ML18017A259

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)

Text

FOHB 2 REGULA Y INFORMATION DISTRIBUTIO 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

SUBJECT:

"Exercise Manual," approved by util as std for conduct in performance of 911016 NRC graded exercise.~i~

~DISTRIBUTION C(8E: DF03D COPIES RECEIVED:LTR J ENCL Q SIZE: iITLE: Direct Flow Distribution:

Subject Files 6 40,70,71 Dkts w out LPDRs NOTES:LPDR 1 cy Transcripts.

LPDR 1 cy Transcripts.

05000387~05000388 33 RECIPIENT ID CODE/NAME INTERNAL: NUDOCS-ABSTRACT EXTERNAL: NRC PDR NOTES: COPIES RECIPIENT LTTR ENCL~CODE/NAME 1 1 REG FILE 01 1 1 2 2 ,COPIES'LTTR ENCL P I 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:

SECURITY: PUBLIC INFORMATION:

GENERAL OFFICE: HEALTH PHYSICS: CHEMISTRY:

Dave Walsh, Bill DiDomenico Brian McBride Ira Kaplan Jack Refling.Margaret Rochester Karen Ziolkowski RAD&ENVIRONMENTAL:

Bruce Carson 9111i30023 9iiOib PDR ADOCN, 05000387 FORWARD SECTION I TABLE OF CONTENTS INTRODUCTION A.Major Exercise Event Schedule B.Exercise Development Philosophy PAGE I-3 I-7 SECTION II OBJECTIVES SECTION III GUIDELINES FOR CONDUCT OF EMERGENCY EXERCISE III-1 SECTION IV REFEREE DATA AND INSTRUCTIONS A.Referee Location and Telephone Numbers IV-1 IV-6 SECTION V TIMELINE A.Summary B.Detailed Timeline C.Basis of Timeline Events 1.Seismic Event V-1 V-2 V-7 V-25 V-26 SECTION VI INITIAL CONDITIONS A.SSES Daily Report of Operation B.NSAG Daily Report C.Priority Lists D.Operator Turnover Sheets VI-1 VI-2 VI-5 VI-9 VI-14 SECTION VI I RADIOLOGICAL CONDITIONS A.Offsite Release Data 1.Weather and Met Data Log 2.Plume Trajectory and Plume Deposition Data 3.Noble Gas and I-131 Release Rate Data 4.EPB Dose Rate, 6 Hour Projections, and Onsite Field Mo'nitoring Team Information 5.Field Monitoring Team Data B.Reactor Water Isotopic C.Suppression Pool Water Isotopic D.Drywell Air Isotopic E.Wetwell Air Isotopic F.Area Rad Monitor Readings (Rx Bldg 8 Ctrl Str)G.In-Plant Dose Survey Maps H.PASS Sample Information PAGE VII-1 VII-4 VI I-6 VII-8 VII-16 VII-25 VII-27 VII-29 VI I-31 VII-33 VII-65 VII-80 SECTION VI I I MESSAGE INFORMATION SHEETS VIII-1 SECTION IX EXERCISE QUESTIONS A.NRC Questions B.Questions/Topics of Discussion for HPN Communicator IX-1 IX-2 IX-5 SECTION X SIMULATOR INFORMATION X-1 WEATHER CHANGES THAT OCCUR DURING EXERCISE RH.WE3.2*FILE*(USER FILE)1.2.3.4.5.6.7.8.9.***1815 WEATHER FOR NRC GRADED EXERCISE***MENU SW PDKVMS01=04.0 SW PDKVMS02=03.0 SW PDKVMX01=150.0 SW PDKVMX02=157.0 OVR 93X15B 25.0 OVR 93X15C 11.0 XFILE RH.WE3.3*FILE*(USER FILE)1~2~3.4.5.6.7.8.9.***1945 WEATHER FOR NRC GRADED EXERCISE***MENU SW PDKVMS01=05.0 SW PDKVMS02=04.0 SW PDKVMX01=080.0 SW PDKVMX02=083.0 OVR 93X15B 12.0 OVR 93X15C 09.0 XFILE RH.WE3.4*FILE*(USER FILE)l.2~3.4~5.6.7.8.9.***2015 WEATHER FOR NRC GRADED EXERCISE***MENU SW PDKVMS01=04.0 SW PDKVMS02=04.0 SW PDKVMX01=150.0 SW PDKVMX02=152.0 OVR 93X15B 12.0 OVR 93X15C 09.0 XFILE RH.WE3.5*FILE*(USER FILE)l.2~3.4~5.6.7~8.'9.***2115 WEATHER FOR NRC GRADED EXERCISE***MENU SW PDKVMS01=03.0 SW PDKVMS02=04.0 SW PDKVMX01=104.0 SW PDKVMX02=106.0 OVR 93X15B 09.0 OVR 93X15C 08.0 XFI LE X-5 P IL C." 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 MESSAGE INFORMATION SHEET IS No.28 Time: 2045 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 MESSAGE INFORMATION SHEET IS No.29 Time: 2045 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 MESSAGE INFORMATION SHEET IS No.30 Time: 2055 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'B'ystem."THIS IS A DRILL." REFEREE NOTES: FOR REFEREE USE ONLY 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 MESSAGE INFORMATION SHEET IS No.30A Time: 2100 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." REFEREE NOTES: EXPECTED ACTIONS: FOR REFEREE USE ONLY 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.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.OVR 22X11A 2,5 12.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'AMP PDVPAR03i100

~Oi120i5 17'OVR A01B05 li20i0~0 17~2 RAMP SPRMV02 2 i 5~1 i 3 00 i 0~0 18.OVR A16G15 1,10 19'AL ECS3 ACTi10 20.OVR A15E04 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;0.0'AMP PDVPAR39 i 05~'0j 3600 i 0~0 RAMP PDVPAR37 i 17~0 j 3600 i 0~0'RAMP SPRMV03 2 i 5~3 i 3 600 g 0~0RAMP SPRMV037 i 2~3E3 i 3 600 i 0~0 RAMP SPRMV03 6, 0.10", 3 600, 0.0 XFILE X-10 MESSAGE INFORMATION SHEET IS No.31 Time: 2100~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." REFEREE NOTES: FOR REFEREE USE ONLY 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' MESSAGE INFORMATION SHEET IS No.32 Time: 2105~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 MESSAGE INFORMATION SHEET IS No.33 Time: 2105 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 MESSAGE INFORMATION SHEET IS No.34 Time: 2115 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 Format¹47."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 MESSAGE INFORMATION SHEET IS No.35 Time: 2120 MESSAGE FOR: Recovery Manager MESSAGE FROM: EOF Referee LOCATION: EOF MESSAGE: "THIS IS A DRILL." ,A Protective Action Recommendation needs to be made at this time.If no PAR is 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 MESSAGE INFORHATION SHEET IS No.36 Time: 2125 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 <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br />.We are also considering dispatching a team to your Main Office in Allentown, we would like the following information, please: 1.2.3.4.5.I need directions to the General Office from Harrisburg.

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

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.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.

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 MESSAGE INFORMATION SHEET IS No.38 Time: 2230 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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.August 13 August 15 August 16 August 16 August 19 August 20 August 21 OVERALL SCHEDULE OF EVENTS FOR ANNUAL EXERCISE EOF Walkthrough Time: 0900-1500 Location: EOF Attendees:

All EOF participants Referee Training Seminar Time: 0800-1200 Location: EOF Large Conference Room (LCR)Attendees:

First Time Referees Lead Referee Simulator Demo Time: 1100 Location: Simulator Attendees:

All Lead Facility Referees TSC Walkthrough Time: 1330-1530 Location: TSC Attendees:

All TSC participants Referee Training Time: 0830-1500 Location: EOF LCR Attendees:

All Referees and Observers First Practice Exercise Time: Day Shift Location: Simulator and all ERFs (HOC from SOP/SEIC/Riverlands)

Attendees:

All Participants, Referees, and Observers Critique Preparation Time: 0800-1300 Location: EOF LCR Attendees:

Lead Facility Referees I-4 August 21 August 21 Sept 20 Sept 23 Critique Presentation Time 1400-1600 Location: EOF LCR Attendees:

All Manager and Coordinator Participants; Lead Referees;other participants and referees invited but attendance optional Operations Meeting (as necessary)

Time: 1600-1800 Location: EOF Attendees:

Lead Control Room Referee Lead Referee Training Time: 1100 Location: Simulator Attendees:

All Lead Facility Referees Referee Training Time: 0830-1530 Location: EOF LCR Attendees:

All Referees and Observers Sept 24 Sept 25 Sept 25 Sept 25 Second Practice Exercise Time: Day Shift Location: Simulator and all ERFs (HOC from YMCA)Attendees:

All Participants, Referees, and Observers Critique Preparation Time: 0800-1300 Location: EOF LCR Attendees:

Lead Facility Referees'riti'que Presentation Time: 1400-1600 Location: EOF LCR Attendees:

All Manager and Coordinator Participants; Lead Referees;other participants and referees invited but attendance optional 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'ocated in the EOF next to the Offsite Dose overhead projector.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?2.3.4.5.Are any of the individuals armed?Have you notified the local law enforcement authorities?

Has outside assistance been requested?

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~b.C.d.e.What is the classification based on?Is there a release in progress?Is the release monitored?

Is the release being filtered?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?34.35.36.37.Are there any protective action recommendations being considered as a result of the environmental samples?Are there any damage control teams presently dispatched in the plant?What is the damage control team attempting to do at this time?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?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 b.c~d.e.What are the What are the What are the How long are path?Is that time doses?projected doses at the EPB?projected thyroid doses at the EPB?integrated doses at the EPB?you expecting to release through the present release the same as what you are using for your projected 3.What sectors are affected by the release?How many people live in the affected sectors?5.6.7.8.What is the present weather and what is the weather forecast?What isotope is the primary contributor to the dose at the EPB?Is the thyroid dose or whole body dose limiting?Is any particulate being released?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?

10.12.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?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?13.15.16.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?

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?

Does your dose calculation model take into account the run-off when the snow melts?LICENSEE OFFSITE MONITORING 2.3.5.6.What is the distance from the plant that your onsite team is doing it'monitoring?

What method does the offsite team use to calculate iodine activity, particulate activity?I 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?What exposures are the offsite monitoring teams allowed to receive?What is their present exposure?Is that value all from today?Where are the offsite teams located?7.8.What are the results of the environmental samples?Where and when were the environmental samples taken?Is the area around the EOF contaminated, was the area surveyed prior to activation?

9.10.Have any of the field monitoring teams experienced any radio interference by any offsite source?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: ar es A.Hyer I Approved: H.Genh 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)]NUREG 0654 RESP GRP NOT DEMO DEMO COMMENTS D.l An emergency classification and emergency action level scheme as set forth in Appendix 1 must be established by the licensee.The specific instruments, parameters, or equipment status shall be shown for establishing each emergency class, in the in-plant emergency procedures.

The plan shall identify the parameter values and equipment status for each emergency class.NEP The core objective and supporting NUREG will be demonstrated by the emergency responders proper use of the SSES EALs.The scenario will use the simulator Control Room indications as initiating conditions.

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

(la): CONT'0 NUREG 0654 RESP GRP NOT DEMO DEMO COMMENTS H.5 Each licensee shall identify 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.

Plant x This equipment shall include: a.geophysical phenomena monitors, (e.g., meteorological, hydrologic, seismic);b.radiological monitor s, (e.g., process, area, emergency, effluent, wound and portable monitors and sampling~quipment);

c.process monitors, (e.g., reactor coolant pressure and temperature, containment pressure and temperature, liquid levels, flow rates, status or lineup of equipment components);

and d.fire and combustion product detectors.

Met Data will be used for dose calculations.

Simulator will display weather parameters.

Applicable radiation readings will indicate in the simulator Control Room on meters and CRT displays.Applicable instrumentation will read out in the Control Room, TSC, and EOF on CRT displays.Not demonstrated.

(la): CONT'D NUREG 0654 RESP GRP NOT DEHO DEHO COHHENTS H.6 Each licensee shall make provision to acquire data from or for emergency access to offsite monitoring and analysis equipment including:

a.geophysical phenomena 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.NEP Actual demonstration using simulated data from the met towers, simulated TLDs, and field monitoring teams receiving simulated data from referees.I.2 Onsite capability and resources to provide initial values and continuing assessment throughout the course of an accident shall include post-accident sampling capability, radiation and effluent monitors, in-plant iodine instrumentation, and containment radiation monitoring in accordance with NUREG 0578, as elaborated in the NRC letter to all power reactor licensees dated October 30, 1979.Plant x The simulator Control Room accident instruments will indicate for accident assessment by responding to transients induced for the exercise.The PASS located in the Training Center will be used for sampling.

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

a.the source term of releases of radioactive material within plant systems.An example is the relationship between the containment radiation monitor(s) reading(s) and radioactive material available for release from containment.

b.the magnitude of the release of radioactive materials based on plant system parameters and effluent monitors.Rad&x Env The rad monitors will indicate proper correlation to the radioactive material released.The values used for the rad monitors are derived by using a computer program.Data indicating the radiological conditions will be available in the Control Room, TSC, EOF, 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)]NUREG 0654 RESP GRP NOT 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 establish procedures for alerting, notifying, and mobilizing emergency response personnel.

NEP Actual demonstration for exercise participants by using pager system and telephone.

E.3 The licensee in conjunction with State and local organizations shall establish the contents of the initial emergency messages to be sent 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.

NEP Actual demonstration by Operations disseminating initial communications to state and local organizations.

(1b): CONT'D NUREG 0654 RESP GRP NOT DEMO DEMO COMMENTS Each licensee shall make provisions for follow up'essages from the facility to 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;NEP x Actual demonstration by Control Room, TSC, and EOF.i.projected dose rates and/II-8 (1b): CONT'D NUREG 0654 RESP GRP NOT 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)]NUREG 0654 RESP GRP NOT DEMO DEMO COMMENTS E.1 Each organization shall establish procedures which describe mutually agreeable 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.NEP x Actual demonstration by response organization at each level of emergency.

E.2 This NUREG is the same as that used to support Core Objective 1b.H.4 Each organization shall provide for timely activation and staffing of the facilities and centers described in the plan.All All facilities will-activate.

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

[FEHA-GH-EX-3:

(3)]NUREG 0654 A.l.d Each organization shall identity a specific individual by title who shall be in charge of the emergency response.RESP NOT GRP DEMO DEMO.COMMENTS NEP x Actual demonstration as each organization is activated.

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

(3)]NUREG 0654 A.l.d This NUREG is the same as that used to support Core Objective 3A.RESP GRP NOT DEHO DEHO COHHENTS (4): Demonstrate ability to communicate with all appropriate locations, organizations, and field personnel including 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day manning of communication links.[FEMA-GM-EX-3:

(4)]NUREG 0654 RESP GRP NOT DEMO DEMO COMMENTS A.l.e Each organization shall provide for 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day emergency response, including 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day manning of communications links.All Demonstration of 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> coverage by filling out a shift manning roster.Actual TSC shift change during 2nd practice exercise.F.1 The communication plans for emergencies shall include organizational titles and alternates for both ends of the communication links.Each 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: NEP Backup communications paths will only be tested if the primary system actually fails during the drill.a.provision for 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 NUREG 0654 RESP GRP NOT 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 that a coordinated communication link for fixed and mobile medical support facilities exists.All x A medical emergency will not be included in the scenario.

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

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

C.2.a Each principal offsite organization may dispatch representatives to the licensee's near-site Emergency Operations Facility.(State technical analysis representatives at the nearsite EOF are preferred.)

NEP Will be demonstrated by representatives from Harrisburg coming to the EOF along with state off-site monitoring teams.

(5): CONT'D NUREG 0654 RESP GRP NOT DEMO DEMO COMMENTS C.2.b The licensee shall prepare for the dispatch of a representative to principal offsite governmental emergency operations centers.NEP Not demonstrated; an individual will not be dispatched to offsite facil i ty.G.3.b Each licensee shall provide space which may be used for a limited number of news media at the nearsite Emergency Operations Facility.Speci Office Not demonstrated.

H.1 Each licensee shall establish a Technical Support Center and an onsite operations support center (assembly area)in accordance with NUREG 0696, Revision l.Plant x To be demonstrated when the control room classifies the emergency as an ALERT or when deemed necesary by the ED.H.2 Each licensee shall establish an Emergency Operations Facility from which evaluation 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.NEP Actual demonstration.

The EOF will be fully activated.

(5): CONT'D NUREG 0654 RESP GRP NOT DEHO DEHO COHHENTS H.9 Each licensee shall provide for an onsite operations support center (assembly area)which shall have adequate 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.Plant x The OSC will be activated and required emergency equipment will be used.I.7 Each organization shall describe the capability and resources for field monitoring within the plume exposure Emergency Planning Zone which are an intrinsic part of the concept of operations for the facility.Rad 8 x Field monitoring Env personnel will be dispatched from the plant and the EOF.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)]NUREG 0654 RESP GRP NOT DEHO DEHO COHHENTS K.3.a Each organization shall make provision for 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day capability to determine the 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.Plant x" Dosimetry will be used as determined by the scenario conditions.

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

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

(7)]NUREG 0654 RESP GRP NOT DEMO DEMO COMMENTS E.2 This NUREG is the same as that used to support Core Objective 1b.I.8 Each organization, where appropriate, shall provide methods, equipment and 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.Rad 5 Env Actual demonstration for airborne-release from the site.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)]NUREG 0654 RESP GRP NOT DEHO DEHO COHHENTS H.12 Each organization shall establish a central point (prefer ably associated with the licensee's near-site Emergency Operations Facility), for the receipt and analysis of all field monitoring data and coordination of sample media.Rad 8 x Actual demonstration by Env collection of field samples and return to the EOF.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)]NUREG 0654 I.8 This NUREG is the same as that used to support Core Objective 7a.RESP GRP NOT DEMO DEMO COMMENTS (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)]NUREG 0654 RESP GRP NOT 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 capability to detect and measure radioiodine concentrations in air in the plqpe exposure EPZ as low as 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.Rad 8.x Env Actual demonstration using data supplied to participants after demonstrating proper sample technique.

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)]NUREG 0654 RESP GRP NOT 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'establish means for relating the various measured parameters (e.g., contamination levels, water and air activity levels)to dose rates for key isotopes (i.e., those given in Table 3, page 18)and gross radioactivity measurements.

e Provisions shall be made for 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.

Rad 8 x Env Dose rates, dose projections, and integrated doses will be calculated based on data indicated on instrumentation and provided from field teams.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 NUREG 0654 RESP NOT GRP DEMO DEMO COMMENTS I.4 Each licensee shall establish the relationship between effluent monitor readings and onsite and offsite exposures and contamination for various meteorological conditions.

Rad 5 x Actual demonstration Env using the STREAM system.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)NUREG 0654 RESP NOT GRP DEHO DEHO COHHENTS I.6 Each licensee shall establish the methodology for determining the release rate/projected doses if the instrumentation used for assessment are offscale or inoperable.

Rad L x Not demonstrated.

Env 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)]NUREG 0654 RESP NOT GRP DEMO DEMO COMMENTS E.7 Each organization shall provide written messages intended for the public, consistent with the licensee's classification scheme.In 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.NEP 5 Speci Office x Actual demonstration, scenario will require a protective action recommendation to be made.J.10.m The bases for the choice of 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.

All x Actual demonstration.

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

II-27 (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)]NUREG 0654 RESP GRP NOT 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 organizations shall establish 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).NOT A LICENSEE RESPONSIBILITY G.4.a Each principal organization shall designate a spokesperson who should have access to all necessary information.

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.Speci Office Actual demonstration using actors and mock phone calls as necessary to initiate public information actions.II-28 (14): Demonstrate the ability to brief the media in an accurate, coordinated, and timely manner.[FEMA-GM-EX-3:

(14)]NUREG 0654 G.3.a Each princi pal organi zati on shall designate the points of contact and physical locations for use by news media during an emergency.

RESP GRP Speci Office NOT DEMO DEMO COMMENTS The activation of the MOC at the YMCA in Berwick will be demonstrated for the 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.II-29 (15): Demonstrate the ability to establish and operate rumor control in a coordinated and timely fashion.[FEMA-GM-EX-3:

(15)]NUREG 0654 RESP NOT GRP.DEMO DEMO COMMENTS G.4.c Each organization shall establish coordinated arrangements for dealing with rumors.Speci Office Actual demonstration; phone calls will be made.by various people asking questions.

II-30 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)]NUREG 0654 RESP GRP NOT 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)]NUREG 0654 J.10.e NOT A LICENSEE RESPONSIBILITY.

RESP GRP NOT DEMO DEMO COMMENTS II-32 0 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, as well as'o distribute and administer it once the decision is made, if necessitated by radioiodine release.[FEMA-GM-EX-3:

(17)]NUREG 0654 J.10.f NOT A LICENSEE RESPONSIBILITY.

RESP GRP NOT DEMO DEMO COMMENTS I j-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)]NUREG 0654 E.7 This NUREG is the same as that used to support Core Objective 11.RESP GRP NOT DEMO DEMO COMMENTS 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)]NUREG 0654 RESP GRP NOT DEMO DEMO COMMENTS J.2 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.

NEP 3 x Site evacuation will be Sec simulated.

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.

II-35 (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)]NUREG 0654 J.10.d NOT A LICENSEE RESPONSIBILITY.

RESP GRP NOT DEMO DEMO COMMENTS IE-36 (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 J.9 NUREG 0654 NOT A LICENSEE RESPONSIBILITY RESP GRP NOT DEMO DEMO COMMENTS J.10.g NOT A LICENSEE RESPONSIBILITY.

II-37 (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)]NUREG 0654 RESP GRP NOT 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.

II-38 (20b): Demonstrate the organizational ability and resources necessary to control access to the evacuated area.[FEMA-GM-EX-3:

(20)]NUREG 0654 J.10.3 NOT A LICENSEE RESPONSIBILITY RESP GRP NOT DEMO DEMO COMMENTS II-39 (21): Demonstrate the adequacy of procedures, facilities, equipment and personnel for registration and radiological monitoring of evacuees.[FEMA-GM-EX-3:

(21)]NUREG 0654 J.12 NOT A LICENSEE RESPONSIBILITY RESP GRP NOT DEMO DEMO COMMENTS 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.II-40 (22): Demonstrate the adequacy of facilities for mass care of evacuees.[FEMA-GM-EX-3: (22)]NUREG 0654 J.10.h NOT A LICENSEE RESPONSIBILITY RESP GRP NOT DEMO DEMO COMMENTS 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)]NUREG 0654 L.4 NOT A LICENSEE RESPONSIBILITY RESP GRP NOT DEHO DEHO COHHENTS II-42 (24): Demonstrate adequacy of hospital facilities and procedures for handling contaminated individuals.

[FEMA-GM-EX-3:

(24)]NUREG 0654 L.I NOT A LICENSEE RESPONSIBILITY RESP GRP NOT DEMO DEMO COMMENTS (25): Demonstrate adequate equipment and procedures for decontamination of emergency workers, equipment, and vehicles and for waste disposal.[FEMA-GM-EX-3:

(25)]NUREG 0654 RESP NOT GRP DEMO DEMO COMMENTS K.5.a Each organization, as appropriate, shall specify action levels for determining the need for decontamination.

HP&x Contamination limits Rad&will be exceeded and Env appropriate action will be required.K.5.b Each organization, as appropriate, shall establish the means for radiological decontamination of emergency personnel wound, supplies, instruments and equipment, and for waste disposal.HP 8 x Scenario does not Rad&include a medical Env emergency.

No equipment will be deconned.K.7 Each licensee shall provide the capability for decontaminating relocated 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.HP&x Not demonstrated.

Rad&Env~'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.

II-44 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)]NUREG 0654 RESP GRP NOT DEMO DEMO COMMENTS C.1 The Federal government

.maintains in-depth capability to assist licensees, States 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;NEP x Not demonstrated; no simulated or actual federal assistance.

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 NUREG 0654 I.8 This NUREG is the same as that used to support Core Objective 7b.RESP GRP NOT DEMO DEMO COMMENTS Il-46 (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)]NUREG 0654 RESP GRP NOT DEMO DEMO COMMENTS C.3 Each organization shall identify radiological laboratories and their general capabilities and expected availability to provide radiological monitoring and analyses services which can be used in an emergency.

Rad L'Not demonstrated.

Env II-47 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)]NUREG 0654 I.10 This NUREG is the same as that used to support Core Objective 9.RESP.GRP NOT DEMO DEMO COMMENTS II-48 (30): Demonstrate ability to implement protective actions for ingestion pathway hazards.[FEMA-GM-EX-3:

(30)]NUREG 0654 J.11 NOT A LICENSEE RESPONSIBILITY.

RESP GRP NOT DEMO DEMO COMMENTS IX-49 (31): Demonstrate ability to estimate total population exposure.[FEMA-GM-EX-3:

(31)i NUREG 0654 M.4 Each plan shall establish a method for periodically estimating total population exposure.RESP NOT GRP DEMO DEMO.COMMENTS Rad 8 x Not demonstrated.

Env 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)]NUREG 0654 RESP GRP NOT DEMO DEMO COMMENTS M.1 Each organization, as appropriate, shall develop 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.

Rad 8.x Not demonstrated.

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

(33)]NUREG 0654 M.1 This NUREG is the same as that used to support Core Objective 32.RESP GRP NOT DEMO DEMO COMMENTS II-52 (34): Demonstrate ability to fully staff facilities and maintain staffing around the clock.[FEMA-GM-EX-3:

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

NOT A LICENSEE RESPONSIBILITY.

A.4 Each principal organization shall be capable of continuous (24-hour)operations for a protracted period.The individual in the principal organization who will be responsible for assuring continuity of resources (technical, administrative, and material)shall be specified by title.All Actual demonstration by filling out shift rosters.An actual shift change will be demonstrated for all the TSC positions during the 10/17 practice exercise.

(34): CONT'0 NUREG 0654 RESP GRP NOT 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:

1.2.3..4.Employees not having emergency assignments.

Visitors.Contractor and construction personnel.

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)]NUREG 0654 RESP GRP NOT DEMO DEMO COMMENTS J.l 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:

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.Ops 5 x Actual demonstration Sec initiated by events in the scenario.II-55 (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)]NUREG 0654 J.2 This NUREG is the same as that used to support Core Objective 18b.RESP GRP NOT DEMO DEMO COMMENTS II-56 (35c): Each licensee shall provide for radiological monitoring of people evacuated.from the site.lFEMA-GM-EX-3:

(35)],.NUREG 0654 RESP GRP NOT DEMO DEMO COMMENTS J.3 Each licensee shall provide for radiological monitoring of people evacuated from the site.HP x Not demonstrated.

II-57 (35d): Demonstrate the ability to effect an orderly evacuation of onsite personnel.

[FEMA-GM-EX-3:

(35)]NUREG 0654 RESP NOT GRP DEMO DEMO COMMENTS J.4 Each licensee shall provide for the evacuation of onsite 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.Plant x Not demonstrated.

S.Sec II-58 (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)]NUREG 0654 RESP GRP NOT DEMO DEMO COMMENTS J.5 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.

Plant x Actual demonstration.

8 Sec II-59 (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)]NUREG 0654 RESP GRP NOT DEMO DEMO COMMENTS J.6 Each licensee shall, for individuals remaining or arriving onsite during the emergency, make provisions for: Hp x Actual demonstration for first individual entering an airborne area.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)]NUREG 0654 RESP GRP NOT DEMO DEMO COMMENTS N.l.b An exercise shall include mobilization of State and local personnel and resources 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.

Plant x Actual demonstration, 5 All except exercises will NOT be unannounced.

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

N.5 Each organization shall establish means for evaluating observer and participant comments on areas needing improvement, including 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.

NEP A formal critique will be written with all areas needing improvement noted and assigned to a specific group or individual for closeout.II-62 SECTION I I I 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: Example of props: 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.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.

Asthe 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-EXAMPLE-movement of resources and/or physical implementation for the exercise.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 YELLOW BLUE GREEN LIGHT BLUE WHITE BROWN BLACK MAROON GREY Emergency Director/Recovery Manager/Asst.RM Emergency Managers and Coordinators (functions identified on ballcap)Emergency Staff (personnel reporting to managers)Operating Crew and On/Offsite Teams Clerical and Stenographic Staff NRC FEMA, EPA, DOE INPO DER/BRP 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 if it is necessary to perform the functions of the response position.Data will be 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: SECOND 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.The area referees get together with the area managers at the conclusion of the exercise and discuss the'verall exercise mentioning strong and/or weak areas.

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 f ter an exerci se.PRE-EXERCISE l.2.3.4.5.Review Referee Information Packet Attend Scheduled Referee Training Session Participate in Referee Walkthrough Review Message Sheets which pertain to your responsibility Become familiar with Referee Observation Sheets (to be presented at training session)EXERCISE l.2.3.4.5.6.Assemble at location early Log participants on Attendance Sheets (name, signature, employee number, and position code)Observe/Evaluate Participant Actions Complete Observation Sheets Provide Exercise Data As Appropriate Debrief participants as soon as possible POST EXERCISE l.2.3.4.5.6.Attend/Conduct Debriefing Complete Observation Sheets Collect Attendance Sheets Turn over completed Observation Sheets, Attendance Sheets, and Referee Nanuals to Area Lead Referee Assure that all participants in your.area of responsibility are informed the exercise is over (ie.all onsite and offsite groups)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: 2.3.4.Satisfactory Satisfactory with a few problems that may be subject to follow-up.

Deficiency is noted but would not seriously affect our ability to protect the health and safety of the public.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 CONTROL ROOM (Simulator)

Phone Number Lead Control Room Referee Simulator Instructor Communications Referee Control Room Referee TECHNICAL SUPPORT CENTER Lead TSC Referee TSC Communications Referee (includes data flow)TSC Rad Referee TSC Tech Referee In-plant Team Referee Coordinator OPERATIONS SUPPORT CENTER D.T.Walsh J.Burke P.E.Homnick W.G.DiDomenico L:D.O'eil R.R.Wehr M.Rochester R.M.Harris S.B.Kuhn ext.3782 ext.3782 ext.3782 ext.3782 ext.3530 ext.3530 ext.3530 ext.3530 ext.3530 Lead OSC Referee In-Plant Team Referee In-Plant Team Referee In-Plant Team Referee In-Plant Team Referee In-Plant Team Referee (Ops/NPO)In-Plant Team Referee (Ops/NPO)In-Plant Team Referee (Maint/I&C)In-Plant Team Referee (Ma i nt/I&C)Lead Security Referee Security Referee Security Referee Reactor Coolant Sampl Referee (Rad)(Rad)(Rad)(Rad)e Team M.G.Bo le E.J.McIlvaine~F.P.J V.M.Zukauskas C.P.Lewis R.W.Brown J.G.Paisle M.J.Beshore G.A.Farle B.P.McBride R.E.Gaudreau G.E.Galla her K.Zielkowski ext.3907 ext.3907 ext.3907 ext.3907 ext.3907 ext.3907 ext.3907 ext.3907 ext.'3907 ext.3115 ext.3115 ext.3115 ext.3907 EMERGENCY OPERATIONS FACILITY Lead EOF Referee EOF Rad Referee EOF Tech Referee EOF Communications Referee Simulated HPN NRC Team Simulated NRC Hotline (ENS)A.M.Male R.L.Dot R.A.Saccone R.E.Hoo es M.J.Sh manski C.T.Coddin ton ext.3605 ext.3605 ext.3605 ext.3605 ext.3605 ext.3605 Referee Phone Number E.GENERAL OFFICE GO Tech Referee F.MEDIA OPERATIONS CENTER Lead MOC Referee MOC Assistant Referee Person to call in, rumors and questions G.ENVIRONMENTAL MONITORING TEAMS OSCAR Referee Near Site Team Referee Offsite Monitor Team Referee Offsite Monitor Team Referee Offsite Monitor Team Referee H.CHIEF REFEREES Chief Rad Referee Chief Referee I.PLANT SITE Evacuation Group J.E.Rothe I.N.Ka lan G.C.Lewis S.R.Walter J.Le o J.A.Bird G.L.Croll R.R.Kurtz Not re uired B.H.Carson R.H.Halm 2nd floor old S&A ext.7550 ext.3561 ext.3561 ext.Fi el d Field Fi el d Field Field ext.3601 ext.3530 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 uehanna Steam q 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 the¹4 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.The¹4 control valve did not respond properly during weekly turbine valve testing.After the¹4 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, the¹4 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 <br />0.561 hours <br />0.00334 weeks <br />7.6861e-4 months <br /> 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 Levelwill 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 set up initial conditions for the Control Room Operators.

Operations to start the process of shift turnover.The IS-1 Control Room Referee will review the following with the oncoming shift: 1.2.3.4.Previous 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> log entries Operations turnover sheets Previous and present plant priority lists Daily Report of Operations and NSAG Daily Report 1500 Referee Hessa e-Equipment set up, initiate activation of the emergency exercise phones, radio, and plant page for the simulator control room.NOTE: The above material is located in the INITIAL CONDITIONS SECTION of the REFEREE MANUAL.Phone company personnel to perform switching in the Service and Administration Building phone room and hook up in the simulator control room.Lead Referee to swap simulator radio and check NRC phone activated.

IS-2 1500 Referee Hessa e-Simulator Instructor initialize the simulator to IC 8125.The initial plant conditions contain the following files: IS-3 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 1530 Referee Hessa e-Plant page announcement for start of 1991 NRC GRADED EXERCISE.Referee Messa e-Simulator initiated alarm from Seismic Monitoring panel.The alarm will be Plant page announcement to be made from Control Room indicating the start of the 1991 NRC GRADED EXERCISE.Control Room Operator will acknowledge the alarm on the main control room panel and investigate the indications on the seismic monitoring back panel.IS-4 IS-5 APPROX.TIME OF DAY INITIATING EVENT EXPECTED SEQUENCE OF EVENTS the"SEISMIC MONITOR SYSTEM TRIGGERED" alarm.This is the trigger for UNUSUAL EVENT.1535 1540 Control Room Operator investigates the back panel, reviews procedure, notifies Unit and Shift Supervisor of readings on panel.The operators will follow the direction given in the alarm response procedure and in the off-normal procedure.

The Shift Supervisor will review the emergency classification levels and notify the Operations Supervisor and the Duty Manager.The Alarm Response procedure directs the Shift Supervisor to refer to the Emergency Classification Action Levels for classification of the situation.

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 1600 Operations Shift Supervisor to classify emergency as an UNUSUAL EVENT.The Control Room Communicator completes notifications to the off-site agencies.The classification will be based on the EAL, NATURAL PHENOMENA which states: 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.

The communicator has provided all the required information to the offsite agencies so that they will be able to take actions as required by their emergency plans.1610 Referee Hessa e-Call to Security from State Police reporting a problem with the bridge over the Susquehanna River at Shickshinny.

The State Police report to Security the bridge in Shickshinny appears to be damaged as a result of the earthquake.

The communicator should pass the information on to the Emergency Director in case an evacuation may be needed at a later time.1615~ff II<<-Ri I I initiated alarm from Seismic Monitoring panel.This alarm will be the"SEISMIC MONITOR SYSTEM TRIGGERED" alarm.The Control Room Operator will acknowledge the alarm on the ma,in control room panel and investigate the indications on the seismic monitoring back panel.This is the trigger for the ALERT classification.

1620 Entr Deleted APPROX.TIHE OF DAY INITIATING EVENT EXPECTED SEOUENCE OF EVENTS 1620 1620 1625 Referee Hessa e-Control Room Communicator will contact one of the seismic monitoring centers as required by the off-normal procedure.

Control Room Operator investigating the back panel, reviews procedure, notifies Unit and Shift Supervisor of readings on panel.Referee Hessa e-The operators will follow the direction given in the alarm response procedure and in the off-normal procedure.

The Control Room operators are directed to contact one of IS-9 the seismic monitoring centers to confirm quake activity.The operator will call and ask for information concerning the indications that the control room has received.The Shift Supervisor will review the emergency classification levels and notify the Operations Supervisor and the Duty Hanager.The Alarm Response procedure directs the Shift Supervisor

-IS-10 to refer to the Emergency Classification Action Levels for classification of the situation.

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 the common feedwater Tunnel.The leak is clean-up recirc line plant will reveal a minor leak on line in the Reactor Building Steam located at the T weld where the to the Hain Condenser taps off.1625 Referee Hessa e-The control room receives word from the operators in the plant that walkdowns of equipment are complete and no damage is noted.The Control Room Operators will report the status of the IS-11 equipment runs and walkdowns to the Shift Supervisor who will in turn inform the rest of the organization.

APPROX.TIHE OF DAY INITIATING EVENT EXPECTED SEQUENCE OF EVENTS 1625 1630 1645 1645 1645 Responders arrive at the OSC and the TSC and begin turnover process.Operations Shift Supervisor to classify emergency as an ALERT.~fP-H tl E g y Director classify the events as an UNUSUAL EVENT if not already done.Duty Hanager and Operations Coordinator report to Control Room for briefing of incident in preparation for turnover of emergency management.

The Control Room Communicator completes upgrade notifications to the off-site agencies.The OSC begins to set up and muster the people arriving for accountability reporting.

The OSC Coordinator is briefed by the Control Room and in turn briefs the OSC responders.

The classification will be based on the EAL, NATURAL 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.To keep the exercise on track the Emergency Director will IS-12 be told to make the classification if he hasn't already done so.The fact that the Emergency Director was prompted will be noted for the critique.Shift Supervisor provides status of seismic event, plant, actions taken, and plans for placing the plant in a safe configuration.

The communicator has informed the off-site agencies of the upgrade of the emergency classification so that the agencies may respond as required by their Emergency Plans.

APPROX.TIHE OF DAY INITIATING EVENT EXPECTED SEIOUENCE OF EVENTS 1700 1700 1700 I 1710 1710 Security reports results of site accountability to the Operations Shift Supervisor and takes required action for any missing individuals.

Referee Hessa e-When the accountability has been completed prompt the Emergency Director to release the people from their accountability stations.Responders arrive at the TSC and begin the process of taking over management of the emergency from the Control Room.Referee Hessa e-The control room receives word from the operators in the plant that walkdowns of equipment are complete.Public Information Hanager and Recovery Hanager briefed by Operations Shift Supervisor as to extent of incident.Security compiles the information required for the accountability and determines the reasons for any discrepancies that turn up.The Emergency Director will release everyone from their IS-13 accountability stations.The TSC-people start to check communication links, start up equipment, determine plant status in preparation for turnover.The Control Room Operators will report the status of the IS-14 equipment runs and walkdowns to the Shift Supervisor who will in turn inform the rest of the organization.

Investigation of the Reactor Building Steam Tunnel reveals a leak at the weld where the feedwater cleanup line taps off the common header.The Public Information Hanager will have the required details for preparation and distribution of information concerning the events at the plant.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 initiated alarm from Seismic Monitoring panel.This will bring in the"SEISMIC MONITOR SYSTEM TRIGGERED" alarm.This is one of the triggers for the SITE AREA EMERGENCY classification.

Control Room Operator will acknowledge the alarm on the IS-15 main control room panel and investigate the indications on the seismic monitoring back panel.

APPROX.TIME OF DAY INITIATING EVENT EXPECTED SEQUENCE OF EVENTS 1800 Referee Messa e-Simulator instructor to initiate FILE RH.HPISO.The file will initiate indication of a steam line break in the HPCI Room.This break will be the trigger for a SITE AREA EMERGENCY classification.

The indication in the Control Room will be a high temperature alarm indicating high energy leakage into the room.There will be a fire protection alarm indicating an auto start of the fire pump and a Simplex panel alarm showing a smoke detector alarmed.The indication is a fire or a steam leak.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 on the sequence of events that has occurred and recommend an upgraded classification.

The Control Room informs the TSC of the events that have just occurred and make a recommendation for the TSC to upgrade the emergency to a SITE AREA EMERGENCY.

The TSC 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 directs operator to HPCI Room to investigate cause for room alarms.Operator dispatched to investigate HPCI steam line break IS-17 indications, proceeds to the TSC for briefing and then to HPCI Room.1805 1805 I o 1810 Referee Hessa e-Control Room directs operator to check out the fire pump auto start.Referee Hessa e-Simulator Instructor to initiate OVR A12C03 which indicates high temperature in the Reactor Building steam tunnel.Referee Messa e-Simulator Instructor to initiate Reactor Building Sump alarm (PANEL 1C692 TROUBLE, OVR A06H14)to indicate an increasing influent to the sump.Operator dispatched to check auto start of fire pump from the steam leak in the HPCI Room.The operator will 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.The high temperature alarm will clue the control room operators to the fact that there is a problem in the steam tunnel which needs to be investigated.

An operator will be dispatched to determine the cause of the alarm and will report back the results of the investigation.

The Control Room operators will acknowledge the front panel alarm and investigate the back panel to determine the origin of the alarm.Review of the back panel will indicate the Reactor Building sump level is high.The 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.IS-18 IS-18A IS-19 APPROX.TIME OF DAY INITIATING EVENT EXPECTED SEQUENCE OF EVENTS 1815 The TSC will classify the event as a SITE AREA EMERGENCY.

The ED will classify the emergency based on the EAL, STEAM LINE BREAK, which states: Failure of HPCI steam isolation valve HV-F002 and HV-F003 to close, indicated by position indicator on Panel 1C601.2.AND (a OR b OR c OR d OR e OR f)'a~OR HPCI steamline pipe routing area high temperature annunciation on panel 1C601, or indication on panel 1C614.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 1815 1820.g 1820 1820 1830 1900 Referee odessa e-Simulator Instructor to initiate FILE: RH.WE3.2 to simulate the meteorological conditions.

Referee Messa e-The Control Room will request Chemistry to obtain a reactor coolant sample.The Alternate Security Control Center will dispatch officers to control access to the EOF and initiate call out of EOF personnel.

General Office personnel will be called and respond to General Office.~ft-E t E g Director classify the events as a SITE AREA EMERGENCY.

Site based individuals begin reporting to EOF and start set up of facility.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.

The file provides indication on the various plant indicators of the weather conditions.

The Chemistry Coordinator will respond to the sample request by initiating set up of the chem lab and a briefing for the chemists for obtaining a coolant sample.The security officers dispatched to the EOF for access control will check the individuals already in the building and help the E&S set up crew as requested to prepare the EOF for activation.

The General Office responders begin set up of the facility and data collection for support of the emergency.

If not already declared the classification needs to be made to reduce the impact on all the participating groups.The late classification will be noted in the critique if this prompt is required.The interim EOF responders will contact their counterparts in the TSC and be updated on the plant 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.IS-19A IS-20 IS-21 APPROX.TIME OF DAY INITIATING EVENT EXPECTED SEQUENCE OF EVENTS 1910 The Engineering Support Manager contacts the TSC.The Engineerihg Support Manager contacts the TSC Emergency Director for plant status and what support is needed from Allentown.

1925 1945 2000 2015 2015 The Engineering Support Hanager initiates an accountability for General Office personnel.

Referee Messa e-Simulator Instructor to initiate FILE: RH.WE3.3 to simulate the meteorological conditions.

Referee Hessa e-The PCC contacts the General Office Engineering Support Hanager and asks for a status of events at the plant.EOF takes control of Emergency Management.

Referee Hessa e-Simulator Instructor to initiate FILE: RH.WE3.4 to simulate the meteorological conditions.

The Engineering Support Manager initiates an accountability to determine if all the key positions are filled.The file provides indication on the various plant indicators of the weather conditions.

The status of the situation and any questions asked will be answered.The GOESH should ask about grid stability and potential for loss of all offsite power because of the widespread damage that can occur as a result of earthquakes.

The Recovery Manager informs the EOF that he has taken over the management of the emergency.

The file provides indication on the various plant indicators of the weather conditions.

IS-21A IS-22 IS-22A 2020 Referee Hessa e-Simulator Instructor to initiate alarm from Seismic Monitoring panel which will be;"SEISMIC MONITORING SYSTEM TRIGGERED" alarm and a FILE: RH.FWBRK to simulate an earthquake event which causes a Design Basis Accident inside the Containment.

The Control Room personnel will acknowledge the alarms on IS-23 the main control panel and investigate the indications on the seismic monitoring back panel.The operators will also respond to the decreased Reactor Water inventory and monitor the makeup water flow to the vessel.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 2030 Referee Messa e-Simulator instructor to initiate FILE: RH.SBGTA file to simulate the auto start of the Standby Gas Treatment System (incorporated in RH.FWBK).Referee Hessa e-Simulator Instructor to initiate FILE: RH.91LOC (incorporated in RH.FWBK).The operators will ackowledge the alarms that will be indicated by the automatic start of the system and verify that the system is operating properly in the auto mode.The file initiates radiological indications on various plant indicators.

The file provides indication of sever fuel damage.IS-23A IS-23B 2035 2035 I Referee Hessa e-The Offsite Monitoring teams will be dispatched from the EOF.Referee Hessa e-The Control Room will dispatch a team to clear the permit on the RHR LPCI Injection valve to reflood the vessel.The Off-site Honitoring teams will receive direction from IS-24 the Off-site Team Director on where to go and when and what to sample.The operators will go to the TSC, be briefed and sent to IS-25 the field to restore the LPCI valve to operable status to reflood the reactor vessel and raise the water level above the active fuel.

APPROX.TIME OF DAY INITIATING EVENT EXPECTED SEQUENCE OF EVENTS 2040 Referee Messa e-Core uncovered time has reached 20 minutes which is the trigger for classification at, the GENERAL BIERGENCY level.The Operators have been monitoring the top of active fuel IS-26 and water level and are aware that portions of the active fuel has been uncovered for a period of 20 minutes.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 2045 Referee odessa e-SPING HI alarm will be received in the Control Room due to the release in the unit 1 Turbine Building.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.

The alarm will be acknowledged by the Control Room Operators and investigated at the SPING console.The STA will evaluate the cause of the alarm and report his conclusions to the Shift Supervisor.

IS-27 APPROX.TINE OF DAY INITIATING EVENT EXPECTED SEQUENCE OF EVENTS 2045 Referee Hessa e-The operators report back from the field some of the dose rates that are observed.The longer it takes for the teams to get into the field to clear the permit the higher the dose rates.The dose rates in the Reactor Building will be increasing IS-28 rapidly due to the severe fuel damage.The permit will have to be cleared and the breaker closed to allow operation of the injection valve.When the permit is cleared the valve can then be operated.2050 Referee Hessa e-The Area Radiation Honitors in the TSC area and the Control Room begin to alarm.The people in the occupied areas will read the indicating transmitters to determine the rad levels.When the rad levels have been read (10 mrem/hr)a determination will-be made if any protective actions are required to be initiated.

IS-29 2055 2100 Referee Hessa e-When the'8'ain Steam Leakage Control System is started the system will not start.Referee Hessa e-Simulator Instructor to initiate FILE RH.91L01.The operators will do an investigation of the system, refer to the procedure for start of the system to insure that all the requirements for starting the system have been met and inform the TSC that support is necessary.

File simulates reactor building radiation levels and provides the indications on the various plant indicators.

IS-30 IS-30A 2100 Referee Hessa e-The Chemistry Coordinator will be prompted to place the SPING background subtract in service.The Chemistry Coordinator will instruct one of the Chem IS-31 Techs to place the background subtract circuit in service to keep the SPING instruments operable.2105 2105~Rf I-Iftt R I Hanager has not made the GENERAL EHERGENCY classification at this time, tell him to do so.Referee Hessa e-The Off-site monitoring teams will report back the field data.To keep the exercise on the proposed time line and to minimize the impact on all the participants it is necessary to make the classification at this time.Data supplied to the monitoring team personnel will be consistent with the actions taken.IS-32 IS-33 2115 Referee Hessa e-The TSC tech engineer to inform the GO that a second shift will be required.The General Office will begin to make up a relief roster.IS-34 APPROX.TIME OF DAY INITIATING EVENT EXPECTED SEIOUENCE OF EVENTS 2115 2115 2120 Licensee, State and NRC to confer concerning the recommended Protective Action Recommendations to the Governor.Referee Hessa e-Simulator Instructor to initiate FILE: RH.WE3.5 to simulate the meteorological conditions.

~Rf-If RR R Hanager has not made a Protective Action Recommendation at this time, tell him to do so.The radiological data from the field will not be available at this time.The data from the field when it starts to come in will support an evacuation out to two miles and shelter out to 10.The file provides indication on the various plant indicators of the weather conditions.

To keep the exercise on the proposed time line and to minimize the impact on all the participants it is necessary to make the classification at this time.IS-34A IS-35 2125 The Governor will initiate an evacuation of the entire EPZ.Notifications will be made to the risk counties to sound the sirens.The sounding of the sirens will be simulated.

2125 Referee Messa e-The EOF Referee to call the HOC Lead Referee to inform them of the Governor's Protective Action Recommendation, times of siren initiation and Emergency Broadcast System Hessage.The HOC referee will simulate the sounding of the sirens IS-36 for the staff of the HOC and will provide the information of what the Emergency Broadcast message will be.2130 Referee Hessa e-Representative from the State Gvernor's office contacts the General Office for information.

The General Office will be contacted by the State with several requests for information.

The General Office will respond to the questions.

IS-37 2145 Conference call between the Recovery Manager, Emergency Director, Engineering Support Manager, and Public Information Manager.The managers will discuss the status of the plant and the radiological conditions on and off-site.They will discuss their short and long term goals and strategy.

APPROX.TIME OF DAY INITIATING EVENT EXPECTED SEQUENCE OF EVENTS 2145 Referee Messa e-Simulator Instructor to initiate FILE: RH.WE3.6 to simulate the.meteorological conditions.

The file provides indication on the various plant indicators of the weather conditions.

IS-37A 2230 Referee Hessa e-The NRC GRADED EXERCISE is terminated.

A page announcement is made in all the facilities by the IS-38 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 <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br /> 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 <br />0.564 hours <br />0.00336 weeks <br />7.72415e-4 months <br />.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 Days on Line: 305 Condition:

1 at 0500 hrs Rx Power: 100%at 0500 hrs MW (e)Gross: 1074 at 0500 hrs MWH Gross: 25,774 previous 24 hrs MWH Net: 24,907 previous 24 hrs Core Flow: 944 Rx Conductivity:

.169 micromho/cm Days Since Last Auto Shutdown: 653 Man-Rem Yesterday:

1.852 UNIT 1:

SUMMARY

PREVIOUS 24 HOURS: UNIT 2 Days on Line: 0 Condition:

5 at 0500 hrs Rx Power: 04 at 0500 hrs MW (e)Gross: 0 at 0500 hrs MWH Gross: 0 previous 24 hrs MWH Net:-102 previous 24 hrs Core Flow: 40%Rx Conductivity:

NA micromho/cm Days Since Last Auto Shutdown: 324 Man-Rem Year-to-Date:

542.989'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.UNIT 2:

SUMMARY

PREVIOUS 24 HOURS: SSES DAILY REPORT Page 2 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: Lost Time: Non-Lost Time: Motor Vehicle: First Aid: YEAR-TO-DATE 0, 5, 0 8 OCTOBER 0 0 0 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 Major Work in Progress/Completed and Problems-Unit 1: Page 2 of 3 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.

ECCS-Core Spray'A'nd'B'oops.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 <br />0.623 hours <br />0.00371 weeks <br />8.527005e-4 months <br /> last night.Core verification has also been completed.(Unit 2 log, 0730 mtg.)3.Logic system functional testing of RHR Division II per SE-249-002 was completed.

Division II 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 <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br /> 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)II 5.Five of the eight main steam relief valves tested at Wylie 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 and Zone III chiller restorations are in.progress.(0730 mtg.)-Short Term Schedule-Unit 1: Repair feedwater heater level control valves.Short Term Schedule-Unit 2: NSAG Management Attention:

Continue outage work.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'AB'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 K W RK'B'OOP RHR WORK.QUARTE RLY 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."NORMAL HOURS 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 NONE IATED W RK ACTIVITIES" 6."GENERAL" U1 RAILROAD BAY WALLS 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."NORMAL HO 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

(~)t Mhfe M Iblhr PSIG~" REMARKS: '~UNIT t ,Vkrr'-"*REMARKS: UNIT L&s e ops 8 P 4 8e.c}i I.'~olacg.gp./llr,'&>, 8'.C4+de<."("'S f t'\/PLANT;CONTROL OPERATOR T , AGUA-303",.-:.>=.ReVIS$

'OIT 9-" UNIT~'.'.Qato~oY/a 9."~".';.':~.': p<<e g8 0p 7g~t}L900 to 0700"",.~~'HIFT 0700 tert L900 Start Enct.Start-:,';, End.PLANT STATUS'Tt TURNOVER PLANT'STATUS AT TURNOV CONOITlON I CQNOITIQN POWER LEVEL C}O POWER LEVEL.t GENERATOR OUTPUT MWe..GENERATOR OUTPUT TOTAL CORE FLOW M Ib/hr'TOTAL CORE FLOW RX PRESSURE PIG'X PRESSURE e t Wdg t't~t~~3<-'Ng v D~V~C'(L.eJ5 (Ho~7ae'57" h)n'oe~"'A f(v 8=c.~t~'lWCNe.s'r:~': t I'~'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~~oar v~2 u'c4'zi (e n iS(pJ Q%>7/7/>(~\~wflw u%$u/}P r i'~k 7' 1900 70 0700 1900 3.700 1900 90 00 t 2.3'.4 5;\II'I l 1 vp big PCIIIF,N~~'-

OFFQOINOPLANT'CONTROt OPERATORCH~~~:

'G W 303':t-"~">"."...'g$

>~j&gi~e~g

'"'->Ravks1on 9: 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.'-.'=-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.-

""'lghted control room annuncfators logged and'.dIsc ecL with-oncoming.

PCO.AII control room annuncfators tested succeastufflro

'+t%:.i'g~ggp:I."~cg"-: "'.i"Vi'"~0700 TO 1900~+r': ONCOIINO PLANT CONTROL.OPERATOR CHKCKUST: Reactor Engfneerfng Operating Instructions reviewed.Front and back panele walked down with otfgofng,PCO..

~outlne Training current."'0700 TO 1900'ncomfng, PCO~r~'~1900 TO 0700 Oncoming PCO~~MMtA04A4N4, Her.9.owLs¹togo s ot s VI-16 Attachment G AO-QA-303 Revision 9 SHIFT to Page 64 pf 74 Stan End aHiFT~boo ta~/6 Stan Enact UNIT SUPERVISOR TURNOVER SHEET co/~<~Date UNIT GENERATOR OUTPUT r'Ot~MWe UNIT CONDITION POWER LEVEL GENERATOR OUTPUT MWe REMARKS: UNIT B/7 lo~do 5 Lcm=~re KK S7 7 I c 7 I T8 a willis 7 v (~cnew'e An.n let~L Scil T~SP~SH (-o rlh4~/GAL 0/oon Ac.e~f~P~x/p i/w>a7 sr v a>o~Ai'Cd~cL (v</a@f7-5 rv 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$1d, Rer.d.OUPLSX.P109 2 ot 2 VI-18 PENNSYLVANIA POWER&LIGHT COMPANY'USQUEHANNA SES UNIT 1 SYSTEM AND EQUIPMENT STATUS SHIFT INITIAL CONDITIONS Attachment A AD"QA-303 Revision 9 Page 35 of 74 Date ioA/~~Shift~74 Power Level (MWth)~>>9 Condition Mode Switch Position 1C668 SYSTEM STATUS Shift Respfensible PCO Additional PCO Completed by Reviewed by (umt Supdnnsoe (Shih Supdfvldoe Reviewed by PROBLEMS 6f COMMENTS EHC~~~~~~~~~~~~~~~~~~~h draulic fluid A h draulic fluid B filter turbine va r extr STEAM SEALING'ckin exhauster A ackin exhauster B main steam su I aux steam su I COND DEMIN"" cond demin A cond demin B cond demin C cond demin 0 cond demin E cond demin F cond demin G MIN fl Ogw~~~~~~~~~~~~~FV-10508 RFPT AUX~~~~~~~~~~~~~~tumin ear A tumin ear B tumin ear C AmnLW A AmnLN B B mnLN C B mnLW 0 C mnL E CmnL F A va r extr B va r extr C va r extr I/S I/S auto I/S avl avl man avl unavl I auto unavl unavl r unavl GPM unavl auto Co,a/e P1 form AORA4034, Aev.0, OUPLE4 Pood 1 ot 12 VI-19 Attachment A AO-QA"303 Revision 9 Paga 36 of 74 1C668 SYSTEM STATUS PROBLEMS 4 COMMENTS OPF GAS~~~~~~~~~~~~~~~I I/$ayl unayl SJAE Mvp main aux CIRC WATER"""" i I/S'.avl unavl min full i pump A pump B pump C pump 0 SERVICE WATER'ump A pump B pump C RBCCW~~~~~~~~~~~~~~~~pump A pump B TBCCW~~~~~~~~~~~~~~~~pump A pump B INST AIR'"" compressor A compressor B d erA d erg dryer C I/S I avl lunavl auto I/S avl unavl I/S i avl lunavl Auto Iunavl B 0x 7~Lc gs (~cc SERV AIR~~~~~~~~~~~~~~compressor A compressor B Auto unavl Form Aooh4034, Aer.9.DUPLEX.P~2 of 12 VI-20 UNIT 1 SYSTEM AND EQUIPMENT STATUS Attachment A AD"QA-303 Revision 9 Page 37 of 74 1C651'YSTEM y!/CU~~~~~~~~~~~~~~~~~pump A pump B filter dern A filter dern B STATUS I/S I avl Iunavl PROBLEMS 8c COMMENTS CONDENSATE

"""" I/S I avl pump A pump B pump C pump D unavl Rf PT~~~~~~~~~~~~~~~~~~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~~~~~~~~~~~~~drive motor/pp A drive motor/pp B RECIRC AUXII.IARIES 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 I/S I/S avl i avl unavl unavl auto RECIRC CONTROL'""" auto controller A controller B man ee Speed%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 RMCS~~~~~~~~~~~~~~~~~RWM RBM RSCS MAIN TURB EHC pressure set in control MAIN TURB'" I lift pumps turning gear I/S I/S auto B/P inop B/P list rods bypassed avl unavl auto OIL SYSTEMS""""" TGOP Mn L suet pp EBOP ESOP GEN EXCITATION volta e regulator I/S auto avl unavl man auto lock Form At.JM034.RW.Q.OVPi.EX.P~4 ot 12 VI-22 UNIT 1 SYSTEM AND EQUIPMENT STATUS Attachment A AO-gA"303 Revision 9 Page 39 of 74 1C601 SYSTEM STATUS PROBLEMS Sc COMMENTS CRO~~~~~~~~~~~~~~~~~~~pump A pump B flow contr A flow contr B SBLC~~~~~~~~~~~~~~~~~~squib cont[nuI squib A squib 8 I/S avl iunavl out ge b~'/d'a/P D/W FLOOR SUMPS"" avl unavl sump A pump A sump A pump B sump 8 pump A sump B pump B~~~~~~~~~~~~~~~~~~turb/pump status RCIC control controller I/S GPM avl unavl auto man'tape aetpttint vatue te 4+GPM CORE SPRAY OIV I"'/S pump A pump C RHROIVII/S pump A pump C avl unavl avl unavl RHR SW OIV I'ump A I/S avl unavl APS~~~~~~~~~~~~~~~~~~~~~~~~~system SPOTMOS~~~~~~~~~~~~~~system A system B MSIV STATUS LIGHT'ight indication avl unavl unavl off Tip e~~~~~~~~~~~~~~~~~~~valve indication close open 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 AR15746A AR15746B Ilos.~0 I ST8 STd SUPP POOL FILTER PP" I I/S I avl~unavl punlp I v INST GAS"""""" auto lunavl compressor A compressor 8 Oe5 4ort.Pn 5 STORAGE BOTTLES"" close PCV-12643 open PCV-12648 CORE SPRAY DIV II" pump B pump 0 I/S I avl i unavl RHR DIV II"""""" I/S i avl pump B pump 0 unavl oo S RHRSW DIV II" pump B HPCI~~~~~~~~~~~~~~~~~~turb/pump status HPCI control~~~~~~~~~~~~controller I/S I/S GPM avl avl auto unavl unavl man tape setpoint value 5/<GPM OOS ECCS/BIS STATUS es oos II hts tested all oos li hts off no v-list oos s stems S Form AO~~.Aev.9.OUPLEX.Psg.4 ot 12 VI-24 UNIT 1 SYSTEM AND EQUIPMENT STATUS Attachment A AO"qA-303 Revision 9 Page 41 of 74 T-10 118 12B T-20 BUS 10 12 BUS 20 13.8KV El El El IZl E1 ElŽ~~m GEN 2 500 KV LEADS SUNBURY 2 500 KV LINE WESCOSVILLE 500 KV UNE 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 MISCELI.SYSTEM STATUS Miscellaneous PROBLEMS 4 COMMENTS RECOMBINER

""""" ,'I/S i avl unavl unit 1 unit 2 common CCW pp 1P145 unit select switch position-unit CCW pp 2P145 CCW pp OP145 UNIT 2 ECCS~~~~~~~~~~~U-2 RCIC 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 I/S avl I unavl~wet g4rAa~~v-C(J 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 SUBJECT, UNIT 1 CONTROL ROOM ANNUNCIATOR LQG Approved By Section Head Pre ared B: Reviewed B Date+~+Pk Expiration Date Effective Date FORM AD-QA-101-5, Rev.1, Page 1 of 1 VI-31 UNIT 1 CONTROL ROOM ANNUNCIATOR LOG"CAUSE/CORRECTIVE ACTION" MON TUE Wf 0 THU FR I SAT SUN (0//9 fo/<5-g%6, lo/I 7 s4/g$lo/g9 so/go~N~N~N~i'I~N~N~N AR 101 1C651 AR 102 1C651 FORM OI-AL-0017 Rev.1, Page 1 of 17 VI-32 UNIT 1 CONTROL ROOM ANNUNCIATOR LOG"CAUSE/CORRECTIVE ACTION" Week Ending I>/Eel 9(~N~N~N~N~N~N~N AR 103 1C651 AR 104 1C651 FORM OI-AL-0017 Rev.1, Page 2 of 17 VI-33 UNIT 1 CONTROL ROOM ANNUNCIATOR LOG"CAUSE/CORRECTIVE ACTION" Meek Ending Io/24/9)~N~N~N~N~N~NAR 105 1C651 t:-I4 H'VAC IC Z7i'.T s STI%T VAC IC 27 ST Tow AR 106 1C651 I 0 0 C7-Ii'HC IC 7 IS I I%i IS I FORM OI-AL-0017 Rev.1, Page 3 of 17 UNIT 1 CONTROL ROOM ANNUNCIATOR LOG Week Ending le/z+/~9~N~N~N~B~N~N~i'I"CAUSE/CORRECT I VE ACTION" AR 107 1C601 AR 108 1C601 FORM OI-AL-0017 Rev.1, Page 4 of 17 VI-35 UNIT 1 CONTROL ROOM ANNUNCIATOR LOG"CAUSE/CORRECTIVE ACTION" Week Ending io l~c I~9~N~N~N~N~N~N (AR 109 1C601 AR 110 1C601 FORM OI-AL-0017 Rev.1, Page 5 of 17 VI-36 UNIT 1 CONTROL ROOM ANNUNCIATOR LOG"CAUSE/CORRECTIVE ACTiON"!Week Endiag/o/g.o/9(~N~N~N QN~MI~N~N AR 111 1C601 AR 112 1C601 B FORM OI-AL-0017 Rev.1, Page 6 of 17 VI-37 UNIT I CONTROL ROON Week EndIng zo/~c,/qg ANNUNCIATOR LOG~N~N~N~N~N~N N IICAUSE/CORRECTIVE ACTION" 8-dR/~$ucu AR 113 1C601 AR 114 1C601.FORM OI-AL-0017 Rev.1, Page 7 of 17 VI-38 UNIT,1 CONTROL ROOM ANNUNCIATOR LOG"CAUSE/CORRECTIVE ACTION" Week Ending/o/~o/9(4~N~N~N~~I<I~i'1 1 I~N~N C-o D Da AR 015 OC653 C-l3'P c.0 l3-f csT'i0 cmp//PIURc oc.5 7C C-/S~Eo>tert A AR 016 OC653 0 E FORM OI-AL-0017 Rev.1, Page 8 of 17 UNIT 1 CONTROL ROOM ANNUNCIATOR LOG'CAUSE/CORRECTIVE ACTION" Week Ending go/3 o/g i~N~N~N~N AR 117 1C668 AR 118 1C668 F FORM OI-AL-0017 Rev.1, Page,9 of 17 VI-40 UNIT 1 CONTROL ROOM ANNUNCIATOR LOG"CAUSE/CORRECTIVE ACTION" Week Ending lo/~e/~q~N'~N~M~N~N~N~N AR 119 1C668-0 C~riz AR 120 1C668)o FORM OI-AL-0017 Rev.1, Page 10 of 17 UNIT 1 CONTROL ROOM ANNUNCIATOR LOG"CAUSE/CORRECTIVE ACTION" Week Ending lo/<o/~~N~N~N~N~M~NAR 121 1C668 AR 122 1C668 , FORM OI-AL-0017 Rev..1, Page ll of 17 VI-42 U NIT 1 CONTROL ROOM ANNUNCIATOR LOG"CAUSE/CORRECTIVE ACTION" Week Ending/o/kc/~~N~N~N~N~N~N~N AR 123 1C668 AR 124 1C668 FORM OI-AL-0017 Rev.1, Page 12 of 17 VI-43 UNIT 1 CONTROL ROOM ANNUNCIATOR LOG"CAUSE/CORRECTIVE ACTION" Meek Ending lo/ko/~9~N~N~N~N~N~N~AR 029 OC681 A AR 030 OC681 A FORM OI-AL-0017 Rev.1, Page 13 of 17 VI-44 UNIT 1 CONTROL ROOM ANNUNCIATOR LOG 0"CAUSE/CORRECTIVE ACTION"!Meek Ending/o/~o/~~N~N~i%~N~N~N AR 127 1C681 AR 128 1C681 FORM 01-AL-0017 Rev.1, Page 14 of 17 vI-45 UNIT 1 CONTROL ROOM ANNUNCIATOR LOG"CAUSE/CORRECTIVE ACTION"!Meek Ending/o/go/~~N~N~N~i8~N~N Q 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 ANNUNCIATOR LOG"CAUSE/CORRECTIVE ACTION" Week'Ending go/go/~I~N~N~N~N~N~iV~N 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)PCO Nightshift (time)PCO Oayshift (time)PCO Afternoonshift (time)US Afternoonshift (time)~l+'0 9(~II'$(Ql>I+9 Qlo syQ+l4 I+tf~lo i~~0 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: TUESDAY: Sunny to partly sunny during the day.Clear tonight.'ncreasing cloudiness with showers and possibly some thunderstorms developing during the afternoon and ending at night.Allentown TEMPERATURES TUESDAY 0400 1100 Min Time 60-75 58 0600 WINDS 0900 Max Time'inds 74 1500 NE 9 8 Harrisburg/

Lancaster 63 77 61 0600 78 1300 NE 8 4 Hazleton/Scranton'Williamsport 58 59 72 56 0600 72 1500 SE 6 3 74 57 0600 75.1400 NE 8 6 WEDNESDAY THURSDAY: FRIDAY: Mostly sunny during the day.Fair to partly cloudy at night.Average Max.Temp.74;Min.58 Partly sunny during the day.Becoming cloudy at night with a chance of some showers and thunderstorms.

Average Max.Temp.80;Min.65 Variable cloudiness with a few scattered showers.Average Max.Temp.78;Min.58 VII-2 91OCT08 ls MIN AUG PER IOO ENOING AT'$~$$$~5$$18:08 18: 15 18l30 18:45 19:00 STAB~$$$C C F F G ORILL METEOROLOGICAL CATA LOG Is-minute Averages UPpor Onsito Lovel Tower PPT MIXING WINO WIND TYPE OPTH<fs)FROM MPH FROM MPH S~S~S~$$$$~~S~S Sss~S~S$$$14ee 11 7 358 5 1480 158 4 157 5 1400 149 3 149 4 1400 130 3 132 4 1400 128 3 128 4 Vari Towe WIND FROM S~S 12 153 149 132 129 MPH sas 4 5 3 3 oole~teh Oownriver M Tower Sw W I iiO FROM MPH Sl sass ssa ss 37 5 3 150 4 3 148 4 1 135 3 1 134 3 1 Sw$$3 9l>>'9+9>>STPEAM 13:31 07r'02i91 19: IS 19:30 19:45 20:00 20: 15"0:30 20 45 21:00 21:15 21:30 21145 22 ee C--1400 120 G--1400 123 c--140e 80 c-14ee 81 c-14ee lse F--1400 150 F--14ee 13e F--1400 129 14eo le4 F--14ee I e4 F--1400 80 G--1408 91 3 123 4 3 124 4 s ee 4+83 4 4>>152 4 4 152 3 4 130 3 4 127 3 3 104 4 3 184 4 3 81 4 4 98 3 125 3 125 3 83 5 83 5 152 5 152 4 130 4 130 4 186 3 186 3 80 3 92 3 124 3 1'.24 3 1 85 5 1 82 5 1 153 5 1 152 4 1 130 4 1 129 4 103 3 I 103 3 I 81 3 I 97 4 I 9>>4>>ew 9w 4$4$VIT.-3 SECTION VII-RADIOLOGICAL CONDITIONS PART A-OFFSITE RELEASE DATA Section 2-Plume Trajectory and Plume Deposition Data VII-4 SELECTEO FILE: ORILL$-91OCT08-22,00 PRESENTATION T ItlE: 13: 00 07812/91~, WEST r"'~NANT I COKE/r I tE NANT I CORP)0"/I I NES GREC K STREAH PUFF PLOT Puff Locotions Sictnificonce OATA FROH,'2,'88 IO/O3/)I ONSITE Nl)IO.'mph 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 REV 7/19/91 INDIVIDUAL VENT RELEASE RATES QCI/min)TIME FROM TO RB1 NG TB1 NG SGTS NG TB1 l-131 SGTS I-131 15:00 18:00 18:15 18:30 18:45 19:00 19:15 19:30 19:45 20:15 20:45 21:00 21:15 21:30 21:45 18:00 18:15 18:30 18:45 19:00 19:15 19:30 19:45 20:15 20:45 21:00 21:15 21:30 21:45 1.70E+03 5.10E+03 5.12E+03 5.21E+03 5.23E+03 5.26E+03 5.26E+03 5.26E+03 5.28E+03 5.30E+03 5.19E+03 5.26E+03 5.32E+03 5.33E+03 0.00E+00 0.00E+00 0.00E+00 1.50E+03 1.71E+03 1.66E+03 1.61E+03 1.57E+03 1.53E+03 1.49E+03 2.30E+01 8.12Et03 2.37E+04 4.08E+04 5.75E+04 7.33E+04 8.80E+04 1.50E+00 7.33E+04 7.32E+04 7.32E+04 7.31E+04 7.30E+04 7.30E+04 3.10E42 7.08E42 2.16E41 3.87E41 5.65E41 7.44E41 9.22E41 REV 7/19/91 TIME SITE TOTAL VENT RELEASE RATES (gCI/min)FROM 15.'00 18:00 18:15 18:30 18:45 19:00 19:15 19:30 19:45 20:15 20:45 21:00 21:15 21:30 21:45 TO 18:00 18:15 18:30 18:45 19:00 19:15 19:30 20:15 20:45 21:00 21:15 21:30 21:45 NOBLE GAS 5.04E+03 1.01E+04 1.02E+04 1.03E+04 1.03E+04 1.03E+04 1.03E+04 1.03E+04 1.03E+04 1.03E+04 1.02E+04 2.01E+04 3.57E+04 5.28Et04~6.41E+04 7.99E+04 9.45E+04 h131 4.43Et00 7.33E+04 7.32E+04 7.32E+04 7.31E+04 7.30E+04 7.30E+04 PARTICULATES 7.15E41 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 TIME AFFECTED SECTOR DOSE RATE (mrem/hr)WHOLE BODY THYROID WHOLE BODY THYROID PROJECTED DOSE (mrem/hr)20:45 21:00 21:15 21:30 21:45 WNW W W 1.25E+00 1.66E+03 1.20E+00 1.65E+03 8.87E41 1.23E+03 8.51E41 1.23E+03 4.91E41 7.38E+02 1.18E+00 1.85E+03 5.15E+00 5.36E+00 3.77E+00 3.90E+00 2.17E+00 5.43E>00 9.91E+03 1.03E+04 7.38E+03 4.42E+03 1.13E+04 VII-9 9 I OCT08 I.BE+12 NOBLE CAS RELEASE RATE TRENDING PLOT Csiiorocurios por tninuto)STREAN 13: 21 07/I 2'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 1930 1945 2080 2015 2030 2045 2100 115 2130 2145 2280 1.BE+02:XIT-to exit STREAN, or any Function Key VII-10 910CTOS I.BE+87 IOOINE-131 RELEASE RATE TRENDING PLOT (microcurias par ainuta)STREAII 13: 23 078!2i91 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.BE~02 I I 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 AT THE EPB (eiIIir em)PRESEHTATlOH TINE!13:06 87/12/91 10000 9eee 90oe sooe 8008"eee 7000 6008 60ee 5000 4eeo seee 4ooe 3000 3008 2eoo 1000 2oee 10oe Data Period Qf Ca I au I a t i oni.o proJ'd Release 1938 1945 28ee 2e1S 2e38 2e4S 21ee 211S 2130 214S 22ee 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 28 w5 STREAH EXPAllDED PROJECTED THYROID DOSE PLOT ExPected Dose Totals if the Release Lasts 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 1 Entire Ptuae Trover ses the 10 ai.EFZ Q4 22 DATA UP TO,'I6',42 i%3/89/91 21 20 QUADRANT'tlIl 19 8~33, E82 1 2 3 4 5 6'8 9 10 11 12 13 14 1'5 16 E"XIT-to exit STREAH, or any Function Key K 9 (ttR tt)-.-:Eh~5000 or 4bove REe~2500-4999 Q 250-2499 GREEtl~1-249 VII-13 T F R s 9 T PRESENTATION TIME l 13: 02 07812i91 16 15 13]2 I$$'$r'/I$$$z)'$'$$$'$$$$$'$$$$y.r OATA UP TO,'6,'42 IO/O3/!I STREA1'1 EXPANOEO PROJECTEO THYROID DOSE PLOT Ex$$eated Dose Tot.el s i f the Release i asts 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> T$Eat ir e Plume Traverses the 10 ml.EPZ QUAORANT,'ll 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 FXIT-to exit STREAH, or any Function Key SE K Y<MR Mi g m000 or Above REG~2500-4999 0 250 2499 CREEN~1-VII-14 SELECTEO FILE: OPILLs-SIOCTB8-22.BB PRESENTATION TIME: 13'12 Bi.12i&I',, WEST N44T I COKE IO,/j" SHI CKSH//<<I%r OATA VP TO',?2,'O8 18/68/91 STREAN OEPOSITIOH PLOT ExPoctod 4roas and Ralati;o 4aiounts of 4CtiVi ty Oorcsi ted on the Gr ound/NESS ECK'r I L'.//'/I X r'4)LETON MINIMUM V4LVE OF INTEREST IS: 1E-1B CI/M++2 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,'rf SOOOOSOOsfl C Orlf ass~OOOCOfSS 4 s~~ssOT~eslC O Os I Css%4vC sssssl~ssfoor sss tOO ss lr Oss C Cssf\4~oOO.I RELEASE: 20:45 to 21:00 C Li L~'l~l Of ssO CCsieTaaf/, OCCOClf Oss llCl~OOffCIIO Oss sssssr~S,s CO I OaossaOra i~COO sossf 1 I%4OCT COOsC 4 rr~OsssOO sofar ssosrf I OsOCCI.Of OOOlrOO~.WscOsssO II~ICOflf Osr SOOl~ssf 4 lsrrsoo~sosscrs oa 5OI IOQI STiTihN RELEASE: 21:16 to 21:30'1~oTs sssf 4 I~4/('VII-17 TIME PERIOD ENDING 20:45 OSC hR: 0.35 EPB.0.54 SECT Ml 2 MI: 5 MI: SECT MI I 0 MI: SECT hRR IV hL DIST VB-NG 3 FT (CY)3 FT (OY)3 IN (CY)3 IN (OY)TIME SECTOR (MILES)(MR/HR)(MR/HR)(MR/HR)(MR/HR)(MR/HR)CPM/100 CM 2 THY MR/HR)I-1 Z1 C hRT.(CI/cc)(NCPM)20 32 20 34 20 36 20 38 20;40 20 42 20 44 20 A6 20 AS 20:50 20.55 21,00 21'05 21."10 21:15 21.20 21 25 21;30 21:35 21:40 21:45 2I.50 22.10 22 30 22:50 23.10:.'3.30 NV I'IV NV NV NV NV NV NV NV le NV I'IV NV NV NV NV NV NV NV NV NV NV~r'L(r V 1.5 1.5 1.4'I.3 13'I.2 1.1 1.1 1.0 0.10 020 0.30 OAO 0.50 060 070 080 0.90 1.0 1 25 1 50 1 75 0.8 06 0.5 0.3 Q 03 P2 P2 Q2 P2 0.2 0.1 2.25 250 2.75 3.00 3.25 3.50=.75 4.00 00 0,0 0.0 0.0 00 6.00 7.00 8.00 9.00:10 IM:: 00 1.6 1.5 1.4 lA 1.3 1.2 1.2 1.1 1.0 1.0 0.8 0.6 0.5 0.3 0.3 02 0.2 0.2 p 7 Q 7 O.I 0.0 0.0 00 OQ 1.8 1.7 1.7 1.6 1.5 1.4 1.4 1.3 1.2 0.9 0.8 0.6 0.4 0.3 0.3 0.3 0.3 P 2 Q 0.2 0.1 0.0 0.0 Q.P il.l I 0.0 00 223.3 213.9 204 6 195.2 185.9 176.,5 167.2 157.8 148.5 139.1 115.8 92.4 69.1 45.7 42.3 38.9 35.5 32.0 28.6 21.8 18.4 48 3.8 1.9 10 0,0 264.1 253.1 242 P 73P 9 219.9 208.8 197.S I 86.7 175.7 164.6 137.0 109.3 81 7 50,0 460 42.0 379 339 29.8 258 21 8 5.6 4.5 3A a 1 00 1.18E+04 1.14E+05 1.09E+05 1.04E+05 9.91E+04 9.42E+04 8.94E+04 8.46E+04 7.97E+04 7A9E+04 6.28E+04 5.07E+04 3.86E+04 2.65E+04 2.43E+04.21E+04 1.99E+04 1.77E+04 1.56E+04 1.34E+ii4 1.12E+04 9.00E+0 2.i SE+02~.22E+02 1.67E+02 1.11E+I.'5.56E+il1 1.I3E-Q.=.2028 1945 1862 1779 1696 1614 1531 1448 1365 1282 1075 867 660 416<<<<8 341 304 266'729 I54 0 5.92E-07 5 68E-07 5 44E-07 5 20E-07 4 95E-07 4 71E-07 4 47E-07 4 23E-07 3.99E-07 3.74E-07 3,14E-07 2 5~E-07 93E 07 1 32E-07 1 21E-07 1.I OE-07 9 96E-08 8 87E-08 7 78E-OS 6 68E-08 5 59E-08 4.50E-08 1 39E-09 I 11E-09 8 34E-10 5 56E-10 2 78E-I 0 r 15E-15 1676 1608 1539 1471 1402 1334 1265 1197 1128 1060 888 717 546 251 22P 1S9 158 127 TIME PERIOD ENDING 21:00 OSChR: EPB: MI 0,35 0.54 SECT NV NV Ml 2 Ml: 5 Ml: SECT NV V Ml I 0 MI: SECT hRR IV AL DIST VB-NG 3 FT (CV)3 FT (OY)3 IN (CV)3 IN (OV)TIME SECTOR (MILES)(MR/HR)(MR/HR)(I IR/HR)(MR/HR)(MR/HR)CPM/100 CM 2 1'HY MR/HR)1-1 31 (Ci/cc)CART.(NCI M)20.47 20.49 20:51 20.53 20 55 2D:57 20.59 21.01 21.03 NV NV NV NV NV NV I'IV I'IV I'IV 0.10 0.20 0.30 0.40 0.50 0.60 0.70 0.80 090 15 1.4 IA 1.3 1.2 1.2 1.0 10 1.5 IA IA 1.3 1.2 1.2 1.1 I.l 1.0 1.7 1.7 1.6 1.5 1.5 1.4 1.3 1.2 1.2 214.3 2n5.4 196A 187.4 178.5 169.5 160.6 151.6 142.7 253.5 2429 202.4 221.8 21 1.2 200.6 190.0 179.4 168.8 I.I 8E+04 1.13E+v5 1.08E+05 1.03E+05 9.85E+04 9.37E+04 8.89E+04 8.41E+04 7.92E+04 016 1933 1851 1769 1686 1604 1522 1439 1~57 5.89E-07 5.65E"07 5.41E-Q7 5,16E"07'92E-07 4 68E-07 4 44E"07 4.OE-07 3'96E-07 I 666 l598 1530 1462 1394 1326 1258 1189 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 21:15 21:20 I'IV I'lV NV 1.25 1.50 1.75 0.8 0.6 0.5 0.8 0.6 0.5 P 9 0.7 0.5 111.3 88.9 66.5 131.7 I 05.2 787 6.24E+04 5.04E+04 3.84E+04 1069 863 657 3 12E-07 2 52E-O7 I 92E-07 883 713 543 21.25 NV::.::2Ã$

03 0.3 522 2.63E+04 451 I 32E-07~3 21:30 21:35 21:4D 21:45 21.50 21:55 22;00 22:05 22 25 22:45 23.05 r,5 23 45 0:05 NV NV I'IV I'lV NV I'IV I'lV NV V V 2.25 2.50 2.75 3.00 3.25 3.50 4 00 6.00 7,.00 8.00 9.00 03 03 P2 0.2 Q 2 P 2 0.1 0.1 0.0 0.0 0.0 0.0 00 0.,0 0.3 0.3 0.2 0.2 0.2 0.2 0.1 D.l 0.0 0.0 D.D D.Q DD Q.n 0.3 0.3 0.3 Qr3 Q 0 r 0."2 O.I 0.0 G.Q 0.0 G.l I Q.n G.U 40.8 37.6 34.3 31.0 27.8 24.5 17.9 49 3.9 29 1.9 1.0 0.0 48.3 44A 40.6 36.7 328'N p 25.1 21 2 4.6 3A 2A2E+04 2.'GE+04 198f<<04 1.76E<<04 1.5 E+04 1.33E+04 1.1 I E+04 8.95E+03 2,53E+0 2.02E<<02 I.52E+02 I.01 E+0"=:.06E+01 6.I;::E-04 339 02 265 l90 I53 n 1 21E-07 I 10E-07 9.9 I E-08 8 82E-08 7.74E-08 6.65E-08 5 56E-08 4 47E-08 I 26E-09 I DIE-09 7 59E-10 5 06E-I 0~53E-10 3 24E-15 342 311.280 250 219 188 157 127 0 TIME PERIOD ENDING 22:25 OSChR: EPB: Ml 0.41 0.69 SECT VNV VNY Ml 2 Ml: 5 MI SECT YNV V 10 Ml: SECT hRR IV hL DIST VB-NG 3 FT (CV)3 FT (OV)3 IN (CV)3 IN (OV)TIME SECTOR (MILES)(MR/HR)(MR/HR)(MR/HR)(MR/HR)(MR/HR)CPM/IOO CM 2 TIIY MR/HR)1-132 C hRT.(Ci/cc)(NCPM)21.01 21:03 21:04 21;06 21.07 21.09 21:10 21 12 21'13 VNV VNV VNV VNV VNV VNV'v<N'r<'f'I'rr'flV 0.10 0.20 0.30 0,40 050 0.60 0.70 0,80 090 1.2 1.1 1.1 I 0 1.0 0,9 09 08 0.8 1.1 1.1 1.0 1.0 0.9 09 0.8 0.8 1.3 1.3 1.2 1.2 1.1 1.0 1.0 0.9 172.2 164.9 157.6 150.3 143.0 135.7 128.4 121.1 113.8 203.8 195.1 186.5 177.8 169.2 160.5 151.9 143.2 134.6 9.54E+03 9.14E+04 8.74E+04 834E+04 7.94E+04 7.55E+04 7.15E+04 6.75E+04 635E+04 1633 I 565 1496 1428 1360 1292 1224 1156 10SS 4.77E-07 4 57E-07 4 37E-07 4,17E-07 3 97E-07 3.77E-07 3 57E-07 3.38E-07 3.18E-07 1349 I'293 l237 1180 11 4 1068 1011 955 899 21:15 Vf4V1'NG" 0.7 0.7 0.9 106A 125.9 595E+04 1019 2.98E-07 21:18 21'22 21:26 VflV Vfl'r<'NV 1.25 1 50 1 75 0.6 0,5 0.4 0.6 0.5 OA 0.7 0.6 OA 88.2 69.9 51.6 104.3 82.7 61.1 4.96E+04 3.96E+04.97E+04 849 a w9 508 2 48E-07 1.98E-O r 1 ASE-07 702 561 420 21.30 VN'r<2>D" 0.2 0.2 39A 1.97E+04 338 9.87E-GS 2'79 21:33 21 37 21-.41 21;45 21.48 21:52 21:56 22.00 VNV VNV'vjl'Pr(VNV'v<NV v<'NV VNV Vf4'v<'.25 2.50 2.75 3.00 3.25 3.50 3.75 4.00 0.2 0.2 02 0.2 0.2 0.1 0.1 0.1 0.2 0.2 0.2 0.2 0.2 0.2 O,l 0.1 0.3 P2 p Q 2 0.2 p Q 0.1 it.4 29.5 27.5 25.6 21.7 19.8 1 7.8 37 1 34 8 32.6 303 28 0 257 Q3 21 1 1,82E+04 1.66E+04 1.50E+04 1 34E+04 1.18E+04 1.02E+04 8.64E+03 7.i<6E+03 311 284')g<229 202 175 l48 121 9 GSE-08 8 29E-OS 7 49E-08 6 70E-08 5 9 I E-08 5 12E-08 4 32E-08 3 53E-08 257 234 212 190 167 145 100 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 22:45 23:GQ>3'15 23"<J sC II v<r 6.00 7.00 8.00 9.00:2 0:IM::: 0.1 0.0 0.0 0.0 00 Q.1<ip 0.0 0.0 Q.Q 0 I O.I P.p 0.0 P.Q 8.3 6.6 4.8 30 13 9.8 7.8 5.7 1 5 5.82E+02~1 A6E+02 3.1 QE+0 1.73E+P.".71E+0 1 10 8 5 2 9 I E-09 2 23E-09 1 55E-<i9 8 67rE-I 0 1 8-E-I 0 TINE PERIOD ENDING 21 30 OSCAR: EPB: 0.41 0.69 SECT YNV YNV Ml 2 Ml: 5 Ml: SECT Ml 10 MI: SECT ARRIVAL DIST VB-NG 3 FT (CV)3 FT (OV)3 IN (CV)3 IN (OY)TIME SECTOR (MILES)(MR/HR)(MR/HR)(MR/HR)(MR/HR)(MR/HR)CPM/I OO CM 2 THY MR/HR)I-1 31 (Ci/cc)C-ART.(NCPM)M M I hD 21'16 21"IS 21;19 21.21 21 22 21'24 21:25 21 27 21:28 VNV VNV VNV VNV VNV VNY'v/NV VNV VNV 0.10 0.20 030 0.40 0.50 0.60 0.70 0.80 0.90 1.1 1.1 1.0 1.0 0.9 0.9 0.8 0.8 0.8 1.1 1.1 1.1 1.0 1.0 0.9 0.9 0.8 0.8 13 1.3 1.2 1.2 I.I 1.1 1.0 0.9 0.9 165.2 158.2 151.2 144.2 137.2 130.2 123.2 116.2 109.2 195.5 187.2 178.9 170.6 162.3 154.1 145.8 137.5 129.2 9.54E+03 9.14E+04 8.74E+04 8.34E+04 7.95E+04 7r.55f+04 7.15E+04 6.75E+04 6.35E+04 1634 1565 1497 1429 1360 1292 1224 1156 1087 4 77E-07 4.57E-07 4.37E-G7"4 17E-07 397E-07 3 77E-07 3 57E-07 3 37E-07 3 I SE-07 1350 1294 I 237 1181 I124 1068 1011 955 899 21:30 VNV'.7 0.7 0.8 102.2 120.9 5.9SE+04 1019 2.9SE-07 21:33 21:37 21:4 I 21 45 21 48 21 52 21.56 22.00 22 03 22.07 22.11 22'15 22 30 22;45 23:00 23:15 23'30 23'45 VNV VNV VNV'vFNV'vFNV'vF IIV VNV VFNV VNV VffvF VNV'rF'vF vl'vF'vF'vF 1 25 1 50 1.75 225 2.50 2.75 3.00 3.25 3.50 3.75 4.00 6.00 7 00 8.00 9.00:.:I 0:.'00: 0.6 0.5 03 Q2 02 02 0.2 0.2 P2 0.1 01 0.1 0.1 0.1 00 00 00 0.0 0.6 0.5 0.3 P 2 0.2 p Q 2 0.2 0.2 G.I O.I O.I 0.1 0 I 0.0 0.0 O.G 00 0.7 0.5 Q 0.2 Q2 0.2 0.2 0.2 P 2 0.1 0.1 0.1 0.1 0.0 O.G 0.0 84.7 67.2 49.7 3>2~p 28.5 26.6 22 9 2'I.0 19.1 17.3 8.1 64 4.6 29 12 100.2 795 58,8 38.1 35.9 337 31 5 29 2 27.0 248 22.6 204 116 9.6 7.5 5.5.5 4.9SE+04 3.96E+04 296E+04 1.96E+04 1.8GE+04 1.65E+04 1.49E+04 I 33E+04 1.17E+04 1.02E+04 8.59E+03 7.02E+0;13E+02 5.7 r E+02 4.42E+02 3,Ij7f+0.I,;2E+II~3.63f+Il I 848 677 507 309 282 255 228 201 174 147 120 12 10 8 5 2 48E-07 I 98E-07 1.48E-07 9 81 E-08 9 02E-08 S 24f-08 7 45E-OS 6 66E-GS 5 87E-08 OSE-08 4 3GE-08 3 SIE-OS 3 56f-09 2 89E-09 2 21 f-09 I 53E-09 8.58E-I 0 I 8 I E-I I3 701 560 419 278 23~211 I S8 166 144 122 99 10 OFFSITE MONITORING TEAM PLUME TRAJECTORY aaasata ass Ipasa ss~sssal I'sasatsl~atyattw i"wa i~a"esl Ll as~aa~~C I\v54vawsssssa Iaaaa<Sa 544 was Oss II Wt I 4~aa4 I RELEASE: 22:00~CO.I aa4I I II IO aata~aatstk wwwwt I i4w.asO.wats t~acsa'rT aaessaei i~at 4~I tt isa ccs aitet/,~ac ass~~)~aassaas44 Catv sct ass4~aaa astatl atsst4afa4

~Wsl Osssa r'I I aacatat ass aaaa~Icatat'asa aaaa CS~I aatlsc T~ss ass~tl, p I saaatsaasn 4aatt.n~'vt'\sarsaa~sass csss at I~a@a salsa RELEASE: 21:45 VTI-22 TIME PERIOD ENDING 21:45 OSCAR.EPB: 0.37 0.61 SECT Y V 2 Ml: 5 Ml: SECT Ml 10 MI.SECT VSY ARRIVAL DIST VB-NG 3 FT (CY)3 FT (OV)3 IN (CV)3 IN (OV)TIME SECTOR (MILES)(MR/HR)(MR/HR)(MR/HR)(MR/HR)(MR/HR)CPM/100 CM 2 THY MR/HR)I-131 CART (Ci/cc)(NCPM)21 31 21.33 21 34 21'36 21'37 21:39 21 Ap 21 A2 21.43 21 A5 21 A8 21:52 21.56 22:00 22:03 22 07 22 11 22:15 22 18~2 22 22 22'30 22 45 23.00 23.15 23 30 23:45 Q:00 V V V V V V V V V V V V'lyl V V V'Eg C V v(SV Y(S'('SV'y(QV VSV 0.10 0.20 0,30 040 0.50 060 0.70 0.80 090 1 25 1.50 1.75 225 250 2.75 3.00 325 350 375 4 00 6.00 7.00 8.00 9.00::1O:.'OO.0,6 0.6 0.5 0.5 0.5 0.5 0.5 OA OA 0.4 0.3 03 p 0.2 0.2 0.2 0,1 0,1 0.1 0.1 0.1 0.0 00 0.0 00 0.0 0.0 0.6 0.6 0.6 0.5 0.5 0.5 0.5 0.5 OA OA OA 0.3 0.3 0 2 0.2 02 0.2 0.1 0.1 O.I 0.1 0.1 0.0 0.0 0.0 0.0 0.0 rj.p 0.7 0.7 0.7 0.6 0.6 0.6 0.6 0.5 0.5 0.5 0.4 0.4 0.3 0.3 P2 P 2 P 2 p 0.1 0.1 Q.l 0.1 0.0 0.0 0.0 0.0 0.0 0.0 86.2 83.3 SOA 77.5 74.6 68.8 65.9 63.0 60.1 52.9 45.7 38A 28.6 26.0 23 4 20 9 18.3 g 13,2 10.6 0.3 0.2 0.2 0.1 01 00 102.0 985 95 I 91 7 883 84 S 81 4 780 74 6 71.1 62 6 540 45A 338 30.8 24 7 21.6 18.6 156 125 0.3 0.3 0.2 0.1 O.l 5.17E+03 S.0QE+04 4.83E+04 4.66E+04 4.49E+04 4.32E+04 4.15E+04 3.99E+04 3.82E+04 3.65E+04 3.22E+04 2.SOE+04 2.3SE+04 1.96E+04 1.79E+04 1.63E+04 1.47f+04 I 31 E+04 1.1-1E+04 9 SOE+CI3 S.l E+Q.=.6.54E+03 2.3SE+01 I upE+0 I 1.43E~QI"..51E+QP 4.76E+QP 1.QE-03 S85 856 827 798 769 740 711 682 653 625 552 480 407 307 279 251 223 196 168 140 112 0 0 0 0 2.58E-07 2 50E-07 2 42E-07 2 33E-07 2 25E-07 2 16E-07 2 OSE-07 I 99E"07 I 91E-07 1.82E-O7 I 61E-07 I 40E-07 1.19E-07 9.7SE-OS 8 97E-08 8 15E-08 7 34E-OS 6 53E"08 5 71E-08 4 90E-08 4 OSE-08 3 27E-08 I 19E" 10 9 51E-11 7 13E-I I 4 75E" 11 2 38E-11 93E" 15 731 708 684 660 636 612 588 564 540 516 456 397 337 277 254 231 208 185 162 139 116 93 0 0 0 0 0 0 TIME PERIOD ENDING 22:00 OSCAR: EPB: Ml 0.37 0.61 SECT Y Y Ml 2 MI: 5 Ml SECT V VSV Ml 10 Ml: SECT ARRIVAL DIST VB-NG 3 FT (CY)3 FT (OY)3 IN (CV)3 IN (OV)TIME SECTOR (MILES)(MR/HR)(MR/HR)(MR/HR)(MR/HR)(MR/HR)CPM/100 CM 2 THY MR/HR)1-131-CART.(Ci/cc)(NCPM)21:46 21.'48 21 49 21:51 2152 21 54 21'55 21'57 21 58 V V V V V'r(V V Qr 0.10 0.20 0.30 0.40 050 060 0.70 0.80 0.90 1.4 13 1.3 1.3 1.2 1.2 1.1 1.1 1.1 1.4 1.4 1.3 1.3 1.2 1.2 1.2 1.1 1.1 1.6 1.6 1.5 1.5 1.4 1A IA 13 1.3 202.4 196A 190A 184 A 178A 172A 166A 160A 154A 239 4 225 2 218.1 211.0 203.9 196.8 189.7 182.6 l.26E+04'l.23E+05 1.19E+05 1.15E+05 1.12E+05 1.08E+05 1.05E+05 1.01E+05 9.76E+04 2161 2100 2039 1977 1916 1855 1794 1671 6 31E-07 6 13E-07 5 95E-07 5 77E-07 5 60E-07 5 42E-07 5 24E-07 5 06E-07 4 88E-07 1786 l735 1685 1634 1584 I 533 l482 1432 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 22 07 22:11 22:15 22'18 22 22 22 26 22:30 22 22.37 22'41 22 A5 23.00 23:15 pp e tQ 23 45 0:00 V V V V V V V Ie(II V VS'(VSV VSV VS'rF'a)rSV 1 25 1.50 1.75 250 2.75 3.00 3.25 3:50 3.75 4.00 6.00 7.00 8.00 9.00 0.9 0.8 0.7 0.6 06 0.5 0.5 OA OA 03 0.3 0.2 0.0 0.0 Q.O 0.0 0.0 09 0.8 0.7 0.6 0.6 0.5 0.5 0.4 OA 0.3 0.3 0.2 0.0 0.0 0,0 Q,Q 1.1 1.0 0.8 0.7 0.7 0.6 0.5 0.5 0.4 OA 0.3 0.2 0.0 0.0 0.0 O.Q 0.0 133.3 118.3 l 03.3 883 81.0 73.8 66.5 59.2 51.9 44.6 37.4 30.1 0.9 08 06 0.4 Q I 57.7 140.0 122.2 104.5 95.9 873 786 700 61 4 528 2 356 09 0.7 0.5 Q2 8.51E+04 7.62E+04 6.72E+04 5.83E+04 534E+04 4.86E+04 4.3 r E+04 3.89E+04 3.40E+04=.92E+04 2.43E+04 1 94E+04 9.23E+00 7.38E+00 5.54E+u0: 69El00 1 85E+00 1457 1304 1151 8~~749 665 58~499 416 0 Q 0 0 0 4 26E" 07 3 81E-07 3.36E-Q 7 2 91E-07 2 67E-07 2 43E-07 2 19E-07 1 94E-07 1 7QE-07 I 46E-07 1 21E-07 9 72E-08 4 61E-11 3 69E-11 2,77E" I 1 1 85E-11 92 1204 1078 951 825 756 687 619 550 481 412 344 275 0 0 0 0 0 0." l 5 rF:.10':OO:::

0 0 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 IODINE-132 4,8 E4 IODINE-133 5.5 E4 IODINE-134 8.7 E4 2.4 E4 4.5 E4 5'E4 7.2 E4 2.4 E4 4.2 E4 5.4 E4 5.9 E4 2.4 E4 3,9 E4 5,4 E4 4.8 E4 2.4 E4 3.6 E4 5.3 E4 4 E4 2.4 E4 3.3 E4 5.3 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 KRYPTN-85N 1.2 EO KRYPTN-85 3.9 E-2 KRYPTN-87 1.6 EO KRYPTN-88 2 8 EO 2,3 E3 I;2 EO 3,9 E-2 1,4 EO 2.6 EO 2'E3 1,1 EO 3.9 E-2 I~2 EO 2.5 EO 2.3 E3 I~I EO 3'E-2 I EO 2'EO 2'E3 1~I EO 3.9 E-2 9'E-I 2.2 EO 2'E3 I EO 3.9 E-2 7.9 E-I 2.1 EO XENN-133 XENN-135 6.2 EO 5 5 EO 6'EO 5.4 EO 6,2 EO 5.3 EO 6.2 EO 5.2 EO 6.2 EO 5~I EO 6.2 EO 5 EO VII-26 SECTION VII-RADIOLOGICAL CONDITIONS PART C-SUPPRESSION POOL ISOTOPIC VII-27 SUPPRESSION POOL DATA: UCI/CC ISOTOPE 2045 IODINE-133 IODINE-134 IODINE-135 CESIN-137 5'E2 8'E2 4.7 E2 2.3 E1 KRYPTN-85H 5 E-2 KRYPTN-85 KRYPTN-87 KRYPTN-88 XENN-133 XENN-135 1.6 E-3 6.3 E-2 1.1 E-I 2,5 E-I 2.2 E-1 IODINE-131 2.4 E2 IODINE-132 4.7 E2 2100 2'E2 4.4 E?5'E2 7 E2 4,6 E2 2'EI 4.8 E-2 1.6 E-3 5.5 E-2 1.1 E-1 2'E-I 2.2 E-I 2115 2.4 E2 4.1 E2 5.3 E2 5.8 E2 4'E2 2'E1 4'E-2 1.6 E-3 4.8 E-2 10 E-2 2.5 E-1 21 E-I 2130 2,4 E2 3.8 E2 5.3 E2 4.7 E2 4'E2 2.3 EI 4'E-2 1.6 E-3 4.2 E-2 9.4 E-2 2,5 E-1 21 E-I 2145?,4 f?3,5 E2 5'E2 3'E2 4.3 E2 2.3 E1 4'E-2 1.6 E-3 3.7 E-2 8,8 E-2 2.5 E-I 2.1 E-I?200 2,4 E2 3.2 E2 5.2 E2 3.2 E2 4.1 E2 2'EI 4.1 E-2 1.6 E-3 3'E-2 8.3 E-2 2.5 E-1 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 IODINE" 132 0 EO IODINE-133 0 EO IODINE"134 0 EO IODINE-135 0 EO KRYPTN-85N 0 EO KRYPTN-85 0 EO KRYPTN-Oot 0 EO KRYPT%-88 0 EO XENN-133 0 EO XENCN-135 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO" 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0 EO 0EO0 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-I 31, 5~I El IODINE-132 I E2 IODINE-I33 1.2 E2 IODINE-I34 1.8 E2 IODINE-I35 I E2 KRYPTN-85H 8.5 E2 KRYPTN-85 2.7 El KRYPTN-87 1.1 E3 KRYPTN-88 1.9 E3 XENN-I33 4.3 E3 XEHN-I35 3.8 E3 5.1 El 9,4 El 1.2 E2 1,5 E2 9'fl 8.2 E2 2.7 El 9.5 E2 1.8 E3 4.3 E3 3.7 E3 5'EI 8.7 El 1.1 E2 I~2 E2 9.6 El 7.9 E2 2.7 El 8.2 E2 1.7 E3 4.3 E3 3.7 E3 5.1 El 8'EI 1,1 E2 I E2 9.4 El 7.6 E2 2.7 El 7'E2 1.6 E3 4.3 E3 3.6 E3 5'El 7.5 El 1.1 E2 8.3 El 9,1 El 7.3 E2 2.7 El 6.3 E2 1.5 E3 4.3 E3 3.5 E3 5.1 El 6~9 El!.1 E2 6.8 El 8.9 EI 7 E2 2.7 El 5.5 E2 1.4 E3 4'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 lEVEl 645 ARH I ARH 25 ARH 2 ARN 3 AR)14 loCAT NN RkR ROON 8 R)6)ROON A L NXN)PCI NXN/RV SIMP ARE A 1-1000 I-loop 01-100 01-100 1-1000 9.20 1220 021 1.65 1.80 ARH)6 AR)136 REN S)ON ROON 0,1).01-100 U-I RR ACCESS BAY O.l I.01-100 92 92 92 122 12 2)2.2 02 02 02 1,7 1.7 1.7 1.8 1.8 I.S 18:15)830 18:45)91X)19:15 19:30 19 A5 20:00 20)5 20.~92 92 92 92 92 92 92 122 122 122 122)22 122 12.2 02 02 02 02 02 02 02 1.7 1.7 1.7 1.7 1,7).7 1.7 I S 1.8 I.B 1.8 1.8 1.8 1.8 p)0)Q.)0.'I O.l Q.l O.l Q,l 0 I P)P.l O.l O.l 0.1 O.l O.l 4)7E405 4.90E F05 4.90EK6 7.50fi03 4.90E F03 I ppfiv5 200fi03 3,75E<05 3.37E+05 3 04E<05 2.75E F05 2 50f F05 4.4)fi05 3.97f F05 3.58f F05 323fi05 2,94fi05 4,17fo03 3,54fi03 30)ft03 2.56fi03 2,17fi03 638E t03 5,42ft03 4 6lf re 3.92E>03 3 33E<03 4 17E F03 3 54E t03 3 pl f F03~56f F03 2)7E i'.00E t04 8.1 pf@04 7,29E@04 6.56E+04 5 90fi04 I SXt03 I 62ft03 I 46f re I 3)f e03 I ISft03 20:45 21:00 21:15 21 30 21 45 22'00 lEVEL 719 ARH 5 ARH 6 ARH 26 AR))4)ARN 9 LEVEL 749 hRH 8 ARH Io lEVEL 779 ARH I I LEVEL 799 CRD NORTH CRD SOUTH 6/TP DRIVE AREA T P CHEER SRD CRD REPAI)ROOH 0.40 I AS 050 0.40 0.70.1-1000.1-1000.I-1000 IE2-IE6.1-1000 0.4 0.4 0.4 0.4 0.4 OA OA 0.4 I 0 1.0 I Al 1.0 1.0 1.0 I 0 I p 05 05 05 05 0 5 05 05 0 5 OA OA OA OA OA 0.4 OA 0 4 0.7 0.7 0.7 07 0.7 07 07 07 04 10 05 OA 07 RYCU RECRC AREA 024.1-)000 02 F)XL KOL PP AREA I 00.I-)000 I 0 02 02 02 02 02 02 p2 p2)O IO)O)O)O IO)O)06.0)-100 I.l 1.1 I.I 1.)I.l 1.1 I.I 04 Io 05 0.4 07).20fi04).20E t04 I 60fi04 2 Ppf to)200fi03 200.0)50 0 320 I OSE t04 9,72E y(g).QSf 104 9 72f y03 I 44E i04 I 30E F04 I.SOE F04 I 62E i04 I Sof tp3 I 62E t03 8.75E<03 8 75fi03 I,)7E@04 1.46E t04 I 46ft03 7 87f F03 7 87fi(6)05E t04 1.3)E F04 I 3)f to3 7 K&03 7.09E+03 9 45E+03 I.I Sfi04)IBfi03 180 0 162 0)45.8 131.2 I I S.I 1350 1215 1094 984 886 288 25.9 233 210)89 288 259 RECRC FAN ROON 0.08.Ol 100 O.l 0.1 0.1 0.1 12 LEVEl 818.I-AOO.Ol 100.01-100.I 1000.01-100 120 0.16 034 025 040 SPNT rm CR)T NQN Rg)XL FI44X)TH SAPP CASK STIR~FUEL CRIT NON REFUEL FL-VEST ARH 14 ARH 15 ARH35 13 ARH 42 I 2 1.2)2 I.2 I 2 1.2 1.2 1.2 p2 02 02 0.2 0.2 02 02 P3 P3 03 03 03 03 03 03 Q3 03 Q3 03 03 03 03 04 p4 GA 04 04 OA QA 04 32.0 320 320 320 320 320 288 259 233 2).Q)8.9"8 8 25 9 23 3 210)8.9 288 259 233 21 0)89 288 259 233 2)0)8.9"88 59"33~)0 189 Vflli I, PAGE I OF I REi/~7/1 9/91 GPOVP HVf'1BER.15 CROUP Polf'IT DISPLAY SERVICES RÃBLDG AREA RAD t"IONIT (E-PLAf<DISPLAY)8-Oct-~I!8 15 POINT rlo.DESCP!PTIGN pApn4 PAR25 PAPOI PARG2 PAROS PAPi6 t AP16 PARO6 PAP.09 PARG5 PAR41 PAP,26 PAR10 PAR08 PAP15 A IMARI I ARI2 PARI@PAP.15 P AR42 APN-04-RB/RV SVI"IP AREA AI?t-I-25-RKR RGGI-I A APt"I-01-PHR ROON B ARt"I-02-RC IC POOM ARI"I-O~-HPC I Roof"I ARI'I"36-VI RR ACCESS BAY APN-16-REN"HDN Rnnt"I ARM-06-CRD SOUTH APt"1-09-CRD REPAIP, ROOM ARN-05-CRG NGPTH APt"1-41"TIP CHAI"IBER SHLD ARN-26-IG/TIP DRIVE APEA ARt"I-10-FUEL POOL PP AREA APM-08-PVCU RECIRC APEA ARf"I-lb-HEV FUEL CRIT I"ION ARM-I I-SANPI.E ROOM ARN-12-1?ECIPC F Afl ROON ARI"I-14-SPNT FUEL CRIT t"IGN APN-15-RFUEL FLP.-f'lORTH ARM-42-RFUEL FLR-VEST wLAP,t"I STATE Ic I'IOV I 80 12.20 9 20 021 1.65 0.11 0.11 1.00 0.70 0.40 040 0.50 1.00 0.24 0.25 1.06 n.os 120 0.16 0.40 V AS HIGH LAST LINIT 1.80 15.00 12.20 50.00 9.20 5O.OO 0.21 4.00 1.65 8.00 0.11 4.00 0.11, 4.00 1.00 15.00 0.70 15.00 0 40 15.00 0.40 300.00 0.50 15.00 1.00 15.00 0.24 4.00 0.25 15.00 1.06 4.00 n.os 4.on 1.20 15.00 0.16 4.00 0 40 4.00 LGV L!NIT NONE HOI'IE HONE['IONE rlorIE HONE HONE NONE NONE NONE HONE NONE NONE Nor<E NONE Nol'IE flofIE HONE, NONE NofIE VI'llTS I"IP/HP, t"IR/HR I"1R/HR I.IR/HP.MR/HR t"IP.!HP, I"1R/HR MR/HR NR/HR I"IR/HR MR/HP.MR/HP, t"IR/HR t"IR/HR MR/HR MR/HR HP./HP.t'IR/HR I"IR/HR MR/HR VII-35 UNIT I, PAGE I OF 1 RE<): 7/19/91 GROUP HUf'IBER.15 GROUP POIflT DISPLAY SERVICES Rn BLDG AREA RAD MONIT (E-PLAf'I DISPLAY)8-Oct-91 18:30 PGIIIT fl0.DESCRIPTIOH PAPG4 O'AR'25 PAPG I PAP02 P RR03 PAP36 PAP,16 PAR06 P ARC9 PARG5 PAR41 PaR 6 PARIO PAR08 PAP.13 PARI I'AP.12 PAR14 PAP.15 PAP.42 ARI"1-04-RB/RV SUt 1P APEA ARM-25-RHR POOt"1 A ARt"I-01-PHR RGOI"I B API"I-02-RC IC POOM ARf"I-03-HPCI ROOI"I ARt"I-36-U1 RR ACCESS BAY ARt I-16-REI-I SHDN ROGt I ARM-06"CPD SOUTH ARt-I-09-CRD REPAR ROGt.1 API"I-05-CRD fl ORTH ARt"I-41-TIP CHAI"IBEP.

SHLD ARM 26 IG/TIP DRIVE APEA ARf"I-10-FUEL POOL PP AREA API"1-08-RVCU PECRC AREA ARt"I-13-NEV FUEL CRIT t"ION ARM-11-SAMPLE ROOM APM-12"I?EC!RC F Af'l PGOt"1 ARM-I 4-SPNT FUEL CRIT I"ION ARI"I-15-RFUEL FLR-f'IORTH ARM-42-PFUEL FLR-VEST ALARM STATE IS V AS HIGH I'lOV LAST LIMIT 1 80 1.80 15 00 12.20 12.20 50.00 9.20 9.20 50.00 0.21 0.21 4.00 1.65 1.65 8.00 0.11 0.11 4.00 0.11 0.11 4.00 1.00 1.00 15.00 0.70 0.70 15.00 0.40 0 40 15.00 0 40 0.40 300.00 0.50 0.50 15.00 I.OO 1.00 15.00 0.24 0.24 4.00 0.25 0.25 15.00 1.06 1.06 4.00 0.08 0.08 4.00 1.20 1.20 15.00 0.16 0.16 4.00 0 40 0.40 4.00 LOV LIMIT HGflE HONE[IONE HONE HONE NONE NONE NONE NOI'IE NONE NOI'IE 1lONE HONE NONE NONE NONE NONE NONE flOI'lE NONE UNITS MP./HR I-1R/HR Mi?!HR t<R/HP.t"IR/HP.f"IP.!HP.I"IR/HP.MR/HR t"IR/HR t"IR/HR I"IR/HR r,P./HR MR/HR t"IR!HP.MR/HR MR/HR t"IR/HP, t"IR/HR MR/HP, MR/HP.VII-36 Uflli I, PAGE 1 GF 1 REV'/19/91 GROUP NUI IBER.15 GROUP POiflT DISPI.AY SERVICES RX BLDG AREA RAD MONIT (E PLAf'l DISPLAY)8-Oct-91 18:45 Pelt~T IIG.DESCP!PT!GN P APG4<<AR25 Pare.PAI?02 PAROS PAP~6 PAP,)6 PARQ6 P APG9 PARG5 PAR41 PAR26 PAR IO PAP08 PAP.!3 t AR11 cgP1 i<<ARI4 PARIS P AR42 APM 04 PB/R i'(SUt"IP AREA API"I-25-RHR ROOt-I A API"I-01-PHR RGOI"I 8 ARI-I-02-RCIC POOt.l ARM-OS-HPCI ROON APt"1-.6-UI RP.ACCESS BAY ARI 1-16-REIN SHDN ROOM ARM-06-CRD SOUTH APt"I-09-CPD PEP AIR RGGM ARI I-l35-CRD flGPTH ARI"I-41-TIP CHAI"1BER SHLD ARM-26-IG/TIP DP.IVE AREA ARM-10-FUEL POOL PP AREA API"1-08"RVCU RECIRC AREA APM-15"NEV FUEL CPIT MGN ARM-11-SAMPLE ROOM ARM-12-I?ECIRC FAf'I PGGM ARt"I-I 4-SFNT FUEL CRIT t IGN ARM-15-RFUEL FLP,-flORTH ARM-42-PFUEL FLP.-VEST ALARM STATE 8 NGV 1,80 12 20 9 2Q 0.21 1.65 0.11 0.1 I 1.00 n.70 0.40 0.40 0.50 1.00 Q 24 0.25 1.06 0.08 1.20 0.16 0.40 VAS HtGH LAST LII"llT 1.80 15.00 12.20 50.00 9.20 50 00 0:21 4.00 1.65 8.00 0.11 4.00 0.11 4.00 1.00 15.00 0.70 15.00 0.40 15.00 0 40"00.00 0.50 15.00 1.00, 15.00 0.24 4.00 0.25 15.00 1.06 4.00 0 08 4.00 1.20 15.00 0.16 4.00 0.40 4.00 LGV LIMIT UillTS NeflE MP/HR riOIIE I.IP/HR rlerlE I-IR/HP NGflE HR/HR NONE I"IR/HR NGflE t"IP./HR f'let lE t"IR/HR Nef'IE MR/HR I'IGIIE MP./HP.NGflE t.IR/HR fief lE I"1P,/HP.NONE r-IP/HP, Nef'IE I"IR/HR NONE MP./Hl?flONE HP/HP.NGI'IE MR/HR NONE I"IP./HR NONE l"IR/HR NefIE I"IP/HR NONE MP./HP.VII-37 UflIT 1, PAGE I OF 1 pnr GROUP HUf"IBER.15 GROUP POlf'lT DISPLAY SEPVICES RX BLDG AREA RAD I"10f'IIT (E-PLAN DISPLAY)8-Oct-~I 1<'00 PG!f!T NO.DESCP, IP I'IGII>APORT." AF:25 PARG I F'ARQ2 FARGO'AP..s6 PpR!6 PARG6>AP09 P AR05 aAP41 PAR26 PAR!0 P AP08 PARI~PARI 1 z>aP i 2 PA!l!4 PAP.15 P AR42.PM-04-RB/RV SUMP AREA ARI"I-5-RHR ROGt"I A API'1-01-PHR ROOM B ARI.I-G2-RClC ROOM ARI"I-Oi-HPC I ROON API"I-~6-UI RR ACCESS BAY API"!-!6-PEM SHDfl RGGt"I ARN-06-CRD SOUTH APN-0'9-CPD PEP AIR PGGM ARI-I-05-CRD flGPTH APM-41-TIP CHAI"IBER SHLD API!-26-!6/TIP DRIVE APEA ARI'1" 10-FUEL POOL PP AREA ARM"08-RVCU RECIRC AREA ARI"I-13-NEV FUEL CRIT I"IGN ARN-11-SANPLE ROOM ARI"I-!2-RECIRC FAN ROOM x!" I"I-14-SPNT FUEL CRIT t"ION ARM-15-RFUEL FLR-NORTH APf"!-42-PFUEL FLP.-VEST Al.AP.f"1 STATE IS VA3 i"lO'iY L AST 1,80 1.80 12.20 12.20 920 920 0,21 0.21 1.65 1.65 0.11, 0.11 0.11 0.11 1.00 1.00 070 0.70 0 40 0.40 0.40 0.40 0.50'.50!.00!.00 0.24 0.24 0.25 0.25 1.06 1.06 G.OS 0.08 1.20 1.20 0.16 0.16 0 40 0.40 HIGH LIMIT 15.00 50.00 50.00-4.00 8.00 4.00 4.00 15.00 15.00 15.00 300.00" 15.00 15.00 4.00 15.00 4.00 4.00 15.00 4.00 4.00 LGV LINIT NONE NONE NOf'lE NONE r!OHE NOI'lE NONE NONE NONE HOflE NONE f'lONE rlONE i"lONE NONE I'lONE NOf'lE NONE NONE NONE UNITS MP,/HR t"IR/HR t"lR/HR I~R/HR t"!R/HR f"IR/HR I"IR/HR MR/HR t"IR/HR I.IR/HP.~'R'HR r-!R/HR MR/HR t'lR/HP.f"!R/HP.MR/HR I"IR/HP.I"IR/HR t!R!HR I"IR/HR VII-38 UfllT I, PACE I OF I PcLP i/19(01 GROUP f'IUf16ER:15 GROUP POlflT DISPLAY SERYICES RX BLDG AREA P.AD NONIT (E-PLAf'I DISPLAY)~-Oct-~I FO!IIT I!i3.DESCRIPTvifI o a,POa PAP:5."-ARO I PAPO2 PIRO'AP."6 PAR16 PARO6 P AP09 PAR05 PAPA I PAR26 PARIO PAR08 PARl i ARII AP,1.PAR14 PAP.15 P APA2>Pt"l-04-PB/RW SUNP AREA APt I-25-RHP Rlilit"I A Ai?t"I-01-PHR ROOt"1 B ARI"!02 PCIC RQOt"1 ARN-Oi-HP C I POOI"I API"1-)6"UI RR ACCESS BAY API"I-16-PEf"I SHDfl ROOM ARM-06-CRD SOUTH APM-09-CRD PEP AIR POON ARt"I-05-CRD NORTH ARI"I-41-TIP CHANBER SHLD ARI"I-26-IG/TIP DRIVE APEA ARI"1-10-FUEL POOL PP AREA APM-08-RVCU RECIRC AREA APM-I 3-NEW FUEL CRIT NOI'I ARM-11-SANPLE ROON APM-12-PECIPC FAf'I ROON ARI"I-14-SPNT FUEL CRIT t"10N ARt.1-15-RFUEL FLR-NORTH APt"1-42-RFUEL FLR-VEST ALAPI"I STATE IS WAS HIGH NOV L AST L IMIT 1.80 1,80 15.00 12.20 12.20 50.00 9.20 9.20 50.00 0.21 0.21 4.00 1.65 1.65 8.00 0.11 0.11 4.00 0.11 0.11 4.00 1.00 1.00 15.00 0.70 0.70 15.00 OAO OAO 15 00 0.40 0AO 300.00 0.50 0.50 15.00 1.00 1.00 15.00 0.24 0.24 4.00 0.25 0.25 15.00 1.06 1.06 4.00 0.08 0.08 4.00 1.20 1.20 15.00 0.16 0.16 4.00 0AO 0.40 4.00 LOV LIt'11T UIIITS flOIIE I-1R/HP NONE I")R/HR f'IONE I"IP./HR NOflE r.>R/HR f'IOf<E t"1R/HR fiOflE t"IP/HP, NOI'IE t"IR/HR I'IOI'IE NP/HR NOt'IE NR/HR NONE t"1R/HR NOflE'R.(HR NONE t"1P/HR NONE I'IR/HR NONE MP,/HR NONE NR/HR I'IONE NR/HR NONE MR/HP.NOIIE MR/HR f'IOI'IE l"1R/HP.NONE t-IR/HR VII-39 UNIT I PAGE'I OF I REV: 7/I aia!GROUP i'IUI" IBER:15 GROUP PGII'IT DISPLAY SERVICES RX BLDG APEA RAD I 10NIT (E-PLAN DISPLAY)8-Oct-91 I a:aO POINT NO.DESCPIPTIGN

>>R 4 PAP,25 PAP,OI PAR02 PAROi PAP~6 PAP.16 1'wRG6+APOa PA%05 PAPA I PAR26 PAR10 PAP08 PAP PARI I rAP12 PAR14 PAR 15 P AR42 ARM-04-RB/RV SUI"1P AREA ARM-25-RHR ROON A ARt"I-01-RHR RGOt"1 B ARM-02-RC IC POGM AP M-OZ-HPC I ROOt"I APM-r6-UI RR ACCESS BAY ARM-16-PEI I SHDH PGOI"1 ARM-06-CRD SOUTH 41?M-Oa-CRD REPAIR ROOI"I ARI"I-05-CRD flORTH APt"1-41-TIP CHAt'1BER SHLD ARM-26-IG!TIP DPIVE AREA ARI"I-10-FUEL POOL PP AREA ARM-08-PVCU RECIRC AREA ARN-13-NEV FUEL CPIT t 1ON ARN-I I-S AMPLE ROON APt"I-12-PECIPC FAN POOM ARt"I-14-SPf<T FUEL CRIT t"ION API"I-15-RFUEL FLR-f'IORTH APM-42-RFUEL FLP.-VEST ALARN STATE IS NOV 1.80 I 2.20 a 20 0.21 1.65 0.11 0.11 1.00 0.70 0.40 0.40 0.50 1.00 0.24 0.25 1.06 0.08 1.20 0.16 0.40 VAS LAST 1.80 12.20 a 20 0.21 1.65 0.11 0.1 I 1.00 0.70 0.40 0.40 0.50 1.00 0.24 0.25 1.06 0.08 1.20 0.16 0.40 HIGH LIMIT 15.00 50.00 50.00 4.00 8.00 4.00 4.00 15.00 15.00 15.00 300.00 15.00 15.00 4.00 15.00 4.00 4.00 15.00 4.00 4.00 LOV LINIT HONE NOflE f'IGtlE NGflE f'iOf'IE NONE HONE f'lGNE flOI'lE rIONE NONE NGflE NONE HONE NONE NONE NONE NONE HOI'IE flGflE UNITS t IR/HR I"IR/HR t"1P.!HR MR/HR t"IR/HR NR/HP MR/HR MR/HR I"IR/HR I"IR/HR'"1P iHR MP./HR NRr'HR t"1P.r HR NR/HR NRiHR t"1R/HR t"1R/HR t"1R/HR NR/HP.VII-40 Uflii I, PACE I OF I REV.7/19/9 GROUP f'IUf"18ER:15 GROUP POINT DISPLAY SERVICES RY 8LDG AREA RAD MONIT (E-FLAN DISFLAY)8-Oct-91 19:45>OINT NO.DESCRIPTION P PP04 PAR25 PAROI P AR02 PAROS PAR>6 PAP16 PAR06>AP09 P AR05 PAR41 P AR26 FAR10 P AP08 PARR PAR11 AR12 PAR14 FAR15 P AR42 ARt"1-04-RB/RV SUt"1P AREA ARt"1-25-RHR ROOt"I A APM-01-RHR ROOI"I B ARt-I-02-RCIC ROOM ARM-03-HFCI ROOM ARt"I-o6"Ui RR ACCESS BAY ARI-I-16-REt I SHDfl ROOt-1 ARM-06-CRD SOUTH ARM"09-CRD REPAIP.POOM ARf"I-05-CRD flORTH ARt"I-41-TIP CHAI"IBER SHLD APt"1-26-IG/TIP DRIVE AREA ARM-10-FUEL POOL PP AREA ARM-08"RWCU PECIRC APEA API"1-I o-fIEV FUEL CRIT MON ARM-11-SAMPLE ROON ARM-12-RECIRC FAI'I ROON ARI"I-14-SPNT FUEL CRIT MON APM-15-PFUEL FLR-NORTH APM-42-RFUEL FLR-'VEST AI.AP.t"I IS STATE flOV 1.80 12.20 Q 90 0.21 1.65 0.1 I 0.1 I 1.00 0.70 OAO 0.40 0.50 1.00 0.24 0.25 1.06 0.08 1.20 0.16 OAO VAS LAST 1.80 12.20 9 20 0.21 1.65 0.11 0.11 1.00 0.70 OAO OAO 0.50 1.00 0.24 0.25 1.06 0.08 1.20 0.16 0.40 HiGH LIMIT 15.00 50.00 000 4.00 8.00 4.00 4.00 15.00 15.00 15.00 300.00 15.00 15.00 4.00 15.00 4.00 4.00 15.00 4.00 4.00 LOV urliTS f'lOf'lE t'1R/HP NOflE t"IR/HP.flONE MP,/HP.NOflE I IR/HR NONE I"IR/HR NOflE MR/HP.I'lONE t"IR/HP.NONE MR/HR NOflE MP,/HR NONE t"1R/HR f'IOI'lE I"IR/HP.I'lONE MR/HR f'lONE MR/HR NONE MR/HR NONE I"IR/HR NONE MR/HR NONE I"IR/HR NONE I"IR/HR f'IOI'IE I'IR/HP.I'IONE MR/HR VII-41 UIIIT 1, PAGE 1 GF I PEY 7/I a/al GROUP f'lUNBER:15 GROUP POINT DISPLAY SERYICES RX BLDG AREA P.AD f"IGNIT (E-PLAf'l DISPLAY)8-Oct-a 1:0:00 POINT HG.DESCRIPTION P ARG4 P*R25 P AR01 I AR02 PARG3 PAR36 PAR16 PARG6 PAR09 P AR05 PAR41 PAP,26 PAR10;ARG8 PAR13 t'ARI I.'AR12 PAR14 PAP.15 PAR42 ARN 04 PB/R<Y SUI IP AREA ARt"I-25-RHR PGGt"I A AP.I"1-01-P,HR ROOI"I B ARM-02-RCIC PGOM API"1-03-HPC I ROON ARI"1-36-Ul RR ACCESS BAY ARt"I-16-PEI"1 SHDN ROGI"1 ARN-06-CRD SOUTH ARN-09-CRD REPAIR ROOI"1 ARt"1-05-CRD NORTH ARIA-41-TIP CHAt"IBER SHLD APN-26-IG/TIP DPIYE APEA ARI I-10-FUEL POOL PP AREA ARM-08-RVCU RECIRC AREA API"I-13-NEV FUEL CRIT MGN ARN-11-SAMPLE ROOM ARM-I.-PECIRC FAfl ROOM API"I-I 4-SPf'lT FUEL CRIT t"IGN ARI"I-15-PFUEL FLR-NOPTH ARI"I-42-RFUEL FLR-'r/EST ALARM IS STATE fIO'r(1.80 12.20 a 20 0.21 1.65 0.11 0.11 1.00 0.70 OAO OAO 0.50 1.00 0.24 0.25 1.06 0.08 1.20 0.16 0.40'r/AS I.AST 1.80 12.20 a 20 0.21" 1.65 0.11 0.11 1.00 0.70 OAO OAO 0.50 1.00 0.24 0.25 1.06 0.08 1.20 0.16 OAO HIGH LIMIT 15.00 50,00 50.00 4.00 8.00 4.00 4.00 15.00 15.00 15.00 300.00 15.00 15.00 4.00 15.00 4.00 4.00 15.00 4.00 4.00 LGV LIMIT flGflE flGflE tlGflE NONE NONE flONE NOflE f'lGI'IE NONE flONE I'lOflE NONE NONE NONE NONE NONE flONE NONE NOf'IE NONE Uf'llTS NP/HP t"IR/HP, I"!R/HR t"IR/HP.t"IR/HR t"1R/HP, I"IR/HR MR/HR MR/HR I"IR/HR MR/HP t"1R/HR I"IR/HP.t"1R/HR MR/HR MR/HR P./HR t"1R/HP.I-IR/HR I"'R/HR VII-42 UIIIT I, PAGE I OF I REV 7 (]0/81 GROUP POiflT DISPLAY SERViCES RN BLDG AREA RAD f.IOf'IIT (E-PLAI'I DISPLAY)8-Oct-91 20:15 Pi INT fjG.DESCPIPTIGfl PPPG4 PA I,'F APOI PAPQ2 PARGS PAR36 PAP.16 PARG6 PAPG PAR05 PAP41 PAI?26 PARI 0 PAP08 PARIS oARI I AP.12 PARI<PAP.15 P AR42 API"!-04-PB/F'V SUt"IP Al?EA ARt"i-25-I:,HR F'.GGI"I A-ARM-0 I-PHR ROGt"I B Apt I-02-Pi IC RQQM ARf"I-OS-HPC I RQGI"I APt'I-.6-Ul PP, ACCESS BAY APM-16-REI"I SHDN RGGM aRM-06-CRD SOUTH ARM-09-CRD REP AIR PGGf", ARI"I-05-CRD NORTH ARI"I-41-TIP CHAt"IBER SHLD ARt I-26-tG/TIP DRIVE APLA ARf"I-10-FUEL POOL PP AREA ARt"I-08-RVCU RECIRC AREA ARM-I 3-NEV FUEL CRIT MON ARM" 11"SAMPLE ROOM APJ"!-12-RECIRC F AN ROOM AF t.1-14-SPfli FUEL CRIT t.iOfl API I-15-RFUEL FLP.-NOPTH APf"I-42-RFUEL FLR-VEST ALAR!"I STATE IS VAS HtGH flOV LAST LIMIT 1.80 1.80 15.00 12.20 12.20 50.00~.20~.20 50.00 0.21 0.21 4.QO 1.65 1.65 8.00 0.11 0.11 4.00 0.11 0.11 4.00 1.00 1.00 15.00 0.70 0.70 15.00 OAO OAO 1500 0AO 0AO 300.00 0.50 0.50 15.00 1.00 1.00 15.00 0.24 0.24 4.00 0.25 0.25 15.00 1.06 1.06 4.00 0.08 0.08 4.00 1.20 1.20 15.00 0.16 0.16 4.00 0.40 OAO 4.00 LGV Lit"IIT Uf'l ITS NONE t"IP./HP.flGNE t"IR/HR flGflE t!R!HR NGI'IE I"!I?/HP.NONE I IR/HR NOflE t'lR/HR f'IGNE I"IP./HR NONE MR/HR NONE I"1R/HR NONE t"IR/HR flONE I"IR/HR NOflE I"IR/HR NOt'IE I"IR/HR flONE MR/HP.NONE MR/HP, NONE t iR/HR I'IOI'IE MR/HR NONE I"IR/HR flONE I"IR/HR NOflE I"IP/HR VII-43 Uf'lli 1, PAGE I OF I PEV: 7/19/91 GROUP NUI"lBER:15 GROUP PO!flT DISPLAY SERVICES RX BLDG AREA RAD I"1ONIT (E-PLAN DISPLAY)8-Gct-91 20 50 POINT NO.DESCRIPTIG[l PAR04 PAR25 PAR01 P Al?02 PARGi PAR>6 PAR16 PAR06 PAP,O'9 P ARO5 PAR41 PAP.26 PAR10 PAP.OS PAP I>PARII r ARl" PrtR14 PAP.15 P AR42 ARM-04-PB/RV SUI"IP AREA ARI"I-25-RHR ROON A ARf"1-01-PHR POOt"1 B ARI"!-02-RC!

C RGGI"1 ARN-05-HPCI POOI"I ARN-i6-UI PP.ACCESS BAY&RIG-16-PEt"I SHDf'I ROON ARN-06-CRD SOUTH ARN-09-CPD REPAIR POON ARI"I-05-CRD flORTH APM-41"TIP CHAf"1BER SHLD ARN-26-IG/TIP DP.!VE AREA ARl I-10-FUEL POOL PP AREA ARN-GS-RVCU RECIRC APE A ARN-I o-NEV FUEL CRIT I"IOI'I ARN-11-SAMPLE ROOM AR<<-12 PECIRC FAN ROON ARI"1-14-SPNT FUEL CRIT t"10N ARI"!-15-RFUEL FLP.-NORTH APt"I-42-PFUEL FLP.-VEST ALARM STATE IS V AS HIGH I'lOV L AST l.INIT 1.SG 1.80 15.00 12.20 12.20 50.00 9.20 9.20 50.00 0.21 021 4.00 1.65 1.65 8.00 0.11 0.11 4.00 0.11 0.11 4.00 1.00 1.00 15.00 0.70 0.70 15.00 0.40 0.40 15 00 0.40 0.40 F00.00 0.50 0.50 15.00 1.00 1.00 15.00 0.24 0.24 4.00 0.25 0.25 15.00 1.10 1.06 4.00 0.08 0.08 4.00 1.20 1.20 15.00 0.16 0.16 4.00 0 40 0.40 4 00 LOV LIMIT NOIIE NONE fIONE NONE I'lONE NONE NONE NOf'lE I'IONE NONE NONE t'lONE NONE NONE NOI'lE I'lGI'lE NOflE f NONE flGflE NONE UfllTS t"IR/Kl?t"IR/HP.t"1R r'Hl?MR/HR'"1R/HR NRr'HR NR/HR MRr'HR t"!R/HR I"IR/HR t"IR!HR NP./HR I"1R/HR I"1R/HR NR/HR MR/HR t"1R!HR I"1R/HR I"IP,/HR NR/HR VII-44 UHIT I, PAGE I OF I REV~7/14/91 OROUF f'{UMBER:15 RX BLDG AREA RAD NONIT (E-FLAN DISPLAY)GROUP POINT DISPLAY SERVICES 8-Oct-91 0:45 PGI!IT HG.DESCP.IPTIGH PARG4 PAR.5 FARO I PAPQ2 F AR03 P AR36 PAR'6 PAR06 P AR09 PARG5 PAR41 P AP'>6 PARI 0 PAP08 PAR I 3 2>ARI I AP.12 PAR14 PAP.15 PAR42 ARN-04-RB(RV S{JMP AREA ARt"I-25-RHR RGGI"I A API"I-01-RHR ROOt"I 8 ARM-02-RCIC POQM API"I-03-HFC I ROOI"I APt"I-36-Ui RR ACCESS BAY AP,N-16-P,Et.i SHDI'l RGGM ARI-06-CRD SOUTH API"I-09-CRD PEPAIP.ROON ARt"I-05-CRD NORTH ARM-41-TIP CHAt"IBEP, SHLD aRI 1-26-IG/TIP DP,IVE AP.EA ARI"I-10-FUEL POOL PP AREA ARN-08-RVCU RECIRC AREA ARI"I-13-NEV FUEL CRIT I"ION ARN" 11-SAMPLE ROOM ARN-12-RECIRC F AN ROOM ARs I-14-SPNT FUEL CRIT NON ARI"I" 15-RFUEL FLR-flORTH ARM-42-RFUEL FLR-VEST AL APt"I STATE IS NOV>1000 12.20>IOOO>>00>100>100>100>1000>1000>1000 2.0E+04>1000 150.00 200.00 32.00 32.00 32.00 32.00 32.00 32.00 V AS HIGH LAST LINIT 1.80 15.00 12.20 50.00 9.20 50.00 0.21 4.00 1.65 8.00 0.11 4.00 0.11 4.00 1.00 15.00 0.70 15.00 0 40 15.00 0 40 300.00 0.50 15.00 1.00 15.00 0.24 4.00 0.25 15.00 1.10 4.00 0.08 4.00 1.20 15.00 0.16 4.00 0 40 4.00 LGV LINIT HGflE HGHE NGflE f{QflE f'IOI'IE NONE flGflE NONE HOf'lE flOflE flof'IE NONE NONE HONE NONE f'{ONE NONE HONE HONE flONE Uf'IIT-t"IP./HR t"IRIHR I"IR/HP.MRIHR MR/HR NR/HP.t"IR/HR MR/HR I"IP./HP.t"IR/HR t"IR/HP, I"IP.IHR I"IR/HR MR/HR MR/HR MR/HR MR/HR t"IP./HP.MR/HP.vII-45 Uflli I, PAGE I OF I REV: 7/19/9!GROUP f'IUt"IBER:15 GPOUP POIflT DISPLAY SERVICES RX BLDG AREA RAD MGNIT (E-PLAf'I DISPLAY)8-Gct-91 21:00 POINT NG.DESCRIPT IGfl PAPG4 PAR 5?APGI PARO2 PAR03 PAR36 PAP.16 PARG6 PARO9 PARO5 PAP41 PAP26 PAR10 PAROS PAR13 PARI I'AR12 PAI?I4 PAP!5 PAP42 ARt"'I 04 RB/R A SUMP AREA ARt"I-25-RHR ROOI"1 A APt-!-01-PHR POOl I 8, ARI 1-02-RCIC ROOt.l ARM-03-HPCI ROOt"I ARt1-36-UI RR ACCESS BAY ARI"I-16-REI"I SHDN ROOM ARM-06-CRD SOUTH ARM-09-CRD PEPAIR ROOM ARI"I-05-CRD NORTH ARI"I-41-T IP CH At"IBER SHLD ARM-26-IG/TIP DRIVE AREA ARI"I-10-FUEL POOL PP AREA ARM-OS-RVCU RECIRC APEA ARM-13-I'IEV FUEL CRIT MON ARM-11-SAMPLE ROOM ARM-I 2-PEC!RC FAN ROOM ARI"I" 14"SPNT FUEL CRIT I"ION ARI-I-15-PFUEL FLR-flORTH ARM-42-RFUEL FLR-VEST ALARt"I STATE IS NOV>1000>1000>1000>100>100>100>100>1000>1000>1000 1.8E+04>1000 135.00 180.00 28.80.S.SG 28.80 28.80 2e.eo 28.80 V AS HIGH LAST LIMIT>1000 15.00 12.20 50.00>1000 50.00>>00 4.00>100 8.00>100 4.00>100 4.00>1000 15.00>1000 15.00>1000 15.00 2.0E+04 300.00>1000 15.00 150.00 15.00 200.00 4.00 32.00 15.00 32.00 4.00 32.00 4.00 32.00 15.00 32.00 4.00 32.00 4.00 LOV LIMIT Uf'IITS NOf'IE MR/HR NONE f"IR/HR I'IGf'IE I"IP./HR f'IONE t"IP./HR flONE t"IR/HR NONE MR/HR NONE t"Il?/HR NONE MR/HR NOI'IE MR/HR f'IGf'IE t"tR/HR HONE I"IR/HR NONE MP./HR NONE MR/HR NONE MR/HR NONE MR/HP.NONE MR/HR f'l ONE I"IR/HR NONE t"1R/HR NONE f IR!HR f'lONE t"IP/HP.VII-46 UfllT I, PAGE I GF I REii'l I'0 191 GROUP NUI"IBER:15 GROUP POifiT DISPLAY SERVICES RY BLDG AREA RAD I"IONIT (E-PLAf'I DISPLAY)8-Qct-91 21'.15 PGIflT NODESCRIPTIGfl P APG4 P AR25.ARQI PARO2 PARGi PAP~6 PAP.16 PAROS P AR09 PARG5 PAR41?AR26 PAP.I 0 P AP.08 PAP I.>i ARI I'AR12 PAR14 PAP.15 P AR42 APN-04-RB/RV SUt"IP AREA ARf"I-:5"RHR RQQt"I A ARN-0 I-RHP, POQI"I S ARt-I-02-RC(C RGQt.I API"I-OZ-HPC I RGOI"I ARI"I-i6-Ul RR ACCESS BAY APt"I-16-REt"I SHDfl PGGI"I ARN-06-CRD SOUTH APN-09-CRD REPAIR PGON ARI"I-05-CRD fIGI?TH ARf"1-41-TIP CHAt"IBEP.

SKLD ARN-26-1G/TIP DPIVE APEA ARt"I-10-FUEL POOL PP AREA ARt"I-08-PVCU RECIRC AREA ARt"I-l i-fIEV FUEL CRIT NON ARM-11"SANPLE ROON APt i-12-RECIRC FAfl PGOt"I ARI"I-14-SPf'IT FUEL CRIT I"IGN ARt"I-15-PFUEL FLR-NGRTH ARN-42-RFUEL FLR-VEST AL AP,I"I IS STATE f'lOV>1000~IQGQ>I 000>100>100>100>100>>000>1000>1000 1.6E+04>1000 121.50 162.00 25.92 5.92 25.92 25.92 25 92 25.92 l(HS LAST>1000>1000>1000>>00>100>100>100>>000>1000>1000 1.BE+04>>000 135.00 180.00 28.80 28.80 28.80 28.80 28.80 28.80 HIGH Llt"IIT 15.00 50.00 50.00 4.00 8.00 4.00 4.00 15.00 15.00 15.00 400.00 15.00 15.00 4.00 15.00 4.00 4.00 15.00 4.00 LG'4J'II"IIT flGflE ilQNE flGIIE i'lQ!IE NONE flGI'IE rlnrlE I'lOI'IE NONE NONE NONE flQflE HONE NONE NONE f'lGNE NONE!IGNE tlOflE flQNE UflITS I"P/HP r.IR/HR iiIR/HP t~R/HR i"'lR/HR i~IR/MR NR/HR NR/HI?NR/HP.I"IR/HR t"IP./HR I"IR/MR NRlHR NRlHP t'IR/HR NR/HR t"IRlHP.NR/HR I"IP./HI?t"IR/KR VII-47 Ul'llT I, PAGE I OF I vE<r 7/tv/a1 GROUP f'IUI'"1BER:15 GROUP PO!f'IT DISPLAY SERVICES RÃBLDG AREA RAD MONIT (E-PLAf'I DISPLAY)8-Oct-91 21 30~OINT MG.DESCRIPTION P AP,04 PAR25 PAP.OI PAP02 PARO3 P AR36 P AP.16 PAR06 P AR09 8 ARO5 P AR41 PAP26 PARIO PARO8 PAR13 PAR11'AP,12 PAR14 PAP.I 5 P AR42 API"I-04-RB/RV SUf'IP AREA ARt"I-25-RHR ROGt"1 A API"I-O 1-RHP.ROOM B API"1-02-RCIC RGGM ARI"I-03-HPCI ROOM ARM-36-Ul RP.ACCESS BAY'RM-16-PEN SHDN RGGt"1 ARM-06-CRD SOUTH ARM-09-CRD REP AIR RGGM ARt"I"05-CRD flGRTH APM-41"TIP CHAI"IBEP.

SHI.D ARM-26-IG/TIP DRWE AREA ARM-10-FUEL POOI.PP AREA ARM-08-RVCU PECIRC AREA APM-13-NEV FUEI.CRIT MOM ARM-1 1-S AMPI.E ROON ARt'1-12-RECIRC F AN ROOM ARt"1-14-SPNT FUEL CRIT I"10f<ARI"1-15-RFUEL FLR-NORTH ARM-42-RFUEL FLR-VEST ALARI"I 8 STATE NOV>1000>1000>1000>100>100>100>100>1000>1000>1000 1.5E+04>1000 109.35 145.80 2333 23 33 2333 23 33 V AS HIGH LAST LIMIT>1000 15.00>1000 50.00>1000 50.00>100 4.00>100 8.00>100 4.00>100 4.00>1000 15.00>1000 15.00>1000 15.00 1.BE+04 300.00>1000 15.00 135.00 15.00 180.00 4.00 28.80 15.00 28.80 4.00 28.80 4.00 28.80 15.00 28.80 4.00 28.80 4.00 LGV I.IMIT UNITS NGf'IE I"1R/HR tlGNE I"IR/HR NOf'lE t"IR/HR NONE I IR!HR NOflE I"1R/HR NONE t"IR/HP.flGf'lE I"IR/HR NONE MR/HR NONE MR/HP, flGNE MR/HR flOf'lE tRR/HR NONE MR/HR NONE MR/HR NONE MR/HR I'IONE MR/HR I'lOI'lE I R/HR NOflE MR/HR NONE t"IR/HR flOflE t"IR/HP.NOI'IE f.IR/HR VII-48 Uflli I, PAGE I OF I REL)~7/I 9/91 GROUP f'!UMBER:15 GPOUP POIfli DISPLAY SERYICES RX BLDG AREA RAD f"10f'lIT (E-PLAN DISPLAY)8-Oct-91~I:45 POINT fl0.DESCRIPTION I'APG4 PwR25 MARGI PAP02 PARG3 PAR36 PAR16 P ARO6 P AR09 PARG5 PAR41 PAP26 PARIG PAP08 PAP,13)>ARI I'AP.!2 PAR!4 PAR15 PAR42 ARM-04-RB/RV SUMP AI?EA ARI"I-25-RHR POOM A ARf"I-01-PHR ROOI"I B API"I-02-RC!C ROOM ARf"I-03-HPC I ROOf"I APt"I-36-UI RR ACCESS BAY API"I-16-REM SHDN PQOM ARM-06-CRD SOUTH API"I-09-CRD REPAIR POCM ARt"I-05-CRD f'lORTH ARI"I-41-TIP CHAt"!BER SHLD ARI"I-26-IG/TIP DRIVE AREA ARt"I-10-FUEL POOL PP AREA APM-08-RVCU RECIRC AREA API"I-13-f'IEV FUEL CRIT MOf'I ARM-11-SAMPLE ROOM API"I-12-REC IRC F AN POGM ARI"I-14-SPNT FUEL CRIT MON AP t-I-15-PFUEL F LR-flORTH AP!" I-42-RFUEL FLR-VEST ALARM IS STATE NOV>1000>!000>1000>100>100>100>I GO>1000>1000>1060 1.3E+04>1000'8.42 131.22 21.00 21.00 21.00 21.00 21.00 21.00 VAS LAST>1000>1000>1000>100>IOO>100>100>1000>'I 000>1000 1.5E+04>1000 109.35 145.80 23.33 2333 2333 23.33 23.33 23.33 HtGH LIMIT 15.00 50.00 50.00 4.00 8.00 4.00 4.00 I 5.00 15.00 15.00 300.00 15.00 15.00 4.00 15.00 4.00 4.00 15.00 4.00 4.00 LOV LIMIT UfllT-f'lONE I"IR/HP, NOflE I"IP,/HR NOflE!"IR/HR NOflE t.!R/HR NOf<E I"IR/HR flGflE t"IR/HP.NOf'lE MR/HR I'IOI'IE MR/HR NGf'lE MP,/HP.fl 0flE t.!R/HR NOIIE MR/HR f'IONE I IP./HP.NONE t"'IR/HR NONE t"!R/HR NONE I"IR/HP.NONE MR/HR NOI'lE t"IR/HR NONE t"IR/HR NOflE t"IR/HR I'lONE I"!R/HR VII-49 UNIT I, PAGE I OF I REV: 7/19/91 GPGUP f'lUMBER:15 GROUP POIf'IT DISPLAY SERVtCES RX BLDG AREA RAD I"IONIT (E"PLAf'I DISPLAY)8-Oct-91 22:00 POINT NO.DESCRIPTION PAP04 P AR25 PAP.OI PAP.02 PAROS PAR36 PARl6 PAR06 PARO9 PAR05 PAP41 PAR25 PAR10 P AROB PARIS PAR11'AP.12 PAR14 PARI5 PAR42 APM-04-RB/RV SUI"1P AREA ARM-25-RHR ROOM A APt"I-01-PHR ROOt"1 B ARIA-02-RC!C ROOf.1 ARM-0$-HPCI ROOt"I ARM"36-UI RR ACCESS BAY ARt"I-16-PEI"1 SHDI'I ROOI"1 ARM-06-CRD SOUTH ARM-09-CRD REPAIR ROOM ARM-05-CRD NORTH ARt"I-41-TIP CHAI"IBER SHLD ARM-26-IG/TIP DRIVE AREA ARM-10-FUEL POOL PP AREA ARM-08-RVCU RECIRC AREA ARt"I-13-NEV FUEL CRIT MON ARM-11-SAMPLE ROOM APM-12-PECIPC FAI'l ROOM API I-14-SPNT FUEL CRIT MON ARt"I" 15-RFUEL FLR-NORTH ARM-42-RFUEL FLR-VEST ALARt"I STATE IS NOV>1000>1000>1000>100>100>100>100>1000>1000>1000 1.2E+04>1000 88.57 118.10 18.90 18.90 18.90 18.90 18.90 18.90 V AS HIGH LAST I.IMIT>1000 I S.OO>1000 50.00>1000 50.00>100 4.00>100 8.00>100 4.00>100 4.00>1000 15.00>1000 15.00>1000 15.00 1.3E+04~00.00>1000 15.00 98 42 15.00 131.22 4.00 21.00 15.00 21.00 4.00 21.00 4.00 21.00 15.00 21.00 4.00 21.00 4.00 LOV LIMIT UNITS f'IOI'lE MP./HR flONE t"1R/HR ilOflE t"IR/HR f'IOf'IE I"IR/HP.NOflE I"IR/HR NOflE t"IP./HR flONE MRIHR t'lOf'lE MR/HR NOflE MR/HR NONE t"IR/HR NOf'IE MR/HR NONE MR/HP.NONE MR/HR NONE MR/HR NONE I"1R/HR NOllE MR/HR I'lOI'lE MR/HR NONE t"1R/HR NONE t"IR/HR NONE t"1R/HR Vjj-50 ARt I 56/I I ARII 55/5 ARt157/12 ARt1 48/3 AP11 53/16 ARI1 50/5 ARtt 51/6 API1 52/18 ARt1 54/10 AP1149/42 lOChf ION RHR ROOI1 8 PI6'OOt1 A RC IC PP TWB R11 tPC I PP TIRB Rt1 PEt1 SDII PM.RI1 CRD HOP TH (SDV's)CRC SOUTH (SDV's)CL&'RECRC~AC fEKL PL PPS'11 RFLXL flR AREA Al RANGE 440 360 380 230 310 280 410 500 210 410 1 f 2-If@If'2" 1 E6 IE2-IE6 I f 2-1E6 lf2-lf6 IE2-1 f6 I E2-'I E6 IE2-I f 6 If2-lf6 IE2-IE6 18:15 18:30 18 45 19 00 19.15 19.30 19:45 20:OO 20:15 20:30 20:45 21 OO 21:15 3.7Et05 4.Of+05 33E t02 1.9Et02 8, If t04 9.9E t03 I.OE t04 4.IE t02 2.9Et02 3.6Et02 4.1Et 05 4.4ft05 3.?E+02 2.1 f t02 9.DE+04 I.If+04 I.IEt04 4.5Et02 3.2E+02 4 OEt02 4.6E+05 4.9E+05 4.IE+02 2.3Et02 I OEt05 I 2Et04 1.2E+04 50ft02 3 6Et02 4.4E+02 4.4Et02 3.6E+02 3 BE+02 2.3Et02 3.If+02 2.8Et02 4.IE+02 5.DE+02 2.If+02 4.1E+02 4.4E+02 3 6E+02 3 BE+02 23E t02 3.1E t02 2 SE+02 4.1E+02 5 OEt02 2 lft02 4.If+02 4.4Et02 3.6Et02 3 Sf t02 2.3E+02 3 I Et02 2 Sf t02 4.1E t02 50ft02 2.I f+02 4.1E+02 4 4E t02 3.6Et02 3 BE+02 2.3E+02 3 I f+02 2.BE+02 4.If+02 5.0E+02 2.IE+02 4 IE+02 4 4E t02 3.6Et02 3.BE+02 2.3Et02 3.if+02 2.BE+02 4.If+02 5 Of t02 2.IE+02 4.1f t02 4.4Et02 36E+02 3 BE+02 2.3Et02 3 If t02 2 BE+02 4.1 f t02 5XKt02 2.1E+02 4 1ft02 4 4E t02 3.6E+02 3.BE+02 2.3Et02 3 IEt02 2 BE+02 4.lf t02 5.DE+02 2.1Et02 4 lft02 4.4E+02 3 6E+02 3 BE+02 2.3E+02 3 Ift02 2 BE+02 4.1E t02 5.Of+02 2.If+02 4.If+02 4.4f+02 3 6Et02 3 BE+02 2.3E+02 3 IEt02 2.BE+02 4.1E+02 5 Of t02 2.If+02 4 IEt02 4.4Et02 3 6Et02 3.BE+02 2.3Et02 3 IEt02 2.BE+02 4.1Et02 5.DE+02 2,1Et02 4 IEt02 HIGH RhttGE REACTOR BUILDING TABLED VAIUES GIVEN Nl INI/ISI RE VIS Stt.tttttt 21:30 3 4E t05 3.6Et05 3.DE+02 1.7Et02 7.3E+04 9 OEt03 9 OEt03 3 6Et02 2.6Et02 3.2E t02 3 Of+05 3.2Et05 2 7E+02 1.5Et02 6 6E+04 S.lft03 S.IEt03 3 3Et02 2.4E+02 2.9E+02 2,7Et05 2.9E+05 2 4E t02 1.4Et02 5 9ft04 73Et03 7 3E+03 3 DE+02 2.1Et02 2 6E t02 21:45 22:OO UNIT I, PAGE 1 GF I GROUP POINT DISPLAY SERVICES 8-Oct-91 18".!5 GP.OUF f'iUf'IBKR:1 0 Hl RANGE ARI I PEAD}f'iGS (E-PLAf'i Dl FLA")PolfiT,NO.

DESCPIPTIOfi PAR~o F" AR55 P AP57 P APAS F AR53 P AP50 P MR51 F AR5=P AR54 P AR49 APt'1-56-PHR ROOt"1 LOOP B AR}.1-55-RHR ROOt-1 LOOP A ARt"1-57"RCIC PP TUPB Rt"1 ARN-48-HPC I PP/TURB Pl"1 ARI"1-53-ACCS TO PEf"1 SHUTD ARI"1-50-CRD NOPTH APN-51-CRD SOUTH ARN-5-R'rirCU PP ACCESS ARI"'I-54-FUEL POOL PP POON ARt}-49-REFUEL FLOOR AREA AL AP.t"1 IS-T ATE NO'r(GA4 0.36 0.38 0,23 0.31 0.28 0.41 0.50 0.21 0.41 3-'AS LAST 030 036 OA4 0.38 023 0.30 0,31 0.41 0.41 0.28 HIGH L It'1IT IS.GO 15.00 15.00 15.UG 1'5.00 15.00 15.00 15.00 15.00 15.00 L It"IIT Nof'IE I'iof'iE NONE rioriE fiof'IE rior E fiofiE Nof'iE NofiE ftONE$lrilwo P./HP.R/nK R/HR g rgn R/Hi?P!HP P./HP.Rr'HR P./HP.R/HP.Uf'ilT 1 p PAGE 1 OF 1 GPOUP f'iUI"IBEP.:10 RGINT No DESCRIPTION ALARM STATE IS'i'(AS'IGH NQE'i'AST L lt"1 IT 0.44 OA4 15.00 0.36 0.36 15.00 0.38 0.38 15.00 0.23 0.23 15.00 0.31 0.31 15.00 0.2S 0.28 15.00 0.41 0.41 1 5.00 0.50 0.50 15.00 0.21 0.21 1 5.00 OA1 OA1 15 00 nRt-1-56-RHR ROOM LOOP B APN-55-RHR POON LOOP A ARf I-57-RCIC PP TL}RB Rf.l APt"1-48-HPCI PP/TURB RN APt"1-5o-ACCS TO REt"1 SHUTD ARI"I-50-CPD NORTH ARN-51-CRD SOUTH ARM-52-'R'v(CU PP ACCESS ARI"1-54-FUEL POOL PP POOH ARI"1-49-REFUEL FLOOR AREA P AP.56 PAR55 P AR57 P APA8 P AP53 P AP50 PAR51 P AR52 P AR54 PAR49 GROUP Polf'iT DISPLAY SERVICES Hl RAfiGE ARM PEADINGS{E-PLAN DISPLAY)0'i r L It"1IT NONE NONE I'iol'IE rior<E fiONE NofiE f'ioNE NONE NONE I'iof'IE Ufi ITS I?!HP.P/HP R/HP.P.iHR P,/HR RiHR P./HR R IHR R!HR R/HP 8-Oct-91 18 30 VII-52 IJf'IIT'I PAGE 1 OF I RQUP f'>tJt"IBER

.'10 GPOUP PGlf'IT DISPLAY SERVICES HI RAf'IGE ARt"I READIf'iGS (E-PLAf'I DISPLAY)8"Oct-91 18:45~Oit'iT NO.DE CRIPTIGN P AR56 P ARSS P AR57 P AR48 F'AR53 P APSO PARSI PAR5 PAP54 P AR@9 APM-S6-PHP.

ROOI"1 LOOP B APt 1-55-PHR RGQt"I LOOP*ARI"I-57-RCIC PP TUPB Pt 1 ARt"'.-43-HPCI PP/TUPB PN APt'1-53-ACCS TO REM SHUTD API"I-50-CRD NOPTH API"I-51-~

PD SOUTH APN-52-RVCU PP ACCESS APM-54-FUEL POOL PP RGQt"1 ARt"I-49-REFUEL FLGOP, AREA ALARI"I 8 STATE NOV 0.44 0.6 038 0.23 0.31 0,28 0.41 0.50 0.2'I 0.41 V AS HIGH L AST L INIT 0.44 15.00 036 IS GO 038 15.00 0.2"-15.00 0.31 15.00 0.28 15.00 0 41 15.00 0.5015.00 0.21 15.QO 0.41 15.00 LOV LIMIT UflITS NOf'iE P./HP.flGNE t:!HP.NOf'IE P/HR tiOflE R!HR NONE.P./HP.flGNE P./HR I'lOfiE P./HR NQt'lE R/HR NQfiE R/HP.fiOf'iE R/HR Uf'llT I, PAGE I QF I GROUP f'lUI"IBEP:10 GPOUP POIf'lT DISPLAY SERVICES HI PAf'lGE ARM READINGS (E-PLAN DISPLAY)8-Oct-91 19:00 PGItlT NO 0 P AP56 P AP.55 P AP57 PAP48 PARS3 P AR50 P AR51 PAR52 P AR54 P AR49 DESCRIPT ION APt"I"'56"RHR POQI"I LOOP B ARN-55-RHR ROON LOOP A API"I-57-PCIC PP TURB PM ARI"1-48-HPC I PP/TURB RN ARM-53-ACCS TO REI"1 SHUTD ARM-50-CPD NORTH ARt"I-S 1"CRD SOUTH ARt"I-52-RVCU PP ACCESS ARI"1-54"FUEL POOL PP ROON&PM-49-REFUEL FLOOR AREA ALARM STATE IS flOV 0.44 0.36 0.38 0.23 O.i 1 0.28 0.41 0.50 0.21 0.41 V AS HIGH L AST L lt"1 IT 0.44 15.00 0.36 1 5.00 0.38 15.00 0.23 15.00 0.31 15.00 0.28 1 5.00 0.41 15.00 0.50 15.00 0.21 1 5.00 0.41 15.00 LOV LIr-1IT iiONE NOf'IE NONE NONE NONE fiOI'lE NOf'lE NONE flOfiE f'iQf'lE IJfit e 8 P/4R R/HP.R/HR R/HP P./HR P./HR R/HR R/HR P./HR VII-53 UfllT I, PAGE 1 GF I GROUP NUI"1BEP.:10 GROUP POINT DISPLAY SERVICES Hl RAflGE ARt"I READINGS (E-PLAN DISPL*Y)8"0:t-91 I 9: I 5 PQI['lT f'IQ.DESCRIPTION P>R56 PAR5~PAR57 PAR48 PAR53 P AR50 P AR51 P AP52 PAR54 APM-56-RHP.

ROON LOOP B*RN-55-PHR ROON LOOP A ARt"1-57-RCIC PP TURB Pt"I ARI"1-48-HPCI PP/TURB Rt"I APt"1-53-ACCS TO REN SHUTD ARN-50-CRD f'IORTH APM-51-CPD SOUTH APN-52-RVCU PP ACCESS ARM-54"FUEL POOL PP ROOM ARt"I-49-REFUEL FLOOR AREA AL AP,t"I STATE IS flGV 0.44 0.36 0.38 0.23 0.31 0.28 OA1 0.50 0.21 OAl VAS LAST OA4 036 0.38 0.23 0.31 0.28 0.41 0.50 0.21 0.41 HIGH LIMIT 15.00 15.00 15.00 15.00 15.00 15,00 15.00 15.00 15.00 15.00 LOV LIMIT NO[IE r.IQFIE f'lQflE NGf'lE NONE f'lOf'lE flOf'IE flOflE NOI'lE flGNE I If<ITS P./HP.P./HP.R/HP.p rQp R/HP.Rr'HP.R.lHR R/HP, R/HR R/HR UNIT 1, P*GE I OF 1 GPQUP flU["1BER:10 PQII'lT f'IQ.DESCR IPT IOI'l V*S HIGH LAST'II"1 IT 0.44 15.00 0.36 15.00 0.38 1 5.00 0.23 15.00 0.31 15.00 0.28 15.00 0.41 15.00 0.50 15.00 0.21 15.00 0.41 15.00 ALARM STATE IS NOV 0.44 0.36 0.38 0.23 0.31 0.28 0.41 0.50 0.21 QA1 ARt"I-56-RHR RQQI"1 LOOP B ARt-1-55-RHP, PQOI"1 LQQP A ARM-57-RCIC PP TUPB RM ARf I-48-HPCI PP/TUPB R[1 ARM-53-ACCS TO PEN SHUTD ARI"1-50"CPD f'lORTH ARM-51-CRD SOUTH ARN-52-RVCU PP ACCESS ARt"I-54-FUEL POOL PP ROON ARM-49-REFUEL FLOOR AREA P AR56 P AR55 P AP.57 PAR<8 P AR53 P AR50 PARSI P AR52 P AR54 P AR49 GROUP POlf'lT DISPLAY SEPVICES Hl RANGE ARt"1 READINGS (E-PLAN DISPLAY)LO'rl LII"1 IT flGNE NONE NO['IE NONE NONE NOflE[lQI'lE NOf'lE NOflE NOflE UNITS P./HR p rHp R/HP.P.r'HP, Rr HR R/HP.R/HR R/HP.P./HR R/HP.8-Oct-'91 19:30 VIT.-54 GPOUP I'IUI"!BER:10 GROUP PolflT DISPLAY SEPVICES HI RAf'lGE APf"I PEADI.'lGS (E-PLAf'I DISPLAY)8-i3ct-91 I.":45 F'OINT HG.DESCRIPT IGf'I PAR56 PAR 5 F'R57 P AP48~wR53 P AR50 P AP51 PAP52 P AR54 P AR49 ARM-56-PHR ROON LOOP B APM-55-PHP.

PGQM LGGP A ARt"I-57-RCIC PP TURB Rt"I ARI"I-48-HPC I PP/TUPB Rt"I ARN-53" ACCS TO REM SHUTD ARt-I-50-CRD flORTH ARN-51-CRD SOUTH APt"I-52-PVCU PP ACCESS ARN-54-FUEI POOL PP ROON ARN-49-REFUEL FLOOP.AREA AL APSE STATE IS NUV 0.44 0.36 0.38 0.23 0.31 0.28 0.41 0.50 0.21 0.41 VAS LA T 0.44 0.36 0.38 0.23 0.31 0.28 0.41 0.5O 0.21 0.41 HIGH L It"I IT 15.00 15.00 15.00 15.00 15.00 15.00 15.00 15.00 15.00 15.00 LQV LIMIT Nof'lE Ni'NE flotlE flGNE NoflE rlOrlE NONE NONE Nof'lE NoflE 1JfllT.P/HR P,/HP.i?/HR R/HR R/HP R r'HR R/HP.P./HP.R/HR R/HR~Jfl IT 1, PAGE 1 OF 1 GPOUP flUNBER:10 GROUP POINT D ISPL AY SERVICES HI RANGE APM PEADINGS (E-PLAN DISPLAY)8-Oct-e1 2O:OO POINT I'lo.P ARS6?AP.55 P AR57 PAR48 P AR53 PAP50 P AR51 P AR52 P AR54 P AR49 DES CR IPT Iol'l ARf"I-56-RHR ROGI"1 LOOP B API"I-55-PHP.

POON LOOP A ARM-57-RCIC PP TURB Rt"1 ARf"1-48-HPC I PP/TURB RM ARM"53-ACCS TO REt"1 SHUTD ARN-50"CPD NORTH ARN-51-CRD SOUTH ARM-52-R'iv'CU PP ACCESS API"I-54-FIJEL POOL PP ROOM ARN-49-REFUEL FLOOR AREA ALARM STATE IS f'lOV 0.44 0.36 038 0.23 0.31 0.28 0.41 0.50 0.21 0.41 VAS LAST 0.44 0.36 0.38 0.23 0.31 0.28 0.41 0.50 0.21 0.41 HIGH LIMIT 15.00 15.00 15.00 15.00 15.00 15.00 15.00 15.00 15.00 15.00 LQV L INIT Uf'l ITS NONE Rr HI?NQflE R/HR NONE P./HR f'lOf'lE Rr'HR fIGNE Rr'HP.NONE P/HP.f'lGNE R/HR NONE R/HR floflE R/HR NoflE P./HP.VII-55 UNIT I, PAGE I OF I GPGUP HIJt"ABER:10 GROUP POlflT DISPLAY SERVICES HI RAf'lGE ARN READlf'lGS (E-PLAf'l DISPLAY)8-Gct-91 20;15 PQIflT flO.DE-CPIPTIOf'l P&R56 P AP55 F AR57 F APAS PAR5~P AR50 P AR51 PAR52 P AR54 PAP,49 ARN-56-PHR ROOM LOOP B ARt"1-55" PHP.PQOt"1 LGGP A APN-57-RCIC PP TURB Rt"1 APN-4S-HPCI PP/TURB RM Al?t"1-SZ-ACCS TO PEt"1 SHUTD ARf"1-50" CRD f'lOPTH ARt"'I-51-CRD SOUTH APt"I-52-PWCU PP ACCESS ARN-54-FUEL POOL PP POON ARt"1-49"REFUEL FLOOR AREA ALAP.I"1 STATE IS~NG'F OA4 096 038 0.23 0.31 0.28 OA1 Q.50 0.21 OA1 VAS LAST OA4 0.~6 O.iS 0.2>031 0.28 0.41 0.50 0.21 OA1 HIGH L ll"I IT 15,00 15.00 15.00 15.00 15.00 15.00 15.00 15.00 15.00 15.00 LOW LII"IIT flGNE NOflE NOf'lE NGflE NGflE flONE NOf'lE flQflE flQflE f'lGf'lE IJfilT::-R!HR R!HR R!HR R HP.P-iHR RlHR R/HR P.!HP.R/HR UfllT 1, PAGE 1 OF 1 GROUP f'lUNBER:1 0 POlf'lT NO.DESCP IPT IQN HIGH LIMIT 15.00 15.00 15.00 15.00 15.0Q 15.00 15.00 15.00 15.00 15.00 ALARN STATE WAS LAST OA4 O.i6 0.38 0.23 031 0.28 OA1 0.50 0.21 0.41 IS NOV OA4 0.36 0.>8 0.23 0.31 0.28 0.41 0.50 0.21 OA1 ARf"I-56-PHR ROON LOOP B APt"1-55-RHP.

ROON LOOP A ARM-57-PCIC PP TIJRB RN ARt"1-4S-HPCI PP!TURB RN ARM-53-ACCS TO REM SHUTD ARI"I-50-CRD NOI?TH ARN-51-CRD SOUTH ARN-52-RVCU PP ACCESS ARN-54-FUEL POOL PP ROON ARN-49-REFUEL FLOOR AREA P AP56 P AP55 PAP.57 PAR48 PAR5i PAR50 PAR51 P AP52 P AR54 P AR49 GPGUP POINT DISPLAY SERVICES Hl P.ANGE ARM READlf'IGS (E-PLAN DISPLAY)LGV Llt"11T f'lQNE NONE I'lof'lE NOf'lE fIGNE flGflE f'lONE f'IONE flOflE NONE IJf'IITS R!HR R/HR P./HP.RPHR P.!HR RUHR P.!HR P.!HR R!HR RiHR 8-Oct-91 20 90 VII-56 VfllT I, PAGE I OF I GPI3UP fIUI-!BEP.:10 GPQUP POINT DISPLAY SERVICES Hl PANGE APM PEADlflGS (E"PLAN DISPLAY)8-0:t-91 ZQ O5 PGlfIT f10.DESCRIPTION PAP56 P AR55 P AR57 P AR43 P AR5Z P AP,50 FAR51 P AP52 P AR54 P AR49 ARM-56-RHP.

ROOM LOOP 8 ARM-55-RHR ROON LOOP A ARI"I-57-RCIC PP TURB Rt"I ARt"I-48-HPC I PP/TURB Rt"I ARI"I-53-ACCS TO REI1 SHUTD APt"I-50-CPD NOPTH APt"I-51-CPD SOUTH API"I-52-RVCU PP ACCESS ARM-54-FUEL POOL PP ROOM ARM-49-REFUEL FLOOR APE A ALARI"I iS STATE IIO'v!'60.94 490.=6 OAI 0.23 10031 12AI 0.50 0 6 OA4 VAS LAST 0.44 0.=6 0.38 Q O.Z I l3.28 OA'I 0.50 0.21 OAI HIGH LIMIT 15.00 15.QG 15.00 15.00 15.00 15.00 15.00 15.00 15.00 15.00 LO'8 Llt"IIT UIIIT~NOI IE R/HR rlnNE P/HR NONE P/HR NOflE F.)HP, NQfi~>4>f'lONE R/HF, flOflE P./HP.flGflE P/HP.f'lONE R/HR NOI'IE P,/HR Vf'IIT 1 PAGE I OF I GPOUP NUt"lBER:10 PQII'lT NQ.DESCRIPTIOI'I V AS HIGH LAST LIMIT 46094 I 5.00 490.36 15.00 0 A I 15.00 0.23 15.00 100.31 15.00 12.28 15.00 12.41 15.00 0.50 15.00 0.36 I 5.00 OA4 15.00 ALARM IS ST ATE NOi'/414.84 441.52 0.37 0.21 90.28 11.05 11.17 0.45 0.32 OAO API-I-56-RHR Ri3i3M LOOP 8 ARI"I"55-RHR ROOI I LOOP A ARM-57-PCIC PP TURB RM ARM-48-HPCI PP/TURB RM ARM-5$-ACCS TO PEt'I SHUTD ARI"I-50-CPD flOPTH ARM-51-CRD SOUTH ARM-52-RVCU PP ACCESS ARt"1-54-FUEL POOL PP ROOM APt"I-49-REFUEL FLOOR AREA P AP.55 P AR57 PAR48 P AR53 PAP50 P AR51 P AP52 P AR54 P AR49 GROUP POINT D(SPLAY SEPArlCES Kl RANGE ARt"I READINGS (E-PLAN DISPLAY)8-Oct-91 21:00 LOV LINIT UfllTS fll3lIE R)HP.flOflE R/HR I'IOf'lE P.)HP.rlorlE NONE R/HP, flGNE P.]HP.NONE R!'HR flQf'lE R/HR rlorlE R/HR flQNE R/HR VTI-57 UIIIT I, PAGE I OF I GROUP f'IUt"IBEP.

'10 PGIfIT NO.DESCRIPTIOf'I V AS HIGH L AST L II"I IT 414.84 15.00 441.32 15.00 0.37 15.00 0.21 15.00 90.28 I S.OO 11.05 15.00 11.17 15.00 0.45 I 5.00 0.32 I 5.00 0.40 15.00 ALARM STATE IS NOV 373.36 397.19 0.3 a 0.19-81.25 9 95 10.05 0.41 0.29 0.36 ARN-56-PHP.

F;GOM LGGP B API"I-'5-PHR POGt"I LOOP A ARI-1-5-RCIC PP TUF.B Pt-I ARI"I-48-HPCIPP/TUPB Pl"I API"I-53-ACCS TO REt"I SHUTD ARM-50-CRD NORTH ARN-51-CRD SOUTH ARI"I-52-PhrCU PP ACCESS ARM-54-FUEL POOL PP PGGM API"I-49-PEFUEL FLOOR AREA PAR56 P AP55 P AR57 P AR48.-AI?53 P ARSG PAP51 P AP.52 P AR54 P AP,49 GROUP POINT DISPLAY SERVICES Hl PAf'IGE ARI"I READIf'IGS (E-PLAN DISPLAY)LGr L It"IIT NOIIE fIOfIE i'IOf'IE HONE NONE NONE:IGIIE IIGfIE NONE f'IOf'IE UfI ITS R/HR R/HP.R/HI?F.'/HP.R/HP.R/HP.P./HF.'/HR R/HR 8-Oct-91 21:!5 Vf'IIT I, PAGE I OF-1 GROUP NUNBEP.:10 PGlf'IT f'IO.DESCRIPTIOf'I V*S HIGH LAST LII"IIT 15.00 397.1 9 I 5.00 0.33 15.00 0.19 15.00 81.25 15.00 9.95 15.00 10.05 I S.OO 0.41 15.00 0.29 15.00 0.36 15.00 ALARN IS ST ATE NG'rr 336.02 w5 0.30 0.17 73.13 8.95 9.05 0.36 0.26 0.32 P AR56 P AR55 P AR57 PAR48 P AP53 P AR50 PAR51 P AP.52 P AR54 P AR49 ARt"I-56-RHR RGOI"I LOOP B APt"I" 55-RHP.ROGI"I LOOP A ARM-57-PCIC PP TURB PN ARt"I-48-HPC I PP/TURB RN ARM"53" ACCS TO REt"I SHUTD ARM-50-CRD NORTH ARN-51-CRD SOUTH ARN 52 R 0 CU PP ACCESS ARI"1-54-FUEL POOL PP RQOI"1 APN-49-REFUEL FLOOR AREA GROUP POII'IT DISPLAY SERVICES Hl RANGE ARN READINGS (E-PLAN DISPLAY)8-Oct-91 21:30 LGV Llt-IIT JfIITS NOf'IE R/HR IIGNE R/HP NONE P./HI?fIGIIE fIONE P./HR NOf'IE R/HP.NONE R/HP.f'IONE R/HR NONE R/HR NONE R/HR VII-58 UNIT I, PAGE I OF I GPGUP f 11JI-IBEP.:10 GPOUP POlf'IT DISPLAY SERVICES HI PANGE API"1 PEADINGS (E-PLAf'I DISPLAY)8-Oct-91 I:45 PGlflT fl0.DESCRIPT IOfl P AR56 P AP.P AR57 PAR48 PAR53 P AR50 PAP51 PAP52 P*R54 P AR49 ARM-56" RHR ROOM LOOP B APt"I-55-PHR ROOM LOOP A ARt"1-57-RCIC PP TURB Rt"1 APt"I-48-HPC I PP rr TURB Rt"I ARI"I-53-ACCS TQ REM SHUTD ARf"I-50-CPD I'(ORTH AF't"1-51-CF,'D SOUTH ARI"I-52-R'ii'CLI PP ACCESS*RN-54-FUEL POOL PP ROuN ARt"1-49-REFUEL FLOOR AREA ALAP,t"1 IS ST ATE flO"(302.42 321.73 0.27 0.15 65.8 8.06 8,14 033 0.24 0.29 V AS HIGH LAST I lf"1IT 336.02 15.00 35 r.4 r 15.00 0.30 15.00 0.17 15.00 73.1 3 1 5.00 895 1500, 9 05 15.00 0.36 15.00 0.26 1 5.00'32 15.00 LOV LII"I IT flOflE'lvflE NONE fIOIIE flOflE NONE NONE NOf'IE flOflE f'lGNE Ufl LTS P.iHP, R/HR R/HR RiHP, R/HF;R(HR R r'HR R F'HR Uf'llT 1, PAGE 1 QF 1 GPGUP NUMBER:10 GPOUP POINT DISPLAY SERVICES Hl RANGE APN READINGS (E-PLAN DISPLAY)8-Oct"91 22:00 PGII'lT f'IO.P A@56 P AP.55 P AP.57 P AR48 P AP53 P AR50 PAR51 P AR52 P AR54 P AR49 DESCRIPT IGI'I ARN-56-PHR ROOM LOOP B ARt"I-55-RHR POOt"1 LOOP A APN-57-RCIC PP TURB Rt"1 ARN-48-HPC I PP/TURB Rf"1 ARN-53-ACCS TO REN SHUTD APt"1-50-CPD NORTH ARN-51-CRD SOUTH ARM-52-Rb'(CU PP ACCESS ARt1-54-FUEL POOL PP ROOM ARt"I-49-REFUEL FLOOR AREA ALARM IS ST ATE NO'r(272.18 289.55 0.24 0.14 59.23 7.25 7.33 0.30 0.21 0.26'r(AS HIGH L AST L INIT 302.42 15.00 321.73 15.00 0.27 15.00 0.15 15.00 65.81 15.00 8.06 15.00 8.14 15.00 033 15.00 0.24 15.00 0.29 1 5.00 LOV Llt"1IT UNITS NOf'lE R J'HF.'ONE R/'HR flQflE Rr'HR I'IOf'IE R r'HR NONE R/HR f'lONE R)HR NOI'lE R r'HR NONE Rr'HR NONE Rr'HR 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 MhNUALLY ENTERED++(mR/ar)LOCATION NORMAL RANGE 20:45 2'1:00 21:15 21:30 21:45 22:00 22:15 ARM 38 ARM 39 MARGI 4 MAR02+ARM 37 ARM 31 ARM 29 ARM 30 ARM 32 ARM 34 ARM 33 ARM 28 RAG CHEM LAB CONTROL ROOM CNTM ACC Hl RAO h CNTM ACC Hl RAG 8 STBY GAS TREAT RM RV 646 CORR-SOUTH RV 646 COPR~TH RV 646 CORR-VEST CTRL ZONE SHOP STOR+EQUIP AREA RAO VASTE CTRL RM RV OR TO 2 FL SA 003 0.2 8 0.03 0.4 0.3 0.5 0.2 0.2 0.4 03.01-100.01-100 1-1E7 1-1E7.01-100.1-1000.1-1000.1-1000.1-1 ODD.1-1000.1-1000.01-100 0.03 I 0.00 6.7E+04 6.0E+04 30.00 0.40 0.30 0.50 0.20 0.20 0.40 0.30 0.03 9.10 6.6E+04 5.9E+04 27.30 0.40 0.30 0.50 0.20 0.20 0 40 0.30 0.03 8.28 5.9E+04 5.4E+04 24.84 0.40 0.30 0.50 0.20 0.20 0.40 0.30 0 03 7.54 53EKN 22.6l 0.40 0.30 0.50 0.20 0.20 0.40 0.30 0.03 6.86 4.SE+04 4.6E+04 20.57 0.40 030 0.50 0 20 0.20 0.40 0.30 003 4.3E+04 4.2E+04 18.72 0,40 0,30 0.50 0,20 0.20 0.40 0.30 003 39E+04 3 SE~OAR02-::

PriRkr P AP31 P AP29lAP30 PAR32 P AR3+P AP33 P AR28 APN-8-RAD CHEN 1.AB AP t"1-3'9-CQflTROL ROGI"1 CGf'ITt"If'I ACC RANG Hl RAD A CQIITINN ACC P.AI'lG Hl P.AD B APN-37-STBY GAS TREAT RN ARI"1-31-RV 646 CORP.-SOUTH APM-29-RV 646 CORP.-NGPTH ARM-30-RV 646 CORR-VEST API"I-32-CTPL ZONE SHOP ARt"I-34-STOR

+EQUIP ARt"1-33"RAD i'i ASTE CTRL ROOI"1 ARN-28-RV DP.TO 2 FL SA ALAPI 1 STATE IS NGV Q.Q3 10.00 6.7E+04 6.QE+04 30.00 GAO 0.30 0.50 0.20 0.20 OAO 0.30 VAS LAST 0.03 0.20 800 5.00 0.03 OAO 0.30 0.50 0.20 0.20 OAQ 0.30 HIGH LIMIT 4.QQ 4.00 NGflE flGf'lE 4.00 15.00 15.00 15.00 15.00 15.00 15.00 4.00 LOV L INIT fl'iflE NONE f'IGf'IE flGfl=NONE lIQflE NG{lE f'IOf'lE flOf IE rlorlE f<ONE NONE~I r,l IT ii'iF/+i"IF.r'rl R/I-:P.i HP i'!F'r H I'1R/H I-IP,/H i~1R/H t"1R/H t-IR/H i+1Pr H I"1P./H T 1,PAGE 1 OF I iiRGUP I'i'Ut"IBEP.:17 GROUP POlflT DISPLAY SERVICES CNTRL STR AND RADVASTE ARMS (E-PLAf'l DISPLAY)8-Gct-91 PGlf'IT f'l0.DESCRIPTIQf'I P AP.38 P AP39 NAP01~t 1AR02+P AR37 P AR31 PAR.9 P AR30 P AP32 P AR34 P AR33 P AR28 ARN-38-RAD CHEM LAB ARM-39-CONTROL ROOM COflTMfl ACC RAf'lG Hl RAD A CGflTt-if<

ACC RAflG Hl RAD B ARN-37-STBY GAS TPEAT Rt"1 ARM-31-RV 646 CORR-SOUTH ARM-29.-RV 646 CORR-NORTH ARI"1-30-RV 646 CORR-VEST ARN-32-CTRI.

ZONE SHOP ARN-34-STOR

+EQUIP ARM-33-RAD VASTE CTRI ROON ARN-28-RV DR TO 2 FL SA ALARM STATE IS NGV 0.03 9.10 6.6E+04 5.9E+04 27.30 0.40 0.30 0.50 0.20 0.20 0.40 0.30 VAS HIGH L AST L IM IT 0.03 4.00 10.00 4.00 6.7E+04 f'lONE 6.0E+04 NONE 30.00 4.00 OAO 15.00 0.30 1 5.00 0.50 15.00 0.20 15.00 0.20 15.00 0.40 1 5.00 0.30 4.00 LOV Llt"IIT[IONE NOI'IE flQNE NONE flONE f'[ONE rcor<E NONE NONE NQf'IE NOflE flQNE Ufl ITS NR/HP.MR/HR P.r'HP.P./HP NR/HP I"1P./HP.f"IRr HR t'!P.r'HP.NP./HP.MP./HR NP/HP t"IP,/HR VII-62 UNIT I, PAGE I GF I Gi?GUP f'IUI"IBER:17 GROUP POIflT DISPLAY SERVICES Cf'lTPL STR Af'lD RADWASTE ARt"IS (E-PLA!'l DISPLAY)8-Oct-91: l:1 5 POINT NO.DESCP IPTiGf1 P AP38 P AR39'1APG'-MARIJ2~P AP37 PAP.'9 P*R30 P AR32 P AR3~P AR33 P AI?28 APN"38-RAD CHEI"1 l.AB ARN-39-COrlTROL Raot-1 COf'ITt"IN ACC PANG HI RAD A CQNTt"1f'l ACC P.ANG Ht P.AD B ARf"1" 37-STBY GAS TPEAT Rt"1 API"I-31-PV 646 CORR-SOUTH APt"1"29-RV 646 CGRR-NORTH ARM-30-RV 646 CQRR-VEST ARN"32"CTRL ZQf'lE SHOP ARI"1-34-STOR

+EQUIP ARI"1-33-PAD VASTE CTRL RQOM ARt"I-28-RV DP.TO 2 FL SA ALARI" I STATE IS f'lOV 0.03 8.28 59E+04 5.4E+04 2<.84 OAO 0.30 0.50 0.20 0.20 0.40 0.30 V AS HIGH L AS 7 L IMIT 0.03 4.00.".10 4.00 6.6E+04 fIQflE 5.9E+04 NONE 27.30 4.0Q 0,40 15.00 0.30 15.00 0.50 15.00 0.20 15.00'.20 15.00 0AO 15.00 0.30 4.00 LIMIT NGflE ilGNE!IGf.IE!lGflE i'IGflE ilGflE NGflE NGI'lE flGflE NONE NOf'lE NONE Uf'l ITS MR/HP.t~'P!hR R/4P, 0 p'LJQ'"IP./HR I"IP./HP.I"I.;/HF;MR/HR MR/HP, t"1R/HR MP./HP.I"1R(HR.1,PAGE I OF1 GROUP PGII'lT DISPLAY SERVICES 8-Oc 1-~1 21 30 GPGUP flUt"IBEP.:17 PQlf'lT NQ.DESCRIPTION ALARM STATE IS NOW 0.03 7.54 5.3E+04 5.0E+04 22.6'I 0.40 0.30 0.50 0.20 0.20 0.40 0.30 HIGH l.IMIT 4.00 4.00 NONE NorlE 4.00 15.00 15.00 15.00 15.00 15.00 15.00 4.00 VAS LAST 0.03 8.28 5.9E+04 5AE+04 24.84 OAO 0.30 0.50 0.20 0.20 QAO 0.30 ARt"1-38-RAD CHEN LAB ARN-39" COf'lTROL ROOM COf'ITI"1f'l ACC RAf'lG HI RAD A CGf'lTNN ACC RA!(G HI RAD B ARt"1-37"STBY GAS TREAT RN ARM-31-RV 646 CORR-SOUTH ARN-29-RV 646 CORR-NORTH

• Rtl-30-RV 646 CORR-VEST ARI"1-32-CTRL ZONE SHOP ARM-34-STOR

+EQUIP ARN-33-RAD VASTE CTRL ROON ARN-28-RV DR TO 2 FL SA P AF;38 P AR3'9 IRAR01:: f"1 AF.'02-P AR37 P AP31 PAR29 P AR30 PAR32 P AR34 P AR33'AR28 CNTRL STR AND P.ADVASTE ARI"1S (E-PLAN DISPLAY)LQV L tt"1IT flGflE i"lGf'IE NONE NONE HONE NONE Nof'lE NONE flGflE flOflE rlorlE rlorlE Uf'l ITS t-IF:!HP.~PP iHn P.!HP.R/HF;I IR/hR MR!HP, t-IR/HP iNP./HP.I"IP,/HP.MR!HR t"IR/HR I"!R/HP, VII-63 GROUP POlflT DISPI AY SEPVICES Uf'IIT I, PAGE I GF I GROUP NUI"18ER:17 POINT f'IQ.DESCP.IPTIGN V AS HIGH L AST L IMIT 0.03 4.00 7.54 4.00 5.3E+04 I'IQI'lE 5.0E+04 flOflE 22.61 4.00 0 40 15.00 0,30 15.00 0.50 15.00 0.20 15.00 0.20 15.00 0.40 15.00 0.30 4.00 IS NQV 0.03 6.86 4.8E+04 4.6E+04 20.57 0.40 0.30 0.50 0.20 0.20 0.40 0.30 AL ARI"I STATE API1-38-RAD CHEM LAB ARM-39-CQflTROL ROOM CONTI'IN ACC PANG Hl PAD A CGflTI"1f'1 ACC P.ANG Hl P.AD B API"I-37-STBY GAS TREAT RM ARM"31-RV 646 CORR"SOUTH APM-29-!?V 646 CQPR-f'IORTH ARM-30-R'iY 646 CQRR-'<'(EST APM-32-CTRL ZONE SHOP API"1-34-STOR

+EQUIP ARM-33-RAD VASTE CTRL ROOM APM-28-RV DR TO 2 FL SA>AP38 P AR39 i~1 AP.Q I" t-!AR02--PAR37 PAP3I PAP29 P AR30 P AR32 P AR34 P AR33 P AR28 Cf'ITRL STR Af'lD RADVASTE ARf"!S (E-PLAN DISPLAY}8-0<.t-91 I.QV LII"!IT flONE'lorlE l'IGflE rlorlE f'IONE flQNE f'IONE f'IONE f'IGf'IE f'lONE NONE NONE Uf'I ITS I!R/~P.f'!F.'4R R,rHP R/HP f"IP./HP, i"'<P,/HP.

I">P/HF: '~E'HR<!R/HR I"1P./HR MR/HF.'"1P./HP.

GPOUP POINT DISPLAY SERVICES.T!, PAGE 1 OF I GPQUP f'IUt"18ER:17 POINT NG.DESCRIPTION ALARM STATE V AS HIGH L AST L IMIT 0.03 4.00 6.86 4.00 4.8E+Q4 NONE 4.6E+04 NGflE 20.57 4.00 0?40 15.00 0.30 15.00 0.50 15.00 0.20 15.00 0.20 15.00 0?40 15.00 0.30 4.00 IS NGV 0.03 6.24 4.3E+04 4.2E+04 18.72 0.40 0.30 0.50 0.20 0.20 0.40 0.30 ARM-38-RAD CHEM LAB ARM-39-COf'ITROL ROOM COflTt"1f'l ACC RANG Hl RAD A CONTt"If'l ACC RAf'lG HI RAD B ARt"1-37" STBY GAS TREAT RM ARM-31-RV 646 CORR-SOUTH ARM-29-RV 646 CORR-NORTH ARM-30-RV 646 CORR-VEST ARI"I-32-CTRL ZONE SHOP ARM-34-STOR

+EQUIP ARt"1-33-RAD VASTE CTRL ROOM ARM-28-RV DR TO 2 FL SA P AP38 P AR39 MAP01:: MARQ2+P AR37 PAR31 P AR29 PAR30 P AP32 P AR34 P AR33 P AR28 CI'ITRL STR AflD RADVASTE ARMS (E-PLAft DISPLAY)8-Grt-91 LQV LIMIT NONE NOf'IE NONE flGNE NONE NONE f'lONE NONE NONE f'lONE NO[IE NQflE Uf'<ITS MR.r'HR'~p'HP..~HP.R/HP, t-!P!HR I"!P./HP.t"1R/I P.t1Rr'HP.I"IP,/HR I<Rr'HP.'"!p/H>I"IF.'/HR VII-64 SECTION VII-RADIOLOGICAL CONDITIONS PART G-IN-PLANT DOSE SURVEY MAPS VII-65 CORE SPRAY PUMPS IA IC 0 0 D SIPPRE 5SIQH POOL WATER FILTER PIRO N~CORE SPRAY PUMPS D x 04~SSKW POOL 48 x 03 x SINP OIL TERCEP gA~SUMP 0 0 OWEO QAP PUMPS 55 x x25 RHR PUMPS 56 Oi x x 0'0 RHR HT.57 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)

TIME REACTOR BUILDING-ELEV 645 DOSE RATE IN MR/HR AREA A AREA B AREA C AREA D AREA E AIRBORNE MPC EXCEPT HPCI 1800 181 NORMAL NORMAL NO NORMAL NORMAL NORMAL:C9T5 1930 1945 2 (.)Mi 2100 2115 0 0 441,000 4400 397,000 4000 73VG~2 8250 300,000 250,000 4400 4000 ,00 206,000 222i000 2T3o~il--IaOD-T5&i TRRl~Goo ,000 ,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 WiLK WAY 53[x S s Q WIN 0 axaa REACTOR BUILDING-ELEV 670 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 1815 NORMAL NORMAL NORMAL NORMAL NO 1930 1945 22I c 2100 211 8500 8250 T'T5, tFoO 2 125,000 100,000 925 850 180 160 1825 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 M5 D C3 0 CHCII AOO TK.SPtIC<<,i POOL EHTRARCCS Z$V u>~lal Cl Z IIECHC g+Ei O OWFH5 i/IA/i RAN~PORKST ENTRANCE REACTOR BUILDING-ELEV 683 DOSE RATE IN MR/HR XNHJ H55KK MPC EXCEPT HPCI 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 1815 1'ORMAL NORMAL NORMAL NOEQGK NORMAL'930 1945 2100 ,00 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 06 X X 51 HCU~5RM IRM ORIVES C RECUR RECIRC IlUARI Q SRM TRM ORIVE5 X IH5T GAS 0 2 X GD TIR g~ORIVK5 CI B Q MSIV LC5 SLOwKR5 HCU~+i~o~ic+c+C c+w+B MOHORAA.HOIST CRO f LOW AIR SSURE 8 K$5 SWITCHGKAR E 5 5 SWITCHGKAR REACTOR BUILDING-ELEV 719 DOSE RATE IN MR/HR MPC EXCEPT HPCZ TFRJ~l 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 1815 NORMAL NO L'ORMAL NO NORMAL NORMAL 1930 1945 2100 211 10,800 9700 14, 00 13, 000 1800 1620 10i800 9 20 180 1 0 00 1825 3200 0, AIRBORNE IS 1/10 IN STAIRWAYS VII-73 CHILLER HILLE R OI PVAE 5 CDIKI WATER CNC.C7 C3 WA fh Clh CIKLLED WATER MK cF Qu O DACKWA5H RECCVNO TANK B u H T EXCH.x 10 x,.54 NIT RDGEH ACCUAKA.A TDR 5 THI5 LEVEL OJ u)52 08 A 5LC TANK c o;,-~SLC RWCU REGEH RWCU NIT REGEN 09 E 5 5 5WITCHGEAR B 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 18 MPC EXCEPT HPCI 1845 1900 1915 2015 2030 2045 30 1 200 600 1 0 2145 2200 200 225 100 75 6030 7400 AIRBORNE IS 1/10 IN STAIRWAYS (1)FROM REACTOR BUILDING AIRBORNE VII-75 A SAMPLE STATION'l lese r.one 5~5.4era g 0~Cv Jltlt PeeP Cm 8@~I he>7 C.vocal.Z CION'A4 C S~2 4et CO+D ca~tv pg WC V/ps'ri 5 z-r i3 CI0 Cr I Z Cr.ec~v.~p g 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 1<KG MPC EXCEPT HPCI 1845 1900 1915 2015 2030 2045 30 30 600 2145 2200 200 225 200 225 6030 7400 AIRBORNE IS 1/10 IN STAIRWAYS VXI-77 46 X 42 xe]3 RRCCW HO TK ON 199 A I i I RWCV-15 FILTERS ON 199'X t~FUEL'ASE STORA N FL'AL PLOL i5 Dl 4 C 4 x 47 REACTOR WELl.5'TEAM ORIER 5 SEPERATCR POOL REFUELINO PLATFORM RAR.5 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 I FK REACTOR BUILDING-ELEV 818 DOSE RATE IN MR/HR 0 MPC EXCEPT HPCI 1845 1900 1915 2015 2030 2045 30 600 2145 2200 200 225 6030 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 Time Sample Station Steps: B.1.35 to B.l.52 RE-507 Monitor mR/hr 20 30 to 21:00 740 21:00 to 21:30 681 21:30 to 22 00 607 22:00 to 22:30 548 Sample Line Dose RE-664 Monitor Sample: No Shield mR/hr 380000 349600 311600 281200 Contact (2 inches)mR/hr 6 inches mR/hr 18 inches mR/hr 36 inches mR/hr Sample: In Cask 490000 80000 10000 2600 450800 401800 362600 73600 65600 59200 9200 8200 7400 2392 2132 1924 Contact (2 inches)mR/hr 6 inches mR/hr 18 inches mR/hr 36 inches mR/hr 163 27 3 1 150 25 3 1 134 22 3 1 121 20 2 1VII-82 PASS REACTOR WATER SMALL VOLUME LIQUID SAMPLE DATA Time 20:30 to 21: 00 21: 00 to 21:30 21:30 to 22:00 22:00 to 22:30 Sample Steps: " RE-507 Sample RE-664 Station B.1.35 to B.1.52 Monitor mR/hr Line Dose Monitor mR/hr 740 681 607 548 380000 349600 311600 ,281200 Sample: No Shield Contact (2 inches)mR/hr 6 inches mR/hr 18 inches mR/hr 36 inches mR/hr Sample: In Cask Contact (2 inches)mR/hr 6 inches mR/hr 18 inches mR/hr 36 inches mR/hr 4900 800 100 26 131 21 3 1 4508 736 92 24 120 20 2 1 4018 656 82 21 107 17 2 1 3626 592 74 19 97 16 2 1 VXI-81 SECTION VIII MESSAGE INFORMATION SHEETS MESSAGE INFORMATION SHEET IS No.1 Time: 1500 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 MESSAGE INFORMATION SHEET IS No.2 Time: 1500 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 MESSAGE INFORMATION SHEET IS No.3 Time: 1500 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.

MESSAGE INFORMATION SHEET IS No.4 Time: 1500 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 MESSAGE INFORMATION SHEET IS No.5 Time: 1530 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 3.6 3.4 3.2 3.0 2.8 2.6 2.4 2.2 2.0 1.9 1.8 1.7 1.6 1.5 1.4 1.3 1.2 1.1 1.0.07.05.06.05.06.06.08.07.05.05.04.04.06.06.05.03.04.03.03.06.05.05.05.05.05.05.05.05.05.05.05.05.05.05.04.04.04.04.03.03 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 3.6.2 3.6.3 3.6.4 PLACE Plant in"SITE EMERGENCY" status and implement EP-IP-00?notifications.(EP-PS-126 Control Room Communicator when issued).MONITOR plant for indicat1on of leaks by observing sump level indicat1on,.

tank level 1nd1cat1ons, and makeup water flow increases.

MAKE surveys for possible damage in accessible areas (espec1ally concrete).

TEST RUN 01esel Generators fn accordance with SO"024-001.

C..r'4 QN-000"002 Revision 7 Page 8 of 12 CHECKEO 3.7'3.7.9 RELOAO blank/rewound cassettes in case of subsequent shock waves.CONTACT agencies listed on Attachment A for information regarding event...",.23XS 3.8 3.7.10 NOTIFY MC to perform SI-099-301 and SI-099-308 within 5 days afte~seismic event.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 3.8.4 NAKE surveys for possible damage in accessible areas (especially concrete).

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 3.8.7 3.8.8 PLAYBACK seismic data in accordance with OP-099-002 to make hard copy which can be transmitted to NPE Civil Group for evaluation.

COLLECT and FORWARO information from cassettes and other seismic monitoring system instrumentation to NPE Civil Group for evaluation.

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 4.17 S0-013"001 4.18 SO-024-001 18 Month Calibration of Peak Recording Accelerographs VR-25701, VR-25702 and VR-25703 Fire Protection System Monthly Operability 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)5.3.2 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.

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 Page 1 of 1 VIII-12 MESSAGE INFORMATION SHEET IS No.6 Time: 1610 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."~EKE FOR REFEREE USE ONLY 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 3.6 3.4 3.2 3.0 2.8 2.6 2.4 2.2 2.0 1.9 1.8 1.7 1.6 1.5 1.4 1.3 1,2 1.1 1.0.07.12.11.09.11.12.11.18.15.13.13.14.13.12.12.11.11.16.13.12.10*10*1P*10*1P*10*]p*.10*1P*.09*10*11*ll*ll*.12*10*ll*.12*11*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 3.6.2 3.6.3 3.6.4 PLACE Plant in"SlTE EMERGENCY" status and implement EP-IP-002 not1f1cat1ons.(EP-PS-126 Control Room Communicator when 1ssued).MONDOR plant for 1nd1cation of leaks by observing sump level indicat1on, tank level 1ndicat1ons, and makeup water flow increases.

MAKE surveys for poss1ble damage in access1ble areas (espec1ally concrete).

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 3.6.7 3.6.8 PLAYBACK seism1c data fn accordance with OP-099-002 to make hard copy which can be transmitted to NPE Civil Group for evaluation.

COLLECT and FORWARD fnformat1on from cassettes and other se1smfc monftor1ng system 1nstrumentatfon to NPE Civfl Group for evaluation.

RELOAD blank/rewound cassettes fn case of subsequent shock waves.3.6.9 3.6.10 CONTACT agencies listed on Attachment A for 1nformat1on regard1ng the event.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 3.7.2 PLACE Plant fn"ALERT"'tatus and implement EP-IP-002 not1ffcatfons.(EP-PS-126 Control Room Communicator when issued).CHECK for indication of'eaks by observing sump level fndfcatfops, tank level 1nd1cat1ons, and makeup water.flow increases.

3.7.3 3.7.4 MAKE surveys for poss1ble damage in access1ble areas (especially concrete).

TEST RUN Diesel Generators fn accordance with S0-024-001.

3.7.5 3.7.6 3.7.7 TEST RUN 01esel Fire Pump in accordance with S0-013-001.

PLAYBACK seismic data in accordance with OP-099-002 to make hard copy which can be transmitted to NPE Civf 1 Group for evaluation.

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 3.7.9 3.7.10 RELOAD blankjrewound cassettes in case of'subsequent shock waves.CONTACT agencies listed on Attachment A for information regarding event.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 3.8.4 MAKE surveys for possible damage in accessibl~

areas (especially concrete).

TEST RUN Ofesel Generators in accordance with S0-024-001.

3.8.5 3'.6 3.8.7 3.8.8 TEST RUN Diesel Fire Pump in accordance with SO-013-001.

II PLAYBACK seismic data in accordance with OP-099-002 to make hard copy wh1ch can be transmitted to NPE Civ11 Group for evaluation.

COLLECT and FORWARD information from cassettes and other seism1c monitor1ng system instrumentation to NPE Civil Group for evaluation.

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)tm.I PP)5.3.2 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.

Operating Basis Earthquake (OBE)The OBE is that earthquake which, considering the regional and local geology and seismology and spec1fic characteristics of local subsurface material, could reasonably be expected to affect the plant site during the operating life of the plant;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 MESSAGE INFORMATION SHEET IS No.8 Time: 1620 MESSAGE FOR: THIS ENTRY WAS DELETED.MESSAGE FROM: LOCATION: MESSAGE: REFEREE NOTES: FOR REFEREE USE ONLY EXPECTED ACTIONS: VI I I-20 MESSAGE INFORMATION SHEET IS No.9 Time: 1620 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 <br />0.448 hours <br />0.00267 weeks <br />6.14127e-4 months <br /> 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 MESSAGE INFORMATION SHEET-IS No.10 Time: 1625 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." REFEREE NOTES: FOR REFEREE USE ONLY 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 C h L>1~h h>h>h h>>'->>>(0 Col 6w~/4 VIIZ-23 STEAM TUNNEL AREA Hr Tep (C-3)~-I-'I'>.-r40 Revf sfon 6: Page 13 ot 34 page-..Op..coi.:.,SETPO:Ni'..

iI~f i'i y NlG jN: TRS:-G33-}N604.

(1574F)~G33-1N605 (6PoF.~'T)'.>LS.1.0 PROBABLE CAUSE: r I~1..1 Mafn Steam 1fne break frr Reactor or Turbfne-Bufldfn Pfpe Tunnel (Qilf elorw on>>>>e0/pe rc4+)..,.':~.

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 QQ..-Z,I.3 R 5r av:IiIieg QconrTci~nei'iin6'sAf pe+75'H 5RI rir6ooh 8 c i'0 iver" yprh'~ev'Idio Z0ce~7unncl M I+on 0 NjCo~>g.r.5 fr~cbr aiildi'ii)

'Pen 7ieiid'CRT FOCII 8RI AV&o>'4 j gZ Z$eicessiQe gpacrr..eo~'euilliny end T~r6ine C~Idi~g~eeni jvnne)c for gpss~/AM,,'>~>,."...i~,'"-.4:.'.3 grigvRg Reecfor aviidiq H<R'~>epceig~llp Hai~Steom Tvn~cI Coakrs~i'n crpeehon in accor'done<

rrr'iK: 0'p-r~rr-cog Reocler euiiding h'yhi-Banc'L crnd gone.X':<".~'*Ž'::~'-"..'",'"-

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 or Rcoe~Sciildiy Miu, 2.7 Pf&ir<filo'g f T 6'E Id~, P~T I Wt 6': Q,7 I~uRK i'c.PSA-BrcekcrS.Zq9r'enoI 6'l-+f80.Z~.Z IVozir 7 a'~]Gaff-~*r'nudge>e MOHi7O4 peecgr cited 76o~Quilltiif Vcnrhrcps go~eicceiruc Ve/eiSe eius'ul argot A7r roN loons (.IIoweuer con'firrvcel 5m~roIurm rrrcreecc couid m>s<<gr V rcao*on)4.0

REFERENCE:

E-324 Sh 16 4.2 M1-B21-98(3) 4.3 IOM 305 VXXX-24 MESSAGE INFORMATION SHEET IS No.11 Time: 1625 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 MESSAGE INFORMATION SHEET IS No.12 Time: 1645 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 MESSAGE INFORMATION SHEET I IS No.13 Time: 1700 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 MESSAGE INFORMATION SHEET IS No.14 Time: 1710 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 MESSAGE INFORMATION SHEET IS No.15 Time: 1800 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." REFEREE NOTES: EXPECTED ACTIONS: FOR REFEREE USE ONLY 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.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 3.6 3.4 3.2 3.0 2.8 2.6 2.4 2.2 2.0 1.9 1.8 1.7 1.6 1.5 1.4 1.3 1.2 1.1 1.0.55.58.53.40.32.36.37.39.34.28.25.27.19.29.29.53.60.43.26.37 2 3**23**23**23**2 3**2 3**2 3**23**'2 3**2 3**2 3**2 3**.11*2P**2P**2P**19**18**18**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 3.6.2 3.6.3 3.6.4 PLACE Plant fn"SITE EMERGENCY" status and implement EP"IP-002 notfffcat1ons.

{EP-PS-126 Control Room Communicator when fssued).MONITOR plant for 1nd1catfon of leaks by observing sump level indication,.tank level indications, and makeup water flow increases.

MAKE surveys for possible damage fn accessible areas (espec1al ly concrete).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 3.7.7 PLAYBACK seism1c data in accordance w1th OP-099-002 to make hard copy which can be transmitted to NPE Civ11 Group for evaluat1on.

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)5.3.2 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.

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 MESSAGE INFORMATION SHEET IS No.16 Time: 1800 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 NOTES'OR REFEREE USE ONLY 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 O~II a n 4$O 0 0/i//~/a AaO~\VIII-35 MESSAGE INFORMATION SHEET IS No.17 Time: 1805 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 Ily Il, OO r~rcgc r rr+~4 4)(((OE I(((I((y E((EO I 11.E(~(l (0 I (g(I (0 MESSAGE INFORMATION SHEET IS No.18 Time: 1805 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.EXPECTED ACTIONS: Refer to the attached alarm response procedure for the expected operator 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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REFERENCE:

4.1 E-324 Sh 16 4.2 M1-B21-98(3) 4.3 IOM 305 VIII-41 MESSAGE INFORHATION SHEET IS No.19 Time: 1810 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." REFEREE NOTES: FOR REFEREE USE ONLY 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 MESSAGE INFORMATION SHEET IS No.19A Time: 1815 MESSAGE FOR: Control Room Operators I IP~*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 Format¹47."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 MESSAGE INFORMATION SHEET IS No.20 Time: 1820 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 MESSAGE INFORMATION SHEET IS No.21 Time: 1830 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: P'J~-Ci 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-46 IS No.22 Time: 2000 MESSAGE INFORMATION SHEET MESSAGE FOR: General Office Engineering Support Manager AP'fj r il~ea.~i~\~NEH EF: Si 1 dPCCDi tt~s<p~~~/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: The information received from the PCC should be passed on;",'o the remainder of the 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

~, MESSAGE INFORMATION SHEET IS No.22A.Time: 1945 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 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.

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 VIII-48 MESSAGE INFORMATION SHEET IS No.23 Time: 2030 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." REFEREE NOTES: FOR REFEREE USE ONLY 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'=.3:.'8 3.4 3.2 3.0 2.8 2.6 2.4 2.2 2.0 1.9 1.8 1.7 1.6 1.5 1.4 1.3 1.2 1.1 1.0.85.76.53.62.44.58.61.51.68.71.54.63.72.56.59.53.60.67.72.52 2 3**2 3**2 3**23**23**23**2 3**2 3**2 3**2 3**2 3**2 3**2 3**20**20**20**19**18**18**i 18**CHANNEL 1 WT-35701 CONT.FND 000 00 30 40 FOOFF12 000 05 36 40 FOOFF12 DIRECT-20%VIII-50 MESSAGE INFORMATION SHEET IS No.23A;Time: 2Q20.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." REFEREE NOTES: FOR REFEREE USE ONLY 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'ndications provided to ensure a proper start and oper ation of the SBGTS.VIII-51 MESSAGE INFORMATION SHEET IS No.238 Time: 2030 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