '

Letdown Line Temp

NI-06

llE-07 NI-10 socs from PCS (R) 120 F F

SOCS to PCS (R) 70. PIP (DEMAND LOG+CONSTANT, ROD, OR FLUX/TEMP)

Grose MW o.

Net.MW O.

(28) Control Rod Position GPl O. GP2 0. GP3 O. GP4 .O GP6(A) ~ GP7(8) O.

Stuck Rode NONE <optional># O Core Exit Temp 119.9F

SHAVPALl T S C S T A T U S PAGE

PALEX 93 Time 0844 Scenario Time 0014 Message # 5 Time Jump 140 Scenario Time Jump c-12 PCP Current (Amps)

Condensate Storage/ Tank Level T-2 89.

o.

Instrument Air Pre'ssure I

(15) Containment Building Pressure 100

-5.

psig P-50A P-50C 678 P-508 667 P-50D O.

I ~-

psig (6) PCS Flow

( l 6) S/G A Compartment Temperature 102 F (3) Thot (F) Loop 1 I 120 F S/G A COMPART~NT Humidity 30.

(16) S/G B Compartment Temperature S/G B Humidit~

93.

30.

F (2)

Loop 2 Tcold (F) Loop lA 120 F 119 F

( 16) Dome Temperat ure

( 11) SIRW Tank Lev~l 1

I 102 98.

F Loop 2A Loop 18 120 F 120 F (15) WR Containmen~ Pressure (R)

I (14) Containment Sµmp Level

9. '

psia (5) Subcooling Loop 28 119 F 281 F 247 PSIA *.

585 (7) PCS WR Pressure (R) 249. PSIA (14) Containment W:ater Level (R) o. (7) PCS NR Pressure (R) 249. PSIA (22) SI Tank Leve~ (%) (30) S/G A LEVEL WR 90.

A 40. i B 39.

SI Tank Press u re (psig) c 39. D 39. (30)

(30)

S/G A LEVEL (R)

S/G A PRESS

90.

1. psia A 149 , B 149 1

C 149 D 150 (21) SIAS Alarm I

NO S/G A STM FLW (R) .o Xl0**6 PPH I S/G A FD FLW (R) .o Xl0**6 PPR I (30) S/G B LEVEL WR 87.

i c-12 I

(30)

S/G B LEVEL (R)

S/G B PRESS

87.

13. psia Concentrated Boric Acid Tank Levels T53A I 100.

S/G B STM FLW (R) .o Xl0**6 PPH T53B I 10.6 ' S/G B FD FLW (R) .o Xl0**6 PPH Reactor Vesse 1 DP 1

(12) PORV Discharg~ Temperature 16.8 112 paid PANEL K:-13 F

(13) Pzr Safety Va:lve Discharge Temp (F)

(20) CONTAINMENT HIGH PRESS RV-1039 I 127 F RV-1040 NO 142 F RV-1041 I 177 F (20) Containment High Radiation NO

SHAVPALl PALEX 9.4 T S C S T A T U S P A G E Time 0844 Scenario Time 0014 Message # 5 141 Time Jump Scenario Time Jump C-01 c-04 MFP Suction PressJre 15. psig (32) D/G Freq 1-1 60. 1-2 .o I

MFP A Discharge ~ressure 15. psig (32) 1-C BUS VOLTS 2433 Amps494 MFP B Discharge Pressure 15. psig (32) 1-D BUS VOLTS 2482 Amps45.

AFW Pump P-8C Amp~res I

o. AMPS AFW Discharge Pre~sure P-8C 18. psig" C-11 BAClt C-llA AFW Pump P-8A Amp~res o. AMPS AFW Pump P-8B steam Pressure I

o. psig (17) Containment Area Monitors AFW Discharge Pre~sure P-8A & P-8B 18. psig RIA-1805 .2E-01 R/Hr Moisture SEP DrairlI Tank Level 26. RIA-1806 .2E-Ol R/Hr Condenser Hotwell /Level Condenser Vacuum :

70.

.o in Hg.

RIA-1807 RIA-1808

.2

.8E-Ol R/Hr R/Hr Gland Seal condenser Vacuum 14.2 in Hg. (17) High Range* containment Monitors Atmospheric Dump ~alves CLOSED RIA-2321 .lE-01 R/Hr AFW Pump P-8A QFF P-8B OFF P-8C OFF RIA-2322 .lE-01 R/Hr Heater Drain Pump i P-lOA OFF P-lOB OFF (19) Containment Hydrogen Concentration Condensate Pump I P-2A OFF P-2B OFF AI-2401R O. \

AI-2401L o.

I c-11 (30) Main Steam Line Gamma '

RIA-2324 .3E+02 CPM I

(31) AFW FLOW TO SGAI RIA-2323 *2E+02 CPM FROM P8A, B 0,. From P-8C o. gpm (31) AFW FLOW TO ~GB EQUIPMENT STATUS:

FROM P-8A&B d.. From P-8C O. gpm Condenser va9uum (R) O. IN HG. 1. SIGNIFICANT EQUIP OUTAGES PCP A Leak-ofjf Flow (R) 1.0 (INOPERABLE EQUIPMENT)

I PCP B Leak-of;f Flow (R) 1.0 2. SURVEILLANCE DUE/PROGRESS PCP c Leak-otl£ Flow (R) 1.0 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-of,f Flow (R) 1.0 OR OUTAGES I

I I

SHAVPALl PALEX 93 T S C S T A T U S PAGE Time 0844 Scenario Time 0014 Message # ! 142 Time Jump Scenario Time Jump c-oe c-02 I

SW Pumps P-7A OFF P-78 ON P-7C OFF (10) VCT Temp as. F ccw Pumps P-52A ON P-528 OFF P-52C STBY (10) VCT Pressure 38. psi FPC Pumps P-SlA OFF P-518 OFF (10) VCT Level 94.

-!- PCP Control Bleedoff Pressure (26) Letdown Flow 150 psig

32. gpm CONTAINMENT COOLE~ RECIRC FANS (26) charging Flow 40. gpm I

VIA OFF V2A OFF V3A OFF V4A ON (9) Quench Tank Temp 102 F Vl8 OFF V28 QFF V38 ON V48 ON (9) Quench TANK Pressure -2. psig (9) Quench TANK Level 65.

C-03 (7) Pressurizer Pressure (R) '

249. psia (8) PZR Level (R) LT0102A 97. '

(23) HPSI Pumps P-66A OFF P-668 OFF LT0103 96.6 '

(25) LPSI Pumps P-67A OFF P-678 ON (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, LPSIATS'PRAY A SUCTION P55A OFF P55B OFF P55C ON CV-3057 (SIRWT) CV-3030 (Sump) (6) PCPS P50A OFF PSOB ON P50C ON P50D OFF I

CLOSED CLOSED PZR HTR AMPS LClS O. LCC 16 o.

(1) PCS TAVE (R) LOOP! (TR-0111) 119' F I! C-02 ( 2 5) REACTOR POWER LEVEL LOOP2 (TR-0121) 119 F NU .18E+02 cps NI3 .82E-08 NI7 .12E-07 I

I Intermediate Press Letdown Temp 98. F NI2 .1BE+02 cps NI4 .BOE-OB NIB .12E-07 I

Charging Line Tem~erature 91. F NI-05 .12E-07 NI-09 '

105 F NI-06

llE-07 NI-10 Letdown Line Temp i socs from PCS (R) 120 F '

SOCS to PCS (R) 73. F PIP (DEMAND LOG+CONSTANT, ROD, OR FLUX/TEMP)

Gross MW o.

Net MW O.

(28) Control Rod Position GPl O. GP2 0. GP3 O. GP4 .O GP6(A) ~ GP7(8) O.

Stuck Rods NONE <optional># .Q

,;-.;;.;:"'* Exit Temp :.?.G. !')'.".'

SHAVPALl T S C S T A T U S PAGE

PALEX 93 Time 0845 Scenario Time 0015 Message # ~ 140 Time Jump Scenario Time Jump C-13 c-12 PCP Current (Amps)

Condensate Storage Tank Level T-2 89. % P-50A o. P-508 667 Instrument Air Pr~ssure 100 psig P-50C 678 P-50D O.

(15) Containment Building Pressure -5. psig (6) PCS Flow (16) S/G A Compartment Temperature 102 F (3) That (F) Loop 1 120 F S/G A COMPARTMENT Humidity 30. % Loop 2 120 F (16) S/G B Compartment Temperature 93. F (2) Tcold (F) Loop lA 119 F S/G 8 Humidi~y 30. % Loop 2A 120 F (16) Dome Temperature 102 F Loop 18 120 F (11) SIRW Tank Level o. ' Loop 28 119 F (15) WR containment Pressure (R) 9. psia (5) Subcooling 281 F 247 PSIA.

(14) Containment Sump Level 585 ' (7) PCS WR Pressure (R) 249. PSIA (14) Containment Water Level (R) o. ' (7) PCS NR Pressure (R) 249. PSIA (22) SI Tank Level (%) (30) S/G A LEVEL WR 90.

A 40. 1 8 39. C 39. D 39. (30) S/G A LEVEL (R) 90.

SI Tank Pressure (psig) (30) S/G A PRESS 1. psia A 149 B 149 C 149 D 150 S/G A STM FLW (R) .o Xl0**6 PPH (21) SIAS Alarm NO S/G A FD FLW (R) .o Xl0**6 PPH (30) S/G 8 LEVEL WR 87. %

c-12 (30) S/G 8 LEVEL (R) 87.

(30) S/G 8 PRESS "

13. psia Concentrated 'Boric Acid Tank Levels S/G 8 STM FLW (R) .o Xl0**6 PPH T53A 100. S/G 8 FD FLW (R) .o Xl0**6 T538 10.6 PPH Reactor Vessel DP 16.8 paid PANEL K-13 (12) PORV Discharge Temperature 112 F (13) Pzr Safety V~lve Discharge Temp (F) (20) CONTAINMENT HIGH PRESS RV-1039 127 F NO RV-1040 142 F RV-1041 177 F (20) Containment High Radiation NO

SHAVPALl PALEX 93 T S C S T A T U S PAGE Time 0845 Scenario Time 0015 Message # 6 141 Time Jump Scenario Time Jump c-01 C-04 MFP Suction Pressure 15. psig (32) D/G Freq 1-1 60. 1-2 .o I

MFP A Discharge Pressure 15. psig (32) 1-C BUS VOLTS 2433 Amps494 I

MFP B Discharge Pressure 15. psig (32) 1-D BUS VOLTS 2482 Amps45.

I AFW Pump P-8C Amperes I

o. AMPS ,_

AFW Discharge Pre~sure P-8C 18. psig C-11 BACJ.t C-llA AFW Pump P-8A Amperes I

o. AMPS AFW Pump P-8B Steam Pressure I

o. psig (17) Containment Area Monitors AFW Discharge Pressure P-8A & P-8B 18. psig RIA-1805 .2E-01 R/Hr Moisture SEP Drai~ Tank Level 26. RIA-1806 .2E-01 R/Hr Condenser Hotwell(Level 70. ' RIA-1807 .2 R/Hr Condenser Vacuum i .o ' in Hg. RIA-1808 .8E-01 R/Hr Gland Seal Condenser Vacuum 14.2 in Hg. (17) High Range Containment Monitors I

Atmospheric Dump Valves CLOSED RIA-2321 .lE-01 R/Hr I

AFW Pump P-BA OFF P-8B OFF P-8C OFF RIA-2322 .lE-01 R/Hr Heater Drain Pump P-lOA OFF P-lOB OFF (19) Containment Hydrogen Concentration Condensate Pump P-2A OFF P-2B OFF AI-2401R o.

AI-2401L o. '

C-11 (30) Main Steam Line Gamma '

II RIA-2324 .3E+02 CPM (31) AFW FLOW TO SGA I

RIA-2323 ~2E+02 CPM FROM P8A, B o. From P-8C O. gpm (31) AFW FLOW TO SGBI EQUIPMENT STATUS:

FROM P-8A&B 0. From P-8C o. gpm Condenser Vacuum I

(R) o. IN HG. 1. SIGNIFICANT EQUIP OUTAGES PCP A Leak-off I Flow (R) 1.0 (INOPERABLE EQUIPMENT)

PCP B Leak-off Flow (R) 1.0 2. SURVEILLANCE DUE/PROGRESS I

PCP c Leak-off I Flow (R) 1.0 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off Flow (R) 1.0 OR OUTAGES

SHAVPALl PALEX 93 T S C S T A T U S PAGE Time 0845 \ Scenario Time 0015 Message # §. 142 Time Jump Scenario Time Jump I

I c-oe c-02 1

i SW Pumps P-7A ON P-7B ON P-7C STBY (10) VCT Temp 85. F ccw Pumps P-52A ON P-52B ON P-52C STBY (10) VCT Pressure 38. psi FPC Pumps P-51A OFF P-51B OFF (10) VCT Level 94.

-!- PCP Control Bleedof f Pressure (26) Letdown Flow 150 psig

32. gprn CONTAINMENT COOLE' RECIRC FANS (26) Charging Flow 40. gpm i

VlA OFF V2A OFF V3A OFF V4A ON (9) Quench Tank Temp 102 F VlB OFF V2B OFF V3B ON V4B ON (9) Quench TANK Pressure -2. psig (9) Quench TANK Level 65.

C-03 (7) Pressurizer Pressure (R)

(8) PZR Level (R). LT0102A 249. psia

97. '

(23) HPSI Pumps P-66A OFF P-66B OFF LT0103 96.6 '

(25) LPSI Pumps P-67A OFF P-67B ON (12) PORV PRV-1042A CLOSED 10438 CLOSED 1

(18) Containment Spray Pumps (12) BLOCK MOV-1042A OPEN 1043A OPEN P-54A OFF P-548 OFF P-54C OFF CHARGING PUMPS (27) HPSIA, LPSIAI"SPRAY A SUCTION P55A ON P55B OFF P55C OFF CV-3057 I (SIRWT) CV-3030 (Sump) (6) PCPS P50A OFF P50B ON P50C ON P50D OFF CLOSED CLOSED PZR HTR AMPS LC15 O. LCC 16 0.

I (1) PCS TAVE (R) LOOP! (TR-0111) 119 F I

LOOP2 (TR-0121) 119 F c-02 (25) REACTOR POWER LEVEL Nil .18E+02 cps NI3 .82E-08 NI7 .12E-07 Intermediate Pres~ Letdown Temp 98. F NI2 .18E+02 cps NI4 .SOE-08 NIB .12E-07

Charging Line Tem~erature 91. F NI-05 .12E-07 NI-09 Letdown Line Temp ] 105 F NI-06

llE-07 NI-10 socs from PCS (R) 120 F SOCS to PCS (R) 73. F PIP (DEMAND LOG+CONSTANT, ROD, OR FLUX/TEMP)

Gross MW o.

Net* MW o.

(28) Control Rod Position GP! O. GP2 O. GP3 O. GP4 .O GP6(A) ~ GP7(B) 0.

Stuck Rods NONE <optional># Q Core Exit Temp 120.0F

SHAVPALl T S C S T A T U S PAGE

PALEX 93 Time 0900 Scenario Time 0030 Message # 7 140 Time Jump i Scenario Time Jump I C-13 1-- c-12 1 PCP Current (Amps)

Condensate Storagei Tank Level T-2 89. % P-50A O. P-508 667 Instrument Air Pre ssure 1

100 psig P-50C 678 P-50D 0.

( 15) Containment B,uilding Pressure -5. psig (6) PCS Flow (16) S/G A Compart~ent Temperature 102 F (3) Thot (F) Loop 1 120 F S/G A COMPARTMENT Humidity 30. % Loop 2 120 F (16) S/G B compartmentI Temperature 93. F (2) Tcold (F) Loop lA 119 F S/G B Humidit~y 30. % Loop 2A 120 F I

( 16) Dome Temperat ure 102 F Loop 18 120 F o.

1 (11) SIRW Tank Le~el % Loop 28 119 F (15) WR containment Pressure (R) 9. psia (5) Subcooling 281 F 247 PSIA *.

(14) Containment s'.ump Level 585 % (7) PCS WR Pressure (R) 249. PSIA (14) Containment ~ater Level (R) o. % (7) PCS NR Pressure (R) 249. PSIA (22) SI Tank Leve~ (%) (30) S/G A LEVEL WR 90. %

A 40. i B 39. c 39. D 39. (30) S/G A LEVEL (R) 90. %

SI Tank Pres~ure (psig) (30) S/G A PRESS 1. psia A 149 !I B 149 c 149 D 150 S/G A STM FLW (R) .o Xl0**6 PPH (21) SIAS Alarm NO S/G A FD FLW (R) .o Xl0**6 PPQ I c-12 (30) S/G B LEVEL WR 87. %

(30) S/G B LEVEL (R) 87. %

I (30) S/G B PRESS 13. psia Concentrated !Boric Acid Tank Levels S/G B STM FLW (R) .o Xl0**6 PPH T53A 100. % S/G B FD FLW (R) .o Xl0**6 PPH T53B I 10.6 %

I Reactor Vessel DP 16.8 paid PANEL K-13 I

(12) PORV Discharge Temperature 112 F I

(13) Pzr Safety V~lve Discharge Temp (F) (20) CONTAINMENT HIGH PRESS RV-1039 / 127 F NO RV-1040 I 142 F RV-1041 I 177 F (20) Containment High Radiation NO

SHAVPALl PALEX 98 T S C S T A T U S PAGE Time 0900 Scenario Time 0030 Message # 7 141 Time Jump Scenario Time Jump c-01 C-04 MFP Suction Pressure 15. psig (32) D/G Freq 1-1 60. 1-2 .o MFP A Discharge Pressure 15. psig (32) 1-C BUS VOLTS 2433 Amps494 MFP B Discharge Pressure 15. psig (32) 1-D BUS VOLTS 2482 Amps45.

AFW Pump P-8c Amperes o. AMPS AFW Discharge Pres.sure P-8C 18. psig C-11 BAClt C-llA AFW Pump P-8A Amperes o. AMPS AFW Pump P-8B Steam Pressure o. psig (17) Containment Area Monitors AFW Discharge Pres,sure P-8A & P-8B 18. psig RIA-1805 .2E-Ol R/Hr Moisture SEP Drain Tank Level 26. % RIA-1806 .2E-Ol R/Hr Condensor Hotwell Level 70. % RIA-1807 .2 R/Hr Condensor Vacuum .o in Hg. RIA-1808 .8E-01 R/Hr Gland Seal Condensor Vacuum 14.2 in Hg. (17) High Range Containment Monitors Atmospheric Dump Valves CLOSED RIA-2321 .lE-01 R/Hr AFW Pump P-8A OFF P-8B OFF P-8C OFF RIA-2322 .lE-01 R/Hr Heater Drain Pump* P-lOA OFF P-lOB OFF (19) Containment Hydrogen Concentration I

Condensate Pump P-2A OFF P-2B OFF AI-2401R o. %

AI-2401L o. %

C-11 (30) Main Steam Line Gamma RIA-2324 .3E+02 CPM (31) AFW FLOW TO SGA RIA-2323 ~2E+02 CPM FROM P8A, B o. From P-8C O. gpm (31) AFW FLOW TO SGB EQUIPMENT STATUS:

FROM P-8A&B O. From P-8C 0. gpm Condensor Vacuum (R) o. IN HG. 1. SIGNIFICANT EQUIP OUTAGES PCP A Leak-off Flow (R) 1.0 (INOPERABLE EQUIPMENT)

PCP B Leak-off Flow (R) 1.0 2. SURVEILLANCE DUE/PROGRESS PCP c Leak-off Flow (R) 1.0 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off Flow (R) 1.0 OR OUTAGES

SHAVPALl PALEX 9?>

T S C S T A T U S PAGE Time 0900 I Scenario Time 0030 Message # z 142 Time Jump I Scenario Time Jump I

I

c-oa 1--

c-02 i

SW Pumps P-7A ONI P-78 ON P-7C ST8Y (10) VCT Temp 85. F

-1 CCW Pumps P-52A ON/ P-528 ON P-52C ST8Y (10) VCT Pressure 38. psi FPC Pumps P-51A OFF P-518 OFF (10) VCT Level 94.

PCP Control 8leedof f Pressure '

150 psig CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow* 32. gpm I

I (26) Charging Flow 40. gpm I

VlA OFF V2A OFF V3A OFF V4A ON (9) Quench Tank Temp 102 F Vl8 OFF V28 OF*F V38 ON V48 ON (9) Quench TANK Pressure -2. psig

-, (9) Quench TANK Level 65.

C-03 (7) Pressurizer Pressure (R) '

249. psia (8) PZR Level (R) LT0102A 97.

(23) HPSI Pumps P-66A OFF P-668 OFF LT0103 96.6

(25) LPSI Pumps I1 P-67A OFF P-678 ON (12) PORV PRV-1042A CLOSED 10438 CLOSED (18) Containment Spray I

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 OFF P55C OFF CV-3057 (SIRWT) cv-3030 (Sump) (6) PCPS P50A OFF P508 ON P50C ON P50D OFF I

CLOSED CLOSED PZR HTR AMPS LC15 O. LCC 16 O.

(1) PCS TAVE (R) LOOPl (TR-0111) 119 F II c-02 LOOP2 (TR-0121)

(25) REACTOR POWER LEVEL 119 F I

Nil .18E+02 cps NI3 .82E-08 I

Intermediate Press;Letdown Temp 98. F NI2 .18E+02 cps NI4 .BOE-08 NI7 .12E-07 NIB .12E-07

Charging Line Temperature 91. F NI-05 .12E-07 NI-09 Letdown Line Temp I

1 105 F NI-06

llE-07 NI-10 socs from PCS (R) 120 F SOCS to PCS (R) 73. F PIP (DEMAND LOG+CONSTANT, ROD, OR FLUX/TEMP)

Gross MW 0.

Net MW O.

(28) Control Rod Position GPl O. GP2 O. GP3 O. GP4 .0 GP6(A) ~ GP7(8) O.

Stuck Rods NONE <optional># .Q 120.0F

SHAVPALl T S C S T A T U S PAGE

PALEX 9,3 Time 0905 Scenario Time 0035 Message # 8 140 Time Jump Scenario Time Jump c-13 c-12 PCP Current (Amps)

Condensate Storage Tank Level T-2 89. P-50A o. P-50B 667 Instrument Air Pressure 100 'psig P-SOC 678 P-50D O.

(15) Containment Building Pressure -5. psig ( 6) PCS Flow (16) S/G A Compartment Temperature 102 F (3) That (F) Loop 1 120 F S/G A COMPARTMENT Humidity 30. % Loop 2 120 F (16) S/G B Compartment Temperature 93. F (2) Tcold (F) Loop lA 119 F S/G B Humidity 30. % Loop 2A 120 F (16) Dome Temperature 102 F Loop lB 120 F

( 11) SIRW Tank Level o. % Loop 2B 119 F (15) WR Containment Pressure (R) 9. psia (5) Subcooling 281 F 247 PSIA*

(14) containment Sump Level 585 % (7) PCS WR Pressure (R) 249. PSIA (14) Containment Water Level (R) o. % (7) PCS NR Pressure (R) 249. PSIA (22) SI Tank Level'(%) (30) S/G A LEVEL WR 90.

A 40. *B 39.

SI Tank Pressure (psig)

A 149 B 149 C 39.

C 149 D 39.

D 150 (30)

(30)

S/G A LEVEL (R)

S/G A PRESS S/G A STM FLW (R) 90.

1.

psia

.o Xl0**6 PPH (21) SIAS Alarm NO S/G A FD FLW (R) .o Xl0**6 PPH (30) S/G B LEVEL WR 87.

c-12 (30) S/G B LEVEL (R) 87. % '

(30) S/G B PRESS 13. psia Concentrated Boric Acid Tank Levels S/G B STM FLW (R) .o Xl0**6 PPH T53A 100. % S/G B FD FLW (R) .o Xl0**6 PPH T53B 10. 6 %

Reactor Vessel DP 16.8 paid PANEL K-13 (12) PORV Discharge Temperature 112 F

( 13) Pzr Safety Va lve Discharge Temp (F) 1 (20) CONTAINMENT HIGH PRESS RV-1039 127 F NO RV-1040 142 F RV-1041 177 F (20) Containment High Radiation NO

SHAVPALl PALEX 93 T S C S T A T U S P A G E Time 0905 Scenario Time 0035 Message # 8 141 Time Jump Scenario Time Jump c-01 c-04 MFP Suction Pressure 15. psig (32) D/G Freq 1-1 60. 1-2 .o MFP A Discharge Pressure 15. psig (32) 1-C BUS VOLTS 2433 Amps494 MFP B Discharge Pressure 15. psig (32) 1-D BUS VOLTS 2482 Amps45.

AFW Pump P-8c Amperes o. AMPS *,

AFW Discharge Pressure P-8C 18. 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 Pres~ure P-8A & P-8B 18. psig RIA-1805 .2E-01 R/Hr Moisture SEP Drain,Tank Level 26. RIA-1806 .2E-01 R/Hr Condenser Hotwell Level 70. RIA-1807 .2 R/Hr Condenser Vacuum .o in Hg. RIA-1808 .BE-01 R/Hr Gland Seal Condenser Vacuum 14.2 in Hg. (17) High Range Containment Monitors Atmospheric Dump Valves CLOSED RIA-2321 .lE-01 R/Hr AFW Pump P-8A OFF P-8B OFF P-8C OFF RIA-2322 .lE-01 R/Hr Heater Drain Pump ' P-lOA OFF P-lOB OFF (19) Containment Hydrogen Concentration Condensate Pump P-2A OFF P-2B OFF AI-2401R o.

AI-2401L o. '

c-11 (30) Main steam Line Gamma '

RIA-2324 .3E+02 CPM (31) AFW FLOW TO SGA RIA-2323 ~2E+02 CPM FROM P8A, B o. From P-8C O. gpm (31) AFW FLOW TO ~GB EQUIPMENT STATUS:

FROM P-8A&B o. From P-8C o. gpm Condenser Vacuum (R) O. IN HG. 1. SIGNIFICANT EQUIP OUTAGES PCP A Leak-off Flow (R) 1.0 (INOPERABLE EQUIPMENT)

PCP B Leak-off Flow (R) 1.0 2. SURVEILLANCE DUE/PROGRESS PCP c Leak-off Flow (R) 1.0 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off Flow (R) 1.0 OR OUTAGES

SHAVPALl PALEX 93 T S C S T A T U S P A G E Time 0905 scenario Time 0035 Message # B 142 Time Jump Scenario Time Jump C-08 c-02 SW Pumps P-7A ON P-78 ON P-7C ST8Y (10) VCT Temp B5. F CCW Pumps P-52A ON P-528 ON P-52C ST8Y (10) VCT Pressure 3B. psi FPC Pumps P-51A OFF P-518 OFF (10) VCT Level 94. '

PCP Control Bleedoff Pressure 150 psig CONTAINMENT COOLER RECIRC FANS (26) Letdown Flow 32. gpm (26) Charging Flow 40. gpm VlA OFF V2A OFF V3A OFF V4A ON (9) Quench Tank Temp 102 F Vl8 OFF .V28 OFF V38 ON V4B ON (9) Quench TANK Pressure -2. psig (9) Quench TANK Level 65. '

c-03 (7) Pressurizer Pressure (R) 249. psia (B) PZR Level (R). LT0102A 97. '

(23) HPSI Pumps P-66A OFF P-668 OFF LT0103 96.6 '

(25) LPSI Pumps P-67A OFF P-678 ON (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, LPSIA,, SPRAY A SUCTION P55A ON P55B OFF P55C OFF CV-3057 (SIRWT) CV-3030 (Sump) (6) PCPS P50A OFF P50B ON P50C ON P50D OFF CLOSED CLOSED PZR HTR AMPS LClS O. LCC 16 O.

(l) PCS TAVE (R) LOOP! (TR-0111) 119 F LOOP2 (TR-0121) 119 F c-02 (25) REACTOR POWER LEVEL NU .1BE+02 cps NI3 .B2E-OB NI7 .12E-07 Intermediate Press Letdown Temp 9B. F NI2 .1BE+02 cps NI4 .BOE-OB NIB .12E-07 '

Charging Line Temp,erature 91. F NI-05 .12E-07 NI-09 '

Letdown Line Temp 105 F NI-06

llE-07 ' NI-10 SCCS from PCS (R) 120 F '

SCCS to PCS (R) 73. F PIP (DEMAND LOG+CONSTANT, ROD, OR FLUX/TEMP)

Gross MW 0.

Net MW 0.

(2B) Control Rod Position GPl 0. GP2 0. GP3 O. GP4 .O GP6(A) 2.!_ GP7(B) 0.

Stuck Rods NONE <optionai># 0 Core Exit Temp 120.0F

SHAVPALl T S C S T A T U S PAGE

PALEX 9.:!9 Time 0915 Scenario Time 0045 Message # 9 140 Time Jump Scenario Time Jump I

lc-13 c-12 1-- PCP Current (Amps)

I Condensate Storage !Tank Level T-2 89. \ P-50A O. P-508 667 Instrument Air Pre~sure 100 psig P-50C 678 P-500 O.

I ~-

( l 5) Containment B~ilding Pressure -5. psig (6) PCS Flow (16) S/G A Compartment Temperature 102 F (3) Thot (F) Loop 1 120 F I ~-

S / G A COMPARTMENT Humidity 30. \ Loop 2 120 F I

(16) S/G B Compartment Temperature 93. F (2) Tcold (F) Loop lA 119 F S/G B Humidit~ 30. Loop 2A 120 F (16) Dome Temperatpre 102 '

F Loop 18 120 F (11) SIRW Tank Level I

o. Loop 28 119 F (15) WR Containmen~ Pressure (R) 9. psia (5) Subcooling 281 F 247 PSIA*

( 14) Containment S ump Level 585 (7) PCS WR Pressure (R) 249. PSIA 1

(14) Containment ~ater Level (R) o. ' (7) PCS NR Pressure (R) 249. PSIA (22) SI Tank Leve~ (\) ' (30) S/G A LEVEL WR 90. '

A 40. : B 39. c 39. D 39. (30) S/G A LEVEL (R) 90. '

SI Tank Pres~ure (psig) (30) S/G A PRESS 1. psia A 149 I B 149 c 149 D 150 S/G A STM FLW (R)

S/G A FD FLW (R)

.O

.O Xl0**6 PPH Xl0**6 PP~

(21) SIAS Alarm NO I (30) S/G B LEVEL WR 87. '

I c-12 (30) S/G B LEVEL (R) 87. '

I (30) S/G B PRESS 13. psia Concentrated/Boric Acid Tank Levels S/G B STM FLW (R) .0 Xl0**6 PPH T53A I 100. ' S/G B FD FLW (R) .O Xl0**6 PPH T53B 10.6 \

Reactor Vessel DP 16.8 paid PARBL lt-13 I

(12) PORV Dischar~e Temperature 112 F (13) Pzr Safety V.alve Discharge Temp (F) (20) CONTAINMENT HIGH PRESS RV-1039[ 127 F NO RV-1049 142 F RV-1041! 177 F (20) Containment High Radiation NO

SHAVPALl PALEX 93 T S C S T A T U S PAGE Time 0915 Scenario Time 0045 Message # 9 141 Time Jump Scenario Time Jump C-01 c-04 MFP Suction Pressure 15. psig (32) D/G Freq 1-1 60. 1-2 .o MFP A Discharge Pressure 15. psig (32) 1-C BUS VOLTS 2433 Amps494 MFP B Discharge Piessure 15. psig (32) 1-D BUS VOLTS 2482 Amps45.

AFW Pump P-8C Amperes o. AMPS AFW Discharge Pressure P-8C 18. psig C-11 BACK C-llA AFW Pump P-8A Ampe~es o. AMPS AFW Pump P-88 Steam Pressure o. psig (17) Containment Area Monitors AFW Discharge Pressure P-8A & P-8B 18. psig RIA-1805 .2E-01 R/Hr Moisture SEP Drain.Tank Level 26. % RIA-1806 .2E-01 R/Hr Condenser Hotwell Level 70. % RIA-1807 .2 R/Hr Condenser Vacuum .o in Hg. RIA-1808 .8E-01 R/Hr Gland Seal Condens9r Vacuum 14.2 in Hg. (17) High Range Containment Monitors Atmospheric Dump Valves CLOSED RIA-2321 .lE-01 R/Hr AFW Pump P-8A OFF P-8B OFF P-8C OFF RIA-2322 .lE-01 R/Hr Heater Drain Pump P-lOA OFF P-lOB OFF (19) Containment Hydrogen Concentration Condensate Pump P-2A OFF P-2B OFF AI-2401R o. %

AI-2401L o. %

C-11 (30) Main Steam Line Gamma RIA-2324 .3E+02 CPM (31) AFW FLOW TO SGA RIA-2323 ** 2E+02 CPM FROM P8A, B ~ From P-8C O. gpm (31) AFW FLOW TO SGB EQUIPMENT STATUS:

FROM P-8A&B O. From P-8C o. gpm Condensor Vacuum (R) o. IN HG. 1. SIGNIFICANT EQUIP OUTAGES PCP A Leak-off Flow (R) 1.0 (INOPERABLE EQUIPMENT)

PCP B Leak-off Flow (R) 1.0 2. SURVEILLANCE DUE/PROGRESS PCP c Leak-off Flow (R) 1.0 3. ABNORMAL ELECTRICAL LINEUPS PCP D Leak-off Flow (R) 1.0 OR OUTAGES

SHAVPALl PALEX 93 T S C S T A T U S PAGE Time 0915 Scenario Time 0045 Message # 9 142 Time Jump Scenario Time Jump C-08 C-02 I

SW Pumps P-7A ON P-78 ON P-7C ST8Y (10) VCT Temp 85. F CCW Pumps P-52A ON P-528 ON P-52C ST8Y (10) VCT Pressure 38. psi FPC Pumps P-51A QFF P-518 OFF (10) VCT Level 94.

-I-I CONTAINMENT COOLER RECIRC FANS PCP Control Bleedoff Pressure (26) Letdown Flow 150 psig

32. gpm I

(26) Charging Flow 40. gpm VlA OFF V2A dFF V3A OFF V4A ON (9) Quench Tank Temp 102 F Vl8 OFF V28 OFF V38 ON V48 ON (9) Quench TANK Pressure -2. psig (9) Quench TANK Level 65.

c-03 (7) Pressurizer Pressure (R) '

249. psia

( 8) PZR Level (R). LT0102A 97. '

(23) HPSI Pumps P-66A OFF P-668 OFF LT0103 96.6 '

(25) LPSI Pumps P-67A OFF P-678 ON (12) PORV PRV-1042A CLOSED 10438 CLOSED (18) Containment ~pray Pumps (12) BLOCK MOV-1042A OPEN 1043A OPEN P-54A OFF P-548 OFF P-54C OFF CHARGING PUMPS (27) HPSIA, LPSIAT"S'PRAY A SUCTION P55A ON P558 OFF P55C OFF CV-3057 i

(SIRWT) CV-3030 (Sump)

ML18059A523

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