Text

Forwards Scenario for 870519 Facility Emergency Plan Exercise,Per Util 870403 Commitment
	ML20214L755
Person / Time
Site:	Palisades
Issue date:	05/26/1987
From:	Johnson B; CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	; NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
	NUDOCS 8706010071
	Download: ML20214L755 (102)
	v • d • e

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@nnesanus Consumers Power AMEANNAAr5 MISsAE55 oeneral of fices: 1946 West Pernell Road, Jackson, MI 49201 e (517) 788 0550 May 26, 1987 Nuclear Regulatory Commission Document Control Desk Washington, DC. 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT -

EMERCENCY PLAN EXERCISE SCENARIO SUBMITTAL The scenario used for the Palisades Plant exercise conducted May 19, 1987 is attached. This submittal fulfills our commitment made in our April 3, 1987 letter to submit a copy of the scenario after completion of the exercise.

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1.0 SCOPE AND OBJECTIVES 1.1 1.1 SCOPE 1.1 1.2 OBJECTIVES 1.1 2.0 EXERCISE CONDUCT 2.1 2.1 EXERCISE ORGANIZATION 2.1 2.2 CONTROLLER ORGANIZATION 2.1 2.3 EXERCISE DATA AND MESSAGES 2.2 2.4 EXERCISE GROUND RULES 2.2 2.5 CRITIQUE 2.3 2.6 EVALUATOR CHECKLISTS 2.4 3.0 SEQUENCE OF EVENTS 3.1 Appendix A - Messages and Plant Parameter Sheets Appendix B - Meteorological Data Appendix C - Rad Monitor Data Appendix D - Resin Spill and Red Levels O

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O 1.0 SCOPE AND OBJECTIVES 1.1 SCOPE PAI.EX 87 is designed to meet exercise requirements specified in 10 CFR 50, Appendix E, Section IV.F.

It will postulate events which would require activation of major portions of the site emergency plan and response by offsite authorities. The exercise will be utility only. There will be no participation from state or local authorities. The Joint Public Information Center will not be activated.

1.2 OBJECTIVES The exercise will demonstrate each item listed under the following categories:

1.

Assessment and Classification a.

Recognition of emergency conditions b.

Timely classification of emergency conditions in accordance with emergency action levels 2.

Communication O

a.

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

Subsequent notification in accordance with procedure (state, local NRC) c.

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

Provision of accurate and timely information to support news release activity 3.

Radioloatcal Assessment and Control a.

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

Performance of in plant and offsite field surveys c.

Objective deleted d.

Trending of radiological data j

e.

Formulation of appropriate protective action recommendations f.

Contamination and exposure control i

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O 4.

Emergency Response Facilities a.

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

Adequacy of emergency equipment and supplies c.

Adequacy of emergency communication systems d.

Access control 5.

Emergency Management a.

Command and control with transfer of responsibilities from Control Room to Technical Support Center to Emergency Operations Facility b.

Assembly and accountability within 30 minutes c.

Coordination with State of Michigan emergency organization

-d.

Mitigation of operational and radiological conditions e.

Mobilization of emergency teams 6.

Reentry and Recovery a.

Assessment of damage and formulation of recovery plan b.

Identification of constraints, requirements and organization to implement the plan 7.

Exercise Control a.

Provision for maximum free play b.

Accurate assessment of player performance O

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O 2.0 EXERCISE CONDUCT 2.1 EXERCISE ORGANIZATION The exercise organization is comprised of Controllers, Evaluators, Players and Observers, all of whom are issued armbands for identification.

Controllers are responsible for providing messages and data to Players.

They also ensure that exercise activity progresses as planned. Con-trollers are authorized to modify scenario data and provide clarification to Players as judged appropriate. They must not, however, prompt Players unless the exercise or plant operation is jeopardized by inappropriate Player response.

If a Player must be prompted, it must be brought to the attention of the Lead Facility Controller or, Exercise Coordinator and prior to doing so if possible. Controllers may also serve as Evaluators.

Evaluators observe Player activity and judge effectiveness of response.

Consumers Power Company Evaluators are required to submit signed Evaluator Checklists'to their Lead Facility Controller. NRC and other utilities' evaluators will be present for exercises.

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

Observers are not allowed to speak to players during the course of the exercise.

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Players include all personnel responding to simulated exercise conditions.

2.2 CONTROLLER ORGANIZATION

The Exercise Coordinator is in charge of overall exercise conduct.

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

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

Controllers and Evaluators will refer all Player inquiries to the Lead Facility Controller.

If unable to resolve a question, the Lead Facility Controller will refer the query to the Exercise Coordinator.

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

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X 2.3 EXERCISE DATA AND MESSAGES Messages and data to drive Player response are contained in the following appendices:

A.

Messages and Plant Parameter Sheets B.

Meteorological Data C.

Rad Monitor Data D.

Resin Spill and Rad Levels Information not to be distributed to players is marked " Controller Use Only." It is ultimately each Controller's responsibility to ensure that only appropriate information is distributed to Players.

2.4 EXERCISE GROUND RULES 1.

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

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

action, tell the Controller / Evaluator how it would be performed.

2.

Periodically speak out loud, identifying your key actions and decisions to the Controller /Eva.luators. This may seem artificial, but it will assist in the evaluation process. If you are in doubt, i

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

1 3.

Know the overall Controller organization. Identify yo'c Controller and NRC evaluators. Controllers may also be Evaluators.

4.

The Controller periodically will issue messages or instructions designed to initiate response actions. Messages must be accepted immediately. They are essential to successful performance.

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If the Controller intervenes, obey the Controller's directions.

This is essential to the overall success of the exercise. If you disagree with your Controller, you can ask him to reconsider. You must, however, accept his/her word as final and proceed. Respond to Controller's questions.

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You must play as if radiation levels actually are present, in accordance with the information you have received. This may require that you wear dosimeters, anti-Cs, observe good radiation protection practices, and be aware of and minimize your radiation exposure.

Identify the individuals in your emergency response organization responsible for informing you of these items. Follow their instructions.

I 7.

If= you are entering normal nuclear station radiation areas, observe all rules and procedures. No one (not even the Controller / Evaluator) is exempt-from normal station radiological practices and procedures.

8.

Demonstrate knowledge of emergency operations and procedures.

I, Utilize status boards, logbooks, and message forms, as much as possible, to' document and record your actions, instructions and reports to your CO-Players.

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9.

Do not enter into conversations unrelated to the drill with other Players. You may answer questions directed to you by Federal i

Evaluators. If the question is misdirected to you or you do not know the answer, refer them to the team leader or the Controller.

l O'. Keep a list of items for improvement. Provide this to your team leader. Team leaders will ensure these are considered.

If necessary, they will identify them to the Controller during the critique which 7-~s

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follows the drill / exercise. Areas for improvement or lessons g

learned, when identified, will improve overall emergency preparedness.

2.5 CRITIQUE Following termir.ation of the e'xercise, facility critiques will be con-

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ducted by Lead Facility Controllers.

j' ' t A joint critique will be conducted following facility critiques. Lead Facility Controllers will present overall observations made at facilit'y critiques.

Following the joint critique, a joint NRC/CP Co critique will be con-3~

ducted. Focus of CP Co comments will be on items judged to be of greater significance. Items of lesser importance cited at facility and joint critiques will be addressed but may not be discussed at the NRC/CP Co l

critique. Comments will be made by:

1.

ExerciseCoordinathr 2.

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Site Emergency Director / Plant Manager 4.

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The Nuclear Emergency Planning Administrator is responsible for evalua-tion, assignment, completion and documcutation of all critique comments.

2.6 EVALUATOR CHECKLISTS The checklists provided in Section 2.6.1 through 2.6.9 are to be used in judging Player and Controller ability to meet stated ' exercise objectives.

These facility specific checklists cross-reference all applicable exercise objectives and prior exercise weaknesses. In sum, they serve as the basis of exercise evaluation and documentation.

Each Evaluator shall submit to the Exercise Coordinator a completed, signed, and dated checklist at the conclusion of the exercise.

Items marked " inadequate" shall be fully explained in the " comments" section.

Comments continuation sheets are provided in Section 2.6.9.

Lead Facility Controllers will conduct critiques using these checklists as guides.

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2.6.1 Control Room Evaluator Checklist b

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i Objective Adequate Inadequate

1A Recognition of emergency conditions 1B Timely classification of emergency conditions

~2A Notification of State and local governments within 15 minutes and NRC within one hour

21B Subsequent notification in accordance with procedure (state, local, NRC) 2C Notification and coordination for offsite assistance (fire, medical) l 3F Contamination and exposure co'ntrol

-4A Not'ification of OSC and TSC staff to activate at alert classification 14B Adequacy of equipment and supplies h

14C Adequacy of communications equipment

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5A Command and control with clear transfer of responsibility from Control Room to TSC SD Mitigation of hypothetical operational problems i

SE Mobilization of emergency teams 6A Assessment of damage 6B Identification of reentry / recovery restraints

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mark N/A (not applicable).

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3F Contamination and exposure control 4A Activated at alert classification 4B Adequacy of equipment and supplies 4C Adequacy of communications 4D Access control SA. Transfer of offsite RMT control to E0P SD Mitigation of hypothetical operational conditions SE Mobilization of teams at appropriate times Comments:

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3B Performance of in plant field surveys 3F Contamination and exposure control 4A Activation at alert classification 4B Adequacy of equipment and supplies 4C Adequacy of communications SE Mobilized at appropriate time Comments:

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Explain in detail items checked " inadequate" under comments. If not observed, mark N/A (not applicable).

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3B Performance of offsite field surveys 3F Contamination 'and exposure control 4A Activation at site area emergency classification 4B Adequacy of equipment and supplies 4C Adequacy of communications SA Transfer of control from OSC to EOF SE Mobilized at appropriate time Comments:

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3F Contamination and exposure control 4B Adequacy of emergency equipment and supplies 4C Adequacy of communications

-4D Access control of site,. Control Room, TSC, OSC, EOF and JPIC SB Assembly and accountability within 30 minutes SE Mobilization at appropriate time Comments:

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Explain in detail items checked " inadequate" under comments. If not observed, mark N/A (not applicable).

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Name:

Date:

4 Objective Adequate Inadequate

1A Recognition of emergency conditions 1B Timely classification of emergency conditions 2B Notification of State and NRC (and possibly locals) at 15-minute intervals or as mutually agreed 2C Notification and coordination with other organizations as required (fire, medical) 2D Provision of accurate and timely informa-tion to support press release activity 3A Calculation of dose protections based on sample results or monitor readings 3D Trending of radiogical data i

3E Formulation of appropriate protective action recommendatibus 3F. Contamination and' exposure control 4A Activation, staffing and operational within one-half hour of alert declaration 4B Adequacy of emergen~cy equipment and supplies 4C Adequacy of communications 4D Access control

b 5A Command and control with clear transfer of responsibilities from Control Room and to EOF 5B Assembly and accountability within 30 minutes i

Explain in detail items checked " inadequate" under comments.

If not observed, mark N/A (not applicable).

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2.6.6 -Technical Support Center Evaluator Checklist (Page 2)

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Objective Adequate Inadequate

SC Coordination with State of Michigan emergency organization SD Mitigation of operational and radiological conditions SE' Mobilization of emergency teams 6A Accessment of damage and formulation of recovery plan 6B Identification of contraints, requirements and organization to implement the recovery plan Comments:

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2.6.7 Emergency Operations Facility Evaluator Checklist 4

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Name:

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Objective Adequate Inadequate

1A Recognition of emergency conditions IB Timely classification of emergency conditions 2B Notification of State and NRC at 15-minute intervals or as mutually agreed 2C Notification and coordination with other organizations as required (other utilities, contractors, fire, medical sources).

2D Provision of accurate and timely informa-tion to support news release activity 3A Calculation of dose projections based on sample results or monitor readings 3D Trending of radiological data 3E Formulation of appropriate protective g-~)g

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action recommendations 3F Contamination and exposure control 4A Activated at site area emergency and operational within about an hour of declaration 4B Adequacy of emergency equipment and supplies 4C Adequacy of communications systems 4D Access control SA Command and control with clear transfer of responsibilities from TSC and OSC SC Coordination with State of Michigan emergency organization

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Explain in detail items checked " inadequate" under comments.

If not observed, mark N/A (not applicable).

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.m 2.6.7 Emergency Operations Facility Evaluator Checklist (Page 2)

Objective Adequate Inadequate

SD Mitigation of operational and radiological 4

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7A Provision for maximum free play 7B Accurate assessment of player performance Comments:

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3.0 SEQUENCE OF EVENTS Scenario Time Event

-0030 Initial conditions - Normal full power Buses 13 and 14 crosstied; buses 77 and 78 crosstied Equipment out of service: Control Rod Drive 36, Air Blast Breaker 25R8, boric acid Pump A and the post-accident sampling monitor A resin transfer is in progress.

Alarms: Control Rod Drive 26 seal leak off temperature and containment monitor RIA-1808 PCS leak rate as of 0736 on 5/19/87: 0.6 gpm unidentified, 0.28 gpm identified, 0.88 gpm total Further historical data will be provided by Controller if requested.

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0000 Exercise begins. A small plane crashes into the PM&MP building.

The north security fence is damaged.

0005 Damage assessment reveals that the plane was destroyed on impact; there is no fire. The plane was apparently unoccupied as no bodies are found. Security fence down nearby.

0015 An alert is classified based on aircraft crash on facility.

Accountability commenced.

The Auxiliary Operators conducting the resin transfer have stopped the pump as the cask is almost full. They depart the scene when accountability begins. The track alley door has been jammed open for several days.

Shortly after the departure of the Auxiliary Operators, the resia cask overflows due to depressurization of hoses. A resin spill is in progress.

0030 Resin spill causes alarm of volume reduction system radiation monitor. By now, the TSC and OSC are staffed. Word is received that the pilot of the plane had bailed out before the crash and has not been injured.

0040 Resin flow stops. T-100 has gone from 90% full to 5% full.

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t-Scenario Time Event 20% full. Thus, 15% of tank volume has spilled. T-100. surface dose rate was 68 R/hr when 60 to 100 Ci in 30 ft3 of resin, j

0045 Severe winds strike plant. Herculite and spilled resins at transfer site are blown northward. Security building portals alarm. Security should notify the Control Room of condition.

0049 A RAD Technician dispatched to check radiological conditions slips and falls into the spilled resin. He sustains a head injury and is contaminated. The injury is reported to the Control Room.

j 0052 An ambulance is called. RAD Technicians decontaminate the injured party to the extent possible.

1 0055 Magnitude of resin spill and subsequent spreading becoming j

clear. Radiation monitor readings and visual evidence indicate

. spread of contamination beyond security fence and possibly site

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boundary. A site area emergency will be declared when dose levels are observed to be greater than 500 millirem per hour beyond site boundary. EOF activated, if not yet done.

0102 Ambulance arrives, either victim taken to ambulance or escort provided to reach victim. Control Room should notify hospital to prepare to receive and treat contaminated injury.

i 0130 Extent of contamination determined. They have been blown from original spill site north across plant and northward up beach beyond site boundary. Apparently resins have gotten into the lake.

Plant staff has reported to EOF.

0155 General Office Response Team arrives at EOF. Planning begins for cleanup of resin contamination. Contaminated area is j

isolated and posted.

0220 General Office EOF staff arrives.

,i Initial clean-up activity in progress.

0330 Clean-up plan completed. Portions will already have been implemented. Full personnel mobilization will not be requested.

4-Players will be expected to mobilize numbers and types of personnel dictated by extent and type of contamination. Prog-ress will be judged by controllers with appropriate results reported to clean-up crews. Some lake washup will occur. Plant and EOF staff will be expected to administratively set up the mechanics of a full-scale cleanup. These include contacts with 7

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l Time Event companies, arrival times, waterborne' contamination control, long-term monitoring program, etc.

0500 Exercise ends. Cleanup has been demonstrated adequately and to long-term plan formulated.

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(0815) INITIAL CONDITIONS A.

The' plant is at full power, 98% to 100% power, at middle of core life.

B.

The following equipment is in a degraded mode:

1.

Station Power Transformer 13 is out of service (00S) for resetting the " taps" on the transformer.

a.

2400-volt Breaker 152-110, the supply to Transformers 13 and 77, is racked out and red tagged.

b.

480-volt' Breaker 52-1302, the supply to Bus 13 from Transformer 13, is racked out and red tagged.

c.

Work on Transformer 13 has not started.

2.

-Station Power Transformer 77 is 00S due to upcoming repairs on XFMR 13.

a.

480-volt Breaker 52-7701, the supply to Bus 77 from XFMR 77, is racked out and red tagged.

3.

Boric acid Pump P-56A will not run.

a.

It is thought to be bound up with solidified boric acid.

b.- Its breaker is open and caution tagged, work order written, but not yet processed.

c.

'It was declared " INOPERABLE" yesterday at 0103 hours0.00119 days 0.0286 hours 1.703042e-4 weeks 3.91915e-5 months .

4.

Post Accident Sampling Monitor (PASM) is out of service for scheduled modifications.

a.

It will be 2-3 weeks before the PASM can be returned to service.

5.

25R8 air blast breaker was opened and red tagged "B" Shift j

yesterday for R Wheeler per REPOCO (Region Power Control).

a.

Preventive maintenance is to be performed on 25R8ABB and it is not scheduled to be returned to service until 1200, 5/22/87.

b.

R Wheeler took clearance at 0847 yesterday and has the breaker partially disassembled.

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Control rod Drive-36 (CRD) is considered inoperable but tripable.

a.

CRD-36 was just discovered to be inoperable the previous shift when operators attempted to move it as part of the biweekly exercise surveillance, b.

Troubleshooting to take place this shift.

7.

RIA-1808 containment radiation monitor has just alarmed and is 4

reading "HI" full scale at 10 R/hr.

a.

RIAs-1805, -1806 and -1807 are reading normal.

C.

The following system lineups are in effect to support plant conditions:

1.

Buses 13 and 14 and Buses 77 and 78 are cross tied to support XFMR 13 maintenance.

D.

The following ALARM conditions exist:

1.

" Service Water Pump P-7A Basket Strainer HI dP" alarm has been intermittent since last evening.

a.

A maintenance order has been written for cleaning the strainer.

b.

P-7B's strainer was cleaned last week.

It was partially plugged with debris and marine life.

(1) The marine life may have been Asiatic class.

2.

" Containment HI Radiation" alarm was received moments ago when RIA-1808 went full scale HI.

3.

" Rod Drive HJ Seal Leak Off Temperature" alarm has been in since 0537 this morning, a.

Alarm was received approximately 20 minutes after the I

completion of CRDM exercising and read 211*F.

j b.

CRD-26 is adjacent to CRD-36 and they are both in the l

southeast quadrant of the core---RIA-1808 is in the SE l

quadrant of containment.

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The following evolutions are in progress:

1.

Resins are being transferred from T-100, the spent resin storage tank, to the shipping cask.

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a.

Spent resins are from the spent fuel pool demineralizer.

b.

Transfer was commenced at 0748; estimated completion time is by 1000 this morning.

2.

"A" evaporator is in service processing T-64C Clean Waste Receiver Tank (CWRT).

F.

The meteorological conditions are as follows:

1.

I't is overcast and cool with forecasts calling for rain (possibly heavy at times) developing before noon. A severe storm warning has been received from "Murray & Trettel Inc" (meteorological consultants) predicting high winds, lightning and heavy rain - in effect.from 0900 until 1400. The MET tower indicates the following at (10 meters):

a.

Wind speed:

17.3 aph b.

Wind direction: 235' c.

Stability: c (based on dt) d.

Ambient temperature: 61'F G.

Primary and secondary chemistry is stable at the following conditions:

1.

Primary system chemistry a.

pH: 6.7 b.

Boron: 500 ppm c.

Dissolved 0 : <.02 ppe 2

d.

H: 24.8 cc/Kg 2

e.

Total beta gamma activity:

1.58 pCi/mL f.

Iodine dose equivalent:

2.5 E-2 pCi/mL g.

Total PCS gas activity: 4.33 pCi/mL 2.

Secondary system chemistry a.

Primary to secondary leak rate:

001 gpm b.

Off gas Xe 133: 2.95 E-6 pCi/mL c.

Condenser air inleakage:

5.0 cfm

()

d.

A and B S/G gross gamma activity:

<5 6 E-6 pCi/mL l

RP0387-0257A-TP12-TP11 1

. -r

-,--,_..-w.

..ww--.%, -,,,,,

r-

,-r-n-w--..m.

-.---,------,r---e

r--

4

-H.

Primary Coolant' System Leak Rate (as of 0736):

1.

Latest as of 0736 i-a.

Identified: 0.28 gpa

b.. Unidentified:

0.6 gpa c.

Total: 0.88 gpm 2.

Previous. day (will be Controller supplied on request).

a.

Identified: 0.28 gpa b.

Unidentified: 0.26 gpm c.

Total: 0.54 gpa d.

CRDM seal leakage: 295 mL/ min I.

CRD seal leak off temperatures for CRDs other than No 26 (as of 0537):

1.

Most were between 135'F and 175*F.

2.

Controller supplied on request

\\

J.

Operator concerns and expected actions post initial conditions review.

1.

The-HI CRD-26 seal leak off temperature alarm - per Alarm Response Procedure No 5 (ARP) references, Attachment 1 of SOP-6, which directs a seal leakage measurement be obtained per SOP-6,-.

(This has not yet been accomplished or directed.)

a.

This involves a containment entry.

I b.

The fact that PCS leakage has also increased, encourages i

operators to obtain a new seal leak rate posthaste.

NOTE: While operators are in containment to obtain seal leak rate, expect them to perform a visual survey / search of all readily accessible areas for leakage.

2.

The alarming of RIA-1808 should prompt operators to reference ARP-8 which directs:

l l

a.

Check remaining containment radiation monitors.

I l --

b.

If two or more monitor alarms verify that CIS (containment isolation signal) activated and that isolation occurs.

c.

Check containment pressure, temperature and humidity indications.

RP0387-0257A-TP12-TP11 l

l l

L

5

/~T d.

Survey containment by remote TV.

e.

Have containment air sampled.

f.

Visually inspect containment if conditions permit.

g.

Operators will most likely conclude that RIA-1808 has simply

. failed HI and seek I&C assistance in troubleshooting.

h.

Once failure is confirmed the monitor should be declared inoperable and placed on the LCO board. Additionally, a work order should be initiated and action taken per S0P 39 to place the remaining monitors in a two out of three trip logic.

3.

The increase in PCS leakage will be a concern:

Again a prime suspect will be increased leakage from CRD-26.

a.

b.

Another leak rate calculation may be started.

(1) Assume first calculation and data used to have already been reverified.

c.

May wait for new CRDM seal leakage prior to starting new PCS O

leak rate check.

b d.

Operators may reference ONP-23.1 and initiate action to locate source of leakage.

4.

Nagging concerns will consist of:

a.

CRD-36 being inoperable and associated troubleshooting to be done b.

25R8 ABB OOS with degraded electrical distribution system and lightning storm with high winds imminent c.

P-56A being bound up with boric acid d.

Status of P-7A's suction strainer NOTE: The time expected actions just described here in Part "J" actually occur will be impacted by events about to occur, and therefore when and at the discretion of Plant Management.

O RP0387-0257A-TP12-TP11

1 SCENARIO NO PALEX-87 TIME =

0815 MESSAGE NO 1

T=

-0030 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSAGE FOR: Control Room Operators / Shift Supervisor / Shift Engineer SIMULATED PLANT CONDITIONS:

Initial conditions. Please review initial conditions sheet, data sheets, logbook sheets, and turnover sheets.

MESSAGE: Annunciator: Make the following announcement over the plant public address system:

" Attention all personnel. The annual emergency exercise will commence shortly. All announcements related to the exercise will be preceded and followed by the statement 'This is a drill.'

Only drill participants are to respond to drill announcements."

()

V CONTROLLER USE ONLY: Provide attached sheets.

O RP0387-0257A-TP12-TP11

Page 1 of 3 i

O PALISADES SEP EVALUATED EXERCISE INITIAL CONDITIONS 1.

The plant is at full power, 98% to 100% power, at middle of core life (5.8 GWO/MTU).

2.

The following operating conditions exist:

a.

Bus 13 and Bus 14 are cross tied in preparation for resetting the

" taps" on station power Transformer 13.

Work has not started.

(1) 2400-volt Breaker 152-110, the supply to Transformers 13 and 77, is racked out and red tagged.

(2) 480-volt Breaker 52-1302, the supply to Bus 13 from Transformer 13, is racked out and red tagged.

b.

Bus 77 and Bus 78 are cross tied since the supply breaker to Trans-former 13 also feeds Transformer 77.

(1) 480-volt Breaker 52-7701, the supply to Bus 77 from Trans-former 77, is racked out and red tagged.

i c.

Boric acid Pump P-56A will not run.

(1) It is thought to be bound up with solidified boric acid.

(2) Its breaker is open and caution tagged, work order written, but not yet processed.

(3) It was declared " INOPERABLE" yesterday at 0103 hours0.00119 days 0.0286 hours 1.703042e-4 weeks 3.91915e-5 months .

i d.

The " SERVICE WATER PUMP P-7A BASKET STRAINER HIdP" alarm has been intermittent since last evening.

i (1) A maintenance order has been written for cleaning the strainer.

(2) P-7B strainer was cleaned last week. It was partially plugged with debria and marine life.

(a) The marine life may have been Asiatic class, e.

Post Accident Sampling Monitor (PASM) - panel is out of service for scheduled modifications.

l l

(1) It will be 2-3 weeks before the PASM can be returned to service.

l l

l t

PALEX-87 RP0387-0257B-TP12-TP11

Page 2 of 3

'I' f.

Per Repoco 25R8ABB was opened and red r.agged for R Wheeler "B" Shift yesterday.

(1) 25R8 ABB is out for preventive mait:tenance and is not scheduled to be returned to service until 1200 hours0.0139 days 0.333 hours 0.00198 weeks 4.566e-4 months , 5/22/87.

(2) R Wheeler took clearance at 0847 yesterday and has the breaker partially disassembled.

3.

The following equipment is in service:

a.

Service water Pumps P-7A and B (1) P-7C is in standby.

b.

CCW Pumps P-52A&B (1) P-52C is in standby.

c.

Battery chargers No 1 and No 2 d.

Main exhaust Fan V-6A e.

Switchyard station power Transformers No 1 and No 2 f.

Fuel pool cooling Pump P-51A 4.

The present meteorological conditions are as follows:

a.

It is overcast and cool with forecasts calling for rain (possibly heavy at times) developing before noon. The MET tt.wer indicates the following at (10 meters):

(1) Wind speed:

17.3 mph (2) Wind direction: 235' (3) Stability:

C_ (based on dt)

(4) Ambient temperature: 61*F 5.

Primary and secondary chemistry is stable at the following conditions:

a.

Primary system chemistry (1) pH: 6.7 (2) Boron: 500 ppm O

PALEX-87 RP0387-0257B-TP12-TP11

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

. ~

J Page 3 of 3 4

(3) Dissolved 0 : less than.02 ppa 2

(4) H: 24.8 cc/Kg 2

(5) Total beta gamma activity:

1.58 pCi/mL

t i

(6) Iodine dose equivalent:

2.5 E-2 pCi/mL 3

(7) Total PCS gas activity: 4.33 pCi/mL

{

b.

Secondary system chemistry (1) Primary to secondary leak rate:

.001 gpm i

(2) Off gas Xe 133: 2.95 E-6 pCi/mL I

(3) Condenser air inleakage:

5.0 cfm (4) A and B S/G gross gamma activity: Less than 5.6 E-6 pCi/mL l

i s

1-1 4

J l

i t

l h

h i

1 I

j PALEX-87 RP0387-0257B-TP12-TP11

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

PALEX-87 Proc No 4.01 Revision 4 m

Page 1 of 1

)

-/'

PALISADES SEP EVALUATED EXERCISE IN111AL cunL IIIONS Shift Turnover Checklist Date 5/19/87

/

1.

Review the following prior to change of shifts:

A

.B G-a.

SS log, Daily Order Book, and SE Shift T/0 Checklist b.

Equipment and LCO Status Boards c.

Switching, Tagging in Progress d.

Testing / Evolutions in Progress

/

A evap - processing T-64C Transferring resins from I-100 to cask B evap - STD FWP - 5/D VRS - 5/D e.

Degraded Equipment

/

\\

Sta Pwr Transf 13 (tagged for saint)

CRD No 36 - Won't move!

/

Sta Pwr Transf 77 (tagged for maint)

RIA-1808: Reading High Full Scale P-56A - 5eized P-7A Strainer - Plugged 7 FASM Panel - for modification 25R8 ABB - for PM" f.

Miscellaneous Ibrnover Items

/

Estimate resin transfer will be completed by 1000 hours0.0116 days 0.278 hours 0.00165 weeks 3.805e-4 months today!

s PC5 leakage has increased.34 Epm from yesterday.

Need to make containment entry to obtain URD seal leakage and check for leaks.

Buses 13 and 14 cross tied and Buses 7/ and 78 cross ties for Transformer 13 maintenance.

Work orders in on F-7A strainer and P-56A 2.

Complete the following during the shift:

a.

Inspect control consoles.

s.

b.

Review alarm status (panels /datalogger) b.

Daily / weekly tech sp/WO for testing or review requirements.

ec surveillance signed c.

c.

Review completed WR d.

d.

e.

Review operation weekly schedule.

e.

f.

Review switching, tagging and maintenance planned, f.

g.

Shift briefing g.

h.

Review shift complement for following shift.

h.

i. Check plant areas for safety hazards or deficiencies.

i.

j. Key signout sheet verified.

J.

k.

Log sheets signed.

k.

4 INil. L ALS NOTE: Use reverse side for additional infcrmation as needed.

RP0387-0257D-TP12-TP11

4

'PALEX 1 PALISADES SEP EVALUATED EXERCISE INITIAL CONDITIONS Shift Supervisor Log Plant @ 99.7%

Power, 800 MWe "A" Shift Anderson, Fenech, Drummond, Rewa, Bowen, Grimes, Weinhart, Pratt,

.-/ c Newton Y;$

0103 Placed "A" evap I/S, processing T-64C.

0200

' Held shift meeting.

0312 Granted clearance to P Rigozzi on Station Power Transformer 13.

\\

0330 Started preparations for resin transfer from T-100 to cask.

(T-100 has spent SFP demin resin in it.)

0405' Commenced CRDM exercising per D/WO-1.

0434 While performing CRD exercising CO-II reported CRD-36 will not move -

't investigating!

il 0437 NRC phoae and plant status check.

t 0440 Confirmed CRD-36 will not move in or out - declared CRD-36 inoperable -

took actions as per ONP-5.3 and SOP-6, Attachment 1; still unable to obtain any movement.

0443 Contacted D&C Superintendent:

Informed him that CRD-36 was inoperable.

Received concurrence that the rod could still be considered tripable.

4 I&C will troubleshoot "B" Shift.

0500 Continuing to exercise remaining CRDs.

i 0510 Completed CRDM exercising.

0537 P.eceived CRDM "HI" seal leak-off temperature alarm: Found CRD No 26 reading 211*F.

0716 Received " Severe Storm Warning" from Murray & Trettel calling for intermittent thunderstorms and high winds:

In effect from 0900-1400 today.

RP0387-0257C-TP12-TP11 g

, ~. _. _ _

a I

PALEX-87 2

xr

\\

0736 Completed 3-hour PCS feak check, results as follows: -0.6 gpa unidentified,.88 gpa total. NOTE: This is an increase of.34 gpm unidentified since yesterday's leak check was performed.

0748 Weinhart and Bowen commenced transferring resins - they estimate transfer should be completed by 1000. They will turn over on station to Rawson and Dopp at 080rf.

g 7

0813 Regeived " Containment HI Rad Alarm" on L-13; found RIA-1808 reading 10 R/hr, RIAs - 1805, 6 + 7 reading normal.

(

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W J

j, e.

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f% i f

(

RP0387-0257C-TP12-TP11

........... m.

O O

O LIMITING CONDITIONS FOR OPERATION I

MESSAGE:

1 TIME =

0815 T=

-0030 SCENARIO: PALEX-87 INITIATED FINISH BY APPLICABLE COMPONENT DATE TIME DATE TIME TECF. SPEC COMMENTS P-56A (Boric Acid Pump) 5/18/87 _0103 3.2.3 No LCO as long as P-56B operable CRD-36 5/19/87 0440 3.10.46 No LCO as long as no other CRDs are mis-l aligned or inoperable i

i I

1 1

i 1

i I

I RP0387-0257A-TP05-TP11 i

.~

i I

4 t

1 i

l

)

MESSAGE:

1 TIME =

0815 T=

-0030

' SCENARIO: PALEX-87 4

C-13 Panel C-12 Panel C-11 Panel 2

1 l

K-11 K-13 K-07 K-09 K-01 K-03 K !

l K-11 No 32 " Service Water Pump K-9 No 54 " Rod Drive - HI Seal i

P-7A Basket Str Leak Off Temperature" i

HI DP" l

l K-13 No 63 " Containment HI 7

i Radiation" t

e i

)

I i

1 1

4 i

i RP0387-0257A-TP05-TP11 i

4

f

(

)

\\

%.)

w)

Message:

1 Time:

0815 T:

-0030 Scenario:

PALEX-87 C-08 C-02 C-01 SW Pumps Hun P-7A Run F-7B Stdby P-7C (10) VCT Temp 120 *F MFP Suction Press 370 psig CCW Pumps Run P-52A Run P-52B Stdby P-52C (10) VCT Press 22 psi MFP A Dsch Press

%0 psig FPC Itaps Run P-51A P-51B (10) VCT Level 72 %

MFP B Dsch Press 940 psig i

PCP Control Bleedoff Press 80 psig AW Pump 8C Amperes apps Containment Cooler Recirc Fans (26) letdown Flow 36 GPM AW Pump 8C Disch Press psig Run VIA Run V2A Run V3A Run V4A (26) Qiarging Flow 41 GPM AW Pump 8A Amperes amps Run V1B Run V2B Run V3B Run V4B (9) Quench Tank Temp 115 'F AW Pump 8B Steam Press psig (9) Quench Tank Press 0.5 psig A W Pumps SA & 8B Disch Press psig C-03 (9) Quench Tank Level 75 %

Moisture Sep Dr Tank 64 %

(7) Pzr Press (R) 2010 psia Condenser Hotwell Level 65 %

(23) HPSI Pumps P-66A P-66B (8) Pzr level (R) LRC-0101A 57 %

Condenser Vacuum 27 in hg.

(24).LPSI Pumps P-67A P-67B LRC-0101B 57 %

Gland Seal Cond Vacuum 18 in hg.

(18) Containment Spray Pteps (12) PORV PRV-1042B C

1043B C

Atm. Stm. Dumps Closed P-54A P-54B P-54C (12) Block HO-1042A C

1043A C

AW Feed Ptssps P8A P8B P8C (27) HPSIA, LPSIA, Spray A Suction Charging Pumps Pun PSSA PSSB P55C Heater Drain Pumps Run P10A Run P10B O

CV-3057 (SIRWT)

C CV-3029 (Sump)

(6) PCPs Run P50A Run P50B Run P50C Run P50D Condensate Pumps Run P2A Run P2B (27) HPSIB, LPSIB, Spray B Suction Pzr Her Amps L.C. 15 130 L.C. 16 130 I

O CV-3031 (SIRWT)

C CV-3030 (Sump)

(1) PCS T,y, (R)

Loop 1 (TR-0111) 562 'F PIP Loop 2 (TR-0121) 562 'F C-02 (25) Reactor Power Level (Demand Log + Constant,' Rod, or Flux / Temp)

NI-1 cps NI-3 100 % NI-7 100 %

Gross MW 800 Intermediate Press Letdown Temp ly *F NT-2 cps NI-4 100 % NI-8 100 %

Net HW @

Charging Line Temp 400,'!

NI-5 100 % NI-9 100 %

(28) Control Rod Position letdown Line Temp 230 *F NI-6 100 % NI-10 100 %

GP1 132 CP2 132 GP3 132 CP4 132 SDCS from PCS (R)

F CP 5(P) 132 CP 6(A) 132 GP 7(B) 132 SDCS to PCS (R)

F Stuck Rods

Yes No

36 (4) Core Exit Temp g *F NOTE: CRD !!o 36 considered inoperable but tripablet t

4 RP0387-0257E-TP12-TP11

n.

p f.

Me*8MW 1

Time:

0815

' T:

-0030 Scen rio:

PA1ZX-87 C-13 C-12 C-04 Ready Ready CST level (T-2) 80 %

PCP Current (32) D/C 1-1 Stdby D/G 1-2 Stdby Instrument Air Press 105 psig A E amps B 630 amps (32) IC Buss Volts 2400 Amps OK (15) Containment Building Press 0.1 psig C 625 amps D 63 amps (32) 1D Buss Volts 2400 Amps OK (16) S/C A Compartment Temp 120 'F (6) PCS Flow 75 %

S/G A Compartment Humidity 0%

(3) T 1

87 'F C41 Back C-11A H

(16) S/G B Compartment Temp 122 *F Loop 2 587 'F S/G B Compartment thanidity 0%

(2) T Loop 1 537 'F (17) Containment Area Monitors (16) Dome Temp 128 'F loop 2 537 *F RIA 1805

.02 R/Hr kIA 1806

.03 R/Hr 0

(11) SIRWT Level 99 %

T WR(R) Imop 1 535 'F RIA 1807

.02 R/Hr RIA 1808 10 R/Hr g

(15) WR Containment Press (R) 14.8 psia loop 2 535 'F (17) High Range Containment Monitors a

(14) Containment Sump Level 0%

(5) Subcooling y 'F 600 psig RIA 23211.01 R/Hr RIA 23221.01 R/Hr (14) Containment Water Level (R) 0%

(7) PCS WR Press (R) 2010 psia (19) Containment H Concentration 2

(22) 51 Tank level (%) A 48 B 48 C 48 D 48 (7) PCS NR Press (R) psia AI 2401 R S1 Tank Press (psig) A 210 B 210 C 210 D 210 (30) S/G A Level WR 70 %

AI 2401 L (21) SIAS Yes X No (30) S/G A level (R) 70 %

(30) Main Steam Canna (30) S/G A Press 700 psia S/G A RIA 2324 40 eps 6

Panel K-13 S/G A Steam Flow (R) 5.6 X10 PPH S/G B RIA 2323 30 cpm 6

S/G A Feed Flow (R) 5.6 X10 ppy; (20) Containment High Pressure (30) S/G B Level WR 70 %

Equipment Status:

Yes X No (30) S/G B Level (R) 70 %

(20) Containment High Radiation (30) S/G B Press 700 psia 1.

Significant Equipment Outages 6

Yes X No S/G B Steam Flow (R) 5.6 X10 PPH (Inoperable Equipment) 0 S/G B Feed Flow (R) 5.6 X10 PPli 2.

Surveillance Due or in Progress f

C-12 3.

Abnormal Electrical Lineups or C-11 Outages Conc. Boric Acid Tank levels l

T53A y%

(31) AFW Flow to SCA

{

T53B y%

From P8A6B 0 gpm From P8C 0 gpa Reactor Vessel DP y psid (31) AFW Flow to SCB (12) PORV Discharge Temp 115 *F From PBA&B 0 gpm From P8C 0 gpm (13) Pzr Safety Valve Dsch Temp Condenser Vacutsa (R) y in hg.

RV-1039 115 *F PCP A Leak-off Flow (R) 1 GPM RV-1040 115 'F PCP B leak-off Flow (R) 1 GPM j

RV-1041 115 *F PCP C Leak-of f Flow (R) j CPM 5

PCP D Leak-off. Flow (R)

J CPM j

RP0387-0257E-TP12-TP11

MURRAY cad TRETTEL sacoapoaA7ao Date: /9 W y//3?

/

Cartehad Consultsig Moveorologists NORTHFIELD. ILUNots Time:

97/6,

/3 Chicogo Phone:

Northfield Phone:

Given By:

f + if A V

(312)-273-5600 (312)-446-7800 Received 8v ~e// Od/

'understorm MMEind/

Warning Current STORM WARNING :

ai ' % w Ty m M J sF ;

from Owr L n to 3 8a fun-i u.i m.,,

mn a., i Probabeiety Factor Probaomtv F actor A.

OPER ATIONAL COLOR CODE (see back) sen.nces out of to E.

STORM CHAR ACTERISTICS cont'd.

ecumes evt of toi Q

1 Black (Maior trouble) -

1%345678910

60. Total Amount of Rain 1"

-12 3 4 5 648 9 to f

2. Red (Significant trouble) -

12345675910 61 Critical rate of fail ttimo B9cv tcup_ 12 3 4 5 6 7A910 3 Yellow (Little or hmited trouble)-

- 12345678910

62. Critical rate of fall tamt i e

nch per L r.

,j 4 Green (No trouble) -

12345678910 F.

TEMPERATURE E TYPE OF WEATHER O 63. Remaining beiow 32oF 123456799'O U 5 None-12345678910 0 64. Hoiding near 32oF -

- 12 3 4 5 6 7 a 910 0

6. inciated Thunderstorm (si (T) -

-12345678910

' 65. Holding above 32oF -

123456789Ji

7. General Thunderstorms (T).

12345678910

66. Fathng during storm -

12 3 4 5 K7 8 910

8. Squall Linets) -

12345678210

67. Rising during storm 12345678910

9. Potential Tornado-52345678910 0 68. Going below 32 by to 12345678910

10. Local High Winds (gusts over 40 mph) - *12 3 4 5 6 7 8X 10 0 69. Rising above 32 by to

-12345678410

11. General High Winds laverage over 30 mph)12 3 4 5%7 8 910 G.

WIND //p i

12. Rain (R) -

12345678%10 0 70. North O 75 Norin

13. Rainshower(s) (RW) -

-12345678910 0 71.Soutn G 74. becoming

@ 76 Sovin

14. Drizzle (L) -

-12345678910 0 72. East O

77. East

@ 173. West O 78 west O 15 Freezing Rain (Ice = ZRl -

1234.5678910 3 79. w,nd direction probabihty -

--------1234/67S9")

C 16 Freezing Drizzle (Ice = ZL)-

12345678910 0 17. Sleet (Ice Pettets = Er -

12345678910 Gr 80. Speed /7 mph to 13 mph 12 3 4 5 6 7 8 9 to C 18. Wet Snow (S) -

12345678910 becoming 17 mph to 1 C mph 12 3 4 5 6 7 8 9 to 0 19. Heavy Snow (over 4 inches = S+) -

12345678910

81. Gusts to 30 mon -

123456789X 0 20_Very He,a,vy SnowJ,over {nches = S++) ;1.2) L5 5 7.8MO

82. Gusts to 40 mph.

1234567X910 7 ft. Combination:, Main-ice Snow - _

, 12345678910

83. Gusts to 50 mph-12 3 4 X6 7 8 910 J 22. Borderkne: Rain-Ice (R. ZR) -

12345678910

84. Gusts to 60 mph-12 X4 5 6 7 8 910 O.

O 23 Borderkne: Rain. Snow (R. Si-12345678910

85. Gusts over 60 mph -

1 X 3 4 5 6 7 8 910 t

i O 24. Borderkne: Snow-Ice (S. ZR) -

12345678910

@ 86. Strong snitting winds -

- 12 3 4 5 6 7 A910 V

O 25 Borderhae. Dr'zzle-ice (L ZL)-

12345678910 0 26.

i2345678910 U 87. Gradual wind shif t -

-12345678910 0 27.

12345678910 0 88. orif ting winds.

1234567s910 0 28.

to 12345678910 0 29.

to

- 12345678910 H.

COMMENTS

@ 89. Major trouble condition -

1 X3 4 5 6 7 8 910 Q TIME OF BEGINNING O 90. Trouble restricted local.

12345678910

$2 3 4 5 6 7 8 910 0 91. Borderkne trouble condition-12345678910 la 30.11 a m.

1 p.m.-

D 31.11 p m.

1 a.m 12345678910 0 92. Little trouble expected-

-12345678910 0 32. i 3 a m.

O 37. i - 3 p.m..

12345678910 0 93. Occasional cloud.to-ground hghtning -

12345678910 0 33. 3 5 a.m.

O 38. 3 5 p.m.-

-- 12 3 4 5 6 7 8 9 to Q1 94. Frequent cloud to ground bghtning.

12 3 4 5 6 7K910 0 34. 5 7 a.m.

O 39. 5 7 p.m.-

12345678910 0 95. Main troubie due to hghtning -

12345678910

@ 35. 7 9 a.m.

O 40. 7 9 p.m.-

X2 3 4 5 6 7 8 910 0 96. Main troubie due to wind -

12345678910

@ 36, 9 11 a.m.

O 41. 9 11 p m.-

--12345675910

@ 97. Trouble due to hghtning and wind -

12 3 4 5 6 7 8X10 L29 98. Series of thunderstorms moving Q.

DURATION from bf b at t7 mph 12345678910

$ 42. Brief - -

1K3 4 5 6 7 8 910

99. Slight glazing -

12345678910 g

43. Less than 3 hrs. -

- 12 3 4 5 6 7 K910 100. Rapid accumulation of ice -

12345678910

44. 3 6 hrs.

O 47.18 24 hrs.

12345678910 0101. Icing heavier to

-- 12345678910

45. 6 12 hrs.

O 48. over 24 hrs.

-12345678910 Q 102. Preventive heating indicated -

-12345678910

,. 46.12 18 hrs.

12345678910 U 103. Rapid accumulation of snow 12345678910 E

STORM CHARACTERISTICS O 104. REMARKS x 49. Shght -

12345678910 1

50. Moderate 12345678910 j

51. Locally Severe

- - 12 3 4 5 6 7,E910 1

52. Generally Severe-12345678910 b $3. Protonged -

12345678910 S 54. Compounded by wind 12 3 4 5 6 7 K910 J.

LOG C

55.1 5/10 of area affected - -

12 3 J 5 6 7 8 910 0105. Warning USEFUL.

[

56. 6 - 9/10 of area aff ected - -

12345678910 0106. Warning NOT useful.*

57. All of area affected-12345678910

Reason f(

i

58. Continuous (steady) -

12345678910

)

k 59. Intermittent (off and on) -

12 3 4 5 6 7)L910i v

MURRAY and TRETTEL OPERATIONAL COLOR CODE The PURPOSE cf the M&T Color Code is to give a MAXIMUM amount of INFORMATION in a MINIMUM n amount of TIME. It makes the subtle TRANSITION from a " meteorological forecast" to an " operational inter-(v) pretation". The Color Code is an extra step to provide not only the weather FORECAST but also the M&T INTERPRETATION of the EFFECT of that forecast on OPERATIONAL PROBLEMS. It is DESIGNED pre manly for SUPERVISORY personnel and presents weather forecasts in terms that are quick and easy to USE and INTERPRET, yet EFFECTIVE in RESULTS.

The colors used are GREEN, YELLOW, RED and BLACK. Their explanation and description are given below. The Color Code is given in terms of PROBABILITY FACTORS (PF) - expressing the probability of occurence of the various color combinations.

M&T WEATHER WARNING COLOR CODE - Explanation and Examples YELLOW: The weather pattern is favorable for the DEVELOPMENT of weather conditions of the TYPE and INTENSITY that will have a "little or limited" effect on client cperations.

EX AMPLES:

1. Isolated thunderstorms with httle wind, or cloud to ground hgntning (1-1). 2. Generai tnuncerstorm act+tv with primarily cloud-to-cloud hghtning (G 1); 3. Brief period of freenng rain resulting in shgnt spotty giarmg - with hgnt winds and temperatures near 32 F. (ZR 1);

4. Freezing drizzle resulting in shght general gladng - with hgnt wincs and temperatures near 32 F. (ZL 1).

RED: The weather pattern is favorable for the DEVELOPMENT of weather conditions of the TYPE and INTENSITY that will have a "significant" effect on client operations.

EXAMPLES:

1. Isolated thunderstorms with strong gusty winds and/or cloud-to-ground hghtning (12); 2. General thunder.

storm activity with considerable cloud-to ground hghtning (G.2): 3. Freezing rain or freezing drizzte of suff.cient duration and intensity to cause a significant buildup of ice on conductors (ZR 2, ZL 2).

BLACK: The weather pattern is favorable for the DEVELOPMENT of weather conditions of the TYPE and INTENSITY that will have a " major" ef fect on client operations.

EXAMPLES:

1. Tornado; 2. Squall kne with widespread strong gusty winds; 3. Heavy wet snow; 4, Heavy, drif ting snow.

5. Freezing rain causing prolonged widespread, heavy glazing - with strong winds.

GREEN: The weather is UNFAVORABLE for the development of " trouble" conditions. This color is used in combination with YELLOW or RED to indicate the "certainity" of the forecast. When GREEN is used in combination with another color the probability factor of the various colors will total 10. (R7G3, Y6G4, R8Y2, Y7G3, etc.)

A)

M&T WEATHER WARNING CLASSIFICATION (Types)

Type I = ISOLATED THUNDERSTORMS (no. 6) 11: Spotty, httle wind.

12; Spotty, but gusty winds locally severe.

Type G = GENERAL THUNDERSTORM ACTIVITY (no. 7)

A general area of Tstms, often associated with a low pressure area or warm front - numerous thundarstorms - one spot may have been more than one Tstm.

G.1 : High level Tstm - primarily cloud to cloud lightning.

G-2: Low level Tstm - considerable cloud-to-ground lightning and/or wind.

Type S = SOUALL LINE (no. 8)

A line of Tstms, high gusty winds - most trouble due to wind but some troubie due to lightning. relatively short duration, hits an area and then is "over,"- one spot has just one thunderstorm.

Type W1 = LOCAL HIGH WINDS (no.10) l Spotty, gusty winds in a limited area - generally experienced in association with a thunderstorm - generally BRIEF duration.

l Type W2 = GENERAL WIND STORM (no.11) l Strong winds, over a wide geographical area (several states) - generally of PROLONGED duration (from several hours to more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) - caused by strong " pressure gradient" associated with a large vigorous low pressure weather system. Issued when sustained winds exceed 30 mph for a period of 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months or more; or any time wind gusts exceed 40 mph.

FREEZING RAIN - Ice (no.15)

Drops of rain (liquid water particles - 0.02 inch or more in diameter) that freeze in impact. A coating of ice, generally clear and smooth, formed on exposed objects by the freezing of supercooled liquid water particles.

FREEZING DRIZZLE - Ice (no.16)

Drops of drizzle (uniform liquid water particles - diameter less than 0.02 inch) that freeze on impact. A coating of ice, generally clear and smooth formed on exposed objects by the freezing of supercooled liquid water particles, SLEET - Ice Pellets (no.17)

Frozen raindrops. Hard grains of ice that rattle and rebound on contact with hard surfaces - d.ameter of 0.2 inches or less.

U The combination of the M&T COLOR CODE and WEATHER WARNING CLASSIFICATION give a compre-hensive description of the weather, (Type I 1, Y6G4; Type 12, R7G3; Type S, B6R4; Type W 2, R8Y2; Type ZR 2, R783;etc.)

SCENARIO.NO

-PALEX-87 TIME =

0845 MESSAGE NO 2A T=

0000 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSAGE FOR: Security guard SIMULATED PLANT CONDITIONS: Plane crash i

MESSAGE: Plane has crashed into PM&MP Building, security fence appears damaged.

I CONTROLLER USE ONLY: Security guard should report situation to CAS, CAS should report to Control Room, then dispatch personnel to check damage.

O 6

4 I

i f

1 i

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RP0387-0257A-TP05-TP11 l

[

SCENARIO NO PALEX-87 TIME =

0845 MESSAGE NO 2B T=

0000

[)

\\s'.

PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSAGE FOR: PM&MP occupants SIMULATED PLANT CONDITIONS: Plane crash MESSAGE: Airplane has just crashed through the northwest side of the PM&MP Building. No personnel appear to be hurt. There is not a fire.

CONTROLLER USE ONLY:

Message recipient should notify Control Room.

O

O RP0387-0257A-TP05-TP11

SCENARIO NO'

-PALEX-87 TIME =

0845 MESSAGE NO 2C T=

0000 0

PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSAGE FOR: CAS SIMULATED PLANT CONDITIONS:

f MESSAGE: Perimeter intrusion alarm CONTROLLER USE ONLY:

Damaged security fence results in alarm. Call from guard making rounds may be expected shortly. CAS should notify Control Room, which may also dispatch assessment personnel.

t

O

~

d 1

f

O 4

RP0387-0257A-TP05-TP11 i

i

l' SCENARIO NO PALEX-87 TIME =

0845 MESSAGE NO 2D T=

0000 t

PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSAGE FOR: Control Room Operators 1

SIMULATED PLANT CONDITIONS: See data sheets.

4 MESSAGE:

l t

CONTROLLER USE ONLY:

i 4

k e

i

?

I

't f

i i

i RP0387-0257A-TP05-TP11

(

p

,,m Message:

2D Time:

0845 T:

0000 Scenario:

PALEX-87 C-08 C-02 C-01 SW Pumps Run P-7A Run P-7B Stdby P-7C (10) VCT Temp 120 'F MFP Suction Press 370 psig CCW Pumps Run P-52A Run P-52B Stdby P-52C (10) VCT Press 22 psi ItFP A Dsch Press

%0 psig FPC Purps Run P-51A P-51B (10) VCT Level 72 %

MFP B Dsch Press 940 psig PCP Control Bleedoff Press 80 psig AIV Pump 8C Amperes amps Containment Cooler Recirc Fans (26) letdown Flow 36 CPH ADi Pump 8C Disch Press psig Run VIA Run V2A Run V3A Run V4A (26) Charging Flow 41 CPM AFW Pump 8A Amperes amps Run V1B Run V2B Run V3B Run V4B (9) Quench Tank Temp 115 'F AIV Pump 8B Steam Press psig (9) Qu,ench Tank Press 0.5 ps!g AEW Pumps BA & 8B Disch Press psig C-03 (9) Quench Tank Level 75 %

Moisture Sep Dr Tank 64 %

(7) Pzr Press (R) 2010 psia Condenser Hotwell Level 65 %

(23) HPSI Pumps P-66A P-66B (8) Pzr Level (R) LRC-0101A 57 %

Condenser Vacuum 27 in hg.

(24) LPSI Pumps P-67A P-67B LRC-0101B 57 %

Cland Seal Cond Vacuum 18 in hg.

(18) Contairnent Spray Pumps (12) PORV PRV-1042B C

1043B C Atm. Stm. Dumps Closed P-54A P-54B P-54C (12) Block HO-1047A C

1043A C APW Feed Pumps P8A P8B P8C (27) HPSIA, LPSIA, Spray A Suction Charging Pumps Run PSSA PSSB PSSC Heater Drain Pumps Run F10A Run P10B O

CV-3057 (SIRWT)

C CV-3029 (Sump)

(6) PCPs Run P50A Run P50B Run P50C Run P50D Condensate Pumps Run P2A Run P2B (27) HPSIR, IPSIB, Spray B Suction Pzr Htr Amps L.C. 15 130 L.C. 16 130 0

CV-3031 (SIRWI)

C CV-3030 (Sump)

(1) PCS T,y, (R)

Icep 1 (TR-0111) 562 *F PIP Loop 2 (TR-0121) 5_62 'F C-02 (25) Reactor Power level (Demand Log + Constant, Rod, or Flux / Temp)

NI-1 cps NI-3 100 % NI-7 100 %

Cross PU 800 Intermediate Press letdown Temp 1_75 'F NI-2

- cps NI-4 100 % NT-8 100 %

Net MW 760 Charging Line Temp M *F NI-5 100 % NI-9 100 %

(28) Control Rod Position letdown Line Temp 230 *F NI-6 100 % NI-10 100 %

CPI 132 CP2132 GP3132 CP4132 SDCS from PCS (R)

'F CP 5(P) 132 CP 6(A) 132 CP 7(B) 132 SDCS to PCS (R)

F Stuck Rods X Yes No 9 36 (4) Core Exit Temp 590 *F 6

RP0387-0257L-TP12-TP11

)

Mecs 2D Time:

0843

' ' T:

0000 Sc:ncri :

PALEX-87 C-13 C-12 C-04 Ready Ready CST level (T-2) 80 %

PCP Current (32) D/G 1-1 Stdby D/G 1-2 Stdby Instrument Air Press 105 psig A 6 0 amps B 630 amps (32) IC Buss Volts 2400 Amps OK (15) Containment Building Press 0.1 psig C 625 amps D 620 amps (32) 1D Buss Volta 2400 Amps OK (16) S/G A Compartment Temp 120 'F (6) PCS Flcv 75 %

S/G A Compartment Humidity 0%

(3) T L P 1 587 'F C-11 Back C-11A H

(16) S/G B Ccapartment Temp 122 *F loop 2 587 'F S/C B Comparta.ent Ikimidity 0%

(2) T to p 1 537 *F (17) Containment Area Ibnitors c

(16) Dome Temp 128 *F loop 2 537 'F RIA 1805

.02 R/llr RIA 1806

.03 R/Ur (11) SIRWT level 99 %

T WR(R) loop 1 535 *T RIA 1807

.02 R/Hr RIA 1808 10" R/Hr (15) WR Containment Press (R) 14.8 psia locp 2 535 *F (17) High Range Containment Monitors (14) Containment Surp Level 0%

(5) Subcooling 3 'F 600 psig RIA 2321 1.01 R/Hr RIA 23221.01 R/Hr (14) Containment Water Level (R) 0%

(7) PCS WR Press (R) 2010 psia (19) Containment H Concentration 2

(22) SI Tank Level (%) A 48 8 48 C 48 D 48 (7) PCS NR Press (R) psia Al 2401 R g%

SI Tank Press (psig) A 210 B 210 C 210 D 210 (30) S/G A level WR 70 %

Al 2401 L (21) SIAS Yes X No (30) S/G A'14 vel (R) 70 %

(30) Main Steam Camma (30) S/G A Press 700 psia S/C A RIA 2324 40 cpm 6

Panel K-13 S/G A Steam Flow (R) 5.6 X10 FPH S/G B RIA 2323 30 cpm 6

S/C A Feed Flow (R) 5.6 X10 PPH (20) Containment High Pressure (30) S/G B Level WR 70 %

Equipment Status:

Yes I No (30) S/G B Level (R) 70 %

(20) Containment liigh Radiation (30) S/G B Press 700 psia 1.

Significant Equipment OutaFes 6

Yes X No S/G B Steam Flow (R) 5.6 X10 PPH (Inoperable Equipment) 6 S/G B Feed Flow (R) 5.6 X10 PPH 2.

Surveillance Due or in Progress C-12 3.

Abnormal Electrical Lineups or C-11 Outages Conc. Boric Acid Tank levels T53A y%

(31)

AFW llow to SCA T53B 97 %

From P8A&B o gpm Frce P8C 0 gpm Reactor Vessel DP y psid (31)

AMI Flow to SCB (12) POEV Discharge Temp 115 *F From F8A&B 0 gpm From P8C 0 gpm (13) Pzr Safety Valve Dsch Temp Conder.ser Vacuum (R) 3 in hg.

RV-1039 115 *F PCP A Leak-off Flow (R) 1 CPM RV-1040 115 'F PCP B leak-off Flow (R) 1 CPP' RV-1041 115 *F PCP C Leak-off Flow (R) 1 CPM PCP D Irak-of f Flow (R)

J CPM 1T0387-0257E-TP12-TF11

w---

++--

a

.+-$

G-

+2 L.

a

-Se a

A k-

~4 Lh-+.

J

-.a SCENARIO NO PALEX-87 TIME =

0850 MESSAGF NO 3A T=

0005 m

PALISADES NUCLEAR PLANT 1

EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM i

MESSAGE.FOR: Personnel responding to assess crash damage SIMULATED PLANT CONDITIONS:

i MESSAGE:

1) Pir.ne destroyed in crash. Appears to have been a small single-engine propeller plane.

2) There are no personnel injuries.

3) There is no fire.

4) The plane appears to have been unoccupied.

CONTROLLER USE ONLY: Message time approximate; provide upon arrival. Assessor should report damage to Control Room /CAS.

l a

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RP0387-0257F-TP12-TP11 i

l

.-.-.-----.-----.-.__~--._,...,.....-.._--,,,_-,,,,..-,-c-

. - - - - ~...-

SCENARIO NO PALEX-87 TIME =

0850

. MESSAGE NO 3B T=

0005 s

PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSAGE FOR: Personnel responding to investigate fence alarm SIMULATED PLANT CONDITIONS:

MESSAGE: Northwest security fence damaged. Hole in side of PM&MP Building CONTROLLER USE ONLY: Message time approximate;. provide upon arrival. Assessor should report damage to CAS.

4 4

i i -

4 1

1 I

4 RP0387-0257F-TP12-TP11

, _ _ _. _ _ ~ _ _.

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

SCENARIO NO PALEX-87 TIME =

0900 MESSAGE NO 4

T=-

0015 f

PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSAGE FOR: Controllers only SIMULATED PLANT CONDITIONS:

MESSAGE:

t i

a CONTROLLER USE ONLY: An alert should be declared based on aircraft crash on facility. Accountability will comunence on declaration. Notifications made to offsite authorities and Power Control.

i I

)

4 t

RP0387-0257F-TP12-TP11 3

SCENARIO NO PALEX-87 TIME =

0902 HESSAGE NO 5

T=

0017 Iv PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSAGE FOR: Controllers only SIMULATED PLANT CONDITIONS:

MESSAGE:

CONTROLLER USE ONLY: Resin cask almost full when accountability begins. Auxil-O iary Operator stops pump and departs scene. The track alley door has been jammed open for several days and remains so after departure. Resin flow continues after pump stopped as hose depressurizes. The cask overflows resulting in an ongoing resin spill in track alley. Resins will be simulated by the spreading of material, possibly colored gravel.

O O

RP0387-0257F-TP12-TP11

=.. -

SCENARIO NO PALEX-87 TIME =

0915

[

NESSAGE NO-6 T=

0030 0

PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSAGE FOR: Control Room Operators

]

SIMULATED PLANT CONDITIONS: See data sheets.

j MESSAGE:

3-CONTROLLER USE ONLY:

i r

i

1) Personnel should be dispatched from OSC to check cause

{

of the alarm.

l

2) The TSC and OSC should be fully staffed by this time.

)

3) VR area monitor 125 mr/h.

1 I

k i

i RP0387-0257F-TP12-TP11 l

i

N-CONTROL ROOM ALARMS MESSAGE:

6 TIME:

0915 T=

0030 SCENARIO:

PALEX-87 C-13 Panel C-12 Panel C-11 Panel K-11 K-13 K-07 K-09 K-01 K-03 K-05 K-13 " Plant Area Monitoring HI Rad" K-9 No 54 " Rod Drive HI Seal Leak Off Temperature" K-13 No 63 " Containment HI Radiation" K-11 No 32 " Service Water Pump P-7A Basket Strainer HI DP" RP0387-0257G-TP12-TP11

p y-

,~.

)

Message:

6 Time:

0915 T:

0030 Scenario:

PALEX-87 C-08 C-02 C-01 SW Pumps Run P-7A Run P-7B Stdby P-7C (10) VCT Temp 120 'F MFP Suction Press 370 psig CCW Pumps Run P-52A Run P-52B Stoby P-52C (10) VCI Press 22 psi MFP A Dsch Press 940 psig FPC Pumps Run P-51A P-51E (10) VCT Level 72 %

MFP B Dsch Press 940 psig PCP Control Bleedoff Press 80 psig A W Pump 8C Amperes amps Containment Cooler Recirc Fans (26) 14tdown Flow 36 GPM AFW Pump 8C Disch Press psig Run VIA Run V2A Run V3A Run V4A (26) Charging Flow 41 GPM AW Pump 8A Amperes asps Run V1B Run V2B Run V3B Run V4B (9) Quench Tank Temp 115 'F AW Pump 8B Steam Press psig (9) Quench Tank Press 0.5 psig AW Pumps 8A & 8B Disch Press psig C-03 (9) Quench Tank Level 75 %

Moisture Sep Dr Tank 64 %

(7) Pzr Press (R) 2010 psia Condenser Hotwell Level 65 %

(23) HPSI Pumps P-66A P-66B (8) Pzr Level (R) LRC-0101A 57 %

Condenser Vacuum 27 in hg.

(24) LPSI Pun:ps P-67A P-67B LRC-0101B 57 %

Cland Seal Cond Vacuum 18 in hg.

(18) Containment Spray Pumps (12) PORY PRV-1042B C

1043B C Atm. Stm. Dumps Closed P-54A P-54B P-54C (12) Block HO-1042A C

1043A C A W Feed Pumps P8A P8B P8C (27) HPSIA, LPSIA, Spray A Suction Charging Pumps Run PSSA P55B P55C Heater Drain Pumps Run P10A Run P10B o

CV-3057 (SIRWT)

C CV-3029 (Sump)

(6) PCPs Run P50A Run P50B Run P50C Run P50D Condensate Pumps Run P2A Run P2B (27) HPSIB, LPSIR, Spray B Suction Pzr Htr Amps L.C.15130 L.C. 16 130 0

CV-3031 (SIRVI)

C CV-3030 (Sump)

(1) PCS T,y, (R) h p 1 h 011D 562 'F PIP Loop 2 (TR-0121) M 'F C-02 (25) Reactor Power level (Demand Log + Constant, Rod, or Flux / Temp)

NI-1 cps NI-3 100 % NI-7 100 %

Cross MW 800, Intermediate Press letdown Temp 1_75 *F NI-2 cps NI-4 100 % NI-8 100 %

Net MW 760 Charging Line Temp 43 'F NI-5 100 % NI-9 100 %

(28) Control Rod Position letdown Line Temp 230 'F NI-6 100 % NI-10100 %

CP1132 CP2132 CP3132 CP4132 SUCS from PCS (R)

'F CP 5(P) 132 CP 6(A) 132 CP 7(B) 132 SDCS to PCS (R)

'F Stuck Rods X Yes No

36 (4) Core Exit Temp 590 'F RP0387-0257E-TP12-TP11

O MecsaPp:

6 Time:

0915 T:

0030 Scenaris:

PALFX-87 C-13 C-12 C-04 Ready Ready CST level (T-2) 80 %

PCP Current (32) D/G 1-1 Stdby D/G 1-2 Stdby Instrument Air Press 105 psig A 620 amps B Q amps (32) IC Buss Volts 2400 Amps OK (15) Containment Building Press 0.1 psig C 625 amps D 620 amps (32) 1D Buss Volts 2400 Amps OK (16) S/G A Compartment Temp 120 'F (6) PCS Flew 75 %

S/G A Compartment Humidity 0%

(3) T

~

' ^

H (16) S/G B Cos*partment Temp 122 'F loop 2 587 'F S/G B Compartment Humidity 0%

(2) T le P 1 537 'F (17) Containment Area Honitors c

(16) Dome Temp 128 'F loop 2 537 *F RIA 1805

.02 R/ltr RIA 1806

.03 R/Ilr (11) SIRWI Level 99 %

T WR(R) Loop 1 535 'F RIA 1807

.02 R/Hr RIA 1808 10" R/Hr c

(15) WR Containment Press (R) 14.8 psia loop 2 535 'F (17) High Range Containment Monitors (14) Centainment Sump level 0%

(5) Subcooling 3 'F 600 psig RIA 2321 1.01 R/Hr RIA 2322 1.01 R/Hr (14) Containment Water Level (R) 0%

(7) PCS WR Press (R) 2010 psia (19) Contalrnent H Concentration 2

(22) SI Tank Level (%) A 48 B 48 C 48 D 48 (7) PCS NR Press (R) psia Al 2401 R g%

SI Tank Press (psig) A 210 B 210 C 210 D 210 (30) S/G A Level WR 70 %

AI 2401 L (21) SIAS Yes X No (30) S/G A level (R) 70 %

(30) Main Steam Cama (30) S/G A Press 700 psia S/G A RIA 2324 40 cpm 6

Panel K-13 S/G A Steam Flow (R) 5.6 X10 PPH S/C B RIA 2323 30 cpm 6

S/G A Feed Flow (R) 5.6 X10 PPH (20) Containment 111gh Pressure (30) S/G B Level WR 70 %

Equipment Status:

Yes I No (30) S/G B Level (R) 70 %

(20) Containment High Radiation (30) S/G B Press 700 psia 1.

Significant Fquipment Outages 6

Yes X No S/G B Steam Flow (R) 5.6 X10 PPH (Inoperable Equipment) 6 S/G B Feed Flow (R) 5.6 X10 PPli 2.

Surveillance Due or in Progress C-12 3.

Abnormal Electrical Lineups or C-11 Ou tages Cenc. Boric Acid Tank levels T53A y%

(31)

A W Flow to SCA T53B 97 %

From P8A&B 0 gpm From P8C 0 gpm Reactor Vessel DP y psid (31)

AW Flow to SGB (12) PORV Discharge Tecip 115 *F From F8A&B 0 gpm From P8C 0 gpm (13) Pzr Safety Valve Dsch Temp Condenser Vacuum (R) y in hg.

RV-1039 115 'F PCP A Leak-of f Flow (R) 1 GPM RV-1040 115 'F PCP B leak-off Flow (R) 1 CPM RV-1041 115 *F PCP C Leak-off Flow (R) 1 GPM PCP D Irak-off Flow (R)

J GPM KPO387-0257E-TP12-TP11

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

. =

-SCENARIO NO-PALEX-87 TIME =

0917 MESSAGE NO 7

T=

0032

^

PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSAGE FOR: TSC Communicator SIMULATED PLANT CONDITIONS: Call from State Police MESSAGE: The pilot of the airplane has been located. He managed to bail out following engine failure. His is not injured.

CONTROLLER USE ONLY: Communicator should report information to the SED.

l 1

1, 1

3'

O RP0387-0257F-TP12-TP11 j

SCENARIO NO PALEX-87 TIME =

0925 MESSAGE NO 8

T=

0040 AU PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSAGE FOR: Controllers only SIMULATED PLANT CONDITIONS: T-100 has gone from 90% full to 5% full. It was expected to fill the shipping liner after decreasing to 20% full. T-100 surface dose rate was 68 R/hr when 90% full.

MESSAGE:

CONTROLLER USE ONIX:

1) Message time approximate. Resin flow stops at 0925. Message information above may be provided to players as requested.

3

2) 15% T-100 volume spilled; loss of approximately 100 Ci in 30 ft og

,,,13,

3) Provide attached sheets if requested or players have taken steps to acquire information.

RPO487-0029A-TP11

A W K87 heua use omf

//r,rsd+r 8 iO V

Radioactive Waste Report - Weekly, Monday a.m.

Date f-IS"-F7 Date of Last Report f - II "F7 1.

Dry Waste Status A.

Compactible T

1.

ft3 compacted since last report boxes @ 98 ft3 ft3 drums @ 7.5 ft3 %

ft3 B.

Non-Compactible 1.

ft3 packaged since last report

~~ boxes-@ 98 ft3 ~

ft3 2.

Radwaste Storage A.

East Radwaste Building M drums '@ 7.5 f t Al-). Efts 3

liners @ 50 ft3 ft3 J boxes @ 98 ft3';& 4 ft3 1.

T-104 Resin liners @ 193 ft -

ft3 3

@ ft B.

South Radwaste Building T drums @ 7.5 ft 3 3

7 liners @ 50 ft3 l et.') f t3 C5_ boxes @ 98 ft3

-" f t3 1.

Clean & dirty waste filters J. liners @ 193 ft3 T17~ ft3 O

2.

Purification filters b at 28 fts i b D ft3 V

Resins (T-69,T-100) IWT.s it IfD ft3

~

Total storage on site 3

Total last report 13"II ds~ f t3 Net Change

+- T W ft3 3.

Waste Resin Status A.

ft3 requiring disposal T-69 T-100 T-109 ft3 last report Allf ft3 last report I.S6_

ft3 last report d ft3 added g

ft3 added J/.o ft3 added

'df ft3 total

/

ft3 total lyo it3 total

/

i B.

Tank Status (Monthly) 7-50

[

R/hr T-100

$T R/br r

4.

Vault Status

/

High Level Vault Status West

.2.

Center

/ff(

East

[v4.4.

5.

Shipment Status A.

Net Shipment due 6'/If/ff?

drums @ 7.5 ft3 ft3 3

ft3 overpack drums @ 11.6 f t ft3 boxes @ 98 ft3 waste resint J~0 h 3 T.

e s H rm -t. i ro -

m.

i

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

y

Nux 87 h/t./44' cWE e2/Vdf

ffs.rd e r" 8 6.

Solidification Status A.

ft3 awaiting solidification:

Clean (T94A_p_%) + (T94B O %) @ 28.32 L/% =

.Ef _ Liters Dirty (T95A/sa %) + (T95B o %) @ 28.32 L/% =p337* Liters B.

ft3 in solidification process VRS........

,#' drum s @ 7.5 f t 3

3 g it C.

ft3 moved to storage since last report VRSg druns @ 7.5 ft3 g_ f t 3

7.

Gaseous Waste T68A T68B T68C T101A T101B T101,y Press Today

-o-

/SO je

-u-

-o-Press Last Report

-o-

- c; -

-o-

6 3

m released M

Isolation date C.

Liquid Waste A.

Dirty Waste Volume:

DW Tk Egg,% + W//o % @ 71 L/%

{/'/73 Liters Misc. Waste A 7e % + B o%+C o % @ 757 L/1

Tp,990 Liters Misc. Dist. Tks A o % + B o % @ 151 L/%

g. Liters

/

F % + N 4 d% @ 109 L/%

/47, (,94. Liters Filtered Waste Mon. Tks S53 Total System Volume (capacity = 293,000 liters) 13/.f9 Liters = Mc %

Total System Volume Last Report y;p o OLiters = utf %

Net Change r,t9ff9 Liters = jg.f %

B.

Clean Wasty Volume CWRT's A <rl.-% + B26 % + C o%+De % @ 1893 1/%

/f 8'72MLiters Clean Waste Hold 9d % @ 189 L/%

/7 0/* Liters Clean Waste Dist. h % @ 189L/%

,y7go Liters litersV4 95// Liters = /ff{%

/

Total CW System Vol.(total capacity =795,000 Total Last Report

/f/ 82.(, Liters = /9. 0 %

Net Change p.f/2 Liters = v,2.%)

C.

Recovered Liquid Waste Volume:

UtilityWaterStorageTankT-91,#/%@2839L/%

(,8/JG Liters j4t,t W Liters

/

Pri. Syst. MkjU Stor. Tk. T-90 & % @ 7570 L/%

Boric Acid A 79% + B 99% + Recycle / 8 % @ 246 L/%

SJ/.St. Liters Total Recovered Waste (capacity = 1,115,000 liters %3f/2. Liters =32.6%

Total Last Report 360,],23 Liters =J2,3 %

Net Change sadJf_ Liters = M%

r.. w. - t a v s

P42fX 87 d/t./4-4 Wefd* ~ 0/V/l M w+er-a

/-m 6.

Solidification Status A.

ft3 awaiting solidification:

Clean (T94A A %) + (T94B_O %) @ 28.32 L/% =

Liters Dirty (T95A/4 a %) + (T95B_ o %) @ 28.32 L/% =A33J Liters B.

ft3 in solidification process VRS........

drums @ 7.5 ft3 g__ f t3 C.

ft3 moved to storage since last report VRSg drums @ 7.5 f t,#

ft3 3

7.

Gaseous Waste T68A T68B T68C T101A T101B T101C Press Today

-c-

/#C_ 99

_gf

-u-

-o-

' Press Last Report

-o-

-u-

-o-

- cs -

-o-4 3

m released Isolation date M

8.

Liquid Waste A.

Dirty Waste Volume:

DW Tk Eg% + W//o% @ 71 L/%

//73 Liters Misc. Waste A 7u % + B o%+C o % @ 757 L/%

1. ,998 Liters Misc. Dist. Tks A_g_% + B o % @ 151 L/%

g Liters Filtered Warte Mon. Tks S Q % + N # d% @ 109 L/%

/4 494, Liters V

Total System Volume (capacity = 293,000 liters) 93/4~9 Liters = #6c %

Total System Volume Last Report g n o oLiters = M / %

Net Change e afff9 Liters = jzp. t,%

B.

Clean Wasty Volume CWRT's A 9't.-% + B 26 % + C,_p_% + DC % @ 1893 1/%

/fl12/ Liters Clean Waste Hold fa % @ 189 L/%

/'t o/* Liters Clean Waste Dist. h % @ 189L/%

,yfgo Liters Total CW Syttem Vol.(total capacity =795,000 litersWft// Liters = /8,8 %

Total Last Report

/f 4 82.(, Liters = /9. 0 %

Net Change gfgjLLiters= #,2.%)

C.

Recovered Liquid Waste Volume:

Utility Water Storage Tank T-9M% @ 2839 L/%

G,5/.76, Liters Pri. Syst. MkU,p,Stor. Tk. T-90 & % @ 7570 L/%

JVt,z W Liters Boric Acid A W % + B 99% + Recycle / 8 % @ 246 L/%

.f3/Jt, Liters Total Recovered Waste (capacity = 1,115,000 liters)?M I/2 Liters =32.9%

Total Last Report 3g,oLzJ.iters =Jz3 %

Net Change s//439_ Liters = M%

's l

w.v.,n-sa u

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

, ;.: :. ;. ;. :. ;. ;. :. ; ;, ; ;. ;. :. :.. ; ;. :. :. ;, a ;, ;, ;, ;. ;. ; ; ; ;. ; ;. ; ;, ;. :. ;. ;, ;, ;. :. ;, ;. :. :. ;. ; ;. ;. ;. :. :. :. ;, ;. : :, ;, ;

peg,1

.: . ;. :. ;. ;, ; ;. :. ;, ;, a ;. :. :. ;.

tg.ngy.87 08:59:32

""W #

N06685 DETECTOR,3, ND-66, SAMPLE ANALYSIS SAMPLE DATE: 18-MAY-87 08:30:00 SAMPLE IDENTIFICATION: T100 RESIN 2424 TYPE OF SAMPLE: PART. FILTER SAMPLE QUANTITY: 0.1580000E-01 UNITS: CC SAMPLE GEOMETRY: 40M FILTER EFFICIENCY FILE NAME: GELIB.EFF4CM

- - - - k********< :. ;, ;, :. ;. ;, :. : : ;, :. ;, ;. ;, a :. ;, ;. ;. ;. ;, ;, ;. : :. ;. : ;, ;. :. ; ;, ;. :. ;. :. ;. :. ;. :.

ACQUIRE DATE: 19-MAY-87 07:59:00

FWHM(1332) 1.874 PRESET TIME (LIVE):

600. SEC

SENSITIVITY:

4.660 ELAPSED REAL TIME:

648. SEC

SHAPE PARAMETER:

10.0%

ELAPSED LIVE TIME:

600. SEC

NBR ITERATIONS:

5.

DETECTOR: DETECTOR #3

LIBRARY: NUC.UPDAT2 CALIB DATE:

11-MAR-87 08:54:45

ENERGY TOLERANCE:

1.000kV KEV /CHNL:

0.4823234

HALF LIFE RATIO:

6.00 0FFSET:

-0.0127985 KEV

ABUNDANCE LIMIT: 50.00%

Q. COEFF.:

7.017E-07 KEV /C**2 *

A

;;;;;;;;;;;

ENFWGY WINDOW 48.28 TO 2919.19 (INTERMEDIATE PRINT 0UTS OMITTED)

O NUCLIDE IDENTIFICATION SYSTEM (REV 5/80)

SUMMARY

OF NUCLIDE ACTIVITY TOTAL LINES IN SPECTRUM 20 LINES NOT LISTED IN LIBRARY 5

IDENTIFIED IN

SUMMARY

REPORT 15 75.00%

ACTIVATION PRODUCT 1-SIGMA NUCLIDE SBHR HLIFE DECAY pCI/ UNIT ERROR

% ERR MN-54 AP 312.50D 1.000 8.830E 1 4.788E -1 0.70 CO-58 AP 71.30D 1.008 1.592E 2 6.602E -1 0.41 CO-60 AP 5.26Y 1.000 1.410E 2 7.612E -1 0.54 FISSION PRODUCT 1-SIGMA NUCLIDE SBHR HLIFE DECAY pCI/ UNIT ERROR

% ERR C0-57 FP 270.00D 1.002 2.013E O 7.385E -2 3.67 CS-134 FP 2.06Y 1.001 1.514E 1 3.302E -1 2.18 CS-137 FP 30.17Y 1.000 7.504E 1 4.960E -1 0.65 NUCLIDE

SUMMARY

REPORT (REV 10/80)

PEAK WIDTH = 3.00 FWHM. CONFIDENCE LEVEL = 4.65.

RPO487-0029A-TP11

(

4 Page 2 pawe SURVEY INSTRUMENT RESPONSES R02 or R02A 1 cm from bead - window closed 25.0 nr/h window open 125.0 ar/h (reading)*

10 cm from bead - window closed

~0.2 ar/h window open 1.0 mr/h (reading)

In widely contaminated areas (many beads)

Factor Times Map Value Open Closed Dose rate at 3' x 1.5 x 1.0 Dose rate at 10 cm x 10 x 2.0 Dose rate at I cm x 20 x 4.0 HP-210 or HP-260 Pancake Probes 1.0 cm from bead - >1E05 cpm above background 10 cm from bead - 1,400 cpm above background 3' from I bead - 5 cpm above background Anywhere contamination is indicated on map, survey instrument with pancake O,'

probe will be off-scale high at any normal reading height. However, as con-tamination is removed so that R02 gives less than 100 mr/h open window, count rate will fall below 100,000 cpa: Ratio cpm to open window ar/h is 1,000 to 1.

Beta Dose Rate equals (open - closed) CF where CF is the instrument-specific beta correction factor. Most instruments have a CF around 4.0, so beta dose rate is around 400 m rad /h at 1 cm and 3 m rad /h at 10 cm.

RPO487-0029A-TP11-TP15

Page 3 Arr.r.wwe LAKE WATER ANALYSIS For lake water, assume one bead in a liter of water. One bead contains 7.3 pCi total activity, so total concentration is 7.3 E-3 pCi/al. Spectral constituents are as follows:

Nuclide pCi/ Bead pCi/cc Water Mn-54 1.1 1.1 E-03 Co-58 2.5 2.5 E-03 Co-60 2.3 2.3 E-03 Co-57 0.03 3.0 E-05 Cs-134 0.2 2.0 E-04 Cs-137 1.2 1.2 E-03 If water is filtered prior to analysis, all activity is found on filter.

It e

is not in filtrate.

I h

e i

i

/

4 i

t

(

e' 1

/

e 2

j RPO487-0029A-TP11 t

n

/

.* r,

/ A 'i j*

q 7

4-l '_ _

.4

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, * -+,,

_..f

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

SCENARIO NO PALEX-87 TIME =

0930 MESSAGE NO 9

T=

0045 O

V PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSAGE FOR: Security personnel in Security Building SIMULATED PLANT CONDITIONS:

MESSAGE: Severe winds strike plant. Debris flying around. Alarm: portal monitors CONTROLLER USE ONLY:

1) Resin spill has been disturbed. Herculite and resins have been blown north across the site and up the beach to the State Park.

2) Security should notify the Control Room of portal alarm.

i a

1 O

RP0387-0257F-TP12-TP11

,.,.,,,.,.m,,.,.,

-_n,.n-v.,,,.

i SCENARIO NO PALEX-87 TIME =

0934 MESSAGE NO 10 T=

0049 (3

m)

PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM l

MESSAGE FOR: RAD Techs responding to volume reduction system monitor alarm 1

SIMULATED PLANT CONDITIONS:

MESSAGE: One RAD Tech has slipped and fallen into the spilled resin. He has sustained a head injury. It is raining initially, then stops. Evidence of resin being washed into stora drain.

Victim Contact Readings:

2500 mr/h in hair initially, down to 1500 ar/h when rain stops 500 mr/h in clothing (inside PCs)

CONTROLLER USE ONLY:

1) Survey area rates available in onsite RAD data.

2) Provide messages verbally, survey readings only as requested.

.3 ) Victim (a Controller) will provide subsequent injury and contamination information.

4) Injury should be reported to Control Room /OSC. Ambulance should be called by Control Room /TSC.

-0 RP0387-0257F-TP12-TP11

SCENARIO NO PALEX-87 TIME =

0940 MESSAGE NO 11 T=

0055 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSAGE FOR: Spill assessment personnel / security guard (s)

SIMULATED PLANT CONDITIONS:

MESSAGE: Herculite has been strewn against security fence and beyond in bushes.

CONTROLLER USE ONLY: Message time approximate. This message will be given to O

players as judged appropriate by Controllers. Ultimately, surveys will indicate RAD levels greater than 500 ar/h beyond the site boundary, resulting in declaration of a site area emergency. At that point, the EOF will be activated if not already done. If players do not appear to be headed toward declaration of a site area emergency, the field team controllers may indicate that the spill encompasses State Park land. 'It was decided not to involve actual State property to avoid potential contact with the public. For exer-cise purposes, the contamination is assumed to have reached the State Park.

I i

RPO487-0029A-TP11

SCENARIO NO PALEX-87 TIME =

0945 MESSAGE NO 12 T=

0100 O

PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSAGE FOR: Control Room Operators SIMULATED PLANT CONDITIONS: See data sheets MESSAGE:

CONTROLLER USE ONLY:

l l

i

O RP0387-0257F-TP12-TP11

m..

J

. v u

Message:

12 Time:

'0945 T:

0100 Scenario PAln -87 j

C-08 C-02 C-01 i

i SW Pumps,Run P-7A Run P-7B Stdby P-7C (10) VCT Temp 120 *F MFP Suction Press 370 pois CCW Pusps Run P-52A Run P-52B Stdby P-52C (10) VCT Press 22 psi ^

MFP A Dsch Press

~940 psis I

FPC Pumps Run P-51A P-518 (10) VCT Level 72 %

MFP B Dsch' Press 940 psig PCP Control Bleedoff Press 80 psig APW Pump 8C Amperes' amps Containment Cooler Recirc Fans '

(26) letdown Flow (Diverting) 36 CPH APW Pump 8C Disch Press psig l

Run VIA Run V2A Run V3A Run V4A (26) Charging Flow 41 GPM AFW Pump 8A Amperes amps 1

Run V1B Run V2B Run V3B Run V4B (9) Quench Tank Temp 115 'F

'AFW Pump 8B Steam Press.

psig j

(9) Quench Tank Press.

0.5 psig

'APW Pumps 8A & 8B Disch Press pois C-03 (9) quench Tank Level 75 %

Moisture Sep Dr. Tank 64 %

(7) Pzr Press (R) 2010 psia Condenser Hotwell Level 65 %

(23) HPSI Pumps P-66A P-66B (8) Pzr Invel (R) LRC-0101A 57 %

Condenser Vacuum 27 in hg.

4 (24) LPSI Pumps P-67A P-675 LRC-0101B 57 %

Cland Seal Cond Vacuum 18 in hs.

I (18) Containment Spray Pumps (12) PORV PRV-10425 C

10438 C Atm.'Sta. Dumps Closed P-54A P-548 P-54C (12) Block MD-1042A C

1043A C AFW Feed Pumps PBA P8B P8C (27) HPSIA, LPSIA, Spray A Suction Charging Pumps Run P55A F55B F55C Heater Drain Pumps Run P10A Run F10B 0

CV-3057 (SIRWT)

C CV-3029 (Sump)

(6) PCPs Run PSOA Run P50B Run P50C Run P50D Condensate Pumps Run P2A Run F2B 4

(27) HPSIB, LFSIB, Spray B Suction Pzr Htr A:sps L.C.15130 L.C. 16 130 y

0 CV-3031 (SIRWT)

C CV-3030 (Sump)

(1) PCS T,,, (R)

Loop 1 (TR-0111) 562 *F

. PIP Loop 2 (TR-0121) M *F i

j C-02 (25) Reactor Power level-(Demand Log + Constant, Rod, or Flux / Temp)

NI-1 cps NI-3 100 % NI-7 100 %

Gross W 800 Intermediate Press 14tdown Temp 175 *P NI cps NI-4 100 f

% NI 100 %

Ne t W M Charging Line Temp 4_00 'F NI-5 100 % N1-9 100 %

(28) Control Rod Position

)

Letdows Line Temp 230 'F NI-6 100 % NI-10 100 CPI 132 CP2132 GP3132 CP4132 i

SDCS from PCS (R) 2 'F CP 5(P) 132 GP 6(A) 13,2. CP.7(B) 132, 3

SDCS to PCS (R)

F Stuck Rods X Yes No

. 36 (4) Core Exit Temp 53 'F e

i 4

4 l

I j

PP0387-0257E-TP12-TP11

. ~..

..~

')

O Mess 4 u 12

' Time:

0945 T:

0100 Scenario:

pal 2X-87 U

C-13 C-12 C-04 Ready Ready CST Level (T-2)'

80 %

PCP Current-(32) D/G 1-1 Stoby D/C 1-2 Stdby Instrument Air Press 105 psig A 620 amps B 630 amps (32) IC Buss Volts 2400 Amps OK (15) Containment Building Press 0.1 psig C 625 amps D 620 amps (32) 1D Buss Volts 2400 Amps. OK (16) S/G A Compartsent Temp 120 'F (6) PCS Flow 75 %.

S/C A Compartment Humidity 0%

(3).T Io0P 1 587 *F C-11 Back C-11A H

(16) S/G B Compartrent Temp 122 *F Loop 2 587 'F S/G B Compartment Humidity 0%

(2) T loop 1 537 'F (17) Containment Area Monitors c

j (16) Dome Temp 128 'F Imop 2 537 'F.

R1A 1805

.02 R/Hr RIA 1806

.03 R/Hr j

(11) SIRWI level 99 %

T WR(R) Loop 1 535 'F RIA 1807~.02 R/Hr RTA 1808 10" R/Hr g

(15) WR Cor,tainment Press (R) 14.8 psia loop 2 535 *F (17) High Range Containment Honitors 4

(14) Containment Sump Invel 0%

(5) Subcooling 3 *F 600 psig RIA 2321 1.01 R/Hr RIA 23221.01 R/Hr (14) Containment Water Level (R) 0%

(7) PCS WR Press (R) 2010 psia (19) Containment H 0 "**"E**EI "

2 y

I (22) S1 Tank Level (%) A 48 B 48 C 48 D 48 (7) PCS NR Press (R) psia AI 2401 R SI Tank Press (psig) A 210 B 210 C 210 D 210 (30) S/G A Invel WR 70 %

AI 2401 L i

(21) SIAS Yes X No (30) S/G A Level (R) 70 %

(30) Main Steam Canuma (30) S/G A Press 700 psia S/G A RIA 2324 40 cpm 6

Panel K-13 S/G A Steam Flow (R) 5.6 X10 PPH.

S/G B RIA 2323 30 cpm 6

S/G A Feed Flow (R) 5.6 X10 PPH (20) Containment High Pressure (30) S/G B 14 vel WR 70 %

Equipment Status:

Yes X No (30) S/G B Level (R) 70 %

(20) Contairment High Radiation (30) S/G B Press 700 psia 1.

Significant Equipment Outages

~

6 Yes X No S/G B Steam Flow (R)

_.5.6 X10 PPH (Inoperable Equipment) 6 S/G B Feed Flow (R) 5.6 X10 PPH 2.

Surveillance Due or in Progress C-12 3.

Abnormal Electrical Lineups or C-11 Outages

}

Conc. Boric Acid Tank Levels i

T53A y4 (31)

AFW Flow to SCA i

T53B 97 %

From P8A&B O spa From P8C 0 gpa Reactor Vessel DP 48 psid (31)

AFW Flow to SCB j

(12) PORV Discharge Temp 115 *F From P8A&B 0 gpm From P8C J gpa

]

(13) Pzr Safety Valve Dsch Temp Condenser Vacuum (R) y in hg.

f RV-1039 115 'F PCP A Leak'-off Flow (R) j CPM

{

RV-1040 115 'F.

PCP B Leak-off Flow (R) 1 GPM i

RV-1041 115 'F PCP C Leak-off Flow (R) 1 GPM PCP D Leak-off Flow (R)

J GPM i

RP0387-0257E-TP12-TP11

SCENARIO NO PALEX-87 TIME =

1015

-MESSAGE NO 13 T=

0130 l

O l

PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSAGE FOR: Control Room Operators SIMULATED PLANT CONDITIONS: See data sheets.

MESSAGE:

CONTROLLER USE ONLY:

O i

O RP0387-0257F-TP12-TP11 I

e

,w-,

-r e-w,-

n.

-- 4

--w..,,,,-,,

--v,----o,---

,,e----

y

--.-v--

<m

.n.-

a w-s

O g

. [^%,.

)

\\

)

J QJ Hessaget 13 Time:

1015 T:

0130 Scenario:

PAIIX-87 C-08 C-02 C-01 I

t SW Pumps Run P-7A Run P-7B Stdby P-7C (10) VCT Temp 120 *F MFP Suction Press 370 psig CCW Pumps Run P-52A Run F-52B Stdby P-52C (10) VCT Press 22 psi MFP A Dsch Press

%0 psig FPC Pumps Run P-51A P-51B (10) VCT I4 vel 72 %

MFP B Dsch Press 940 psig PCP Control Bleedoff Press 80 psig AW Pump 8C Amperes amps Containment Cooler Recirc Fans (26) Ietdown Flow 36 GPM AfW Pump 8C Disch Press psig Run VIA Run V24 Run V3A Run V4A (26) Qiarging Flow 41 GPM AW Pump 8A Amperes amps Run V1B Run V2B Run V3B Run V4B (9) Quench Tank Temp 115 'F AFW Pump 8B Steam Press psig (9) Quench Tank Press 0.5 psig AFW n;mps 8A in 8B Disch Press psig C-03 (9) Quench Tank level 75 %

Moisture Sep Dr Tank 64 %

(7) Pzr Press (R) 2010 psia Condenser Hotwell Level 65 %

(23) HPSI Pumps P-66A P-66B (8) Pzr Level (R) LRC-0101A 57 %

Condenser Vacuum 27 in hg.

(24) LPSI Pumps P-67A P-67B LRC-0101B 57 %

Gland Seal Cond Vacuum 18 in hg.

(18) Containment Spray Pumps (12) PORY PRV-1042B C

1043B C Atm Sta. Dumps Closed P-54A P-54B P-54C (12) Block MD-1042A C

1043A C APW Feed Pumps P8A P8B P8C (27) HPSIA, LPSIA, Spray A Suction Charging Pumps Run PSSA F55B P5SC Heater Drain Pumps Run P10A Run P10B O

CV-3057 (SIRWT)

C CV-3029 (Sump)

(6) PCPs Run P50A Run P50B Run P50C Run P50D Condensate Pumps Run P2A Run P2B l

(27) HPSIB, LPSIB, Spray B Suction Pzr Her Amps L.C.15130 L.C. 16 130 i

0 CV-3031 (SIRWT)

C CV-3030 (Sump)

(1) PCS T,y, (R)

Lwp 1 (TR-0111) 562 'F PIP j

loop 2 (TR-0121) 562 'F C-02 (25) Reactor Power level (Demand Log + Constant, Rod, or Flux / Temp)

NI-1 cps NI-3 100 % NI-7 100 %

Cross MW 800 Intermediate Press Letdown Temp 175,'F NI-2 eps NI-4 100 % NI-8 100 %

Net MW M Charging Line Temp 3 *F 4

N1-5 100 % NI-9 100 %

(28) Control Rod Position letdown Line Temp 230 'F NI-6 100 % NI-10 100 %

GPI 132 CP2 132 GP3 132 CP4 132 SDCS froet PCS (R)

F CP 5(P) 132 GP 6(A) 132 GP 7(B) 132 SDCS to PCS (R)

F Stuck Rods X Yes No

36 (4) Core Exit Temp g o_ 'F RP0387-0257E-TP12-TP11

N A

Mess 13 Time:

1015 T:

0130 Scen:rios PALEX-87 C-13 C-12 C-04 keady Ready CST Level (T-2) 80 %

PCP Current (32) D/G 1-1 Stoby D/G 1-2 Stdby Instrument Air Press 105 psig A g amps B 630, amps (32) IC Buss Volts 2400 Amps OK (15) Containment Building Press 0.1 psig C 625 arps D 620 amps (32) 1D Buss Volts 2400 Amps OK 2

(16) S/G A Compartment Temp 120 *F (6) PCS Flow 75 %

S/G A Compartment Humidity 0%

(3) T I4 P 1 587 *F C-11 Back C-11A H

(16) S/G B Compartment Temp 122 'F Loop 2 587 'F S/G B Compartment !!unidity 0%

(2) T, Imop 1 537 'F (17) Containment Area Monitors (16) Dome Temp 128 *F loop 2 537 'F RIA 1805

.02 R/Hr RIA 1806 03 R/Hr N

(11) SIRET level 99 %

T WR(R) Loop 1 535 *F RIA 1807

.02 R/Hr R1A 1808 IO R/Hr c

(15) WR Containment Press (R) 14.8 psia loop 2 535 *F (17) High Range Containment Monitors (14) Containment Sump Level 0%

(5) Subcooling 3 'F 600 psig RIA 2321 1.01 R/Hr RIA 2322 1.01 R/Hr (14) Containment Water Level (R) 0%

(7) PCS WR Press (R) 2010 psia (19) Containment H Concentration 2

(22) bl Tank Level (%) A 48 B 48 C 48 D 48 (7) PCS NR Press (R) psia AI 2401 R SI Tank Press (psig) A 210 B 210 C 210 D 210 (30) S/G A level WR 70 %

Al 2401 L (21) SIAS Yes X No (30) S/G A Level (R) 70 %

(30) Hain Steam Camma (30) S/G A Press 700 psia S/G A RIA 2324 40 cpm 6

Panel K-13 S/G A Steam Flow (R) 5.6 X10 PPH S/G B RIA 2323 30 cpm 6

S/G A Feed Flow (R) 5.6 X10 PPH (20) Containment High Pressure (30) S/G B Level WR 70 %

Equipment Status:

Yes X No (30) S/G B Level (R) 70 %

(20) Containment High Radiation (30) S/C B Press 700 psia 1.

Significant Equipment Outages 6

Yes X No S/G B Steam Flow (R) 5.6 X10 PPH (Inoperable Equipment) 6 S/G B Feed Flow (R) 5.6 X10 PPH 2.

Surveillance Due or in Progress C-12 3.

Abnorme1 Electrical Lineups or C-11 Conc. Boric Acid Tank Levels Outages T53A y%

(31)

AW Flow to SGA T53B 97 %

From P8A&B 0 gpm From P8C J gpm Reactor Vessel DP 3 psid (31)

A N Flow to SGB l

(12) PORY Discharge Temp 115,'F From P8A&B 0 gpm From P8C J gpm

~

(13) Pzr Safety Valve Dsch Temp Condenser Vacuum (R) 3 in hg.

RV-1039 115 *F PCP A Leak-off Flow (R) 1 GPM RV-1040 M 'F PCP B Leak-off Flow (R)

J GPM RV-1041 115 *F PCP c Leak-of f Flow (R) 1 GPM

]

PCP D Leak-off Flow (R)

J GPH RP0387-0257E-TP12-TP11 1

.. SCENARIO NO PALEX-87 TIME =

1045-MESSAGE NO 14

.T=

0200 O

PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM j

MESSAGE FOR: Control Room Operators SIMULATED PLANT CONDITIONS: See data sheets.

I

.l MESSAGE:

I l

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i O

RP0387-0257F-TP12-TP11

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V Message:

14 Time:

10t.5 T:

0200 Scenario: _ PALEX-87_,

4 1

C-08 C-02 C-01 SW Pumps Run P-7A Run P-7B Stdby P-7C (10) VCT Temp 120 'F HFP Suction Press

_ 370 psig CCW Pumps Run F-52A Run P-52B Stdby P-52C (10) VCT Press 22 psi HFP A Dsch Press

%0 psig 3

FPC Pumps Run P-51A P-51B (10) VCT level 72 %

MFP B Dsch Press 940 psig j

PCP Control Bleedoff Press 80 psig AFW Pump 8C Amperes amps I

Containment Cooler Recirc Fans (26) 14tdown Flow 36 CPM AFW Pump 8C Disch Press

_ _ psig Run VIA Run V2A Run V3A Run V4A (26) Charging Flow 41 GPM AFW Puep 8A Amperes

_ _ amps 4

Run V1B Run V2B Run V3B Run V4B (9) Quench Tank Temp 115 'F AEW Pump 8B Steam Press psig (9) Quench Tank Press 0.5 psig AFW Pumps 8A & 8B Disch Press psig C-03 (9) Quench Tank Level 75 %

Moisture Sep Dr Tank 64 %

(7) Pzr Press (R) 2010 psia Condenser Hotwell level 65 %

(23) HPSI Pumps P-66A P-66B (8) Pzr level (R) LRC-0101A 57 %

Condenser Vacuum 27 in hg.

(24) LPSI Pumps P-67A P-67B LRC-0101B 57 %

Cland Seal Cond Vacuum 18 in hg.

(18) Containment Spray Pumps (12) PORY PRV-10428 C

1043B C Atm. Stm. Dumps Closed P-54A P-54B P-54C (12) Block MD-1Cf 2A C

1043A C AIV Feed Pumps P8A P8B P8C (27) HPSIA, LPSIA, Spray A Suction Charging Pumps Run PSSA P55B P55C Heater Drain Pumps Run F10A Run P10B O

CV-3057 (SIRWI)

C CV-3029 (Sump)

(6) PCPs Run P50A Run P50B Run P50C Run P50D Condensate Pumps Run P2A Run P2B i

(27) HPSIB, LPSIB, Spray B Suction Pzr Htr Amps L.C.15130 L.C. 16 130 O

CV-3031 (STRWI)

C CV-3030 (Sump)

(1) PCS T,y, (R)

Loop 1 (TR-0111) 562 'F PIP loop 2 (TR-0121) 5_62 'F 6

C-02 (25) Reactor Power level (Demand Log + Constant, Rod, or Flux / Temp)

NI-1 cps NI-3 100 % NI-7 100 %

Gross MW g Intermediate Press Letdown Temp 175 *F NI-2 cps NI-4 100 % NI-8 100 %

Net MW-g 4

NI-5 100 % NI-9 '100 %

(28) Control Rod Position Charging Line Temp 3 'F Intdown Line Temp 230 *F NI-6 100 % NI-10 100 %

CP1 132 GP2 132 CP3 132 CP4 132 SDCS from PCS (R)

F CP 5(P) 132 CP 6(A) 132 CP 7(B) 132 SDCS to PCS (R)

'F Stuck Rods ' X -- Yes No e 36 (4) Core Exit Temp g 'F 1

1 RP0387-0257E-TP12-TP11

In Me ssy-14 Times 1045 _

T:

0200 Scintrior PAI2X-87 ~

C-13

.C-12 C-04 Ready Ready CST Level.(T-21 80 %

PCP Current (32) D/C 1-1 Stdby D/G 1-2 Stdby Instrument Air Press 105 psig A 620 amps B 630 amps (32) IC Buss Volts 2400 Amps OK (15) Containme.t Building Press 0.1 pois C g amps D 6_20 amps (32) ID Burs Volts 2400 Amps OK 2

(16) S/G A Compartment Temp 120 'F (6) PCS Flow-75 %

S/G A Compartment Humidity

-0%

(3) T %1 587 'F C-11 Pack C-11A H

(16) S/G B Compartment Temp 122 'F Loop 2 587

'F-S/G B Compartment Humidity 0%

(2) T, Imop 1 537 'F (17) Containment Area Monitors (16) Deme Temp 128 'F Isop 2 537 'F RIA 1805

.02 R/Hr RIA 1806 0.3 R/Hr (11) SIRWI Level 99 %

T,WR(R) Loop 1 535 'F RIA 1807

.02 R/Hr RIA 1808.10" R/Hr (15) WR Containment Press (R) 14.8 psia loop 2 535 'F (17) High Range Containment Honitors (14) Containment Stanp Level 0%

(5) Subcooling y *F 600 psig.

RIA 2321 1.01 R/Hr -RIA 2322.' 1.01 R/Hr.

(14) Containment Water Level (R) 0%

(7) PCS WR Press (R) 2010 psia (19) Containment H Concentration 2

(22) SI Tank Level (%) A 48 B 48 C 48 D 48 (7) PCS ER Press (R) psia AI 2401 R SI Tank Press (psig) A 210 B 210 C 210 D 210 (30) S/G A Level WR 70 %

Al 2401 L (21) SIAS Yes X No (30) S/G A level (R) 70 %

(30) Nain Steam Gamma (30) S/G A Press 700 psia S/G A RIA 2324

' 40 cpm 6

Panel K-13 S/G A Steam Flow (R) 5.6 X10 PPH S/G B RIA 2323 30 cpm 6

S/G A Feed Flow (R) 5.6 X10 PPH-(20) Containment High Pressure (30) S/G B Invel WR 70 %

Et!uipment Status:

Yes X No (30) S/G B level (R) 70 %.

(20) Containment High Radiation (30) S/G B Press 700 paia 1.

Significant Equipment Outages 6

Yes X No S/C B Steam Flow (R) 5.6 X10 PPH.

(Inoperable Equipment) 6 S/G B' Feed Flow (R) 5.6 X10 PPH 2.

Surveillance Due or.in Progress C-12 3.

Abnormal Electrical Lineups or C-11 Outages Conc. Boric Acid Tank Levels T53A y%

(31)

AFW Flow to SCA T53B y%

From P8A&B J ppm From P8C J gym Reactor Vessel DP y paid (31)

APW Flow to SGB (12) PORV Discharge Temp 115 'F From P8A&B 0 Fpm From P8C J gpa (13) Pzr Safety Valve Dsch Temp Condenser Vacuum (R) y in hg.

Rv-1039 115 'F PCP A Leak-off Flow (R)-

J CPM RV-1040 M 'F PCP B Isak-of f Flow (R)

J GPM

~ 15 *F PCP C Leak-off Flow (R) 1 CPM RV-1041 1

PCP D Leak-off Flow (R)

J GPM.

RP0387-0257E-TP12-TP11

~._.

SCENARIO NO PALEX-87 TIME =

1115 i

MESSAGE NO 15 T=

0230 PALISALES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSAGE FOR: Control Room Operators i

SIMULATED PLANT CONDITIONS: See data sheets.

i MESSAGE:

O CONTROLLER USE ONLY:

f 4

t i

O RP0387-0257F-TP12-TP11

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

-r

.f 3

NJ Message:

15 Time:

1115 T:

0230 Scenario:

PAIEX-87 _

C48 C42 C41 SW Pumps Run P-7A Run P-7B Stdby P-7C (10) VCT Temp 120 'F MFP Suction Press 370 psig CCW Pumps Run P-52A Run P-52B Stdby P-52C (10) VCT Press 22 psi MFP A Dsch Press

%0 psig FPC Pumps Run P-51A P-51B (10) VCT Level 72 %

MFP B Dsch Press 940 psig PCP Control Bleedoff Press 80 psig AW Pump 8C Amperes

. asps Containment Cooler Recirc Fans (26) letdown Flow 36 CPM A W Pump BC Disch Press psig Run VIA Run V2A Run V3A Run V4A (26) Charging Flow 41 CPfl AW Pump 8A Amperes amps Run V1B Run V2B Run V3B Run V4B (9) Quench Tank Temp 115 *F AW Pump 8B Steam Press psig (9) Quench Tank Press 0.5 psig AW Pumps 8A & 8B Disch Press psig C-03 (9) Quench Tank Level 75 %

Moisture Sep Dr Tank 64 %

(7) Pzr Press (R) 2010 psia Condenser Hotwell level 65 %

(23) HPSI Pumps P-66A P-66B (8) Pzr level (R) LRC-0101A 57 %

Condenser Vacuus 27 in hg.

(24) LPSI Pumps P-67A P-67B LRC-0101B 57 %

Gland Seal Cond Vacuum 18 in hg.

(18) Containment Spray Pumps (12) PORY PRV-1042B C

1043B C Atm. Stm.. Dumps Closed P-54A P-54B P-54C (12) Block HO-1042A C

10r.3A C

A W Feed Pumps P8A P8B P8C (27) HPSIA, LPSIA, Spray A Suction Charging Pumps Run P55A PSSB P55C Heater Drain Pumps Run P10A Run F10B 0

CV-3057 (SIET)

C CV-3029 (Sump)

(6) PCPs Run P50A Run P508 Run P50C Run P50D Condensate Pumps Run P2A Run P2B (27) HPSIB, LPSIB, Spray B Suction Pzr Htr Amps L.C. 15 130 L C.16130 0

CV-3031 (SIET)

C CV-3030 (Sump)

(1) PCS T,y, (R)

Loop 1 (TR-0111) 562 'F PIP Loop 2 (TR-0121) 562 'F 2

C-02 (25) Reactor Power level (Demand Log + Constant, Rod, or Flux / Temp)

NI-1 eps NI-3 100 % NI-7 100 %

Cross MW g Intermediate Press latdown Temp 175 *F N1-2 eps NI-4 100 % NI-8 100 %

Net MW M Charging Line Temp g 'F NI-5 100 % NI-9 100 %

(28) Control 1:od Position letdown Line Temp 230 *F NT-6 100 % NI-10 100 %

CP1132 CP2132 CP3132 CM 132 SDCS from PCS (R)

'F CP 5(P) 132 CP 6(A) 132 CP 7(B) 132 SDCS to PCS (R)

'T Stuck Rods X Yes No

36 (4) Core Exit Temp 590 "F i

9 KP0387-0257E-TP12-IP11

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O lies % :

15 Time:

1115 T

0230

-Scenario:

PAIEX C-13 C-12 C-04 d

Ready'

. Ready CST level (T-2) 80 %

PCP Current (32) D/G 1-1 S_tdby D/G 1-2 Stdby Instrument Air Press 105 psig A 620, amps B 630 amps (32) IC Buss Volts 2400 Amps OK (15) Containment I>uilding Press 0.1 psig

.C 625, amps D 6_20 amps (32) 1D Buss Volts 2400 Amps OK.

2 (16) S/G A Compartment Temp 120 *F (6) PCS Flow 75 %

S/G A Comparteient Humidity 0%

(3) T ISOP 1 587 *F C-11 Back C-11A H

(16) S/G B Ccepartment Temp 122 'F Loop 2 587 *F j

S/G B Compartment Humidity 0%

(2) T IceP 1 537 'F (17) Containment Area Monitors c

(16) Dome Temp 128 *F Imop 2 537 'F RIA 1805

.02 R/Hr RIA 1806

.03 R/Hr (11) SIRWI 14vc1 99 %

T, WR(R) Loop 1 535 'F~

RIA 1807

.02 R/Hr RIA 1808 lokR/Hr (15) WR Containment Press (R) 14.8 psia loop 2 535 *F (17) High Range Containment Monitors (14) Containment Sump level 0%

(5) Subcooling 3 'F 600 psig RIA 23211.01 R/Hr RIA 2322 1.01 R/Hr (14) Containment Water level (R) 0%

(7) PCS WR Press (R) 2010 psia (19) Containment H Concentration 2

(22) SI Tank Level (%) A 48 B 48 C 48 D 48 (7) PCS NR Press (R) psia AI 2401 R g%

Si Tank Press (psig) A 210 8 210 C 210 D 210 (30) S/G A level WR 70 %

AI 2401 L (21) SIAS Yes X No (30) S/G A level (R) 70 %

(30) Main Steam Gamusa (30) S/G A Press 700 psia S/G A RIA 2324 40 cpm 6

l Panel K-13 S/G A Steam Flow (R) 5.6 X10 PPH S/G B R1A 2323 30 cpm 6

S/G A Feed Flow (R) 5.6 X10 PPH (20) Containment High Pressure (30) S/G B level WR 70 %

Equipment Status:

Yes X No (30) S/G B Level (R) 70 %

(20) Containment High Radiation (30) S/G B Press 700 psia 1.

Significant Fquipment Outages 6

i Yes X No S/G B Steam Flow (R) 5.6 X10 PPH (Inoperable Equipment) 6 S/G B Feed Flow (R) 5.6 X10 PPH

' 2.

Surveillance Due or in Progress C-12 3.

Abnormal Electrical Lineups or C-11 Outages i

Conc. Boric Acid Tank Levcis T53A y%

(31)

AW Flow to SGA.

T53B 97 %

From P8A&B 0 spe' From P8C J gpa 1

Reactor Vessel DP 3 psid (31)

A W Flow to SGB (12) PORV Discharge Temp 115 *F From P8A&B 0 spa From P8C J gpm (13) Pzr Safety Valve Dsch Temp Condenser Vacuum (R) y in hg.

RV-1039 115 *F PCP A Leak-off Flow (R).

1 Citt RV-1040 115 *F PCP B laak-off Flow (R) 1 GPM RV-1041 115 *F PCP C leak-off Flow (R) 1 CPM PCP D Leak-off Flow (R) 1 CPM RP0387-0257E-TP12-TP11

SCENARIO NO PALEX-87 TIME =

1145 MESSAGE NO 16 T=

0300 0

PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSAGE FOR: Control Room Operators SIMULATED PLANT CONDITIONS: See data sheets.

i MESSAGE:

t i-I CONTROLLER USE ONLY:

1 I

i h

i s

O

-RP0387-0257F-TP12-TP11 i

. ~

O..

N-

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f' w

Message 16 Time:

1145 T:

0300 Scenario:

PAIIX-87 C-08 C-02 C-01 f

SW Pumps Run P-7A kn P-7B Stdby P-7C (10) VCT Temp 120 'F MFP Suctio'n Press 370 psig CCW Ptsops Run P-52A Run P-52B Stoby P-52C (10) VCT Press 22 psi MFP A Dsch Press 940 psig FPC Pumps Run P-51A P-51B (10) VCT Level 72 %.

MFP B Dsch Press 940 psig PCP Control Bleedoff Press 80 psig AW Pump 8C Amperes amps Containment Cooler Recirc Fans (26) letdown Flow 36 GPM A W Pump BC Disch Press psig Run 71A Run V2A Run V3A Run V4A (26) Charging Flow 41 GPM AW Pump 8A Amperes amps Run V1B Run V2B Run V3B Run V4B (9) Quench ' Tank Temp 115 'F A W Pump 8B Steam Press psig (9) Quench Tank Press 0.5 psig APW Pumps 8A & 8B Disch Press psig C-03 (9) Quench Tank Level 75 %

Moisture Sep Dr Tank 64 %

(7) Pzr Press (R) 2010 psia Condenser Hotwell I4 vel 65 %

(23) IIPSI Purps P-66A P-66B (8) Pzr Level (R) LRC-0101A 57 %

Condenser vacuum 27 in hg.

(24) LPSI Pumps P-67A P-67B LRC-0101B 57 %

Gland Seal Cond Vacuum 18 in hg.

(18) Containment Spray Pumps (12) PORV PRV-1042B C

1043B C Atm. Sta. Dumps Closed P-54A P-54B P-54C (12) Block MD-1042A C

1043A C AW Feed Pumps P8A P85 P8C (27) IIPSIA, LPSIA, Spray A Suction Charging Ptaps Run PSSA P55B F55C llester Drain Pumps Run PinA Run F10B O

CV-2057 (SIRWI)

C CV-3029 (Sump)

(6) PCPs Run P50A Run P50B Run P50C Run P50D Condensate Pumps Run P2A Run P2B (27) HPSIB, LPS1b, Spray B Suction Pzr 11tr Amps L.C.15130 L.C. 16 130 O

CV-3031 (SIRWI)

C CV-3030 (Supp)

(1) PCS T,y, (R)

Loop 1 (TR-0111) 562 *F PIP Loop 2 (TR-0121) 562 'F C-02 (25) Reactor Power level (Demand Log + Constant, Rod, or Flux / Temp)

NI-1 cps NI-3 100 % NI-7 100 %

Cross MW 83 Intermediate Press letdown Temp 175, *F NI-2 eps NI-4 100 % NI-8 100 %

Net MW 760 Charging Line Temp 400,'F NI-5 100 % NI-9 100 %

(28) Control Rod Position Letdown Line Temp 230 *F NI-6 100 % NI-10 100 %

GP1 132 CP2 132 CP3 132 CP4 132 SDCS from PCS (R)

'F CP 5(P) 132 GP 6(A) 132 GP 7(B) 132 SDCS to PCS (R)

F Stuck Rods X Yes No

36 (4) Core Exit Temp g 'F I

RP0387-0257E-TP12-TP11

c O

O Mess g:rt 16 Time:

1145 T:

0300 Securioi PA15X-87 C-13 C-12 C-04 Ready Ready CST Level (T-2) 80 *.

PCP Current (32) D/G 1-1 Stdby D/C 1-2 Stdby Instrument Air Press 105 psig A g amps B 630, amps (32) IC Buss Volts 2400 Amps OK (15) Containment Building Press 0.1 psig C g amps D 620 amps (32) 1D Buss Volts 2400 Amps OK (16) S/G A Compartment Temp 120 'F (6) PCS Flow 75 %

S/C A Compartment Humidity 0%

(3) T %1 587 *F C-H Back C-nA H

(16) S/G B Compartment Temp 122 *F Loop 2 587 'F S/G B Compartment Humidity 0%

(2) T, loop 1 537 'F (17) Containment Area Monitors (16) Dome Temp 128 'F Icop 2 537 'F RIA 1805

.02 R/Hr RIA 1806.03 R/Hr (11) SIRWT Level 99 %

T, WR(R) Loop 1 535 'F

.RIA 1807

.02 R/Hr RIA 1808 10" R/Hr (15) WR Containment Press (R) 14.8 psia loop 2 535 'F (17) High Range Containment Monitors (14) Containment Sump Level 0%

(5) Subcooling y 'F 600 psig RIA 2321 1.01 R/Hr RIA 2322 1.01 R/Hr (14) Containment Water level (R) 0%

(7) PCS WR Press (R).

2010 psia (19) Containment H Concentration 2

(22) SI Tank Level (%) A 48 B 48 C 48 D 48 (7) PCS NR Press (R) psia AI 2401 R g%

S1 Tank Press (psig) A 210 B 210 C 210 D 210 (30) S/G A level WR 70 %

AI 2401 L (21) SIAS Yes X No (30) S/C A I4 vel (R) 70 %

(30) Main Stesa Gamma (30) S/G A Press 700 psia S/G A RIA 2324 40 cpm 6

Panel K-13 S/G A Steam Flow (R) 5.6 X10 PPH S/G B RIA 2323 30 cpm 6

S/G A Feed Flow (R) 5.6 X10 ppg (20) Containment High Pressure (30) S/G B level WR 70 %

Equipment Status:

Yes I No (30) S/G B Level (R) 70 %

(20) Containment High Radiation (30) S/G B Press 700 psia 1.

Significant Equipment Outages 6

Yes X No S/G B Steam Flow (R) 5.6 X10 PPH (Inoperable Equipment) 6 S/G B Feed Flow (R) 5.6 X10 PPH 2.

Surveillance Due or in Progress C-12 3.

Abnorral Electrical Lineups or C-11 Outages Conc. Boric Acid Tank Levels T53A y%

(31)

AFW Flow to SGA T53B y%

From P8A&B J gpa From P8C 0 gpm Reactor Vessel DP y psid (31)

AFW Flow to SCB (12) PORV Discharge Temp 115 'F From P8A&B 0 gpa From P8C 0 gpm (13) Pzr Safety Valve Dsch Temp Condenser Vacuum (R) y in hg.

RV-1039 115 *F PCP ?. Leak-off Flow (R) 1 CPM RV-1040 115 'F PCP B leak-of f Flow (R) 1 GPM RV-1041 115 'F PCP C Leak-of f Flow (R) 1 CPM PCP D Leak-of f Flow (R)

J GPM RP0387-0257E-TP12-TP11

SCENARIO NO PALEX-87 TIME =

1330 MESSAGE NO 17A T=

0445 O

PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSAGE FOR: Control Room Players SIMULATED PLANT CONDITIONS: Exercise terminated for Control Room personnel.

MESSAGE: The exercise has been terminated for all personnel except those in the TSC and F0F who will continue with development of a recovery plan. Make the following public address announcement: " Attention all personnel. The annual emergency exercise has been terminated for all personnel except those in the TSC and EOF. Following your facility critiques you may return to normal duty."

O CONTROLLER USE ONLY: Conduct facility critique. You may provide recovery parameters to Control Room personnel for their information.

O RPO487-0029A-TPil-TP15 1

- ~

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

SCENARIO NO PALEX-87 TIME =

1330 MESSAGE NO 17B T=

0445 O

PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSAGE FOR: OSC Personnel SIMULATED PLANT CONDITIONS: Exercise terminated for OSC personnel.

MESSAGE: The exercise has been terminated for all personnel except those in the TSC and SOF who will continue with development of a recovery plan.

CONTROLLER USE ONLY: Conduct OSC critique when field teams arrive.

You may

.\\

provide recovery parameters to OSC/ Field Team personnel for their information.

l FP0487-0029A-TP11-TP15

SCENARIO NO PALEX-87 TIME =

1330 NESSAGE NO 17C T=

0445

\\~J PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSAGE FOR: MSC Personnel SIMULATED PLANT CONDITIONS: Exercise terminated for MSC personnel.

I MESSAG": The exercise has been terminated for all personnel except those in the TSC and EOF who will continue with development of a recovery plan.

O CONTROLLER USE ONLY: Conduct facility critique.

You may provide recovery parameters to MSC personnel for their information.

i i

O RPO487-0029A-TPil-TP15 l

I

SCENARIO NO PALEX-87 TIME =

1330 MESSAGE NO 17D T=

0445 O

PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSAGE FOR: Field Teams SIMULATED PLANT CONDITIONS: Exercise terminated for field teams.

MESSAGE: The exercise has been terminated for all personnel except those in the TSC and EOF who will continue with development of a recovery plan. Report to the OSC to participate in the facility critique.

CONTROLLER USE ONLY:

O Ree4ez-ee m - m i

SCENARIO NO PALEX-87 TIME =

1330 MESSAGE NO 17E T=

0445 PALISADES NUCLEAR PLANT EMERGENCY PREPAREDNESS EXERCISE MESSAGE FORM MESSAGE FOR: TSC and EOF Personnel SIMULATED PLANT CONDITIONS:

MESSAGE: Review the attached data sheets and take about an hour to develop a plan for recovery. Submit the plan to the EOF Lead Controller when complete.

CONTROLLER USE ONLY: Once a recovery plan has been submitted, terminate the exercise and conduct TSC and EOF critiques.

1 RPO487-0029A-TP11-TP15

, - ~ _ - - - - -

M & W /74-t

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SCENARIO CONDITIONS -

PM, 5/20/87 1.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months have elapsed. During that period, you were relieved by another shift. You have now returned to duty.

2.

Contaminated areas havs been fully posted and secured by CP Co personnel.

3.

The following has occurred since you were relieved:

a.

Heavy equipment was brought in and approximately three inches of the surface of contaninated areas, except pavement, were removed (sand, gravel and rock).

b.

Residual radiation levels are approximately.12 mr/h in all areas ini-tially contaminac.ed except: 1. near the drain outlet which reads approximately 400 mr/h; and 2. Area at the Site Boundary with the State Park, whicit shows no residual contamination. All contamination is within 100 yards of the protected area or 550 yards from the boundary with the park. No beta is detected (R02 open and closed readings equal) and occasionally HP-210 net count rate is greater than 100 cpm.

c.

In all,18 truchloads full of sand, rock, gravel and soil were removed and are being stored in an appropriate, secured location.

O d.

Based on estimates of resins spilled and readings of material col-lected, it is believed that approximately 90% to 95% of resins spilled have been recoveted.

e.

Washup continued through the night in the area initially contaminated and was subsequently cleaned up.

No further washup is occurring in the immediate area. Monitoring of the beach for 10 miles north and south of the plant has shown no evidence of contamination. Water sam-ples taken througho:st the 10-mile lake portion of the EPZ have shown no contamination.

O RPO487-0029A-TPil-TP15

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METEOROLOGICAL TOWER DATA

/'N 05/19/87 0800 15-MINUTE AVERACES

(

j PARAMETER TEMP STAB DT WS10 WD10 SICI WS60 WD60 SIG6 PRECIP N _,/

UNITS C

PASQ C

MPH DEG DEG MPH DEG DEG (IN/HR) s 05/19/87 0800 16.0 C

-0.73 17.0 252 12.4 24.7 240 12.3 Status 00 DT 05/19/87 0815 16.1 C

-0.71 17.1 235 12.2 26.6 241 12.1 Status 00 DT 05/19/87 0830 16.2

.D

-0.30 16.3 276 8.2 27.0 263 9.3 Status 00 DT 05/19/27 0845 16.3 E

-0.24 21.9 289 7.0 28.7 292 7.1 Status 00 DT 05/19/87 0900 16.3 E

-0.22 22.9 252 7.2 31.8 265 6.5 Status 00 DT 05/19/87 0915 16.1 E

-0.20 5.2 215 6.7 12.4 248 10.3 0.4 Status 00 DT 05/19/87 0930 15.9 F

-0.10 57.6 184 16.5 78.4 108 13.7 3.7 Status 00 DT 05/19/87 0945 16.0 E

-0.20 12.3 174 7.5 22.7 168 6.8 1.5 Status 00 DT 05/19/87 1000 16.6 r

-0.73 4.5 152 5.3 6.2 148 7.0 Status 00 DT 05/19/87 1015 16.7 E

-0.22 5.7 172 5.6 7.0 160 5.5 Status 00 DT

,r ss

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05/19/87 1030 16.8 E

-0.24 3.5 178 6.7 4.7 172 6.2 Status 00 DT 05/19/87 1045 16.9 E

-0.24 4.3 166 7.2 5.8 170 6.5 Status 00 DT 05/19/87 1100 17.1 D

-0.26 5.1 185 7.7 6.4 182 7.3 Status 00 DT 05/19/87 1115 17.2 E

-0.23 7.2 177 6.6 8.4 180 6.8 Status 00 DT 05/19/87 1130 17.4 E

-0.24 5.0 172 6.5 6.9 175 6.6 Status 00 DT 05/19/87 1145 17.6 D

-0.28 5.2 168 7.8 7.5 172 8.3 Status 00 DT 05/19/87 1200 17.7 E

-0.24 5.4 170 6.3 7.0 165 7.0 Status 00 DT 05/19/87 1215 17.9 D

-0.32 5.9 176 8.2 7.4 173 7.8 Status 00 DT

,Oi

\\g METEOROLOGICAL TOWER DATA

2 Results of WSI forecasts requested prior to 1000:

+ - MOSPAL-Interpolated MOS for PAL (4219N, 8619W) using ORD, SBN and GRR:

Date/GNT 19/06 19/12 19/18 20/00 20/06 20/12 20/18 21/00

'Date/EST 19/01 19/07 19/13 19/19 20/01 20/07

_20/13 20/19 Wind-sph 2220 1927 1810 1808 1705 1905

-2008 1805 Cids.1 2

10 5

2 6

2

.1 1

- Hat-f t -

7200 800 800 1500 2000

> 7500

> 7500 PAS D

E C

D E

E E

E

+ LOGOUT Results of WSI forecasts requested after 1000:

+ - MOSPAL Interpolated MOS for PAL (4219N, 8619N) using ORD, SBN, GRR:

Date/GMT 19/12 19/18 20/00 20/06 20/12 20/18 21/00 21/06 i

Date/EST 19/07 19/13 19/19 20/01 20/07 20/13 20/19 21/01-

-Wind-MPH 1829 1810 1708 1905 3010 2710 2705 2703

?

--Clds.1 10 4

6 8

6 2

2 1

Hgt-ft 500 500 500 2000 5000 7000

> 7500

> 7500 PAS.

E C

C

C D

D D

E

-(

+ LOGOUT i

9 Y

t f-1 i

()

f RP0686-0150A-TP13-TP14 l

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RESIN SPILL CONTAMINATIdi AND RADT'ATION LEVELS s

The following map provides Ekvels of contamination and fshine inunediately

~

following resin ' spill disperiial by high winds. Players should realize that resinf have entered the 'lak.g from the drain adjacent to the plant and directly through the air from the prOximiity of the contaminated ', area to the North at the water line. Visual clues (simulated herculite) wf31 be provide'd to assist players in determining extent of contamination. At tt.4 gime.of res'in dispersal, portals in the Ser/arity Bdilding will alarm; the friske'r' will read offscale -

500,000 cpm.

9 F,

j.

n, s,

r Cleanup person e~. kill be directed to physically collect simulated resins.I Their effectf u ness will be judged by the assigned HP Controller. - ('werall ;

sudcass in re'.

tion' of contamination and rad levels will be judged by the Idad Field HPs ' croller..4.

g Due to the resins ' that enter t'ne lake, washup will continue along the beach.

l The extent of washup, success of cleanup, and rad levels will be determined by the Lead lield lip Controller.

~

j.

/'

Cleanup will be considered complete when:

el 1.

Contamination is removed to the fullest extent possible recognizing limitations: yegt.tation will not be removed, lake washup, contamination in riprap.

p'

~

1 2.

Plans have bee'n formulated for long-term monitoring, short-term monitoring,

.e disposal / storage of collected resins.

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ML20214L755

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