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Exercise Manual, Approved by Util as Std for Conduct in Performance of 911016 NRC Graded Exercise
	ML18017A259
Person / Time
Site:	Susquehanna
Issue date:	10/16/1991
From:	; PENNSYLVANIA POWER & LIGHT CO.
To:	;
References
	RTR-NUREG-0654, RTR-NUREG-654 PROC-911016, NUDOCS 9111130023
	Download: ML18017A259 (326)
	v • d • e

FOHB 2 DISTRIBUTIO REGULA Y INFORMATION YSTEM (RIDS)

ACCESSION NBR:9111130023 DOC.DATE: 91/10/16 NOTARIZED: NO DOCKET FACIL:50-387 Susquehanna Steam Electric Station, Unit 1, Pennsylva 05000387 50-388 Susquehanna Steam Electric Station, Unit 2, Pennsylva 05000388 AUTH. NAME AUTHOR AFFILIATION

Pennsylvania Power & Light Co.

RECIP.NAME RECIPIENT AFFILIATION "Exercise Manual," approved by util as std for conduct in

SUBJECT:

performance of 911016 NRC graded exercise.~i~ ~

DISTRIBUTION C(8E: DF03D COPIES RECEIVED:LTR iITLE: Direct Flow Distribution: Subject Files J

6 ENCL Q SIZE:

40,70,71 Dkts w out LPDRs NOTES:LPDR 1 cy Transcripts. 05000387

~

LPDR 1 cy Transcripts. 05000388 33 RECIPIENT COPIES RECIPIENT ID CODE/NAME LTTR ENCL ~ CODE/NAME

,COPIES

'LTTR ENCL INTERNAL: NUDOCS-ABSTRACT 1 1 REG FILE 01 P I EXTERNAL: NRC PDR 1 1 NOTES: 2 2 TOTAL NUMBER OF COPIES REQUIRED: LTTR 5 ENCL 5

FORWARD This exercise package has been developed to provide the basis for conduct of the simulated radiological accident at the Susquehanna Steam Electric Station Unit 81, located in Luzerne County, the state of Pennsylvania.

The exercise will test and evaluate the effectiveness and capabilities of the Emergency Preparedness Response Program for the Pennsylvania Power and Light Company. This package is to be utilized by the exercise referees to initiate, control, and evaluate the activities of the participants in the exercise.

The Pennsylvania Power and Light Company approves this document as the standard for conduct in performance of the October 16, 1991 NRC Graded Exercise.

This Exercise Manual has been reviewed and approved by the following Task Force members:

MEMBERS OF THE TASK FORCE RESPONSIBLE FOR EXERCISE SCENARIO OPERATIONS: Dave Walsh, Bill DiDomenico SECURITY: Brian McBride PUBLIC INFORMATION: Ira Kaplan GENERAL OFFICE: Jack Refling.

HEALTH PHYSICS: Margaret Rochester CHEMISTRY: Karen Ziolkowski RAD & ENVIRONMENTAL: Bruce Carson 9111i30023 9iiOib PDR ADOCN, 05000387

FORWARD TABLE OF CONTENTS PAGE SECTION I INTRODUCTION A. Major Exercise Event Schedule I-3 B. Exercise Development Philosophy I-7 SECTION II OBJECTIVES SECTION III GUIDELINES FOR CONDUCT OF EMERGENCY EXERCISE III-1 SECTION IV REFEREE DATA AND INSTRUCTIONS IV-1 A. Referee Location and Telephone Numbers IV-6 SECTION V TIMELINE V-1 A. Summary V-2 B. Detailed Timeline V-7 C. Basis of Timeline Events V-25

1. Seismic Event V-26 SECTION VI INITIAL CONDITIONS VI-1 A. SSES Daily Report of Operation VI-2 B. NSAG Daily Report VI-5 C. Priority Lists VI-9 D. Operator Turnover Sheets VI-14

PAGE SECTION VI I RADIOLOGICAL CONDITIONS A. Offsite Release Data

1. Weather and Met Data Log VII-1

2. Plume Trajectory and Plume Deposition Data VII-4

3. Noble Gas and I-131 Release Rate Data VI I-6

4. EPB Dose Rate, 6 Hour Projections, and Onsite Field Mo'nitoring Team Information VII-8

5. Field Monitoring Team Data VII-16 B. Reactor Water Isotopic VII-25 C. Suppression Pool Water Isotopic VII-27 D. Drywell Air Isotopic VII-29 E. Wetwell Air Isotopic VI I-31 F. Area Rad Monitor Readings (Rx Bldg 8 Ctrl Str) VII-33 G. In-Plant Dose Survey Maps VII-65 H. PASS Sample Information VII-80 SECTION VI I I MESSAGE INFORMATION SHEETS VIII-1 SECTION IX EXERCISE QUESTIONS IX-1 A. NRC Questions IX-2 B. Questions/Topics of Discussion for HPN Communicator IX-5 SECTION X SIMULATOR INFORMATION X-1

WEATHER CHANGES THAT OCCUR DURING EXERCISE RH.WE3.2 *FILE* (USER FILE)

1. *** 1815 WEATHER FOR NRC GRADED EXERCISE ***

2. MENU

3. SW PDKVMS01=04.0

4. SW PDKVMS02=03.0

5. SW PDKVMX01=150.0

6. SW PDKVMX02=157.0

7. OVR 93X15B 25.0

8. OVR 93X15C 11.0

9. XFILE RH.WE3.3 *FILE* (USER FILE) 1~ *** 1945 WEATHER FOR NRC GRADED EXERCISE ***

2 ~ MENU

3. SW PDKVMS01=05.0

4. SW PDKVMS02=04.0

5. SW PDKVMX01=080.0

6. SW PDKVMX02=083.0

7. OVR 93X15B 12.0

8. OVR 93X15C 09.0

9. XFILE RH.WE3.4 *FILE* (USER FILE)

l. *** 2015 WEATHER FOR NRC GRADED EXERCISE ***

2 ~ MENU

3. SW PDKVMS01=04.0 4 ~ SW PDKVMS02=04.0

5. SW PDKVMX01=150.0

6. SW PDKVMX02=152.0

7. OVR 93X15B 12.0

8. OVR 93X15C 09.0

9. XFILE RH.WE3.5 *FILE* (USER FILE)

l. *** 2115 WEATHER FOR NRC GRADED EXERCISE ***

2 ~ MENU

3. SW PDKVMS01=03.0 4 ~ SW PDKVMS02=04.0

5. SW PDKVMX01=104.0

6. SW PDKVMX02=106.0 7 ~ OVR 93X15B 09.0

8. OVR 93X15C 08.0

'9. XFILE X-5

C.

P "IL RH.WE3.6 *FILE* (USER FILE)

l. *** 2145 WEATHER FOR NRC GRADED EXERCISE ***

2. MENU

3. SW PDKVMS01=03.0

4. SW PDKVMS02=04.0

5. SW PDKVMX01=084.0

6. SW PDKVMX02=086.0

7. OVR 93X15B 08.0

8. OVR 93X15C 08.0

9. XFILE X-6

IS No. 28 Time: 2045 MESSAGE INFORMATION SHEET MESSAGE FOR: Control Room Operators/In-Plant Operators MESSAGE FROM: Control Room Referee/In-Plant Referees LOCATION: Control Room/Field MESSAGE: "THIS IS A DRILL." The individuals assigned the task to close the breaker for the 'B'oop injection valve will determine dose rates in the Reactor Building as they enter the 683'levation by surveying the area. The values to be given are on the radiological maps. "THIS IS A DRILL."

FOR REFEREE USE ONLY REFEREE NOTES: The dose rates on elevation 683'hould not be high enough to affect the task of closing, in the breaker for the breaker for the RHR injection valve.

EXPECTED ACTIONS: The operators will identify the required breaker and close the breaker for the control room to operate the valve.

VIII-57

IS No. 29 Time: 2045 MESSAGE INFORMATION SHEET MESSAGE FOR: Control Room Operators/In-Plant Operators/TSC MESSAGE FROM: Control Room/In-Plant/TSC Referees LOCATION: Control Room/Field/TSC MESSAGE: "THIS IS A DRILL." The local Area Radiation Monitors (ARMs) begin to alarm. This includes the horns in the Control Room, the TSC and the field. "THIS IS A DRILL."

FOR REFEREE USE ONLY REFEREE NOTES: The dose rates in the plant, control room and the TSC increase to the alarm point. The rad levels increase in conjunction with the radiation levels in the containment and the ECCS rooms.

EXPECTED ACTIONS: Health Physics will be contacted to survey the various area that are occupied with emergency workers. Required protective actions will be considered and initiated if deemed necessary.

VIII-58

IS No. 30 Time: 2055 MESSAGE INFORMATION SHEET MESSAGE FOR: Control Room Operators MESSAGE FROM: Control Room Referee LOCATION: Control Room MESSAGE: "THIS IS A DRILL." The 'B'ain Steam Line Inboard Leakage Control System will not start when HS-13904F keyswitch is placed in the operate position. No operator actions will start the "THIS IS A DRILL." 'B'ystem.

FOR REFEREE USE ONLY REFEREE NOTES: The system will not initiate because the Inboard MSIV limit switch is not picked up. The limit switch is a permissive for system start. To get the system in service a jumper will need to be placed in the circuit around the limit switch contact.

EXPECTED ACTIONS: The operators will identify that a permissive for starting the system is not picked up or that the keyswitch is not working properly. The control room will contact the TSC for support to troubleshoot the problem.

The TSC will contact the electrical shop for electricians to investigate the problem.

VIII-59

IS No. 30A Time: 2100 MESSAGE INFORMATION SHEET MESSAGE FOR: Control Room Operators MESSAGE FROM: Simulator Instructor LOCATION: Simulator Control Room MESSAGE: "THIS IS A DRILL." The Simulator Instructor to initiate the FILE RH.91LOl which simulates the radiological conditions in the plant by displaying the radiation levels on the meters and computer formats. "THIS IS A DRILL."

FOR REFEREE USE ONLY REFEREE NOTES: There is no simulator model which drives the various computer points or meter indications for the radiological conditions in the plant, The radiological conditions are required by the control room during an emergency exercise to determine leak location, monitor migration of radioactivity through the plant nd evaluate severity of accident.

The rad levels in the plant for the in-plant team referees are provided on the building radiological maps in section VII of the Referee Manual.

EXPECTED ACTIONS: The control room operators will monitor the radiological conditions as indicated on meters and computer displays and take appropriate action as dictated by the indications and field sample results which will be input to the Control Room.

VI I 1-60

SEISMIC EVENT BREAKS HCPI STEAM LINE DRAIN RH.HPISO *FILE* (USER FILE)

1. *RH.HPISO

2. *HPCI STEAM LINE LEAK AND ISOLATION

3. OVR A14E5 1

4. OVR A14F4 1,5 5 ~ OVR A14F5 1,5

6. OVR A14B5 1,5 7 ~ OVR 22X9A 1,5 8 ~ OVR 22X9B 2 i 5

9. OVR 22X10A 1,5

10. OVR 22X10B 2,5 ll.

12.

OVR 22X11A 2,5 OVR 22X25A 1,5

13. OVR 22X25B 2,5

14. OVR 22X45A 1,5

15. OVR 22X58A 1,5

16. MAL ECS1 ACT,5 17 17 '

'AMP PDVPAR03i100 Oi120i5 OVR A01B05 li20i0 0

~

17 2~ RAMP SPRMV02 2 i 5 ~ 1 i 3 00 i 0 ~ 0 18.

19 20.

'ALOVR A16G15 1,10 ECS3 OVR A15E04 ACTi10 1,300

21. OVR A14H03 1,1200

22. XFILE X-7

SEISMIC EVENT WHICH CAUSES DBA AND FEEDWATER LINE BREAK RH.FWBRK *FILE* (USER FILE)

~RH.FWBRK

- FW LINE BREAK OUTSIDE CONTAINMENT WITH DBA LOCA **

MAL RUP1 ACT OVR 03X26A 1 OVR 03X26B 2 OVR 03X26C 1 OVR 03X26D 2 OVR 03X26E 1 OVR 03X34A 1 OVR 03X34B 2 OVR 03X34C 1 OVR 03X34D 2 OVR 03X34E 1 OVR 03X41A 2 OVR 03X41B 1 OVR 03X41C 1 OVR 03X41D 2 OVR 03X42A 2 OVR 03X42B 1 OVR 03X42C 1 OVR 03X42D 2

- SGTS START INDICATIONS AND SPDS RAD DATA FOR LOCA **

RAMP SPRMA001 i 6 ~ 7E4 i 1200 i 0 ~ 0 OVR AOlB05 1,240 RAMP PDKMAROli6~ 7E4i1200i0 ~ 0 RAMP PDKMAR0216 ~ OE411200g0 ~ 0 OVR A11D02 li300i0 ~ 0 OVR A12D02 1,300,0.0 OVR A06A16 1 OVR A06B16 1 OVR A06C16 1 OVR A06D16 1 OVR A16F16 1 OVR A16G16 1 OVR A15F04 1 SW SPFMV020=0.0 SW SPFMV023=5.0E3 SW SPRMV035=0.84E-05 SW SPRMV036=0..75E-5 SW SPRMV037=3.62 SW SPRMV038=3.4 SW SPRMV039=5.4

.*** RXBD RAD INDICATIONS FOR LOCA WITH 104 FUEL DAMAGE X-8

I RAMP PDVPAR01 g 1000 ~ Og 800~ 0 ~ 0 RAMP PDVPAR25, 1000.0,800,0.0 RAMP PDVPAR02/ 100 'g800~0 ~ 0 RAMP PDVPAR04 g 1 000 ~ 0 g 800 f 0 ~ 0 RAMP PDVPAR16 J 100 ~ 0 g 800 ~ 0 ~ 0 RAMP PDVPAR3 6 / 1 00 ~ 0 g 8 00 ~ 0 ~ 0 RAMP PDVPAR05 g 1 000 ~ 0 g 800 g 0 ~ 0

- - RAMP CONT RAD RECORDER DURING FUEL DAMAGE 1ST RAMP OVR 20X81C 12 ~ Og 300~ 0 ~ 0 OVR 20X89C 12 ~ Og 300' ~ 0 XFILE X-9

RADIATION CONDITIONS IN THE REACTOR BUILDING RH. 9:1LO1 -'FILE* (USER FILE)

- - 2100 RAD INDICATIONS FOR LOCA WITH 104-FUEL DAMAGE MENU' RAMP'DVPAR08, 118~ 0, 3 600, 0. 0 RAMP PDVPAR10 i 88 0 i 3600 i 0 0 ~

RAMP PDVPA'R1 1 i 18 0 i 3 600 i 0 0

~ ~

RAMP PDVPAR12 i 18 0'i 3600 i 0 0

~ ~

'RAMP PDVPAR14 i 18 0 i 3600 i 0 0

~ ~

RAMP PDVPAR15 i 18 0 i 3600 i 0 0

~ ~

'RAMP PDVPAR35, 18 0, 3600, 0. 0

~

'RAMP 'PDVPAR13 i 18'0 i 3600 i 0 0 ~

'RAMP 'PDVPAR42, 18'. 0, 3600, 0. 0 OVR "20X8 1C 68 0 i3600

'OVR" 20X89C 68.0,3600 "RAMP PDKMAROl, 4E4,3600,'0.0

'RAMP PDKMAR02i 4E4"i3600i0 ~ 0 RAMP SPRMA'b01, 4E4, 360,0;0.

PDVPAR39 i 05 ~ '0j 3600 i 0 ~ 0 0'AMP RAMP PDVPAR37 i 17 ~ 0 j 3600 i 0 ~ 0

'RAMP SPRMV03 2 i 5 ~ 3 i 3 600 g 0 ~ 0

RAMP SPRMV037 i 2 ~ 3E3 i 3 600 i 0 ~ 0 RAMP SPRMV03 6, 0. 10 ", 3 600, 0. 0 XFILE X-10

IS No. 31 Time: 2100 MESSAGE INFORMATION SHEET

~ii E': ii ii C ii MESSAGE FROM: TSC Chemistry Referee LOCATION: TSC H~SSAG: "THIS IS A DRILL." The Chemistry Referee will inform the Chemistry Coordinator to input the background subtract to the SPING console to keep the SPING operable while the background radiation levels on 818'ncrease. "THIS IS A DRILL."

FOR REFEREE USE ONLY REFEREE NOTES: To insure the SPING consoles continue to put out reasonable data while the rad levels are high on 818't will be necessary to install the background subtract. The intent of the exercise is not to take the SPINGs out of service.

EXPECTED ACTIONS: The background subtract will be inserted.

VIII-61 '

IS No. 32 Time: 2105 MESSAGE INFORMATION SHEET

~EE Recovery Manager MESSAGE FROM: EOF Referee LOCATION: EOF

~MESSAG : "THIS IS A DRILL." The classification at the GENERAL EMERGENCY level needs to be made at this time. The classification is to be made in accordance with LOSS OF REACTOR VESSEL INVENTORY or FUEL CLADDING DEGRADATION. "THIS IS A DRILL."

FOR REFEREE USE ONLY REFEREE NOTES: The exercise needs to be kept fairly close to the planned time line due to the large number of people involved with the exercise.

EXPECTED ACTIONS: The Recovery Manager will make the GENERAL EMERGENCY classification and direct the communicator to begin upgrade notifications, prepare for Protective Action Recommendation and combat the emergency.

VI I I-62

IS No. 33 Time: 2105 MESSAGE INFORMATION SHEET MESSAGE FOR: Offsite Monitoring Teams MESSAGE FROM: Offsite Monitoring Team Referee LOCATION: In Field MESSAGE: "THIS IS A DRILL." The radiological data for the offsite teams is located in section seven (7) of the exercIse manual. "THIS IS A DRILL."

FOR'EFEREE USE ONLY REFEREE NOTES: The monitoring teams will be given information (raw data) based on sampling procedures/techniques, location in the field relative to plume centerline, and questions asked.

EXPECTED ACTIONS: The EOF Offsite Team Director is expected to have the teams dispatched to the sectors between North and West.

VIII-63

IS No. 34 Time: 2115 MESSAGE INFORMATION SHEET MESSAGE FOR: General Office via TSC Tech Engineer MESSAGE FROM: TSC Tech Referee LOCATION: TSC MESSAGE: "THIS IS A DRILL." The General Office is to be informed that a second shift is required for continued support of the emergency.

"THIS IS A DRILL. "

FOR REFEREE USE ONLY REFEREE NOTES: The message is given to the TSC Tech Engineer to prompt the General Office to consider a second shift manning roster.

EXPECTED ACTIONS: The General Office will begin the process of selecting individuals to support a second shift.

VIII-64

IS No. 34A Time: 2115 MESSAGE INFORMATION SHEET MESSAGE FOR: Control Room Operators MESSAGE FROM: Simulator Instructor LOCATION: Simulator Control Room MESSAGE: "THIS IS A DRILL." The Simulator Instructor to initiate the FILE RH.WE3.5 which is the meteorological conditions around the plant as indicated on PMS Format ¹47. "THIS IS A DRILL."

FOR REFEREE USE ONLY REFEREE NOTES: There is no simulator model which drives the various computer points or meter indications for the weather conditions around the site. The weather conditions are required by the control room during an emergency exercise to plot plume travel, direct evacuation and response routes and protect site personnel not evacuated.

The rad levels in the plant for the in-plant team referees are provided on the building radiological maps in section VII of the Referee Manual.

EXPECTED ACTIONS: The control room operators will monitor the weather conditions as indicated on meters and computer displays and take appropriate action as dictated by plume travel and resultant doses/contamination.

VIII-65

IS No. 35 Time: 2120 MESSAGE INFORMATION SHEET MESSAGE FOR: Recovery Manager MESSAGE FROM: EOF Referee LOCATION: EOF MESSAGE: "THIS IS A DRILL."

at this time.

,AIfProtective is Action Recommendation needs to be made no PAR prepared the following is to be made; "Recommend evacuation in a 2 mile radius, and sheltering 2 miles to 10 miles radius. This recommendation does not take into account any weather conditions or time of day. "THIS IS A DRILL."

FOR REFEREE USE ONLY REFEREE NOTES: The exercise needs to be kept fairly close to the planned time line due to the large number of people involved with the exercise.

EXPECTED ACTIONS: 'he Recovery Hanager will make the Protective Action recommendation and direct the communicator to begin notifications to the appropriate agencies and prepare for implementation of the Protective Action Recommendation, VI I 1-66

IS No. 36 Time: 2125 MESSAGE INFORHATION SHEET MESSAGE FOR: MOC Lead Referee MESSAGE FROM: EOF Lead Referee LOCATION: MOC/EOF MESSAGE: "THIS IS A DRILL." Pass on to the MOC referee what protective action recommendations the governor has made including time the sirens are to sound and the wording of the emergency broadcast system message. "THIS IS A DRILL."

FOR REFEREE USE ONLY REFEREE -NOTES: The people at the MOC would hear the siren if they were in fact set off. The MOC lead referee will simulate to the personnel in the MOC the sounding of the sirens and the message that would come over the emergency broadcast system.

EXPECTED ACTIONS: The Public Information Manager will contact the EOF if he has not already been in touch with the EOF. The MOC will be making preparations to answer the questions that will occur as a result of the Protective Action Recommendation.

VIII-67

IS No. 37 Time: 2130 MESSAGE INFORMATION SHEET MESSAGE FOR: General Office MESSAGE FROM: Simulated Lieutenant Governor LOCATION: General Office MESSAGE: "THIS IS A DRILL." This is the Lieutenant Governor. The State is responding to the emergency and expects to have a team at the site by 2200 hours0.0255 days 0.611 hours 0.00364 weeks 8.371e-4 months . We are also considering dispatching a team to your Main Office in Allentown, we would like the following information, please:

1. I need directions to the General Office from Harrisburg.

2. We will need space for 6 individuals at the General Office with phones available that have outside line capability.

3. The Governor is requesting a tour of the plant site first thing in the morning (0900) and will require escorted access for 6 people at the power station.

4. A briefing for each team upon arrival which includes current status of the plant, releases, and duration; plans for stopping releases; schedule and content of future briefings.

5. The Governor would like to hold a joint news conference in the morning after the tour of the plant at you Media Operations Center.

Please FAX the above requested information to (717) 759-4946 marked ATTENTION: A. Male. "THIS IS A DRILL."

FOR REFEREE USE ONLY REFEREE NOTES: The General Office is expected to prepare the above requests for transmission.

EXPECTED ACTIONS: The General Office will fulfill the requests of the State and fax the material.

VIII-68

IS No. 37A Time: 2145 MESSAGE INFORMATION SHEET MESSAGE FOR'ontrol Room Operators MESSAGE FROM: Simulator Instructor LOCATION: Simulator Control Room MESSAGE: "THIS IS A DRILL." The Simulator Instructor to initiate the FILE RH.WE3.6 which is the meteorological conditions around the plant as indicated on PMS Format 847. "THIS IS A DRILL."

FOR REFEREE USE ONLY REFEREE NOTES: There is no simulator model which drives the various computer points or meter indications for the weather

'onditions around the site. The weather conditions are required by the control room during an emergency exercise to plot plume travel, direct evacuation and response routes and protect site personnel not evacuated.

The rad levels in the plant for the in-plant team referees are provided on the building radiological maps in section VII of the Referee Manual.

EXPECTED ACTIONS: The control room operators will monitor the weather conditions as indicated on meters and computer displays and take appropriate action as dictated by plume travel and resultant doses/contamination.

VIII-69

IS No. 38 Time: 2230 MESSAGE INFORMATION SHEET MESSAGE FOR: All Areas Via the Plant Page MESSAGE FROM: TSC Communications Referee and All Facility Lead Referees LOCATION: Plant Control Room and All Emergency Response Facilities MESSAGE: "THIS IS A DRILL." The, following page announcement is to be made from the plant Control Room: "The 1991 FULL SCALE NRC GRADED EXERCISE is now terminated; the 1991 FULL SCALE NRC GRADED EXERCISE is now terminated."

t The Facility Lead Referees shall ensure that the exercise records are turned in and key individuals attend the area debriefing.

Ensure that the telephone system and the plant page system are restored. Transfer the simulator radio back to the training condition and restore the simulator computer to normal operation.

Ensure the response facilities are picked up and ready to respond to an actual emer ency. "THIS IS A DRILL."

FOR REFEREE USE ONLY REFEREE NOTES: The page announcement is to be made in the following areas:

The Simulator Control Room The TSC The Plant The OSC The EOF The MOC The General Office EXPECTED ACTIONS: Ensure that all the previously notified offsite agencies are informed that the exercise is terminated.

VIII-70

SECTION I PART A - MAJOR EXERCISE EVENT SCHEOULE

ANNUAL EXERCISE DATE AND TINE This exercise has been developed to initiate response actions on August 20 and September 24 for the practice exercises and October 16, 1991 for the graded exercise. The exercises have been designed to test the response of the station's emergency preparedness program. The duration of the exercises is expected to be about 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

OVERALL SCHEDULE OF EVENTS FOR ANNUAL EXERCISE August 13 EOF Walkthrough Time: 0900-1500 Location: EOF Attendees: All EOF participants August 15 Referee Training Seminar Time: 0800-1200 Location: EOF Large Conference Room (LCR)

Attendees: First Time Referees August 16 Lead Referee Simulator Demo Time: 1100 Location: Simulator Attendees: All Lead Facility Referees August 16 TSC Walkthrough Time: 1330-1530 Location: TSC Attendees: All TSC participants August 19 Referee Training Time: 0830-1500 Location: EOF LCR Attendees: All Referees and Observers August 20 First Practice Exercise Time: Day Shift Location: Simulator and all ERFs (HOC from SOP/SEIC/Riverlands)

Attendees: All Participants, Referees, and Observers August 21 Critique Preparation Time: 0800-1300 Location: EOF LCR Attendees: Lead Facility Referees I-4

August 21 Critique Presentation Time 1400-1600 Location: EOF LCR Attendees: All Manager and Coordinator Participants; Lead Referees; other participants and referees invited but attendance optional August 21 Operations Meeting (as necessary)

Time: 1600-1800 Location: EOF Attendees: Lead Control Room Referee Sept 20 Lead Referee Training Time: 1100 Location: Simulator Attendees: All Lead Facility Referees Sept 23 Referee Training Time: 0830-1530 Location: EOF LCR Attendees: All Referees and Observers Sept 24 Second Practice Exercise Time: Day Shift Location: Simulator and all ERFs (HOC from YMCA)

Attendees: All Participants, Referees, and Observers Sept 25 Critique Preparation Time: 0800-1300 Location: EOF LCR Attendees: Lead Facility Referees'riti'que Sept 25 Presentation Time: 1400-1600 Location: EOF LCR Attendees: All Manager and Coordinator Participants; Lead Referees; other participants and referees invited but attendance optional Sept 25 Operations Meeting (as necessary)

Time: 1600-1800 Location: EOF LCR Attendees: Lead Control Room Referee October ll Lead Referee Training Time: 1100 Location: Simulator Attendees: Lead Facility Referees I-5

October 15 Referee Training Time: 0830-1530 Location: EOF LCR Attendees: All Referees and Observers October 16 NRC Exercise Time: Afternoon Shift Location: Simulator and all ERFs (MOC from YMCA)

Attendees: All Participants, Referees, and Observers October 17 Critique Preparation Time: 0800-1300 Location: EOF LCR Attendees: Lead Facility Referees October 17 Critique Presentation Time: 1400-1600 Location: EOF LCR Attendees: All Manager and Coordinator Participants; Lead Referees; other participants and referees invited but attendance optional October 17 Operations Meeting (as necessary)

Time: 1600-1800 Location: EOF LCR Attendees: Lead Control Room Referee 1-6

SECTION I PART B - EXERCISE DEVELOPMENT PHILOSOPHY

EXERCISE DEVELOPMENT PHILOSOPHY NUREG N.3 Proper scenario development determines the outcome of the exercise. All operating nuclear power plants, including SSES have already demonstrated their ability to protect the health and safety of 'the public. SSES has people who are knowledgeable and'an respond in an emergency, therefore chances of failing an exercise are remote. SSES can fail an exercise or get a reduced SALP rating because of attitude and that is where scenario development is important.

An attitude is generated when an exercise is being conducted and observed; this attitude will affect present and future exercises. The scenario must be detailed enough to test and challenge the participants, and provide information to support expected operator and engineer responses. An answer to a participant's question should be an exact summary of why their solution will or will not mitigate the event. If participants are given that type of answer they will react as if the situation is more realistic and will work on a solution eagerly. This type of attitude is contagious and this willingness to respond will be transferred to the offsite participants. If an individual asks a question and only gets the reply, "no, that won't work" time after time, they get disgruntled and disgusted with the scenario and won't look further since they expect the same answer. This down attitude will affect how communications flow and how interfaces between the different groups occur.

Scenario development is important so that no matter how unrealistic the initiating conditions appear, after the participants are involved for a period of time, they have forgotten the beginning. They then become active participants in providing input and corrective actions to the other participants.,

It is important to realize that the scenario is not to test the participants knowledge of the plant. The scenario SHOULD test the response organization's knowledge of the Emergency Plan Implementing Procedures and other plant procedures, and how the people and the procedures interface with each other.

Periodic exercises are conducted to evaluate major portions of emergency response capabilities. Sub portions of exercises or separate drills such as fire or medical emergencies develop, maintain, and test key skills.

An emergency exercise must involve significant effort in research and development to ensure that the events depicted are as realistic as possible.

Realism is created through the use of the simulator and additional referee supplied information. The referee supplied information will come in the form of supplied data sheets simulating CRT screens, gage/meter/recorder readings, area conditions, props (simulated injuries), and simulated reports (daily operating report, service information letters, Nuclear Network messages, etc).

Information will be supplied to the Emergency Response Facilities directly from the simulator via phone lines to a CRT displaying live plant data. The CRT display will not be normal plant display but one used for exerci'ses only.

I-8

Initiating events for an exercise can be human error or equipment malfunction.

No one wants to assume that they will make mistakes, especially of the magnitude that can cause significant plant damage. Since the possibility does exist for human error, events may be initiated as a result but are not meant as an indication of staff incompetence.

Equipment malfunction is difficult to incorporate into a scenario to the extent required to cause plant damage and serious offsite environmental problems. The plant design, equipment reliability and redundancy, construction, and installation of systems preclude such events. The SSES Final Safety Analysis Report analyzes the capabilities of plant systems to maintain control over radioactive material in the plant during all types of abnormal conditions. Therefore to cause a serious event for an exercise some unrealistic assumptions must be made.

If the conditions listed in the scenario were probable, an unanswered safety question would exist and actions would be taken to remedy the situation., This must be clear so that the general public doesn't believe that the scenario events are probable.

(

SECTION IX EXERCISE QUESTIONS PART A - NRC QUESTIONS

SSES EMERGENCY EXERCISE NRC QUESTIONS When the Control Room Communicator calls for the initial notification, the simulated on-duty NRC Operations Center individual will ask if the Control Room is prepared to maintain an open line. The Control Room should respond with an affirmative.

The following is a list of questions that can be asked of the Control Room/TSC/EOF Communicators.

These questions can be asked periodically during the exercise to determine if the participants are aware of plant conditions.

Refer to the timeline for when significant events occur and note the time the Communicator provides updated information.

Verification of the information provided by the Communicator can be done by reviewing the print out of information from the simulator. The print out is in the EOF next to the Offsite Dose overhead projector . 'ocated What was the initiating event of the emergency?

What is the expected duration'of the emergency?

Has there been any injuries to plant personnel?

~ . Have the NRC residents report to the Control Room yet?

~ What emergency operating procedures are presently in use?

~ Has a news release been initiated?

~ What is the Control Room ventilation line up?

~ What is the Reactor Building ventilation line up?

~ Is the electric plant line up normal?

~ Is the Reactor completely shutdown?

~ Has boron been injected in the reactor vessel?

~ Is the plant responding in a normal fashion?

IX-2

Give me the values for the following parameters:

Steam Flow-Core Flow-Recirc Pump Flow-Reactor Pressure-Reactor Level Recirc Loop Temperature-Gross Coolant Activity-Dose Equivalent Iodine-Drywell Pressure-Drywell Temperature-Drywell Radiation Levels-Drywell Oxygen Concentration-Drywell Hydrogen Concentration-Suppression Pool Pressure-Suppression Pool Temperature-Suppression Pool Level-

~ What ECCS is in operation?

HPCI ADS Core Spray LPCI ESW Diesel Generators Batteries Ventilation

~ Is the TSC being manned?

~ Is the EOF being manned?

Has any outside support been requested?

Has the stability of the grid been affected by the unit coming off line?

~ Due to grid stability, what are the chances for a loss of offsite power?

IX-3

~ Review the values of the parameters given previously:

Steam Flow-Core Flow-Recirc Pump Flow-Reactor Pressure-Reactor Level-Recirc Loop Temperature-Gross Coolant Activity-Dose Equivalent Iodine-Drywell Pressure-Drywell Temperature-Drywell Radiation Levels-Drywell Oxygen Concentration-Drywell Hydrogen Concentration Suppression Pool Pressure-Suppression Pool Temperature-Suppression Pool Level-Has the answer to any of the other questions changed?

SECURITY EVENT QUESTIONS How many individuals are attempting to penetrate the site?

2. Are any of the individuals armed?

3. Have you notified the local law enforcement authorities?

4. Has outside assistance been requested?

5. Have any of the individuals been apprehended?

ADDITIONAL QUESTIONS Are there any abnormal inplant radiation levels?

2. What is the radiation level in the containment?

3. Is there a release in progress; if so, what are the current levels at the EPB, what is the current trend, how long do you expect to continue?

IX-4

SECTION IX - EXERCISE QUESTIONS PART B - QUESTIONS/TOPICS OF DISCUSSION FOR HPN COMMUNICATOR IX-5

SSES EMERGENCY EXERCISE QUESTIONS/TOPICS OF DISCUSSION FOR HPN COMMUNICATOR The following questions to be asked by the individual playing the NRC Health Physics are generic in nature and can be made more specific and pointed depending on the type of scenario.

This particular scenario has seasonal met conditions, including snow. Many different questions should be asked as a result of a release with precipitation; see the DOSE CALCULATOR and LICENSEE OFFSITE MONITORING sections.

IN-PLANT QUESTIONS

1. Which unit is the affected unit?

2. What is the present classification?

'a ~ What is the classification based on?

b. Is there a release in progress?

C. Is the release monitored?

d. Is the release being filtered?

e. Is there fuel damage?

3. What is the Containment Radiation levels?

4. What is the airborne concentrations inside the containment?

5. What is the suppression pool activity?

6. What are the results of the reactor coolant samples? Is this a PASS sample? What is the dose of the 10 ml PASS sample?

7. Has there been any emergency exposures?

a. How many people?

b. To what exposure level?

c. What are the reasons for the emergency exposures?

8. What actions are being taken to terminate the release?

a. What actions are being taken to minimize the release?

b. Is there any way to hold up the release for decay?

c. Is there any liquid release in progress?

9. Is the TSC, OSC, Control Room, EOF all habitable?

10. Have all the non-essential people been evacuated from the site?

ll. Was everyone accounted for during the accountability?

a. Was search and rescue required to find any of the missing individuals?

b. Is anyone still missing?

12. Are the counting labs on site operable?

13. What is the operating status of your ventilation systems?

14. What areas of the plant are affected radiologically by the accident?

15. Are there any areas of the site that are u'naccessible?

16. What are the contamination levels in the plant and around the site?

17. What are the airborne levels in the plant and around the site?

18. Has KI been distributed or administered to the onsite emergency workers?

19. Who or what group are your consulting physician(s)?

20. At what time was the TSC activated?

21. At what time was the EOF activated?

22. Who is the Radiation Protection Hanager on duty?

23. Who is the Emergency Director?

24. Have there been any security events?

25. Have there been any injuries or fatalities?

26. Has there been anyone transported offsite to an area hospital?

27. Are you prepared to grant unfettered access to our NRC Response Team?

28. What protective action recommendations have been made for the site personnel and/or the offsite populace at this time?

29. What is the basis for making or not making a protective action recommendation at this time?

30. Have any of the area sirens been sounded?

31. Have any surface sources such as the Spray Pond or lakes and reservoirs been affected by the release?

32. Are these bodies of water used for drinking water by anyone?

33. Have environmental teams been dispatched at this time?

34. Are there any protective action recommendations being considered as a result of the environmental samples?

35. Are there any damage control teams presently dispatched in the plant?

What is the damage control team attempting to do at this time?

36. Have any traffic patterns around the plant been changed due to the plume path? Are there any delays expected as a result of the plume path?

37. Has the site requested any additional offsite response support such as fire company, ambulance police, outside contractors?

38. Have you established communications with DER/BRP? Who?

39. Is anyone from DER/BRP being dispatched to the site? Who?

40. At what time will the organization make a shift change? Who is your relief?

DOSE CALCULATOR QUESTIONS Is there a release in progress in excess of the tech spec limit or causing offsite doses?

2. What are the dose rates at the EPB?

a 0 What are the projected doses at the EPB?

b. What are the projected thyroid doses at the EPB?

c~ What are the integrated doses at the EPB?

d. How long are you expecting to release through the present release path?

e. Is that time the same as what you are using for your projected doses?

3. What sectors are affected by the release? How many people live in the affected sectors?

What is the present weather and what is the weather forecast?

5. What isotope is the primary contributor to the dose at the EPB?

6. Is the thyroid dose or whole body dose limiting?

7. Is any particulate being released?

8. Are the field monitoring teams and dose calculations in agreement? What are the relative errors to one another?

9. What is the source term in the primary containment?

10. What is the source term in the secondary containment?

What would the dose rates at the EPB be if the source term in either the primary or secondary containment were immediately released?

12. Is the release monitoring instrumentation working properly? Is the instrumentation expected to remain in service? What is the backup if the instrumentation dose not remain in service?

13. What is the trend of the nobel gases and iodine releases? (Increasing, decreasing, no change).

Is this an analyzed accident scenario as found in the FSAR? If so what are the predicted releases and offsite consequences?

15. How do your dose calculations take into account the snow and the resultant washout? What would be the difference if the precipitation turned to rain; would the dose projections be different?

16. Does your dose calculation model take into account the run-off when the snow melts?

LICENSEE OFFSITE MONITORING What is the distance from the plant that your onsite team is doing it' monitoring?

2. What method does the offsite team use to calculate iodine activity, particulate activity? I

3. Are the individuals that are offsite monitoring wearing respirator protecti on, have they been given KI?

What type of respirators are the team members wearing, what is the protection factor?

5. What exposures are the offsite monitoring teams allowed to receive?

What is their present exposure? Is that value all from today?

6. Where are the offsite teams located?

7. What are the results of the environmental samples? Where and when were the environmental samples taken?

8. Is the area around the EOF contaminated, was the area surveyed prior to activation?

9. Have any of the field monitoring teams experienced any radio interference by any offsite source?

10. How are the monitors collecting air samples in the snow?

11. What efficiency are they using for the detectors in the field?

12. Is there a lower" limit of temperature for use of your field monitoring instruments?

13. Would you please explain how you take snow samples?

14. What factor are you using for shielding from the deposited radioactivity or how much is the snow affecting the ground contamination reading?

IX-10

SECTION II OBJECTIVES

1991 NRG Graded Exercise Objectives The following list of objectives are a compilation from NUREG 0654 and the Federal Emergency Management Agency (FEHA) Guidance Memorandum EX-3 (GH EX-3).

The CORE OBJECTIVES are taken directly from the FEMA Guidance Memorandum EX-3 (GM EX-3) and are presented in three groups, A, B, and C.

Group A are "Core Objectives that are Scenario Independent," to be demonstrated each biennial exercise.

Group B are "Scenario Dependent," only impact some organizations but scenarios are to be varied to,demonstrate appropriate emergency response at least once every six years.

Group C are "Other Objectives: To Be Demonstrated At Least Once Every Six Years;" an example, the ingestion pathway related objectives need to be demonstrated once every six years.

The Federal Emergency Management Agency sends GM EX-3 to the state of Pennsylvania several months prior to the scheduled exercise. FEMA outlines the objectives required to be satisfied and a description of the expected actions to be demonstrated. The FEHA expectations are listed below the applicable objective as a NOTE.

PP&L coordinates with the State to develop a scenario that provides the local communities and the State the opportunity to demonstrate all the objectives specified by FEHA. Working with the off-site agencies requires PP&L to review and be familiar with the objectives listed in the Guidance Hemorandum.

Each "FEHA" Core Objective is correlated to NUREG 0654 planning standards.

The NRC measures the emergency preparedness of PP&L using the NUREG 0654, therefore the correlation between the FEMA document and the NUREG. The FEMA Objectives are listed numerically 1-37. Below each objective are the NUREG planning standards that are related or directly support the FEMA Objectives.

The NUREG 0654 requirements denote which group is responsible for ensuring the exercise demonstrates the organizations preparedness and how the objective will be demonstrated.

Approved:

R t Byram Approved:

Approved:

Iar H. Genh es A. Hyer Stanley

GROUP A: CORE OBJECTIVES - SCENARIO INDEPENDENT

'la):~ Demonstrate the organization's ability to recognize operational symptoms and

~ ~ ~ ~ ~ ~

parameters indicative of degrading plant conditions and relate such symptoms to

~ ~ ~

prescribed Emergency Action Levels (EAL). [FEMA-GM-EX-3: (l)]

~

RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS D. l An emergency classification NEP The core objective and and emergency action level supporting NUREG will be scheme as set forth in demonstrated by the Appendix 1 must be established emergency responders by the licensee. The specific proper use of the SSES instruments, parameters, or EALs. The scenario will equipment status shall be use the simulator shown for establishing each Control Room indications emergency class, in the in- as initiating plant emergency procedures. conditions.

The plan shall identify the parameter values and equipment status for each emergency class.

The initiating conditions NEP The core objective and shall include the example supporting NUREG will be conditions found in Appendix I demonstrated by the and all postulated accidents emergency responders in the Final Safety Analysis proper use of the SSES Report (FSAR) for the nuclear EALs. The scenario will facility. use the simulator Control Room indications as initiating conditions.

(la): CONT'0 RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS H.5 Each licensee shall identify Plant x and establish onsite monitoring systems that are to be used to initiate emergency measures in accordance with Appendix 1, as well as those to be used for conducting assessment.

This equipment shall include:

a. geophysical phenomena Met Data will be used monitors, (e.g., for dose calculations.

meteorological, hydrologic, Simulator will display seismic); weather parameters.

b. radiological monitor s, Applicable radiation (e.g., process, area, readings will indicate emergency, effluent, wound in the simulator Control and portable monitors and Room on meters and CRT sampling ~quipment); displays.

c. process monitors, (e.g.,

reactor coolant pressure Applicable and temperature, instrumentation will containment pressure and read out in the Control temperature, liquid levels, Room, TSC, and EOF on flow rates, status or CRT displays.

lineup of equipment components); and

d. fire and combustion product detectors. Not demonstrated.

(la): CONT'D RESP NOT NUREG 0654 GRP DEHO DEHO COHHENTS H.6 Each licensee shall make NEP Actual demonstration provision to acquire data from using simulated data or for emergency access to from the met towers, offsite monitoring and simulated TLDs, and analysis equipment including: field monitoring teams receiving simulated data

a. geophysical phenomena from referees.

monitors, (e.g.,

meteorological, hydrologic, seismic);

b. radiological monitors including rate meters and sampling devices.

Dosimetry shall be provided and shall meet, as a minimum, the NRC Radiological Assessment Branch Technical Position for the Environmental Radiological Honitoring Program; and

c. laboratory facilities, fixed or mobile.

I.2 Onsite capability and Plant x The simulator Control resources to provide initial Room accident values and continuing instruments will assessment throughout the indicate for accident course of an accident shall assessment by responding include post-accident sampling to transients induced capability, radiation and for the exercise.

effluent monitors, in-plant iodine instrumentation, and The PASS located in the containment radiation Training Center will be monitoring in accordance with used for sampling.

NUREG 0578, as elaborated in the NRC letter to all power reactor licensees dated October 30, 1979.

(la): CONT'0 RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS I.3 Each licensee shall establish Rad & x methods and techniques to be Env used for determining:

a. the source term of releases The rad monitors will of radioactive material indicate proper within plant systems. An correlation to the example is the relationship radioactive material between the containment released. The values radiation monitor(s) used for the rad reading(s) and radioactive monitors are derived by material available for using a computer release from containment. program.

b. the magnitude of the Data indicating the release of radioactive radiological conditions materials based on plant will be available in the system parameters and Control Room, TSC, EOF, effluent monitors. 5 OSC.

(1b): Demonstrate the organization's ability to properly classify emergency conditions, make initial notifications, and follow up notifications. [FEMA-GM-EX-3: (1)]

RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS D. 1 This NUREG is the same as that used to support Core Objective lA.

D.2 This NUREG is the same as that used to support Core Objective 1A.

E.2 Each organization shall NEP Actual demonstration for establish procedures for exercise participants by alerting, notifying, and using pager system and mobilizing emergency response telephone.

personnel.

E.3 The licensee in conjunction NEP Actual demonstration by with State and local Operations disseminating organizations shall establish initial communications the contents of the initial to state and local emergency messages to be sent organizations.

from the plant. These measures shall contain information about the class of emergency, whether a release is taking place, potentially affected population and areas, and whether protective measures may be necessary.

(1b): CONT'D RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS Each licensee shall make NEP x Actual demonstration by provisions for follow Control Room, TSC, and from the facility to up'essages EOF.

offsite authorities which shall contain the following information if it is known and appropriate:

a. location of incident and name and telephone number (or communications channel identification) of caller;

b. date/time of incident;

c. class of emergency;

d. type of actual or projected release (airborne, waterborne, surface spill),

and estimated duration/impact times;

e. estimate of quantity of radioactive material released or being released and the points and height of releases;

f. chemical and physi,cal form of released material, including estimates of the relative quantities and concentration of noble

, gases, iodines, and particulates.

g. meteorological conditions at appropriate levels [wind speed, direction (to and from), indicator of stability, precipitation, if any];

h. actual or projected dose rates at site boundary; projected integrated dose at site boundary;

i. projected dose rates and

/

II-8

(1b): CONT'D RESP NOT NUREG 0654 GRP DEHO DEHO COHHENTS integrated dose at the projected peak and at 2, 5, and 10 miles, including sector(s) affected;

j. estimate of any surface radioactive contamination inplant, onsite or offsite;

k. licensee emergency response actions underway;

l. recommended emergency actions, including protective measures;

m. request for any needed onsite support by offsite organizations; and

n. prognosis for worsening or termination of event based on plant information.

(2): Demonstrate ability to fully alert, mobilize and activate personnel for both facility and field based emergency functions. [FEMA-GM-EX-3: (2)]

RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS E. 1 Each organization shall NEP x Actual demonstration by establish procedures which response organization at describe mutually agreeable each level of emergency.

bases for notification of response organizations consistent with the emergency classification and action level scheme set forth in Appendix 1. These procedures shall include means for verification of messages. The specific details of verification need not be included in the plan.

E.2 This NUREG is the same as that used to support Core Objective 1b.

H.4 Each organization shall All All facilities will provide for timely activation - activate.

and staffing of the facilities and centers described in the plan.

(3a): Demonstrate the ability to direct, coordinate, and control emergency activities.

[FEHA-GH-EX-3: (3)]

RESP NOT NUREG 0654 GRP DEMO DEMO . COMMENTS A. l.d Each organization shall NEP x Actual demonstration as identity a specific individual each organization is by title who shall be in activated.

charge of the emergency response.

(3b): Demonstrate the adequacy of the SSES Emergency Plan Implementing Procedures applicable to the scenario. [FEHA-GH-EX-3: (3)]

RESP NOT NUREG 0654 GRP DEHO DEHO COHHENTS A. l.d This NUREG is the same as that used to support Core Objective 3A.

(4): Demonstrate ability to communicate with all appropriate locations, organizations, and field personnel including 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months per day manning of communication links.

[FEMA-GM-EX-3: (4)]

RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS A. l.e Each organization shall All Demonstration of 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months provide for 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months per day coverage by filling out emergency response, including a shift manning roster.

24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months per day manning of Actual TSC shift change communications links. during 2nd practice exercise.

F. 1 The communication plans for NEP Backup communications emergencies shall include paths will only be organizational titles and tested if the primary alternates for both ends of system actually fails the communication links. Each during the drill.

organization shall establish reliable primary and back up means of communication for licensees, local, and State response organizations. Such systems should be selected to be compatible with one another. Each plan shall include:

a. provision for 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months per day notification to and activation of the State/local emergency response network; and at a minimum, a telephone link and alternate, including 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months per day manning of communications links that initiate emergency response actions.

b. provision for communications with continuous State/local governments within the Emergency Planning Zones;

c. provision for communications as needed with Federal emergency response organizations;

d. provision for communications between the nuclear facility and the licensee's near-site Emergency Operations II-13

(4): CONT'D RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS Facility, State and local emergency operations centers, and radiological monitoring teams;

e. provision for alerting or activating emergency personnel in each response organization; and

f. provision for communication by the licensee with NRC headquarters and NRC Regional Office Emergency Operations Centers and the licensee's near-site Emergency Operations Facility and radiological monitoring team assembly area.

F.2 Each organization shall ensure All x A medical emergency will that a coordinated not be included in the communication link for fixed scenario.

and mobile medical support facilities exists.

(5): Demonstrate the adequacy of facilities and displays to support emergency (5)] operations'FEMA-GM-EX-3:

RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS C. I The Federal government NEP x Not demonstrated; no maintains in-depth capability simulated or actual to assist licensees, States federal assistance.

and local governments through the Federal Radi'ological Monitoring and Assessment Plan

[formerly Radiological Assistance Plan (RAP) and Interagency Radiological Assistance Plan (IRAP)]. Each State and licensee shall make provisions for incorporating the Federal response capability into its operation plan, including the following:,

a. specific persons by title authorized to request Federal assistance; see A.l.d, A.2.a.

b. specific Federal resources

'expected, including expected times of arrival at specific nuclear facil'.+v sites; and

c. specific licensee, State and local resources available to support the Federal response, e.g., air fields, command posts, telephone lines, radio frequencies and telecommunications centers.

C.2.a Each principal offsite NEP Will be demonstrated by organization may dispatch representatives from representatives to the Harrisburg coming to the licensee's near-site Emergency EOF along with state Operations Facility. (State off-site monitoring technical analysis teams.

representatives at the nearsite EOF are preferred.)

(5): CONT'D RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS C.2.b The licensee shall prepare for NEP Not demonstrated; an the dispatch of a individual will not be representative to principal dispatched to offsite offsite governmental emergency facil i ty.

operations centers.

G.3.b Each licensee shall provide Speci Not demonstrated.

space which may be used for a Office limited number of news media at the nearsite Emergency Operations Facility.

H. 1 Each licensee shall establish Plant x To be demonstrated when a Technical Support Center and the control room an onsite operations support classifies the emergency center (assembly area) in as an ALERT or when accordance with NUREG 0696, deemed necesary by the Revision l. ED.

H.2 Each licensee shall establish NEP Actual demonstration.

an Emergency Operations The EOF will be fully Facility from which evaluation activated.

and coordination of all licensee activities related to an emergency is to be carried out and from which the licensee shall provide information to Federal, State and local authorities responding to radiological emergencies in accordance with NUREG 0696, Revision l.

(5): CONT'D RESP NOT NUREG 0654 GRP DEHO DEHO COHHENTS H.9 Each licensee shall provide Plant x The OSC will be for an onsite operations activated and required support center (assembly area) emergency equipment will which shall have adequate be used.

capacity, =and supplies, including, for example, respiratory protection, protective clothing, portable lighting, portable radiation monitoring equipment, cameras and communications equipment for personnel present in the assembly area.

I.7 Each organization shall Rad 8 x Field monitoring describe the capability and Env personnel will be resources for field monitoring dispatched from the within the plume exposure plant and the EOF.

Emergency Planning Zone which are an intrinsic part of the concept of operations for the facility.

NOTE: FEHA expects that all risk counties and support counties demonstrate the capability and evidence of operation of an emergency generator.

(6): Demonstrate the ability to continuously monitor and control emergency worker exposure. ,[FEHA-GH-EX-3: (6)]

RESP NOT NUREG 0654 GRP DEHO DEHO COHHENTS organization shall make Dosimetry will be used K.3.a Each Plant x provision for 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months per day as determined by the capability to determine the scenario conditions.

doses received by emergency personnel involved in any nuclear accident, including volunteers. Each organization shall make provisions for distribution of dosimeters, both self-reading and permanent record devices.

K.3.b Each organization shall ensure Plant x Dosimetry will be used that dosimeters are read at as required by scenario appropriate frequencies and conditions and results provide for maintaining dose provided to participants records for emergency workers will be recorded. Any involved in any nuclear readings from TLDs will accident. be simulated.

(7a): Demonstrate ability to mobilize and deploy field monitoring teams in a timely fashion. [FEMA-GM-EX-3: (7)]

RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS E.2 This NUREG is the same as that used to support Core Objective 1b.

I.8 Each organization, where Rad 5 Actual demonstration for appropriate, shall provide Env airborne- release from methods, equipment and the site.

expertise to make rapid assessments of the actual or potential magnitude and locations of any radiological hazards through liquid or gaseous release pathways.

This shall include activation, notification means, field team composition, transportation, communication, monitoring equipment and estimated deployment times.

NOTE: FEMA expects the State to demonstrate two field monitoring teams. Both teams will be evaluated by FEMA.

(7b): Demonstrate appropriate equipment and procedures for determining ambient radiation levels. [FEHA-GH-EX-3: (7)]

RESP NOT NUREG 0654 GRP DEHO DEHO COHHENTS H. 12 Each organization shall Rad 8 x Actual demonstration by establish a central point Env collection of field (prefer ably associated with samples and return to the licensee's near-site the EOF.

Emergency Operations Facility), for the receipt and analysis of all field monitoring data and coordination of sample media.

1.8 This NUREG is the same as that used to support Core Objective 7a.

XX-20

(Tc): Demonstrate appropriate equipment and procedures for collection, transport, and analysis of samples of soil, vegetation, water, and milk. [FEMA-GM-EX-3: (7)]

RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS I.8 This NUREG is the same as that used to support Core Objective 7a.

(8): Demonstrate appropriate equipment and procedures for measurement of airborne radioiodine concentrations as low as 10 pCi/cc in the presence of noble gases.

[FEHA-GH-EX-3 (8)]

RESP NOT NUREG 0654 GRP DEHO DEHO COHHENTS I.7 This NUREG is the same as that used to support Core Objective 5.

I.8 This NUREG is the same as that used to support Core Objective 7a.

1.9 Each organization shall have a Rad 8. x Actual demonstration capability to detect and Env using data supplied to measure radioiodine participants after concentrations in air in the demonstrating proper plqpe exposure EPZ as low as sample technique.

10 pCi/cc (microcuries per cubic centimeter) under field conditions. Interference from the presence of noble gas and background radiation shall not decrease the stated minimum detectable activity.

II-22

(9): Demonstrate the ability to obtain samples of particulate activity in the airborne plume and promptly perform laboratory analysis. [FEMA-GM-EX-3: (9)]

RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS I.7 This NUREG is the same as that used to support Core Objective 5.

I.8 This NUREG is the same as that used to support Core Objective 7b.

I. 10 Each organization shall Rad 8 x Dose rates, dose

'establish means for relating Env projections, and the various measured integrated doses will be parameters (e.g., calculated based on data contamination levels, water indicated on and air activity levels) to instrumentation and dose rates for key isotopes provided from field (i.e., those given in Table 3, teams.

page 18) and gross radioactivity measurements.

Provisions shall be made for e estimating integrated dose from the projected and actual dose rates and for comparing these estimates with the protective action guides. The detailed provisions shall be described in separate procedures.

XI-23

( 10a): Demonstrate the ability, within the plume exposure pathway, to project dosage to the public via plume exposure, based on plant and field data. [FEMA-GM-EX-3:

(10)3 RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS I.4 Each licensee shall establish Rad 5 x Actual demonstration the relationship between Env using the STREAM system.

effluent monitor readings and onsite and offsite exposures and contamination for various meteorological conditions.

I. 10 This NUREG is the same as that used to support Core Objective 9.

II-24

(10b): Demonstrate the methodology for determining the release rate/projected doses if the instrumentation used for assessment is offscale or inoperable. (NUREG ONLY)

RESP NOT NUREG 0654 GRP DEHO DEHO COHHENTS I.6 Each licensee shall establish Rad L x Not demonstrated.

the methodology for Env determining the release rate/projected doses if the instrumentation used for assessment are offscale or inoperable.

II-25

( ll): Demonstrate the ability to make appropriate protective action decisions, (recommendations for licensee) based on projected or actual dosage, EPA PAGs, availability of adequate shelter, evacuation time estimates, and other relevant factors. [FEMA-GM-EX-3: (Il)]

RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS E.7 Each organization shall NEP 5 x Actual demonstration, provide written messages Speci scenario will require a intended for the public, Office protective action consistent with the licensee's recommendation to be classification scheme. In made.

particular, draft messages to the public giving instructions with regard to specific protective actions to be taken by occupants of affected areas shall be prepared and included as part of the State and local plans. Such messages should include the appropriate aspects of sheltering, ad hoc respiratory protection, e.g.,

handkerchief over mouth, thyroid blocking or evacuation. The role of the licensee is to provide supporting information for the

'essages. For ad hoc respiratory protection see "Respiratory Protective Devices Manual" American Industrial Hygiene Association, 1963 pp. 123-126.

J.10.m The bases for the choice of All x Actual demonstration.

recommended protective actions from the plume exposure pathway during emergency conditions. This shall include expected local protection afforded in residential units or other shelter for direct and inhalation exposure, as well as evacuation time estimates.

II-26

(12): Demonstrate the ability to initially alert the public within the 10-mile EPZ and begin dissemination of an instructional message within 15 minutes of a decision by appropriate State and/or local official(s). [FEMA-GM-EX-3: (12)]

RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS E.6 Each organization shall All Protective action establish administrative and recommendations will physical means, and the time result in discussions required for notifying and with simulated state providing prompt instructions representatives to the public within the plume initiating public exposure pathway Emergency information messages.

Planning Zone. (See Appendix 3.) It shall be the licensee's responsibility to demonstrate that such means exist, regardless of who implements this requirement.

It shall be the responsibility of the State and local governments to activate such a system.

NOTE: FEMA expects two route alert teams per county will actually perform a route alert for the hearing impaired. No contact with the hearing impaired individual is necessary. However, the team should drive to the location and point out the residence of the hearing impaired individual for the evaluator.

All other :urisdictions with hearing impaired residents should demonstrate the ability to notify these individuals by documented identification of hearing impaired residents and their locations within the jurisdiction. No actual dispatch of route alert teams is necessary.

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(13): Demonstrate the ability to coordinate the formulation and dissemination of accurate information and instructions to the public in a timely fashion after the initial alert and notification has occurred. [FEMA-GM-EX-3: (13)]

RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS E.3 This NUREG is the same as that used to support Core Objective lb.

E.4 This NUREG is the same as that used to support Core Objective 1b.

E.5 State and local government NOT A LICENSEE organizations shall establish RESPONSIBILITY a system for disseminating to the public appropriate information contained in initial and followup messages received from the licensee including the appropriate notification to appropriate broadcast media, e.g., the Emergency Broadcast System (EBS).

G.4.a Each principal organization Speci Actual demonstration shall designate a spokesperson Office using actors and mock who should have access to all phone calls as necessary necessary information. to initiate public information actions.

b Each organization shall establish arrangements for timely exchange of information "among designated spokespersons.

c Each organization shall establish coordinated arrangements for dealing with rumors.

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(14): Demonstrate the ability to brief the media in an accurate, coordinated, and timely manner. [FEMA-GM-EX-3: (14)]

RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS G.3. a Each princi pal organi zati on Speci The activation of the shall designate the points of Office MOC at the YMCA in contact and physical locations Berwick will be for use by news media during demonstrated for the an emergency. 9/17 and 10/8 exercises.

The Information Center will be used for the 8/20 exercise.

G.3.b This NUREG is the same as that used to support Core Objective 5.

G.4.a This NUREG is the same as the used to support Core Objective 13.

.4.b This

~ ~ NUREG is the same as that used to support Core Objective 13.

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(15): Demonstrate the ability to establish and operate rumor control in a coordinated and timely fashion. [FEMA-GM-EX-3: (15)]

RESP NOT NUREG 0654 GRP . DEMO DEMO COMMENTS G.4.c Each organization shall Speci Actual demonstration; establish coordinated Office phone calls will be made.

arrangements for dealing with by various people asking rumors. questions.

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GROUP B: SCENARIO DEPENDENT 16a): Demonstrate the ability to make the decision, based on predetermined criteria, whether to issue KI to emergency workers. [FEMA-GM-EX-3: (16)]

RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS J. 10. f NOT A LICENSEE RESPONSIBILITY.

NOTE: FEMA expects the following to be demonstrated:

Both parts of this objective should be demonstrated:

a) a decision by the appropriate state health officials as to whether to authorize the use of KI by emergency workers and institutionalize persons, and b) the availability of an adequate supply of KI, and the distribution procedure.

The second part is closely tied to Objective 86, and should include:

1) supply of KI at storage locations (to verify quantity; sealed KI not to be opened).

2) delivery procedure, in real time, if required. This includes transfer of (simulated) KI from the storage location to the distribution site, during the exercise, according to the plans.

3) distribution procedure to emergency workers, including briefing.

Monitors at mass care and emergency worker decon centers should have simulated KI and be fully knowledgeable of the procedures for its administration.

(16b): Demonstrate the ability to supply and administer KI, once the decision has been made to do so. [FEMA-GM-EX-3: (16)]

RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS J.10.e NOT A LICENSEE RESPONSIBILITY.

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Demonstrate the ability to make the decision, if the State plan so specifies, to recommend the use of KI for the general public, based on predetermined criteria, it if 0 as well as'o distribute and administer necessitated by radioiodine release.

once the decision is made,

[FEMA-GM-EX-3: (17)]

RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS J.10. f NOT A LICENSEE RESPONSIBILITY.

Ij-33

Demonstrate ability to project dosage to the public via plume exposure, based on plant and field data, and to determine appropriate protective measures, based on PAGs, available shelter, evacuation time estimates, and all other appropriate factor s. [FEMA-GM-EX-3: (18) ]

RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS E.7 This NUREG is the same as that used to support Core Objective 11.

I. 10 This NUREG is the same as that used to support Core Objective 9.

J. 10.m The NUREG is, the same as that used to support Core Objective 11.

(18b): Demonstrate the organizational ability and resources necessary to manage an orderly evacuation of all or part of the plume EPZ. [FEMA-GM-EX-3: (18)]

RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS J.2 Each licensee shall make NEP 3 x Site evacuation will be provisions for evacuation Sec simulated.

routes and transportation for onsite individuals to some suitable offsite location, including alternatives for inclement weather, high traffic density, and specific radiological conditions.

NOTE: FEHA expects the following to be demonstrated:

1. Lists of people with special needs

2. calls to providers of buses, ambulances, and other vehicles to verify availability (vehicles will not be dispatched)

3. Counties are to notify hospitals and nursing homes at the initial notification.

Calls to hospitals and nursing homes for patient census, and arrangements for transportation to host health care facilities should be demonstrated.

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(18c): Demonstrate the organizational ability and resources necessary to effect an orderly evacuation of mobility-impaired individuals within the plume EPZ.

[FEMA-GM-EX-3: (18)]

RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS J.10.d NOT A LICENSEE RESPONSIBILITY.

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(19): Demonstrate the ability and resources necessary to implement appropriate protective actions for school children within the plume EPZ. [FEMA-GM-EX-3:

(19) I RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS J.9 NOT A LICENSEE RESPONSIBILITY J.10.g NOT A LICENSEE RESPONSIBILITY.

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(20a): Demonstrate the organizational ability and resources necessary to control evacuation traffic flow and to control access to evacuated and sheltered areas.

[FEMA-GM-EX-3: (20)]

RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS J.IO.k NOT A LICENSEE RESPONSIBILITY NOTE: FEMA expects the following to be demonstrated:

The requirements for establishing traffic and access control for the entire evacuated area should be addressed administratively at the state and local EOCs, in accordance with the plans. Actual field demonstrations should be:

1) two Traffic Control Points per risk county

2) two Access Control Points per each risk county

3) One traffic control point in each risk municipality which has traffic control responsibilities.

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(20b): Demonstrate the organizational ability and resources necessary to control access to the evacuated area. [FEMA-GM-EX-3: (20)]

RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS J.10.3 NOT A LICENSEE RESPONSIBILITY II-39

(21): Demonstrate the adequacy of procedures, facilities, equipment and personnel for registration and radiological monitoring of evacuees. [FEMA-GM-EX-3: (21)]

RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS J.12 NOT A LICENSEE RESPONSIBILITY NOTE: FEMA expects the following demonstration:

One center per county. Centers should be staffed, including monitoring/decontamination personnel if applicable. Staffing will consist of a minimum of two persons, and one volunteer evacuee per center.

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(22): Demonstrate the adequacy of facilities for mass care of evacuees. [FEMA-GM-EX-3: (22)]

RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS J.10.h NOT A LICENSEE RESPONSIBILITY NOTE: FEMA expects the following to be demonstrated:

One center per county. Centers should be staffed, including monitoring/decontamination personnel. Staffing will consist of a minimum of two persons,to manage the center, one monitoring and decontamination team of two people, and one volunteer evacuee per center.

(23): Demonstrate adequacy of ambulance facilities and procedures for handling contaminated individuals. [FEHA-GH-EX-3: (23)]

RESP NOT NUREG 0654 GRP DEHO DEHO COHHENTS L.4 NOT A LICENSEE RESPONSIBILITY II-42

(24): Demonstrate adequacy of hospital facilities and procedures for handling contaminated individuals. [FEMA-GM-EX-3: (24)]

RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS L.I NOT A LICENSEE RESPONSIBILITY

(25): Demonstrate adequate equipment and procedures for decontamination of emergency workers, equipment, and vehicles and for waste disposal. [FEMA-GM-EX-3: (25)]

RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS K.5.a Each organization, as HP & x Contamination limits appropriate, shall specify Rad & will be exceeded and action levels for determining Env appropriate action will the need for decontamination. be required.

K.5.b Each organization, as HP 8 x Scenario does not appropriate, shall establish Rad & include a medical the means for radiological Env emergency.

decontamination of emergency personnel wound, supplies, No equipment will be instruments and equipment, and deconned.

for waste disposal.

K.7 Each licensee shall provide HP & x Not demonstrated.

the capability for Rad &

decontaminating relocated Env onsite personnel, including provisions for extra clothing and decontaminants suitable for the type of contamination expected, with particular attention given to radioiodine

~

contamination of the skin.

'OTE:

FEMA expects the following to be demonstrated:

One emergency worker decontamination station per risk county; station should be staffed with minimum of a two person team. Monitoring and decontamination of equipment should be demonstrated.

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GROUP C: OTHER OBJECTIVES TO BE DEMONSTRATED AT LEAST ONCE EVERY SIX YEARS (26): Demonstrate ability to identify need for, request, and obtain Federal assistance. [FEMA-GM-EX-3: (26)]

RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS C. 1 The Federal government NEP x Not demonstrated; no

. maintains in-depth capability simulated or actual to assist licensees, States federal assistance.

and local governments through the Federal Radiological Monitoring and Assessment Plan

[formerly Radiological Assistance Plan (RAP) and Interagency Radiological Assistance Plan (IRAP)]. Each State and l.icensee shall make provisions for incorporating the Federal response capability into its operation plan, including the following:

a. specific persons by title authorized to request Federal assistance; see A.l.d, A.2.a.

b. specific Federal resources expected, including expected times of arrival at specific nuclear facility sites; XI-45

(2I): Demonstrate appropriate equipment and procedures for collection, transport, and analysis of soil, vegetation, snow, water, and milk. [FEMA-GM-EX-3:

(~7)f RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS I.8 This NUREG is the same as that used to support Core Objective 7b.

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(28): Demonstrate the appropriate lab operations and procedures for measuring and analyzing samples of vegetation, food crops, milk, meat, poultry, water,and animal feeds (indigenous to the area and stored). [FEMA-GM-EX-3: (28)]

RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS C.3 Each organization shall Rad L Not demonstrated.

identify radiological Env laboratories and their general capabilities and expected availability to provide radiological monitoring and analyses services which can be used in an emergency.

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Demonstrate the ability to project dosage to the public via ingestion pathway exposure based on field data, and to determine appropriate protective measures, based on PAGs and other relevant factors. [FEMA-GM-EX-3'29)]

RESP NOT NUREG 0654 . GRP DEMO DEMO COMMENTS I. 10 This NUREG is the same as that used to support Core Objective 9.

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(30): Demonstrate ability to implement protective actions for ingestion pathway hazards. [FEMA-GM-EX-3: (30)]

RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS J.11 NOT A LICENSEE RESPONSIBILITY.

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(31): Demonstrate ability to estimate total population exposure. [FEMA-GM-EX-3:

(31)i RESP NOT NUREG 0654 GRP DEMO DEMO . COMMENTS M.4 Each plan shall establish a Rad 8 x Not demonstrated.

method for periodically Env estimating total population exposure.

Demonstrate the ability to determine appropriate measures for controlled reentry and recovery based on estimated total population exposure, available EPA PAGs, and other relevant factors. [FEMA-GM-EX-3: (32)]

RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS M. 1 Each organization, as Rad 8. x Not demonstrated.

appropriate, shall develop Env general plans and procedures for reentry and recovery and describe the means by which decisions to relax protective measures (e.g., allow reentry into an evacuated area) are reached. This process should consider both existing and potential conditions.

(33): Demonstrate ability to implement appropriate measures for controlled recovery and reentry. [FEMA-GM-EX-3: (33)]

RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS M. 1 This NUREG is the same as that used to support Core Objective 32.

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(34): Demonstrate ability to fully staff facilities and maintain staffing around the clock. [FEMA-GM-EX-3: (34)]

RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS A. l.e This NUREG is the same as that used to support Core Objective A.2.a Each organization shall NOT A LICENSEE specify the functions and RESPONSIBILITY.

responsibilities for major elements and key individuals by title, of emergency response, including the following: Command and Control, Alerting and Notification, Communications, Public Information, Accident Assessment, Public Health and Sanitation, Social Services, Fire and Rescue, Traffic Control, Emergency Medical Services, Law Enforcement, Transportation, Protective Response (including authority to request Federal assistance and to initiate other protective actions), and Radiological Exposure Control.

The description of these functions shall include a clear and concise summary such as a table of primary and support responsibilities using the agency as one axis, and the function as the other.

(See Section B for licensee.)

A.4 Each principal organization All Actual demonstration by shall be capable of continuous filling out shift (24-hour) operations for a rosters.

protracted period. The individual in the principal An actual shift change organization who will be will be demonstrated for responsible for assuring all the TSC positions continuity of resources during the 10/17 (technical, administrative, practice exercise.

and material) shall be specified by title.

(34): CONT'0 RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS E. l This NUREG is the same as that used to support Core Objective 2.

E.2 This NUREG is the same as that used to support Core Objective lb.

F. 1 This NUREG is, the same as that used to support Core Objective 2.

H.4 This NUREG is the same as that used to support Core Objective 2.

NOTE: FEMA expects the fo'allowing to be demonstrated:

A complete shift change must be demonstrated at the following locations: risk counties EOCs and risk municipal EOCs.

II-54

(35a): Each licensee shall establish the means and time required to warn or advise onsite individuals and individuals who may be in areas controlled by the operator, including:

1. Employees not having emergency assignments.

2. Visitors.

3. Contractor and construction personnel.

.4. Other persons who may be in the public access areas on or passing through the site or within the owner controller area.

tFEMA-GM-EX-3: (35)]

RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS J.l Each licensee shall establish Ops 5 x Actual demonstration the means and time required to Sec initiated by events in warn or advise onsite the scenario.

individuals and individuals who may be in areas controlled by the operator, including:

a. Employees not having emergency assignments;

b. Visitors;

c. Contractor and construction personnel; and

d. Other persons who may be in the public access areas on or passing through the site or within the owner controlled area.

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(35b): Each licensee shall make provisions for evacuation routes and transportation for onsite individuals to some suitable offsite location, including alternatives for inclement weather, high traffic density and specific radiological conditions. [FEMA-GM-EX-E: (35)]

RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS J.2 This NUREG is the same as that used to support Core Objective 18b.

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(35c): Each licensee shall provide for radiological monitoring of people evacuated .from the site. lFEMA-GM-EX-3: (35)],.

RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS J.3 Each licensee shall provide HP x Not demonstrated.

for radiological monitoring of people evacuated from the site.

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(35d): Demonstrate the ability to effect an orderly evacuation of onsite personnel. [FEMA-GM-EX-3: (35)]

RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS J.4 Each licensee shall provide Plant x Not demonstrated.

for the evacuation of onsite S. Sec non-essential personnel in the event of a Site or General Emergency and shall provide a decontamination capability at or near the monitoring point specified in J.3.

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(35e): Each licensee shall provide for a capability to account for all individuals onsite at the time of the emergency and ascertain the names of missing individuals within 30 minutes of the start of an emergency and account for all onsite individuals continuously thereafter. IFEMA-GM-EX-3: (35)]

RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS J.5 Each licensee shall provide Plant x Actual demonstration.

for a capability to account 8 Sec for all individuals onsite at the time of the emergency and ascertain the names of missing individuals within 30 minutes of the start of an emergency and account for all onsite individuals continuously thereafter.

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(35f): Each licensee shall, for individuals remaining or arriving onsite during the emergency, make provisions for:

l. Individual respiratory protection

2. Use of protective clothing

3. Use of radioprotective drugs (e.g. individual thyroid protection)

[FEMA-GM-EX-3: (35)]

RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS J.6 Each licensee shall, for Hp x Actual demonstration for individuals remaining or first individual arriving onsite during the entering an airborne emergency, make provisions area.

for:

a. Individual respiratory protection;

b. Use of protective clothing; and

c. Use of radioprotective drugs, (e.g., individual thyroid protection).

IT-60

(36): Demonstrate the ability to carry out emergency response functions (i.e.,

activate EOCs, mobilize staff that report to the EOCs, establish communications linkages, and complete telephone call down) during an unannounced off-hours drill or exercise. [FEMA-GM-EX-3: (36)]

RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS N. l.b An exercise shall include Plant x Actual demonstration, mobilization of State and 5 All except exercises will local personnel and resources NOT be unannounced.

adequate to verify the capability to respond to an accident scenario requiring response. The organization shall provide for a critique of the annual exercise by Federal and State observers/evaluators. The scenario should be varied from year to year such that all major elements of the plans and preparedness organizations are tested within a five-year period. Each organization should make provisions to start an exercise- between 6:00

~

p.m. and

~ midnight, and another between midnight and 6:00 a.m. ~

once every six years.

Exercises should be conducted under various weather conditions. Some exercises should be unannounced.

GENERAL OBJECTIVES RESP NUREG-0654 GROUP COMMENTS N. 4 Off i ci al observers from NEP Individual debriefs will be Federal, State, or local conducted in conjunction with governments will observe, facility 'and overall evaluate, and critique the critiques.

required exercises. A critique shall be scheduled at the conclusion of the exercise to evaluate the ability of organizations to respond as called for in the plan. The critique shall be conducted as soon as practicable after the exercise, and a formal evaluation should result from the critique.

N.5 Each organization shall NEP A formal critique will be establish means for evaluating written with all areas needing observer and participant improvement noted and assigned comments on areas needing to a specific group or improvement, including individual for closeout.

emergency plan procedural changes, and for assigning responsibility for implementing corrective actions. Each organization shall establish management control used to ensure that corrective actions are implemented.

II-62

SECTION III GUIDELINES FOR CONDUCT OF EMERGENCY EXERCISE

CONDUCT OF EMERGENCY EXERCISES (NUREG 0654 N.3)

The following guidelines are provided to all players, referees, and observers to describe how exercises and drills are to be carried out to allow free play for decision-making and to meet the stated objectives. (NUREG 0654 N.3)

SSES EXERCISE MANUAL The exercise will be carried out using the information contained in the SSES EXERCISE MANUAL. This document is safeguarded to insure exercise participants do not have access to it's contents. Distribution is limited to exercise referees and various offsite reviewers such as NRC and FEMA personnel.

The exercise manual contains administrative material such as objectives, guidelines for conduct of the exercise, etc. and scenario support material.

The scenario support material includes:

SCENARIO TIMELINE - Section V EVENT DESCRIPTIONS AND SUPPORT MATERIAL - Section VI PLANT PARAMETER DATA - Section V INITIALS CONDITIONS (DAILY REPORT OF OPERATIONS) - Section VI PLANT RADIOLOGICAL DATA - Section VII ONSITE RADIOLOGICAL DATA - Section VII OFFSITE RADIOLOGICAL DATA - Section VII METEOROLOGICAL DATA - Section VII REFEREE MESSAGES - Section VIII How this material is transmitted to the participants is described in the following sections.

EXERCISE, REFEREES Individuals that have experience in emergency response are selected to be referees. The referees are responsible for exercise initiation per the scenario timeline and evaluation of the area/position assigned.

Each emergency response facility has a lead referee who is designated by a red T-shirt. Reporting to the lead referee are additional referees assigned to initiate and monitor/evaluate individual and group performance. These referees are identified by yellow T-shirts. A chief referee is assigned the responsibility of coordinating the entire exercise and the lead facility referees report to this individual.

Referees should prepare for the training session by reviewing the following sections in the exercise manual.

Section V Part A - Summary ,

Part B - Detailed Timeline Part C - Event Description

Section VIII - Referee Message Sheets These message sheets should be read in conjunction with the Detailed Timeline.

The referees will transmit information contained in the exercise manual to the participants per the timeline in a manner designated by pre-exercise briefings.

For more information concerning referee functions and conduct see the tab labeled Section 4.0 (REFEREE DATA) in the exercise manual.

INITIAL CONDITIONS (DAILY REPORT OF OPERATIONS)

The day of the exercise a simulated DAILY REPORT OF OPERATIONS will be sent to all the key participants by the Chief Referee. The DAILY REPORT OF OPERATIONS is a document used during normal operation to provide general information company wide. The information included in this report is general information that gives status of both units and radwaste. For exercise purposes this simulated report will set up the initial conditions of the station. The report will have pertinent and nonpertinent information to set up the scenario. The exercise participants will not know which information is or is not directly related to the exercise.

EXERCISE INITIATION The day of the exercise all the referees will take up their positions for initiation and monitoring of the exercise. The exercise initiating events will be controlled by the lead controllers. The initiating events will be in the form of supplied data or props as designated by the exercise manual.

Example of supplied data: A Health Physics Tech is determining area radiation and the readings that he is seeing on the instrument are supplied by the accompanying referee.

OR A phone call is made to the Control Room informing them of an injury in the plant.

Example of props: An Operator in the plant investigating an alarm received by the control room finds a photograph of the equipment he is investigating. The photograph depicts the drill conditions.

OR A maintenance man is provided a mock up in the plant to simulate the actual

equipment. The mock up is used to demonstrate trouble shooting technique and damage control repairs.

HOW TO REPORT INFORMATION TO PARTICIPANT The exercise timeline (Section V) and referee message sheets (Section VIII) will provide the necessary information for the referees so they will be able to report information to the participants. The transfer of informati'on is only what the participant would be able to determine in their particular situation. The referees are briefed by the message sheets as to what information is appropriate. An example would be an operator in the plant looking at a local panel with a referee. The operator would not be given any information unless he asked what the indications on the panel were. In another instance where an individual was going into an area affected by fire, the referee would volunteer sensory information such as what smell was in the air, temperature of the room, any smoke that would be seen. The information given to the participants is indicated on the referee message sheets.

The timeline (Section V) indicates referee/participant interface by showing the time and the words REFEREE MESSAGE. The words, REFEREE MESSAGE, indicate that if the participant performs the right -actions or asks the proper questions, information is available and will be provided. The far right column indicates the number of the information sheet which provides the information. When (Appx) is listed after the time the initiating event is an expected action of the participant and there is normally no information sheet associated.

As the initiating events are provided to the plant staff, they will determine the nature of the emergency and implement the appropriate emergency response proc dures. These actions will occur through a free-play response. ;If actions by the participants are other than anticipated and the exercise continuity is jeopardized the lead or chief referee must step in as appropriate and provide the required guidance to keep the scenario on the timeline. This may be done with a prompt called a contingency message and so noted for the critique.

Certain inconsistencies (such as technical reason for the simulated release, etc.) may be intentional and required to provide an exercise basis which tests the plant and corporate response capabilities to the maximum extent in a limited time frame. If an inconsistency is known or determined to be intentional, then the emergency response personnel will note the inconsistency and ignore it. The lead referees have the authority to resolve or explain these problems that occur during the exercise in a manner that maintains the integrity of the exercise.

The internal operations of the emergency response facilities will be identical to their intended operation in a real emergency.

SIMULATING EMERGENCY ACTIONS Exercises are intended to demonstrate actual capabilities as realistically as possible, participants should act as they would during a real emergency.

Wherever possible, actions should be carried out. When it is not feasible to perform an action it should be simulated. ANY QUESTION AS TO THE SIMULATION OF ACTIONS SHOULD BE DIRECTED TO A REFEREE FOR APPROVAL.

SIMULATION - involves identification and utilization of requirements and procedures short of actual employment.

ACTUAL- movement of resources and/or physical implementation for the exercise.

EXAMPLE- Fire hose would be rolled out but not charged without approval of a referee.

ACTIONS OF PARTICIPANTS SHOULD BE IDENTIFIED TO THE REFEREES IF NOT OBVIOUS.

PARTICIPANT IDENTIFICATION Exercise participants will wear color coded baseball caps which identify their position/function in the exercise. The color designation is as follows:

RED Emergency Director/Recovery Manager/Asst .RM YELLOW Emergency Managers and Coordinators (functions identified on ballcap)

BLUE Emergency Staff (personnel reporting to managers)

GREEN Operating Crew and On/Offsite Teams LIGHT BLUE Clerical and Stenographic Staff WHITE NRC BROWN FEMA, EPA, DOE BLACK INPO MAROON DER/BRP GREY PEMA PARTICIPANT CONDUCT Participation in the exercise shall be carried out to the fullest extent possible in accordance with the Emergency Plan and Implementing Procedures as if the exercise were a real emergency. Data should 'be requested from the

referees ifbe it is necessary to perform the functions of the response position.

Data will supplied by the referees after the participants have taken the required actions.

If-there is a question ask the referee for clarification. The referee will not prompt or coach. The referee will not provide information concerning scenario development or resolution of problem areas encountered. The responders are expected to obtain information through their own organizations and exercise their own judgement in determining response actions and resolving problems.

The scenario data follows a predetermined course to accomplish objectives for the exercise; this does not mean that the players should limit their attempts at problem solving. Alternate solutions are encouraged and should be brought to the attention of the referee in their area. The referees will note the alternate solutions but may not allow implementation since it may alter the course of the scenario.

PARTI CI PANT PRECAUTIONS ACTUAL EMERGENCY Should at any time during the course of the exercise, an actual emergency situation arise, all activities and communications related to the exercise will be suspended. All messages concerning actual emergency events shall be preceded with "THIS IS NOT, REPEAT NOT, AN EXERCISE MESSAGE". The lead referee is responsible for terminating or placing on hold the exercise until the actual emergency is handled.

EXERCISE COMMUNICATIONS All exercise communications should begin with, "THIS IS A DRILL". This includes telephone conversations, radio transmissions, plant page announcements, and written documents. The end of the communication should have, "THIS IS A DRILL". It is important that nonparticipating individuals who may overhear exercise communications are not mislead into believing that an actual emergency exists.

COMPLIANCE WITH LAWS Intentional violation of any laws is not permitted during any exercise.

Any motor vehicle response shall observe all normal motor vehicle operating laws which includes: posted speed limits, stop signs/lights, one way streets, etc.

AVOID PROPERTY ENDANGERMENT Exercise participants, referees, and observers should avoid endangering property (public or private), members of the general public, or the environment.

MINIMIZE PUBLIC INCONVENIENCE It is not the intent to arouse or inconvenience the public during the conduct of an exercise. In order to minimize public inconvenience, the public should be informed both prior to .and during the exercise. Also, all communications, particularly in the public relations area,'should be prefaced with "This is a drill."

RADIOLOGICAL CONTROLS Standing Radiation Work Permits (RWPs) are not issued for the conduct of exercises. If scenario events direct players to areas that are actually RWP controlled due to high radiation, surface contamination, or airborne radioactivity, players will simulate the activities they would have performed without actually entering the RWP controlled area.

NO ONE IS EXEMPT (including company and Federal referees) FROM NORMAL STATION RADIOLOGICAL PRACTICES AND CONTROLS.

OBSERVER CONDUCT Individuals must have prior permission from the Supervisor of Nuclear Emergency Planning to observe an exercise. A blue T-shirt will designate an Observer.

The scenario events and times are confidential and shall be kept confidential during the exercise.

While in emergency response facilities, observers must not block the view of status boards, charts, or access to equipment.

Observers should not participate in the exercise nor interfere with the actions of participants and referees. Any questions .should be directed to a referee and not a participant.

EXERCISE CRITIQUE (NUREG 0654 .N. 5)

A critique shall be conducted as soon as practicable after the exercise, and a formal evaluation should result from the critique (NUREG 0654 N.4).

Three tiers of evaluation are involved in the critique process.

FIRST LEVEL: The exercise participants are debriefed after each major portion of the exercise. An example: The PASS SAMPLE TEAM has completed sampling and the assigned referee discusses the evolution with the participants and indicates any weak and/or strong areas.

SECOND LEVEL: The area referees get together with the area managers at the conclusion of the exercise and discuss the exercise mentioning strong and/or weak areas.'verall

THIRD LEVEL: The area lead referees convene to discuss the overall exercise results. The lead referees are responsible for publishing the exercise critique.

EXERCISE CLOSEOUT (NUREG 0654 N.5)

The areas identified in the critique requiring improvement will be addressed, responsibility for corrective action will be controlled as described in NSI 2.2. I to ensure that corrective actions are implemented.

SECTION IV REFEREE DATA AND INSTRUCTIONS

REFEREE INSTRUCTIONS INTRODUCTION Referees are an important aspect of emergency exercises for several reasons.

An emergency exercise could not be conducted without them and would be of little value without the critique process at the end. As mentioned in the EXERCISE PHILOSOPHY section, the attitude of the participants is directly related to how the referees conduct themselves during the exercise. This point 'cannot be stressed enough and the following sections will provide guidance for referee conduct during the exercise.

REFEREE RESPONSIBILITIES Generally referees have the following responsibilities to fulfill before, dur ing, and a fter an exerci se.

PRE-EXERCISE

l. Review Referee Information Packet

2. Attend Scheduled Referee Training Session

3. Participate in Referee Walkthrough

4. Review Message Sheets which pertain to your responsibility

5. Become familiar with Referee Observation Sheets (to be presented at training session)

EXERCISE

l. Assemble at location early

2. Log participants on Attendance Sheets (name, signature, employee number, and position code)

3. Observe/Evaluate Participant Actions

4. Complete Observation Sheets

5. Provide Exercise Data As Appropriate

6. Debrief participants as soon as possible POST EXERCISE

l. Attend/Conduct Debriefing

2. Complete Observation Sheets

3. Collect Attendance Sheets

4. Turn over completed Observation Sheets, Attendance Sheets, and Referee Nanuals to Area Lead Referee

5. Assure that all participants in your .area of responsibility are informed the exercise is over (ie. all onsite and offsite groups)

6. Participate in Critique Presentation IV-2

GUIDELINES FOR REFEREES HOW TO DEAL WITH EXERCISE PROBLEMS The referee structure is laid out such that each area has a lead referee and the other referees in that area report to the lead. As an example, the Control Room Lead Referee has the Simulator Instructor, Communications Referee, and the Control Room Data Man reporting to him. Any problems or questions that the referees cannot answer are to be refereed to the lead referee. The area lead referees report to the Chief Referee and refer any problems or questions they can't answer to him. A complete listing of referees and the telephone number for contact during the exercise is located in this tab.

Referees shall not provide information to the participants regarding scenario development or resolution of problem areas encountered. The participants are expected to obtain information through their own organization and exercise their own judgement in determining response actions and resolving problems.

In the event of incorrect or incomplete responses, or if the participant indicates lack of knowledge of how to proceed, the referee will prompt the participant with necessary instructions and will note the deficiency on the critique forms.

Referees will only guide the actions of the players when it is obvious that unchecked actions will have a significant impact on the successful completion of the exercise. REFEREE PROMPTS SHOULD BE KEPT TO A MINIMUM AND AVOIDED IF AT ALL POSSIBLE.

Each referee has a copy of the exercise manual and the sections necessary to carry out their responsibilities. Each referee is responsible to be knowledgeable in their particular area and of the overall scenario. The referees are selected because of their experience and knowledge. The exercise package has been designed to allow for various response actions to occur in a natural sequence. The data that has been provided in the exercise package is so the referees can feed information to the participants when they ask for it.

The referees are to play the part of the normally used instruments and gauges that are not available during an exercise.

Any portions of the scenario depicting plant system operational transients are simulated events. No Control Room actions, or reactions involving operation of plant systems or affecting generation capability, will be initiated. All exercise messages will be prefixed and suffixed with the words "THIS IS A DRILL."

Referees do not have to follow the radiation exposure control practices for the simulated radiation levels from the emergency exercise. The players must follow the radiation protection rules as applicable to the scenario. Both par ticipants and the referees must adhere to all normal station radiation control practices.

As always SAFETY TAKES PRECEDENCE OVER ALL OTHER EXERCISE RE(UIRENENTS. The referees are responsible to insure that all safety rules are followed at all times.

REFEREE REMINDERS

1. Stick to the timeline as far as giving out information is concerned. If questions arise contact the lead or chief referee.

2. Players are not allowed to introduce items into the exercise.

t

3. Respond to player's questions but provide answers that do not prompt specific actions.

4. Hake notes on both the good and the weak areas on the observation sheets.

5. Debrief the participants as possible during the exercise to provide immediate feedback. The participants should not be surprised at any of the comments found in the final critique package.

6. Be prepared to contribute to the critique at the end of the exercise.

OBSERVATION SHEETS Referee Observation Sheets are an important part of the evaluation process in each exercise. The formal critique is developed around the completed Observation Sheets. To help you complete the Observation Sheets, here are a few helpful suggestions:

Complete the upper portion of your sheet including name, location, and date. This is helpful if questions arise later.

2. If your Observation Sheet includes a log, complete all parts of it.

This aids in reconstruction of the exercise.

3. Observe par ticipant actions.

Evaluate participant actions and record on Referee Observation Sheet using the following scale:

Satisfactory

2. Satisfactory with a few problems that may be subject to follow-up.

3. Deficiency is noted but would not seriously affect our ability to protect the health and safety of the public.

4. Deficiency is noted which would affect our ability to protect the health and safety of the public.

NOTE: ALL EVALUATIONS RECEIVING A 2, 3, OR 4 MUST BE ACCOMPANIED BY A BRIEF EXPLANATION.

5. Note any action, good or bad, you feel worthy of comment but not covered by the questions on the back of the Observation Sheet.

POST EXERCISE CRITIQUE PROCESS Immediately upon completion of the exercise the lead area referees will conduct a debriefing with the lead participants and the area referees. The purpose of this debrief is to solicit input from the exercise participants on the referee observations presented. This information will be the backbone of the formal critique package and player input is important for the overa] l evaluation.

Upon completion of the area debriefing the lead referees will gather at the EOF to provide a general impression of how the overall exercise went.

The lead referees will meet the next day at the EOF to put together an exercise timeline and the exercise critique package. The critique package will then be presented to the company management at a designated time and location.

IV-5

SECTION IV PART A - REFEREE LOCATION AND TELEPHONE NUMBERS IV-6

REFEREE LOCATION AND TELEPHONE NUMBER Referee Phone Number CONTROL ROOM (Simulator)

Lead Control Room Referee D.T. Walsh ext. 3782 Simulator Instructor J. Burke ext. 3782 Communications Referee P.E. Homnick ext. 3782 Control Room Referee W.G. DiDomenico ext. 3782 TECHNICAL SUPPORT CENTER Lead TSC Referee L:D. O'eil ext. 3530 TSC Communications Referee (includes data flow) R.R. Wehr ext. 3530 TSC Rad Referee M. Rochester ext. 3530 TSC Tech Referee R.M. Harris ext. 3530 In-plant Team Referee Coordinator S.B. Kuhn ext. 3530 OPERATIONS SUPPORT CENTER Lead OSC Referee M.G. Bo le ext. 3907 In-Plant Team Referee (Rad) E.J. McIlvaine ext. 3907 In-Plant Team Referee (Rad) ~F.P. J ext. 3907 In-Plant Team Referee (Rad) V.M. Zukauskas ext. 3907 In-Plant Team Referee (Rad) C.P. Lewis ext. 3907 In-Plant Team Referee (Ops/NPO) R.W. Brown ext. 3907 In-Plant Team Referee (Ops/NPO) J.G. Paisle ext. 3907 In-Plant Team Referee (Maint/I&C) M.J. Beshore ext. 3907 In-Plant Team Referee (Ma i nt/I &C) G.A. Farle ext.'3907 Lead Security Referee B.P. McBride ext. 3115 Security Referee R.E. Gaudreau ext. 3115 Security Referee G.E. Galla her ext. 3115 Reactor Coolant Sampl e Team Referee K. Zielkowski ext. 3907 EMERGENCY OPERATIONS FACILITY Lead EOF Referee A.M. Male ext. 3605 EOF Rad Referee R.L. Dot ext. 3605 EOF Tech Referee R.A. Saccone ext. 3605 EOF Communications Referee R.E. Hoo es ext. 3605 Simulated HPN NRC Team M.J. Sh manski ext. 3605 Simulated NRC Hotline (ENS) C.T. Coddin ton ext. 3605

Referee Phone Number E. GENERAL OFFICE GO Tech Referee J.E. Rothe ext. 7550 F. MEDIA OPERATIONS CENTER Lead MOC Referee I.N. Ka lan ext. 3561 MOC Assistant Referee G.C. Lewis ext. 3561 Person to call in, rumors and questions S.R. Walter ext.

G. ENVIRONMENTAL MONITORING TEAMS OSCAR Referee J. Le o Fi el d Near Site Team Referee J.A. Bird Field Offsite Monitor Team Referee G.L. Croll Fi el d Offsite Monitor Team Referee R.R. Kurtz Field Offsite Monitor Team Referee Not re uired Field H. CHIEF REFEREES Chief Rad Referee B.H. Carson ext. 3601 Chief Referee R.H. Halm ext. 3530 I. PLANT SITE Evacuation Group 2nd floor old S&A IV-8

SECTION V - TIMELINE PART A - Summary

FULL SCALE EXERCISE WRITTEN

SUMMARY

The following is an overview describing the events of the detailed timeline and predicted response of the Emergency Organization.

SCENARIO OVERVIEW The exercise will be an afternoon exercise, starting for the operators in the simulator control room with a shift turnover/briefing. The affected unit will be unit 1. The first event will be an earthquake event which will require classification as an UNUSUAL EVENT.

The notifications for the seismic event will be made and the exercise will have begun for the participating organizations. The time of the initial notifications should be about 3:45 p.m.

The next portion of the plant events will be another earth tremor which will cause an upgrade of the emergency classification to an ALERT. The time of the upgrade notifications should be about 4:30 p.m. No major plant component damage will be evident to the plant staff at this time.

At 6 p.m. another tremor will cause a unisolable steam line break in the High Pressure Coolant Injection (HPCI) system, which will initiate an upgrade of the emergency classification to a SITE AREA EMERGENCY. The plant staff will concentrate on reducing primary leakage by reducing plant pressure, attempting to place the plant in a cold shutdown condition. Off site monitoring will be begun by the plant staff. The radioactive release during the initial portion of the exercise will not be of consequence to the general public, since there is no fuel damage and the Reactor Building ventilation system is operating by design.

At 8:20 p.m. another earthquake will cause a design basis break (DBA-recirculation suction line break); available emergency systems will be unable to reflood the reactor core, with subsequent fuel damage. The resultant radioactive release will be from the previously broken steam line. Uncovering the core will initiate a classification upgrade to a GENERAL EMERGENCY and a protective action recommendation.

Additional plant damage is caused by this earthquake to the feedwater system.

A leak is initiated in the Reactor Building Steam Tunnel at an unisolable T.

The operators will be forced to isolate the feedwater piping, thus isolating the feed and condensate to the reactor vessel.

The exercise will be terminated when the correct protective action recommendations have been made and all the objectives for the participating municipalities have been fulfilled, this is expected to occur about 10:30 p.m.

V-2

INITIAL CONDITIONS Sus q uehanna Steam Electric Station Unit 1 has been at 100% power since the refuel outage with the exception of: I

~ the normal surveillance testing (HSIV and Turbine Valve testing, rod swaps, etc.),

~ a problem identified with the ¹4 Main Turbine Control Valve has required additional down powers for investigation and testing,

~ a series of Feedwater heater level. control valve problems,

~ packing leak at the Steam Seal Evaporator 1RV PP-10703.

The ¹4 control valve did not respond properly during weekly turbine valve testing. After the ¹4 control valve was closed, it failed to reopen. The test switch was taken to closed again and released, but the valve failed to open. As the operators were consulting the off normal procedure, the ¹4 control valve slowly opened. All turbine valves appeared to operate normally after that. ,A down power was planned and no abnormalities were found. Hain Turbine valve testing has been completed several times since with no problems noted.

Power reductions have been conducted as a result of feedwater level control problems. The first problem occurred right after turbine valve testing when the 3C feedwater emergency dump valve failed and water level control was lost.

The extraction steam supplies for the 3C, 4C and 5C heaters automatically isolated as high water levels developed in those heaters.

Four group 1 CRAM rods were inserted and reactor recirculation pump flow was decreased. Reactor power stabilized at about 78%. Off normal procedure ON-147-001 was in effect. Power was reduced to 70% and the C feed water string isolated. Later power was reduced to 60% with the reactor recirculation pumps in manual flow control. The emergency dump valve has been repaired and the normal 3C feedwater level control valve is being repaired.

After the repairs were made to the C feedwater heater string it was found that the 5B heater drain and dump valves were not operating. A power reduction was taken and the string was isolated again and repairs made to the 5B feedwater heater level control valves. Power was restored when the valve repairs were completed. The C feedwater heater levels have been oscillating and I&C is investigating.

Other problems not requiring power reductions but ongoing are; M

~ Reactor water cleanup pump seal failures, which require repair and subsequent chemistry excursions,

~ Hain Generator field ground currents increasing,

~ Lube oil intrusion from the Reactor Feedpumps, V-3

~ Pressurization of the 'B'oop of RHR, due to back leakage from the reactor vessel.

The problems with Reactor Water Clean Up continue and are not expected to be resolved until the new pumps are installed.

The Hain Generator Field ground problem appears to have been resolved by flushing the Stator Cooling Water side. The ground currents dropped after flushing and have been fairly constant since. The tech staff engineer is monitoring the situation closely.

The Reactor Feedpump lube oil intrusion problem also appears to be resolved.

The source of the lube,oil has been determined and the injection has been stopped. Chemistry is continuing to monitor for oil and extra effort is being made to get the oil out of the Condensate Demins.

The 'B'HR discharge pressure relief valve (PSV 151-F025B) was found lifted.

The RHR keepfill was isolated to the loop but did not decrease pressure allowing the PSV to reseat.

Investigation of the increasing pressure determined that the problem began after the quarterly valve stoking surveillance. It appears that when the valve stroking was done a problem developed with the HV-1F0158 valve motor operator torque switch and the valve wouldn't seat properly allowing leakage from the first isolation (HV-1F050B and HV-1F0122B) past the second isolation (HV-1F015B), lifting the relief.

It has been determined that the back leakage is greater than the Tech Spec allowable 1 gpm which has placed the plant in action statement 3.4.3.2c. The HV-1F017B valve has been manually closed and the breaker to the motor operator opened. De-energizing HV-1F017B places the RHR system in a 7 day LCO.

A permit has been applied to the power supply of the HV-1F017B motor operator.

Electrical Maintenance is preparing to investigate the problem by looking at the torque switch.

The remainder of the items under investigation are listed on the priority list along with the other plant scheduled work.

SHIFT TURNOVER The above information statements will be given to Operations during a turnover process. The Operators will be given a shift turnover by the Control Room Referees. The turnover will discuss the status of the above items as shown on,,

the Station Priority List. (See Initial ConditionsSection VI.)

SCENARIO The scenario begins with an alarm from the seismic monitoring panel indicating ground motion less than OBE. The operators will acknowledge the alarm, V-4

consult the Off-Normal Procedure and take appropriate actions which will include making an emergency classification. The time of the alarm is 1530.

The operators check the plant for damage by performing surveillances and walk downs as outlined in the Off-Normal procedure. The walkdowns and surveillance procedures will not reveal any physical problems with the plant. A call will come into the site from a simulated State Police officer providing information that the bridge in Shickshinny is damaged and traffic is not being allowed on the bridge.

It is expected that the control room will call the duty manager and the Operations supervisor to report the plant status, and discuss the actions to be taken. The TSC is not expected to be manned until the ALERT classification.

The ALERT classification should be made based on the seismic alarm that will be received in the Control Room at 1615 indicating another ground motion event greater than OBE but less than SSE. The operators will review the procedure again, perform very similar actions as already performed for the UNUSUAL EVENT, start a plant shutdown and upgrade the classification to an ALERT. The TSC will be activated at the ALERT classification and an accountability initiated.

At 1800 another seismic monitor alarm will be received in the Control Room indicating a SITE AREA EMERGENCY level due to ground motion greater than SSE.

The earth tremor will cause a break in the HPCI main steam line drain where the drain attaches to the 10 inch pipe cap. The leak will be unisolable allowing flow into the HPCI room from the Reactor vessel. The release will be to the Reactor Building Compartment Filtered Exhaust system which will filter and treat the effluent. The release will be nobel gas only and low levels, not measurable in the field. The plant Staff will concentrate on isolating the leak in the HPCI Room by attempting to close either the inboard and/or the outboard HPCI Steam isolation valve.

Control Room alarms and a walkdown of the plant will reveal damage from the latest event. The damage will be a cracked weld in a feedwater pipe in the main steam tunnel. The indication outside of the steam tunnel will be an increase of the leak detection temperature and an increased pumping rate of the steam tunnel sump pumps. If entry is made to the steam tunnel it will be explained what the operator will see when he enters the steam tunnel. There will be no actions that the operators will be able to do to reduce the leakage or isolate the leakage at this time. The leakage does not adversely affect the operation of the plant during this time frame.

The plant will be concerned with the line break in the HPCI room and how to isolate it, the leak in the feedwater header and how to isolate it and walk down of the plant components and structures to ensure there is no additional damage.

The final event will be an earthquake which is felt at 2020 hours0.0234 days 0.561 hours 0.00334 weeks 7.6861e-4 months and causes the Design Basis Accident DBA, a break in the reactor recirculation system suction line and a break in the FW line at the previously mentioned crack V-5

location. Due to various pieces of equipment out of service for routine maintenance the core will be uncovered for a significant amount of time allowing significant fuel overheating and damage. The fission products will be released to the HPCI room, recirculated in the Reactor Building by the Standby Gas Treatment System and released after treatment through the HEPA and charcoal.

The leakage from the HPCI system will not be a large amount but will be enough to cause the general area dose rates in the Reactor Building to increase. The largest contributor to off-site dose will be leakage from the main steam system out into the Turbine Building and into the Turbine Building ventilation system. The leakage is through the Hain Steam Isolation Valves (LLRT values) and out a Steam Seal Evaporator packing leak.

Classification of the emergency at the GENERAL EMERGENCY Level will require a protective action recommendation. The extent of the protective action recommendation will be based on the activity released plus the potential for release of large amounts of radioactivity.

The exercise will be terminated when the objectives for extent of play have been fulfilled by the licensee, local municipalities, counties and State.

This is expected to occur about 2230.

SUMMARY

TIMELINE 1500 - Control Room briefing.

1530- Seismic event initiating an emergency classification at the UNUSUAL EVENT level. No significant plant damage.

1615 - Seismic event initiating an emergency classification, at the ALERT level and a plant shutdown. Classification expected to be made by the TSC and no significant plant damage.

1800 - Seismic event initiating an emergency classification at the SITE AREA EMERGENCY level which causes a steam line break in the HPCI system.

2020- Seismic event which causes a pipe failure in the Reactor Recirculation piping inside the containment. The reactor water level will not be restored to above the active fuel for 20 minutes which is a trigger for a GENERAL EMERGENCY classification.

2040 - Core uncovered time has reached 20 minutes and the classification for the GENERAL EMERGENCY will be made and upgrade notifications begun.

2105 - PROTECTIVE ACTION RECOMMENDATION made by the'icensee based on the release to the environment and or the GENERAL EMERGENCY Classification.

2230 - The Annual NRC exercise is terminated.

V-6

SECTION V - TIMELINE PART B - DETAILED TIMELINE V-7

APPROX. TIME OF DAY INITIATING EVENT EXPECTED SEIOUENCE OF EVENTS 1500 Referee Hessa e - Shift Briefers to Operations to start the process of shift turnover. The IS-1 set up initial conditions for the Control Room Referee will review the following with the Control Room Operators. oncoming shift:

1. Previous 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months log entries

2. Operations turnover sheets

3. Previous and present plant priority lists

4. Daily Report of Operations and NSAG Daily Report NOTE: The above material is located in the INITIAL CONDITIONS SECTION of the REFEREE MANUAL.

1500 Referee Hessa e - Equipment set up, Phone company personnel to perform switching in the IS-2 initiate activation of the emergency Service and Administration Building phone room and hook exercise phones, radio, and plant up in the simulator control room.

page for the simulator control room.

Lead Referee to swap simulator radio and check NRC phone activated.

1500 Referee Hessa e - Simulator The initial plant conditions contain the following files: IS-3 Instructor initialize the simulator to IC 8125. RH.91NRC - Equipment status and alarms RH.RAD 1 - Initial radiological conditions for SPDS 8 containment rad RH.PMS65 - RX Building ARHs RH.PHS66 - Turbine Building ARHs RH.PHS67 - Miscellaneous ARHs RH.WE3. I - Initial weather conditions 1

See SECTION IX SIMULATOR INFORMATION for data contained in these files.

1500 Referee Hessa e - Plant page Plant page announcement to be made from Control Room IS-4 announcement for start of 1991 NRC indicating the start of the 1991 NRC GRADED EXERCISE.

GRADED EXERCISE.

1530 Referee Messa e - Simulator Control Room Operator will acknowledge the alarm on the IS-5 initiated alarm from Seismic main control room panel and investigate the indications Monitoring panel. The alarm will be on the seismic monitoring back panel.

APPROX. TIME OF DAY INITIATING EVENT EXPECTED SEQUENCE OF EVENTS the "SEISMIC MONITOR SYSTEM TRIGGERED" alarm.

This is the trigger for UNUSUAL EVENT.

1535 Control Room Operator investigates The Shift Supervisor will review the emergency the back panel, reviews procedure, classification levels and notify the Operations notifies Unit and Shift Supervisor Supervisor and the Duty Manager.

of readings on panel.

1540 The operators will follow the The Alarm Response procedure directs the Shift Supervisor direction given in the alarm to refer to the Emergency Classification Action Levels response procedure and in the off- for classification of the situation.

normal procedure.

The operators are directed by the Off-Normal procedure (ON-000-002) to determine magnitude of the seismic event at the monitoring panel and initiate actions based on the magnitude. For this event the operators will survey the plant looking for potential damage to structures and equipment and run the diesel generators and fire pump.

The Shift Supervisor will review the classification matrix and determine that an UNUSUAL EVENT CLASSIFICATION is required.

APPROX. TIME OF DAY INITIATING EVENT EXPECTED SEQUENCE OF EVENTS 1545 Operations Shift Supervisor to The classification will be based on the EAL, NATURAL classify emergency as an UNUSUAL PHENOMENA which states:

EVENT.

A. Natural Phenomenon occurrence, indicated by:

Earthquake detected by seismic instrumentation systems on panel OC696.

The Shift Supervisor will declare an UNUSUAL EVENT appoint a Control Room Communicator to announce classification over the plant page, initiate initial notifications, announce to Control Room personnel that he is the Emergency Director, and initiate communications with the Duty Manager, Recovery Manager, Operations Coordinator, and Public Information Manager to inform them of the plant status and situation.

1600 The Control Room Communicator The communicator has provided all the required completes notifications to the off- information to the offsite agencies so that they will be site agencies. able to take actions as required by their emergency plans.

1610 Referee Hessa e - Call to Security The State Police report to Security the bridge in from State Police reporting a Shickshinny appears to be damaged as a result of the problem with the bridge over the earthquake. The communicator should pass the information Susquehanna River at Shickshinny. on to the Emergency Director in case an evacuation may be needed at a later time.

1615 ~ff II<< -Ri I I The Control Room Operator will acknowledge the alarm on initiated alarm from Seismic the ma,in control room panel and investigate the Monitoring panel. This alarm will indications on the seismic monitoring back panel.

be the "SEISMIC MONITOR SYSTEM TRIGGERED" alarm.

This is the trigger for the ALERT classification.

1620 Entr Deleted

APPROX. TIHE OF DAY INITIATING EVENT EXPECTED SEOUENCE OF EVENTS 1620 Referee Hessa e - Control Room The Control Room operators are directed to contact one of IS-9 Communicator will contact one of the the seismic monitoring centers to confirm quake activity.

seismic monitoring centers as The operator will call and ask for information concerning required by the off-normal the indications that the control room has received.

procedure.

1620 Control Room Operator investigating The Shift Supervisor will review the emergency the back panel, reviews procedure, classification levels and notify the Operations notifies Unit and Shift Supervisor Supervisor and the Duty Hanager.

of readings on panel.

1625 Referee Hessa e - The operators will The Alarm Response procedure directs the Shift Supervisor -

IS-10 follow the direction given in the to refer to the Emergency Classification Action Levels alarm response procedure and in the for classification of the situation.

off-normal procedure.

The operators are directed by the Off-Normal procedure (ON-000-002) to determine magnitude of the seismic event at the monitoring panel and initiate actions based on the magnitude. For this event the operators will survey the plant looking for potential damage to structures and equipment and run the diesel generators and fire pump.

The Shift Supervisor will review the classification matrix and determine that an ALERT CLASSIFICATION is required.

Investigation of the plant will reveal a minor leak on the common feedwater line in the Reactor Building Steam Tunnel. The leak is located at the T weld where the clean-up recirc line to the Hain Condenser taps off.

1625 Referee Hessa e - The control room The Control Room Operators will report the status of the IS-11 receives word from the operators in equipment runs and walkdowns to the Shift Supervisor who the plant that walkdowns of will in turn inform the rest of the organization.

equipment are complete and no damage is noted.

APPROX. TIHE OF DAY INITIATING EVENT EXPECTED SEQUENCE OF EVENTS 1625 Responders arrive at the OSC and the The OSC begins to set up and muster the people arriving TSC and begin turnover process. for accountability reporting. The OSC Coordinator is briefed by the Control Room and in turn briefs the OSC responders.

1630 Operations Shift Supervisor to The classification will be based on the EAL, NATURAL classify emergency as an ALERT. PHENOHENA Mhich states:

A. Natural Phenomenon occurrence, indicated by:

Earthquake at greater than operating basis earthquake (OBE) levels, indicated on panel OC696.

The Shift Supervisor will declare an ALERT, instruct the Control Room Communicator to initiate upgrade notifications, initiate activation of the TSC, and accountability. The Duty Hanager and the Operations Coordinator will report to the Control Room for the turnover process. The Off-Normal procedure also directs that the plant begin a shutdown which the Shift Supervisor will initiate.

1645 ~fP classify Director H tl E g the events as an y To keep be told the exercise on track the Emergency Director will to make the classification if he hasn't already IS-12 UNUSUAL EVENT if not already done. done so. The fact that the Emergency Director was prompted will be noted for the critique.

1645 Duty Hanager and Operations Shift Supervisor provides status of seismic event, plant, Coordinator report to Control Room actions taken, and plans for placing the plant in a safe for briefing of incident in configuration.

preparation for turnover of emergency management.

1645 The Control Room Communicator The communicator has informed the off-site agencies of completes upgrade notifications to the upgrade of the emergency classification so that the the off-site agencies. agencies may respond as required by their Emergency Plans.

APPROX. TIHE OF DAY INITIATING EVENT EXPECTED SEIOUENCE OF EVENTS 1700 Security reports results of site Security compiles the information required for the accountability to the Operations accountability and determines the reasons for any Shift Supervisor and takes required discrepancies that turn up.

action for any missing individuals.

1700 Referee Hessa e - When the The Emergency Director will release everyone from their IS-13 accountability has been completed accountability stations.

prompt the Emergency Director to release the people from their accountability stations.

1700 Responders arrive at the TSC and The TSC- people start to check communication links, start begin the process of taking over up equipment, determine plant status in preparation for management of the emergency from the turnover.

Control Room.

I 1710 Referee Hessa e - The control room The Control Room Operators will report the status of the IS-14 receives word from the operators in equipment runs and walkdowns to the Shift Supervisor who the plant that walkdowns of will in turn inform the rest of the organization.

equipment are complete.

Investigation of the Reactor Building Steam Tunnel reveals a leak at the weld where the feedwater cleanup line taps off the common header.

1710 Public Information Hanager and The Public Information Hanager will have the required Recovery Hanager briefed by details for preparation and distribution of information Operations Shift Supervisor as to concerning the events at the plant.

extent of incident.

1730 TSC takes control of emergency. The TSC Emergency Director completes briefing the respective Coordinators, receives updates, and announces the TSC has management responsibility of the event. The information that the TSC is in control is passed over the plant page.

APPROX ~ TIME OF DAY INITIATING EVENT EXPECTED SEQUENCE OF EVENTS 1800 Referee Messa e - Simulator Control Room Operator will acknowledge the alarm on the IS-15 initiated alarm from Seismic main control room panel and investigate the indications Monitoring panel. This will bring on the seismic monitoring back panel.

in the "SEISMIC MONITOR SYSTEM TRIGGERED" alarm.

This is one of the triggers for the SITE AREA EMERGENCY classification.

APPROX. TIME OF DAY INITIATING EVENT EXPECTED SEQUENCE OF EVENTS 1800 Referee Messa e - Simulator The indication in the Control Room will be a high instructor to initiate FILE temperature alarm indicating high energy leakage into the RH.HPISO. The file will initiate room. There will be a fire protection alarm indicating indication of a steam line break in an auto start of the fire pump and a Simplex panel alarm the HPCI Room. This break will be showing a smoke detector alarmed. The indication is a the trigger for a SITE AREA fire or a steam leak.

EMERGENCY classification.

The Control Room Operators will check that the HPCI system isolates and continue with the plant shutdown/cooldown. The shift supervisor will refer to the classification matrix and review the steam line break Emergency Action Level.

The plant status at the start of the transient is variable since the previous event required the operators to initiate a controlled shutdown. The plant will probably still be critical and at normal operating temperature and pressure but reduced power. It is expected that reactor power will be about 20%.

The immediate operator action will be to continue the plant shutdown and depressurize the plant. The operators will pay close attention to the HPCI Room Area Radiation Monitors, the vent stack monitors and room temperatures to determine the severity and spread of activity.

The Control Room may discuss with the TSC the option of initiating a Reactor scram at this time. The discussion of whether or not to scram should mention the motion transient that the plant has already been through and the effects of a reactor scram in addition to that transient.

1805 The Control Room will brief the TSC The Control Room informs the TSC of the events that have on the sequence of events that has just occurred and make a recommendation for the TSC to occurred and recommend an upgraded upgrade the emergency to a SITE AREA EMERGENCY. The TSC classification. ED will confer with the Operations Coordinator for actions to be taken based on the sequence of events.

APPROX. TINE OF DAY INITIATING EVENT EXPECTED SE(UENCE OF EVENTS 1805 Referee Hessa e - Control Room Operator dispatched to investigate HPCI steam line break IS-17 directs operator to HPCI Room to indications, proceeds to the TSC for briefing and then to investigate cause for room alarms. HPCI Room.

1805 Referee Hessa e - Control Room Operator dispatched to check auto start of fire pump from IS-18 directs operator to check out the the steam leak in the HPCI Room. The operator will fire pump auto start. report back to the Control Room that the pump start is valid, that there is flow through the system and the pumps are operating properly.

1805 Referee Hessa e - Simulator The high temperature alarm will clue the control room IS-18A Instructor to initiate OVR A12C03 operators to the fact that there is a problem in the which indicates high temperature in steam tunnel which needs to be investigated. An operator the Reactor Building steam tunnel. will be dispatched to determine the cause of the alarm and will report back the results of the investigation.

I o 1810 Referee Messa e - Simulator The Control Room operators will acknowledge the front IS-19 Instructor to initiate Reactor panel alarm and investigate the back panel to determine Building Sump alarm (PANEL 1C692 the origin of the alarm. Review of the back panel will TROUBLE, OVR A06H14) to indicate an indicate the Reactor Building sump level is high. The increasing influent to the sump. Control Room will dispatch an operator to the Reactor Building to investigate.

The source of the leakage is the Reactor Building Steam Tunnel and the common feedwater header leakage.

APPROX. TIME OF DAY INITIATING EVENT EXPECTED SEQUENCE OF EVENTS 1815 The TSC will classify the event as a The ED will classify the emergency based on the EAL, SITE AREA EMERGENCY. STEAM LINE BREAK, which states:

Failure of HPCI steam isolation valve HV-F002 and HV-F003 to close, indicated by position indicator on Panel 1C601.

AND

2. (a OR b OR c OR d OR e OR f)

'a ~ HPCI steamline pipe routing area high temperature annunciation on panel 1C601, or indication on panel 1C614.

OR

b. HPCI equipment area high temperature annunciation on panel 1C601 or indication on panel 1C614.

OR

c. HPCI steaml inc high flow annunciation- on panel 1C601.

OR

d. HPCI steamline tunnel ventilation high delta temperature annunciation on panel 1C601.

OR

e. HPCI turbine exhaust diaphragm high pressure annunciation on panel 1C601.

OR

f. Other indication of steam leakage from the

APPROX. TINE OF DAY INITIATING EVENT EXPECTED SEQUENCE OF EVENTS HPCI system.

The ED will initiate upgrade notifications to offsite and internal, initiate evacuation of non-essential personnel, activation of the EOF, and dispatch the OSCAR monitoring team if not already dispatched.

1815 Referee odessa e - Simulator The file provides indication on the various plant IS-19A Instructor to initiate FILE: indicators of the weather conditions.

RH.WE3.2 to simulate the meteorological conditions.

1820 Referee Messa e - The Control Room The Chemistry Coordinator will respond to the sample IS-20 will request Chemistry to obtain a request by initiating set up of the chem lab and a reactor coolant sample. briefing for the chemists for obtaining a coolant sample.

. g 1820 The Alternate Security Control The security officers dispatched to the EOF for access Center will dispatch officers to control will check the individuals already in the control access to the EOF and building and help the E&S set up crew as requested to initiate call out of EOF personnel. prepare the EOF for activation.

1820 General Office personnel will be The General Office responders begin set up of the called and respond to General facility and data collection for support of the 1830 ~ft-E Office.

t Director classify the events E g as a emergency.

If not made already declared the classification needs to be to reduce the impact on all the participating IS-21 SITE AREA EMERGENCY. groups. The late classification will be noted in the critique if this prompt is required.

1900 Site based individuals begin The interim EOF responders will contact their reporting to EOF and start set up of counterparts in the TSC and be updated on the plant facility. status, actions in progress, and support required. These

'individuals will update the status boards and will provide updated information to the responding managers when they begin to arrive.

APPROX. TIME OF DAY INITIATING EVENT EXPECTED SEQUENCE OF EVENTS 1910 The Engineering Support Manager The Engineerihg Support Manager contacts the TSC contacts the TSC. Emergency Director for plant status and what support is needed from Allentown.

1925 The Engineering Support Hanager The Engineering Support Manager initiates an initiates an accountability for accountability to determine if all the key positions are General Office personnel. filled.

1945 Referee Messa e - Simulator The file provides indication on the various plant IS-21A Instructor to initiate FILE: indicators of the weather conditions.

RH.WE3.3 to simulate the meteorological conditions.

2000 Referee Hessa e - The PCC contacts The status of the situation and any questions asked will IS-22 the General Office Engineering be answered. The GOESH should ask about grid stability Support Hanager and asks for a and potential for loss of all offsite power because of status of events at the plant. the widespread damage that can occur as a result of earthquakes.

2015 EOF takes control of Emergency The Recovery Manager informs the EOF that he has taken Management. over the management of the emergency.

2015 Referee Hessa e - Simulator The file provides indication on the various plant IS-22A Instructor to initiate FILE: indicators of the weather conditions.

RH.WE3.4 to simulate the meteorological conditions.

2020 Referee Hessa e - Simulator The Control Room personnel will acknowledge the alarms on IS-23 Instructor to initiate alarm from the main control panel and investigate the indications on Seismic Monitoring panel which will the seismic monitoring back panel.

be; "SEISMIC MONITORING SYSTEM TRIGGERED" alarm and a FILE: The operators will also respond to the decreased Reactor RH.FWBRK to simulate an earthquake Water inventory and monitor the makeup water flow to the event which causes a Design Basis vessel.

Accident inside the Containment.

The core will not be reflooded due to various ECCS equipment out of service. The core being uncovered for twenty minutes is the trigger for a GENERAL EMERGENCY classification.

APPROX. TINE OF DAY INITIATING EVENT EXPECTED SEQUENCE OF EVENTS 2020 Referee Messa e - Simulator The operators will ackowledge the alarms that will be IS-23A instructor to initiate FILE: indicated by the automatic start of the system and verify RH.SBGTA file to simulate the auto that the system is operating properly in the auto mode.

start of the Standby Gas Treatment System (incorporated in RH.FWBK).

2030 Referee Hessa e - Simulator The file initiates radiological indications on various IS-23B Instructor to initiate FILE: plant indicators. The file provides indication of sever RH.91LOC (incorporated in RH.FWBK). fuel damage.

2035 Referee Hessa e - The Offsite The Off-site Honitoring teams will receive direction from IS-24 Monitoring teams will be dispatched the Off-site Team Director on where to go and when and from the EOF. what to sample.

2035 Referee Hessa e - The Control Room The operators will go to the TSC, be briefed and sent to IS-25 I will dispatch a team to clear the the field to restore the LPCI valve to operable status to permit on the RHR LPCI Injection reflood the reactor vessel and raise the water level valve to reflood the vessel. above the active fuel.

APPROX. TIME OF DAY INITIATING EVENT EXPECTED SEQUENCE OF EVENTS 2040 Referee Messa e - Core uncovered The Operators have been monitoring the top of active fuel IS-26 time has reached 20 minutes which is and water level and are aware that portions of the active the trigger for classification at, fuel has been uncovered for a period of 20 minutes.

the GENERAL BIERGENCY level.

The Containment Radiation monitors show an increase which is an indicator of failed fuel.

The Recovery Manager will classify the emergency as a GENERAL based on the EAL, LOSS OF REACTOR VESSEL INVENTORY which states:

I. Loss of coolant accident with the possibility of imminent release of large amounts of radioactivity, indicated by:

Water level below (and failure to return to) top of active fuel for greater than 20 minutes as indicated on fuel zone level indicator on panel 1C601.

OR II. Loss of 2 out of 3 fission product barriers (fuel cladding 8 reactor coolant pressure boundary) with the potential loss of the third barrier (primary containment).

The Recovery Hanager will initiate upgrade notifications both offsite and internal,,will review the radiological effects of the emergency, and make a protective action recommendation.

2045 Referee odessa e - SPING HI alarm The alarm will be acknowledged by the Control Room IS-27 will be received in the Control Room Operators and investigated at the SPING console. The STA due to the release in the unit 1 will evaluate the cause of the alarm and report his Turbine Building. conclusions to the Shift Supervisor.

APPROX. TINE OF DAY INITIATING EVENT EXPECTED SEQUENCE OF EVENTS 2045 Referee Hessa e - The operators The dose rates in the Reactor Building will be increasing IS-28 report back from the field some of rapidly due to the severe fuel damage. The permit will the dose rates that are observed. have to be cleared and the breaker closed to allow The longer it takes for the teams to operation of the injection valve. When the permit is get into the field to clear the cleared the valve can then be operated.

permit the higher the dose rates.

2050 Referee Hessa e - The Area Radiation The people in the occupied areas will read the indicating IS-29 Honitors in the TSC area and the transmitters to determine the rad levels. When the rad Control Room begin to alarm. levels have been read (10 mrem/hr) a determination will-be made if any protective actions are required to be initiated.

2055 Referee Hessa e - When the '8'ain The operators will do an investigation of the system, IS-30 Steam Leakage Control System is refer to the procedure for start of the system to insure started the system will not start. that all the requirements for starting the system have been met and inform the TSC that support is necessary.

2100 Referee Hessa e - Simulator File simulates reactor building radiation levels and IS-30A Instructor to initiate FILE provides the indications on the various plant indicators.

RH. 91L01.

2100 Referee Hessa e - The Chemistry The Chemistry Coordinator will instruct one of the Chem IS-31 Coordinator will be prompted to Techs to place the background subtract circuit in service place the SPING background subtract to keep the SPING instruments operable.

in service.

2105 ~Rf I -Iftt R Hanager has not made the GENERAL I To keep the exercise on the proposed time line and to minimize the impact on all the participants it is IS-32 EHERGENCY classification at this necessary to make the classification at this time.

time, tell him to do so.

2105 Referee Hessa e - The Off-site Data supplied to the monitoring team personnel will be IS-33 monitoring teams will report back consistent with the actions taken.

the field data.

2115 Referee Hessa e - The TSC tech The General Office will begin to make up a relief roster. IS-34 engineer to inform the GO that a second shift will be required.

APPROX. TIME OF DAY INITIATING EVENT EXPECTED SEIOUENCE OF EVENTS 2115 Licensee, State and NRC to confer The radiological data from the field will not be concerning the recommended available at this time. The data from the field when it Protective Action Recommendations to starts to come in will support an evacuation out to two the Governor. miles and shelter out to 10.

2115 Referee Hessa e - Simulator The file provides indication on the various plant IS-34A Instructor to initiate FILE: indicators of the weather conditions.

RH.WE3.5 to simulate the meteorological conditions.

2120 ~Rf If RR R To keep the exercise on the proposed time line and to IS-35 Hanager has not made a Protective minimize the impact on all the participants it is Action Recommendation at this time, necessary to make the classification at this time.

tell him to do so.

2125 The Governor will initiate an Notifications will be made to the risk counties to sound evacuation of the entire EPZ. the sirens. The sounding of the sirens will be simulated.

2125 Referee Messa e - The EOF Referee to The HOC referee will simulate the sounding of the sirens IS-36 call the HOC Lead Referee to inform for the staff of the HOC and will provide the information them of the Governor's Protective of what the Emergency Broadcast message will be.

Action Recommendation, times of siren initiation and Emergency Broadcast System Hessage.

2130 Referee Hessa e - Representative The General Office will be contacted by the State with IS-37 from the State Gvernor's office several requests for information. The General Office contacts the General Office for will respond to the questions.

information.

2145 Conference call between the Recovery The managers will discuss the status of the plant and the Manager, Emergency Director, radiological conditions on and off-site. They will Engineering Support Manager, and discuss their short and long term goals and strategy.

Public Information Manager.

APPROX. TIME OF DAY INITIATING EVENT EXPECTED SEQUENCE OF EVENTS 2145 Referee Messa e - Simulator The file provides indication on the various plant IS-37A Instructor to initiate FILE: indicators of the weather conditions.

RH.WE3.6 to simulate the .

meteorological conditions.

2230 Referee Hessa e - The NRC GRADED A page announcement is made in all the facilities by the IS-38 EXERCISE is terminated. Lead Referee that the exercise is terminated.

All participants to collect emergency plan records and submit to the facility lead referee.

The Facility Lead Referee will conduct a debriefing in their area and collect the Referee Observation Sheets.

The TSC Lead Referee to contact the phone company personnel at 3999 to restore the phone and page system to normal.

The Control Room Referee to restore the simulator radio system to normal training status.

The formal critique will be worked on 10/17/91 in the EOF starting at 0900 and the critique results will be presented 10/17/91 at 12:30pm.

SECTION V - TIMELINE PART C - BASIS OF TIMELINE EVENTS Section I - Seismic Event V-25

BASIS AND DETAILED DISCUSSION FOR SEISMIC EVENT The seismic monitor alarm, "SEISMIC MONITOR SYSTEM TRIGGERED" will be initiated by the simulator instructor at 1530 to initiate the emergency exercise. The alarm is to simulate a ground motion event monitored by the plant seismic instrumentation. The alarm will come in on the main control board. The operators will acknowledge the alarm and go to the back panel to review the indications on the back panel. The various lights and print outs from the seismic monitoring back panel will provide the operators with the magnitude of the earth quake.

The initial action of the operators will be to check the Alarm Response procedure for required actions. The alarm response procedure refers the operators to the Emergency Plan procedures for classification of the situation and refers to ON-000-002 the Off Normal (ON) procedure for Natural Events.

The ON requires an emergency classification depending on the severity, walkdown of the plant checking concrete structures, tank levels, sump levels, makeup requirements and test runs of the D/Gs and the Diesel Fire Pump. The Control Room will initiate actions in all the mentioned areas by dispatching operators to walk down the plant and check out the building and equipment.

The Shift Supervisor will make the emergency classification as an UNUSUAL EVENT and initiate the notification process. At the same time that the classification is being made, a simulated State Police Officer calls security with information indicating that the bridge across the Susquehanna River at Shickshinny is no longer serviceable. The information concerning the bridge has no affect on the scenario at this time but will affect how the participants react later when an evacuation recommendation needs to be made.

The bridge information will have to be passed through the emergency organization.

The trigger for the ALERT will also be an earthquake as indicated by the "SEISMIC MONITOR SYSTEM TRIGGERED" alarm. The operator actions will be the same as the first event with two notable exceptions. The first is that the operators will begin a plant shutdown and second, the operators will call an

'outside agency for confirmation of the control room indication.

A telephone number will be provided as part of the procedure and an actor will provide answers to the operators questions. The actor will provide a magnitude, the time, and general location of where the center of the quake was.

There will be no indications. of significant damage in the plant or around the plant site.

At 1800 hours0.0208 days 0.5 hours 0.00298 weeks 6.849e-4 months a third seismic event will occur and alarm in the Control Room.

At the time of the seismic event there will be a break in a HPCI steam line drain and a feedwater leak in the Reactor Building Steam tunnel. The control room will receive indication of both breaks via alarms and plant parameter changes.

V-26

Indication of the steam leak in the HPCI room will be high temperature and fire protection alarms. The system will isolate and the steam isolation valves will indicate full close but leakage will continue into the room at the rate of . I GPM.

s'i ll '4g Similar alarms will be received at the same time for the leak in the Reactor Building Main Steam Tunnel. The alarms are high ambient temperature which indicates a fire or steam leak in the steam tunnel and high sump level indicating increased influent.

The operators are expected to investigate the location of the leaks as directed by the alarm response procedure. The leak in the steam tunnel is significant in nature at an unisolable weld. The control room will be shutting down at this time. A reactor scram may or may not be initiated at this time.

The seismic event will be the trigger for the SITE AREA EMERGENCY. The steam line break in the HPCI room may also be used as the trigger for classification since the steam isolation valves are leaking through.

The last initiating event of the exercise will be a seismic event which causes a Design Basis Accident (DBA) inside the containment and a feedwater line break in the Reactor Building steam tunnel at 2030 hours0.0235 days 0.564 hours 0.00336 weeks 7.72415e-4 months .

The break in the feedwater line is to prevent the use of condensate to reflood the reactor vessel. No water will pass through the feedwater header to the vessel.

The 'B'oop of RHR LPCI injection is inop as a result of the injection valve being closed and out of service with the power supply breaker open. As a result the core will not be recovered in 30 minutes and a GENERAL EMERGENCY will be declared.

To restore the vessel level the operators will have to enter the Reactor Building, clear the protection tagging on the breaker for the LPCI injection valve and close the breaker in. During the time that the operators are in the reactor building the dose rates will be increasing.

The leak in the HPCI room has not been stopped and is inputting into the room.

The Standby Gas Treatment system auto started during the DBA and is recircing the Reactor Building atmosphere. There will be a slight release from the Standby Gas Treatment vent. The majority of the release will be out the Turbine building ventilation system.

The initial conditions of the exercise provided a leak at the Steam Seal evaporator in the Turbine Building. With minimal leakage through'he Hain Steam Isolation Valves (0.01 gpm) and out the Turbine Building ventilation, untreated, a significant release will be realized off site.

The control room will attempt to place Hain Steam Leakage Control in service but a limit switch in one of the Hain Steam Isolation Valves is preventing the system from going into operation. When it is determined what is preventing V-27

the system from being placed in service the leakage through the Hain Steam Isqlation Valves will be stopped (a jumper will have to be installed around a position limit switch).

A protective action recommendation will be made based on the classification of General Emergency. When the General Emergency is declared there will not be a significant release in progress. After the reactor core has been uncovered for 30 minutes there will be significant fuel damage. The damaged fuel will cause a large, rapid increase in the containment radiation levels. The containment radiation used for 'what if'alculations will also push the classification to a General Emergency due to the size of the source term. The simulated damage will be 5% fuel melt.

The exercise will be terminated after the state has implemented protective actions and fulfilled the objectives necessary for satisfactory demonstration and the field monitoring teams have verified the release to the environment.

V-28

SECTION VI INITIAL CONDITIONS PART A SSES DAILY REPORT

SUSQUEHANNA STEAM ELECTRIC STATION UNIT 1/UNIT 2 DAILY REPORT FOR 10/16/91 SSES DUTY MANAGER: G. J. Kuczynski G.O. DUTY MANAGER: R. G. Byram UNIT 1 UNIT 2 Days on Line: 305 Days on Line: 0 Condition: 1 at 0500 hrs Condition: 5 at 0500 hrs Rx Power: 100% at 0500 hrs Rx Power: 04 at 0500 hrs MW (e) Gross: 1074 at 0500 hrs MW (e) Gross: 0 at 0500 hrs MWH Gross: 25,774 previous 24 hrs MWH Gross: 0 previous 24 hrs MWH Net: 24,907 previous 24 hrs MWH Net: -102 previous 24 hrs Core Flow: 944 Core Flow: 40%

Rx Conductivity: .169 micromho/cm Rx Conductivity: NA micromho/cm Days Since Last Auto Shutdown: 653 Days Since Last Auto Shutdown: 324 Man-Rem Yesterday: 1.852 Man-Rem Year-to-Date: 542.989 UNIT 1:

SUMMARY

PREVIOUS 24 HOURS:

'B'esidual Heat Removal (RHR) quarterly flow surveillance not completed.

problem with primary leakage into RHR system. 7 day LCO entered.

Steam leak investigation found leak in SSE room on PP isolation valve.

Unit 1 off gas recombiner not placed in service, water found in the recombiner MAJOR EVOLUTIONS IN PROGRESS/PLANNED:

Complete quarterly work window and flow surveillance on 'B'HR Loop.

LCO's REQUIRING SHUTDOWN ACTION (within 3 days):

None

SIGNIFICANT OPERATING OCCURRENCE REPORTS/LICENSEE EVENT REPORTS:

1-91-326 RHR flow switch found out of tolerance.

1-91-327 Steam leak in the Steam Seal Evaporator area.

SSES DAILY REPORT Page 2 UNIT 2:

SUMMARY

PREVIOUS 24 HOURS:

Completed fuel loading.

Restored the Electro-Hydraulic Control system.

MAJOR EVOLUTIONS IN PROGRESS/PLANNED:

Control Rod Drive friction testing is in progress.

Restore service water.

Restore RHR Division II.

LCO's REQUIRING SHUTDOWN ACTION (within 3 days):

None SIGNIFICANT OPERATING OCCURRENCE REPORTS/LICENSEE EVENT REPORTS:

2-91-198- Five Safety Relief Valves were found out of Tech Spec tolerance 2-91-200 Small fire in the drywell.

INSPECTORS ON SITE:

NRC ALARA Team onsite 10/15 thru 10/18: Jim Noggle, Anthony Markley, David Mann and Bruce Dionne NRC ISI Inspector onsite 10/16 thru 10/17: P. Patniak NRC Inspector onsite for close-out of Open Items: Fred Bower LIQUID RADWASTE: 101,706 gallons

SAFETY RECORD: YEAR-TO-DATE OCTOBER Lost Time: 0, 0 Non-Lost Time: 5, 0 Motor Vehicle: 0 0 First Aid: 8 0 DAYS SINCE LAST NUCLEAR DEPARTMENT LOST TIME ACCIDENT: 255 VI-4

SECTION VI INITIAL CONDITIONS PART B NSAG DAILY REPORT VI-5

PP&L NUCLEAR SAFETY ASSESSMENT GROUP SUSQUEHANNA STEAM ELECTRIC STATION DAILY REPORT DATE: 10/16/91 Report period: 0800 hrs 10/15/91 to 0800 hrs 10/16/91 Unit 1 Plant Parameters:

Plant Condition 1 Power 100% Megawatts Gross 1076 Total Core Flow 93.4 Million lbs/hr Primary Coolant Conductivity 0.17 umhos/cm HP Condenser Backpressure 2.8 in. Hga Offgas Pretreatment Rate 106 uCi/sec Flow 16 scfm Number of Control Room Alarms Lit 10 Unit 2 Plant Parameters:

Plant Condition 5, Refueling Reactor Coolant Temperature 104 Deg F.

Reactor Cavity Flooded.

Reactor Cavity to Fuel Pool Gates Removed.

Unit Common Plant Parameters:

Number of Control Room Alarms Lit 7 Page 2 of 3 Major Work in Progress/Completed and Problems Unit 1:

1. The Unit 1 off gas recombiner has been found to contain water. Efforts to return the recombiner to service were halted last night at about midnight when the water was discovered. Water was also found in the guard bed in Radwaste. The problem is being investigated.

(0730 mtg., Unit 1 log)

2. A steam leak has developed at valve 1 RV PP-10703, inboard root valve for PP-10703 located on the main Steam supply line to the Steam Seal evaporator between HV-10703 and HV-10109.

The leakage is in the SSE room. (SOOR 1-91-327)

Major Work in Progress/Completed and Problems Unit 1: (cont ')

3. The 'B'BCCW heat exchanger is out of service to retube the heat exchanger. The hydrostatic test was completed. (0730 mtg.)

4. Main Generator field ground current is increasing slightly.

This mornings reading wass 2.8 milliamps. (0730 mtg., tour)

5. The 'B'HR loop quarterly flow surveillance was not completed. The

'B'PCI injection valve is leaking back into the RHR system causing the system to pressurize. The HV-1F017B has been closed and an LCO entered. (Unit 1 log, 0730 mtg.)

6. The 'B'ontainment instrument gas compressor is out of service for preventive and corrective maintenance. (0730 mtg.)

Major Work in Progress/Completed and Problems Unit 2:

1. Core Cooling Status Board (0740 10/16/91)

Electrical All AC available.

All DC available.

Core Spray 'A'nd 'B'oops.

ECCS RHR 'A'HR pump.

Alt. Ul FPC system.

OPDRV None Notes Reactor cavity flooded/fuel pool to cavity gates removed.

Fuel pools crosstied via the cask storage pit.

2. Fuel loading was completed at 2241 hours0.0259 days 0.623 hours 0.00371 weeks 8.527005e-4 months last night. Core verification has also been completed. (Unit 2 log, 0730 mtg.)

3. Logic system functional testing of RHR Division SE-249-002 was completed. Division II II per will be declared operable and placed in shutdown cooling. (0730 mtg.)

4. A small fire occurred in the drywell at about 1830 hours0.0212 days 0.508 hours 0.00303 weeks 6.96315e-4 months last night.

A small bag of rags was ignited due to welding in the area. The workers stomped out the fire and moved the smoldering rags to the decon room where they were wetted down. The fire caused no damage and no fire suppression systems were activated.

(SOOR 2-91-200)

Five of the eight main steam relief valves tested at Wylie II 5.

Laboratories failed to meet the + or 14 tolerence.

Three valves lifted below their setpoint and two lifted above their setpoint. (SOOR 2-91-198)

Major Work In Progress/Completed and Problems Unit: 2 (cont'd)

6. The problem with the RHR F024B full flow test valve not closing fully is not resolved. (Unit 2 log)

Major Work in Progress/Completed and Problems Unit: Common

1. The 'C'hlorine evaporator work was completed. (0730 mtg.)

2. Radwaste chiller in. progress.

and Zone III chiller restorations are (0730 mtg.)

-Short Term Schedule Unit 1: Repair feedwater heater level control valves.

Short Term Schedule Unit 2: Continue outage work.

NSAG Management Attention: None Richard Henry Andre Dominguez Written By Reviewed by VI-8

SECTION VI INITIAL CONDITIONS PART C PRIORITY LISTS VI-9

iO sic s~

PRIORITY LIST 10 1 91 THROUGH 10 1 /91 UNIT 1/CNNON/UNIT 2 PRIORITY LIST UNIT 1 'A' 'B'HR PLAN AUX BOILER PLAN SURV 1/DML3A REPORTS APPROVED:

l5IT I O ~UIT 2 0 V1-10

UNIT ONE PRIORITY LIST FROM 10 15 91 THROUGH 10 16 91 "AROUND-THE L KW RK'B'OOP RHR WORK. QUARTERLY FLOW SURVEILLANCE TO FOLLOW COMPLETION OF WORK.

2. "HCl ENDED HOURS WORK"

'B'BCCW HX OOS TO RETUBE HX PER PMR 88-3041B (WKG - E&SM - ECD 10/22).

3. "NORMALHOURS WORK'EACT BLDG ZONE I AND III HEATING COIL PM'S (WKG - E&SE - ECD 10/18).

TURB BLDG HVAC SPPLY FILTER 1F151 CHANGEOUT (WKG - E&SE - ECD 10/16).

RX BLDG CRANE HOIST 1H213 PM (WKG <<E&SM ECD - 10/22).

TURB BLDG HVAC HEATING COILS 1E151A-H PM'S (FRI - ELEC - ECD 10/26).

'C'FPT LO COOLER 1E118E CORR MAINT (FRI - MECH - ECD 10/26).

'B'IG COMP PM'S (WKG - MECH - ECD 10/25)

"PROBLEMS UNDER REVIEW" STEAM LEAK IN STEAM SEAL EVAPORATOR ROOM (MAIT LEAD)

'O'EEDWATER HEATER STRING LEVELS OSCILATING (l&C LEAD)

5. "CHEMI TRY RELATED PR BLEMS A IATED W RK ACTIVITIES" NONE

6. "GENERAL" U1 RAILROADBAYWALLS REMOVED FOR MISC. WORK ACTIVITIES- PREVENTS 101 DOOR OPENING AND 818'ATCH REMOVAL WALL REINSTALLATION ECD 10/18.

INVEST INTO VARIOUS OFFGAS RECOMB CONCERNS UNDERWAY(TECH LEAD).

PLAN UNDER DEVELOPMENT.

UNIT COMMON PRI RITY LI T FROM 1 1 1 THROUGH 1 16 91 1~ "ARO ND-THE L CK WORK"

'B'S CHILLER Y-STRAINER CLEANING (TUES - E&SM - ECD 10/16).

2. "EXTENDED H R NONE

3. "NORMALHO R WORK"

'A'UX BOILER POST - POST-PMR TESTING TO RESUME AFTER CONDUCT METER RESOLUTION AND COMPLETION OF MOD TESTING; 'B'OILER WORK TO FOLLOW.

MISC. ARM PM'S (WKG - I&C - ECD 10/25).

SIMPLEX PANEL OC551 PWR SPPLY CORR MAINT (WKG - l&C - ECD - 10/16).

CARDOX REFRIG COMPR INVEST/REPAIR (WKG - ELEC - ECD 10/17).

D/G JACKET WTR DRAIN TANK OT597 LINER REPAIR (WKG - E&SM - ECD-10/20).

'C'/G FUEL OIL SYSTEM PMR 91-9013C & MISC LEAK REPAIRS (WKG - E8 SM-ECD 10/20).

OUTSIDE YARD FIRE PROT SYST VALVE REPL'S (WKG - E&SM - ECD - 10/19).

SERV AIR TO MUD NEUT BASIN AIR INLET VLV REPL'S (TUES - E&SM - ECD 10/17).

'D'/G STARTING AIR SKID PREFILTER OF519D2 AUTO DRAIN REPAIR (WKG -

MECH ECD 10/16).

CWPH CRANE OH503 CORR MAINT (TUES - E&SM - ECD 10/19).

4. 'PROBLEMS UNDER REVIEW'ONE

5. 'EMI TRY RELATED PR BLEMS A S IATED W RK A TIVITIE "

6. "RADWASTE RElATED PROBLEMS ASSOCIATED WORK ACTIVITIES'ASTE SLUDGE PHASE SEP DISCH PUMP OP332 REWORK (WKG - MECH -ECD 10/20).

LRW EFFL FLOW RECORDER INOP - LCO (WKG - I&C).

LAUNDRY DRAIN SAMPLE TANK PUMP OP3'I9A REWORK (WKG - MECH/E&SE-ECD 10/20).

'B'ASTE MIX TANK AGITATOR REPAIR (WKG - E&SM - ECD UNDER EVAL).

7. "GENERAL" VI-12

UNIT TWO PRI RITYLI TFR M1 1 1 THRO H'I 1 1

1. "AROUND-THE L K WORK" SEE OUTAGE PRIORITY LIST

2. "EXTENDED H URSW RK" SEE OUTAGE PRIORITY LIST

3. "N RMAL HOURS WORK" SEE OUTAGE PRIORITY LIST

4. "PROBLEMS UNDER REVIEW"

~

SEE OUTAGE PRIORITY LIST "CHEMISTRY RELATED PROBLEMS ASSOCIATED W RK ACTIVmES" SEE OUTAGE PRIORITY LIST

6. 'GENERAL'EE OUTAGE PRIORITY LIST VI-13

SECTION VI - INITIAL CONDITIONS PART 0 - OPERATOR TURNOVER SHEETS VI-14

S ft'\/

PLANT; CONTROL OPERATOR T , AGUA-303

~ t UNIT ~'. '. Qato ~oY/a 9 ."~".';. ':~ ",.-:

.':.>=.ReVIS$ 'OIT 9-p<<e g8 0p 7g

}

L900 to 0700 ",. ~ ~

'HIFT 0700 tert L900 Start Enct . Start -:,';, End.

PLANT STATUS'Tt TURNOVER PLANT'STATUS AT TURNOV CONOITlON I CQNOITIQN ( ~ ) t POWER LEVEL C}O t POWER LEVEL.

GENERATOR OUTPUT MWe.. GENERATOR OUTPUT Mhfe TOTALCORE FLOW RX PRESSURE PIG 'X M Ib/hr 'TOTAL CORE FLOW

~"

PRESSURE M Iblhr PSIG REMARKS: REMARKS:

UNIT ' ~

UNIT t

L&s ,Vkrr'- "*

e ops 8 P 4 8e.

c}i I. '~olacg. gp./llr,'&>, 8 '.C4+

de<. "( " '

~

e ~

t Wdg t 't ~

t 3 <-'Ng v D~V~C ' (L.eJ ' '

5 Ho~ 7ae '57" h)n 'oe ~"' A f(v 'lWCNe. s'r:~':

~ t~

I' t

(

8 =

c.

~

'p(

7 g3, ) ~ pg ~ '7 /5 > 5'T((} <Ti ~ n It AJT A2cE /(( ~ A dr/ J. ll I ((=

N orrC -

\

iP/f4 6'a 'ierJcr7i <re~ V - // o ro 4U- ~/ C.

COMMON ~ ~ '

c4'zi (e oar v~2 u n iS(

\

pJ Q% > 7/ 7/> ( ~ ~wflwu%$

u/}P r i'~k 7'

big PCIIIF,N~~'-

OFFQOINOPLANT'CONTROt OPERATORCH~~~: 'G W 303 1900 70 ':t-" ~">"."...'g$>~j&gi~e~g '" '->Ravks1on 9:

0700 1900 tnformatfon fn Unit Log is complete. and has.beerr dfscusied. v'nth lbs. 'age 69 of'4

-AII testable lights tested and avay Indicator pair show@at least one Ilght. '-.'=-

3. gvofutlons in progress ancl items to be completed during.next sMtas noted In remarks, have been discussed with oncoming PCO..~".'. <gjM;>< Pz,~";",j,:;.'j';: -'",-;".'.,

Problems encountered during past shift anctabnormil plant conditions as noted in remarks,

. have been discussed with oncoming. PCO; .Q~p~~~W>:g.";.~,,~,,r".r.-

control room annuncfators logged and'.dIsc

""'lghted ecL with-oncoming. PCO.

AII control room annuncfators tested succeastufflro '+t%:.i'g~ggp:I." ~cg "-: "'.i"Vi'"~

\

II '

I 0700 TO 1900 l

~ + r '

1 vp

ONCOIINO PLANT CONTROL.OPERATOR CHKCKUST:

700 90 1900 00 t 2.

3'. Reactor Engfneerfng Operating Instructions reviewed.

4 Front and back panele walked down with otfgofng,PCO..

5; ~outlne Training current.

"'0700 TO 1900

'ncomfng, PCO

~ r

~ '

~

1900 TO 0700 Oncoming PCO

~ ~

VI-16 MMtA04A4N4,Her.9. owLs¹ togo s ot s

UNIT SUPERVISOR TURNOVER SHEET Attachment G co/~<~ AO-QA-303 Date Revision 9 aHiFT ~boo ta ~/6 SHIFT to Page 64 pf 74 Stan Enact Stan End UNIT UNIT CONDITION POWER LEVEL GENERATOR OUTPUT r'Ot~ MWe GENERATOR OUTPUT MWe REMARKS:

UNIT B /7 lo~ do 5 Lcm =~re KK i/ w >a7 sr v a> o~ Ai S7 7 Cd~cL (v< /a@f7 - 5 rv 7 v ( ~cnew'e An.

cI n let~ L Scil T~

7 I SP ~ SH ( - o rlh4~ /GAL willis 0/ oon T8 a Ac. e~f~ P~ x /p C M ON SiK e 0 ~e L HOCK DOE' 9 8 flbJs 8 RsT MK OO>

Form A~A@03.1d. Aev. d. OU. LEX. Panto t of 2 (Ftto Number Ad 5)

VI-17

Attachment G AO-gA-303 Revision 9 OFFGOING UNIT SUPERVISOR CHECKLIST:

'r 900- 0700-0700 1900

1. Evolutions in progress and items to be completed during next shift, as noted in remarks, have been discussed with oncoming Unit Supervisor.

2. Problems encountered during past shift and abnormal plant conditions, as noted in remarks, have been discussed with oncoming Unit Supervisor.

19004700 0700-1 900 Offgoing Unit Supervisor ONCOMING UNIT SUPERVISOR CHECKLIST:

0700. 1900.

1900 0700

1. LCO Log reviewed.

2. Non-Routine Training current.

0700-1 900 19004700 Oncoming Unit Supervisor POST RELIEF 0700 1900

1. Walk down Control Room panels with Unit Responsible PCO.

2. Unit Log reviewed.

3. Night orders book reviewed.

Form AW.A40$ 1d, Rer. d. OUPLSX. P109 2 ot 2 VI-18

PENNSYLVANIA POWER & LIGHT COMPANY

'USQUEHANNA SES Attachment A AD"QA-303 UNIT 1 Revision 9 SYSTEM AND EQUIPMENT Page 35 of 74 STATUS Date ioA/~~

Shift ~74 SHIFT INITIALCONDITIONS Power Level (MWth) ~>> 9 Shift Respfensible PCO Condition Additional PCO Mode Switch Position Completed by Reviewed by (umt Supdnnsoe Reviewed by (Shih Supdfvldoe 1C668 SYSTEM STATUS PROBLEMS 6f COMMENTS

~~ ~ ~ ~ ~~~ ~ ~~~~~~ ~ ~ ~~

EHC I/S avl unavl I auto h draulic fluid A h draulic fluid B filter turbine va r extr STEAM SEALING I/S avl unavl exhauster A 'ckin ackin exhauster B main steam su I aux steam su I COND DEMIN "" unavl r cond demin A cond demin B cond demin C cond demin 0 cond demin E cond demin F cond demin G MIN fl Ogw ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ auto man unavl GPM FV-10508 RFPT AUX~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ I/S avl unavl auto tumin ear A tumin ear B tumin ear C AmnLW A AmnLN B B mnLN C B mnLW 0 C mnL E Co,a/e P1 CmnL F A va r extr B va r extr C va r extr form AORA4034, Aev. 0, OUPLE4 Pood 1 ot 12 VI-19

Attachment A AO-QA"303 Revision 9 Paga 36 of 74 1C668 SYSTEM STATUS PROBLEMS 4 COMMENTS OPF GAS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ I I/$ ayl unayl main aux SJAE Mvp CIRC WATER """ " i I/S '.

avl unavl min full i pump A pump B pump C pump 0 SERVICE WATER I/S I avl lunavl auto A 'ump pump B pump C

~

RBCCW ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ I/S avl unavl pump A pump B B 0x 7~ Lc gs (~cc TBCCW ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ I/S i avl lunavl pump A pump B INST AIR '"" Auto Iunavl compressor A compressor B d erA d erg dryer C SERV AIR ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ Auto unavl compressor A compressor B Form Aooh4034, Aer. 9. DUPLEX. P~ 2 of 12 VI-20

Attachment A AD"QA-303 Revision 9 Page 37 of 74 UNIT 1 SYSTEM AND EQUIPMENT STATUS 1C651

'YSTEM STATUS PROBLEMS 8c COMMENTS

~ ~ ~ ~ ~ ~ ~ ~ ~~~~~~~~~

y!/CU I/S I avl Iunavl pump A pump B filter dern A filter dern B CONDENSATE """ " I/S I avl unavl pump A pump B pump C pump D RfPT ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ I/S ! avl unavl auto man turb/pump A turb/pump B turb/pump C low load b pass DC LppA OC Lpp B OCLppC

~ ~~ ~~ ~ ~ ~~~ ~~~

RX RECIRC I/S avl i unavl drive motor/pp A drive motor/pp B RECIRC AUXII.IARIES I/S avl unavl auto vent fan A vent fan B AC LN pp A-1 AC LN pp A-2 AC L pp B-1 AC LN pp B-2 DC LN ppA OC L&pp B RECIRC CONTROL'""" auto man controller A ee Speed controller B % Speed Form ADCIA40$4, Aer. 9, OU~~. P~ 3 ot 12 VX-21

Attachment A AO-gA-303 Revision 9 Page 38 of 74 1C651 SYSTEM STATUS PROBLEMS Ec COMMENTS BYPASS SWITCH POS " .'.normi inst I byp list bypassed instrument in inst column RBM A/B APRM A/C/E flow A/C IRM A/C/E/G APRM B/0/F flow B/0 IRM B/0/F/H SRM A/B/C/0 auto RMCS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ I/S B/P inop B/P RWM RBM RSCS list rods bypassed MAIN TURB EHC pressure set in control MAIN TURB' " I I/S avl unavl lift pumps auto turning gear OIL SYSTEMS""""" I/S avl unavl auto lock TGOP Mn L suet pp EBOP ESOP GEN EXCITATION auto man volta e regulator Form At. JM034. RW. Q. OVPi.EX. P~ 4 ot 12 VI-22

Attachment A AO-gA"303 Revision 9 UNIT 1 Page 39 of 74 SYSTEM AND EQUIPMENT STATUS 1C601 SYSTEM STATUS PROBLEMS Sc COMMENTS

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

CRO I/S avl iunavl pump A pump B ge b~'/d 'a/P flow contr A flow contr B SBLC ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

squib cont[nuI out squib A squib 8 D/W FLOOR SUMPS" " avl unavl sump A pump A sump A pump B sump 8 pump A sump B pump B

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

I/S avl unavl turb/pump status RCIC control GPM auto man 4+

controller CORE SPRAY OIV I "'/S avl unavl

'tape aetpttint vatue te GPM pump A pump C RHROIVI' ' I/S avl unavl pump A pump C RHR SW OIV I I/S avl unavl A 'ump APS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ avl unavl system SPOTMOS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ unavl system A system B MSIV STATUS off LIGHT'ight indication Tip e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ close open valve indication Form AOC)Pre@, Rev. 9. OUPLEX, Po9o 5 of 19 VI-23

Attachment A AD-QA-303 Revision 9 Page 40 of 74 1C601 SYSTEM STATUS PROBLEMS 5, COMMENTS CONTAINMENT H9/02 " ! Hz'4 I Oz%%d I

AR15746A los . ~ 0 AR15746B SUPP POOL FILTER PP " I ST8 I I/S I avl STd

~unavl punlp INST GAS """ """ I auto lunavl v

compressor A compressor 8 STORAGE BOTTLES "" close open Oe5 4ort. Pn 5 PCV-12643 PCV-12648 CORE SPRAY DIV II" I/S I avl i unavl pump B pump 0 RHR DIV II"""""" I/S i avl unavl pump B pump 0 oo S RHRSW DIV II" I/S avl unavl pump B HPCI ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ I/S avl unavl turb/pump status HPCI control ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ GPM auto man controller tape setpoint value 5 /< GPM OOS ECCS/BIS STATUS es no oos II hts tested all oos li hts off v- list oos s stems S Form AO~~. Aev. 9. OUPLEX. Psg. 4 ot 12 VI-24

Attachment A AO"qA-303 UNIT 1 Revision 9 SYSTEM AND EQUIPMENT Page 41 of 74 STATUS T-10 118 12B T-20 BUS 10 BUS 20 12 13.8KV El El El IZl E1 El '~

~m GEN 2 500 KV LEADS SUNBURY 2 WESCOSVILLE 500 KV 500 KV UNE LINE T-21 SOOKV Use an "X" in the applicable boxes to represent closed breaker positions.

Circle those boxes which represent unavailable breakers.

Form ADCIA4CH, Rm. 9 OUPLEX, Pro 1 of 12 VI-25

Attachment A AO-QA"303 Revis1on 9 Page 46 of 74 Miscellaneous MISCELI.

SYSTEM STATUS PROBLEMS 4 COMMENTS RECOMBINER """""'I/S , i avl unavl unit 1 unit 2 common unit select switch position-unit CCW pp 1P145 CCW pp 2P145 CCW pp OP145 UNIT 2 ECCS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ I/S avl I unavl U-2 RCIC ~wet g4rAa~~ v- C (J U-2 core spra pp A U-2 core spray pp C U-2 RHR pp A U-2 RHR p C U-2 RHR sw pp A U-2 core spra pp B U-2 core spra pp 0 U-2 RHR pp B U-2 RHR pp 0 U-2 RHR sw pp B U-2 HPCI CROSSTIE0 SYS """""" no common S.W. from U-2 CRD U-1/U-2 IA U-1/U-2 SA U-1/U-2 CST U-1/U-2 Fam AIR)ARCH, Rer. 9. OUPLEX. Pago 12 ot 12 VI-30

SECTION: OPERATIONS Inst. No. OI-AL-0017 Revision 1 UNIT 1 CONTROL ROOM Pre ared B :

SUBJECT, ANNUNCIATOR LQG Reviewed B Approved By Date + ~+ Pk Section Head Expiration Date Effective Date FORM AD-QA-101-5, Rev. 1, Page 1 of 1 VI-31

UNIT 1 CONTROL ROOM MON TUE Wf0 THU FR I SAT SUN ANNUNCIATOR LOG (0 //9 fo/<5- g%6, lo/I 7 s4/g$ lo/g9 so/go

~N ~N ~N ~i'I ~N ~N ~N "CAUSE/CORRECTIVE ACTION" AR 101 1C651 AR 102 1C651 FORM OI-AL-0017 Rev. 1, Page 1 of 17 VI-32

UNIT 1 CONTROL ROOM Week Ending I>/Eel 9(

ANNUNCIATOR LOG

~N ~N ~N ~N ~N ~N ~N "CAUSE/CORRECTIVE ACTION" AR 103 1C651 AR 104 1C651 FORM OI-AL-0017 Rev. 1, Page 2 of 17 VI-33

UNIT 1 CONTROL ROOM Meek Ending Io /24/9)

ANNUNCIATOR LOG

~N ~N ~N ~N ~N ~N "CAUSE/CORRECTIVE ACTION" AR 105 1C651 AR 106 1C651 t:-I4 H'VAC IC Z7i'.

T s STI%T VAC IC 27 ST Tow I 0 0 C7

- Ii' HC IC 7 IS I I%i IS I FORM OI-AL-0017 Rev. 1, Page 3 of 17

UNIT 1 CONTROL ROOM Week Ending le /z+/~9 ANNUNCIATOR LOG

~N ~N ~N ~B ~N ~N ~i'I "CAUSE/CORRECT I VE ACTION" AR 107 1C601 AR 108 1C601 FORM OI-AL-0017 Rev. 1, Page 4 of 17 VI-35

UNIT 1 CONTROL ROOM Week Ending io l~c I~9 ANNUNCIATOR LOG "CAUSE/CORRECTIVE ACTION"

~N ~N ~N ~N ~N ~N (

AR 109 1C601 AR 110 1C601 FORM OI-AL-0017 Rev. 1, Page 5 of 17 VI-36

UNIT 1 CONTROL ROOM Week Endiag /o /g.o/9( !

ANNUNCIATOR LOG

~N ~N ~N QN ~MI ~N ~N "CAUSE/CORRECTIVE ACTiON" AR 111 1C601 AR 112 1C601 B

FORM OI-AL-0017 Rev. 1, Page 6 of 17 VI-37

UNIT I CONTROL ROON Week EndIng zo /~c,/qg ANNUNCIATOR LOG

~N ~N ~N ~N ~N ~N N IICAUSE/CORRECTIVE ACTION" AR 113 1C601 8- dR /~$ ucu AR 114 1C601.

FORM OI-AL-0017 Rev. 1, Page 7 of 17 VI-38

UNIT,1 CONTROL ROOM Week Ending /o/~o/9( 4 ANNUNCIATOR LOG

~N ~N ~N ~~I< I ~i'1 1 I~N ~N "CAUSE/CORRECTIVE ACTION" AR 015 OC653 C- o D Da C-l3 P c.

0 l3 AR 016 OC653

-f csT'i0 cmp // PIURc oc.5 7C C- /S ~ Eo>tert A 0

E FORM OI-AL-0017 Rev. 1, Page 8 of 17

UNIT 1 CONTROL ROOM Week Ending go /3 o / g i ANNUNCIATOR LOG

~N ~N ~N ~N

'CAUSE/CORRECTIVE ACTION" AR 117 1C668 AR 118 1C668 F

FORM OI-AL-0017 Rev. 1, Page,9 of 17 VI-40

UNIT 1 CONTROL ROOM Week Ending lo/~e/~q ANNUNCIATOR LOG

~N '~N ~M ~N ~N ~N ~N "CAUSE/CORRECTIVE ACTION" AR 119 1C668 AR 120 1C668

-0 C ~riz

)o FORM OI-AL-0017 Rev. 1, Page 10 of 17

UNIT 1 CONTROL ROOM Week Ending lo/<o/~

ANNUNCIATOR LOG

~N ~N ~N ~N ~M ~N "CAUSE/CORRECTIVE ACTION" AR 121 1C668 AR 122 1C668

, FORM OI-AL-0017 Rev.. 1, Page ll of 17 VI-42

U NIT 1 CONTROL ROOM ANNUNCIATOR LOG Week Ending /o /kc/~

~N ~N ~N ~N ~N ~N ~N "CAUSE/CORRECTIVE ACTION" AR 123 1C668 AR 124 1C668 FORM OI-AL-0017 Rev. 1, Page 12 of 17 VI-43

UNIT 1 CONTROL ROOM Meek Ending lo /ko/~9 ANNUNCIATOR LOG

~N ~N ~N ~N ~N ~N

~

"CAUSE/CORRECTIVE ACTION" AR 029 OC681 A

AR 030 OC681 A

FORM OI-AL-0017 Rev. 1, Page 13 of 17 VI-44

UNIT 1 CONTROL ROOM Meek Ending /o /~o/~ !

0 ANNUNCIATOR LOG

~N ~N ~i% ~N ~N ~N "CAUSE/CORRECTIVE ACTION" AR 127 1C681 AR 128 1C681 FORM 01-AL-0017 Rev. 1, Page 14 of 17 vI-45

UNIT 1 CONTROL ROOM Meek Ending /o /go/~ !

ANNUNCIATOR LOG

~N ~N ~N ~i8 ~N ~N Q "CAUSE/CORRECTIVE ACTION" AR 125 1C692 AR 126 1C692 AR 148 1C644 0

AR 147 1C645 A

FORM OI-AL-0017 Rev. 1, Page 15 of 17 vj-46

UNIT 1 CONTROL ROOM Week 'Ending go /go/~I ANNUNCIATOR LOG

~N ~N ~N ~N ~N ~iV ~N "CAUSE/CORRECTIVE ACTION" AR 146 1C693 AR 045 OC693 AR 036 OC650 FORM OI-AL-0017 Rev. 1, Page 16 of 1'7 VI-47

UNIT 1 CONTROL ROOM ANNUNCIATOR LOG "CAUSE/CORRECTIVE ACTION" AR 131 OC673 AR 031 OC673 0

(OATE) ~l+ '0 9( ~II '$( Ql> I+9 Qlo syQ +l4 I+tf ~lo i ~~0 PCO Nightshift (time)

PCO Oayshift (time)

PCO Afternoonshift

( time)

US Afternoonshift (time)

FORM OI"AL-0017 Rev. 1, Page 17 of 17 VI-48

SECTION VII - RADIOLOGICAL CONDITIONS PART A - OFFSITE RELEASE DATA Section 1 - Weather and Met Data Log

SYSTEM WEATHER FORECAST FOR 10/08/91 UPDATE Issued: 0930 Hours Froa: PCC MONDAY: Sunny to partly sunny during the day. Clear tonight.'ncreasing TUESDAY: cloudiness with showers and possibly some thunderstorms developing during the afternoon and ending at night.

TEMPERATURES WINDS TUESDAY 0900 0400 1100 Min Time Max Time 'inds Allentown 60 -

75 58 0600 74 1500 NE 9 8 Harrisburg/

Lancaster 63 77 61 0600 78 1300 NE 8 4 Hazleton/

Scranton 58 72 56 0600 72 1500 SE 6 3

'Williamsport 59 74 57 0600 75 . 1400 NE 8 6 WEDNESDAY Mostly sunny during the day. Fair to partly cloudy at night.

Average Max. Temp. 74; Min. 58 THURSDAY: Partly sunny during the day. Becoming cloudy at night with a chance of some showers and thunderstorms.

Average Max. Temp. 80; Min. 65 FRIDAY: Variable cloudiness with a few scattered showers.

Average Max. Temp. 78; Min. 58 VII-2

91OCT08 ORILL METEOROLOGICAL CATA LOG STPEAM 13:31 07r'02i91 Is-minute Averages UPpor Onsito Vari Oownriver M oole Lovel Tower Towe Tower Sw teh

~

ls MIN AUG PER IOO PPT MIXING WINO WIND WIND W I iiO ENOING AT' STAB TYPE OPTH<fs) FROM MPH FROM MPH FROM MPH FROM MPH Sl Sw

$~$$$~5$$ ~$$$ S ~S~ S~$$$$~ ~ S ~ S Sss ~S~S $$$ S ~S sas sass ssa ss $$

18:08 C 14ee 11 7 358 5 12 4 37 5 3 18: 15 C 1480 158 4 157 5 153 5 150 4 3 3 18l30 F 1400 149 3 149 4 149 148 4 1 9l>>

18:45 F 1400 130 3 132 4 132 3 135 3 1 '9 +

19:00 G 1400 128 3 128 4 129 3 134 3 1 9>>

19: IS -- 1400 120 3 123 4 125 3 124 3 9>>

19:30 C

-- 1400 123 3 124 4 125 3 '.24 3 1

4>>

19:45 G

c -- 140e 80 s ee 83 5 85 5 1

ew 20:00 c 14ee 81 4+ 83 4 83 5 82 5 1

1 20: 15 c 14ee lse 4>> 152 4 152 5 153 5 1 "0:30 F -- 1400 150 4 152 3 152 4 152 4 9w 20 45 F -- 14ee 13e 4 130 3 130 4 130 4 1

4$

21:00 F -- 1400 129 4 127 3 130 4 129 4 1

4$

21:15 14eo le4 3 104 4 186 3 103 3 I 21:30 F -- 14ee I e4 3 184 4 186 3 103 3 I 21145 F -- 1400 80 3 81 4 80 3 81 3 I 22 ee G -- 1408 91 4 98 3 92 3 97 4 I VIT.-3

SECTION VII - RADIOLOGICAL CONDITIONS PART A - OFFSITE RELEASE DATA Section 2 - Plume Trajectory and Plume Deposition Data VII-4

SELECTEO r

r

" '~

FILE: ORILL$-91OCT08-22,00 I

/

~, WEST NANT I COKE PRESENTATION T ItlE: 13: 00 07812/91 STREAH PUFF PLOT Puff Locotions Sictnificonce tE NANT I CORP

)0" /

OATA FROH,'2,'88 IO/O3/)I I

I ONSITE Nl)IO.' mph NES GREC K 8 ~ SOURCE I tiS I GNIF I CANT

~ SIGN IF I CANT (fONYNGHA HAPLETON IBX Tech Spec for NG, 1-131 or PAPT EXIT - to exit STREAH, or any Function Key VII-5

SECTION VII - RADIOLOGICAL CONDITIONS PART A - OFFSITE RELEASE DATA Section 3 - Noble Gas and I-131 Release Rate Data VII-6

INDIVIDUALVENT RELEASE RATES QCI/min)

REV 7/19/91 TIME RB1 TB1 SGTS TB1 SGTS FROM TO NG NG NG l-131 I-131 15:00 18:00 1.70E+03 1.50E+03 2.30E+01 1.50E+00 3.10E42 18:00 18:15 5.10E+03 18:15 18:30 5.12E+03 18:30 18:45 5.21E+03 18:45 19:00 5.23E+03 19:00 19:15 5.26E+03 19:15 19:30 5.26E+03 19:30 19:45 5.26E+03 19:45 5.28E+03 20:15 5.30E+03 20:15 5.19E+03 20:45 5.26E+03 1.71E+03 8.12Et03 7.33E+04 7.08E42 20:45 21:00 5.32E+03 1.66E+03 2.37E+04 7.32E+04 2.16E41 21:00 21:15 5.33E+03 1.61E+03 4.08E+04 7.32E+04 3.87E41 21:15 21:30 0.00E+00 1.57E+03 5.75E+04 7.31E+04 5.65E41 21:30 21:45 0.00E+00 1.53E+03 7.33E+04 7.30E+04 7.44E41 21:45 0.00E+00 1.49E+03 8.80E+04 7.30E+04 9.22E41 SITE TOTALVENT RELEASE RATES (gCI/min)

REV 7/19/91 TIME FROM TO NOBLE GAS h131 PARTICULATES 15.'00 18:00 5.04E+03 4.43Et00 7.15E41 18:00 18:15 1.01E+04 18:15 18:30 1.02E+04 18:30 18:45 1.03E+04 18:45 19:00 1.03E+04 19:00 19:15 1.03E+04 19:15 19:30 1.03E+04 19:30 1.03E+04 19:45 1.03E+04 20:15 1.03E+04 20:15 1.02E+04 20:45 2.01E+04 7.33E+04 20:45 21:00 3.57E+04 7.32E+04 21:00 21:15 5.28Et04 ~ 7.32E+04 21:15 21:30 6.41E+04 7.31E+04 21:30 21:45 7.99E+04 7.30E+04 21:45 9.45E+04 7.30E+04 VII-7

SECTION VII - RADIOLOGICAL CONDITIONS PART A - OFFSITE RELEASE DATA Section 4 - EPB Dose Rate, 6 Hour Projections, and Onsite Field Honitoring Team Information VII-8

EPB DOSE RATE AND 6 HOUR PROJECTED DOSE REV 7/19/91 DOSE RATE (mrem/hr) PROJECTED DOSE (mrem/hr)

TIME AFFECTED WHOLE BODY THYROID WHOLE BODY THYROID SECTOR 20:45 1.25E+00 1.66E+03 5.15E+00 9.91E+03 21:00 1.20E+00 1.65E+03 5.36E+00 1.03E+04 21:15 8.87E41 1.23E+03 3.77E+00 7.38E+03 21:30 WNW 8.51E41 1.23E+03 3.90E+00 21:45 W 4.91E41 7.38E+02 2.17E+00 4.42E+03 W 1.18E+00 1.85E+03 5.43E >00 1.13E+04 VII-9

9 I OCT08 NOBLE CAS RELEASE RATE TRENDING PLOT STREAN 13: 21 07/I 2' Csiiorocurios por tninuto)

I . BE+12 I . OEi12 I.BE+II I.BE+11 I . BE+10 I .BE+10 I,BE+89 IiOE+89 I OE+08

~ I.BE+08 I . BE+87 I OE+07

~

I.BE+Be I.BE+06 I.BE+05 I.BE+05 I.BE+04 I OE+04

~

I.BE+03 I.BE+03 I.BE~02 1. BE+02 1930 1945 2080 2015 2030 2045 2100 115 2130 2145 2280

XIT - to exit STREAN, or any Function Key VII-10

910CTOS IOOINE-131 RELEASE RATE TRENDING PLOT STREAII 13: 23 078!2i91 (microcurias par ainuta)

I.BE+87 I.BE+07 I.BE+06 I.BE+06 I.BE+85 !.BE+05 I.BE+04 I.BE+04 I BE+03

~ I.BE~03 I I I.BE~02 I 0E+ 02

~

I . BE+01 I BE+8 1

~

I.BE+08 !.BE+00 I BE-Ol

~ I OE"01

~

I.OE-B2 I OE-02

~

I . OE-03 I.OE-03 1930 1945 2800 2015 2830 2845 2180 2115 2138 2145 2200 c.NIT - to exit STREAN, or any Function Key

STREAN PROJECTED THYR010 DOSE PRESEHTATlOH TINE! 13:06 87/12/91 AT THE EPB (eiIIir em) 10000 9eee 90oe sooe 8008 "eee 7000 6008 60ee 5000 seee 4eeo 4ooe 3000 3008 2eoo 2oee 1000 10oe Data Period Qf Ca I au I a t i oni.o 22ee proJ 'd Release 1938 1945 28ee 2e1S 2e38 2e4S 21ee 211S 2130 214S Duration (hr): 6 6 6 6 6 6 6 6 6 EXIT - to exit STREAII, or any Function Key VII-12

31

-OTEO f: R. PR tiTRT ON TlltE: 13.'04 0",i'12891 30 STREAH EXPAllDED PROJECTED 28 THYROID DOSE PLOT ExPected Dose Totals if the Release Lasts 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 1 Entire Ptuae Trover ses the 10 ai. EFZ w5 Q4 DATA TO,'I6',42 UP i%3/89/91 22 21 QUADRANT'tlIl 20 19 K 9 (ttR tt) 8 33, -.-:Eh ~ 5000 or 4bove 2500 - 4999

~

E82 REe ~

Q 250 - 2499

' 1'5 GREEtl ~ 1 - 249 1 2 3 4 5 6 8 9 10 11 12 13 14 16 E"XIT - to exit STREAH, or any Function Key VII-13

T F R s 9 T PRESENTATION TIME l 13: 02 07812i91 r'/

16 I 15 I $ $ $

z )

STREA1'1 EXPANOEO PROJECTEO 13 THYROID DOSE PLOT

]2 Ex$ $ eated Dose Tot.el s i f the Release i asts 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months T$ Eat ir e Plume Traverses the 10 ml. EPZ y.r OATA TO,'6,'42 UP IO/O3/!I QUAORANT,'ll SE K Y <MR Mi g m000 or Above REG ~ 2500 - 4999 0 250 2499 CREEN ~ 1-1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 FXIT - to exit STREAH, or any Function Key VII-14

SELECTEO FILE: OPILLs-SIOCTB8-22.BB PRESENTATION TIME: 13'12 Bi. 12i&I

',, WEST N44T I COKE STREAN OEPOSITIOH PLOT ExPoctod 4roas and Ralati;o 4aiounts of IO, / 4CtiVi ty Oorcsi ted on j " SHI CKSH the Gr ound

/ ?2,'O8 OATA

/ <<I VP TO', 18/68/91 NESS

/ECK

%r X

'/

I MINIMUM V4LVE OF INTEREST IS: 1E-1B CI/M++2

'r I L'. / r'4)LETON

/ P T N K Y PEC ~ ~ HIGH P MEO I VM GPEEli ~ ~ LOW EXIT - to exit, STREAN, or any Function Key VII-15

SECTION VII - RADIOLOGICAL CONDITIONS PART A - OFFSITE RELEASE DATA Section 5 - Field Honitoring Team Data VII-16

OFFSITE MONITORING TEAM PLUME TRAJECTORY ssrfssla fssrrsf ssf ssrll,

'rfSOOOOSOOsfl C Orlfass

~ OOOCOfSS 4 s ~

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~ ssfoor Css%4vC lrsssssl Oss C Cssf \ 4

~

Os sss tOO ss ssOT ~ oOO.

~ esl I Li L

~ l Of ssO

~'l RELEASE: 20:45 to 21:00 CCsieTaaf C

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OCCOClf Oss llCl I

~ OOffCIIO OaossaOra

~ COO i

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Oss S,s CO OsOCCI.

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~ sosscrs oa rr 5OI IOQI STiTihN RELEASE: 21:16 to 21:30 I

'1

~ oTs sssf 4 ~ 4

/('

VII-17

SECT Ml SECT MI SECT TIME PERIOD ENDING OSC hR: 0.35 2 MI: I0 MI:

20:45 EPB. 0.54 5 MI:

hRR IVhL DIST VB-NG 3 FT (CY) 3 FT (OY) 3 IN (CY) 3 IN (OY) CPM/ THY I-1 Z1 C hRT.

TIME SECTOR (MILES) (MR/HR) (MR/HR) (MR/HR) (MR/HR) (MR/HR) 100 CM 2 MR/HR) ( CI/cc) (NCPM) 20 32 NV 0.10 1.5 1.6 1.8 223.3 264.1 1.18E+04 2028 5.92E-07 1676 20 34 I'IV 020 1.5 1.5 1.7 213.9 253.1 1.14E+05 1945 5 68E-07 1608 20 36 NV 0.30 1.4 1.4 1.7 204 6 242 P 1.09E+05 1862 5 44E-07 1539 20 38 NV OAO 'I .3 lA 1.6 195.2 73P 9 1.04E+05 1779 5 20E-07 1471 20;40 NV 0.50 13 1.3 1.5 185.9 219.9 9.91E+04 1696 4 95E-07 1402 20 42 NV 060 'I .2 1.2 1.4 176.,5 208.8 9.42E+04 1614 4 71E-07 1334 20 44 NV 070 1.1 1.2 1.4 167.2 197.S 8.94E+04 1531 4 47E-07 1265 20 A6 NV 080 1.1 1.1 1.3 157.8 I 86.7 8.46E+04 1448 4 23E-07 1197 20 AS NV 0.90 1.0 1.0 1.2 148.5 175.7 7.97E+04 1365 3.99E-07 1128 20:50 le 1.0 1.0 139.1 164.6 7A9E+04 1282 3.74E-07 1060 20.55 NV 1 25 0.8 0.8 0.9 115.8 137.0 6.28E+04 1075 3,14E-07 888 21,00 I'IV 1 50 06 0.6 0.8 92.4 109.3 5.07E+04 867 2 5~E-07 717 21 '05 NV 1 75 0.5 0.5 0.6 69.1 81 7 3.86E+04 660 93E 07 546 21 ."10 NV 0.3 0.4 45.7 2.65E+04 1 32E-07 21:15 NV 2.25 Q 0.3 0.3 42.3 50,0 2.43E+04 416 1 21E-07 21 .20 NV 250 03 0.3 0.3 38.9 460 .21E+04 <<<<8 1. I OE-07 21 25 NV 2.75 P2 02 0.3 35.5 42.0 1.99E+04 341 9 96E-08 21;30 NV 3.00 P2 0.2 0.3 32.0 379 1.77E+04 304 8 87E-08 251 21:35 NV 3.25 Q2 0.2 P 2 28.6 339 1.56E+04 266 7 78E-OS 22P 21:40 NV 3.50 P2 p 7 Q 29.8 1.34E+ii4 '729 6 68E-08 1S9 21:45 NV =.75 0.2 Q 7 0.2 21.8 258 1.12E+04 5 59E-08 158 2I .50 NV 4.00 0.1 O. I 0.1 18.4 21 8 9.00E+0 I54 4.50E-08 127 22.10 00 0.0 48 5.6 2. i SE+02 1 39E-09 22 30 6.00 0,0 0.0 0.0 3.8 4.5 ~

.22E+02 I 11E-09 22:50

~

r 7.00 0.0 0.0 Q.P 3A 1.67E+02 8 34E-10 23.10 'L(r 8.00 0.0 00 il.l I 1.9 a 1.11E+I.' 5 56E-10

.'3.30 V 9.00 00 OQ 0.0 10 1 5.56E+il1 2 78E- I 0

10 IM:: 00 00 0,0 00 1. I3E-Q.=. 0 r 15E-15

MI SECT Ml SECT Ml SECT TIME PERIOD ENDING OSChR: 0,35 NV 2 Ml: NV I0 MI:

21:00 EPB: 0.54 NV 5 Ml: V hRR IV AL DIST VB-NG 3 FT (CV) 3 FT (OY) 3 IN (CV) 3 IN (OV) CPM/ 1'HY 1-1 31 CART.

TIME SECTOR (MILES) (MR/HR) (MR/HR) (I IR/HR) (MR/HR) (MR/HR) 100 CM 2 MR/HR) ( Ci/cc) (NCI M) 20.47 NV 0.10 15 1.5 1.7 214.3 253.5 I . I 8E+04 016 5.89E-07 I 666 20.49 NV 0.20 1.4 IA 1.7 2n5.4 2429 1.13E+v5 1933 5.65E"07 l598 20:51 NV 0.30 IA IA 1.6 196A 202.4 1.08E+05 1851 5.41E-Q7 1530 20.53 NV 0.40 1.3 1.3 1.5 187.4 221.8 1.03E+05 1769 5,16E"07 1462 20 55 NV 0.50 1.2 1.2 1.5 178.5 21 1.2 9.85E+04 1686 ' 92E-07 1394 2D:57 NV 0.60 1.2 1.2 1.4 169.5 200.6 9.37E+04 1604 4 68E-07 1326 20.59 I'IV 0.70 1.1 1.3 160.6 190.0 8.89E+04 1522 4 44E"07 1258 21.01 I'IV 0.80 1.0 I.l 1.2 151.6 179.4 8.41E+04 1439 4 .OE-07 1189 21 .03 I'IV 090 10 1.0 1.2 142.7 168.8 7.92E+04 1~57 3 '96E-07 1121 2 I:05 NV:::::f MS 0.9 0.9 133.7 158.2 7.44E+04 1274 3 72E-07 1053 2 I;,10 I'IV 1.25 0.8 0.8 P 9 111.3 131.7 6.24E+04 1069 3 12E-07 883 21:15 I'lV 1.50 0.6 0.6 0.7 88.9 I 05.2 5.04E+04 863 2 52E-O7 713 21:20 NV 1.75 0.5 0.5 0.5 66.5 787 3.84E+04 657 I 92E-07 543 21 .25 NV::.::2Ã$ :::: 03 0.3 522 2.63E+04 451 I 32E-07

~

3 21:30 NV 2.25 03 0.3 0.3 40.8 48.3 2A2E+04 1 21E-07 342 21:35 NV 2.50 03 0.3 0.3 37.6 44A 2. 'GE+04 I 10E-07 311.

21:4D I'IV 2.75 P2 0.2 0.3 34.3 40.6 198f <<04 339 9.9 I E-08 280 21:45 I'lV 3.00 0.2 0.2 Qr3 31.0 36.7 1.76E <<04 02 8 82E-08 250 21.50 NV 3.25 Q 2 0.2 Q 27.8 328 1.5 E+04 265 7.74E-08 219 21:55 I'IV 3.50 P 2 0.2 0r 24.5 'N p 1.33E+04 6.65E-08 188 22;00 I'lV 0.1 0.1 0."2 25.1 1.1 I E+04 l90 5 56E-08 157 22:05 NV 4 00 0.1 D.l O.I 17.9 21 2 8.95E+03 I53 4 47E-08 127 22 25 V 0.0 0.0 0.0 49 2,53E+0 I 26E-09 22:45 V 6.00 0.0 0.0 G.Q 3.9 4.6 2.02E <<02 I DIE-09 23.05 7,.00 0.0 D.D 0.0 29 3A I .52E+02 7 59E-10 r,5 8.00 0.0 D.Q G.l I 1.9 I .01 E+0"=: 5 06E- I 0 23 45 9.00 00 DD Q.n 1.0 .06E+01 ~ 53E-10 0:05 0.,0 Q.n G.U 0.0 6. I;::E-04 n 3 24E-15 0

Ml SECT Ml SECT SECT TIME PERIOD ENDING OSChR: 0.41 VNV 2 Ml: YNV 10 Ml:

22:25 EPB: 0.69 VNY 5 MI V hRR IV hL DIST VB-NG 3 FT (CV) 3 FT (OV) 3 IN (CV) 3 IN (OV) CPM/ TIIY 1-132 C hRT.

TIME SECTOR (MILES) (MR/HR) (MR/HR) (MR/HR) (MR/HR) (MR/HR) IOO CM 2 MR/HR) ( Ci/cc) (NCPM) 21 .01 VNV 0.10 1.2 172.2 203.8 9.54E+03 1633 4.77E-07 1349 21:03 VNV 0.20 1.1 1.1 1.3 164.9 195.1 9.14E+04 I 565 4 57E-07 I'293 21:04 VNV 0.30 1.1 1.1 1.3 157.6 186.5 8.74E+04 1496 4 37E-07 l237 21;06 VNV 0,40 I 0 1.0 1.2 150.3 177.8 834E+04 1428 4,17E-07 1180 21 .07 VNV 050 1.0 1.0 1.2 143.0 169.2 7.94E+04 1360 3 97E-07 11 4 21 .09 VNV 0.60 0,9 0.9 1.1 135.7 160.5 7.55E+04 1292 3.77E-07 1068 21:10 0.70 09 09 1.0 128.4 151.9 7.15E+04 1224 3 57E-07 1011 21 12

'v<N'r<'f'I'rr'flV 0,80 08 0.8 1.0 121.1 143.2 6.75E+04 1156 3.38E-07 955 21 '13 090 0.8 0.8 0.9 113.8 134.6 635E+04 10SS 3.18E-07 899 21:15 Vf4V ' '1'NG" 0.7 0.7 0.9 106A 125.9 595E+04 1019 2.98E-07 21:18 VflV 1.25 0.6 0.6 0.7 88.2 104.3 4.96E+04 849 2 48E-07 702 a w9 21 '22 Vfl'r<'NV 1 50 0,5 0.5 0.6 69.9 82.7 3.96E+04 1.98E-O r 561 21:26 1 75 0.4 OA OA 51.6 61.1 .97E+04 508 1 ASE-07 420 21 .30 VN'r<' '2>D" 0.2 0.2 39A 1.97E+04 338 9.87E-GS 2'79 21:33 VNV 0.2 0.2 0.3 it.4 37 1 1,82E+04 311 9 GSE-08 257 21 37 VNV 2.50 0.2 0.2 P2 29.5 34 8 1.66E+04 284 8 29E-OS 234 21-.41 'vjl'Pr( 2.75 02 0.2 p 27.5 32.6 1.50E+04 ')g <

7 49E-08 212 21;45 VNV 3.00 0.2 0.2 Q 2 25.6 303 1 34E+04 229 6 70E-08 190 21 .48 'v<NV 3.25 0.2 0.2 0.2 28 0 1.18E+04 202 5 9 I E-08 167 21:52 Vf4'v<'.25 v<'NV 3.50 0.1 0.2 p 21.7 257 1.02E+04 175 5 12E-08 145 21:56 VNV 3.75 0.1 O,l Q 19.8 Q3 8.64E+03 l48 4 32E-08 22.00 4.00 0.1 0.1 0.1 1 7.8 21 1 7.i<6E+03 121 3 53E-08 100 22'.15 V:::::5:.66 0.1 0.1 0.1 10.1 119 7.18E+i<2 12 3 59E-09 10 22:30 6.00 0.1 Q. 1 0 I 8.3 9.8 5.82E+02 10 2 9I E-09 22:45 sC II 7.00 0.0 <ip O. I 6.6 7.8 ~

1 A6E+02 8 2 23E-09 23:GQ v<r 8.00 0.0 0.0 P.p 4.8 5.7 3.1 QE+0 5 1 55E-<i9

>3'15 9.00 0.0 0.0 0.0 30 1.73E+P. 8 67rE- I 0 23 "<J :2 0:IM::: 00 Q.Q P.Q 13 1 5 ".71E+0 1 1 8-E- I0

SECT Ml SECT Ml SECT TINE PERIOD ENDING OSCAR: 0.41 YNV 2 Ml: 10 MI:

21 30 EPB: 0.69 YNV 5 Ml:

ARRIVAL DIST VB-NG 3 FT (CV) 3 FT (OV) 3 IN (CV) 3 IN (OY) CPM/ THY I-1 31 C-ART.

TIME SECTOR (MILES) (MR/HR) (MR/HR) (MR/HR) (MR/HR) (MR/HR) I OO CM 2 MR/HR) ( Ci/cc) (NCPM) 21 '16 VNV 0.10 1.1 1.1 13 165.2 195.5 9.54E+03 1634 4 77E-07 1350 21 "IS VNV 0.20 1.1 1.1 1.3 158.2 187.2 9.14E+04 1565 4.57E-07 1294 21;19 VNV 030 1.0 1.1 1.2 151.2 178.9 8.74E+04 1497 4.37E-G7 I 237 21.21 VNV 0.40 1.0 1.0 1.2 144.2 170.6 8.34E+04 1429 "4 17E-07 1181 21 22 VNV 0.50 0.9 1.0 I.I 137.2 162.3 7.95E+04 1360 397E-07 I124 21 '24 VNY 0.60 0.9 0.9 1.1 130.2 154.1 7r.55f+04 1292 3 77E-07 1068 M 21:25 'v/NV 0.70 0.8 0.9 1.0 123.2 145.8 7.15E+04 1224 3 57E-07 1011 M 21 27 VNV 0.80 0.8 0.8 0.9 116.2 137.5 6.75E+04 1156 3 37E-07 955 VNV'.7 I

hD 21:28 VNV 0.90 0.8 0.8 0.9 109.2 129.2 6.35E+04 1087 3 I SE-07 899 21:30 0.7 0.8 102.2 120.9 5.9SE+04 1019 2.9SE-07 21:33 VNV 1 25 0.6 0.6 0.7 84.7 100.2 4.9SE+04 848 2 48E-07 701 21:37 VNV 1 50 0.5 0.5 0.5 67.2 795 3.96E+04 677 I 98E-07 560 21:4 I VNV 1.75 03 0.3 49.7 58,8 296E+04 507 1.48E-07 419 21 45 Q2 P 2 3> 2 38.1 1.96E+04 9 81 E-08 278 21 48 'vFNV 225 02 0.2 Q ~p 35.9 1.8GE+04 309 9 02E-08 21 52 'vFNV 2.50 02 p 0.2 28.5 337 1.65E+04 282 S 24f-08 23~

21.56 'vF IIV 2.75 0.2 Q 2 Q2 26.6 31 5 1.49E+04 255 7 45E-OS 211 22.00 VNV 3.00 0.2 0.2 0.2 29 2 I 33E+04 228 6 66E-GS I S8 22 03 VFNV 3.25 P2 0.2 0.2 22 9 27.0 1.17E+04 201 5 87E-08 166 22.07 VNV 3.50 0.1 G. I 0.2 2'I .0 248 1.02E+04 174 OSE-08 144 22.11 VffvF 3.75 01 O. I P 2 19.1 22.6 8.59E+03 147 4 3GE-08 122 22'15 VNV 4.00 0.1 O. I 0.1 17.3 204 7.02E+0 120 3 SIE-OS 99 22 30 'rF 0.1 0.1 0.1 116 ; 13E+02 12 3 56f-09 10 22;45 'vF 6.00 0.1 0 I 0.1 8.1 9.6 5.7 r E+02 10 2 89E-09 23:00 vl 7 00 00 0.0 0.1 64 7.5 4.42E+02 8 2 21 f-09 23:15 'vF 8.00 00 0.0 0.0 4.6 5.5 3,Ij7f+0. 5 I 53E-09 23 '30 'vF 9.00 00 O.G O.G 29 .5 I,;2E+II ~ 8.58E- I 0 23 '45 'vF :.:I 0:.'00: 0.0 00 0.0 12 3.63f+Il I I 8 I E- I I3

OFFSITE MONITORING TEAM PLUME TRAJECTORY aaasata ass Ipasa ss ~ sssal I'sasatsl

~ atyattw i"wa C

I as ~ aa ~ ~ \v54vawsssssa Sa 544 was Oss

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~ aatstk wwwwt I i4w .asO. astatl atsst4afa4 wats t ~ Wsl Osssa

~ acsa 'rT r' RELEASE: 22:00 I I

~ Icatat'asa aaaa saaatsaasn 4aatt ~ 'vt'\ sarsaa at

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~ sass csss

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~ a@a salsa RELEASE: 21:45 VTI-22

SECT SECT Ml SECT TIME PERIOD ENDING OSCAR. 0.37 Y 2 Ml: 10 MI. VSY 21:45 EPB: 0.61 V 5 Ml:

ARRIVAL DIST VB-NG 3 FT (CY) 3 FT (OV) 3 IN (CV) 3 IN (OV) CPM/ THY I-131 CART TIME SECTOR (MILES) (MR/HR) (MR/HR) (MR/HR) (MR/HR) (MR/HR) 100 CM 2 MR/HR) ( Ci/cc) (NCPM) 21 31 V 0.10 0.6 0.7 86.2 102.0 5.17E+03 S85 2.58E-07 731 21 .33 V 0.20 0,6 0.6 0.7 83.3 985 S.0QE+04 856 2 50E-07 708 21 34 V 0,30 0.6 0.6 0.7 SOA 95 I 4.83E+04 827 2 42E-07 684 21 '36 V 040 0.5 0.5 0.6 77.5 91 7 4.66E+04 798 2 33E-07 660 21 '37 V 0.50 0.5 0.5 0.6 74.6 883 4.49E+04 769 2 25E-07 636 21:39 V 060 0.5 0.5 0.6 84 S 4.32E+04 740 2 16E-07 612 21 Ap 0.70 0.5 0.5 0.6 68.8 81 4 4.15E+04 711 2 OSE-07 588 21 A2 V 0.80 0.5 0.5 0.5 65.9 780 3.99E+04 682 I 99E"07 564 21 .43 V 090 OA OA 0.5 63.0 74 6 3.82E+04 653 I 91E-07 540 21 A5 OA OA 0.5 60.1 71.1 3.65E+04 625 1.82E-O7 516 21 A8 V 1 25 0.4 OA 0.4 52.9 62 6 3.22E+04 552 I 61E-07 456 21:52 V 1.50 0.3 0.3 0.4 45.7 540 2.SOE+04 480 I 40E-07 397 21 .56 1.75 03 0.3 0.3 38A 45A 2.3SE+04 407 1.19E-07 337 22:00 p 02 0.3 1.96E+04 9.7SE-OS 277 22:03 V 225 0.2 0.2 P2 28.6 338 1.79E+04 307 8 97E-08 254 22 07 V 250 0.2 02 P 2 26.0 30.8 1.63E+04 279 8 15E-08 231 22 11 'lyl 2.75 0.2 0.2 P 2 23 4 1.47f+04 251 7 34E-OS 208 22:15 V 3.00 0,1 0.1 p 20 9 24 7 I 31 E+04 223 6 53E"08 185 22 18 V 325 0,1 0.1 0.1 18.3 21.6 1.1-1E+04 196 5 71E-08 162 g

~

2 22 V 350 0.1 O. I 0.1 18.6 9 SOE+CI3 168 4 90E-08 139 22 'Eg C 375 0.1 0.1 Q.l 13,2 156 S.l E+Q.=. 140 4 OSE-08 116 22 '30 V 4 00 0.1 0.1 0.1 10.6 125 6.54E+03 112 3 27E-08 93 22 45 v(SV 0.0 0.0 0.0 0.3 0.3 2.3SE+01 I 19E" 10 0 23.00 Y(S'('SV 6.00 00 0.0 0.0 0.2 0.3 I upE+0 I 0 9 51E-11 0 23.15 7.00 0.0 0.0 0.0 0.2 0.2 1.43E~QI 0 7 13E-I I 0 23 30 'y(QV 8.00 00 0.0 0.0 0.1 0.1 "..51E+QP 0 4 75E" 11 0 23:45 VSV 9.00 0.0 0.0 0.0 01 O.l 4.76E+QP 0 2 38E-11 0 Q:00 ::1O:.'OO . 0.0 rj.p 0.0 00 1. QE-03 93E" 15 0

Ml SECT Ml SECT Ml SECT TIME PERIOD ENDING OSCAR: 0.37 Y 2 MI: V 10 Ml:

22:00 EPB: 0.61 Y 5 Ml VSV ARRIVAL DIST VB-NG 3 FT (CY) 3 FT (OY) 3 IN (CV) 3 IN (OV) CPM/ THY 1-131 - CART.

TIME SECTOR (MILES) (MR/HR) (MR/HR) (MR/HR) (MR/HR) (MR/HR) 100 CM 2 MR/HR) ( Ci/cc) (NCPM) 21:46 V 0.10 1.4 1.4 1.6 202.4 239 4 l.26E+04 2161 6 31E-07 1786 21 .'48 V 0.20 13 1.4 1.6 196A 'l.23E+05 2100 6 13E-07 l735 21 49 V 0.30 1.3 1.3 1.5 190A 225 2 1.19E+05 2039 5 95E-07 1685 21:51 V 0.40 1.3 1.3 1.5 184 A 218.1 1.15E+05 1977 5 77E-07 1634 21 52 V 050 1.2 1.2 1.4 178A 211.0 1.12E+05 1916 5 60E-07 1584 21 54 'r( 060 1.2 1.2 1A 172A 203.9 1.08E+05 1855 5 42E-07 I 533 21 '55 V 0.70 1.1 1.2 IA 166A 196.8 1.05E+05 1794 5 24E-07 l482 21 '57 V 0.80 1.1 1.1 13 160A 189.7 1.01E+05 5 06E-07 1432 21 58 Qr 0.90 1.1 1.1 1.3 154A 182.6 9.76E+04 1671 4 88E-07 1381 22:00 :1:M$ 6:::: 1.0 1.0 1.2 148.3 175.5 9.40E+04 1610 4 70E-07 1331 22:03 V 1 25 0.9 09 1.1 133.3 I 57.7 8.51E+04 1457 4 26E" 07 1204 22 07 V 1.50 0.8 0.8 1.0 118.3 140.0 7.62E+04 1304 3 81E-07 1078 22:11 1.75 0.7 0.7 0.8 l 03.3 122.2 6.72E+04 1151 3.36E-Q 7 951 22:15 0.6 0.6 0.7 883 104.5 5.83E+04 2 91E-07 825 22 '18 V 06 0.6 0.7 81.0 95.9 534E+04 2 67E-07 756 22 22 V 250 0.5 0.5 0.6 73.8 873 4.86E+04 8~~ 2 43E-07 687 22 26 V 2.75 0.5 0.5 0.5 66.5 786 4.3 r E+04 749 2 19E-07 619 22:30 V 3.00 OA 0.4 0.5 59.2 700 3.89E+04 665 1 94E-07 550 22 V 3.25 OA OA 0.4 51.9 61 4 3.40E+04 58~ 1 7QE-07 481 22.37 Ie( 3:50 03 0.3 OA 44.6 528 =.92E+04 499 I 46E-07 412 22 '41 II 3.75 0.3 0.3 0.3 37.4 2 2.43E+04 416 1 21E-07 344 22 A5 V 4.00 0.2 0.2 0.2 30.1 356 1 94E+04 9 72E-08 275 23.00 VS'( 0.0 0.0 0.0 0.9 9.23E+00 0 4 61E-11 0 23:15 VSV 6.00 0.0 0.0 0.0 08 09 7.38E+00 Q 3 69E-11 0 pp e tQ VSV 7.00 Q.O 0,0 0.0 06 0.7 5.54E+u0 0 2,77E" I 1 0 23 45 VS'rF 8.00 0.0 O.Q 0.4 0.5 : 69El00 0 1 85E-11 0 0:00 'a)rSV 9.00 0.0 Q,Q 0.0 Q Q2 1 85E+00 0 92 0 0." l 5 rF :.10':OO::: 00 Q.l) 0.0 0.0 6.83E -u4 0 ~

P I

~

0

SECTION VII - RADIOLOGICAL CONDITIONS PART B - REACTOR WATER ISOTOPIC VII-25

REACTOR WATER DATA: UCI/CC ISOTOPE 2045 2100 2115 2130 2145 2200 IODINE-131 '2.4 E4 2.4 E4 2.4 E4 2.4 E4 2.4 E4 2.4 E4 IODINE-132 4,8 E4 4.5 E4 4.2 E4 3,9 E4 3.6 E4 3.3 E4 IODINE-133 5.5 E4 5' E4 5.4 E4 5,4 E4 5.3 E4 5.3 E4 IODINE-134 8.7 E4 7.2 E4 5.9 E4 4.8 E4 4 E4 3.3 E4 IODINE-135 4.8 E4 4.7 E4 4.6 E4 4.5 E4 4.4 E4 4.2 E4 CESIN-137 2.3 E3 2,3 E3 2' E3 2.3 E3 2' E3 2' E3 KRYPTN-85N 1.2 EO I;2 EO 1,1 EO I I

~ EO 1 ~ I EO I EO KRYPTN-85 3.9 E-2 3,9 E-2 3.9 E-2 3' E-2 3.9 E-2 3.9 E-2 KRYPTN-87 1.6 EO 1,4 EO I 2

~ EO I EO 9' E-I 7.9 E-I KRYPTN-88 2 8 EO 2.6 EO 2.5 EO 2' EO 2.2 EO 2.1 EO XENN-133 6.2 EO 6' EO 6,2 EO 6.2 EO 6.2 EO 6.2 EO XENN-135 5 5 EO 5.4 EO 5.3 EO 5.2 EO 5~I EO 5 EO VII-26

SECTION VII - RADIOLOGICAL CONDITIONS PART C - SUPPRESSION POOL ISOTOPIC VII-27

SUPPRESSION POOL DATA: UCI/CC ISOTOPE 2045 2100 2115 2130 2145 ?200 IODINE-131 2.4 E2 2' E2 2.4 E2 2,4 E2 ?,4 f? 2,4 E2 IODINE-132 4.7 E2 4.4 E? 4.1 E2 3.8 E2 3,5 E2 3.2 E2 IODINE-133 5' E2 5' E2 5.3 E2 5.3 E2 5' E2 5.2 E2 IODINE-134 8' E2 7 E2 5.8 E2 4.7 E2 3' E2 3.2 E2 IODINE-135 4.7 E2 4,6 E2 4' E2 4' E2 4.3 E2 4.1 E2 CESIN-137 2.3 E1 2' EI 2' E1 2.3 EI 2.3 E1 2' EI KRYPTN-85H 5 E-2 4.8 E-2 4' E-2 4' E-2 4' E-2 4.1 E-2 KRYPTN-85 1.6 E-3 1.6 E-3 1.6 E-3 1.6 E-3 1.6 E-3 1.6 E-3 KRYPTN-87 6.3 E-2 5.5 E-2 4.8 E-2 4.2 E-2 3.7 E-2 3' E-2 KRYPTN-88 1.1 E-I 1.1 E-1 10 E-2 9.4 E-2 8,8 E-2 8.3 E-2 XENN-133 2,5 E-I 2' E-I 2.5 E-1 2,5 E-1 2.5 E-I 2.5 E-1 XENN-135 2.2 E-1 2.2 E-I 21 E-I 21 E-I 2.1 E-I 2 E-1 VII-28

SECTION VII - RADIOLOGICAL CONDITIONS PART D - DRYMELL AIR ISOTOPIC VII-29

DRYNELL AIR SPACE GAS SANPLE DATA: UCI/CC ISOTOPE 2045 2100 2115 2130 2145 2200 IODINE-131 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO IODINE"132 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO IODINE-133 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO IODINE"134 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO IODINE-135 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO KRYPTN-85N 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO KRYPTN-85 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO KRYPTN-Oot 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO KRYPT%-88 0 EO 0 EO 0 EO 0 EO 0 EO 0EO XENN-133 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO XENCN-135 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO VTI-30

SECTION VII - RADIOLOGICAL CONDITIONS PART E - WETWELL AIR ISOTOPIC VII-31

MElMELL AIR SPACE GAS SAMPLE DATA: UCI/CC ISOTOPE 2045 2100 2115 2130 2145 2200 IODINE-I31, 5 ~ I El 5.1 El 5' EI 5.1 El 5' El 5.1 El IODINE-132 I E2 9,4 El 8.7 El 8' EI 7.5 El 6 9

~ El IODINE-I33 1.2 E2 1.2 E2 1.1 E2 1,1 E2 1.1 E2 !.1 E2 IODINE-I34 1.8 E2 1,5 E2 I 2 E2

~ I E2 8.3 El 6.8 El IODINE-I35 I E2 9' fl 9.6 El 9.4 El 9,1 El 8.9 EI KRYPTN-85H 8.5 E2 8.2 E2 7.9 E2 7.6 E2 7.3 E2 7 E2 KRYPTN-85 2.7 El 2.7 El 2.7 El 2.7 El 2.7 El 2.7 El KRYPTN-87 1.1 E3 9.5 E2 8.2 E2 7' E2 6.3 E2 5.5 E2 KRYPTN-88 1.9 E3 1.8 E3 1.7 E3 1.6 E3 1.5 E3 1.4 E3 XENN-I33 4.3 E3 4.3 E3 4.3 E3 4.3 E3 4.3 E3 4 ' E3 XEHN-I35 3.8 E3 3.7 E3 3.7 E3 3.6 E3 3.5 E3 3' E3 VII-32

SECTION VI I .- RADIOLOGICAL CONDITIONS PART F - AREA RADIATION MONITOR READINGS (RX BLDG 5. CONTROL STRUCTURE)

VII-33

REACTOR BU)LD)NG REV 7/19/91 )830 18:45 ) 91X) 19:15 19:30 19 A5 20:00 20 ) 5 20.~ 20:45 21:00 21:15 21 30 21 45 22'00 loCAT NN 18:15 lEVEl 645 92 92 92 92 92 92 92 92 92 4 )7E405 3,75E<05 3.37E+05 3 04E<05 2.75E F05 2 50f F05 RkR ROON 8 9.20 1-1000 92 ARH I 122 122 )22 122 12.2 122 12 2 )2.2 4.90E F05 4.4) fi05 3.97f F05 3.58f F05 323fi05 2,94fi05 R)6) ROON A 1220 I-loop 122 122 02 02 02 02 02 4.90EK6 4,17fo03 3,54fi03 30) ft03 2.56fi03 2,17fi03 ARH 25 01-100 02 02 02 02 02 ARH 2 L NXN 021 ).7 1.7 1,7 1.7 1.7 7.50fi03 638E t03 5,42ft03 4 6lf re 3.92E>03 3 33E<03 1.7 1.7 1.7 1,7

)PCI NXN 1.65 01-100 1.7 1.8 1.8 1.8 1.8 I.S 4.90E F03 4 17E F03 3 54E t03 3 pl fF03 ~ 56fF03 2 )7E ARN 3 1.8 I.B 1.8 1.8

/RV SIMP ARE A 1.80 1-1000 IS AR)14 i'.00E p) 0 ) Q.) 0.'I O.l Q.l O.l Q,l I ppfiv5 t04 8.1 pf @04 7,29E @04 6.56E+04 5 90fi04 0,1) .01-100 ARH )6 REN S)ON ROON 0I P ) P.l O.l O.l 0.1 O.l O.l 200fi03 I SXt03 I 62ft03 I 46f re I 3)f e03 I ISft03 U-I RR ACCESS BAY O.l I .01-100 AR)136 lEVEL 719 0.4 0.4 0.4 0.4 OA OA 0.4 04 04 ).20fi04 I OSE t04 9,72E y(g 8.75E<03 7 87f F03 7 K&03 0.40 .1-1000 0.4 ARH 5 CRD NORTH

.1-1000 I0 1.0 I Al 1.0 1.0 1.0 I0 Ip 10 Io ).20E t04 ) .QSf 104 9 72f y03 8 75fi03 7 87fi(6 7.09E+03 CRD SOUTH I AS 05 05 05 05 05 I 60fi04 I 44E i04 I 30E F04 I,) 7E @04 ) 05E t04 9 45E+03 ARH 6 050 .I-1000 05 05 05 05 05 ARH 26 6/TP DRIVE AREA OA OA OA OA 0.4 OA 04 OA 0.4 2 Ppf to) I.SOE F04 I 62E i04 1.46E t04 1.3)E F04 I.ISfi04 0.40 IE2-IE6 OA AR))4) TP CHEER SRD 0.70 .1-1000 0.7 0.7 0.7 07 0.7 07 07 07 07 07 200fi03 I Sof tp3 I 62E t03 I 46ft03 f I 3) to3 ) IBfi03 ARN 9 CRD REPAI) ROOH LEVEL 749 02 02 02 02 02 02 p2 p2 200.0 180 0 162 0 )45.8 131.2 I I S. I RYCU RECRC AREA 024 .1-)000 02 IO )O hRH 8 )O IO )O )O )O )50 0 1350 1215 1094 984 886 F)XL KOL PP AREA I 00 .I-)000 I0 ARH Io lEVEL 779 I.I 1.) I.l 1.1 I. I 320 288 259

) 06 .0)-100 I.l 1.1 ARH I I LEVEL 799 0.1 0.1 0.1 320 288 25.9 233 210 )89 0.08 .Ol 100 O.l RECRC FAN ROON LEVEl 818 )2 I 12 .2 I2 1.2 1.2 1.2 32.0 288 259 233 2).Q )8.9 rm CR)T NQN 120 .I-AOO I2 1.2 "8 8 ARH 14 SPNT p2 02 02 0.2 0.2 02 02 320 25 9 23 3 210 )8.9 Rg)XL FI44X)TH 0.16 .Ol 100 03 03 03 03 03 320 288 259 ARH 15 P3 P3 233 21 0 )89 SAPP CASK STIR 034 .01-100 03 03 03 03 2)0 ARH35 13 ~ FUEL CRIT NON REFUEL FL-VEST 025 040

.I 1000

.01-100 03 04 Q3 p4 03 GA Q3 04 04 OA QA 04 320 320 288 "88 259 59 233 "33 ~) 0

)8.9 189 ARH 42

Vflli I, PAGE I OF I CROUP Polf'IT DISPLAY SERVICES 8-Oct-~I ! 8 15 REi/ ~

7/1 9/91 GPOVP HVf'1BER .15 RÃ BLDG AREA RAD t"IONIT (E-PLAf< DISPLAY)

POINT rlo. DESCP!PTIGN wLAP,t"I Ic VAS HIGH LGV STATE I'IOV LAST LINIT L!NIT VI'llTS pApn4 APN-04-RB/RV SVI"IP AREA I 80 1.80 15.00 NONE I"IP/HP, PAR25 AI? t-I-25-RKR RGGI-I A 12.20 12.20 50.00 HOI'IE t"IR/HR PAPOI APt"I-01-PHR ROON B 9 20 9.20 5O.OO HONE I"1R/HR PARG2 ARt"I-02-RC IC POOM 021 0.21 4.00 ['IONE I.IR/HP.

PAROS ARI"I-O~-HPCI Roof"I 1.65 1.65 8.00 rlorIE MR/HR PAPi6 ARI'I"36-VI RR ACCESS BAY 0.11 0.11 4.00 HONE t"IP.!HP, t AP16 APN-16-REN "HDN Rnnt"I 0.11 0.11, 4.00 HONE I"1R/HR PARO6 ARM-06-CRD SOUTH 1.00 1.00 15.00 NONE MR/HR PAP.09 APt"1-09-CRD REPAIP, ROOM 0.70 0.70 15.00 NONE NR/HR PARG5 ARN-05-CRG NGPTH 0.40 0 40 15.00 NONE I"IR/HR PAR41 APt"1-41 "TIP CHAI"IBER SHLD 040 0.40 300.00 HONE MR/HP.

PAP,26 ARN-26-IG/TIP DRIVE APEA 0.50 0.50 15.00 NONE MR/HP, PAR10 ARt"I-10-FUEL POOL PP AREA 1.00 1.00 15.00 NONE t"IR/HR PAR08 APM-08-PVCU RECIRC APEA 0.24 0.24 4.00 Nor<E t"IR/HR PAP15 ARf"I-lb-HEV FUEL CRIT I"ION 0.25 0.25 15.00 NONE MR/HR IMARI I ARM-I I -SANPI.E ROOM 1.06 1.06 4.00 Nol'IE MR/HR ARI2 ARN-12-1? ECIPC F Afl ROON n.os n.os 4.on flofIE HP./HP.

PARI@

A ARI"I-14-SPNT FUEL CRIT t"IGN 120 1.20 15.00 HONE, t'IR/HR PAP.15 APN-15-RFUEL FLP.-f'lORTH 0.16 0.16 4.00 NONE I"IR/HR P AR42 ARM-42-RFUEL FLR-VEST 0.40 0 40 4.00 NofIE MR/HR VII-35

UNIT I, PAGE I OF 1 GROUP POIflT DISPLAY SERVICES 8-Oct-91 18:30 RE<): 7/19/91 GROUP HUf'IBER .15 Rn BLDG AREA RAD MONIT (E-PLAf'I DISPLAY)

PGIIIT fl0. DESCRIPTIOH ALARM IS VAS HIGH LOV STATE I'lOV LAST LIMIT LIMIT UNITS PAPG4 ARI"1-04-RB/RV SUt 1P APEA 1 80 1.80 15 00 HGflE MP./HR O'AR'25 ARM-25-RHR POOt"1 A 12.20 12.20 50.00 HONE I-1R/HR PAPG I ARt"I-01-PHR RGOI"I B 9.20 9.20 50.00 [IONE Mi?!HR PAP02 API"I-02-RC IC POOM 0.21 0.21 4.00 HONE t<R/HP.

P RR03 ARf"I-03-HPCI ROOI"I 1.65 1.65 8.00 HONE t"IR/HP.

PAP36 ARt"I-36-U1 RR ACCESS BAY 0.11 0.11 4.00 NONE f"IP.!HP.

PAP,16 ARt I-16-REI-I SHDN ROGt I 0.11 0.11 4.00 NONE I"IR/HP.

PAR06 ARM-06"CPD SOUTH 1.00 1.00 15.00 NONE MR/HR P ARC9 ARt-I-09-CRD REPAR ROGt.1 0.70 0.70 15.00 NOI'IE t"IR/HR PARG5 API"I-05-CRD flORTH 0.40 0 40 15.00 NONE t"IR/HR PAR41 ARt"I-41-TIP CHAI"IBEP. SHLD 0 40 0.40 300.00 NOI'IE I"IR/HR PaR 6 ARM 26 IG/TIP DRIVE APEA 0.50 0.50 15.00 1lONE r,P./HR PARIO ARf"I-10-FUEL POOL PP AREA I .OO 1.00 15.00 HONE MR/HR PAR08 API"1-08-RVCU PECRC AREA 0.24 0.24 4.00 NONE t"IR!HP.

PAP.13 ARt"I-13-NEV FUEL CRIT t"ION 0.25 0.25 15.00 NONE MR/HR PARI I ARM-11-SAMPLE ROOM 1.06 1.06 4.00 NONE MR/HR

'AP.12 APM-12"I?EC!RC F Af'l PGOt"1 0.08 0.08 4.00 NONE t"IR/HP, PAR14 ARM- I 4-SPNT FUEL CRIT I"ION 1.20 1.20 15.00 NONE t"IR/HR PAP.15 ARI"I-15-RFUEL FLR-f'IORTH 0.16 0.16 4.00 flOI'lE MR/HP, PAP.42 ARM-42-PFUEL FLR-VEST 0 40 0.40 4.00 NONE MR/HP.

VII-36

Uflli I, PAGE 1 GF 1 GROUP POiflT DISPI. AY SERVICES 8-Oct-91 18:45 REV'/19/91 GROUP NUI IBER .15 RX BLDG AREA RAD MONIT (E PLAf'l DISPLAY)

Pelt~ T IIG. DESCP!PT!GN ALARM 8 VAS HtGH LGV STATE NGV LAST LII"llT LIMIT UillTS P APG4 APM 04 PB/R i'( SUt"IP AREA 1,80 1.80 15.00 NeflE MP/HR

<<AR25 API"I-25-RHR ROOt-I A 12 20 12.20 50.00 riOIIE I.IP/HR Pare. API"I-01-PHR RGOI"I 8 9 2Q 9.20 50 00 rlerlE I-IR/HP PAI?02 ARI-I-02-RCIC POOt.l 0.21 0:21 4.00 NGflE HR/HR PAROS ARM-OS-HPCI ROON 1.65 1.65 8.00 NONE I"IR/HR PAP~6 APt"1-.6-UI RP. ACCESS BAY 0.11 0.11 4.00 NGflE t"IP./HR PAP,)6 ARI 1-16-REIN SHDN ROOM 0.1 I 0.11 4.00 f'let lE t"IR/HR PARQ6 ARM-06-CRD SOUTH 1.00 1.00 15.00 Nef'IE MR/HR P APG9 APt"I-09-CPD PEP AIR RGGM n.70 0.70 15.00 I'IGIIE MP./HP.

PARG5 ARI I-l35-CRD flGPTH 0.40 0.40 15.00 NGflE t.IR/HR PAR41 ARI"I-41-TIP CHAI"1BER SHLD 0.40 0 40 "00.00 fief lE I"1P,/HP.

PAR26 ARM-26-IG/TIP DP.IVE AREA 0.50 0.50 15.00 NONE r-IP/HP, PAR IO ARM-10-FUEL POOL PP AREA 1.00 1.00, 15.00 Nef'IE I"IR/HR PAP08 API"1-08"RVCU RECIRC AREA Q 24 0.24 4.00 NONE MP./Hl?

PAP.! 3 APM-15"NEV FUEL CPIT MGN 0.25 0.25 15.00 flONE HP/HP.

t AR11 ARM-11-SAMPLE ROOM 1.06 1.06 4.00 NGI'IE MR/HR cgP1 i ARM-12-I?ECIRC FAf'I PGGM 0.08 0 08 4.00 NONE I"IP./HR

<<ARI4 ARt"I- I 4-SFNT FUEL CRIT t IGN 1.20 1.20 15.00 NONE l"IR/HR PARIS ARM-15-RFUEL FLP,-flORTH 0.16 0.16 4.00 NefIE I"IP/HR P AR42 ARM-42-PFUEL FLP.-VEST 0.40 0.40 4.00 NONE MP./HP.

VII-37

UflIT 1, PAGE I OF 1 GROUP POlf'lT DISPLAY SEPVICES 8-Oct-~ I 1< '00 pnr GROUP HUf"IBER .15 RX BLDG AREA RAD I"10f'IIT (E-PLAN DISPLAY)

PG! f!T NO. DESCP, IP I'IGII Al. AP.f"1 IS VA3 HIGH LGV STATE i"lO'iY L AST LIMIT LINIT UNITS

>APORT . PM-04-RB/RV SUMP AREA 1,80 1.80 15.00 NONE MP,/HR

." AF:25 ARI"I- 5-RHR ROGt"I A 12.20 12.20 50.00 NONE t"IR/HR PARG I API'1-01-PHR ROOM B 920 920 50.00- NOf'lE t"lR/HR F'ARQ2 ARI.I-G2-RClC ROOM 0,21 0.21 4.00 NONE I~R/HR ARI"I-Oi-HPCI ROON 1.65 1.65 8.00 r!OHE t"!R/HR FARGO'AP..s6 API"I-~6-UI RR ACCESS BAY 0.11, 0.11 4.00 NOI'lE f"IR/HR PpR!6 API"!-! 6-PEM SHDfl RGGt"I 0.11 0.11 4.00 NONE I"IR/HR PARG6 ARN-06-CRD SOUTH 1.00 1.00 15.00 NONE MR/HR

>AP09 APN-0'9-CPD PEP AIR PGGM 070 0.70 15.00 NONE t"IR/HR P AR05 ARI-I-05-CRD flGPTH 0 40 0.40 15.00 HOflE I.IR/HP.

aAP41 APM-41-TIP CHAI"IBER SHLD 0.40 0.40 300.00 NONE ~'R 'HR PAR26 API !-26-!6/TIP DRIVE APEA 0.50 '.50 "

15.00 f'lONE r-!R/HR PAR!0 ARI'1" 10-FUEL POOL PP AREA !.00 !.00 15.00 rlONE MR/HR P AP08 ARM"08-RVCU RECIRC AREA 0.24 0.24 4.00 i"lONE t'lR/HP.

PARI~ ARI"I-13-NEVFUEL CRIT I"IGN 0.25 0.25 15.00 NONE f"!R/HP.

PARI 1 ARN-11-SANPLE ROOM 1.06 1.06 4.00 I'lONE MR/HR z>aP i2 ARI"I-!2-RECIRC FAN ROOM G.OS 0.08 4.00 NOf'lE I"IR/HP.

PA!l! 4 x!"I"I-14-SPNT FUEL CRIT t"ION 1.20 1.20 15.00 NONE I"IR/HR PAP.15 ARM-15-RFUEL FLR-NORTH 0.16 0.16 4.00 NONE t!R!HR P AR42 APf"!-42-PFUEL FLP.-VEST 0 40 0.40 4.00 NONE I"IR/HR VII-38

UfllT I, PACE I OF I GROUP POlflT DISPLAY SERYICES ~-Oct-~ I PcLP i/19(01 GROUP f'IUf16ER:15 RX BLDG AREA P.AD NONIT (E-PLAf'I DISPLAY)

FO!IIT I!i3. DESCRIPTvifI ALAPI"I IS WAS HIGH LOV STATE NOV L AST L IMIT LIt'11T UIIITS o a,POa >Pt"l-04-PB/RW SUNP AREA 1.80 1,80 15.00 flOIIE I-1R/HP PAP:5 APt I-25-RHP Rlilit"I A 12.20 12.20 50.00 NONE I")R/HR

."-ARO I Ai? t"I-01-PHR ROOt"1 B 9.20 9.20 50.00 f'IONE I"IP./HR PAPO2 ARI"! 02 PCIC RQOt"1 0.21 0.21 4.00 NOflE r.>R/HR ARN-Oi-HPC I POOI"I 1.65 1.65 8.00 f'IOf<E t"1R/HR PIRO'AP."6 API"1-)6"UI RR ACCESS BAY 0.11 0.11 4.00 fiOflE t"IP/HP, PAR16 API"I-16-PEf"I SHDfl ROOM 0.11 0.11 4.00 NOI'IE t"IR/HR PARO6 ARM-06-CRD SOUTH 1.00 1.00 15.00 I'IOI'IE NP/HR P AP09 APM-09-CRD PEP AIR POON 0.70 0.70 15.00 NOt'IE NR/HR PAR05 ARt"I-05-CRD NORTH OAO OAO 15 00 NONE t"1R/HR PAPA I ARI"I-41-TIP CHANBER SHLD 0.40 0AO 300.00 NOflE 'R.(HR PAR26 ARI"I-26-IG/TIPDRIVE APEA 0.50 0.50 15.00 NONE t"1P/HR PARIO ARI"1-10-FUEL POOL PP AREA 1.00 1.00 15.00 NONE I'IR/HR PAR08 APM-08-RVCU RECIRC AREA 0.24 0.24 4.00 NONE MP,/HR PARl i APM- I 3-NEW FUEL CRIT NOI'I 0.25 0.25 15.00 NONE NR/HR ARII ARM-11-SANPLE ROON 1.06 1.06 4.00 I'IONE NR/HR AP,1. APM-12-PECIPC FAf'I ROON 0.08 0.08 4.00 NONE MR/HP.

PAR14 ARI"I-14-SPNT FUEL CRIT t"10N 1.20 1.20 15.00 NOIIE MR/HR PAP.15 ARt.1-15-RFUEL FLR-NORTH 0.16 0.16 4.00 f'IOI'IE l"1R/HP.

P APA2 APt"1-42-RFUEL FLR-VEST 0AO 0.40 4.00 NONE t-IR/HR VII-39

UNIT I PAGE 'I OF I GROUP PGII'IT DISPLAY SERVICES 8-Oct-91 I a:aO REV: 7/I aia!

GROUP i'IUI"IBER:15 RX BLDG APEA RAD I 10NIT (E-PLAN DISPLAY)

POINT NO. DESCPIPTIGN ALARN IS VAS HIGH LOV STATE NOV LAST LIMIT LINIT UNITS

>>R 4 ARM-04-RB/RV SUI"1P AREA 1.80 1.80 15.00 HONE t IR/HR PAP,25 ARM-25-RHR ROON A I 2.20 12.20 50.00 NOflE I"IR/HR PAP,OI ARt"I-01-RHR RGOt"1 B a 20 a 20 50.00 f'IGtlE t"1P.!HR PAR02 ARM-02-RC IC POGM 0.21 0.21 4.00 NGflE MR/HR PAROi AP M-OZ-HPC I ROOt"I 1.65 1.65 8.00 f'iOf'IE t"IR/HR PAP~6 APM-r6-UI RR ACCESS BAY 0.11 0.11 4.00 NONE NR/HP PAP.16 ARM-16-PEI I SHDH PGOI"1 0.11 0.1 I 4.00 HONE MR/HR 1'wRG6 ARM-06-CRD SOUTH 1.00 1.00 15.00 f'lGNE MR/HR

+ APOa 41?M-Oa-CRD REPAIR ROOI"I 0.70 0.70 15.00 flOI'lE I"IR/HR PA%05 ARI"I-05-CRD flORTH 0.40 0.40 15.00 rIONE I"IR/HR PAPA I APt"1-41-TIP CHAt'1BER SHLD 0.40 0.40 300.00 NONE '"1P iHR PAR26 ARM-26-IG!TIP DPIVE AREA 0.50 0.50 15.00 NGflE MP./HR PAR10 ARI"I-10-FUEL POOL PP AREA 1.00 1.00 15.00 NONE NRr'HR PAP08 ARM-08-PVCU RECIRC AREA 0.24 0.24 4.00 HONE t"1P.r HR PAP ARN-13-NEV FUEL CPIT t 1ON 0.25 0.25 15.00 NONE NR/HR PARI I ARN- I I -S AMPLE ROON 1.06 1.06 4.00 NONE NRiHR rAP12 APt"I-12-PECIPC FAN POOM 0.08 0.08 4.00 NONE t"1R/HR PAR14 ARt"I-14-SPf<T FUEL CRIT t"ION 1.20 1.20 15.00 NONE t"1R/HR PAR 15 API"I-15-RFUEL FLR-f'IORTH 0.16 0.16 4.00 HOI'IE t"1R/HR P AR42 APM-42-RFUEL FLP.-VEST 0.40 0.40 4.00 flGflE NR/HP.

VII-40

Uflii I, PACE I OF I GROUP POINT DISPLAY SERVICES 8-Oct-91 19:45 REV. 7/19/9 GROUP f'IUf"18ER:15 RY 8LDG AREA RAD MONIT (E-FLAN DISFLAY)

>OINT NO. DESCRIPTION AI. AP.t"I IS VAS HiGH LOV STATE flOV LAST LIMIT urliTS P PP04 ARt"1-04-RB/RV SUt"1P AREA 1.80 1.80 15.00 f'lOf'lE t'1R/HP PAR25 ARt"1-25-RHR ROOt"I A 12.20 12.20 50.00 NOflE t"IR/HP.

PAROI APM-01-RHR ROOI"I B Q 90 9 20 000 flONE MP,/HP.

P AR02 ARt-I-02-RCIC ROOM 0.21 0.21 4.00 NOflE I IR/HR PAROS ARM-03-HFCI ROOM 1.65 1.65 8.00 NONE I"IR/HR PAR>6 ARt"I-o6"Ui RR ACCESS BAY 0.1 I 0.11 4.00 NOflE MR/HP.

PAP16 ARI-I-16-REt I SHDfl ROOt-1 0.1 I 0.11 4.00 I'lONE t"IR/HP.

PAR06 ARM-06-CRD SOUTH 1.00 1.00 15.00 NONE MR/HR

> AP09 ARM"09-CRD REPAIP. POOM 0.70 0.70 15.00 NOflE MP,/HR P AR05 ARf"I-05-CRD flORTH OAO OAO 15.00 NONE t"1R/HR PAR41 ARt"I-41-TIP CHAI"IBER SHLD 0.40 OAO 300.00 f'IOI'lE I"IR/HP.

P AR26 APt"1-26-IG/TIP DRIVE AREA 0.50 0.50 15.00 I'lONE MR/HR FAR10 ARM-10-FUEL POOL PP AREA 1.00 1.00 15.00 f'lONE MR/HR P AP08 ARM-08"RWCU PECIRC APEA 0.24 0.24 4.00 NONE MR/HR PARR API"1- I o-fIEV FUEL CRIT MON 0.25 0.25 15.00 NONE I"IR/HR PAR11 ARM-11-SAMPLE ROON 1.06 1.06 4.00 NONE MR/HR AR12 ARM-12-RECIRC FAI'I ROON 0.08 0.08 4.00 NONE I"IR/HR PAR14 ARI"I-14-SPNT FUEL CRIT MON 1.20 1.20 15.00 NONE I"IR/HR FAR15 APM-15-PFUEL FLR-NORTH 0.16 0.16 4.00 f'IOI'IE I'IR/HP.

P AR42 APM-42-RFUEL FLR-'VEST OAO 0.40 4.00 I'IONE MR/HR VII-41

UIIIT 1, PAGE 1 GF I GROUP POINT DISPLAY SERYICES 8-Oct-a 1:0:00 PEY 7/ I a/al GROUP f'lUNBER:15 RX BLDG AREA P.AD f"IGNIT (E-PLAf'l DISPLAY)

POINT HG. DESCRIPTION ALARM IS 'r/AS HIGH LGV STATE fIO'r( I.AST LIMIT LIMIT Uf'llTS P ARG4 ARN 04 PB/R<Y SUI IP AREA 1.80 1.80 15.00 flGflE NP/HP P*R25 ARt"I-25-RHR PGGt"I A 12.20 12.20 50,00 flGflE t"IR/HP, P AR01 AP.I"1-01-P,HR ROOI"I B a 20 a 20 50.00 tlGflE I"!R/HR I AR02 ARM-02-RCIC PGOM 0.21 0.21 4.00 NONE t"IR/HP.

PARG3 API"1-03-HPC I ROON 1.65

" 1.65 8.00 NONE t"IR/HR PAR36 ARI"1-36-Ul RR ACCESS BAY 0.11 0.11 4.00 flONE t"1R/HP, PAR16 ARt"I-16-PEI"1 SHDN ROGI"1 0.11 0.11 4.00 NOflE I"IR/HR PARG6 ARN-06-CRD SOUTH 1.00 1.00 15.00 f'lGI'IE MR/HR PAR09 ARN-09-CRD REPAIR ROOI"1 0.70 0.70 15.00 NONE MR/HR P AR05 ARt"1-05-CRD NORTH OAO OAO 15.00 flONE I"IR/HR PAR41 ARIA-41-TIP CHAt"IBER SHLD OAO OAO 300.00 I'lOflE MR/HP PAP,26 APN-26-IG/TIP DPIYE APEA 0.50 0.50 15.00 NONE t"1R/HR PAR10 ARI I-10-FUEL POOL PP AREA 1.00 1.00 15.00 NONE I"IR/HP.

ARG8 ARM-08-RVCU RECIRC AREA 0.24 0.24 4.00 NONE t"1R/HR PAR13 API"I-13-NEV FUEL CRIT MGN 0.25 0.25 15.00 NONE MR/HR t'ARI I ARN-11-SAMPLE ROOM 1.06 1.06 4.00 NONE MR/HR

.'AR12 ARM-I .-PECIRC FAfl ROOM 0.08 0.08 4.00 flONE P./HR PAR14 API"I- I 4-SPf'lT FUEL CRIT t"IGN 1.20 1.20 15.00 NONE t"1R/HP.

PAP.15 ARI"I-15-PFUEL FLR-NOPTH 0.16 0.16 4.00 NOf'IE I-IR/HR PAR42 ARI"I-42-RFUEL FLR-'r/EST 0.40 OAO 4.00 NONE I"'R/HR VII-42

UIIIT I, PAGE I OF I GROUP POiflT DISPLAY SERViCES 8-Oct-91 20:15 REV 7 (] 0/81 RN BLDG AREA RAD f.IOf'IIT (E-PLAI'I DISPLAY)

Pi INT fjG. DESCPIPTIGfl ALAR!"I IS VAS HtGH LGV STATE flOV LAST LIMIT Lit"IIT Uf'lITS PPPG4 API"!-04-PB/F'V SUt"IP Al? EA 1.80 1.80 15.00 NONE t"IP./HP.

PA I,' ARt"i-25-I:,HR F'.GGI"I A- 12.20 12.20 50.00 flGNE t"IR/HR F APOI ARM-0 I -PHR ROGt"I B ~.20 ~.20 50.00 flGflE t!R!HR PAPQ2 Apt I-02-Pi IC RQQM 0.21 0.21 4.QO NGI'IE I"!I? /HP.

PARGS ARf"I-OS-HPC I RQGI"I 1.65 1.65 8.00 NONE I IR/HR PAR36 APt'I-. 6-Ul PP, ACCESS BAY 0.11 0.11 4.00 NOflE t'lR/HR PAP.16 APM-16-REI"I SHDN RGGM 0.11 0.11 4.00 f'IGNE I"IP./HR PARG6 aRM-06-CRD SOUTH 1.00 1.00 15.00 NONE MR/HR PAPG ARM-09-CRD REP AIR PGGf", 0.70 0.70 15.00 NONE I"1R/HR PAR05 ARI"I-05-CRD NORTH OAO OAO 1500 NONE t"IR/HR PAP41 ARI"I-41-TIP CHAt"IBER SHLD 0AO 0AO 300.00 flONE I"IR/HR PAI?26 ARt I-26-tG/TIP DRIVE APLA 0.50 0.50 15.00 NOflE I"IR/HR PARI 0 ARf"I-10-FUEL POOL PP AREA 1.00 1.00 15.00 NOt'IE I"IR/HR PAP08 ARt"I-08-RVCU RECIRC AREA 0.24 0.24 4.00 flONE MR/HP.

PARIS ARM-I3-NEV FUEL CRIT MON 0.25 0.25 15.00 NONE MR/HP, oARI I ARM"11 "SAMPLE ROOM 1.06 1.06 4.00 NONE t iR/HR AP.12 APJ"!-12-RECIRC F AN ROOM 0.08 0.08 4.00 I'IOI'IE MR/HR PARI < AF t.1-14-SPfli FUEL CRIT t.iOfl 1.20 1.20 15.00 NONE I"IR/HR PAP.15 API I-15-RFUEL FLP.-NOPTH 0.16 0.16 4.00 flONE I"IR/HR P AR42 APf"I-42-RFUEL FLR-VEST 0.40 OAO 4.00 NOflE I"IP/HR VII-43

Uf'lli 1, PAGE I OF I GROUP PO!flT DISPLAY SERVICES 8-Gct-91 20 50 PEV: 7/19/91 GROUP NUI"lBER:15 RX BLDG AREA RAD I"1ONIT (E-PLAN DISPLAY)

POINT NO. DESCRIPTIG[l ALARM IS V AS HIGH LOV STATE I'lOV L AST l. INIT LIMIT UfllTS PAR04 ARM-04-PB/RV SUI"IP AREA 1.SG 1.80 15.00 NOIIE t"IR/Kl?

PAR25 ARI"I-25-RHR ROON A 12.20 12.20 50.00 NONE t"IR/HP.

PAR01 ARf"1-01-PHR POOt"1 B 9.20 9.20 50.00 fIONE t"1R r'Hl?

P Al?02 ARI"!-02-RC!C RGGI"1 0.21 021 4.00 NONE MR/HR PARGi ARN-05-HPCI POOI"I 1.65 1.65 8.00 I'lONE '"1R/HR PAR>6 ARN-i6-UI PP. ACCESS BAY 0.11 0.11 4.00 NONE NRr'HR PAR16 &RIG-16-PEt"I SHDf'I ROON 0.11 0.11 4.00 NONE NR/HR PAR06 ARN-06-CRD SOUTH 1.00 1.00 15.00 NOf'lE MRr'HR PAP,O'9 ARN-09-CPD REPAIR POON 0.70 0.70 15.00 I'IONE t"!R/HR P ARO5 ARI"I-05-CRD flORTH 0.40 0.40 15 00 NONE I"IR/HR PAR41 APM-41 "TIP CHAf"1BER SHLD 0.40 0.40 F00.00 NONE t"IR!HR PAP.26 ARN-26-IG/TIP DP.!VE AREA 0.50 0.50 15.00 t'lONE NP./HR PAR10 ARl I-10-FUEL POOL PP AREA 1.00 1.00 15.00 NONE I"1R/HR PAP.OS ARN-GS-RVCU RECIRC APE A 0.24 0.24 4.00 NONE I"1R/HR PAP I> ARN-Io-NEV FUEL CRIT I"IOI'I 0.25 0.25 15.00 NOI'lE NR/HR PARII ARN-11-SAMPLE ROOM 1.10 1.06 4.00 I'lGI'lE MR/HR r ARl" AR<<-12 PECIRC FAN ROON 0.08 0.08 4.00 NOflE t"1R!HR PrtR14 ARI"1-14-SPNT FUEL CRIT t"10N 1.20 1.20 15.00 fNONE I"1R/HR PAP.15 ARI"!-15-RFUEL FLP.-NORTH 0.16 0.16 4.00 flGflE I"IP,/HR P AR42 APt"I-42-PFUEL FLP.-VEST 0 40 0.40 4 00 NONE NR/HR VII-44

UHIT I, PAGE I OF I GROUP POINT DISPLAY SERVICES 8-Oct-91 0:45 REV

~

7/14/91 OROUF f'{UMBER:15 RX BLDG AREA RAD NONIT (E-FLAN DISPLAY)

PGI!IT HG. DESCP.IPTIGH AL APt"I IS V AS HIGH LGV STATE NOV LAST LINIT LINIT Uf'IIT-PARG4 ARN-04-RB(RV S{JMP AREA >1000 1.80 15.00 HGflE t"IP./HR PAR.5 ARt"I-25-RHR RGGI"I A 12.20 12.20 50.00 HGHE t"IRIHR FARO I API"I-01-RHR ROOt"I 8 >IOOO 9.20 50.00 NGflE I"IR/HP.

PAPQ2 ARM-02-RCIC POQM >>00 0.21 4.00 f{QflE MRIHR F AR03 API"I-03-HFCI ROOI"I >100 1.65 8.00 f'IOI'IE MR/HR P AR36 APt"I-36-Ui RR ACCESS BAY >100 0.11 4.00 NONE NR/HP.

PAR'6 AP,N-16-P,Et.i SHDI'l RGGM >100 0.11 4.00 flGflE t"IR/HR PAR06 ARI CRD SOUTH >1000 1.00 15.00 NONE MR/HR P AR09 API"I-09-CRD PEPAIP. ROON >1000 0.70 15.00 HOf'lE I"IP./HP.

PARG5 ARt"I-05-CRD NORTH >1000 0 40 15.00 flOflE t"IR/HR PAR41 ARM-41-TIP CHAt"IBEP, SHLD 2.0E+04 0 40 300.00 flof'IE t"IR/HP, P AP'>6 aRI 1-26-IG/TIP DP,IVE AP.EA >1000 0.50 15.00 NONE I"IP.IHR PARI 0 ARI"I-10-FUEL POOL PP AREA 150.00 1.00 15.00 NONE I"IR/HR PAP08 ARN-08-RVCU RECIRC AREA 200.00 0.24 4.00 HONE MR/HR PAR I 3 ARI"I-13-NEVFUEL CRIT I"ION 32.00 0.25 15.00 NONE MR/HR

>ARI I ARN" 11-SAMPLE ROOM 32.00 1.10 4.00 f'{ONE MR/HR 2

AP.12 ARN-12-RECIRC F AN ROOM 32.00 0.08 4.00 NONE MR/HR PAR14 ARs I-14-SPNT FUEL CRIT NON 32.00 1.20 15.00 HONE PAP.15 ARI"I"15-RFUEL FLR-flORTH 32.00 0.16 4.00 HONE t"IP./HP.

PAR42 ARM-42-RFUEL FLR-VEST 32.00 0 40 4.00 flONE MR/HP.

vII-45

Uflli I, PAGE I OF I GPOUP POIflT DISPLAY SERVICES 8-Gct-91 21:00 REV: 7/19/9!

GROUP f'IUt"IBER:15 RX BLDG AREA RAD MGNIT (E-PLAf'I DISPLAY)

POINT NG. DESCRIPT IGfl ALARt"I IS V AS HIGH LOV STATE NOV LAST LIMIT LIMIT Uf'IITS PAPG4 ARt"'I 04 RB/R A SUMP AREA >1000 >1000 15.00 NOf'IE MR/HR PAR 5 ARt"I-25-RHR ROOI"1 A >1000 12.20 50.00 NONE f"IR/HR

?APGI APt-!-01-PHR POOl I 8, >1000 >1000 50.00 I'IGf'IE I"IP./HR PARO2 ARI 1-02-RCIC ROOt.l >100 >>00 4.00 f'IONE t"IP./HR PAR03 ARM-03-HPCI ROOt"I >100 >100 8.00 flONE t"IR/HR PAR36 ARt1-36-UI RR ACCESS BAY >100 >100 4.00 NONE MR/HR PAP.16 ARI"I-16-REI"ISHDN ROOM >100 >100 4.00 NONE t"Il?/HR PARG6 ARM-06-CRD SOUTH >1000 >1000 15.00 NONE MR/HR PARO9 ARM-09-CRD PEPAIR ROOM >1000 >1000 15.00 NOI'IE MR/HR PARO5 ARI"I-05-CRD NORTH >1000 >1000 15.00 f'IGf'IE t"tR/HR PAP41 ARI"I-41-TIP CH At"IBER SHLD 1.8E+04 2.0E+04 300.00 HONE I"IR/HR PAP26 ARM-26-IG/TIP DRIVE AREA >1000 >1000 15.00 NONE MP./HR PAR10 ARI"I-10-FUEL POOL PP AREA 135.00 150.00 15.00 NONE MR/HR PAROS ARM-OS-RVCU RECIRC APEA 180.00 200.00 4.00 NONE MR/HR PAR13 ARM-13-I'IEV FUEL CRIT MON 28.80 32.00 15.00 NONE MR/HP.

PARI I ARM-11-SAMPLE ROOM .S.SG 32.00 4.00 NONE MR/HR

'AR12 ARM- I 2-PEC!RC FAN ROOM 28.80 32.00 4.00 f'lONE I"IR/HR PAI? I4 ARI"I"14"SPNT FUEL CRIT I"ION 28.80 32.00 15.00 NONE t"1R/HR PAP!5 ARI-I-15-PFUEL FLR-flORTH 2e.eo 32.00 4.00 NONE f IR!HR PAP42 ARM-42-RFUEL FLR-VEST 28.80 32.00 4.00 f'lONE t"IP/HP.

VII-46

UfllT I, PAGE I GF I GROUP POifiT DISPLAY SERVICES 8-Qct-91 21 '.15 REii' l I '0 191 GROUP NUI"IBER:15 RY BLDG AREA RAD I"IONIT (E-PLAf'I DISPLAY)

PGIflT NODESCRIPTIGfl ALAP,I"I IS l(HS HIGH LG'4J'II"IIT STATE f'lOV LAST Llt"IIT UflITS P APG4 APN-04-RB/RV SUt"IP AREA >1000 >1000 15.00 flGflE I"P/HP P AR25 ARf"I-:5"RHRRQQt"I A ~IQGQ >1000 50.00 ilQNE r.IR/HR

. ARQI ARN-0 I -RHP, POQI"I S >I 000 >1000 50.00 flGIIE iiIR/HP PARO2 ARt-I-02-RC(C RGQt.I >100 >>00 4.00 i'lQ!IE t~R/HR PARGi API"I-OZ-HPCI RGOI"I >100 >100 8.00 NONE i"'lR/HR PAP~6 ARI"I-i6-Ul RR ACCESS BAY >100 >100 4.00 flGI'IE i~IR/MR PAP.16 APt"I-16-REt"I SHDfl PGGI"I >100 >100 4.00 rlnrlE NR/HR PAROS ARN-06-CRD SOUTH >> 000 >> 000 15.00 I'lOI'IE NR/HI?

P AR09 APN-09-CRD REPAIR PGON >1000 >1000 15.00 NONE NR/HP.

PARG5 ARI"I-05-CRD fIGI?TH >1000 >1000 15.00 NONE I"IR/HR PAR41 ARf"1-41-TIP CHAt"IBEP. SKLD 1.6E+04 1.BE+04 400.00 NONE t"IP./HR

?AR26 ARN-26-1G/TIP DPIVE APEA >1000 >>000 15.00 flQflE I"IR/MR PAP. I 0 ARt"I-10-FUEL POOL PP AREA 121.50 135.00 15.00 HONE NRlHR P AP.08 ARt"I-08-PVCU RECIRC AREA 162.00 180.00 4.00 NONE NRlHP PAP I.> ARt"I-l i-fIEVFUEL CRIT NON 25.92 28.80 15.00 NONE t'IR/HR i ARI I ARM-11 "SANPLE ROON 5.92 28.80 4.00 f'lGNE NR/HR

'AR12 APt i-12-RECIRC FAfl PGOt"I 25.92 28.80 4.00 NONE t"IRlHP.

PAR14 ARI"I-14-SPf'IT FUEL CRIT I"IGN 25.92 28.80 15.00 !IGNE NR/HR PAP.15 ARt"I-15-PFUEL FLR-NGRTH 25 92 28.80 tlOflE I"IP./HI?

P AR42 ARN-42-RFUEL FLR-VEST 25.92 28.80 4.00 flQNE t"IR/KR VII-47

Ul'llT I, PAGE I OF I GROUP PO!f'IT DISPLAY SERVICES 8-Oct-91 21 30 vE<r 7/tv/a1 GROUP f'IUI'"1BER:15 RÃ BLDG AREA RAD MONIT (E-PLAf'I DISPLAY)

~OINT MG. DESCRIPTION ALARI"I 8 V AS HIGH LGV STATE NOV LAST LIMIT I. IMIT UNITS P AP,04 API"I-04-RB/RV SUf'IP AREA >1000 >1000 15.00 NGf'IE I"1R/HR PAR25 ARt"I-25-RHR ROGt"1 A >1000 >1000 50.00 tlGNE I"IR/HR PAP.OI API"I-O1 -RHP. ROOM B >1000 >1000 50.00 NOf'lE t"IR/HR PAP02 API"1-02-RCIC RGGM >100 >100 4.00 NONE I IR!HR PARO3 ARI"I-03-HPCI ROOM >100 >100 8.00 NOflE I"1R/HR P AR36 ARM-36-Ul RP. ACCESS BAY >100 >100 4.00 NONE t"IR/HP.

P AP.16 SHDN RGGt"1 'RM-16-PEN

>100 >100 4.00 flGf'lE I"IR/HR PAR06 ARM-06-CRD SOUTH >1000 >1000 15.00 NONE MR/HR P AR09 ARM-09-CRD REP AIR RGGM >1000 >1000 15.00 NONE MR/HP, 8 ARO5 ARt"I"05-CRD flGRTH >1000 >1000 15.00 flGNE MR/HR P AR41 APM-41 "TIP CHAI"IBEP. SHI.D 1.5E+04 1.BE+04 300.00 flOf'lE tRR/HR PAP26 ARM-26-IG/TIP DRWE AREA >1000 >1000 15.00 NONE MR/HR PARIO ARM-10-FUEL POOI. PP AREA 109.35 135.00 15.00 NONE MR/HR PARO8 ARM-08-RVCU PECIRC AREA 145.80 180.00 4.00 NONE MR/HR PAR13 APM-13-NEV FUEI. CRIT MOM 2333 28.80 15.00 I'IONE MR/HR PAR11 ARM-1 1-S AMPI.E ROON 23 33 28.80 4.00 I'lOI'lE I R/HR

'AP,12 ARt'1-12-RECIRC F AN ROOM 2333 28.80 4.00 NOflE MR/HR PAR14 ARt"1-14-SPNT FUEL CRIT I"10f< 23 33 28.80 15.00 NONE t"IR/HR PAP.I 5 ARI"1-15-RFUEL FLR-NORTH 28.80 4.00 flOflE t"IR/HP.

P AR42 ARM-42-RFUEL FLR-VEST 28.80 4.00 NOI'IE f.IR/HR VII-48

Uflli I, PAGE I OF I GPOUP POIfli DISPLAY SERYICES 8-Oct-91 ~

I:45 REL) ~

7/I 9/91 GROUP f'!UMBER:15 RX BLDG AREA RAD f"10f'lIT (E-PLAN DISPLAY)

POINT fl0. DESCRIPTION ALARM IS VAS HtGH LOV STATE NOV LAST LIMIT LIMIT UfllT-I'APG4 ARM-04-RB/RV SUMP AI?EA >1000 >1000 15.00 f'lONE I"IR/HP, PwR25 ARI"I-25-RHR POOM A >! 000 >1000 50.00 NOflE I"IP,/HR MARGI ARf"I-01-PHR ROOI"I B >1000 >1000 50.00 NOflE !"IR/HR PAP02 API"I-02-RC!C ROOM >100 >100 4.00 NOflE t.!R/HR PARG3 ARf"I-03-HPCI ROOf"I >100 > IOO 8.00 NOf<E I"IR/HR PAR36 APt"I-36-UI RR ACCESS BAY >100 >100 4.00 flGflE t"IR/HP.

PAR16 API"I-16-REM SHDN PQOM >I GO >100 4.00 NOf'lE MR/HR P ARO6 ARM-06-CRD SOUTH >1000 >1000 I 5.00 I'IOI'IE MR/HR P AR09 API"I-09-CRD REPAIR POCM >1000 >'I 000 15.00 NGf'lE MP,/HP.

PARG5 ARt"I-05-CRD f'lORTH >1060 >1000 15.00 fl0flE t.!R/HR PAR41 ARI"I-41-TIP CHAt"!BER SHLD 1.3E+04 1.5E+04 300.00 NOIIE MR/HR PAP26 ARI"I-26-IG/TIP DRIVE AREA >1000 15.00 f'IONE I IP./HP.

>1000'8.42 PARIG ARt"I-10-FUEL POOL PP AREA 109.35 15.00 NONE t"'IR/HR PAP08 APM-08-RVCU RECIRC AREA 131.22 145.80 4.00 NONE t"!R/HR PAP,13 API"I-13-f'IEVFUEL CRIT MOf'I 21.00 23.33 15.00 NONE I"IR/HP.

)

>ARI I ARM-11-SAMPLE ROOM 21.00 2333 4.00 NONE MR/HR

'AP.!2 API"I-12-REC IRC F AN POGM 21.00 2333 4.00 NOI'lE t"IR/HR PAR!4 ARI"I-14-SPNT FUEL CRIT MON 21.00 23.33 15.00 NONE t"IR/HR PAR15 AP t-I-15-PFUEL F LR-flORTH 21.00 23.33 4.00 NOflE t"IR/HR PAR42 AP!"I-42-RFUEL FLR-VEST 21.00 23.33 4.00 I'lONE I"!R/HR VII-49

UNIT I, PAGE I OF I GROUP POIf'IT DISPLAY SERVtCES 8-Oct-91 22:00 REV: 7/19/91 GPGUP f'lUMBER:15 RX BLDG AREA RAD I"IONIT (E"PLAf'I DISPLAY)

POINT NO. DESCRIPTION ALARt"I IS V AS HIGH LOV STATE NOV LAST I.IMIT LIMIT UNITS PAP04 APM-04-RB/RV SUI"1P AREA >1000 >1000 I S.OO f'IOI'lE MP./HR P AR25 ARM-25-RHR ROOM A >1000 >1000 50.00 flONE t"1R /HR PAP.OI APt"I-01-PHR ROOt"1 B >1000 >1000 50.00 ilOflE t"IR/HR PAP.02 ARIA-02-RC!C ROOf.1 >100 >100 4.00 f'IOf'IE I"IR/HP.

PAROS ARM-0$-HPCI ROOt"I >100 >100 8.00 NOflE I"IR/HR PAR36 ARM"36-UI RR ACCESS BAY >100 >100 4.00 NOflE t"IP./HR PARl6 ARt"I-16-PEI"1 SHDI'I ROOI"1 >100 >100 4.00 flONE MRIHR PAR06 ARM-06-CRD SOUTH >1000 >1000 15.00 t'lOf'lE MR/HR PARO9 ARM-09-CRD REPAIR ROOM >1000 >1000 15.00 NOflE MR/HR PAR05 ARM-05-CRD NORTH >1000 >1000 15.00 NONE t"IR/HR PAP41 ARt"I-41-TIP CHAI"IBER SHLD 1.2E+04 1.3E+04 ~00.00 NOf'IE MR/HR PAR25 ARM-26-IG/TIP DRIVE AREA >1000 >1000 15.00 NONE MR /HP.

PAR10 ARM-10-FUEL POOL PP AREA 88.57 98 42 15.00 NONE MR/HR P AROB ARM-08-RVCU RECIRC AREA 118.10 131.22 4.00 NONE MR/HR PARIS ARt"I-13-NEV FUEL CRIT MON 18.90 21.00 15.00 NONE I"1R/HR PAR11 ARM-11-SAMPLE ROOM 18.90 21.00 4.00 NOllE MR/HR

'AP.12 APM-12-PECIPC FAI'l ROOM 18.90 21.00 4.00 I'lOI'lE MR/HR PAR14 API I-14-SPNT FUEL CRIT MON 18.90 21.00 15.00 NONE t"1R/HR PARI5 ARt"I"15-RFUEL FLR-NORTH 18.90 21.00 4.00 NONE t"IR/HR PAR42 ARM-42-RFUEL FLR-VEST 18.90 21.00 4.00 NONE t"1R/HR Vjj-50

HIGH RhttGE REACTOR BUILDING TABLED VAIUES GIVEN Nl INI/ISI RE VIS Stt .

lOChf ION Al 18:15 tttttt RANGE 18:30 18 45 19 00 19.15 19.30 19:45 20:OO 20:15 20:30 20:45 21 OO 21:15 21:30 21:45 22:OO 1 f2-If@ 4.4Et02 ARt I 56/I I RHR ROOI1 8 440 4 4E t02 4 4E t02 4.4Et02 4.4f+02 4.4Et02 4.4E+02 4 4E t02 4.4E+02 4.4Et02 4.6E+05 4.1Et 05 3.7Et05 3 4E t05 3 Of+05 2,7Et05 ARII 55/ 5 PI6'OOt1 A 360 If'2"1 E6 3.6Et02 3.6Et02 ARt157/12 3.6E+02 3 6Et02 3 6Et02 36E+02 3 6E+02 3.6Et02 3 6E+02 3.6E+02 4.9E+05 4.4ft05 4.Of+05 3.6Et05 3.2Et05 2.9E+05 RC IC PP TWB R11 380 IE2-IE6 3 Sf t02 3 BE+02 3.BE+02 3.BE+02 3 BE+02 3 BE+02 3 BE+02 3.BE+02 3 BE+02 3 BE+02 4. IE+02 3.?E+02 33E t02 3.DE+02 2 7E+02 2 4E t02 ARt1 48/3 tPC I PP TIRB Rt1 230 I f2-1E6 2.3E+02 2.3E+02 2.3Et02 2.3Et02 2.3E+02 2.3Et02 2.3E+02 2.3Et02 23E t02 2.3Et02 2.3Et02 f 2.1 t02 1.9Et02 1.7Et02 1.5Et02 1.4Et02 AP11 53/16 PEt1 SDII PM. RI1 310 lf2-lf6 3 I Et02 3 I f+02 3 IEt02 3 IEt02 3 IEt02 3 Ift02 3 Ift02 3.if+02 3.1E t02 3.If+02 I OEt05 If 9.DE+04 8, t04 7.3E+04 6 6E+04 5 9ft04 ARI1 50/5 CRD HOP TH (SDV's) 280 IE2-1 f6 2 Sf t02 2.BE+02 2 BE+02 2.BE+02 2.BE+02 2 BE+02 2 BE+02 2.BE+02 2 SE+02 2.8Et02 I 2Et04 I.If+04 9.9E t03 9 OEt03 S.lft03 73Et03 ARtt 51/6 API1 52/18 ARt1 54/10 CL&'RECRC ~

CRC SOUTH (SDV's) fEKL PL PPS'11 AC 410 500 210 I E2-'I E6 4.1E t02 4.If+02 f

IE2-I 6 50ft02 5.0E+02 If2-lf6 2. I f+02 2.IE+02 4.lft02 4.1Et02 4.1E+02 4.1 ft02 5.DE+02 5.DE+02 5 Oft02 5XKt02 4.1E t02 4.If+02 4.1E+02 4.IE+02 1.2E+04 5.Of+02 5 Of t02 5 OEt02 5.DE+02 50ft02 I.IEt04 I.OE t04 4.5Et02 4.IE t02 9 OEt03 S.IEt03 3 6Et02 3 3Et02 7 3E+03 3 DE+02 2.1Et02 2,1Et02 2.If+02 2.1E+02 2.If+02 2. IE+02 2 lft02 2.If+02 3 6Et02 3.2E+02 2.9Et02 2.6Et02 2.4E+02 2.1Et02 AP1149/42 RFLXL flR AREA 410 IE2-IE6 4.1E+02 4 IE+02 4 lft02 4 IEt02 4 IEt02 4 1ft02 4.If+02 4.1f t02 4.If+02 4.1E+02 4.4E+02 4 OEt02 3.6Et02 3.2E t02 2.9E+02 2 6E t02

UNIT I, PAGE 1 GF I GROUP POINT DISPLAY SERVICES 8-Oct-91 18".! 5 GP.OUF f'iUf'IBKR:10 Hl RANGE ARI I PEAD}f'iGS (E-PLAf'i Dl FLA")

PolfiT,NO. DESCPIPTIOfi AL AP.t"1 IS 3-'AS HIGH

- T ATE NO'r( LAST L It'1IT L It"IIT $ lrilwo PAR~o APt'1-56-PHR ROOt"1 LOOP B GA4 030 IS.GO Nof'IE P./HP.

F" AR55 AR}.1-55-RHR ROOt-1 LOOP A 0.36 036 15.00 I'iof'iE R/nK P AP57 ARt"1-57"RCIC PP TUPB Rt"1 0.38 OA4 15.00 NONE R/HR P APAS ARN-48-HPC I PP /TURB Pl"1 0,23 0.38 15.UG rioriE g rgn F AR53 ARI"1-53-ACCS TO PEf"1 SHUTD 0.31 023 1'5.00 fiof'IE R/Hi?

P AP50 ARI"1-50-CRD NOPTH 0.28 0.30 15.00 rior E P!HP P MR51 APN-51-CRD SOUTH 0.41 0,31 15.00 fiofiE P./HP.

F AR5= ARN-5 -R'rirCU PP ACCESS 0.50 0.41 15.00 Nof'iE Rr'HR P AR54 ARI"'I-54-FUEL POOL PP POON 0.21 0.41 15.00 NofiE P./HP.

P AR49 ARt }-49-REFUEL FLOOR AREA 0.41 0.28 15.00 ftONE R/HP.

Uf'ilT 1 p

PAGE 1 OF 1 GROUP Polf'iT DISPLAY SERVICES 8-Oct-91 18 30 GPOUP f'iUI"IBEP.:10 Hl RAfiGE ARM PEADINGS {E-PLAN DISPLAY)

RGINT No DESCRIPTION ALARM IS 'i'(AS'IGH 0'i r STATE NQE'i'AST L lt"1 IT L It"1IT UfiITS P AP.56 nRt-1-56-RHR ROOM LOOP B 0.44 OA4 15.00 NONE I?!HP.

PAR55 APN-55-RHR POON LOOP A 0.36 0.36 15.00 NONE P /HP P AR57 ARf I-57-RCIC PP TL}RB Rf.l 0.38 0.38 15.00 I'iol'IE R/HP.

P APA8 APt"1-48-HPCI PP/TURB RN 0.23 0.23 15.00 rior<E P.iHR P AP53 APt"1-5o-ACCS TO REt"1 SHUTD 0.31 0.31 15.00 fiONE P,/HR P AP50 ARI"I-50-CPD NORTH 0.2S 0.28 15.00 NofiE RiHR PAR51 ARN-51-CRD SOUTH 0.41 0.41 1 5.00 f'ioNE P./HR P AR52 ARM-52-'R'v(CU PP ACCESS 0.50 0.50 15.00 NONE R IHR P AR54 ARI"1-54-FUEL POOL PP POOH 0.21 0.21 1 5.00 NONE R!HR PAR49 ARI"1-49-REFUEL FLOOR AREA OA1 OA1 15 00 I'iof'IE R/HP VII-52

IJf'IIT 'I PAGE 1 OF I GPOUP PGlf'IT DISPLAY SERVICES 8"Oct-91 18:45 RQUP f'>tJt"IBER .'10 HI RAf'IGE ARt"I READIf'iGS (E-PLAf'I DISPLAY)

~Oit'iT NO. DE CRIPTIGN ALARI"I 8 V AS HIGH LOV STATE NOV L AST L INIT LIMIT UflITS P AR56 APM-S6-PHP. ROOI"1 LOOP B 0.44 0.44 15.00 NOf'iE P./HP.

P ARSS APt 1-55-PHR RGQt"I LOOP

0. 6 036 IS GO flGNE t:!HP.

P AR57 ARI"I-57-RCIC PP TUPB Pt 1 038 038 15.00 NOf'IE P /HR P AR48 ARt"'.-43-HPCI PP/TUPB PN 0.23 0.2"- 15.00 tiOflE R! HR F'AR53 APt'1-53-ACCS TO REM SHUTD 0.31 0.31 15.00 NONE. P./HP.

P APSO API"I-50-CRD NOPTH 0,28 0.28 15.00 flGNE P. /HR PARSI API"I-51-~ PD SOUTH 0.41 0 41 15.00 I'lOfiE P./HR PAR5 APN-52-RVCU PP ACCESS 0.50 0.50 15.00 NQt'lE R/HR PAP54 APM-54-FUEL POOL PP RGQt"1 0.2'I 0.21 15.QO NQfiE R/HP.

P AR@9 ARt"I-49-REFUEL FLGOP, AREA 0.41 0.41 15.00 fiOf'iE R/HR Uf'llT I, PAGE I QF I GPOUP POIf'lT DISPLAY SERVICES 8-Oct-91 19:00 GROUP f'lUI"IBEP:10 HI PAf'lGE ARM READINGS (E-PLAN DISPLAY)

PGItlT NO 0 DESCRIPT ION ALARM IS V AS HIGH LOV STATE flOV L AST L lt"1 IT LIr-1IT IJfit 8 e

P AP56 APt"I"'56"RHR POQI"I LOOP B 0.44 0.44 15.00 iiONE P AP.55 ARN-55-RHR ROON LOOP A 0.36 0.36 1 5.00 NOf'IE P /4R P AP57 API"I-57-PCIC PP TURB PM 0.38 0.38 15.00 NONE R/HP.

PAP48 ARI"1-48-HPC I PP /TURB RN 0.23 0.23 15.00 NONE R/HR PARS3 ARM-53-ACCS TO REI"1 SHUTD O.i 1 0.31 15.00 NONE R/HP P AR50 ARM-50-CPD NORTH 0.28 0.28 1 5.00 fiOI'lE P./HR P AR51 ARt"I-S 1 "CRD SOUTH 0.41 0.41 15.00 NOf'lE P./HR PAR52 ARt"I-52-RVCU PP ACCESS 0.50 0.50 15.00 NONE R/HR P AR54 ARI"1-54"FUEL POOL PP ROON 0.21 0.21 1 5.00 flOfiE R/HR P AR49 &PM-49-REFUEL FLOOR AREA 0.41 0.41 15.00 f'iQf'lE P./HR VII-53

UfllT I, PAGE 1 GF I GROUP POINT DISPLAY SERVICES 8"0:t-91 I 9: I 5 GROUP NUI"1BEP.:10 Hl RAflGE ARt"I READINGS (E-PLAN DISPL*Y)

PQI['lT f'IQ. DESCRIPTION AL AP,t"I IS VAS HIGH LOV STATE flGV LAST LIMIT LIMIT I If<ITS P>R56 APM-56-RHP. ROON LOOP B 0.44 OA4 15.00 NO[IE P./HP.

PAR5 ~ *RN-55-PHR ROON LOOP A 0.36 036 15.00 r.IQFIE P./HP.

PAR57 ARt"1-57-RCIC PP TURB Pt"I 0.38 0.38 15.00 f'lQflE R/HP.

PAR48 ARI"1-48-HPCI PP /TURB Rt"I 0.23 0.23 15.00 NGf'lE p rQp PAR53 APt"1-53-ACCS TO REN SHUTD 0.31 0.31 15.00 NONE R/HP.

P AR50 ARN-50-CRD f'IORTH 0.28 0.28 15,00 f'lOf'lE Rr'HP.

P AR51 APM-51-CPD SOUTH OA1 0.41 15.00 flOf'IE R.lHR P AP52 APN-52-RVCU PP ACCESS 0.50 0.50 15.00 flOflE R/HP, PAR54 ARM-54"FUEL POOL PP ROOM 0.21 0.21 15.00 NOI'lE R/HR ARt"I-49-REFUEL FLOOR AREA OAl 0.41 15.00 flGNE R/HR UNIT 1, P*GE I OF 1 GROUP POlf'lT DISPLAY SEPVICES 8-Oct-'91 19:30 GPQUP flU["1BER:10 Hl RANGE ARt"1 READINGS (E-PLAN DISPLAY)

PQII'lT f'IQ. DESCR IPT IOI'l ALARM IS V*S ' HIGH LO'rl STATE NOV LAST II"1 IT LII"1IT UNITS P AR56 ARt"I-56-RHR RQQI"1 LOOP B 0.44 0.44 15.00 flGNE P./HR P AR55 ARt-1-55-RHP, PQOI"1 LQQP A 0.36 0.36 15.00 NONE p rHp P AP.57 ARM-57-RCIC PP TUPB RM 0.38 0.38 1 5.00 NO['IE R/HP.

PAR<8 ARf I-48-HPCI PP/TUPB R[1 0.23 0.23 15.00 NONE P.r'HP, P AR53 ARM-53-ACCS TO PEN SHUTD 0.31 0.31 15.00 NONE Rr HR P AR50 ARI"1-50"CPD f'lORTH 0.28 0.28 15.00 NOflE R/HP.

PARSI ARM-51-CRD SOUTH 0.41 0.41 15.00 [lQI'lE R/HR P AR52 ARN-52-RVCU PP ACCESS 0.50 0.50 15.00 NOf'lE R/HP.

P AR54 ARt"I-54-FUEL POOL PP ROON 0.21 0.21 15.00 NOflE P./HR P AR49 ARM-49-REFUEL FLOOR AREA QA1 0.41 15.00 NOflE R/HP.

VIT.-54

GROUP PolflT DISPLAY SEPVICES 8-i3ct-91 I .":45 GPOUP I'IUI"!BER:10 HI RAf'lGE APf"I PEADI.'lGS (E-PLAf'I DISPLAY)

F'OINT HG. DESCRIPT IGf'I ALAPSE IS VAS HIGH LQV STATE NUV LA T L It"IIT LIMIT 1JfllT.

PAR56 ARM-56-PHR ROON LOOP B 0.44 0.44 15.00 Nof'lE P/HR PAR 5 APM-55-PHP. PGQM LGGP A 0.36 0.36 15.00 Ni'NE P,/HP.

F'R57 ARt"I-57-RCIC PP TURB Rt"I 0.38 0.38 15.00 flotlE i? /HR P AP48 ARI"I-48-HPC I PP /TUPB Rt"I 0.23 0.23 15.00 flGNE R/HR

~wR53 ARN-53" ACCS TO REM SHUTD 0.31 0.31 15.00 NoflE R/HP P AR50 ARt-I-50-CRD flORTH 0.28 0.28 15.00 rlOrlE R r'HR P AP51 ARN-51-CRD SOUTH 0.41 0.41 15.00 NONE R/HP.

PAP52 APt"I-52-PVCU PP ACCESS 0.50 0.5O 15.00 NONE P./HP.

P AR54 ARN-54-FUEI POOL PP ROON 0.21 0.21 15.00 Nof'lE R/HR P AR49 ARN-49-REFUEL FLOOP. AREA 0.41 0.41 15.00 NoflE R/HR

~Jfl IT 1, PAGE 1 OF 1 GROUP POINT D ISPL AY SERVICES 8-Oct-e1 2O:OO GPOUP flUNBER:10 HI RANGE APM PEADINGS (E-PLAN DISPLAY)

POINT I'lo. DES CR IPT Iol'l ALARM IS VAS HIGH LQV STATE f'lOV LAST LIMIT L INIT Uf'lITS P ARS6 ARf"I-56-RHR ROGI"1 LOOP B 0.44 0.44 15.00 NONE Rr HI?

? AP.55 API"I-55-PHP. POON LOOP A 0.36 0.36 15.00 NQflE R/HR P AR57 ARM-57-RCIC PP TURB Rt"1 038 0.38 15.00 NONE P./HR PAR48 ARf"1-48-HPC I PP /TURB RM 0.23 0.23 15.00 f'lOf'lE Rr'HR P AR53 ARM"53-ACCS TO REt"1 SHUTD 0.31 0.31 15.00 fIGNE Rr'HP.

PAP50 ARN-50"CPD NORTH 0.28 0.28 15.00 NONE P /HP.

P AR51 ARN-51-CRD SOUTH 0.41 0.41 15.00 f'lGNE R/HR P AR52 ARM-52-R'iv'CU PP ACCESS 0.50 0.50 15.00 NONE R/HR P AR54 API"I-54-FIJEL POOL PP ROOM 0.21 0.21 15.00 floflE R/HR P AR49 ARN-49-REFUEL FLOOR AREA 0.41 0.41 15.00 NoflE P./HP.

VII-55

UNIT I, PAGE I OF I GROUP POlflT DISPLAY SERVICES 8-Gct-91 20;15 GPGUP HIJt"ABER:10 HI RAf'lGE ARN READlf'lGS (E-PLAf'l DISPLAY)

PQIflT flO. DE-CPIPTIOf'l ALAP.I"1 IS ~ VAS HIGH LOW STATE NG'F LAST L ll"IIT LII"IIT IJfilT::-

P &R56 ARN-56-PHR ROOM LOOP B OA4 OA4 15,00 flGNE R!HR P AP55 ARt"1-55"PHP. PQOt"1 LGGP A 096 0.~6 15.00 NOflE R!HR F AR57 APN-57-RCIC PP TURB Rt"1 038 O.iS 15.00 NOf'lE R!HR F APAS APN-4S-HPCI PP /TURB RM 0.23 0.2> 15.00 NGflE R HP.

PAR5~ Al?t"1-SZ-ACCS TO PEt"1 SHUTD 0.31 031 15.00 NGflE P- iHR P AR50 ARf"1-50"CRD f'lOPTH 0.28 0.28 15.00 flONE P AR51 ARt"'I-51-CRD SOUTH OA1 0.41 15.00 NOf'lE RlHR PAR52 APt"I-52-PWCU PP ACCESS Q.50 0.50 15.00 flQflE R/HR P AR54 ARN-54-FUEL POOL PP POON 0.21 0.21 15.00 flQflE P.!HP.

PAP,49 ARt"1-49"REFUEL FLOOR AREA OA1 OA1 15.00 f'lGf'lE R/HR UfllT 1, PAGE 1 OF 1 GPGUP POINT DISPLAY SERVICES 8-Oct-91 20 90 GROUP f'lUNBER:1 0 Hl P.ANGE ARM READlf'IGS (E-PLAN DISPLAY)

POlf'lT NO. DESCP IPT IQN ALARN IS WAS HIGH LGV STATE NOV LAST LIMIT Llt"11T IJf'IITS P AP56 ARf"I-56-PHR ROON LOOP B OA4 OA4 15.00 f'lQNE R!HR P AP55 APt"1-55-RHP. ROON LOOP A 0.36 O.i6 15.00 NONE R/HR PAP.57 ARM-57-PCIC PP TIJRB RN 0.>8 0.38 15.00 I'lof'lE P./HP.

PAR48 ARt"1-4S-HPCI PP !TURB RN 0.23 0.23 15.00 NOf'lE RPHR PAR5i ARM ACCS TO REM SHUTD 0.31 031 15.0Q fIGNE P.!HR PAR50 ARI"I-50-CRD NOI? TH 0.28 0.28 15.00 flGflE RUHR PAR51 ARN-51-CRD SOUTH 0.41 OA1 15.00 f'lONE P.!HR P AP52 ARN-52-RVCU PP ACCESS 0.50 0.50 15.00 f'IONE P.!HR P AR54 ARN-54-FUEL POOL PP ROON 0.21 0.21 15.00 flOflE R!HR P AR49 ARN-49-REFUEL FLOOR AREA OA1 0.41 15.00 NONE RiHR VII-56

VfllT I, PAGE I OF I GPQUP POINT DISPLAY SERVICES 8-0:t-91 ZQ O5 GPI3UP fIUI-!BEP.:10 Hl PANGE APM PEADlflGS (E"PLAN DISPLAY)

PGlfIT f10. DESCRIPTION ALARI"I iS VAS HIGH LO'8 STATE LAST LIMIT Llt"IIT UIIIT~

IIO'v!'60.94 PAP56 ARM-56-RHP. ROOM LOOP 8 0.44 15.00 NOI IE R/HR P AR55 ARM-55-RHR ROON LOOP A 490.=6 0.=6 15.QG rlnNE P/HR P AR57 ARI"I-57-RCIC PP TURB Rt"I OAI 0.38 15.00 NONE P/HR P AR43 ARt"I-48-HPC I PP /TURB Rt"I 0.23 Q 15.00 NOflE F.)HP, P AR5Z ARI"I-53-ACCS TO REI1 SHUTD 10031 O.Z I 15.00 NQfi~ > 4>

P AP,50 APt"I-50-CPD NOPTH l3.28 15.00 f'lONE R/HF, FAR51 APt"I-51-CPD SOUTH 12AI OA'I 15.00 flOflE P./HP.

P AP52 API"I-52-RVCU PP ACCESS 0.50 0.50 15.00 flGflE P/HP.

P AR54 ARM-54-FUEL POOL PP ROOM 0 6 0.21 15.00 f'lONE R/HR P AR49 ARM-49-REFUEL FLOOR APE A OA4 OAI 15.00 NOI'IE P,/HR Vf'IIT 1 PAGE I OF I GROUP POINT D(SPLAY SEPArlCES 8-Oct-91 21:00 GPOUP NUt"lBER:10 Kl RANGE ARt"I READINGS (E-PLAN DISPLAY)

PQII'lT NQ. DESCRIPTIOI'I ALARM IS V AS HIGH LOV ST ATE NOi'/ LAST LIMIT LINIT UfllTS API-I-56-RHR Ri3i3M LOOP 8 414.84 46094 I 5.00 fll3lIE R)HP.

P AP.55 ARI"I"55-RHR ROOI I LOOP A 441.52 490.36 15.00 flOflE R/HR P AR57 ARM-57-PCIC PP TURB RM 0.37 0 AI 15.00 I'IOf'lE P.)HP.

PAR48 ARM-48-HPCI PP /TURB RM 0.21 0.23 15.00 rlorlE P AR53 ARM-5$-ACCS TO PEt'I SHUTD 90.28 100.31 15.00 NONE R/HP, PAP50 ARI"I-50-CPD flOPTH 11.05 12.28 15.00 flGNE P.]HP.

P AR51 ARM-51-CRD SOUTH 11.17 12.41 15.00 NONE R!'HR P AP52 ARM-52-RVCU PP ACCESS 0.45 0.50 15.00 flQf'lE R/HR P AR54 ARt"1-54-FUEL POOL PP ROOM 0.32 0.36 I 5.00 rlorlE R/HR P AR49 APt"I-49-REFUEL FLOOR AREA OAO OA4 15.00 flQNE R/HR VTI-57

UIIIT I, PAGE I OF I GROUP POINT DISPLAY SERVICES 8-Oct-91 21:! 5 GROUP f'IUt"IBEP. '10 Hl PAf'IGE ARI"I READIf'IGS (E-PLAN DISPLAY)

PGIfIT NO. DESCRIPTIOf'I ALARM IS V AS HIGH LGr STATE NOV L AST L II"IIT L It"IIT UfIITS PAR56 ARN-56-PHP. F;GOM LGGP B 373.36 414.84 15.00 NOIIE R/HR P AP55 API"I-'5 -PHR POGt"I LOOP A 397.19 441.32 15.00 fIOfIE R/HP.

P AR57 ARI-1-5 -RCIC PP TUF.B Pt-I 0.3 a 0.37 15.00 i'IOf'IE R/HI?

P AR48 ARI"I-48-HPCIPP/TUPB Pl"I 0.19- 0.21 15.00 HONE

.- AI?53 API"I-53-ACCS TO REt"I SHUTD 81.25 90.28 I S.OO NONE F.'/HP.

P ARSG ARM-50-CRD NORTH 9 95 11.05 15.00 NONE R/HP.

PAP51 ARN-51-CRD SOUTH 10.05 11.17 15.00 :IGIIE R/HP.

P AP.52 ARI"I-52-PhrCU PP ACCESS 0.41 0.45 I 5.00 IIGfIE P./HF.'/HR P AR54 ARM-54-FUEL POOL PP PGGM 0.29 0.32 I 5.00 NONE P AP,49 API"I-49-PEFUEL FLOOR AREA 0.36 0.40 15.00 f'IOf'IE R/HR Vf'IIT I, PAGE I OF-1 GROUP POII'IT DISPLAY SERVICES 8-Oct-91 21:30 GROUP NUNBEP.:10 Hl RANGE ARN READINGS (E-PLAN DISPLAY)

PGlf'IT f'IO. DESCRIPTIOf'I ALARN IS V*S HIGH LGV ST ATE NG'rr LAST LII"IIT Llt-IIT JfIITS P AR56 ARt"I-56-RHR RGOI"I LOOP B 336.02 15.00 NOf'IE R/HR P AR55 APt"I"55-RHP. ROGI"I LOOP A w5 397.1 9 I 5.00 IIGNE R/HP P AR57 ARM-57-PCIC PP TURB PN 0.30 0.33 15.00 NONE P./HI?

PAR48 ARt"I-48-HPC I PP /TURB RN 0.17 0.19 15.00 fIGIIE P AP53 ARM"53"ACCS TO REt"I SHUTD 73.13 81.25 15.00 fIONE P./HR P AR50 ARM-50-CRD NORTH 8.95 9.95 15.00 NOf'IE R/HP.

PAR51 ARN-51-CRD SOUTH 9.05 10.05 I S.OO NONE R/HP.

P AP.52 ARN 52 R 0 CU PP ACCESS 0.36 0.41 15.00 f'IONE R/HR P AR54 ARI"1-54-FUEL POOL PP RQOI"1 0.26 0.29 15.00 NONE R/HR P AR49 APN-49-REFUEL FLOOR AREA 0.32 0.36 15.00 NONE R/HR VII-58

UNIT I, PAGE I OF I GPOUP POlf'IT DISPLAY SERVICES 8-Oct-91 I:45 GPGUP f 11JI-IBEP.:10 HI PANGE API"1 PEADINGS (E-PLAf'I DISPLAY)

PGlflT fl0. DESCRIPT IOfl ALAP,t"1 IS V AS HIGH LOV ST ATE flO"( LAST I lf"1IT LII"IIT UflLTS P AR56 ARM-56"RHR ROOM LOOP B 302.42 336.02 15.00 flOflE P.iHP, P AP. APt"I-55-PHR ROOM LOOP A 321.73 35 r.4 r 15.00 'lvflE R/HR P AR57 ARt"1-57-RCIC PP TURB Rt"1 0.27 0.30 15.00 NONE PAR48 APt"I-48-HPC I PP rr TURB Rt"I 0.15 0.17 15.00 fIOIIE R/HR PAR53 ARI"I-53-ACCS TQ REM SHUTD 65.8 73.1 3 1 5.00 flOflE P AR50 ARf"I-50-CPD I'(ORTH 8.06 895 1500, NONE RiHP, PAP51 AF't"1-51-CF,'D SOUTH 8,14 9 05 15.00 NONE R/HF; PAP52 ARI"I-52-R'ii'CLIPP ACCESS 033 0.36 15.00 NOf'IE R(HR P*R54 *RN-54-FUEL POOL PP ROuN 0.24 0.26 1 5.00' flOflE R r'HR P AR49 ARt"1-49-REFUEL FLOOR AREA 0.29 32 15.00 f'lGNE R F'HR Uf'llT 1, PAGE 1 QF 1 GPOUP POINT DISPLAY SERVICES 8-Oct"91 22:00 GPGUP NUMBER:10 Hl RANGE APN READINGS (E-PLAN DISPLAY)

PGII'lT f'IO. DESCRIPT IGI'I ALARM IS 'r(AS HIGH LOV ST ATE NO'r( L AST L INIT Llt"1IT UNITS P A@56 ARN-56-PHR ROOM LOOP B 272.18 302.42 15.00 NOf'lE R J'HF.'ONE P AP.55 ARt"I-55-RHR POOt"1 LOOP A 289.55 321.73 15.00 R/'HR P AP.57 APN-57-RCIC PP TURB Rt"1 0.24 0.27 15.00 flQflE Rr'HR P AR48 ARN-48-HPC I PP /TURB Rf"1 0.14 0.15 15.00 I'IOf'IE R r'HR P AP53 ARN-53-ACCS TO REN SHUTD 59.23 65.81 15.00 NONE R/HR P AR50 APt"1-50-CPD NORTH 7.25 8.06 15.00 f'lONE R)HR PAR51 ARN-51-CRD SOUTH 7.33 8.14 15.00 NOI'lE R r'HR P AR52 ARM-52-Rb'(CU PP ACCESS 0.30 033 15.00 NONE Rr'HR P AR54 ARt1-54-FUEL POOL PP ROOM 0.21 0.24 15.00 NONE Rr'HR P AR49 ARt"I-49-REFUEL FLOOR AREA 0.26 0.29 1 5.00 flotlE Rr'HR VII-59

CNTL STR AND RADWASTE ARMS GATE GF E .EPCISE: 'IO/8/91 PEVISION: 7/12/91 CNTL STRUCTURE hND RhDVhSTE hRMS + 404Th MhNUALLYENTERED++

(mR/ar)

LOCATION NORMAL RANGE 20:45 2'1:00 21:15 21:30 21:45 22:00 22:15 ARM 38 RAG CHEM LAB 003 .01-100 0.03 0.03 0.03 0 03 0.03 003 003 ARM 39 CONTROL ROOM 0.2 .01-100 I 0.00 9.10 8.28 7.54 6.86 MARGI 4 CNTM ACC Hl RAO h 8 1-1E7 6.7E+04 6.6E+04 5.9E+04 53EKN 4.SE+04 4.3E+04 39E+04 MAR02+ CNTM ACC Hl RAG 8 1-1E7 6.0E+04 5.9E+04 5.4E+04 4.6E+04 4.2E+04 3 SE~O<

ARM 37 STBY GAS TREAT RM 0.03 .01-100 30.00 27.30 24.84 22.6l 20.57 18.72 I 7.04 ARM 31 RV 646 CORR-SOUTH 0.4 .1-1000 0.40 0.40 0.40 0.40 0.40 0,40 0.40 ARM 29 RV 646 COPR~TH 0.3 .1-1000 0.30 0.30 0.30 0.30 030 0,30 0 30 ARM 30 RV 646 CORR-VEST 0.5 .1-1000 0.50 0.50 0.50 0.50 0.50 0.50 0.50 ARM 32 CTRL ZONE SHOP 0.2 .1-1 ODD 0.20 0.20 0.20 0.20 0 20 0,20 0 "0 ARM 34 STOR+ EQUIP AREA 0.2 .1-1000 0.20 0.20 0.20 0.20 0.20 0.20 0.20 ARM 33 RAO VASTE CTRL RM 0.4 .1-1000 0.40 0 40 0.40 0.40 0.40 0.40 0.40 ARM 28 RV OR TO 2 FL SA 03 .01-100 0.30 0.30 0.30 0.30 0.30 0.30 0.30 CHAN 43 CTR TVR OBSER GK 0.2 .01-100 10 9 9 8 7 7 6 CHAN 44 CHAN 45 CTR TVR ~

CTR TVR DOC AREA RM 02 0~

.01-100

.01-100 10 10 IO 10 9

9 9 9 8 8

8 3 '7 VIT.-60

UNIT 1, PAGE 1 GF 1 GROUP POlflT DISPLAY SERVICES 8-Oct-91 48;g5 Tp GPOUP NUt"IBEP.:17 CNTPL STP. AND RADVASTE ARt 1S (E-PLAfl DISPLAY) 20130 POINT f'IO. DESCP.IPT ION ALARt"1 IS VAS HIGH LOV STATE NOV LAST LIMIT Llt"IIT UNITS P AP38 ARM-3S-RAD CHEI"1 LAB 0.03 0.03 4.00 flGNE t"IP.!HP.

PAR39- ARt"1-39-CGf'ITROL PGGt"1 0.20 0.20 4.00 NONE t"1P./MR I'1 AP01 + CONTMfl ACC RAf(G Hl PAD A 8.00 S.GO fIOfIE IIONE R/HP.

r 1AR02+ CGflTMf'I ACC P.Af'IG Hl P.AD B 5.00 5.00 NONE NOfIE R! Ml?

PAR37 ARM-37-STBY GAS TPEAT Rt"1 0.03 0.03 4.00 NONE t'1R/HP, P AR31 APM-31-RV 646 COPR"SOUTH OAO OAO 15.00 NONE Ml?/HP.

PAP29 ARI"I-29-PV 646 CORR-NORTH 0.30 0.30 15.00 NOfIE t"IP./HP, P AR30 ARM-30-RV 646 CORR-VEST 0.50 0.50 15.00 f'IONE MR/HR

~ AR32 ARM-32-CTRL ZONE SHOP 0.20 0.20 15.00 NONE I"1R/HR P AR34 ARt"1-34-STOR + EQUIP 0.20 0.20 15.00 NONE t"IR/HR P AR33 ARt"1-33-RAD VASTE CTRL ROOM OAO 0.40 15.00 NONE I'1P./HR PAR28 ARM-28-RV DR TO 2 FL SA 0.30 0.30 4.00 fiONE I"1P.!MR

UNIT I, PAGE 1 GF 1 GPQUP PGiflT DISPLAY SERVICES 8-Uct-'I iG GROUP i"lUf"18ER:1 7 CNTRL STR AND RADVASTE ARMS (E-PLAf'l DISPLAY)

F GiflT 'lO. DESCP IPT IQfl ALAPI 1 IS VAS HIGH LOV I r,l LAST LIMIT L INIT

~

STATE NGV IT APN- 8-RAD CHEN 1.AB Q.Q3 0.03 4.QQ fl'iflE ii'iF /+

PAF39 AP t"1-3'9-CQflTROL ROGI"1 10.00 0.20 4.00 NONE i"IF. r'rl t"I ARV I -" CGf'ITt"If'I ACC RANG Hl RAD A 6.7E+04 800 NGflE f'IGf'IE R/I-:P.

I->AR02-:: 6.QE+04 5.00 flGf'lE flGfl= i HP CQIITINN ACC P.AI'lG Hl P.AD B PriRkr APN-37-STBY GAS TREAT RN 30.00 0.03 4.00 NONE i'!F'r H P AP31 ARI"1-31-RV 646 CORP.-SOUTH GAO OAO 15.00 lIQflE I'1R/H P AP29 APM-29-RV 646 CORP.-NGPTH 0.30 0.30 15.00 NG{lE I-IP,/H l AP30 ARM-30-RV 646 CORR-VEST 0.50 0.50 15.00 f'IOf'lE i~1R/H PAR32 API"I-32-CTPL ZONE SHOP 0.20 0.20 15.00 flOfIE t"1R/H P AR3+ ARt"I-34-STOR + EQUIP 0.20 0.20 15.00 rlorlE t-IR/H P AP33 ARt"1-33"RAD i'i ASTE CTRL ROOI"1 OAO OAQ 15.00 f<ONE i+1Pr H P AR28 ARN-28-RV DP. TO 2 FL SA 0.30 0.30 4.00 NONE I"1P./H T 1,PAGE 1 OF I GROUP POlflT DISPLAY SERVICES 8-Gct-91 iiRGUP I'i'Ut"IBEP.:17 CNTRL STR AND RADVASTE ARMS (E-PLAf'l DISPLAY)

PGlf'IT f'l0. DESCRIPTIQf'I ALARM IS VAS HIGH LOV STATE NGV L AST L IM IT Llt"IIT UflITS P AP.38 ARN-38-RAD CHEM LAB 0.03 0.03 4.00 [IONE NR/HP.

P AP39 ARM-39-CONTROL ROOM 9.10 10.00 4.00 NOI'IE MR/HR NAP01 ~ COflTMfl ACC RAf'lG Hl RAD A 6.6E+04 6.7E+04 f'lONE flQNE P.r'HP.

t 1AR02+ CGflTt-if< ACC RAflG Hl RAD B 5.9E+04 6.0E+04 NONE NONE P./HP P AR37 ARN-37-STBY GAS TPEAT Rt"1 27.30 30.00 4.00 flONE NR/HP P AR31 ARM-31-RV 646 CORR-SOUTH 0.40 OAO 15.00 f'[ONE I"1P. /HP.

PAR.9 ARM-29.-RV 646 CORR-NORTH 0.30 0.30 1 5.00 rcor<E f"IRr HR P AR30 ARI"1-30-RV 646 CORR-VEST 0.50 0.50 15.00 NONE t'!P. r'HP.

P AP32 ARN-32-CTRI. ZONE SHOP 0.20 0.20 15.00 NONE NP./HP.

P AR34 ARN-34-STOR + EQUIP 0.20 0.20 15.00 NQf'IE MP./HR P AR33 ARM-33-RAD VASTE CTRI ROON 0.40 0.40 1 5.00 NOflE NP/HP P AR28 ARN-28-RV DR TO 2 FL SA 0.30 0.30 4.00 flQNE t"IP,/HR VII-62

UNIT I, PAGE I GF I GROUP POIflT DISPLAY SERVICES 8-Oct-91: l:1 5 Gi? GUP f'IUI"IBER:17 Cf'lTPL STR Af'lD RADWASTE ARt"IS (E-PLA!'l DISPLAY)

POINT NO. DESCP IPTiGf1 ALARI"I IS VAS HIGH STATE f'lOV L AS 7 L IMIT LIMIT Uf'l ITS P AP38 APN"38-RAD CHEI"1 l. AB 0.03 0.03 4.00 NGflE MR/HP.

P AR39 ARN-39-COrlTROL Raot-1 8.28 .".10 4.00 ilGNE t~'P! hR

'1APG'- COf'ITt"IN ACC PANG HI RAD A 59E+04 6.6E+04 fIQflE ! IGf.IE R/4P, MARIJ2~ CQNTt"1f'l ACC P.ANG Ht P.AD B 5.4E+04 5.9E+04 NONE ! lGflE 0 p'LJQ'"IP./HR P AP37 ARf"1"37-STBY GAS TPEAT Rt"1 2<.84 27.30 4.0Q i'IGflE API"I-31-PV 646 CORR-SOUTH OAO 0,40 15.00 ilGflE I"IP./HP.

PAP. '9 APt"1"29-RV 646 CGRR-NORTH 0.30 0.30 15.00 NGflE I"I.;/HF; P*R30 ARM-30-RV 646 CQRR-VEST 0.50 0.50 15.00 NGI'lE MR/HR P AR32 ARN"32"CTRL ZQf'lE SHOP 0.20 0.20 15.00 flGflE MR/HP, P AR3~ ARI"1-34-STOR + EQUIP 0.20 '.20 15.00 NONE t"1R/HR P AR33 ARI"1-33-PAD VASTE CTRL RQOM 0.40 0AO 15.00 NOf'lE MP./HP.

P AI?28 ARt"I-28-RV DP. TO 2 FL SA 0.30 0.30 4.00 NONE I"1R(HR

. 1,PAGE I OF1 GROUP PGII'lT DISPLAY SERVICES 8-Oc 1-~1 21 30 GPGUP flUt"IBEP.:17 CNTRL STR AND P.ADVASTE ARI"1S (E-PLAN DISPLAY)

PQlf'lT NQ. DESCRIPTION ALARM IS VAS HIGH LQV STATE NOW LAST l. IMIT L tt"1IT Uf'lITS P AF;38 ARt"1-38-RAD CHEN LAB 0.03 0.03 4.00 flGflE t-IF:!HP.

P AR3'9 ARN-39"COf'lTROL ROOM 7.54 8.28 4.00 i"lGf'IE ~

PP iHn IRAR01:: COf'ITI"1f'l ACC RAf'lG HI RAD A 5.3E+04 5.9E+04 NONE NONE P.!HP.

f"1 AF.'02- CGf'lTNN ACC RA!(G HI RAD B 5.0E+04 5AE+04 NorlE NONE R /HF; P AR37 ARt"1-37"STBY GAS TREAT RN 22.6'I 24.84 4.00 HONE I IR/hR P AP31 ARM-31-RV 646 CORR-SOUTH 0.40 OAO 15.00 NONE MR!HP, PAR29 ARN-29-RV 646 CORR-NORTH 0.30 0.30 15.00 Nof'lE t-IR/HP P AR30 *Rtl-30-RV 646 CORR-VEST 0.50 0.50 15.00 NONE iNP./HP.

PAR32 ARI"1-32-CTRL ZONE SHOP 0.20 0.20 15.00 flGflE I"IP,/HP.

P AR34 ARM-34-STOR + EQUIP 0.20 0.20 15.00 flOflE MR!HR P AR33' ARN-33-RAD VASTE CTRL ROON 0.40 QAO 15.00 rlorlE t"IR/HR AR28 ARN-28-RV DR TO 2 FL SA 0.30 0.30 4.00 rlorlE I"!R/HP, VII-63

Uf'IIT I, PAGE I GF I GROUP POlflT DISPI AY SEPVICES 8-0<.t-91 GROUP NUI"18ER:17 Cf'ITRL STR Af'lD RADVASTE ARf"!S (E-PLAN DISPLAY}

POINT f'IQ. DESCP.IPTIGN AL ARI"I IS V AS HIGH I.QV STATE NQV L AST L IMIT LII"!IT Uf'I ITS

> AP38 API1-38-RAD CHEM LAB 0.03 0.03 4.00 flONE I!R/~P.

P AR39 ARM-39-CQflTROL ROOM 6.86 7.54 4.00 'lorlE f'!F.'4R i~1 AP.Q I CONTI'IN ACC PANG Hl PAD A 4.8E+04 5.3E+04 I'IQI'lE l'IGflE R,rHP t-! AR02-- CGflTI"1f'1 ACC P.ANG Hl P.AD B 4.6E+04 5.0E+04 flOflE rlorlE R /HP PAR37 API"I-37-STBY GAS TREAT RM 20.57 22.61 4.00 f'IONE f"IP./HP, PAP3I ARM"31-RV 646 CORR"SOUTH 0.40 0 40 15.00 flQNE i"'<P,/HP.

PAP29 APM-29-!?V 646 CQPR-f'IORTH 0.30 0,30 15.00 f'IONE I">P /HF:

P AR30 ARM-30-R'iY 646 CQRR-'<'(EST 0.50 0.50 15.00 f'IONE '~E 'HR P AR32 APM-32-CTRL ZONE SHOP 0.20 0.20 15.00 f'IGf'IE <!R/HR P AR34 API"1-34-STOR + EQUIP 0.20 0.20 15.00 f'lONE I"1P./HR P AR33 ARM-33-RAD VASTE CTRL ROOM 0.40 0.40 15.00 NONE MR P AR28 APM-28-RV DR TO 2 FL SA 0.30 0.30 4.00 NONE

/HF.'"1P./HP.

.T!, PAGE 1 OF I GPOUP POINT DISPLAY SERVICES 8-Grt-91 GPQUP f'IUt"18ER:17 CI'ITRL STR AflD RADVASTE ARMS (E-PLAft DISPLAY)

POINT NG. DESCRIPTION ALARM IS V AS HIGH LQV STATE NGV L AST L IMIT LIMIT Uf'< ITS P AP38 ARM-38-RAD CHEM LAB 0.03 0.03 4.00 NONE MR.r'HR P AR39 ARM-39-COf'ITROL ROOM 6.24 6.86 4.00 NOf'IE '~p 'HP MAP01:: COflTt"1f'l ACC RANG Hl RAD A 4.3E+04 4.8E+Q4 NONE NONE .. HP.

~

MARQ2+ CONTt"If'l ACC RAf'lG HI RAD B 4.2E+04 4.6E+04 NGflE flGNE R /HP, P AR37 ARt"1-37"STBY GAS TREAT RM 18.72 20.57 4.00 NONE t-!P!HR PAR31 ARM-31-RV 646 CORR-SOUTH 0.40 0?40 15.00 NONE I"!P./HP.

P AR29 ARM-29-RV 646 CORR-NORTH 0.30 0.30 15.00 f'lONE t"1R/I P.

PAR30 ARM-30-RV 646 CORR-VEST 0.50 0.50 15.00 NONE t1Rr'HP.

P AP32 ARI"I-32-CTRL ZONE SHOP 0.20 0.20 15.00 NONE I"IP,/HR P AR34 ARM-34-STOR + EQUIP 0.20 0.20 15.00 f'lONE I <Rr'HP.

P AR33 ARt"1-33-RAD VASTE CTRL ROOM 0.40 0?40 15.00 NO[IE '"!p/H>

P AR28 ARM-28-RV DR TO 2 FL SA 0.30 0.30 4.00 NQflE I"IF.'/HR VII-64

SECTION VII - RADIOLOGICAL CONDITIONS PART G - IN-PLANT DOSE SURVEY MAPS VII-65

CORE SPRAY N~

PUMPS IA IC 0 0 CORE SPRAY PUMPS D

D SIPPRE 5SIQH POOL WATER FILTER PIRO

~SSKW 48 x POOL x 04 03 x SINP OIL TERCEP gA~SUMP 0 0 57 OWEO QAP 56 Oi PUMPS 55 x x x

RHR PUMPS x25 0'0 RHR HT.

0 D C'hei A MPC WCEPT HPCI)

AIRBORNE IS 1/10 IN STAIRWAYS (1) FROM SHINE FROM RHR PIPING (2) FROM AIRBORN FROM STEAM LEAK IN HPCI (10'UEL MELT)

REACTOR BUILDING ELEV 645 DOSE RATE IN MR/HR TIME AREA A AREA B AREA C AREA D AREA E AIRBORNE MPC EXCEPT HPCI 1800 NORMAL NORMAL NO NORMAL NORMAL NORMAL 181

C9T5 1930 1945 2 (.)Mi 2100 441,000 0 0 4400 ~273VG 300,000 4400

,00 206,000

~il-IaOD~Goo 2115 397,000 4000 8250 250,000 4000 222i000 2T3o ,000 T5&i TRRl ,0 AIRBORNE IS 1/10 IN STAIRWAYS (1) FROM SHINE FROM RHR PIPING (2) FROM AIRBORN FROM STEAM LEAK IN HPCI (104 FUEL MELT)

VII-67

53[x WiLK WAY s S

Q WIN REACTOR BUILDING -

0 ELEV 670 axaa DOSE RATE IN MR/HR MPC EXCEPT HPCI I~mt)

PaiiP AIRBORNE ZS 1/10 ZN STAIRWAYS (1) FROM AIRBORNE IN HPCI (2) FROM CORE SPRAY PIPING IN NE CORNER

3) FROM HPCI STEAM LEAK BEING CIRCULATED THROUGHOUT BUILDING BY SGBT VII-68

REACTOR BUILDING ELEV 670 DOSE RATE IN MR/HR TIME AREA A AREA B AREA C AREA D AREA E AIRBORNE MPC EXCEPT HPCI 1800 NORMAL NORMAL NORMAL NORMAL NO 1815 1930 1945 22I c T'T5, tFoO 2

2100 8500 125,000 925 180 1825 211 8250 100,000 850 160 3200 F50 AIRBORNE IS 1/10 IN STAIRWAYS (1) FROM AIRBORNE IN HPCI (2) FROM CORE SPRAY PIPING IN NE CORNER (3) FROM HPCI STEAM LEAK BEING CIRCULATED THROUGHOUT BUILDING BY SGBT VII-69

'C'N D M5C3 SPtIC POOL

<<,i 0

CHCII EHTRARCCS AOO TK.

Z IIECHC

$V g+

u>

~ lal OWFH5 i/ Ei ClZ O IA /i

~ RAN PORKST ENTRANCE REACTOR BUILDING - ELEV 683 DOSE RATE IN MR/HR MPC EXCEPT HPCI XNHJ H55KK AIRBORNE IS 1/10 IN STAIRWAYS VII-70

REACTOR BUILDING ELEV 683 DOSE RATE IN MR/HR TIME AREA A AREA B AREA C AREA D AREA E AIRBORNE MPC EXCEPT HPCI 1800 NORMAL NORMAL NOEQGK NORMAL 1'ORMAL 1815

'930 1945

,00 2100 10 i 800 10 i 800 1800 180 1825 2115 9720 9720 1620 1 0 3200 ZfHi 09 00 AIRBORNE IS 1/10 IN STAIRWAYS VII-71

2 X

GD TIR X g~ ORIVK5 CI C RECUR IH5T GAS 0 Q MSIV LC5 HCU ~

RECIRC IlUARI B SLOwKR5 HCU ~

06 Q SRM TRM ORIVE5 X

X 51 5RM IRM ORIVES

+i~o~

ic +c

+ C c+w+

B CRO fLOW MOHORAA.

HOIST AIR SSURE 8

K$ 5 SWITCHGKAR E 55 SWITCHGKAR REACTOR BUILDING - ELEV 719 DOSE RATE IN MR/HR MPC EXCEPT HPCZ

~l TFRJ TEE

.RJYI5 AIRBORNE IS 1/10 IN STAIRWAYS VII-72

REACTOR BUILDING ELEV 719 DOSE RATE IN MR/HR

, TIME AREA A AREA B AREA C AREA D AREA E AIRBORNE MPC EXCEPT HPCI 1800 NORMAL NO L 'ORMAL NO NORMAL NORMAL 1815 1930 1945 00 2100 10,800 14, 00 1800 10i800 180 1825 211 9700 13, 000 1620 9 20 1 0 3200 0,

AIRBORNE IS 1/10 IN STAIRWAYS VII-73

CHILLER Clh fh WA CDIKI WATER CNC.

C7 C3 O DACKWA5H MK cF CIKLLED WATER RECCVNO HILLER TANK B

OI PVAE 5 Qu H T EXCH. NIT RDGEH ACCUAKA.ATDR 5 THI5 u x 10 LEVEL OJ 52 x,.54 u) 08 A RWCU 5LC TANK REGEH c o;,-

~SLC RWCU NIT REGEN 09 B E 55 5WITCHGEAR E 5 5 5WITCHGEAR REPAS RDOA Aa] A W p, REACTOR BUILDING ELEV 7i9 DOSE RATE IN MR/HR MPC EXCEPT HPCI AIRBORNE IS 1/10 IN STAIRWAYS VII 74'

REACTOR BUILDING ELEV 749 DOSE RATE IN MR/HR MPC EXCEPT HPCI 18 1845 1900 1915 2015 2030 2045 30 1 200 600 1 0 2145 200 100 6030 2200 225 75 7400 AIRBORNE IS 1/10 IN STAIRWAYS (1) FROM REACTOR BUILDING AIRBORNE VII-75

SAMPLE A

STATION'l lese r.one 5 5.

~

0

~Cv 4era g

Jltlt PeeP Cm 8

@~I he> CO+ D 7 C.

ca~tv pg vocal.

Z S~

CION'A4 C

2 4et CI0 Cr IZ Cr.ec z-r i3 ~v. ~p g WC V /ps

'ri 5 i4- g>t REACTOR BUILDING - ELEV 779 DOSE RATE IN MR/HR MPC EXCEPT HPCI AIRBORNE IS 1/10 IN STAIRWAYS , VII-76

REACTOR BUILDING ELEV 779 DOSE RATE IN MR/HR MPC EXCEPT HPCI 1<KG 1845 1900 1915 2015 2030 2045 30 30 600 2145 200 200 6030 2200 225 225 7400 AIRBORNE IS 1/10 IN STAIRWAYS VXI-77

42 xe t ~

46 ]3 RRCCW I

RWCV i- I 15 HO TK FILTERS X ON 199 ON 199' A X N

FL'AL PLOL x 47 5'TEAM ORIER 5

REACTOR SEPERATCR WELl. POOL REFUELINO PLATFORM i5 RAR.5 Dl 4

C 4 FUEL'ASE STORA X

14 RPV HE AO STORAGE b WASHOOWN REACTOR BUILDING - ELEV 818 DOSE RATE ZN MR/HR MPC EXCEPT HPCI AIRBORNE ZS 1/10 ZN STAIRWAYS VII-78

REACTOR BUILDING ELEV 818 DOSE RATE IN MR/HR 0

MPC I EXCEPT HPCI FK 1845 1900 1915 2015 2030 2045 30 600 2145 200 6030 2200 225 7400 AIRBORNE IS 1/10 IN STAIRWAYS VII-79

SECTION V I I - RADIOLOGICAL CONDITIONS PART H - PASS SAMPLE INFORMATION VII-80

PASS REACTOR WATER LARGE VOLUME LIQUID SAMPLE DATA 20 30 21:00 21:30 22:00 Time to to to to 21:00 21:30 22 00 22:30 Sample Station Steps: B.1.35 to B.l.52 740 681 607 548 RE-507 Monitor mR/hr Sample Line Dose RE-664 Monitor mR/hr 380000 349600 311600 281200 Sample: No Shield Contact (2 inches) mR/hr 490000 450800 401800 362600 6 inches mR/hr 80000 73600 65600 59200 18 inches mR/hr 10000 9200 8200 7400 36 inches mR/hr 2600 2392 2132 1924 Sample: In Cask Contact (2 inches) mR/hr 163 150 134 121 6 inches mR/hr 27 25 22 20 18 inches mR/hr 3 3 3 2 36 inches mR/hr 1 1 1 1 VII-82

PASS REACTOR WATER SMALL VOLUME LIQUID SAMPLE DATA 20:30 21: 00 21:30 22:00 Time to to to to 21: 00 21:30 22:00 22:30 Sample Station Steps: B.1.35 to B.1.52 740 681 607 548

" RE-507 Monitor mR/hr Sample Line Dose RE-664 Monitor mR/hr 380000 349600 311600 ,281200 Sample: No Shield Contact (2 inches) mR/hr 4900 4508 4018 3626 6 inches mR/hr 800 736 656 592 18 inches mR/hr 100 92 82 74 36 inches mR/hr 26 24 21 19 Sample: In Cask Contact (2 inches) mR/hr 131 120 107 97 6 inches mR/hr 21 20 17 16 18 inches mR/hr 3 2 2 2 36 inches mR/hr 1 1 1 1 VXI-81

SECTION VIII MESSAGE INFORMATION SHEETS

IS No. 1 Time: 1500 MESSAGE INFORMATION SHEET NE EFO Operations Personnel in Control Room MESSAGE FROM: Control Room Referee LOCATION: Training Center Simulator.

MESSAGE: "THIS IS A DRILL." The Initial Conditions of the plant which is the material under the tab of INITIAL CONDITION SECTION VI of the exercise manual. "THIS IS A DRILL."

FOR REFEREE USE ONLY REFEREE NOTES: This material provides the initial conditions of the plant for the participants. Included in this section are the Daily Operating Reports, previous logs and turnover sheets, and Station Priority List.

EXPECTED ACTIONS: The Operators will process the information as a normal shift briefing. After the classroom briefing the Operators will enter the simulator control room and start a walkdown of the control boards to familiarize themselves with the plant conditions.

VIII-2

IS No. 2 Time: 1500 MESSAGE INFORMATION SHEET MESSAGE FOR'hone Company Personnel MESSAGE FROM: Lead Referee LOCATION: S&A phone room and Simulator Control Room MESSAGE: "THIS IS A DRILL." S&A phone room telephone number - 3999. Hook up the Exercise communications equipment in the S&A phone room and the simulator control room, both the page and the telephones.

Ensure the NRC red phone is hooked up and the plant radio is activated in the simulator control room. "THIS IS A DRILL."

FOR REFEREE USE ONLY REFEREE NOTES: The communications equipment needs to be set up prior to the start of the exercise.

EXPECTED ACTIONS: The systems will be checked out prior to the start of the exercise.

VIII-3

IS No. 3 Time: 1500 MESSAGE INFORMATION SHEET MESSAGE FOR: Simulator Instructor MESSAGE FROM: Referee Manual LOCATION: Simulator Control Room MESSAGE: "THIS IS A DRILL." Initialize simulator to IC 8125. The following files are included in the IC:

RH.91NRC - Initial Conditions RH.RADl - SPDS and Containment Rad Initial Conditions RH.PMS65,66,67 - Initial ARM Data RH.WE3. 1 - Initial Weather Conditions "THIS IS A DRILL" FOR REFEREE USE ONLY REFEREE NOTES: The IC sets the initial conditions supported by the annunciator, operator logs, turnover sheets, etc.

EXPECTED ACTIONS: Check the alarms against the annunciator log, check equipment status of sim versus status sheets, verify SPDS rad points active, verify weather conditions per Radiological section, verify ARMs are active and Unit 2 electrical line up.

IS No. 4 Time: 1500 MESSAGE INFORMATION SHEET MESSAGE FOR: Control Room and Onsite Personnel MESSAGE FROM: Operations in the plant Control Room LOCATION: Control Room MESSAGE: "THIS IS A DRILL." The 1991 NRC GRADED FULL SCALE EXERCISE has begun. All exercise communications shall begin with "This is a Drill" and end with "This is a Drill." Line 3 of the plant page system is to be used for the exercise. Exercise Referees please mark the time as "THIS IS A DRILL."

REPEAT ABOVE MESSAGE.

FOR REFEREE USE ONLY REFEREE NOTES: This message is to be passed over the PA system by Operations to note the beginning of the exercise.

EXPECTED ACTIONS: Message to be announced over plant page system on line 3.

The message shall be announced from the actual Control Room.

VIII-5

IS No. 5 Time: 1530 MESSAGE INFORMATION SHEET EE AE Operations Control Room MfSSAGE FROM: Simulator Instructor LOCATION: Simulated Control Room MfSSAGE: "THIS IS A DRILL." The "SEISMIC MONITOR SYSTEM TRIGGERED" alarm is brought in by depressing the prearranged function button.

"THIS IS A DRILL "

FOR REFEREE USE ONLY RfFfREE NOTES: The alarm is to simulate an earthquake event in New York state. The main control room alarm requires the operators to check the seismic monitoring back panel.

EXPECTED ACTIONS: The Plant Control Operator will acknowledge the main control panel alarm and go to the seismic monitoring back panel to determine the magnitude of the event. The information on the back panel will indicate the need to make an Emergency Classification at the UNUSUAL EVENT level.

The alarm response procedure will direct the operators to ON-000-002 NATURAL PHENOMENA, which has the operator review the printer output of the Seismic Monitoring panel. The printout determines the type of event. In this case the event will be less than the Operating Basis Earthquake because ther e will be no asterisk on the right column of the printout. See the attached simulated printout which will be presented to the operators.

FREQUENCY VALUE SETPOINT 3.8 .07 .05 3.6 .05 .05 3.4 .06 .05 3.2 .05 .05 3.0 .06 .05 2.8 .06 .05 2.6 .08 .05 2.4 .07 .05 2.2 .05 .05 2.0 .05 .05 1.9 .04 .05 1.8 .04 .05 1.7 .06 .05 1.6 .06 .05 1.5 .05 .04 1.4 .03 .04 1.3 .04 .04 1.2 .03 .04 1.1 .03 .03 1.0 .06 .03 CHANNEL 1 WT-15701 CONT. FND 000 00 30 40 FOOFF12 000 05 36 40 FOOFF12 DIRECT - 20%

VIII-7

ON"000"002 Revi sion 7 Page 6 of 12 CHECKED

. 3.4.6 At 510" (525'8") an aaaputar pafnt.VIL01, PREPARE far a loss of Rive~ Water Makeup in accordance with ON-009-001.

NOTE: Equipment should be de"energized per d1rection of Shift Superv1sion. Plant can be operated at 100% power for -5 hours without R1ver Water Makeup.

3.5 At Seism1c Mon1tor1ng Panel QC696, DETERMINE type of event which occurred by reviewing output of printer and seismic status lights.

Channel output occurs automatically when earthquake occurs. Following listing 1dentifies types of events which could occur:

3.5.1 Greater than or equal to Safe Shutdown Earthquake (SSE)-

two asterisks on right column of pr1ntout, PROCEED to section 3.6.

3.5.2 Greater than or equal to Operating Basis Earthquake (OBE)-

one asterisk on r1ght column of printout, PROCEED to sect1on 3.7.

3.5.3 Less than Operating Basis Earthquake - no aster1sk on right column of pr1ntout, PROCEED to section 3.8.

3.5.4 Seismic Monitor1ng System Malfunction, PROCEED to section 3.9.

3.6 If earthquake occur~ed greater than or equal to a SSE (two asterisks on right column of pr1ntout), COMMENCE SHUTDOWN 1n accordance with general operating procedures and PERFORM following:

3.6.1 PLACE Plant in "SITE EMERGENCY" status and implement EP-IP-00? notifications. (EP-PS-126 Control Room Communicator when issued).

3.6.2 MONITOR plant for indicat1on of leaks by observing sump level indicat1on,. tank level 1nd1cat1ons, and makeup water flow increases.

3.6.3 MAKE surveys for possible damage in accessible areas (espec1ally concrete).

3.6.4 TEST RUN 01esel Generators fn accordance with SO"024-001.

C..r '4

QN-000"002 Revision 7 Page 8 of 12 CHECKEO 3.7 ' RELOAO blank/rewound cassettes in case of subsequent shock waves.

3.7.9 CONTACT agencies listed on Attachment A for information regarding event.

3.7.10 NOTIFY MC to perform SI-099-301 and SI-099-308 within 5 days afte~ seismic event.

..",.23XS 3.8 If earthquake less than OBE has been verified by actual tremor or verbally from one of geological ]abs, PERFORM following:

3.8.1 PlACE Plant in "UNUSUAL EVENT" status and implement EP-IP-002 notifications. {EP"PS-126 Control Room Communicator when issued).

3.8.2 'HECK for lndlcat1on of leaks by observ1ng sump level 1ndlcatlons, tank level 1nd1catl one, and makeup water flow increase".

3.8.3 NAKE surveys for possible damage in accessible areas (especially concrete).

3.8.4 TEST RUN Oiesel Generators in accordance with S0-024-001.

3.8.5 TEST RUN Oiesel Fire Pump in accordance with SO-013-001.

3.8.6 PLAYBACK seismic data in accordance with OP-099-002 to make hard copy which can be transmitted to NPE Civil Group for evaluation.

3.8.7 COLLECT and FORWARO information from cassettes and other seismic monitoring system instrumentation to NPE Civil Group for evaluation.

3.8.8 RELOAO blank/rewound cassettes in case of subsequent shock waves.

3.8.9 NOTIFY IKC to perform SI-099-301 and SI-099-308 within 5 days of seismic event.

ON-000"002 Rev)s)on 7 Page 9 of 12 3.9 If event determined to be inadvertent or nonvfbratfonally induced, cause shall be determined and problem shaTl be corrected. After problem rect) f)ed, PERFORM SI-099-201 on seismic monitoring system to ensure operability.

4.0 REFERENCES

4.1 FSAR Section 3.3.W)nd and Tornado Loadfngs 4.2 FSAR Sect)on 3.4 Water Level (Flood) Oesfgn 4.3 FSAR Sect)on 3.5 Mfss)'le Projection 4.4 FSAR Section 3.7 Seismic Oesfgn 4.5 10CFR100 Appendix A - Seismic and Geological Siting Criteria For Nuclear Power Plants.

(') 4.6 NUMARC 87-00 Station Blackout, Initiatives 4.7 EP"IP-001 Emergency Classfffcatfons 4.8 EP-IP"002 Emergency Management Notfffcatfons 4.9 ON"009"001 Loss of Makeup Water Supply 4.10 ON-104-001 Unit 1 Response to Loss of All Offsfte Power 4.11 ON-204-001 Unit 2 Response to Loss of All Offsfte Power 4.12 OP-099-002 Seismic Monitoring System 4.13 SE-000-015 Settlement Monitoring of the ESSW Pumphouse

4. 14 SI-099-201 Semi Annual Functional Test of Strong Motion Seismic Instruments VT-05701, VT"15701, VT-25701, VT-05702, VT-15702, VT-15703 and VRS-05703 4.15 SI-099-301 18 Month Calibration of Strong Motion Seismic Instruments VT-05701, VT-15701, VT-25701, VR-05701, VR-05702, VT-05702, VT-15702 and VT-15703 4'.16 SI-099-308 18 Month Calibration of Peak Recording Accelerographs VR-25701, VR-25702 and VR-25703 4.17 S0-013"001 Fire Protection System Monthly Operability 4.18 SO-024-001 0)esel Generator Monthly Operability

ON'-000-002 Revision 7 Page ll of 12 The four Oiesel Generator sets are housed in individual water tight compartments within the Oiesel Generator Building. Floor drain 11ne branches from each of these compartments are equ1pped with check valves to prevent backflooding from the common sump.

The ESSW Pumphouse is divided into two redundant compartments.

Flood1ng from internal leakage would, only affect one of the redundant pump sets. The control and electrical panels are mounted on min1mum 4 inch high concrete pads or structural supports. Operating floor open1ngs allow dra1nage of any leakage to the ESSW Pump suct1on space below or to a reserve sump space that could be emptied with a portable pump.

5.3 Earthquake 5.3.1 Safe Shutdown Earthquake (SSE)

The Safe Shutdown Earthquake defines that earthquake which has commonly been referred to as the Oes1gn Basis Earthquake (OBE).

The OBE 1s that earthquake wh1ch 1s based upon an evaluation of the maximum earthquake potential considering the regional and local geology and seismology and specific characteristics of local subsurface material. It is that earthquake which produces the maximum vibratory ground motion for which certain structures, systems, and components are designed to remain functional. These structures, systems, and components are those necessary to assure:

a. The integr1ty of the reacto~ coolant pressure boundary.

b. The capability to shutdown the reactor and maintain it in a safe shutdown condition, or

c. The capab1lity to prevent or m1tigate the consequences of accidents which could result in potential offsfte exposures comparable to the guideline exposures.

5.3.2 Operating Basis Earthquake (OBE)

The OBE is that earthquake which, considering the regional and local geology and seismology and specific characteristics of local subsurface material, could reasonably be expected to affect the plant site during the operating life of the plant; 1t is that earthquake which produces the v1bratory growth motion for which those features of the nuclear power plant necessary for cont1nued operation without undue r1sk to the health and safety of the public are designed to remain funct1onal.

Attachment A QN-000-002 Revision 7 Page 12 of 12 SEISMIC EVENT INFORMATION National Earthquake Information Center (24 hrs)

Golden, Colorado 303-236-1500 PA Bureau of Topographic 2 Geologic Survey 717"787-5828 717-783-7257 Penn State University (AU) Geosciences Office 814-865-0083 814-865-6711 Oelaware Geological Survey 302-451-8257 Columbia University 914-359-2900 x 643 Primary X 581 or 582 Seismolog Computer Lab Alternate VIII-12 Page 1 of 1

IS No. 6 Time: 1610 MESSAGE INFORMATION SHEET MESSAGE FOR: ASCC Security Controller MESSAGE FROM: Simulated State Police LOCATION: Alternate Security Control Center MESSAGE: "THIS IS A DRILL." This is Sergeant Smith down at the Shickshinny barracks. Wanted to let you know that there is a problem with the bridge over the Susquehanna at Shickshinny due to the earth tremor that we just had. It appears that the bridge will not support vehicle traffic and we are in the process of closing it off.

"THIS IS A DRILL "

FOR REFEREE USE ONLY REFEREE NOTES: The message from the state police is to be passed on to the rest of the emergency organization for use later when an evacuation needs to be initiated.

EXPECTED ACTIONS: The Emergency Director will log the message and pass it on to the duty manager'nd the Operations Coordinator later in the exercise during the turnover process when the TSC is activated.

VIII-13

IS No. 7 Time: 1615 MESSAGE INFORMATION SHEET MESSAGE FOR: Simulator Control Room Operators MESSAGE FROM: Simulator Instructor LOCATION: Simulator Control Room MESSAGE: "THIS IS A DRILL." The Simulator Instructor will initiate the "SEISMIC MONITORING SYSTEM TRIGGERED" alarm. "THIS IS A DRILL."

FOR REFEREE USE ONLY

~EKE The Operators will acknowledge the main control room alarm and go to the back panel to determine the magnitude of the earth tremor. The indication that is given to the operator is that of an OBE or Operating Basis Earthquake. The operator will be given a printer output from the seismic monitoring panel (attached) that has one asterisk indicating an OBE.

Mock telephone numbers are provided for offsite agencies to be called in the event of an earth quake.

EXPECTED ACTIONS: The operators will follow their procedures and initiate walkdowns of the plant looking for equipment damage, start the emergency diesel generators and fire pump, initiate a controlled plant shutdown, and declare an ALERT. The operators will also be contacting one of the agencies listed in the procedure to confirm the event.

Declaration of the ALERT will require activation of the TSC.

VIII-14

FREQUENCY VALUE SETPOINT 3.8 .07 .10*

3.6 .12 10*

3.4 .11 1P*

3.2 .09 10*

3.0 .11 1P*

2.8 .12 10*

2.6 .11 ]p*

2.4 .18 .10*

2.2 .15 1P*

2.0 .13 .09*

1.9 .13 10*

1.8 .14 11*

1.7 .13 ll*

1.6 .12 ll*

1.5 .12 .12*

1.4 .11 10*

1.3 .11 ll*

1,2 .16 .12*

1.1 .13 11*

1.0 .12 ll*

CHANNEL 1 WT-15701 CONT. FND 000 00 30 40 FOOFF12 000 05 36 40 FOOFF12 DIRECT - 20%

VIII-15

ON"000-002 Revision 7 Page 6 of 12 CHECKED 3.4.6 At 510" (525'8") on computer point 3/IL01, PREPARE for a loss of River Water Makeup in accordance w1th ON-009-001.

NOTE: Equipment should be de-energized per d1rection of Shift Supervision. Plant can be operated at l0% power for -5 hours without River Water Makeup.

3.5 At Seism1c Monitoring Panel QC696, DETERMINE type of event which occurred by review1ng output of printer and seism1c status lights.

Channel output occurs automatica) ly when earthquake occurs. Following listing 1dent1fies types of events which could occur:

3.5.1 Greater than or equal to Safe Shutdown Earthquake (SSE)-

two asterisks on right column of printout, PROCEED to sect1on 3.6.

3.5.2 Greater than or equal to Operating Bas1s Earthquake (OBE)-

one asterisk on right column of printout, PROCEED to section 3.7.

3.5.3 Less than Operat1ng Basis Earthquake - no asterisk on right column of printout, PROCEED to section 3.8.

3.5.4 'e1smic Monitoring System Malfunct1on, PROCEED to sect1on 3.9.

3.6 lf earthquake occurred greater than or equal to a SSE (two asterisks on r1ght column of printout), COMMENCE SHUTDOWN 1n accordance with general operating procedures and PERFORM following:

3.6.l PLACE Plant in "SlTE EMERGENCY" status and implement EP-IP-002 not1f1cat1ons. (EP-PS-126 Control Room Communicator when 1ssued).

3.6.2 MONDOR plant for 1nd1cation of leaks by observing sump level indicat1on, tank level 1ndicat1ons, and makeup water flow increases.

3.6.3 MAKE surveys for poss1ble damage in access1ble areas (espec1ally concrete).

3.6.4 TEST RUN Diesel Generators 1n accordance with SO-024-001.

ON-000"002 Revision 7 Page 7 of 12 CHECKED 3.6.5 TEST RUN Of esel Ff re Pump 1 n accordance wf th S0-013-001.

3.6.6 PLAYBACK seism1c data fn accordance with OP-099-002 to make hard copy which can be transmitted to NPE Civil Group for evaluation.

3.6.7 COLLECT and FORWARD fnformat1on from cassettes and other se1smfc monftor1ng system 1nstrumentatfon to NPE Civfl Group for evaluation.

3.6.8 RELOAD blank/rewound cassettes fn case of subsequent shock waves.

3.6.9 CONTACT agencies listed on Attachment A for 1nformat1on regard1ng the event.

3.6.10 NOTIFY ICC to perform SI-099-301 and SI-099-308 wfthfn 5 days after seismfc event.

If earthquake occurred greater than or equal to an OBE (one asterisk an right column of pr1ntout), iQMMENCE SHUTDOWN fn accordance w1th general operating procedures and PERFORM follow1ng:

3.7.1 PLACE Plant fn "ALERT"'tatus and implement EP-IP-002 not1ffcatfons. (EP-PS-126 Control Room Communicator when issued).

3.7.2 CHECK for indication of'eaks by observing sump level fndfcatfops, tank level 1nd1cat1ons, and makeup water

.flow increases.

3.7.3 MAKE surveys for poss1ble damage in access1ble areas (especially concrete).

3.7.4 TEST RUN Diesel Generators fn accordance with S0-024-001.

3.7.5 TEST RUN 01esel Fire Pump in accordance with S0-013-001.

3.7.6 PLAYBACK seismic data in accordance with OP-099-002 to make hard copy which can be transmitted to NPE Civf 1 Group for evaluation.

3.7.7 COLLECT and FORWARD information fram cassettes and other seismic monitoring system fnstrumentatfon to NPE Civil Group for 'evaluat1on.

VIXEN-17

ON-000-002 Revision 7 Page 8 of 12 CHECKED 3.7.8 RELOAD blankjrewound cassettes in case of 'subsequent shock waves.

3.7.9 CONTACT agencies listed on Attachment A for information regarding event.

3.7.10 NOTIFY IBC to perform SI"099-301 and SI-099-308 within 5 days after seismic event.

3.8 If earthquake less than OBE has been verified by actual tremor or verbally from one of geological )abs, PERFORM follow1ng:

PLACE Plant in "UNUSUAL EVENT" status and implement EP-IP-002 notifications. (EP-PS-126 Control Room Communicato~ when issued).

3.8.2 CHECK for indicat1on of leaks by observing sump level indicat1ons, tank level indications, and makeup water 1'low increases.

3.8.3 MAKE surveys for possible damage in accessibl~ areas (especially concrete).

3.8.4 TEST RUN Ofesel Generators in accordance with S0-024-001.

3.8.5 TEST RUN Diesel Fire Pump in accordance with SO-013-001.

II 3 '.6 PLAYBACK seismic data in accordance with OP-099-002 to make hard copy wh1ch can be transmitted to NPE Civ11 Group for evaluation.

3.8.7 COLLECT and FORWARD information from cassettes and other seism1c monitor1ng system instrumentation to NPE Civil Group for evaluation.

3.8.8 RELOAD blank/rewound cassettes in case of subsequent shock waves.

3.8.9 NOTIFY ISC tn perfnrfn SI-099-301 and SI-099-308 wfthfn 5 days of seismic event.

VIII-'18

ON'"000-002 Revision 7 Page ll of 12 The four Diesel Generator sets are housed in individual water tight compartments w1th1n the Diesel Generator Building. floor drain line branches from each of these compartments are equ1pped with check valves to prevent backflooding from the common sump.

The ESSM Pumphouse is divided into two redundant compartments.

Flooding from internal leakage would, only afFect one of the redundant pump sets. The control and electrical panels are mounted on minimum 4 inch high concrete pads or structural supports. Operat1ng floor openings allow drainage of any leakage to the ESSM Pump suct1on space below or to a reserve sump space that could be empt1ed with a portable pump.

5.3 Earthquake 5.3.1 Safe Shutdown Earthquake (SSE)

The Safe Shutdown Earthquake defines that earthquake which has commonly been referred to as the Oes1gn Basis Earthquake (OBE).

The OBE is that earthquake which is based upon an evaluation of the maximum earthquake potent1al consider1ng the regional and local geology and se1smology and spec1ftc characteristics of local subsurface material. It is that earthquake wh1ch produces the max1mum vibratory ground motion for which certain structures, systems, and components are designed to remain functional. These structures, systems, and components are those necessary to assure:

a. The integrity of the reactor coolant pressure boundary.

b. The capability to shutdown the reactor and maintain it in a safe shutdown condition, or

c. The capability to prevent or mitigate the consequences of accidents which could result in potent1al offsite exposures comparable to the guideline exposures.

5.3.2 Operating Basis Earthquake (OBE)

The OBE is that earthquake which, considering the regional tm and local geology and seismology and spec1fic characteristics of local subsurface material, could reasonably be expected to

.I affect the plant site during the operating life of the plant; PP) it is that earthquake which produces the vibratory growth motion for which those features oi'he nuclear power plant necessary for continued operation without, undue risk to the health and safety of the public are des1gned to remain funct1onal.

V VIIX-19

IS No. 8 Time: 1620 MESSAGE INFORMATION SHEET MESSAGE FOR: THIS ENTRY WAS DELETED.

MESSAGE FROM:

LOCATION:

MESSAGE:

FOR REFEREE USE ONLY REFEREE NOTES:

EXPECTED ACTIONS:

VI I I-20

IS No. 9 Time: 1620 MESSAGE INFORMATION SHEET MESSAGE FOR: Control Room Communicator MESSAGE FROM: Simulated Off-site Agency LOCATION: Telcon, Control room to Geoscience Office MESSAGE: "THIS IS A DRILL." The actor will be answering questions asked by the Control Room communicator. The actor is simulating one of the locations the operator will call to get seismic event information.

The earth quake information is as follows; the earthquake occurred at 1614 hours0.0187 days 0.448 hours 0.00267 weeks 6.14127e-4 months with the center about 65 miles south west of Albany, New York. The magnitude of the quake appears to be about 5.0 on the Richter Scale. (1.5 is the smallest that can be felt, 4.5 would cause slight damage, 8.5 would be a devastating uake . "THIS IS A DRILL."

FOR REFEREE USE ONLY REFEREE NOTES: The earth quake was of sufficient magnitude to cause minor damage at the plant in portions of the plant that are not seismically designed.

EXPECTED ACTIONS: The operator will pass the information on that he has received from the Geoscience Office.

VIII-21

-IS No. 10 Time: 1625 MESSAGE INFORMATION SHEET MESSAGE FOR: In-plant Team Investigating Steam Tunnel High Temp MESSAGE FROM: India Team Referee LOCATION: Reactor Building Steam Tunnel MESSAGE: "THIS IS A DRILL." Refer to the attached drawing of the steam tunnel for location of the leak. The steam/vapor plume from the leak is not extensive it will extend out a couple of feet from the crack. The extent of the leak is difficult to determine since there is lagging on the pipe. The report to the Control Room should indicate that there is a leak, with no good estimate of amount. "THIS IS A DRILL."

FOR REFEREE USE ONLY REFEREE NOTES: The leak in the feedwater system is to force the operators to consider taking feedwater out of service or being careful not to cause any feedwater transients that would make the leak worse. The leak is also a precursor to a larger problem that will prevent using feedwater for injection into the vessel.

EXPECTED ACTIONS: The in-plant operator will report the findings to the Control Room, who will in turn discuss the options available with the TSC Staff, VIII-22

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page-.. Op .. Page 13 ot 34 coi.

STEAM TUNNEL AREA

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)

~G33-1N605

'. > LS. (6PoF. ~'T) 1.0 PROBABLE CAUSE: r I ~

1..1 Mafn Steam 1fne break frr Reactor

( Qilf elorw on>>>> e0 /pe rc4+)..,.':~.or Turbfne- Bufldfn Pfpe Tunnel 1.2'afn Steam Instrumentatfon lfne. break frr Pfpe Tunnel 1.3 Ventflatfon System malfunctforr 1.4 Turbf~e Bufldfng Pfpe Tunnel P'ortable:

Fan mal Nnctfon 1,

Z.Q OPcRATOR ACTEON:

pprpHrqe i(p<A. g-~>icrefvre i~'occurring in 4oct'or Sviidii gr Tvr6ina 8w'Idi'nq jv~+cl ~cii6s~+>Ih7", +I~<+. ~ I+~H-IH6oS(ITS I $ 0).

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2.9 cfffcrr for ercrerut condenecrhon on Me n Stem 7~nel Coolers.

QHcu~ Trrtbinc'EeeldiircI gym i~ Viicrf/jolt in'eedeircc. ~tg oP-rta-aors 7prCtsr BpiicIiwj HVhC 2.4 Ch%'ct fur ancccesi~ /eekoqc: into. 7urhinc.

8ui4iiig Pipe Tunnrl Suiiip 2.7 or Rcoe~ Sciildiy Pf&ir< filo 'g Miu, f T 6' E Id ~, P~ T Q,7 I ~uRK i'c.PSA- BrcekcrS. Zq9r'enoI 6'l-+f80.

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4.0

REFERENCE:
E-324 Sh 16
4. 2 M1-B21-98(3) 4.3 IOM 305 VXXX-24
IS No. 11 Time: 1625 MESSAGE INFORMATION SHEET MESSAGE FOR: In-Plant Teams Investigating the Plant MESSAGE FROM: In-Plant Team Referees LOCATION: Plant and Site MESSAGE: "THIS IS A DRILL." The operators will find nothing out of the ordinary as they walk down the plant. The only problem noted is the feedwater leak in the Steam Tunnel. "THIS IS A DRILL."
FOR REFEREE USE ONLY REFEREE NOTES: The plant has sustained no damage outside of the feedwater line in the steam tunnel.
EXPECTED ACTIONS: The operators will continue monitoring the plant parameters and doing the required surveillances to prove that all the required equipment is operable.
VIII-25
IS No. 12 Time: 1645 MESSAGE INFORMATION SHEET MESSAGE FOR: Emergency Director MESSAGE FROM: Control Room/TSC Referee LOCATION: TSC/Control Room
~H SSAGE: "THIS IS A DRILL." The classification at the ALERT classification level needs to be made at this time.'he classification is to be made in accordance with the Natural Phenomena of earthquakes.
"THIS IS A DRILL."
FOR REFEREE USE ONLY REFEREE NOTES: The exercise needs to be kept fairly close to the planned time line due to the large number of people involved with the exercise. Plant has sustained no damage outside of the feedwater line in the steam tunnel.
EXPECTED ACTIONS: The operators will continue monitoring the plant parameters and doing the required surveillances to prove that all the required equipment is operable.
VIII-26
IS No. 13 Time: 1700 MESSAGE INFORMATION SHEET I
MESSAGE FOR: Emergency Director MESSAGE FROM: Control Room or. TSC Referee LOCATION: Simulator Control Room or TSC MESSAGE: "THIS IS A DRILL." When the results of the accountability are complete release the people from their accountability stations.
"THIS IS A DRILL."
FOR REFEREE USE ONLY REFEREE NOTES: The release of the people from their accountability stations will allow them to resume their normal plant activities.
EXPECTED ACTIONS: The Emergency Director will announce over the plant page system that the accountability is complete and all people may continue with their normal routine.
VI I 1-27
IS No. 14 Time: 1710 MESSAGE INFORMATION SHEET MESSAGE FOR: In-Plant Teams Investigating the Plant MESSAGE FROM: In-Plant Team Referees LOCATION: Plant and Site MESSAGE: "THIS IS A DRILL." The operators will find nothing out of the ordinary as they walk down the plant. The only problem noted is the feedwater leak in the Steam Tunnel, which has not changed since the last time it was investigated. For additional information concerning the steam tunnel see message sheet 8 8.
"THIS IS A DRILL."
1 FOR REFEREE USE ONLY REFEREE NOTES: The plant has sustained no additional damage. There is no change concerning the feedwater line leak in the steam tunnel.
EXPECTED ACTIONS: The operators will continue monitoring the plant parameters and doing the required surveillances to prove that all the required equipment is operable.
VIII-28
IS No. 15 Time: 1800 MESSAGE INFORMATION SHEET MESSAGE FOR'imulator Control Room Operators MESSAGE FROM: Simulator Instructor LOCATION: Simulator Control Room MESSAGE: "THIS IS A DRILL." The Simulator Instructor will initiate the "SEISMIC MONITORING SYSTEM TRIGGERED" alarm. "THIS IS A DRILL."
FOR REFEREE USE ONLY REFEREE NOTES: The Operators will acknowledge the main control room alarm and go to the back panel to determine the magnitude of the earth tremor. The indication that is given to the operator is that of an SSE or Safe Shutdown Earthquake. The operator will be given a printer output from the seismic monitoring panel (attached) that has two asterisks indicating an SSE.
Hock telephone numbers are provided for offsite agencies to be called in the event of an earth quake.
EXPECTED ACTIONS: The operators will follow their procedures and initiate walkdowns of the plant looking for equipment damage, start the emergency diesel generators and firepump, initiate a controlled plant shutdown and declare a SITE AREA EHERGENCY. The operators will also be contacting one of the agencies listed in the procedure to confirm the event.
Declaration of the SITE AREA EMERGENCY will require activation of the EOF.
VIII-29
FRE(UENCY VALUE SETPOINT 3.8 .55 2 3**
3.6 .58 23**
3.4 .53 23**
3.2 .40 23**
3.0 .32 2 3**
2.8 .36 2 3**
2.6 .37 2 3**
2.4 .39 23**
2.2 .34 '2 3**
2.0 .28 2 3**
1.9 .25 2 3**
1.8 .27 2 3**
1.7 .19 .11*
1.6 .29 2P**
1.5 .29 2P**
1.4 .53 2P**
1.3 .60 19**
1.2 .43 18**
1.1 .26 18**
1.0 .37 18**
CHANNEL 1 WT-15701 CONT. FND 000 00 30 40 FOOFF12 000 05 36 40 FOOFF12 DIRECT - 20%
VIII-30
ON-000"002 Revision 7 Page 6 of 12 CHECKED
. 3.4.6 At 510" (525'8") on computer point VIL01, PREPARE for a loss of Rfver Water Makeup fn accordance wfth ON-009-001.
NOTE: Equipment should be de-energized per d1rectfon of Shift Supervision. Plant can be operated at 100% power for -5 hours without River Water Makeup.
3.5 At Se1sm1c Mon1torfng Panel QC696, DETERMINE type of event which occurred by reviewing output of printer and seismic status lights.
Channel output occurs automatica) ly when earthquake occurs. Following 11sting identifies types of events which could occur:
3.5.1 Greater than or equal to Safe Shutdown Earthquake (SSE)-
two aster1sks on right column of printout, PROCEED to section 3.6.
3.5.2 Greater than or equal to Operat1ng Bas1s Earthquake (OBE)-
one asterisk on right column of printout, PROCEED to sectfon 3.7.
3.5.3 Less than Operatfng Basis Earthquake - no asterisk on right column of printout, PROCEED to section 3.8.
3.5.4 Seismic Mon1tor1ng System Malfunct1on, PROCEED to sectfon 3.9.
3.6 If earthquake occurred greater than or equal to a SSE (two asterisks on rfght column of printout), COMMENCE SHUTDOWN 1n accordance w1th general operating procedures and PERFORM follow1ng:
3.6.1 PLACE Plant fn "SITE EMERGENCY" status and implement EP"IP-002 notfffcat1ons. {EP-PS-126 Control Room Communicator when fssued).
3.6.2 MONITOR plant for 1nd1catfon of leaks by observing sump level indication,.tank level indications, and makeup water flow increases.
3.6.3 MAKE surveys for possible damage fn accessible areas (espec1al ly concrete) .
3.6.4 TEST RUN Ofesel Generators fn accordance with SO-024-001.
VIII-31
ON-000"002 Revision 7 Page 7 of 12 CHECKED 3.6.5 TEST RUN Diesel Fire Pump in accordance w1th S0-013-001.
3.6.6 PLAYBACK se1smic data in accordance with OP-099-002 to make hard copy which can be transmitted to NPE Civil Group for evaluation.
3.6.7 COLLECT and FORWARD information from cassettes and other se1sm1c mon1tor1ng system 1nstrumentation to NPE Civil Group for evaluation.
3.6.8 RELOAD b'lank/rewound cassettes in case of subsequent shock waves.
3.6.9 CONTACT agencies listed on Attachment A for information regarding the event.
3.6.10 NOTIFY IEC to 'perform SI-099-301 and SI-099-308 within 5 days after seismic event.
3.7 If earthquake occurred greater than or equal to an OBE (one asterisk on right column of printout), COMMENCE SHUTDOWN in accordance with general operating procedures and PERFORM following:
3.7. I PLACE Plant in "ALERT"'tatus and 1mplement EP-IP-002 notif1cations. (EP-PS-126 Control Room Commun1cator when issued).
3.7.2 CHECK for indication of leaks by observing sump level indicatiops, tank level indications, and makeup water flow increases.
3.7.3 MAKE surveys for possible damage in accessible areas (especially concrete).
3.7.4 TEST RUN Diesel Generators in accordance with S0-024-001.
3.7.5 TEST RUN Diesel Fire Pump in accordance with SO"013-001.
3.7.6 PLAYBACK seism1c data in accordance w1th OP-099-002 to make hard copy which can be transmitted to NPE Civ11 Group for evaluat1on.
3.7.7 COLLECT and FORWARD informat1on from cassettes and other seismic monitoring system instrumentation to NPE Civil Group for evaluation.
VIII-32
ON'-000-002 Revision 7 Page L1 of 12 The four Diesel Generator sets are housed in individual water tight compartments with1n the Diesel Generator Bui ld1ng. Floor drain line branches from each of these compartments are equipped with check valves to prevent backflooding from the common sump.
The ESSW Pumphouse is divided into'wo redundant compartments.
Flooding from internal leakage would, only affect one of the redundant pump sets. The control and electrical panels are mounted on minimum 4 inch high concrete pads or structural supports. Operating floor openings allow drainage of any leakage to the ESSW Pump suct1on space below or to a reserve sump space that could be emptied with a portable pump.
5.3 Earthquake 5.3.1 Safe Shutdown Earthquake (SSE)
The Safe Shutdown Earthquake defines that earthquake which has commonly been referred to as the Design Bas1s Earthquake (OBE).
The OBE is that earthquake which fs based upon an evaluation of the maximum earthquake potential consider1ng the regional and local geology and seismology and specific characterist1cs of local subsurface material. It is that earthquake which produces the maximum vibratory ground motion for which certain structures, systems, and components are designed to remain functional. These structures, systems, and components are those necessary to assure:
a. The integrity of the reactor coolant pressure boundary.
b. The capability to shutdown the reactor and maintain it in a safe shutdown condition, or
c. The capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to the guideline exposures.
5.3.2 Operating Basis Earthquake (OBE)
The 08E is that earthquake which, considering the regional and local geology and seismology and specific characteristics of local subsurface material, could reasonably be expected to affect the plant site during the operat1ng life of the plant; it is that earthquake which produces the vibratory growth motion for which those features of the nuclear power plant necessary for continued operation without undue risk to the health and safety of the public are designed to remain functional.
VIII-33
IS No. 16 Time: 1800 MESSAGE INFORMATION SHEET MESSAGE FOR: Simulator Control Room Operators MESSAGE FROM: Simulator Instructor LOCATION: Simulator Control Room MESSAGE: "THIS IS A DRILL." The Simulator Instructor will initiate the file RH.HPISO. "THIS IS A DRILL."
REFEREE USE ONLY REFEREE NOTES'OR This file simulates a line break inside the HPCI room as a result of the seismic event. The room isolation logic will isolate the main steam isolation valve. The valves will indicate closed, but in fact are leaking by to HPCI room.
The operators are in the middle of a plant shutdown and will probably continue on with the shutdown.
EXPECTED ACTIONS: The operators will follow their procedures and closely monitor the radiological instruments such as the Stack Monitoring, and Area Radiation Monitors. The plant will continue with the shutdown and declare a SITE AREA EMERGENCY based either on the seismic event or the broken steam line.
Declaration of the SITE AREA EMERGENCY will require activation of the EOF.
VIII-34
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VIII-35
IS No. 17 Time: 1805 MESSAGE INFORMATION SHEET MESSAGE FOR: Operator Investigating the break in the HPCI Room MESSAGE FROM: In-Plant Team Referee LOCATION: Reactor Building MESSAGE: "THIS IS A DRILL." The following information will be given to the investigating team when they have demonstrate the ability to obta'in the information. Any information that would be provided by the senses, are to be provided. (If it was supposed to be very hot and humid, it would be felt by the individual investigating.)
The dose rates inside the Reactor Building are normal, except in the HPCI room. See the Rad map for HPCI room dose rates.
Reaching the HPCI Room door, the door will be warm with the sound of running water on the other side of the door. The running water is due to the fire protection system being started automatically.
Inside the room the dose rates are elevated, the room is warm and the fire protection system has operated. The deluge of the fire protection was due to a steam leak in the room.
The simulated steam leak is located at the point where the main steam line drain taps off of the steam line. The break is a complete shear of the drain line. The drain line is still leaking at a rate of 0. 1 GPM, this is the leakage through the closed HPCI steam isolation valves. "THIS IS A DRILL."
FOR REFEREE USE ONLY REFEREE NOTES: Ensure the any information given out is "earned" by the individual investigating. The leakage after the HPCI steam line isolation valves go closed to the HPCI room is minimal.
There is no fuel damage so the release from the building will be minimal. The leak rate from the broken pipe after the isolation valves are closed will be approximately . 1 GPM As long as the fire protection system is in service, fire protection water will accumulate on the HPCI Room floor at the rate of 2 inches an hour, unless the operators open the room drain.
EXPECTED ACTIONS: The investigating individual will be checking their accumulated dose as they enter the Reactor Building.
The individual will follow the directions provided at the TSC briefing and will report back to the TSC all that is determined.
VIII-36
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IS No. 18 Time: 1805 MESSAGE INFORMATION SHEET MESSAGE FOR: Pump House Operator MESSAGE FROM: In-Plant Team Referee LOCATION: Circ Water Pump House MESSAGE: "THIS IS A DRILL." The Motor driven fire pump is running and any attempts to shut it down cause it to restart. The level in the Clarified Water Tank is decreasing indicating flow in the system.
"THIS IS A DRILL. "
FOR REFEREE USE ONLY REFEREE NOTES: The Fire Pump will remain running and not be able to be shut down until the fire protection to the HPCI room is isolated.
EXPECTED ACTIONS: The operator will contact the Control Room and report that he is unable to shut down the fire pump that it continues to run. He will also pass on that the Clarified Water tank level is decreasing and ask if the suction should be shifted to the cooling tower.
VIII-38
IS No. 18A Time: 1805 MESSAGE INFORMATION SHEET MESSAGE FOR'ontrol Room Operators MESSAGE FROM: Simulator Instructor LOCATION: Simulator Control Room MESSAGE: "THIS IS A DRILL." The Simulator Instructor to initiate the Steam Leak High Temperature alarm (OVR A12C03) in the control room.
"THIS IS A DRILL."
FOR REFEREE USE ONLY REFEREE NOTES: The alarm is to indicate a feed water leak in the Reactor Building steam tunnel. The leak is at the common header to the feedwater cleanup T. The leak is minor in nature and will not affect the overall operation of the plant.
The referee who goes with the operator to investigate the alarm needs to pay attention to feedwater temperature. If the turbine is taken off the line the feedwater temperature will drop.
See the attached drawing for the leak location. The leak is not great so there will not be a large steam/vapor plume associated with the leak.
Refer to the attached alarm response procedure for the expected operator actions.
EXPECTED ACTIONS: The in-plant operator will notify the Control Room of his findings and wait for instructions. It is not expected that the Control Room will have the operator do any further investigations.
VIII-39
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VIII-40
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( <4'If 4E/4EtiFE OFE ~ 20 CIP 666 I44+). ">'~or 7urbfne Bufldfn Pf e Tunnel 1.2'afn Steam Enstrumentatfon lfne break fa Pfpe Tunnel 1.3 1.4 Ventflatfon System mal tunctforr ',
Turbf ~e Bufldfng Pf pe Tunnel P'ortable.
Fan mal'1'unctfon Z.Q OPERATOR ACTION:
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REFERENCE:
4.1 E-324 Sh 16
4. 2 M1-B21-98(3) 4.3 IOM 305 VIII-41
IS No. 19 Time: 1810 MESSAGE INFORHATION SHEET MESSAGE FOR: Control Room Operators MESSAGE FROH: Simulator Instructor LOCATION: Simulator Control Room MESSAGE: "THIS IS A DRILL." The Simulator Instructor to bring in the Reactor Building Sump high level alarm in the control room. "THIS IS A DRILL."
FOR REFEREE USE ONLY REFEREE NOTES: The leak in the feedwater system is in the Reactor Building Steam Tunnel. The drains for the Steam Tunnel are directed to the Reactor Building sump. Leakage into the Steam Tunnel will show up in the Reactor Building sump.
EXPECTED ACTIONS: The Control Room Operator will acknowledge the alarm on the main control panel and then check the back panel.
The back panel will indicate a problem with the Reactor Building sump and an operator will be dispatched to check it out.
VIII-42
IS No. 19A Time: 1815 MESSAGE INFORMATION SHEET MESSAGE FOR: Control Room Operators IP I
~*
MESSAGE FROM: Simulator Instructor LOCATION: Simulator Control Room MESSAGE: "THIS IS A DRILL." The Simulator Instructor to initiate the FILE RH.WE3.2 which is the meteorological conditions around the plant as indicated on PMS Format ¹47. "THIS IS A DRILL."
FOR REFEREE USE ONLY REFEREE NOTES: There is no simulator model which, drives the various computer points or meter indications for the weather conditions around the site. The weather conditions are required by the control room during an emergency exercise to plot plume travel, direct evacuation and response routes and protect site personnel not evacuated.
The rad levels in the plant for the in-plant team referees are provided on the building radiological maps in section VII of the Referee Manual.
EXPECTED ACTIONS: The control room operators will monitor the weather conditions as indicated on meters and computer displays and take appropriate action as dictated by plume travel and resultant doses/contamination.
VIII-43
IS No. 20 Time: 1820 MESSAGE INFORMATION SHEET MESSAGE FOR: Chemistry Technician MESSAGE FROM: Chemistry Referee LOCATION: Chemistry Lab MESSAGE: "THIS IS A DRILL." Provide the Chemist with normal reactor coolant sample results. "THIS IS A DRILL."
FOR REFEREE USE ONLY REFEREE NOTES: The coolant sample is normal at this time since there is no fuel damage. The fuel damage occurs later after the core is uncovered for a period of time.
EXPECTED ACTIONS: The Chemist will be asked to get a normal reactor coolant sample from the Reactor Building Sample Station. The Chemist will use normal operating procedures to obtain the sample.
VIII-44
IS No. 21 Time: 1830 MESSAGE INFORMATION SHEET MESSAGE FOR: Emergency Director MESSAGE FROM: Control Room/TSC Referee LOCATION: TSC/Control Room MESSAGE: "THIS IS A DRILL." The classification at the SITE AREA EMERGENCY level needs to be made at this time. The classification is to be made in accordance with the Natural Phenomena of earthquakes OR Steam Line Break. "THIS IS A DRILL."
FOR REFEREE USE ONLY REFEREE NOTES: The exercise needs to be kept fairly close to the planned time line due to the large number of people involved with the exercise.
EXPECTED ACTIONS: The Emergency Director will make the SITE AREA EMERGENCY classification and direct the communicator to begin upgrade notifications, site evacuation, activation of the EOF and combat the emergency.
VIII-45
IS No. 21A Time: 1945 MESSAGE INFORMATION SHEET MESSAGE FOR: Control Room Operators MESSAGE FROM: Simulator Instructor LOCATION: Simulator Control Room MESSAGE: "THIS IS A DRILL." The Simulator Instructor to initiate the FILE RH.WE3.3 which is the meteorological conditions around the plant as indicated on PMS Format 847. "THIS IS A DRILL."
FOR REFEREE USE ONLY REFEREE NOTES: There is no simulator model which drives the various computer points or meter indications for the weather conditions around the site. The weather conditions are required by the control room during an emergency exercise to plot plume travel, direct evacuation and response routes and protect site personnel not evacuated.
The rad levels in the plant for the in-plant team referees are provided on the building radiological maps in section VII of the Referee Manual.
EXPECTED ACTIONS: The control room operators will monitor the weather conditions as indicated on meters and computer displays and take appropriate action as dictated by plume travel P
'J ~
-Ci and resultant doses/contamination.
VIII-46
IS No. 22 Time: 2000 MESSAGE INFORMATION SHEET r il ~ \
~
AP 'fj ea.~i MESSAGE FOR: General Office Engineering Support Manager
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LOCATION: General Office MESSAGE: "THIS IS A DRILL." This is the PCC calling. We have received numerous request for information concerning the site from within the company and also from outside. Would you please provide an overview of what has happened so far, what you expect could happen from now on, when do you expect to have the plant in a stable condition and is this going to be a long term shutdown for both units? If asked about grid stability the answer should be that the PP8L grid is in good shape, with no major problems foreseen.
The PJM may not be in as good a shape due to the loss of several transmission networks into the New York/New Jersey area causing some instabilities. "THIS IS A DRILL.",
FOR REFEREE USE ONLY REFEREE NOTES: The information provided by the General Office should compare favorably with what has happened in the plant. The General Office may or may not think about asking the status of the grid.
EXPECTED ACTIONS:
'o theinformation The received remainder of the from the PCC should be passed on;",
General Office Staff. If the" question of grid stability was asked that information is expected to be passed on to the site as well as the EOF.
VI I I-47
IS No. 22A
~, . Time: 1945 MESSAGE INFORMATION SHEET MESSAGE FOR: Control Room Operators MESSAGE FROM: Simulator Instructor LOCATION: Simulator Control Room MESSAGE: "THIS IS A DRILL." The Simulator Instructor to initiate the FILE RH.WE3.4 which is the meteorological conditions around the plant as indicated on PMS Format 847. "THIS IS A DRILL."
FOR REFEREE USE ONLY REFEREE NOTES: There is no simulator model which drives the various computer points or meter indications for the weather conditions around the site. The weather conditions are required by the control room during an emergency exercise to plot plume travel, direct evacuation and response routes and protect site personnel not evacuated.
The rad levels in the plant for the in-plant team referees are provided on the building radiological maps in section VII of the Referee Manual.
ENTENTE T N The control room operators will monitor the weather conditions as indicated on meters and computer displays and take appropriate action as dictated by plume travel and resultant doses/contamination.
VIII-48
IS No. 23 Time: 2030 MESSAGE INFORMATION SHEET MESSAGE FOR: Control Room Operators MESSAGE FROM: Control Room Referee LOCATION: Simulator Control Room MESSAGE: "THIS IS A DRILL." The Simulator Instructor will initiate FILE:
to simulate an earth quake event which causes a design basis accident and a failure of the feedwater cleanup line in the Reactor Building Steam Tunnel. "THIS IS A DRILL."
FOR REFEREE USE ONLY REFEREE NOTES: The plant does not have a full compliment of ECCS for core reflood. With the broken feedwater line the core will remain uncovered until the plant operators are able to get out and restore the permit that was applied to the 'B'HR LPCI injection valve.
EXPECTED ACTIONS: The operators will monitor the vital core parameters and determine what systems are injecting, what systems are not injecting and what is needed to regain core coverage.
VIII-49
FREQUENCY VALUE SETPOINT 3:8 '=.
.85 2 3**
3:.'8 .76 2 3**
3.4 .53 2 3**
3.2 .62 23**
3.0 .44 23**
2.8 .58 23**
2.6 .61 2 3**
2.4 .51 2 3**
2.2 .68 2 3**
2.0 .71 2 3**
1.9 .54 2 3**
1.8 .63 2 3**
1.7 .72 2 3**
1.6 .56 20**
1.5 .59 20**
1.4 .53 20**
1.3 .60 19**
1.2 .67 18**
1.1 .72 18** i 1.0 .52 18**
CHANNEL 1 WT-35701 CONT. FND 000 00 30 40 FOOFF12 000 05 36 40 FOOFF12 DIRECT - 20%
VIII-50
IS No. 23A; Time: 2Q20.
MESSAGE INFORMATION SHEET MESSAGE FOR: Control Room Operators MESSAGE FROM: Simulator Instructor LOCATION: Simulator Control Room MESSAGE: "THIS IS A DRILL." The Simulator Instructor to initi'ate the FILE RH.SBGTA which provides indications to the operators, of the Standby Gas Treatment System starting. "THIS IS A DRILL."
FOR REFEREE USE ONLY REFEREE NOTES: There is no simulator model which indicates the start of the SBGTS. There are several alarms and indications that the operators would have on an auto start of the SBGTS which are not modeled by the simulator.
<)X EXPECTED ACTIONS: The control room operators will monitor the alarms and provided to ensure a proper start and 'ndications oper ation of the SBGTS.
VIII-51
IS No. 238 Time: 2030 MESSAGE INFORMATION SHEET r
'MESSAGE- FOR: Control Room Operators
- MESSAGE-'(ROM: - Simulator Instructor
"'LOCATION: Simulator Control Room MESSAGE: "THIS 'IS A DRILL." The Simulator Instructor to initiate the FILE RH:91LOC.which provides indications to the operators of the changing 'pl'ant "radi.ological conditions. "THIS IS A DRILL."
FOR REFEREE USE ONLY REFEREE .NOTES: There is no simulator model which indicates plant rad conditions so the conditions are input to the computer for display on the meters and computer formats.
EXPECTED ACTIONS: The control room operators will monitor the alarms and indications provided to ensure proper actions taken as a result of the plant radiation values.
VI I I-52

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