ML20043A512
| ML20043A512 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 04/03/1990 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20043A511 | List: |
| References | |
| NUDOCS 9005220177 | |
| Download: ML20043A512 (190) | |
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- rg CAROLINA' POWER & LIGHT COMPANY -
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PLAN FOR_ BRUNSWICK STEAM ELECTRIC PLANT EMERGENCY EXERCISE 1 u- ., APRIL 3, 1990- . E T .
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tI Lj l l CAROLINA-POWER in LIGHT COMPANY' PLAN FOR BRUNSWICK STEAM ELECTRIC PLANT EMERGENCY EXERCISE APRIL 3. 19901 TABLE OF CONTENTS , PAGE I. MISSION AND PURPOSE OF-EXERCISE................................. l' A s II. SCOPE AND OBJECTIVES. 1 l I,3% A. - Scope- ..................................................... 2-
- 8. 0bjectives.................................................. ?2.
I I'I . SITUATION AND ASSUMPTIONS ' l A.= Exercise 0ates.............................................. 3. -+ B. Exercise Locations / Facilities;.............................. 3 IV. CONCEPTS AND CONDUCT OF THE EXERCISE
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I A. . Exercise Scenario............................................. 4 , B. BSEP Exercise Organization Activities....................... 25-C. Evaluation and Critique..................................... 6
- 0. Exercise Exempt' Personnel................................... 7: r E. General Guidance for the Conduct of the Exercise............ 7-V. COMMAND. CONTROL. AND COMMUNICATIONS- -
A. SiteEmergencyCoordinator,(SEC).....................;...... 9 B. Communications.............................................. 9-C. Records ....................................................- 9 . O. Exercise Message Card...............i....................... 9 t E. Time .................................................... 9' F. Message Preamble and Close.................................. 10 > VI. ATTACHMENTS Attachment 1 - Instructions for Controllers and Evaluators Attachment 2 - Instructions and Rules for Players Attachment 3 - Exercise Control / Evaluation Organization Attachment Scenario and Time Schedule of Simulated Plant Conditions f i a 4 (90-002HRG/ebc)
g, f 4 j CAROLINA POWER &' LIGHT COMPANY: } PLAN FOR BRUNSWICK STEAM' ELECTRIC PLANT EMERGENCY EXERCISE APRIL 3, 1990
- 1. MISSION AND PURPOSE OF EXERCISE-To activate and. evaluate major ' portions - of emergency response-ct.pabilities and other elements _ of the CP&L Brunswick Steam- Electric
' Plant Plan, associated implementing procedures, and the :CP&L Corporate -I Emergency Planszin accordance with Nuclear. Regulatory Commission (NRC)=
Regulation 10CFR50.47(b). 11.- SCOPE AND OBJECTIVES. A. 1Sccce A simulated ! accident at the Brunswick Steam- ElectHe PlantE(BSEP)- whichicould-escalate to a general emergency.and will involve planned' response and recovery actions to include:' emergency classification; notification of off-site organizations and.-plant personnel;. actions ~ to correct the - emergency conditions;J and -initiation . of accident assessment -and protectivei actions as : necessary to; cope with the - accident. The exercise wi.ll' simulate- an emergency that results . in off-site, radiological releases which require responses 'by' state- and-local government personnel (state' participation will bevlimited: to-those functions: necessary to support _ implementation of county-plans). B. Objectives The 1990 Brunswick Emergency Preparedness Exercise will provide an , opportunity for. emergency response personnel to: e
- 1. Demonstrate the capability of on-site personnel to. effectively utilize.the emergency action level-' scheme.
- 2. Demonstrate the adequacy of the control room staff 'in control and accident mitigation activities. along) with accident assessment. 9
% 3. Demonstrate the adequacy of procedures for alerting, notifying,
, and mobilizing emergency response personnel '(some . individuals
- will be pre-stated within the local area). j
- 4. Demonstrate that communications' capabilities exist to accomplish q notification of off-site agencies. ;j q
- 5. Demonstrate the capability to notify off-site authorities within I 15 minutes of the emergency classification, j
_ 6. Demonstrate the adequacy of the information provided in the j initial notification, as well as follow-up notifications to the , state and counties. (90-002HRG/ebc) { k
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. 7. Demonstrate the capability -of personnel to activate the Technical: Support- Center. Operations Support: Center . and J o : Emergency Operations facility as-described in-the emergency-plan-.
and procedures.
' 8. Demonstrate 1 the transfer. of' responsibility between emergency- '
response facilities as described in the plan and procedures. j
- 9. Demonstrate the capability .' to-- communicate between emergency response-facilities. '
- 10. Demonstrate the - adequacy - of the - Operations Support Center in- '
providing manpower support.and coordination., .
- 11. Demonstrate the ' adequacy of the : Technical Support Center in providing accident assessment and mitigation. dose assessment. -*
and communication / notification activities.
-12.-Demonstrate the adequacy of: the Emergency' Operations f acility in coordinating'off-site utility-activities.
- 13. Demonstrate recordkeeping requirements as described :in - the plan ~ .
Land procedures, j
- 14. Demonstrate that status boards are maintained.and updated.
- 15. Demonstrate the capability to provide L '~ adequate radiation protection services- such as = dosimetry' and. ' personnel monitoring. -
- 16. Demonstrate the capability -to perft.,rm radiological monitoring activities and assessments. ,
- 17. Demonstrate the capability to support the rac ciogical assessment process while maintaining personnel. radiation exposure.as low as reasonably achievable.
% 18. Demonstrate the capability to perform on-site . accountability within' 30 minutes from .the time -of the~ order for accountability.
- 19. Demonstrate the capability to provide safe on-site access to off-site emergency services and/or support personnel (normal securityaccessprocedureswillbeadheredto). ;
- 20. Demonstrate those NRC identified open items resulting from- the 1989 BSEP exercise. ,
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f , p: 111.--SITUATION AND ASSUMPTIONS
~A. Exercise Dates
,1. Pre-Exercise Evaluator Meeting: Apri1=2, 1990: ,
TSC/E0F Training Building, Room No.--143-B-
- 2. Exercise: April _3,_1990'
- 3. Evaluator Group. Meeting: April'4, 1990-
- 4. Lead Evaluator Meeting: Room No.'122-April-4, 1990 1
' 5. - Post Exercise Critique Report _to Players' April 5, 1990
- 6. NRC Exit / Critique -!
I April 5, 1990 l l B. Exercise Locations / Facilities
- 1. Brunswick Plant, Southport, North Carolina i
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- a. Control Room . - Function is to . provide plant control and i initial' direction. of. all plant related_ emergency (
conditions.
- b. Operations Support Center (OSd - The OSC will be -located in.
the Service Building. The function of'the OSCtis to provide- ; an area for assembly and briefing ' ofEoff-shif t and :other j support personnel. '
- c. Technical Support Center -(TSC) - The cTechnical Support j
. Center is located in the Training Duildingsand.isito provide- a an assembly location for technical. personnel. who provide i engineering and ' management . support of plant activities l
.following an accident; direction and coordination of overall plant emergency activities; direction and coordination of: -
field, mobile, radiological monitoring teams prior 'to. E0F activation; on-site dose - projections; off-site . dose- 4 projections prior to EOF activation; display of status of plant parameters;- and provide an emergency . reference-collection of selected engineering and plant-documents.- The TSC is activated and emergency functions performed _i n 1 accordance with the provisions of . the plant radiological J emergency response plan and procedures. 4 (90-002HRG/ebc) i se _ _ .,m. -.
m 4 The:TSC'will:performthe.EmergencyOperationsfacility(E0F) functions until-the EOF is operational. In; addition to the normal _ plant" communications system . redundant Jemergency a- comunications : facilities Jin the::TSC 'prov.idei telephone; contact with required-agencies.and other response centers-by-use of the Corporate Emergency Communications System..
- d. Emergency 0)erations Facility (EOF) .The' EOF is located?in the plant ." raining, Building.- When_ activated. the EOF Lisi managed.by.the Emergency' Response Manager. . He will have'a-staff . to provide - support in: Technical .. Analysis.
Administration and Logistics Radiological Control',- and1 'r Emergency. Comunications.
- e. Meteorology Tower - Located north: of the. TSC on- the ' plant: -i site. Measures wind.: at 11.46 -meters :(38.. feet)-- and-.104.55z meters'(345' feet)~above the ground.. 4
-Meteorology and Weather-
- 1. = Start of' Exercise: : Canned .
- 2. Subsequent: Canned.
- f. Miscellaneous Facilities O (1) Brunswick County ' Airport foot elevation, ~ 3200-foot:
runway, is located;approximately 5 miles via Route - 133: from the'BSEP. -Phone (919)L457-6577. (2) Motels- . Sea Captain Hotel, Southport ;NC, (919) 457-5263 la d k., 4 , Wayward Wynds. Yaupon Beach, (919)'278-5975 . Oak Island-Inn, Yaupon Beach, (919)i278-5442; Ocean Crest Motel, Long Beach,-(919) 278-5212: BestWesternCarolinian,-Wilmington,(919)763-4653 IV. CONCEPTS AND CONDUCT OF THE EXERCISE A. Exercise Scenario The exercise will simulate an off-normal incident - at ' BSEP that ; should escalate -to a General Emergency and require: . accident-recognition and classification; assessment of on-site and'.off-site - radiological consequences;- alerting, notification, and mobilization [ of.'various organizations and personnel; in-plant corrective. actions; activation and use of emergency facilities and equipment;~ effective use of communications; preparation. of. reports, messages, and' I records; and implementation of on-site protective actions. During l the course of the exercise, there will also arise incidents that (90-002HRG/ebc)
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- J. I require ' deployment. of CP&L radiological monitoring teams for.
of f-site monitoring. The scenario and; timed schedulei of simulated!
. plant conditions isT contained in1 Attachment ~4. Only the NRC and -
CP&L Controllers / Evaluators will receive the4 scenario'.f .
'B. Brunswick Exercise Organization Activities The- exercise. organization - will ' consist of' players; the Exercise 1 Director; Lead Controller; the' Controllers;:the Chief, Evaluator; the
~ Evaluators;.and Observers as follows:
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.l. The CP&L Players include all . p.lant and other : CP&L a personnel )
assigned (to perform i functions of1the -emergency _ positions Las-
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described 'ini Section"-3' of 'the Plant Emergencyl Procedures-1
-(PEP). ?Tne success of. the exercise. is largely dependent ,upon
- playerfreaction, player knowledge of thelRadiological Emergency' '
Response Plan-_and Procedures, sand Jan : understanding - of the- i Exercise Plan ~and. objectives. :Some situations-affecting player t action or. : reaction. may-.' exist. - at L the . time' the exercise : play begins, however,'most will be introduced through-the_ vehicle of; 1 Controller _ Exercise Message ' Cards and ' messages- generated L by players as; a. result .of.-_following, the Dprocedures for. the: particular emergency activity they perform.;= Players,?therefore. are responsible for1 initiating: actio_nsDand/or messages : during the exercisejaccording-to the procedures. responsibilities, and
-tasks- outlined .for ^their particular function in - thea Plant ~
Radiological Emergency ResponseL Plan and: Procedures and in the Exercise > Plan-and objectives. Certain inconsistencies (such;as plume width, release.' duration - technical reason for. the-simulated release. etc.)J may be identified _ by players. These may be intentional and required to provide an exercise basis which tests the plant to the maximum . extent feasible in a . , limited time frame. With the exception ~of the already cited and ' potential inconsistencies.- the' internal- operations of- the' emergency response- facilities ,will bei identical--with their ., intended operation ein -a real emergency. Players will be: ' identified by wearing a 10 badge or Wil!TE ribbon, k
- 2. The Exercise Director will be responsible for overall conduct of i the exercise and to arrange preparation at the conclusion of the j exercise for a consolidated evaluation and critique report. '
- 3. Lead Controller will be responsible for coordinating controller.
input as necessary to initiate player response = and keep the exercise action moving according to the scenario and exercise objectives.
- 4. The Contollers will deliver " Exercise Message Cards" to designated exercise players at various times and pieces during the exercise; inject or deliver additional messages, signs, etc., as may be required to initiate the. appropriate player l response and keep the exercise action moving according to the scenario and exercise objectives; observe the exercise at their j assigned locations; prepare critique notes; and submit l (90-002HRG/cbc) l J
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L recommendations L on ' corrective actions . to' the J Chief ' Exercise; L Evaluator prior to thel scheduled' critique. ' Controllers will- be identified by wearing a:10 badge,or RED ribbon. l: 5.- Chief Evaluator and Evaluators ~. are 3. CP&L , or . other . qualified , I personnel .who .are assigned; < to ~ observe' and judge ;the - effectiveness ofi selected organizations, ' personnel.. functions, and/or 1 activities of! thel plant radiological; emergency' response-plan-and procedures. Selection of evaluators:is based on their
. expertise in,: or their. qualifications to. evaluate the activity,
-or area Lassigned. : for ' example, health:. physics activities 'will
.be-: evaluated x by qualified _' health; physics : personnel. _ When feasible, persons designated as_ Controllers forla given function 1 will also' .be assigned as. evaluators of t :that. function.. ^
Evaluators will record theiri -observations, ands provide recommendations ons corrective actions. toe the ' Chief L Exercise = Evaluator prior: to. the > scheduled critique'. .They willicrttique s
- exercise performance on the! basis of standards or rSquirements
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contained in~the Plant Radiological Emergency Reeponse: Plan .and: Procedures;: in- the: "ActionsiExpected" portion'of the Exercise'
. Message Cards and1 1 n the planifor the' exercise. : They will take steps whenever possible to collect datacon.-the time!and motion; aspects 'ofc the activity observed ' for: post exerciseJ use ,in' designing ~ y Wemgimprovements. Evaluators will be identified by wearing--a LO4 badge or BLUE ribbon.. - Wheni an Evaluator ^ is -
serving in T6~ntrol.ler role, they- will wearJa - 101 badge..oriRED ribbon.- .,
- 6. Observers from Lvarious ' CP&L components, and- from other organizations may ,be authorized on'.a . limited basis: to participate =in:the exercise solely for the purpose of' observing exercise activity. -
C. Evaluation and Critique 1
- 1. The exercise will be evaluated by = Evaluators who will be ,
assigned to key locations and response -- activi_ ties where they-will record their observations... Following -the- exercise,. Evaluators will present'their findings.at critiques as scheduled: in Section III.A of this" plan.
- 2. The following _ facilities will be evaluated -in addition to the Plant Emergency. Plan and Procedures: 1
- a. Control Room l
- b. Operational Support-Center
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- c. Technical Support Center .
- d. Emergency Operations Facility l
- 3. The following activities will .be evaluated 'as approprf ate based 1 on response to the. scenario. I f
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- a. LAccidentfrecognition,' classification, and assessment.E of- on-site- and' off-site radiological-
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- b. - Assessment :
consequences.'
- c. Alerting, notification ~and mobilization activities.
- d. In plant corrective-actions.
- e. : Activation and-use ~of emergency f acilities;and-equipment.
-f. Use of communications equipment and procedures,
- g. Praparation of reports,' messages and records.-
h.. Protective actions.-
- 1. On-siteLand off-site; radiological monitoring.:
- 4. Evaluations L will be made- on '.the basisiof exercise'-objectives;:
standards 1r requirements contained oin -the Plant 4 Radiological' Emergency Response ~ Plan and Implementing , Procedures; .and notations- Lin 'the " Actions Expected"- portion ;of : the! Exercise. Message Cards for the area evaluated. ' '
'5. Any' deficiency ,in the~ Plant Radiological. Emergency Response Plan- j and Implementing.. Procedures, training, etc. ,, that 'is widentified '
through the5 critique process shall: bei documented 1by. the Chief
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Evaluator and corrected by;the organizations and' individuals;who- i have- responsibility for tne ' areas identified. ,_ - Management ~j controls shalls be f.stablished;to ensure-that~ corrective _ actions; i are taken.as.necessary. 1
- 0. Exercise Exempt Personnel .!
3 Some plant' personnel must' be exempt from exercise > participation in- ! order to ' maintain 1 vital - plant functions such as security, normal. ) operations,' chemistry, etc. :1 E. General Guidance for the Conduct of the Exercise
- 1. Simulating Emergency Actions. ;
y Since exercises are intended:to demonstrate actual capabilities i as realistically as possible, participants should act as they i would-during a real emergency. Wherever'possible .-action should be carried out. Only when it is not feasible to perform an ~ action should it be simulated. Any orders given .that' for. any reason cannot: or should not actually be performed'should begin ,- with the word " Simulate." For example, the. order to put out a - .! l fire that is being hypothesized would' state:. " Simulate- ! discharging tho fire extinguisher." Whe're such actions' are L being taken. -it f si suggested- that participants inform any-controller / evaluators-in the area of what~ action really would:be- j taken had the emergency been real. .;
- 2. Avoiding Violation of Laws E
Intentional violation of laws is not justifiable during any exercise. To implement this guideline, the following actions must be taken: i (90-002HRG/ebc)
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- a. - Allc evaluators - and potenti.al exerciseiparticipants' inust be' I specifically informed: of rthe; need to avoid 7 1'ntentional. l violation of all -federal, state .and- local: 11aws, ,
regulations, ordinances, . statutes,- ~ and' other legal i restrictions. i b.; Exercise participants will' not direct illeg4' . actions beingj
.taken . by . other exerciseL participants- Lor _ memoers- of ? the =
general public.
- c. Exercise participants wil1 ~ not intentionally takefillegal actions when--being Ecalled -out1 tof participate' in _an '
' exercise.- Specifically... local traffic laws: such as: speed limits will"be observed.
- 3. Avoiding Personnel and Property Endangerment Participants ' and ~ evaluators - will' : be: instructedl to; avoid -
endangering property ~(public-~or private), other. -personnel ! responding- to 1the exercise', members 'of a the general public, ! animals,- and the environment..
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- 4. Actions to Minimize Public Inconvenience!
It is not the intent,~. nor is it1 desirable or feasible, to effectively train or-test the_public response during the. conduct; , of radiological emergency exercises. Public inconvenience is to. be minimized. The actions of - federal, state, and county ' agencies and nuclear power plant operators receive continuous- public' notice and- i scrutiny; therefore, the conduct of- an exercise .could' arouse s public concern that an actual emergency is occurring. It'is. important that conversations that can be monitored by=the public! (radio, ~ loudspeakers, etc.) is prefaced and concluded with the words, "This is an exercise message."
- 5. Maintaining Emergency Readiness During the performance of an exercise, the ability to recognize =i a real emergency,' terminate the exercise, and respond to.the new situation must be maintained. Therefore,'the exercise scenario ;
and actions of participants will not include any actions which seriously degrade the condition _ of systems, equipment or supplies, or affect ' the detection, assessment. 'or response capability to radiological or other emergencies. Actions take.n by the participants will also avoid actually 3 reducing plant or public safety. The potential for creating real radiological or other emergencies will be specifically avoided. ' i (90-002HRG/ebc) I
n , 1 If a real emergency ; occurs;duringdn exercise,_ requiring the j
-actions of' Company . personnel, then' the:-exerciseJ will' be- '
terminated ,by the Lead Controller ~or. the' Exercise. Directori in consultation with appropriate plant ' management.- . All messages : ;; ' about the real events will be clearly. identified, as such. For example. precede ~a peak message'with:. g "This is NOT, repeat NOT an exercise' message."- 4 V. COMMAND CONTROL, AND COMMUNICATIONS- r A.- Site Emergency Coordinat'or (SEC) l The - SEC -has-. immediate and unilateral authority to. act on behalf of the Company to manage and direct all on-site emergency ' operations. j
. involving the facility. 'During= the;-exercise, .he will:-have. :[
-responsibility- also. fori the. simulated emergency. exercise operations. . The~ SEC will be located in- the Control' Room at the -
beginning of. the' exercise and! will relocate to. the TSC -upon 1 activation of the TSC. B. Communications-
. Communication. equipment and procedures, are" described in Plant'-
-Emergency Procedures (PEP). The: telephone will.be the primary means
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of communication. C. Records 1 BSEP Emergency Procedures require that1 plant personnel- responsible for maintaining records during an emergency shall provide a copy of those. records to the. Emergency PreparednessLSpecialist following an. emergency or emergency exercise. - D. Exercise Message Card I The " Exercise Hessage Cards" are prepared . by the exercises drill planners / controller prior' to the exercise 'to ' satisfy. the requirements of the exercise scenario. The purpose of the completed form is to initiate-the appropriate exercise player response and to. keep the exercise action-moving according ' to the scenario and exercise objectives. The messages that are delivered to players during the play of - the exercise should allow " free play," i.e., should not tell the players what should be done. E. Message Preamble and Close
-l The words "THIS IS AN EXERCISE MESSAGE" should be used at the beginning and end of each message.
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~Attz hment 31
-INSTRUCTIONS FOR CONTROLLERS AND EVALUAf0ts
' 1.- Personnel are assigned as controllers or evaluators at;all key function areas to monitor and control the exercise. In addition, they will-accompany radiological' monitoring teams, plant health physics personnel,.
and maintenance repair / rescue' teams.<
- 2. The in plant. controllers.will be coordinated by the Exercise Lead Controller located in the TSC'(Ext. *).= He/she will: be responsible .for the overall conduct of the exercise scenario. If unable to reach thel Exercise Lead Controller, contact.the OSC Lead Controller (Ext. *).
Fleid controllers should contact the Environmental Honitoring Lead. Controller in the EOF (Ext. *) regarding coordination problems or questions. "
- 3. Nessage forms and simulated Control: Room data will be used co initiate -
modify, and complete the events comprising the overall scenario. Selected controllers will use the message forms to place the scenario eesnts in effect and to trigger responses fron the involved emergency- , response o'rganisations. Each controller will have copies.-of:the ' messages controlling the portion of the' exercise. scenario ~for whichL he/she is responsible. i Two kinds of messages will be used: Contro11ina 1 Messages used as a primary means of implementing' scenario > events.by announcing or placing an event in effect by hypothesizing , i conditions resulting from previous actions. i Continaency ' Messages used at the discretion of the' controllers with the approval of the Exercise Lead Controller in order to maintain the
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scenario plan continuity or schedule. Controlling messages will'be presented to.the designated exercise !i participant at the . time specified in the event- schedule. The controller i 1 should follow up with an explanation of the message ~and answer questions ' to ensure that the participant understands the message'. < Controllers will n_ot o initially 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 heir own judgment .in determining response actions and resolving oblems. l
- Phone numbers will t$e promulgated at the Controller / Evaluator briefing L_ preceeding the exercise.
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- 4. Note that the scenario events are hypothetical.. Any portions of the scenario depicting plant system operational transients are simulated'
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events.' Wo Control Room actionsh or reactions involving operation of, 1 plant:3ystems or affecting generation capability, will be initiated. l
- All exercise; scenario messages willi be previewed by and ended with the' words "THIS IS AN EXERCISE." Controllers stationed at areas vital'to 1 maintaining generating capability should be especially aware and take.
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-extra precautions in issuing messages or giving~ instructions regarding L
the scenario events. 5 >
- 5. Required controllers- will have, the time-related . plant and radiological-parameters of the exercise scenario. . This 'information: should be : issued i upon . request to the appropriate exercise participants by' either the' Control Room controller or controllers accompanying the< radiological
- monitoring fleid teams.
- 6. Some exercise participants may' insist that certain parts of the scenario-are-unrealistic. ._ The controllers and: evaluators have the authority, with.the approval.from.the lead controllers, to clarify any questions a regarding scenario content. In some cases, it may be necessary to -
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exercise " controller's prerogative" and say, "This'is due to exercise- , requirements" to preserve-the continuity and objective-of the exercise.1
- 7. Prior to commencement, all telecommunications should be' tested: to ensure- !
satisfactory communications between the lead controllers and all other controllers.
- 8. Controllers will commence their assignments at assembly locations-for players that they are to observe or as directed by the lead-controllers.
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- 9. Players are not allowed to introduce problems or events into thei exercise or its scenario.
CONTROLLER'S AND EVALUATOR'S RULES
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- 1. Know the overall Controller's Organization.
L 2. Identify the players by name and function.
- 3. Identify yourself at all times to all players. Wear' identification as provided by CP&L.
- 4. Identify.the phone (or radio for fleid teams) you will use to maintain communications with lead controllers.
- 5. Position yourself to maximize your effectiveness in issuing messages and' observing the players.
- 5. Be sure you understand the' player's scenario script and the master scenario.
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- 7. Keep the play on schedule by checking your script.
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-8. Issue the message on time'. Make sure the players understandtit.
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- 9. Remember to call the Exercise Lead Controller to: report on status of = '
~p layers' actions.if off schedu'le~or if.in' doubt about what-to- do. Cal 1< l for advice if' players depart significantly from thefscenario script.- ;
- 10. 'A11nw the players reasonable flexibility to_ perform their functions and demonstrate'their skill, knowledge, and initiative. j
- 11. - Identify the federal evaluators (s). 'Make sure they are' reasonably:~ aware '
of,all your actions and those of'the, players., q
- 12. Make notes on good and-bad points of players' actions,-the-strengths and.
j weaknesses, and_ areas for improvements. 13 Attend;the post-exercise' critique session'to provide;your comments!and~ recommendations to the Lead Controller.
- 14. Identify _the players': leaders.. Work with-them-as appropriate.-
- 15. .If a real. emergency occurs and this affects theJplayers, call off your portion of the ? exercise,;and_ notify the Exercise' Lead Controller immediately.
16 . - Be at your post at least 20 minutes prior to.any player action-commencement. , Set yourself up.
- 17. The federal evaluators will not issue." surprise" messages or. direct' '
" surprise" actions at:the players., They must' work through the, Exercise-Lead Controller; This'is-essential for the success-'of 'the exercise.
- 18. Controllers and federal' evaluators do not have to follow the radiation .
exposure control practices? appropriate for the simulated radiation levels., However, the players must' follow the' radiation protection rules for actual plant conditions. Controllers ~and evaluators will be' exempt. : ( from accountability and have access tofall areas.
- 19. Do not issue gontingency messages without clearance from the Exercise-Lead Controller.
l -DON'Ts
- 1. Don't leave your post at key times. '
- 2. Don't prompt the players to take action. 't i 3. Don't coach the players.
- 4. Don't criticize the players' actions during the play.
- 5. Don't forget to call the lead controllers to seek advice or help as necessary, 1
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.g 4 =6.- ! Don't allow the media /other! external' influences to distract the-l.-
I players. No interviews with' players are allowed unless. arranged through appropriate Corporate Communications personnel.- 7.- . Don't allow simulation when equipment-and facilities are available= except for: causing flow discharge of.. fits extinguishers, operation ~ of ~ + plant, systems,: etc. NOTE All participants will comply with radiation' exposure. control practices-for actual conditions existing at'the station at the time of the exercise. i L. 3 l
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J 1 1 INSTRlrFIONS AND RULES FOR PLAYERS ~ All' players-(at.least.the' leaders'of the player groups).must read and, follow the rules given below. This'is important to the successfult
' demonstration ~of emergency response capabilitie s.
,~
- 1. Identify your controller.by his identification badge.- Thesen controllers ~are also evaluators.: *'
- 2. fMRC/ FEMA (federal agencies) evaluators are also present. Identify.
~
- them by their identification badges.: .They are here to1 judge players' perf ormance -and approve - the ' energency . plan. -
- 3. Visitors may be present. Identify them by their identification A badges.- ;
- 4. Identify'yourself by name and function to'the exercise' controllers- Li and the NRC/ FEMA evaluators., This will-be helpful.H
- 5. Play out a11' actions. as much as 4ossible, in accordance with your ^
emergency plan and procedures as if it were a realtenergency. I Unless authorized by the controller, you should not simulate lyour actions. If authorized'to simulate an action, tell the' evaluator 1how and'when you:would actually do them. . j
- 6. Periodically speak out loud, identifying your. key actions and-decisions to'the controller and federsl: evaluators. This.may seem ni artificial, but it will assist in the evaluation = process and-is:to.
your benefit.
- 7. If you are in doubt, ask your._ controller for clarification. The -
controller will not prompt or coach you.
- 8. The controller periodically will issue mescages'or instructions designed to initiate response actions.'_You must accept these-messages immediately.=.They are. essential tc your' successful-performance.
i
- 9. If the controller intervenes with your play, i.t is for a good-L reason. ~ Obey your controller's directions at all times. ~ This is '
K essential to the overall success of the exercise.. 3 L 10. If you disagree with your controller, =you can ank him to reconsider. or consult with the controller's command center as tica permits. You must, however, accept.his/her word as final snd proceed.
- 11. Respond to the controller's questiona.
- 12. You must not accept any message / instruction from the fed
- cal evaluetors. If they want to initiate actions, test you abilities,
- or give you "sur' prises,"'they must work throuah your controller.
y This is essential to the overall success of the exercise. i' j (87-2HRC/pcj) I
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- 13. - ^ You must play as if-- radiation _ levels. actually are present', in -
-accordance with'the information you have received. This will' .
-require'that you; wear radiation dosimeters, anti-contamination I clothing, observe ~ good ra'diation protection practices, and be aware-of and minimise your radiation esposure.. Identify _the individuals in your emerger.cy response organisation_ responsible for. informing-you of these iteos. Follow their instructions.
a
- 14. 1The contro11ersrand federal evaluators areLemempt from actingLas;ifi ;
-radiation levels from the-emergency.asercise are present. 'Do not- ~
1
'let thse confuse you or cause.you to'act unwisely. t i
- 15. .If you~are entering normal l nuclear station' radiation areas, observe all rules land' procedures. Notone'(even the controller and< federal <
evaluators) is exempt from1 radiological ' practices and' procedures = '( required,by actuat= conditions.- i NOTE: 'DO NOT ENTER HICH RADIATION AREAg IN THE PLANT WITHOUT AUTHORIZATION'FROM THE CONTROLLER.;' FOLLOW ALARA PRINCIPLES.
- 16. Demonstrate knowledge of your' emergency plan, emergency operations,_
and procedures.- s 17 Utilise status boards,. log = book,.three part interoffice 1menos,. etc., as much as possible' to document: and record. your actions, instructions, and-reports (to your co players.~ This is very' , important'. Remember,."Put it in writing."
- 18. Do not enter- intoiconversations wicht the . visitors. ;
- 19. You may answer questions directed to you;by federal evaluators.: If the question is misdirected to you or you do not know the answer, refer them to your lead player or'the controller.
- 20. Keep a list 1of items you feel will improve your plans.and- .;
procedures. Remember'or.e of the mein ~ purposes of the exercise is for you, the players, to: assure yourself-that you are prepared adequately. Areas for improvement or Lessons learned, when identified, will improve'your overall emergency planning and preparedness. 21.' A critique of the exercise will occur after the exercise is i ! terminated. Provide your input to your lead player or the l controller. This will help in the overall evaluation the l controller will present at the critique. ; {. l
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l (87-2HRC/pej) '
. . -.. - - . . = . ,. - . . . .
.s Brunswick Emergency Preparedness Exercise
. Control / Evaluation Organization April 3. '1990 m
OFF-SIM FAClWTIES EXERCISE DIRECTOR EXERCISE LEAD EVALUATOR JIC C/E JIC C/E HCC C/E t I I I I LEAD C/E CONMOt. ROOM LEAD C/E TSC (EAD C/E OSC 1.EAD C/E EOF . C/E C/E C/E_._ C/E- ! C/E C/E C/E, C/E MEDICAL C/E' C/E SECURTW C/E C/E ENV MON I 4 C/E C/E , C/E ENV MON s C/E'
, . , . .. - - .:- . . . ~ , . . . . c :. .- . . . ~ , , . . . _ . . . . . - . . . . .
l {r ~ Narrative Summary i i
~
The' initial' conditions for this drill are Unit1'at 100*. power with-no equipment out of.scrvice. Unitc2;is:in refuel with CRD' removal-in- , L E progress-for rebuild.- During removal:of the control rod drive one of:
.the maintenance workers is injured frequiring transport to Desher ,
1 hospital. 1An. UNUSUAL EVENT will be declared due to transport of a potentially-contaminated person off site. The first hour of this drill will focus'on transport of the individual and installation of i the control rod-drive. One hour into the drill the main breaker for. j 480V motor control center ITK will trip due to a fault on the bus-bars of MCC 1TK. MCC 1TK feeds 120V distribution panel ID-TB2 which will fail three out of four Turbine Building supply fan-exhaust dampers to the common supply plenum.. The main steam tunnel will ' begin to heat up due to loss of ventilation flow until a main steam line isolation and reactor scram occur to the operating unit. Reactor water level will drop to 112 inches and HPCI and RCIC will automatically start and recover water level to' normal 15 minutes after the reactor trip the high' side tap for the HPCI steam.line high-flow detection device will break causing HPCI to ' isolate' and creating an unisolatable small break LOCA. The small break LOCA wil'1 require an ALERT to be declared and activation of the TSC. This small steam line leak will erode the pipi'ng and steadily gros larger as the event j progresses, but will remain within the capacity.of CRD and RCIC. l When suppression pool cooling is placed in service,a gasket leak will ! develop on the RHR heat exchanger outlet valve E11-F002B, forcing this loop to be secured. The drywell temperature and pressure will slowly increase for the next hour and 30 minuten until suppression j chamber pressure exceeds 13 psig where the-emergency operating j1 procedures will require initiation of drywell sprays. When drywell l sprays are initiated the Reactor Building to suppression. chamber I vacuum breakers (CAC-X-20A and CAC-X-20B) will open to relieve the l 3 negative pressure. These vacuum breakers function similar to check i valves and upon opening the hinge pin breaks on CAC-X20A and the i valve disk is wedged under the setting surface of the inboard MSC/90-0010 i
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s Narrative Summary (Cont'd)' , C -
!1 solation valve CAC-V16. -This resultsLin aLloss of primary-
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containment integrity which Tis' the second fissioniproduct barriorl to be breachedtand the event;should beLupgraded-to alSITE EMERGENCY. ' The Control Room indicationsiof this failure will be firef alarms, high temperature alarms, high radiation alarms.fand drywell pressure' ', remaining low-even though!the! steam leak stilliexist"andLdrywell.
~
w s q sprays were secured. =During'thernext' hour CRDiand-RCIC will'mAintainn
- vessel level but: RCICL flow wil1~ have to beJ increased, .despite the lowc ,
levels of decay heat,,as. the. steam: break size ' increases'. The RCIC. oil cooler developsfaLtube leak which?ds not:indicatediin the Control-
~
Room. After one' hour.at 2215 the RCIC' turbine'will seize. This'will: be indicated by'high turbine and bearing temperature alarms and lo( pump discharge flow. The steam" leak;is_getting-largerland vessel-level rapidly falls'.: When' ADS is: manually.or automatically Initiated all SRVs fail to open due to a common-mode solenoid:failuret LWith no-
- way to depressurize the reactor.to inject with low pressure ~ECCS:
pumps (core spray and LPCI) a GENERAL EMERGENCY = is dedlared. The emergency operating procedures will direct.that the main steam'line isolation be bypassed:and the reactor depressurized to the main- , condenser. .,.. When the bypass jumpers are installed ~and the MSIVs are asked to go l open, fuses will blow to the AC'.and DC solenoids on.the inboard i MSIVs. The cause of the fuse blowing will'be a ground on the inboard MSIV l-B21-F0220, with its AC and DC solenoids seeing moisture accumulation generated from the steam leak and drywell sprays. ~While - 1. the cause of the MSIV failure to open is being repaired, vessel level decreases to the bottom 1/3 of core causing significant fuel damage. The ground fault will be removed and some MSIVs will then open, allowing low pressure ECCS to reflood the core. The drill can be l' terminated when shutdown cooling is placed in service, thus terminating the release. MSC/90-0010 l
w - y y . BRUNSWICK STEAM ELECTRIC PLANT ANNUAL EMERGENCY PREPAREDNESS EXERCISE J APRIL 3,1990 - l UNIT 1 TIME EMERGENCY l CLASS UNIT 2 REACTOR TRIP LOCA - RELEASE
* - CONTAMINATEL 1800 ~ I " ' "' " " 'I -
LOSE TE sUPpLv raNs' 1900 lRancTOm Tarp l [ l
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~ TORtle VACUUN g g l SITE EMERGENCY l RREJeEER FAILS 2200 l RCIC TRIP GENERAL EMERGENCY l lAngyazLa DON'T OPEN
_ rhs. rarz.si 2300
- . . usIV OPEN 0000 - I " I 911mmunne
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Reactor Press u re i , 1200 i 1100-- 1000- - 900- - gog. . i 700 . ; Cn
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500-- g.
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i 4 200- - 100-- O : : : : : : " 1900 1930 2000 2030 2100.2130 2200 2230 2300 2330 2400 1915 1945 2015 2O45 2115 2145 2215 2245 2315 2345 0015 ' TIME E I """ y +. w 9 .yy w-e.- +eav , - + gg y,a e w tm , P ---we- # i-w -% w ge ' w -
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. CP&L-
' EXERCISE MESSAGE / DRILL CARD U-1/U-2 3 Plant:
Message 1No. 1- -Date- '04/3/901 4
- Time 1750 t
. MESSAGE FOR: Shift;0perating. Supervisor
. FROM :- CONTROLLER
- MESSAGE / SIMULATED PLANT CONDITIONS:
~
7
-Initial Plant' Conditions
~
Unit l'- 100*s power.,no significant LCOs ,
-Unit 2~ . R'efuel CRD.remova?L forErebu'ildLin progress' , .
Het tower motor link is:-down ACTIONS EXPECTED: , None , l ~. FOR CONTROLLER USE ONLY t g-s MSC/90 0011 , 6 i
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. CP&L l L -EXERCISE MESSAGE / DRILL CARD U-2 .
Plant- 4 i Message No. 2 Date 04/3/90 Time 1800- f-l= . , I MESSAGE FOR: Shift Operating Supervisor ,
, FROH t . CONTROLLER (call in by controller acting as1 mechanic)
MESSAGE / SIMULATED PLANT CONDITIONS: "THIS IS AN EXERCISE MESSAGE" , j
^The: Control Rod Drive;Holst-broke during the removal:of a CRD.
g
.The CRDLfell over on John Doe:k' nocking him to carousel. He is barely l !i conscious. I can see a lot of: blood and;there appears to be bone
~
sticking out.of his right les. ,Looks111ke..it is bent in anfunnatural s way. He has been pulled onto the' step >off-pad; e
! l ACTIONS EXPECTED: i i
Notify Health Physics. [ Notify on-site EMTs. 3 4 May notify rescue squad : May notify hospital (simulated) May declare unusual event.
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- FOR CONTROLLER USE ONLY .;
MSC/90-0011 ; [
- y. ...
J s. ? h CPE < EXERCISE HESSAGE/ DRILL CARD' U 2-
. Plant, ,-
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3 Message No. DateL 04/3/90I / Time' 1802--
. Provide after SOS receives call'-
MESSAGE FORi> Shift-Operating Supervisor: , , FRON:. CONTROLLER- -s- '! T '
! MESSAGE / SIMULATED PLANT. CONDITIONS: "THIS IS AN EXERCISE MESSAGE" For. the: purposes of the drill, the- frijury has .'s'ctually been staged at - the'-
west end of the Maintenance Building.
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ACTIONS EXPECTED: E CONTROLLER USE ONLY
- I
- q MSC/90-0011 .!
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'l CP&L. ..
EXERCISE MESSAGE / DRILL CARD 'U-2' Plant-
' Hessage No.- 4 Date. 04/3/90 Time Floatina-h MESSAGE FOR: Shift' Operating Supervisor- .
, (to be provided prior to hospita1' notification) ,
t FROM: CONTROLLER HESSAGE/S1*lVLATED PLANT CONDITIONS:l "THIS IS AN EXERCISE MESSAGE" For the pnrposes of the drill',1Dosher hospital.isinot playing.- Notifications to the hospital-only.will be simulated. HPsupportathospitalwil'1)be,simdlated. T
\
- ACTIONS EXPECTED:
Simulate hospital notification.- FOR CONTROLLER USE ONLY
-4
- MSC/90-0011-7 f-4
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1 CP&L-EXERCISE MESSAGE / DRILL CARD U-2' Plant. Message No. 5 Date :04/3/90~ Time 1805' MESSAGE FOR:- Responding personnel on scene FROM: CONTROLLER MESSAGE / SIMULATED PLANT CONDITIONS:= "THIS.IS AN EXERCISE MESSAGE" The ' actual injury occurred under . vessel during a' CRD _ pull.17he CRD!was dropped knocking the individual to the carousel. ;He was_quickly cut _out'
.of his bubble hood and. carried to the drywell step-off pad.. You'are now;
-at'the step-off pad for the Unit _2 drywell.~
ACTIONS EXPECTED: l 1 FOR CONTROLLER USE ONLY Provide the information on the attached page as necessary. MSC/90-0011
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Vital'Sians for Injured' Person'
. Blood Pressure , --
18:05 E i10/76; ' 18:20 _110/72 . . . 18:35- 90/60'
. Pulse-100-120 weak 1
-Respiration m 24 ,
Radiatton Levels'Undervessel
~
Work area dose rates; prior _to CRD_ removal'- 75^mr/hr
' Contact _ reading on CRD.at spud - 15,R/hr.;. -
18"' reading - 300 mr/hr 400,000 dpm/100 cm8 ' Radiation Levels at Victim < Dose rates at the step off pad'- 2,0'mr/hr: . RM-14 will go off scale when turned on. Contact reading on Anti-C's is 8lmr/hr Victim - after removal of all' Ant 14C's-and removal' from' area. Right leg at injury - 2800 cpm above bkg Forehead and hair - 1500. cpm above bkg i.- (': MSC/90-0011 l v ,
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CP&L1 EXERCISE' MESSAGE / DRILL CARD d-2 Plant Date' 04/3/90' Message'No. 6 l Time Floatina Provide when: D' i
, patient ~is' ready- D to: load into ;
cambulance- , i o MESSAGE-FORT EMT's and ambulance crew FROM't CONTROLLER j i MESSAGE / SIMULATED PLANT CONDITIONS: " Tills IS. AN EXERCISE MESSAGE"' I Transportation'of the victim'to the hospital will be~ simulated. ' a You may stop play at this point. 1 Notify Control Room that transportation to the-hospital is bding. e l simulated. -j l 1
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ACTIONS EXPECTED: Discontinue play.by all personnel involved'in-injury, FOR CONTROLLER USE ONLY HSC/90-0011 l' > _,m_. m ~
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CP&L-EXERCISE MESSAGE / DRILL CARD: . --U-2 Plant- ;
. sI aL - Hessage No.- I. Date . 04/3/90 Time. 1830' 1 contingency., 1
- MESSAGE FOR:-'- Shift Operating Supervisor'- ,
FROM:-. CONTROLLER- ,
- MESSAGE / SIMULATED PLANT.CONDITIONSr '"THIS IS AN EXERCISE' MESSAGE". ]
An' Unusual Event =should be declared based'on a.potentially,contaminat'ed injury requiring transportation off-site. l I i l
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ACTIONS EXPECTED: ;
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-)
a i l FOR CONTROLLER USE ONLY .( To be used only with approval of exercise lead controller. I l e MSC/90-0011 g
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CP&L _. .. .
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EXERCISE MESSAGE / DRILL CARD U- l ' ;j Plant '
~
Message No. 8 Date 04/3/90" . Time- ~ 1900-
.]
MESSAGE FOR:: Control: Operator (c j:;
'FROM: CONTROLLER ' ,
_l MESSAGE / SIMULATED. PLANT CONDITIONS: L "THIS-IS AN EXERCISE HESSAGE": You have justfreceived; UA-06 Window 1-5 i
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ACTIONS EXPECTED: - I.- Reference annunciator procedure. 2.- Dispatch A0 to investigate. i. FOR CONTROLLER.USE ONLY UA-6, Window.1-5 SUB IE 480V FEEDER BKR TRIP 1 $ l MSC/90-0011
. - ' .:i
4 o t . J, ' , , -CP&L-
- EXERCISE MESSAGE / DRILL CARD '
U Plant- ! Message No.: 9~ Date 04/3/90- , Time 1905 'i y MESSAGE FOR:- Auxiliary' Operator j . FROM: CONTROLLER > HESSAGE/ SIMULATED PLANT. CONDITIONS: "THIS IS'AN EXERCISE MESSAGE" - . MCC ITK'is tripped. ;
'I You'.can smell burnt. insulation coming from substation. ,
q No visible smoke.' , t k
-).
'I I
q ACTIONS EXPECTED: '!
- 1. Report to Site Emergency Coordinator.' .j
- 2. Investigate what loads are fed from MCC ITK..- !
3.- Initiate trouble shooting to recover the MCC. r t it
'h
.i 9
FOR CONTROLLER USE ONLY -
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-l MSC/90-0011 ~l l
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- CP&L.
. EXERCISE MESSAGE / DRILL CARD U-2 Plant
.- Message'No.'-10'
_ .Date 04/3/90 - Time' 1910
. MESSAGE FOR - ' Control Operator
'FROM: ' CONTROLLER MESSAGE / SIMULATED PLANT CONDITIONS: "THIS IS AN 1XERCISE MESSAGE" You have just' received annunciator:
A-02, Window 5-7: ACTIONS EXPECTED:
- 1. Reference annunciator procedure-
- 2. Attempt to determitie cause of alarm.
FOR CONTROLLER USE ONLY A-02, Window 5-7 STM LEAK DET ABM TEMP HI
\
MSC/90-0011 1 4
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CP&L EXERCISE MESSAGE / DRILL CARD U1 Plant Message No. 11 Dato 04/3/90 . Time 1913~ HESSAGE FOR:- Control Operator TROM's CONTROLLER ,
' MESSAGE / SIMULATED PLANT CONDITIONS: "THIS IS:AN EXERCISE MESSAGE"
- 1. You have just received the following annunciators:
A-05' Window 1-7 A-05 Window 2-7 A-05' Window 5-3 A 05 Window.5 4
- 2. Reactor water level quickly drops to 112 inches where HPCI and RCIC auto starts and Reactor. level.begins:to recover quickly.
ACTIONS EXPECTED:
- 1. Enter E0Ps and execute-Path 4
'2. Enter PEP-02.1. ,
- 3. Enter 01-51 to evaluate reportability,
- a. Should recognize that.one hour ~NRC notiff' cation is required due to HPCI injection to the. reactor,
- b. Four hour report on MSIV isolation a
l FOR CONTROLLER USE ONLY -) A-05 Window 1-7 ' REACTOR AUTO SCRAM SYS A l A 05 Window 2-7 REACTOR AUTO SCRAM SYS B A-05 Window 5-3 GRP I, ISO LOGIC A TRIPPED A-05 Window 5-4 GRP I ISO LOGIC B TRIPPED. i HSC/90-0011 I l i 4 b - a
,,7 3 A
L CP&L - EXERCISE MESSAGE / DRILL CARD sU-1~
- Plant <
12 Date 04/3/90 Message No, -Time 1930 i MESSAGE FOR:! -. Control. Operator TROM: CONTROLLER MESSAGE /S1HULATED PLANT CONDITIONS: Drywell pressure increasingi(ptnsently 2.0.psig)'
'HPC1 isolated on steam line break AP Hi Drywell fic ;r drain sump Hi alarms fin i
ACTIONS EXPECTED '
- 1. if path 4 is still'being executed the Shift: foreman should switch-to Path 5 >
- 2. Evaluate PEP for emergency action levels.
Alert s,hould be declared oncsmall break LOCA > 50 gpm
- 3. Evaluate 01-51 reportability Four-ho'.tr report on llPC1 isolation I
?
FOR CONTROLLER USE ONLY ,j i h a I i MSC/90-0011 i e
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, :- N -.r CP&L.
' EXERCISE' MESSAGE / DRILL CARDJ. U-l' Plant 1 ,
Message No. 13 g Date 04/3/90,,_ . Time-'1935 'l When suppression pool , l cooling is attempted.*- i
- MESSAGE'FOR: ' Control Operator'
[.
. . . ?!
1 .FROMt. CONTROLLER > 4 4 MESSAGE /SINULATED PLANT CONDITIONS , A0 reports a 20'gpm gasketEleaN on E11-F002B ] ! i d
.l
'I ACTIONS EXPECTED: ,
,1 Isolate B loop i!HR: servicu1 water and attempt to . limit salt water; intrusion'into Radwaste systems.
- 1
- t Place A loop RHR in suppression pool cooling. . . .
t d 4 t FOR CONTROLLER USE ONLY .
'I 6
a i
-. i MSC/90-0011 i
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- CP&L LEXERCISE' MESSAGE / DRILL CARD U1 Plant-Message lNo., 15 Date 04/3/90 Time
- 2000
. Contingency-
- MESSAGE FOR: Shift. Operating' Supervisor' FROM- CONTROLLER MESSAGE / SIMULATED. PLANT CONDITIONS: "THIS IS AN EXERCISE MESSAGE"
-AnAlertshould-bedeclaredbasedonasmall'b'thakLOCAwithprimary' system. leakage greater than 50 gpm..
m ....
- ACTIONS EXPECTED:
~~
FOR CONTROLLER USE ONLY To be used only with app.roval of exercise lead controller, MSC/90-0011-h
k i 3 s
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CP&L EXERCISE MESSAGE / DRILL' CARD' U '
. Plant..
- Me'ssage No. ' 15 LDate 64/3/90 Times 2015
' MESSAGE FOR: Control Room FROMi CONTROLLER ~
t --, + l .NESSAGE / SIMULATED-PLANT CONDITIONS: - THIS-IS AN EXERCISE!HESSAGE. The victim has'been' decontaminated andfall contaminated materials.have. been returned'to the site. i i
-i ACTIONS EXPECTED: I
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4, / L FOR CONTROLLER USE ONLY , a L-L- : ll I ll
- k MSC/90-0011 s
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- . .. < ' EXERCISE MESSAGE / DRILL CARD U.1' Plant
- Message No. 16 - - Date 04/3/90 1*Jime 2052?
- HESSAGE FOR' -Con' trol! Operator '
7 i'
- FRON - CONTROLLER . 9i m
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.. it HESSAGE/ SIMULATED PLANT CONDITIONSi., ,
Suppression.chambhr, pressure has exceeded.13.psig' .f ,
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ACTIONS EXPECTED: Initiate drywell sprays ,
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FOR CONTROLLER USE ONLY l
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'" 1 EXERCISE-MESSAGE / DRILL CARD U ~
Plant-1
-Message No. 17 Dato 04/3/90 .
Time c2055 < i When drywell_ sprays: are initiated, q MESSAGE FOR: Control Operator _ , FRDMs CONTROLLER MESSAGE / SIMULATED PLANT CONDITIONS - "THIS IS AN EXERCISE MESSAGE" , The - following' alarms have been received. UA-03 Window 2-7' 3 A-02 Window 6-7 1 UA-26_ Window 3 : l i i l
.i ACTIONS EXPECTED: Enter annunciator. procedure and dispatch personnel to ,
investigate cause. i 1,
-t FOR CONTROLLER USE ONLY UA-03 Window 2-7 " AREA RX BLDG HIGH" A-02. Window 6-7 " STEAM LEAK DET A TEMP.HIGH UA-26 Window 3-3 " FIRE REACTOR NO.-1 EL 17 NE MSC/90-0011 f-4
- [ 1 l
a, i l CP&L' EXERCISE HESSAGE/ DRILL CARD , U-1 Plant , (.
- Message No. is Date 04/3/90 _.. '. Time 2057 --
when requested ; HESSAGE FOR: Control Operator - <
.l 1.
TRON: CONTROLLER ' MESSAGE / SIMULATED PLANT. CONDITIONS: f' =NRHR ateam Isak AT $5'T '
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5, 5
, i ACTIONS EXPECTED: -Enter E0P-03 SCCP' 't Restart Reactor Building HVAC per E0P-01,SEP t;
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- FOR CONTROLLER USE ONLY i .?
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EXERCISE MESSAGE / DRILL CARD. :U it'
, Plant: cv f
i ' Message,No.
'I9 Date' 04/3/90 . Time' 2100-
- j. ,
i Fi-- ; i, 7> l MESSAGE FORT , Auxiliary Operator i FROM - CONTROLLEk-MESSAGE / SIMULATED PLANT CONDITIONS: ' THIS 18 AN EXERCISE MESSAGE"'- Tempinbuilding'1h'above. normal.. ' Larae amount of' steam is coming from NRHR pipe chase'and stairwell. , t ( ACTIONS-EXPECTED a Notify SOS. t; - r t FOR CONTROLLER USE ONLY a ( MSC/90-0011 i
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. CP&L -
EXERCISE MESSAGE /DWILL CARD-. U 1 -- Plant .. . Message No.. 20 Date_ 04/3/90' . Time' 2100
.i
-NESSAGE FOR: Control' Operator:
< -a ir -FRON: CONTROLLER MESSAGE /SIHULATED PLANT CONDITIONS:-
High drywell pressure alarms cleared. . Drywell- pressure at: 1..!,' ps'ig s.nd'. no longer. increasing.- '
\.. !
l t i i ACTIONS EXPECTED:
- t Should suspect loss of primary containment site emergency.should.be-declared when this is recognized.
d m TOR CONTROLLER USE ONLY
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;i EXERCISE MESSAGE / DRILL CARD U-11 Plant
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, Mer c e r,e ' Noi ..215 6Date- 04/3/90I .
tTime~ 4 2111 n > > i f, . m,
,, _ . .MES.*J., f0R:7 : Control Operatora s- ,
-FROM: CONTROLLER-4 , , :- ;; ,
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' MESSAGE / SIMULATED PLANT CONDITIONS: ,
~ . . , .
- CAcaV16findicates3 dual 1ndication whenTi solating'CAC-X 20Ah R
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N I.Y . 1 LIf not alrea'dy? declared; declareLsite.: emergency;;andl '
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JACTIONS EXPECTED: - D
= evacuate sitei < ~
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Plant: i
~
Message No.:. 22 -Date? 0S/3/90b ' Time s 2130- i I, r '
. ;- < Contingency:
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- MESSAGE FORis = Shift. Operating, Supervisor 4 , >
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FROM:- CONTROLLER [ L MESSAGE / SIMULATED _ PLANT' CONDITIONS: "THIS IS AN> EXERCISE MESSAGE"'* m A Sit'e Emergency-shouldabsi declared l b'asedi on 'a: loss" of;.two-out vof-three1-fission product barriers. , j n ,
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i i 5 i 9 i-2 ACTIONS EXPECTED: 4 ' r
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FOR CONTROLLER USE ONLY 'l l To be used only with approval: of exercise lead: controller. ,
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- s MSC/90-0011 I
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' , l EXERCISE-MESSAGE / DRILL ~ CARD; U-1 0-4
...P lant ' .:
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-MG5ag4)c. 23 ;Date 04/3/90 '
Timei 2212 l y;., :3 '
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"MEGSAGE FORT.- Control Op974 tor l
..'FROM: CONTROLLER:
1MESShGE/ SIMULATED PLANT CONDITIONSh '?THIS IS' AN! EXERCISE' MESSAGE" . a #
,- :The?following alarms have been received:, <
s, A-03,. Window 1-5
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l A-03, Window 2-5=
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;a ACTIONS EXPECTED: , (
Reference annunciator' procedures. ,
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*. s FOR CON' TROLLER USE ONLY .
A-03', Window 1-5 "RCIC TURB CPLG END BRG TEMP-HI" A-03, Window 2-5 "RCIC TURB GOV'END BRG TEMP HI" - 1 MSC/90-0011 , i
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CP&Ls . j t ; EXERCISE-MESSAGE / DRILL CARD-. U-11 1 1 Plantx 1 _i q? tje s s age < No ,' - ' 2 4~ 'Date 04/3/90 iTirne ?2'215 u l
, - 4 i
ControliOperatorL
- MESSAGE FOR:. '
f.: E FR'OM: CONTROLLER - l. MESSAGE /SIMULATEDiPLANT CONDITIONS: "THISlIS'ANIEXERCISE MESSAGE"4 i,E i 'I
-You have just received.
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ft , RCIC Speediand. Flow-JIndicate .-0: , F u)
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, > :t ACTIONS EXPECTED:
tFollowE0P-01-EPPfordecreasing_ water (level ( , if zy P 3 i
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FOR CONTROLLER USE ONLY
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J A-03, Window 3-4 "RCIC PUMP DISCH FLOW LO" it
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. EXERCISE flESSAGE/ DRILL CARD.. U _
' Plant
=
- 25 'pate '04/3/904
?!es s age ' Nd .- :;T.tme i
. 2230--'
-ADS. valves-
+
!are) attempted ,
7'i E!:- :-t!ESSAGE;FORb JControl;0peratorj ' b .-
- FR0t!: CONTROLLER:. ; :1; iflESSAGE/ sit!ULATED PLANT CONDITIONS:. ,,
No SRV's can: be. opened withi the- control: switch'.t ' r
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1 1 4 x
-U ACTIONS EXPECTED:
Enter E0P-01-AEOP,(" Alternate emergench depres,surization andfattemp't .to :
- depressurize the reactor'.through:the. main steam: lines.:-
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'l FOR CONTROLLER USE ONLY 1
O f t!SC/90-0011 .. H
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' EXERCISE" MESSAGE / DRILL CARD ' :"
,,. 1.
- Plant
,, .m Message-No. -26 > Timer 2235
- Date _04/3/90' .
~{
JwhenMSIV are-- J;
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. ~ attempted ' ' '
a:
/Controlbperator MESSAGE .FOR:
o> l 4 FROM: CONTROLLER: E
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.R, i MESSAGE / SIMULATED: PLANT. CONDITIONS::
> 1i
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> in;,1 Group:1. isolation reset butlinboard MSIV's will not,open!-and have no; .
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indicating lights. 4 M t
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- ACTIONS: EXPECTED:. .
s ..a , s Continue-attempts to.depressurize the reactor;2generallemergency/should .]
.have been declared: by this: point.- Ms 5
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N o r f FOR CONTROLLER USE ONLY - t t f MSC/90-0011 , m J E
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-EXERCISE MESSAGE / DRILL CARD U-l
-Plant:.
l
, 3 Message-- No. '
~
27: _Date':04/3/90-
- Titoe: =:2300 ,
J s
' > Contingency- l
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MESSAGE FOR:s Shift Operating; Supervisor.. -? r m - FROM: -' CONTROLLER" if 1
- MESSAGE / SIMULATED PLANT CONDITIONS:- ~THIS IS! AN EXERCISE MESSAGE" JA General-Emergency;shduld be. declared: based:otraT16ss:6fSall-three:
- fission product barriers. < , .-.; 1 1
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ACTIONS EXPECTED: < !
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- FOR CONTROLLER USE ONLY To be used only with approval of exercise lead controller. Y
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MSC/90-0011 l
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' Carolina Power 6.Lig t y Brunswick Steam Electric Plant
]
Exercise Message / Drill Card. , Date: ' April.3rd,1990 Mission No: Mission: Evaluate the validity of the-HPCI. isolation.
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Background:
At 19:30 Operations received' annunciator A 01 2-4, HPCI STEAM LINE BREAK dp High. The_-inboard isolation valve,- E41-F002, closed. Annunciator'HPCI ISOL TRIP SIC-BT , INITIATED (A 01 4 5) and HPCI TUR TRIP SOL ENER (A-01 4 1) _ were in alarm. Indication: The trip unit E41-PDTM N005 1, .on panel CBJU-64', shows
-300" H2O dp and relaysLE41A K43, E41A K36, E41A K44,-on ~
panel H12-P618 and E41A K12, on panel,H12-P620-are energized. Current-in.the' transmitter loop is- ' approximately 4-Ha and-transmitter appears to_ function ' normally. ' Expected Actions: Investigata and inform OSC that. it. appears to be a validi reverse dp-signal coming from E41 PDT-N005.
^
Drawing / Procedure: FP 50039, D-2523, 1MST-HPCI21R Time Line Data: There is no_ repair within the time line-of this scenario. If.they decide to use HPCI by overriding the' isolation signal, HPCI will remain isolated due to thermal binding: , l of the already-closed E41 F002,'as a contingency. ' i Simulation: Only actions that would interfere with plant _ operations or '
' expenditure of' funds should be-simulated. :All other. T actions such as gathering prints; _ tools, test equipment, making surveys, team briefings, etc, should be performed.
Any questions should be referred to' the Lead' Controller. i.
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l
._ . - . a
5 t i Carolina Power & Light [ s; Brunswick Steam Electric Plant Exercise Message / Drill Card , r !
- Date:' April 3rd,1990~ Mission No: -!
Mission:- Repair-leak on'the'RHR heat exchange' outlet valve,'-
- 1. Ell-F002B, ->
Backgroundi An Auxiliary. Operator had, reported a 20. GPM ~ gasket -leak on t <
.1-E11-F002B at 19:35. This1occured shortly afterc suppression pool cooling was attempted. l "Theheatexchangercareahad-beenwettedwithLsaltwater
~ ~
Indications: Espewing'from the' gasket, until operations isolated the'B loop RHR service water.' ;The lower. elevation emergency' + i
-lighting unit was also wetted, but seemst functional. - The southern most gasket;of'l E11-F002B-(see attached figure)-
is the apparent cause. The mock-up will provide , additionalLindications. Expected Actions: Request a clearance (e~g,;MCC 1XB compartment l'-DN9 off, heat exchanger drained,11-E11 F014B closed) : for: both the i hydraulic and electrical hazards. Replace the damaged. gasket,;using 0CM VBF506 as_a guide'
~
References:
D-25037, FP-6789, LL-92037 she 97, 0CM-VBF504' 4 Time Line Data: Simulated clearance request will.take approximately 20' minutes. Actual gasket installation will' determine repair l time. The clearance removal will: take an, additional L15' ! minutes. Simulation: Only actions that would interfere with plant; operations or ', expenditure of significant: funds should be. simulated,- including clearance request'ard removal. .All'other: actions such as gathering prints,- tools, team briefings, and valve repair should be performed. -There will be.a i butterfly valve mockup staged, for purposes of exercising a OSC team under a simulated hands on mission. Any . questions should be referred to the Lead Controller. k 5 t
, . _ , ,, -4
.. .,. ..- . - . . . ~ . - -. . -
~
l l I Mission' i
. .3 l
l-E11-F002B . REPAIR j l I-i
,,_ , g r', Il - ( -WWE FCR:
WOTOR R'MfML ? I i
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e DIA Twill 3
/ 3 H HOLES , .l Outboard Gasket / - -
- c -l J
l Blew out here i}*.m a t[Mmer 4.cn nnem asa wot i A m. m W 4 t:
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-Carolina' Power & Light-Brunswick Steam Electric Plant-Exercise Message / Drill Card '
1 4 Date: April 3rd,1990 : Mission No: i r.ission: Assist in' evaluating cause of alarms in north RHR.
Background:
Shortly after using containment spray, at: around 20:55.
' Operations received UA 03 2-7, AREA RAD RX HICH, A-02 6-7. STEAM LEAK A TEMP HIGH, and-.UA-26 3-3, FIRE REACTOR NO. l'EL 17 NE. -The problem is actually )
associated with a broken = vacuum breaker 1-CAC X20A, .in the i overhead of North RHR. . Indication: The -17 North RHR' area temperature.is almost unbearable, i High radiation readings will.be provided._ Upon-investigation it is~ noticed that.the steam appears to'be' emanating from the northern most 20"l vacuum breaker.
'.(1-CAC X20A).
' Expected' Actions: Possibly no actions upon' initial; investigation. Manual' attempts to snatch the breaker closed may be attempted
'(simulated) and if so they would. meet with only limited success,. minimizing the size of the containment breach.
Temperature readingsiare too high to afford the time it. . would take for repair (a broke hinge pin) and establishing '. a good seal. Drawing / Procedure: N/A Time Line Data: The .0SC Mission Leader needs to report steam coming; from vacuum breaker (1-CAC-X20A), byfaround 21:10, to provide the input for recognition of the prima y containment failure. Simulation: Only acrtons that would interfere with plant operations or expuGiture of funds should'be simulated. 'All other actions such as gathering prines, making surveys, team J briefings, e.~.c. should be performed. Any questions should be referred to the Lead Controller.
c Carolina Power & Light Brunswick Steam Electric Plant Exercise Messag'/ e Drill Card Date: April 3rd,1990' Mission.No: Mission: Repair of leaking vacuum breaker,'l-CAC X20A.'
Background:
See' initial north RHR area investigations for background. - Indication: The -17 North RHR area temperature is still almost unbearable and high radiation-readings will- be provided. The 20" vacuum breaker (1 CAC-X204);is; stuck open-and:the hinge pin is broke. 1f close_ inspection is'performedh it can be seen that X20A is hung up on the inboard air operated valva, 1-CAC.V16 (see attached), Expected-Actions: Manual' attempts to snatch the breaker closed may be. . _ attempted (simulated) -and if so,; they would meet with onlyn i limited success,1 minimizing'the size of the. containment -_ ! breach. Temperature readings are'still to high to afford-the time it'would take for repair-(a broke hinBe pin) and ;
'i establishing'a good seal. Attempts at bracing or securing a flange or obstruction over'the opening will also meet i with only. limited success, minimizing the size of the i containment breach. 7 Drawing / Procedure: FP 6597, D 25015, IMST CAC22R',.1MST-CAC23R Time Line Data: Repair attempts should not establish leak tight b containment. The containment breach should' remain throughout the rest of tho scenario. The primary contingency is that their efforts meet withronly limited success, minimizing the size of the containment breach l (e.g. Hinge pin pieces are stuck between body and disk of.
V16, if they free up X20A). q l Simulation: Only actions that would interfere with plant operations'or expenditure of funds should be simulated. 'All other actions such as gathering prints, gathering tools, getting test equipment, making surveys, team briefings, etc. should be performed. Any questions should be referred to the Lead Controller. , 4
^
, .f
-l
Mission - Primary Containment Failure
,d' I
s-1-CAC-V16 J1 l Broken . hinge pin.-
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3~ i -..-., ,
) :n 1 1-CAC-X20A o 1
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i Carolina Power & Light- l Brunswick Steam Electric Plant [ Exercise Message / Drill' Card' , Date: April 3rd,1990- Mission No: Mission: Trouble-shoot RCIC failure.
Background:
RCIC had been running cince, the Group l' Isolation. It developed an oil-coolar tube leak which has: allowed' cooling water.into;the. oil system.- Continued running without proper lubrication' caused the- bearing surfaces to overheati metal: to expand, and eventually ~ the turbine lugs to ' the point - of seizing. 0perations' received RCIC PUMP DISCHARGE LOW FLOV, A-03.3-4, TURBINE COUPLING END BEARING TEMP HIGH, A-03-1 5, and TURBINE GOVERNOR END BEARING' TEMP t HIGH, A 03 2-5. .. Indication: The turbine bearing surfaces are-overly hot to the touch, on_both governor and' coupling bearings. _ The_ oil-inspection sight glasses show a milky light brown oil.(see attached). Expected Actions: 11e turbine bearings are ruined. ' Major = turbine overhaul is required and the . time line wil1 ~ not afford these repairs. All attempts to_ roll-the turbine will' fail. Drawing / Procedure: FP-5245, D 25029, FP-5446-Time Line Data: There is no resolution of this fault within the time line-of the scenario.
- Simulation
- Only actions that'would interfere ~with plant operatidns or l
expenditure of funds should_be simulated, All other. actions such as gathering prints, ' tools, test' equipment,- making surveys, team briefings, etc._should be' performed. l Any questions should be referred to the Lead controller. ; l l l l l 4
. Mission No. .
TROUBLE SHOOT RCIC FAILURE
- RCIC TURBINE DRIVEN PUMP l-OIL C00lIR = .,
Milk 0' . . '
* -i:
' ~ -
! l a--
) -
s/ . V
~
ur r m i 3 O'
,,l W
_ y ilky Oil -
- r 4
I ! T( L c attb._ C4 s.. _z n m o t
- HiCEP l
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J Carolina Power & Light' [ Brunswick Steam' Electric Plant. Exercise Message / Drill Card j Date: April 3rd,1990 Mission No: ! Mission: Trouble shoot. failure of SRVs to open. f
Background:
-. Operations made an attempt to use-thetADS valves at 22:30,-
to gain use of low. pressure systems. The valves failed to ; open. The actual cause is hypothesized as a common mode
~~
failure of the 0 ring seals,. causing: solenoid valve . sticking on all actuated valves, due_to over heating in- , containment, j Indication: The tail pipe: temperature is only elevated-due to; containment. warming associated with the HPCI steam leak. , The valve sonic detection position indication system (both on panel XU 73 and H12-P601) shows no. valves have lifted,- with all green lights for;B21-F013s on H12-P601. :The 4 solenoid voltage'and pneumatic. supply to the valves appears ncrmal. Expected Actions: Investigate the potential failure. Check non-interruptible instrument air'(reference:~D-73068 and-D 70007). . check DC voltage for solenoid, and validate control switch. functions (reference: FP-5887). Drawing / Procedure: FP-5887, D-73068, D 70007 ; Time Line Data: Repairs require drywell access,anc therefore can not be > performed within this scenarios time line. ' Simulation: Only actions that would interfere with plant operations or expenditure of funds should be simulated. A11 other actions such as gathering prints, tools,' test equipment, making surveys,. team briefings,- etc. 'should be performed. Any questions should be referred to the Lead Controller.
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Carolina Power'& Light Brunswick Steam-Electric Plant j Exercise Message / Drill Card- _l Date: April 3rd,1990 Mission No: Mission: Trouble' shoot the MSIV fatiure to open.
Background:
Operations entered E0P-01 AEDP- at around 22: 30,' but_ MSIVs - , did not open - The problem is_actually associated with the - .( PICS jumpers of the EOP causing an attempt to energize , circuits with electrical faults, thereby. blowing fuses 4 A71B F10A and A71B F12A. .The fault is proposedly faulty-
~
solenoid valve gasket installations'on 1-B21-F0220, which~ j ' allowed intrusion of. containment spray'and condensate to the solenoid valve coils (both AC and DC). s Indication: ~ Relays A71B K7A, B, C, D on panels H12 P609,sP611--are .i, energized but white lights and solenoid LEDs on panel. H12-P623, are not on. Also, the. red and green position-indications as well'as.the half group'one white: lights on. RTCB panel H12 P601, are not.on..The inboard relays + A71B K13, K15, K21 and K23 in panel H12 P622 and P623 are also de-energized. The Fuses, F10A and F12A in-panel-H12 P622 locations AA Fil and AA F13 respectivelyi_would show an open circuit if tested. Expected Actions: Cather prints and test equipment'(DVM) Land trouble. shoot. The circuit indications should show no voltage on any of the attached drawings inboard isolation valve circuits and low resistance on the AC and DC solenoids _' wiring for F022C. Fuse-replacements could hypothetically fix the-problem that prevents B21-F022A, B, and D from opening,' if its in keeping with the time line (see below). otherwise, wire lifts to isolate F022C defects or using the control switch A71B-SIC to isolate the defects, along with fuse replacement should work. Drawing / Procedure: FP 55109, FP-50180, FP-50477
- Time Line Data: Because the fuel damage is _ developing in conjunction with -
this failure, repairs should not achieve success. prior to 23:30. Contingencies to string out the failure should include, needing higher amp rating fuses (5 amps normally), needing circuit isolation on F022C, or getting a bad fuse out of stock, Neither an AC or a DC solenoid of any inboard valve should be allowed tc energize before the assigned time. If fuses are bypassed, the circuit-breakers open to retain the time line.
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Date: April 3rd,1990 Mission No: Mission: Trouble shoot the-MSIV failure to open (continued).
' Simulation: Only actions that_would-interfere with' plant operations or-
= expenditure of funds should be. simulated.-
NOTE Permission from the actual operating shift should be obtained prior to opening panels for; purpose of , 1 simulated (look only) identification of the-fault.. All other actions such as gathering prints, tools, test equipment, making surveys, team briefings,Jetc._should be performed. Any questions should be referred to the Lead Contrc11er, j i
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-BRUNSWICK EMERGENCY EXERCISE.
. APRIL 3. 1990'
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I i i 1 NOTE: Calls to be used as a guide'for exercise conto 11ers to use in placing calls to Rumor Control personnel. 3 l I e
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_. (Situations Based On Press Releases) ' '
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Hi,- I have just heard an ambulance go by my house twice'.. My neighbor said that.they said something on the; , radio about an accident at the_ nuclear plant. . : L !, Can you tell- me if there is. _something wrong at the i nuclear plant? W
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Hey, can youitell me .what a " cold sh'utdown" .is?: They just said on the radio that because of the accident '
' at the nuclear. plant that Unit 1:is in a cold shutdown.-
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i Hey, I just heard on 'the radio that-due to a loss- of 3 j
'" shutdown cooling". for the. Unit I reactor at' the nuclear plant that they were declaring an alert. . What does .that - '
mean? Is the plant about to' have a meltdown? ~ 1
' Hello,lI'm. George Settle,ithey' just told about the -
4 nuclear plant over the radio. . They keep talking about i a reactor - what-is a reactor? What does " control: rods"' have to do with it? ' Well, if the'rametor gets too hot what
- is: going to keep the. plant from melting or burning,oe -
)
whatever it does? "' i Hey, I just heard on .tv'about- the problem at the-- nuclear plant at Southport. Aren't there two reactors at y that plant? If one of' the reactors -gets too hot like i they claim is happening right now. whatiist going to happen with the other reactor?a 1 They said something about cooling the containment - what la that - is it the same. thing as the reactor? -- 1 i
' Hello, they just reported'on tv that things at 'the {
' nuclear plant at Southport have' gotten. worse. and that. ' the plant is about to melt down. They said'something . l about venting the containment. What 'are they.goingLto
- vent that is radioactive? They said that they were going i i- to send monitoring teams into the field < what are they
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going to do - will they be looking for material to pick up? , l i-1 wish they would be more specific about what is -; happening over there. 1 i 2 5 1
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- Hey, I.have just heard ~ that the same thing has . I happened at that nuclear plant in Brunswick County as; happened in: Russia. Why haven't they evacuated the county?. You know they didn't tell the Russian people about the situation'and many of them died because they
- didn't know to leave. Why doesn't CPkL tell the truth sol that peopb will have time.to get out of there? -
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f Telephone. Message Hi,- I'm secretary 'in _the elementary school 'in Southport.- ~One of our parents- has called to sayz that I you have asked people to take ' shelter. I want to know, when~ you are going to evacuate this area. I - think = l -- parents are going to come to get their. children now and?- _I want to be prepared for what might come later. l Hello, I've been listening: to _the radio arid- I hear.- ' l_ that there is something wrong at that nuclear plant. I'm scared. because I'm the -- onlym one ~ at home ; inD my . neighborhood. If I le' ave now, where should I go? i
. Hello, I'm Joe Smith and my friend is manning one- 1 of the phones for the State in that center you are in. Will ^
you please let me' talk with him? '
, Hello, I'm Harry Richardson and-I'm callin'g:from Nashville, Tennessee.' - I have1just heard on the news. .i t
about the accident at the nuclear plant.: That's close.to ' ' Long Beach, isn't it? , Well my family is vacationing there
- my. wife and' two children and I wonder if you have a way to notify them about what-is happening? I've been -- i trying to call them, but. I can't get an: answer. I know that they must be on -the beach and they have no idea that there has been this accident.. If i
address _ will you" have~ someone gor there ovelI give and;tellyou their ; them to leave and then ask them' to call me as soon as j l they can? I'll be glad to. pay.you for your trouble. H I i ,
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Hello, I'm Marion Strock. I'm a county commissioner -
-and I-thought I would call this number to see what you .
all were telling . people about that . plant. I've been
. listening. to the news but it sounds like they just keep L
repeating' the same . thing over and over. What is s happening at the plant right now? .Are you all leveling with the people? How soon do you think it's going to be : before you evacuate all this area? People are calling here 1 and I don't know what to tell them. I think I.should just leave so I won't get all these calls. , i , 7 L ;
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; Hi,-- I'm Doris McGee and' I'm _ calling for some ;
Information. I work in Wilmington and live on Oak u Island. .I have two children in school; Will you tell me where they will evacuate the Southport Primary School to - ' l: if they evacuate the area? I got'one of those calendars i : but it s at home and I can't remember where they told mei l l < the children would be.- '
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[h I'm insd"asI can' be abSut this 'here'accfdent' at f i. that nuclear plant. I told the folks when they put .that' '!
, plant here inat something like this was going.to happen..
- Everything I've worked for all my life is rightfhere in.
. this area. - If something happens to it and I-can't live - >
here no longer, I want.you to know that I'm going to sue-CP&L. -You can tell Sherwood Smith that I'm going to get i all my neighbors:to sue too.1It ain't fair for people to ' lose their homes and~everything they've got'so that they: , can put these nuclear plants hem, c-_What is your name? - y Do you: work for CP&L7 Well . you will hear from me. if' " l this here thing gets worse. i j Hey, I'm Madge White and I live in Southport. I'm
- a senior citizen and I-keep my great grandchild for her'- ,
mother to work. I don't-have a car,and I wonder if you ( 1 can tell me how we can get'a ride out of Southport if we are told to evacuate? E ' I can walk.but I can't walk very far and carry the little - ' girl. . If nothing happens before 5:00 I' will' have a ride - 1 but I don't know what to do inwe need to Lleave this morning. k n i-f 4 -i
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5 i 8 Hello, I'm Carl Cheek'I have just heard the news- l about that plant. -I'dlnever thought much about.'it 'but,. ! now that something has! happened,LI want you to know that I don't like the way you all have got this evacuation '_ set up. I've- got three. chldren -'and - they are' all :in . a different schools and they- will be taken to; different 1 shelters. How do you think a family is golng .to get t together when you've got everybody scattered'about. It'
- seems to me that you ought to get families together - I've-decided that:I'm going to' get my children out of. school right now for I don't;want to. have to run allt over' New.
Hanover County to find them. I hope thisLthing never happens again but if it does I want you all-to handle it- ; different.
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. l Hey, I'm . Pauline Scott ' and < I am vacationing :at Wrightsville' Beach and I lived close to Three Mile Island' when they had that. accident. I-thought somebodyfought ;
to know= that they evacuated 7 pregnant women and ; children around that plant when they had that accident. ~ I haven't heard:any. announcements on the-radio about -
-that and I think 'someone ought to announce that women ._3 and children ought: to leave . this area.= I called the.
Wilmington station and toldUthem: that : I thought . they- s
- ought to announce it and they toldf me that they made - -
4 ~ such announcements when the state told them too. : Well . ;
- it was the governor, Governor Thornhill, who told them -
i to leave in Pennsylvania, and'I think somebody ought to , talk to Governor Martin' about it.- They 'shouldn't wait ~ ! until it's ~ tooilate. There could:be lots of babies born" , with deformities and-children'can have leukemia. I think ' : it's serious and I hope that you will do'something about-letting the right people know about it. I think I've done everything I can.do! d [ . i 1 - b, ,i
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+: Hello, I'm Deputy. Sheriff Laurence Keen.; I hav'e -
' the' radio on and I've been riding around the county to >
see what people are .doing. :I' want you to know that people are really scared.i I don't know whether there is u
- going to be anybody left in~ the county. to. evacuate even '
if there should' be 'the need. - Traffic is bumper- to bumper and- people 1have got; their cars loaded down! People don't want. to talk'.with you about : the situation, ; i they just want-you to help them find a ride if they don't -( have some kind of transportation. Tell.whoever is putting : out those press releases to remind the people again how-they can get rides'. : Well, you~all better not stay.ther too.
.long or you'll need: help.'
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-Hi, I'm calling from Bald' Head. When they tellLus- 1 to evacuate. we're supposed .to go get on the Coast - 1 Guard ship. Do you know. where they will.take us?L The' evacuation shelters are inland and I don't know how we, can get to them..
' Hello, I've just heard lfrom' my; neighbor that' the Governor is sending the national guard to; protect our j homes in case we have to, evacuate. Doesn't.that sound j strange toJ you?- - If we - have c to leave i becausec of 1 radiation, how can the national . guard stay here? l 1
. Hi, can you tell me if everything in my houseLwill l be radioactive when I' get back from; the evacuation shelter? My son works at.the nuclear plant and-I have heard him tell! about fkeeping people Jwho ' are j
4- contaminated. ' They. wash them or something. Will all of 1 my plants be dead - what about my' garden,'can I eat.the - green beans? It probably won't hurt the potatoes'since-they are underground will it?- '! Hello, I'm Clarence Todd. I'm the administrator ofL 4 the hospital. Do you have a way to ask people to not call '1 our office to find out what we are going to do with't_he l patients in case we need to evacuate the area? Assure. ; them that we . will seee that the - patients are' taken = to l other hospitals. The same thing is probably true with a the nursing homes too - I wish people would stop' calling l us - we will do our job! > 1
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. Hello, I'm Karen Tate.y INe just gotten home fmra school and I'm all alone. . I don't have any friends i.cw *
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by and my mother won't get home from work until 5:00 . ' I'm 11stening to the radioj and I heard .them give;this [ number. That's the reason why-I called you. . I'm scared :- ' and'needed to talk to someone. What should I dot: 1 i i 7 4
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.+. . Hi, -I'm Marshall ~ Scott .with the New York ~ Times. $
. I hear you ' are at: the plant 'that has. hadl the nuclear:
~
emergency. I want to ask you some questions.; t
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1 L Hello, I'm Maureen Walker. My husband works in - ,
- - the. control room. at the plant.c Can you tell me if
- they ,
have evacuateddhe plant? Do you think that they will.
-t let all who wantLto, leave the plant site? ' ! have'the car; today and;I will come to get'him if I know when' hefcan? .
leave. . I called'the plant and they won't even answer the' , 4 telephone. What is happening at the plant'nowff Do you > think things are getting worse? {
.. . Hi, I'm John' Monroe. I'm getting alot of.' questions; , r
< from people inithe Eastern Division and I'm just calling: '* to see what information you are giving outh: Should.I put 1 a recording on my. telephone: referring L calls eto ithis >
- number? Do you think:the situation is improving?>.
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Hi, I'm Ed Lowe and-I live at Wrightsville Beach. ! I've just heard on the news that Carolina Beach has been ! evacuated because the wind is blowing from sne i southwest and bringing the gases being vented from the i plant over the beach.. What I want to know is why i Wrightsville Beach hasn't been evacuated. Whatever comes overBeach Wrightsville Carolina tool Beach in bound to come over ; i i Hello, I'm calling from Raleigh. I do a lot of fishing at Southport. Am I going to be able to eat the e fish and ersbs I get-in that area if that nuclear plant j spews out all that radiation?. It's a shame that this kind ' of thing has to happen for it sum poisons everything. ; i
. Hi, I'm' Chad Warwick and. . I'm calling ~ from I Brevard, North Carolina. My son and daughter are at i the Baptist Assembly at Caswell with a group of young i people from our church. We have faith that nothing is' !
going to happen to our children but we want to know how ' bad the situation is there. Are people leaving the area - or is there so much congestion that nobody can gn -- nnywhere? ; Hi, I wonder if you can tell me if I should give our kida a shower since they have been at the school that l l has been evacuated. Should I throw their clothes away l since they are contaminated? , Heuo, I've heard them telling people over the radio to take shelter; What I want to know is:if there is something falling that will ruin everything that we have. !
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Hello, I've called before and you told me to call the county emergency center .if 1 needed trsnsportation. . Well, I called them and they said for me to go out to the highway and wave someone down who was passing by. Well, I went out them and stayed 30 minutes and no one would stop for me. Everyone of them looked like they ; had their car loaded and they just kept going. Do you have some way to help me?
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i Hello, I wonder if you un help me. My husband- ; has been out of town on business and he is supposed to ! get home tonight. Since we have been evacuated I know I he won't know where we are. Will they let him go home ; or will someone stop him and help him find us? i i Hi, I'm Joe Harrington 'and I live in Leland. My { wife works at the Brunswick plant. . She came home this ! i- afternoon and said that we wouldn't have to leave if the ! situation at the plant got worse. Why is that? Hi, I live between Southport and Supply. Can you . tell me what will happen to my garden if they vent the ; plant? I don't guess it will kill everything but will I be able to est it? Do you think the Agriculture Extension. i Department will be able to come out and look at it?'
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Hello, my neighbor just told me that babies will be born with deformities because of this nuclear accident. 'i He said he read it in a magnaine recently. He said thet ! afte.r Chernobyl both animals and humans had more birth .;
- defects. What do you know about that?
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Hello, I get my water from a well on my property. , Will. the water be affected by the telease of the ' radioactive gases in this arest I just heard them talking about how to store food and I'm wondering about the ' i water. , { l Hi, we've been told' to evacuate and I'm wondering if you can tell me if the shelter we're going to'is air-conditioned. I live on Oak Island and we are supposed ' to go to West Brunswick High School. If it's not air-conditioned my mother won't be able to stay there. ; Hello, my aunt just called and said that she heard that if we have to evacuate, that- CP&L has insurance that will pay for our lodging and any expense we have related to this accident at the plant. Can you tell me if J-that is true? e
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l I I e I Hl. my brother who works at the plant just called ! his wife and told her that the the condition at the plant' is getting worse. And they just told on the radio that - the condition is stable. Who should I believe? I've been : calling everyone I know to tell them what my brother said ! and that they better get out of here. l-i i I Heuo, theiy just said on the radio. that Bill Lee, President of Duke Power Company, has :ald .that he i would come to the Brunswick plant to help out like he did when the accident happened at Three Mile Island. ~ Why - is he coming down here - is the situation as bad as it was j - at Three Mile Island? I didn't think that it sounded'so' bad the way they are talking about it on television. ~i n j Hi, I read in a magazine that they give out iodine ; tablets around nuclear power plants when an accident ' occurs. Who is giving them out in my ares? I live at Boiling Springs. t
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_ q Hello,- I'm Jim Cox ' and' I operste a wholesale ' nursery at Supply. 'I've pt n truck load of plants ' 1 enroute to my nursery and I a wondering if I should try to stop the truck before it gets here. If the' plants get . contaminated with Cesium 137 nobody'is going to want to .: buy them. What do you, recommend that I do? : Hello, I wonder if you.would'get them to announce l over the radio and on television that I would be glad to 0 come and get anyone who needs transportation to. an evacuation shelter if they would call me at 846-7543. My name is Charlie Lewis. l
- a Hi, I'm Lynn Moore and I'm here on vacation. I was just listening to my .CB and heard some county !
officials talking about the possibility of evacuating this J area. Can you tell me what is happening at the plant L don't they have it under control? 3 I i b s
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y_ .%, - - - - - SAFETY PARAMETER DISPLAY SYSTEM i s? i UNIT 1 t
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I UNIT O' . f PEP-02.6.21 Attachment 6 ; Page 1 of 1 .! EKRIBIT 2.6.21-6 i SAFETY PARAMETER DISPLAY SYSTEM (UNIT. I _) , i 0,2,erabia Inoperable 8,tandby Running Yes No Isolated ! NA - Not available Time /fOO ; i 1 1 KPCI Flow (apa) .5 ARIA RAD MONIMORS mR/hr 2 Core S? ray A Flow (aps) .5 37 Rs. 8;.da. 20 Jt Airlock :L ! 3 RRR A .rlow (non) 1 Rs. 5;,ds. 50 de Sample ! 4 RCIC Flow (apa) f 38 Station .S~ .~ 5 Core Spray 8 F;,ow (apa) .t 39 Rk. BLc,a. 50 fC Airlock / ' 6 RHP. B Flow (mos) J Rx. 3;,a3. North of Fuel )' 7 SLC Injectina A/ 40 Pool 1__
. 8 CRD Flow (apa) so Between Fuel Fool and ;
9 APRM % t o o */ , 41 Drywell Du,. s a. /. 1 10 Reactor Pressure (psia)- / o o 4- Turbine Bldg. Sample i 11 Reactor Level (in) /fa . 42 Station- ,2 , 12 Main Stack Flow Rate (scia) 70.000 43 SJAE A (aR/hr) 2is Turbine Bldg. Roof Vent ' 44 SJAE 8 (aR/hr) / 9 s- i 13 Flow (sefs) / T. 00 u Am. Bids. Ventilation ' Rx. Bldg. Roof Vent Flow 45 Monitor (aR/hr) .5 14 (scia) ro coo Service Water Rad Monitor l Rx. Bids. Negative Press ' 46 (cos) f/ ^ 15 (inches of water vacuus) ,AT 16 Suppression Pool Level (in) - s.9 OTHER UNIT 17 Drywel;, Pressure (psia) .r Turbine Bldg. Roof Vent 18 S8GT F;,ow A (scia) s 47 Flow (sefa) /fvov , 19 SBGT Flow B (scfa) .5 Turbine. Bldg. Roof , 20 Drywela H,4409 (1 conc.) . v s- 48. Vent Monitor (uCi/sec.) 43s" 21 Drywel;, H 4410 (1 conc.) , y t- I 22 Drywela O! 4409 (1 conc.) 2. P 23 Drywell O' 4410 (% cone.) 1.r l i 24 A0G Systet Flow (sefs) 4o 25 Off-Site Power Available v Main Stack Gas Monitor / y/ 26 (pCi/sec) 'A , a f , Turbine 81dg. Vent Monitor g i l 27 (',ici/sec) 6.C E DitYWELL HIGH RAD MONITOR R/hr l 28 D22-RM-4195 - 30 ft El.- r ' 29 D22-RM-4196 - 57 fe El. r/ 30 D22-RM-4197 - 23 ie El. f-31 D22-RM-4198 - 57 ft El. .r- t , 32 Drywell Temp ("F) to6 33 Suppression Pool Temp ("F) Pr RX. BLDG. ROOF VENT RAD MONITOR t 34 Particulate (cpa) 2.oo , 35 lodine (eps) Aou 36 Noble Gas (cpa) /S o - ' O PEP-02.6.21 Rev. 20 Page 22 of 34 v . - , , . - . - - - - , - ,
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.p UNIT 0 :
PEP-02.6.21 Attachment 6 . Page 1 of 1 EIMIBIT 2.6.21-6 SAFETY PARAMETElt DISPLAY SYSTEM (UNIT ! ) ! l
,0.lerable Inoperable Standby R,unning Yes No Isolated !
NA,-A Not available Tina /7/)~ , 1 RPCI Flow (apa) v3 ou ARIA RAD MONI' 0RS mR/hr ! 2 Ccre Spray A F;,0w (apa) s 37 Rx. B;,da. 20 lt' Airlock .i 3111 A Flow (apu) ( Aic. 3:.dg. 50 dt Sample .- 4 RCIC Flow (apa) 40o 38 Station f !
$ Core S> ray B F ,ow (apa)- .i 39 Rx. B;.da. 50 fe Airlock i 6 RRR B ' low (apa) .c Rx. B;,ds. North of Fuel 7 SLC Injectina u 40 Pool .lL ;
- 8 CRD Flow (apa) >/00 Between Fuel Pool and-
, 9 APRM I o -41 Drywell Dow,.., u. /.
- 10 Reactor Pressure (psia) 900 Turbine Bldg. Sample 11 Reactor Level (in) 17s-- 42 Station .1 12 Main Stack Flow Rate (scia) 74; 000 _4_3 SJAE A (aR/hr) /oo ,
Turbine Bldg. Roof Vent / 44 SJAE B (aR/hr) y s-13 Flow (scfa) 3' /r os o Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flow 45 Monitor (aR/hr) . f~ , 14 (sefs) o Service Water Rad Monitor
- Ax. Blds. Nagative Press 46 (cos) '
f/ 15 (inches of water vacuum) . A f~ l 16 Suppression Pool Level (in) - A-# OTHER UNIT 17 Drywe; , Pressure (psis)
, o,VT Turbina Bldg. Roof Vent 18 SBGT E.ow A (ucfa) 1r e o o 47 Flow (sefs) /f000 19 SBGT Flow B (sefs) 3 opo Turbine Bldg. Roof o :
20 Drywell H, 4409 (% cone.) .vr 48 Vent Monitor (VCi/sec.) 3. 3 &
- 21 Drywell H' 4410 (I conc.) '.vf 22 Drywell O! 4409 (% conc.) 3, f j 23 Drywell O' 4410 (1 conc.) L. 9 24 A0G Systei Flow (scfa) D '
25 Off-Site Power Available V Main Stack Gas Monitor / 26 (uci/sec) 1. O f " ' Turbine Bldg. Vent Monitor 27 (uCi/sec) 4. 0 E i
- DRYWELL HIGH RAD MONITOR R/hr 28 D22-RM-4195 - 30 fe El.
e i I 29 D22-RM-4196 - 57 ft El. 3 30 D22-RM-4197 - 23 fe El. O F 31 D22-RM-4198 - 57 fe El. Y ! 32 Drywell Temp ('F) /aY 33 Suppression Pool Temp ('F) 9f" i RX. BLDG. ROOF VENT RAD ' MONITOR 34 Particulate (cpa) r_f 35 Iodine (cpa) 2-5 36 Noble Gas (cpa) .T.s F , l 0 PEP-02.6.21 Rev. 20 Page 22 of 34 I i
UNIT 0 PEP-02.6.21 Attachment.6 ! Page 1 of 1 ; EXHIBIT 2.6.21-6 ; SAFETY PARAMETER DISPLAY SYSTEM (UNIT /) i l. Of , arable I,noperable S,tandby R,unning Y,es N,o - s J_solated j!A,- Not available Tina / 9.N 1 HPCI Flow (apall 25 AREA RAD MONITORS mR/hr I 2 Core Sirty A F ,ow (apa) 3 37 Rz. 8 ,ta. 20 fe Airlock 2 ?
- 3 RRR A Flow (apu) yceo Rx. 8
- ,og. 50 ft Sample- !
l 4 RCIC Frow (mosll voo 38 Station 15' ! ,- 5 Core Spray B Frow (apa) 39 Rx. B:,on. 50 ft Air ,ock _C / 6 RER B Flow (apa) _c Rx. B; og. North of Puel,
- _7 SLC Injectina N 40 Pool 1
! - 8 CRD Flow (apa) y/co Between Fuel Fool and-9 APRM % o 41 Drywell Co w ,,0ce,/a '[ 10 Reactor Pressure (psia) fro Turbine Bldg. Sample-11 Reactor Level (in) . 42 Station' ifo .1 ;
; 12 Main Steck F ,ow Rate (scra) 74 eaa 43 SJAE A -(aR/hr) - fo l
! Turbine Bldg. Roof Vent ' 44 SJAE B (aR/hr) 7 l 13 Flow (sefs) /S oop Rx. Bldg. Ventilation I
- .Ra. Blds. Roof Vent Flow '
45 Monitor (aR/hr) e f' ,i j 14 (sefs) d . Service Water Rad Monitor . Rx. Bldg. Negative Press 46 (cos) _F/ '! j 15 (inches of water vacuus) , a 5' i 16 Suppression Pool Level (in) -17 OTHER UNIT ! 17 Drywell Pressure (psia) s.o Turbine Bldg. Roof Vent ' i 18 SBGT Flow A (scia) looo 47 Flow (sefs) D'oou : ! 19 SBCT Flow B (sefs) J ooo Turbine Bldg. Roof '. , ! ! 20 Drywell H, 4409 (! conc.) .ef 48 Vent Monitor (uci/sec.) ;;t.?,= l 21 Drywell H" 4410 (% conc.) , yr , l 22 Drywell O! 4409 (% conc.) 1. y ! 23 Drywell O' 4410 (% cone.) s,y 24 A0G Systei Flow (sefs) o i 25 Off-Site Power Available y i ! Main Stack Gas Monitor ' l 26 (uC1/sec) 1. O E , Turbine Bldg. Vent Monitor l ' 27 (uci/sec) 6. O d ' # > DRYVELL HIGH RAD MONITOR R/hr ,. j 28 D22-RM-4195 - 30 fe El. e l 29 D22-RM-4196 - 57 fe El. i
- 30 D22-RM-4197 - 23 f
- El. o g 31 D22-RM-4198 - 57 ft El. o j 32 Drywell Temp ('F) I a. O 33 Suppression Pool Temp ('F) /a/ ,
RX. BLDG. ROOF VENT RAD ; MONITOR 34 Particulate (cpa) 3: J
- 35 Iodine (cpa) rJ 36 Noble Gas (cpa) WJ j
0 PEP-02.6.21 Rev. 20 , Page 22 of 34
I
-UNIT 0.
PEP-02.6.21 Attachment 6 l
? age 1 of 1 !
EXXIBIT 2.6.21-6 -l SAFETY PARAMETER DISPLAY SYSTEM (UNIT /) j 02 erable ,1,noperable Standby R,unning -Yes No Isolated
,NA A - Not available > Time /f W i
1 HPCI Flow (ape) l IJ AREA RAD MONITORS mR/hr 2 Core S1 ray A F:,ow (11,a) J 37 Rs. Blda. 20 fC Airlock 1 1 [ 3 RER A ' low (apn) n r e, Rx. Bldg. 50 fe Sample - ~ 4 RCIC Fiow (aps? roo 38 Station 5' 5 Core Spray B F;,ow (apa) 5 39 Rx. 5:,0m. 50 fe Air l,ock i i 6 RHR B Flow (apa) i 5 Rs. B;og. North of Puoi 7 SLC Iniectina /v 40 Pool ,:L !
, - 8 CRD Flow (apa) proo Between Fuel Pool and =;
9 APRM I o 41 Drywell msac.4 + 10 Reactor Pressure (psia) fro Turbine Bldg. Sample 11 Reactor Level (in) # 9 s- 42 Station ,a j 12 Main Stack Flow Race (sefs) ps ooo 43 SJAE A (mR/hr) j e, Turbine Bldg. Roof Vent '- 44 SJAE B (mR/hr) 7 13 Flow (sefs) /r ao o Rs. Bldg. Ventilation Rx. Bldg. Roof Vent Flow 45 Monitor (aR/hr) ,f 14 (scfa) O . Service Water Rad Monitor Rx. Bldg. Negative Press 46 (cos) S'/
- 15 (inches of water vacuum) .AS 16 Suppression Pool Level 1(in) ~ 2 S- OTHER UNIT 17 Drywell Pressure (psia) L 5- Turbine Bldg. Roof Vent 4
18 SBGT Flow A (scfa) 2ooo 47 Flow (sefs) /f oc o ! 19 S'BGT Flow B (sefs) 3 ..o Turbine Bldg. Roof ,
+
20 Drywell H, 4409 (% conc.) ,vr 48 Vent Monitor-(uCi/sec.) A . 3 ,.e 21 Drvwell H: 4410 (I conc.) . v s-I 22 Drywell 0 4409 (I conc.) 2 . s' 23 Drvwell 0 4410 (% conc.) s.r 24 A0G Syste5 Flow (sefs) a 25 Off-Site Power Available v Main Stack Gas Monitor ' ' 26 (uCi/sec) 1.OE Turbine Bldg. Vent Monitor , 27 (uci/sec) 4. O E DRYWELL HIGH RAD MONITOR R/hr 28 D22-RM-4195 - 30 ft E1. e ' 29 D22-RM-4196 - 57 fe El. :L i 30 D22-RM-4197 - 23 ft El. o 31 D22-RM-4198 - 57 ft El. / 32 Drywell Temp ("F) /yr 33 Suppression Pool Temp ("F) /od RX. BLDG. ROOF VENT RAD MONITOR 34 Particulate (cpa) ff 35 lodine (cos) s5 l 36 Noble Gas (cpa) F5
,l 0 PEP-02.6.21 Rev. 20 Page 22 of 34 6
- - . . . _ . , , , , , , . - . . . , . - _ - . _ . , , , , , - . . . . . . . , _ , ,,--._,%__.....w..,_., , , - , .-
i UNIT 0 t PEP-02.6.21 , Attachment 6 i EERIBIT 2.6.21-6 h SAFETY PARAMETER DISPLAY SYSTEM (UNIT / ) j op,erable Inoperabia, Standby R,unning ' Yes N,o Is,olated f NA - Not available Time 200er l t i KPCI Flow (ape) -r _s AREA RAD MONITORS mR/hr 2 Core Spray A Fiov (apa)- .5 37 Rx. Bida. 20 it Airlock 2 !
~T RER A Flow (apu) // re a Rx. Bids. 50 fa Sample >
4 RCIC Flow (apa) Aco- 38 Station f 5 Core Spray B F:,ow (apa) ,5 39 Rx. - 5:,on. 50 ft Airlock i ; 6 RER R Flow (apa) _r Rx. 5:,0s. North of Fuel. 7 SLC Injectina w 40 Pool A. ; 8 CRD Flow (apa) rise Between Fuel Fool and i _9 APRM % e 41 Drywell' haan 4 i 10 Reactor Pressure (psia) 9qo Turbine Bldg. Sample ; 11 Reactor Level (in) /y( 42 Station .A ' 12 Main Stack Flow Rate (scia) 7c,eev 43 SJAE A (aR/hr) so Turbine Bldg. Roof Vent ' 44 SJAE B (aR/hr) */ 13 Flow (sefs) /f os v Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flow 45 Monitor (aR/hr) , S- r 14 (sefs) O Service Water Rad Monitor I Rx. Bldg. Negative Press 46 (cos)- . S'/ ' 15 (inches of water vacuum) 1 55 ; 16 Suppression Pool Level (in) - 2.1 OTRER UNIT 17 Drywell Pressure (psia) r, o Turbine Bldg. Roof Vent j 18 SBGT Flow A (scfa) _aeco 47 Flow (sefs) /fvoo ' 19 SbGT Flow 5 (scfe) 7ooo Turbine Bldg. Roof ' P# 20 Drvnell H, 4409 (1 conc.) ,yr 48 Vent' Monitor (uci/ cec.) 2.35 [ 21 Drywell H! 4410 (I conc.) . Y >- 22 Drywell 0; 4409 (I cone.) 1.t i 23 Drywell O! 4410 (% cone.) s, . tr i l 24 A0G Syste& Flow (sefs) o l 25 Off-Site Power Ava11abis v Main Stack Gas Monitor / 26 (uci/sec) 1.SE" ' l Turbine Bldg. Vent Monitor 27 (uci/sec) 4, Og ' j ' DRYWELL RIGH RAD MONITOR R/hr l 28 D22-RM-4195 - 30 fe El. e, 29 D22-RM-4196 - 57 fe El. r , i 30 D22-RM-4197 - 23 fe El. o ') 31 D22-RM-4198 - 57 fe El. _P j 32 Drywell Temp ('F) / Ss I 33 Suppression Pool Temp ("F) //o j RK. BLDG. ROOF VENT RAD 1 MONITOR l l 34 Particulate (cpa) 35 lodine (cpa) te ) rs j 36 Noble Gas (cpa) _2: 3 j r i O PEP-02.6.21 Rev. 20 Page 22 of 34 l I
~- . . - . - -. .- - . . - - _ - - - - - - - _ - - _ _ - - _ - - - _ _ _ - - - - . - - -
u UNIT 0 l PEP-02.6.21 ; Attachment 6 ; Page 1 of 1 j , EKHIBIT 2.6.21-6 ;
- SAFETY PARAMETER DISPLAY SYSTEM (UNIT / ) i a j 0,gerable I,noPerable Standby _ Running Yes, No Isolated j i
NA - Not available Time A O /.F ( 1 KPCI Flow (apa) r3 AREA RAD MONITORS mR/hr {' l 2 Core Saray A F;.ow (aps) s 37 Rs. Blds. 20 ft Airlock a j 3 RER A Flow (apu) nro o Rs. Tids. 50 f t Sample t
- 4 RCIC F;,ow (spa? a. ro 38 Stat <.on f* !
! $ Core Spray B F ,ow (apa) J 39 Rs. L,c.a. 50 fe Air l,oca i ;
i 6 RHR B Flow (ups) J Rx. ,l;,s g. North of Juul .{
! 7 SLC Injectina a 40 Fool .:L - ;
j . 8 CRD Flow (apa) > ,e o Between Fuel Fool and l 9 APRM I e- 41 Drywell - D om e cd, 10 Reactor Pressure (psia) 9ao Turbine Bldg. Sample ! 11 Reactor Leve;, (in) /fo 42 Stat $on . llL -: j 12 Main Stack F;,ow Rate (scia) 74 ea o 43 SJAE A (aR/hr) io ; Turbine Blds. Roof Vent 44 SJAE B (aR/hr) 7 ,
- 13 Flow (sefs) /fooo Ra. Bldg. Ventilation -i
! Rx. Bldg. Roof Vent Flow ' 45 Monitor (aR/hr) , f~ l 14 (scia) O Service Water Rad Monitor j Ax. Bldg. Negative Press 46 (cos) f/ ! j 15 (inches of water vacuus) , a s~ .
;. 16 Suppression Pool Level (in) .a. i OTHER UNIT i 17 Drywe,,1 Pressure (psia) 4 , r' Turbine Bldg. Roof Venc !
2 18 SBGT P ,ow A (scia) Joao- 47 Flow (sefs) / 5'Ocv i 19 SBGT F:,ow B (scfa) 3 oo o Turbine Bldg. Roof ' 20 Drvwell H, 4409 (I conc.) .wr 48 Vent Monitor (uci/sec.) s. . P s ) 21 Drywell H: 4410 (I conc.) . v 3" l 22 Drywell O! 4409 (I conc.) a,& l 23 Drywell O! 4410 (I cone.) 2.F l
- 24 A0G Syste5 Flow (scfs) a 25 off-Site Power Available y Main Stack Gas Monitor /
26 (uci/sec) a.0E d Turbine Bldg. Vent Monitor { 27 (uCi/sec) & O s '# [ DRYWELL HIGH RAD MONITOR R/hr ' 28 D22-RM-4195 - 30 fe El. a 29 D22-RM-4196 - 57 ft El. r !' 30 D22-RM-4197 - 23 fe El. a 31 D22-RM-4198 - 57 ft El. + I
- . 32 Drywell Temp ('P, wo I 33 Suppression Pool Temp ('F)
//y l RK. BLDG, ROOF VENT RAD
' MONITOR 1
34 Particulate (cos) s l 35 Iodine (eps) rs I 36 Noble Gas (cpa) rf 1 l- 0 PEP-02.6.21 Rev. 20 Page 22 of 34 ' i f i <
;(
I I l UNIT 0 ! PEP-02.6.21 l Attachment 6 ) Page 1 of 1 j EXEIBIT 2.6.21-6 j SAFETY PARAMETER DISPLAY SYSTEM (UNIT / ) , i l 02,erable J,noperable Standby Running Yes No Isolated j l ' i- NA,- Not available Time .boPo i i
! HPCI Flow (105) z3 ARIA RAD MONI':0RS- mR/hr i 2 Care 5:> rey A F ,ow (aps) .s 37 Rs. B .da. 20 lt Airlock L ;
3R 1R A :' low (mos) n ro u . Rx. 8:dg.,50 fe Sample 4 RCIC F,,ow (mos) s to 38 Station T 5 Core Spray B flow (mos) s 39 Ex. 5:,on. 50 fe Airlock i ! 6 RER R Flow (apa) _r . Ax. B:,og. North of Fuel .i 78 ,C In a 40 Pool' A ! - 8 C: tD F:.owh (aps) ina p ree Between Fuel Pool and 9APRM o 41 Drywell Dewuc (e : 10 Reactor Pressure ( sis) r7f Turbine Bldg. Sample . 11 Reactor Level
- 1h> ' /90 -42 Station ,a f e 12 Main Stack Flow Late (sefs) ys e.o 43 SJAE A (aR/hr) to >
turbine Alds. Roof Vent ' 44 SJAE B (aR/hr) 7 13 Flow (scfs) / r dea Rs. Bldg. Ventilation Rx. Bldg. Roof Vent Flow ' 45 Nonitor (aR/hr) . ' f~ 14 (scia) o Service Water. Rad Monitor Rx. Bldg. Negative Press 46 (cos)- I /' 15 (inches _of water vacuus) .Af 16 Suppress:Lon Pool Level (in) ta OTHER UNIT 17 Drywell Pressure (psta) r,o Turbine Bldg. Roof Vent 18 SBGT F:,0w A (scle) Poea 47 Flow (sefs) /ST c>v o 19 SBCT F: sow 8 (scfs) m weo Turbine Bldg. Roof ' ' 20 Drywel;,ii,4409 (1 conc.) . v s- 48 Vent Monitor'(uCi/sec.) A, 3 5 # l 21 Drvwell H! 4410 (5 cone.) . v s-l 22 Drywell 0; 4409 (% conc.) 2. y 1 23 Drywell O! 4410 (f cone.) 2. . ar 24 A0G Syste5 Flow (scfa) e { 25 off-site Power Available v ' Main Stack Gas Monitor _7 26 (vCi/sec) 2.or Turbine 81dg. Vent Monitor 27 (uci/sec) (,06'~# ^ DRYWELL !!IGH RAD MONITOR R/hr 28 *122-RM-4195 - 30 ft El. o
- 29 D22-RM-4196 - 57 fe El. r 30 D22-RM-4197 ~ 23 ft E
- ..
O
- 31 D22-RM-4198 - 57 ft E .. v 32 Drywell Temp ("F) 11e 1 33 Suppression Pool Tea) ("F) ff7 '{
RX. BLDG. ROOF VENT LAD
)
MONITOR i 34 Particulate (cpa) 55 ! 'J5 Iodine (cpa) T t' q 36 Noble Gas (com) T3 1 l O PF" f.2.6.21 Rev. 20 Page 22 of 34 [
UNIT 0 : PEP-02.6.21 l Attachment 6 , Page 1 of 1 ! EXHIBIT 2.6.21-6 i i SAFEIT PARANETER DISPLAY SYSTEM (UNIT / _) . r ! O l erable J,noperable S,tandby _ Running _ Yes No Isolated i jiA - Not available Time b o v.3- l 1 HPCI Flow (apa) 15 ARIA R4D MONITORS mR/hr ' 2 Core S > ray A F:,ow tape) _s 37 Rx. B:,q.a. 20 ft Airlock i { 3 RRR A riow (apa) iff , Rx. B:,s,s. 50 ft Sample , 4 RCIC F..ow (apa) Jeo 38 Station 'S' 5 core Spray B Flow (apa) 39 Rx. 5:,t.a. 50 ft Air',ock i
.s / ,
6 RER B Flow (mps) 5 Rx. B:,c,g. North of Puol .l 7 SLC Injectina v 40 Pool L
- 8 CRD F:.ow (mos) p re o - Between Fuel Fool and ,
9 APRM o _41 Drywell Dom ac /a, 10 Reactor Pressure (psta)- Pro Turbine Bldg._ Sample j 11 Reactor Love <, (in) / y 4- 42 Station ,1 12 Main Stack F:,ow Rate--(scfa) 76.a00 43 SJAE A (aR/hr) /o ) Turbine Bldg. Roof Vent " 44 SJAE B (mR/hr) 7 13 Flow (scfa) /r o ao - Rz. Bldg. Ventilation Rx. Bldg. Roof Vent flow ' 45 Monitor (mR/hr) .5~ - 14 (sefs) O Service Water Rad Monitor Rx. Bldg. Negative Press 46 (cos) ' S'/ l 15 (inches of water vacuus) , A 5" : 16 Suppression Pool Level (in) -fy OTHER UNIT J7 Drywell Pressure (psia) /s,o- . Turbine Bldg.. Roof Vent-18 SBGT Flow A (scia) Ja,o 47 Flow (sefs) ' /r Occ) 19 SBGT Flow B (sefa) 2 o,o Turbine Bldg. Roof 20 Drvve11 H, 4409 # (% cone.) , er 48 Vent Monitor (uCi/sec.) A.
~ 3 E i
21 Drywell H: 4410 (% conc.) , y s-22 Drywell O! 4409 (% conc.) m. v 23 Drywell 0" 4410 (% conc.) s.s 24 A0G SysteR Flow (sefs) a 25 Off-Site Power Available y-Main Stack Gas Monitor ' 26 (uci/sec) 2. O E
- I Turbine Bldg. Vent Monitor :
27 (uci/sec) 4, O E ~ # DRYWELL HIGH RAD MONITOR R/hr 28 D22-RM-4195 - 30 ft El. / ' 29 D22-RM-4196 - 57 fe El. 3-30 D22-RM-4197 - 23 ft El. / 31 D22-RM-4198 - 57 ft El. y 32 Drywell Temp ('F) syd 33 Suppression Pool Temp ("F) i s. o ' RX. BLDG. ROOF VENT RAD MONITOR 34 Particulate (eps) sf 35 Iodine tcpa) :c3 36 Noble Gas (cpa) T5 0 PEP-02.6.21 Rev. 20 Page 22 cf 34
i UNIT 0 ! PEP-02.6.21 i Attachment 6 l Page 1 of 1 l EXHIBIT 2.6.21-6 ,
- SAFETY PARAMETER DISPI.AY SYSTEM (UNIT 1 )
0.2orable J,noperable ,$,tandby R,unning Yes No Isolated j NA - Not available
- Time A./ o o I 1
1 KPCI Flow (apa) re _. ARIA RAD MONITORS mR/hr 2 Core Siray A F:,ow (apa) _r 37 Rs. Blda. 20 ft Airlock a ! 3 RER A Flow (apa) /irco Rs. Alds. 50 ft Sample- > 4 RCIC F..ow (apa) 15f- '38 Station r-5 Core Spray B Flow (apa) J 39 Rx. 5 .c.a. 50 ft Airlock / 6 RHR B Flow (apa) 5____ Rs. B:,s.g. North of Fusi 7 SLC Injectina /v' 40 Pool -L 't
. 8 CRD Flow (com) > re o Between Fuel Fool and 9 APRM 3 o 41 Drywell D u nsea (a- -
10 Reactor Pressure (psia) er a. 5" . Turbine Bldg. Sample .; 11 Reactor Level (in) ivo 42 Station ,4 l 12 Main Stack Flev Rate (sefa) 7 6 op o 43 SJAE A (aR/hr) to -( Turbine Bldg. Roof Vent ' 44 SJAE B (aR/hr) '7 13 Flow (scfa) /f' 000 Rx. Bldg. Ventilation Rx. Blds. Roof Vent Flow 45 Mouttor (aR/hr) If~ i 14 (scfa) o Service Water Rad Monitor Rx. Bldg. Negative Press- -46 (cos) f/ , 15 (inches of water vacuus) ,/0 + 16 Suppression Pool Level (in) ~/y OTHER UNIT- . 17 Drywell Pressure (psia) Lr Turbine _ Bldg. Roof Vent 18 SBGT Flow A (scia)
~ 3.o. 47 Flow (scia) /TOCO '
19 SBdT Flow B (scia) Je e o Turbine Bldg. Roof ,. 20 Drvvell H, 4409 (1 conc.) . v5- 4,8 Vent Monitor-(uCi/sec.) 13E 21 Drywell H: 4410 (1 cone.) . y 5- -' 22 Drywell O! 4409 (% conc.) 2.F I3 Drywell O! 4410 (% cone.) AF 24 A0G Syste6-Flow (scia) o 25 Off-Site Power Available v Main Stack Gr.s Monitor / l 26 (uci/sec) 3. O s 6 , i Turbine Bldg. Vent Monitor ,j - 27 (uci/sec) 4. 6 E DRYWELL HIGH RAD MONITOR R/hr } 28 D22-RM-4195 - 30 ft El. 1 29 D22-RM-4196 - 57 ft El. t. d 37,""522-RM-4197 - 23 f t El. / 31 D22-RM-4198 - 57 ft El. F 32 Drywell Temp ('F) Mr 33 Suppression Pool Temp ('F) />7 , RX. BLDG. ROOF VENT RAD MONITOR 34 Particulate (cpa) T3
- 35 Iodine (cpa) rc j 36 Noble Gas (cpa) 1 73 i
] O PEP-02.6.21 Rev. 20 Page 22 of 34 u
)
UNIT 0 l PEP-02.6.21 Attachment 6 i Page 1 of 1 l EERIBIT 2.6.21-6 I SAFETY PARAMETER DISPLAY SYSTEM (UNIT / ) ) Ogerable I,noperable S,tandby R_unning Yes No Isolated
]Q - Not available Time a / /r 1 HPCI Flow (ass) Tc AREA RAD MONITORS mR/hr 2 Core S tray A Flow (aps) S 37 Rx. 8:,da. 20 fC Airlock A ~~
j 3 RER A Flow (apu) / Lr a , Rx. B,ds. 50 ft Sample 4 RCIC Faow (apa) 7.ro 38 Station y ] 5 Core Spray B Frow (apa) J 39 Rx. BJa. 50 ft Airlock / 6 RHR 8 Flow (apa) 1 Rx. B,og.-North of Fuel 7 SLC Injectina N 40 Pool A.
. 8 CRD Flow (apa) p ie , Between Fuel Fool and 9 APRM ! o 41 Drywell b, _, u (, . ,
10 Reactor Pressure (psis) Ir'o u Turbine Bldg. Sample i 11 Reactor Leve;, (in) iva 42 Station . ~ .1 j 12 Main Stack F:.ow Rate (scfa) vs 000 43 SJAE A (aR/hr) io i Turbine Bldg. Roof Vent ' 44 SJAE B- (aR/hr) 7 'j 13 Flow (sefs) / 5*up o .Rx. Bldg., Ventilation , Rr.. Bldg. Roof Vent Flow- 45 Monitor (aR/hr) , f' 14 (sefs) O ~ Service Water Rad Monitor Rx. 31dg. Negative fress 46 (cos) S"'/ ' 15 (inches of water vacuum) .ao i 16 Suppression Pool Level (in) -f r CTRER UNIT' 17 Drywell Pressure (psia) / , s- Turbine Bldg. Roof Vent 18 SBGT Flow A (scfa) _t c> c o 47 Flow (sefs) I S'o o o 19 SBGT Flow B (scfe) -Joep Turbine Bldg. Roof , j 20 Drywell H, 4409 (I cone.) .tr* 48 Vent Monitor (uci/sec.) 2 . .? s: ' 21 Drywell H! 44iG T! conc . ) .vr 22 Drywell O! 4409 (% conc.) n , er 23 Drywell 0: 4410 (1 cone.) A. Y 24 A0G Systet Flow (sefs) o 25 off-Site Power Available V l ' Main Stack Gas Monitor / 26 (uci/sec) 2.o s ## ,. Turbine Bldg. Vent Monitor ,, i 27 (uci/sec) 4.64 DRYWELL HIGH RAD MONITOR R/hr
- 28 D22-RM-4195 - 30 fe El. 2 29 D22-RM-4196 - 57 fe El. 4 30 D22-RM-4197 - 23 fe El.
~
L 31 D22-RM-4198 - 57 f t El.-
/ ]
5 ! 32 Drywell Temp ('F) /rr t 33 Suppression Pool Temp ('F) i a 5-l RX. BLDG. ROOF VENT RAD MONITOR ! i 34 Particulate (cpa) :r_1 i 35 Iodine (com) s1 I 36 Nuble Gas (cpa) 2P5 l I 1 0 PEP-02.6.21 Rav. 20 Page 22 of 34 {
, - - n+--
l' UNIT 0 PEP-02.6.21 ! Attachment 6 ! Page 1 of l' : l- I EXHlBIT 2.6.21-6 ' SAFETY PARAMETER DISPLAY SYSTEM (UNIT / ) l Ogerable inoperable Standby R,unning Yes No- ' Isolated l l ! l NA - Not available Time A/30 ; 1 WCI Flow (S t :23 ARIA RAD MONITORS mR/hr ___, ! 2 Core SJray A F%ow (apa) 3 37 Rx. Blt.a. 20 ft Airlock 2: I 3 RER A Flow-(apu) // S po Rx. Bisg. 50 ft Sample 4 RCIC F;,cw (ana.1 d/ p o 38 Station 5~ , 5 Core Spray B F;,ow-(apa) 5 39 Rx. B:.t.a. 50 ft Airlock / ' 6 RHR 8 Flow (apa) y Rx. 3;,sg. North of Fuel : 7 SLC Injectina a 40 Pool 1. i
. 8 CRD Flow (apa) wfou -Between Fuel Pool and '
9 APRM % o 41 Drywell Dow,,re /c [ 10 Reactor Pressure (psia) 79a . Turbine Bldg. Sample i 11 Reactor Level (in) i90 42 Station ,1 , 12 Main Stack Flow Race (scfa) /s. ara 43 SJAE A (aR/hr) io , Turbine Bldg. Roof Vent ' 44 SJAE B (aR/hr) 7 ' 13 Plow (sefs) /Svou Rx. Bldg. Ventilation Rx. Bldg. Roof Vent Flow 45 Monitor (aR/hr) < f-14 (scia) ft see . Service Water Rad Monitor l Rx. Bids. Negative Press '~ 46 (cpe) I'/ , 15 (inches of water vacuum) , 3 3- > 16 Suppression Pool Level (in) -/y OTHER UNIT - i 17 Drywell Pressure (psia) i,r Turbine Bldg. Roof Vent 18 SBGT Flow A (sefs) woo 47 Flow (scfa) /3To o i 19 SBGT Flow B (scfa) 7oep Turbine Bldg. Roof- '
,20 Drvvell H, 4409 (1 cone.) ,vr 48 Vent Monitor-(uci/sec.) .t . ? s #
21 Devvell H: 4410 (I cone.) ,yr 22 Drvwell O! 4409 (% conc.) 2. . F 23 Drywell O! 4410 (% conc.) s.V
- 24 A0G Systet Flow (scfa) o 25 Off-Site Power Available y
( Main Stack Gas Monitor / 26 (uci/sec) 2, Os d , Turbine Bldg. Vent Monitor 27 (uci/sec) 6. 0 6E ~ , DRYWELL HIGH RAD MONITOR R/hr 4 28 D22-RM-4195 - 30 f e El. 29 D22-RM-4196 - 57 f t El. 4 .' 30 D22-RM-4197 - 23 fe El. J. 31 D22-RM-4198 - 57 fe El. r 32 Drywell Temp ('F) / 4 s-33 Suppression Pool Temp ('F) / .i 7
- 1 RX. BLDG. ROOF VENT RAD MONITOR
- 34 Particulat's (cpa) a 5 t>
35 I.odine (eps) asa a 36 Noble Gas (cpa) Apo O PEP-02.6.21 Rev. 20 Page 22 of 34
I 4 UNIT 0 PEP-02.6.21 l Attachment 6 - Page 1 of 1 EKMIBIT 2.6.21-6 SAFETY PARAMETER DISPLAY SYSTEM (UNIT / ) Og,erable J,,noperable Standby R,unning Yes No Isolated {
- j. N_A - Not available Time- sk / 'i'T I i 1 HPCI Flow (apa) rs AREA RAD MONITORS mR/hr
! 2 Core Spray A F;,ow (apa) 5 37 Rx. B;.da. 20 fC Airlock a , 1- j l 3 RER A Flow (apu) u ro, Rm. B;.dg. 50 ft Sample ' 4 RCIC-Flow (apa) vo. 38 Station S~ )- 5 Core Stray B F; Low (apa) 5 39 Rx. B1ta. 50 fe Airlock .1 'I 6 RHR 8 Plow (rps) S Rx. Blog. North of Fuel. j 7 SLC Injectina /v' 40 Pool 2 y l - 8 CRD Flow (apa)-
- eau Between Fuel Pool and
- 9 APRM % o 41 Drywell D e w e c. L j l 10 Reactor Pressure (psia) 775 Turbine Bldg. Sample )
11 Reactor Level (in) /fo 42 Station .1 1 1 12 Main Stack Flow Race (scfe) 74eop 43 SJAE A (aR/hr) so , Turbine Bldg. Roof Vent 44 SJAE B- (aR/hr) 7 1 a ' 13 Flow (scia) i 6 oo a Rx. Bldg. Ventilation l Rx. Bids. Roof Vent Flow ~45 Monitor-(aR/hr) ,f j 14 (scfa) 'h oea- Service Water Rad Monitor Rx. Bldg. Negative Press . 46-(cos) T/'
- l 15 (inches of water vacuus) , 3 f" 1
16 Suppression Pool Level (in) -n OTHER UNIT ! 17 Drywell Pressure (psia) /,r Turbine Bldg. Roof Vent 18 SBGT Flow A (scfa) _? co o 47 Flow (scfu) / 3~o 00 i l 19 SBGT Flow B (sefs) 3coe Turbine Bldg. Roof , 1 ! 20 Drywell H, 4409 (1 cone.) , v_c 48 Vent Monitor (uCi/sec.) .L f 6 I I 21 Drywell H 4410 (% conc.) , ys-22 Drywell 0; 4409 (% conc.) 2, y l 23 Drywall 0: 4410 (% cone.) 5,y i 24 A0G Systet Flow (sefs) o .I 25 Off-Site Power Available v i Main Stack Gas Monitor ' 26 (uci/sec) a, e i es Turbine Bldg. Vent Monitor 27 (aci/sec) 6, o s -t DltYWELL HIGH RAD MONITOR R/hr { 28 D22-RM-4195 - 30 fe El. 3 29 D22-RM-4196 - 57 fe El. 4 30 D22-RM-4197 - 23 fe El. 1 31 D22-RM-4198 - 57 ft El. r 32 Drywell Temp ('F) / 'y y 33 Suppression Pool Temp ('F) /Ay l RX. BLDG. ROOF VENT RAD MONITOR 34 Particulate (cpa) Joo 35 Iodine (cpa) 3og 36 Noble Gas (eps) , A. S g 0 PEP-02.6.21 Rev. 20 Page 22 of 34 l
P l UNIT 0 PEP-02.6.21 j Attachment 6 l Page 1 M i ! EXEIBIT 2.6.21-6 i SAFETY PARAMETER DISPLAY SYSTEM (UNIT / ) og,erable Inoperable Standby- R,unning Yes . No Isolated l l NA - Not available Time . M a o i ! l 1 KPCI Flow (apa) 23 ARIA RAD MONITORS mR/hr ' 2 Core Spray A Flow (apa) f 37 Rx. B;.da. 20 fC Airlock a,r . 3 RER A Flow (apa) // re o Rx. B;.dg. 50 ft Sample- ! l 4 FCIC Flow (aps) voo 38 Station S- *
- 5 Core Spray B Flow (apa) S 39 Rx. B;,on. 50 fC Airlock
- L j 6 RER B Flow (apa) S Rz. B;.03. North of Fuel i At 40 Pool' 7 SLC Injectina :L 8 CRD Flow (apa)
L- - *t e
- Between Fuel Pool and *
- 9 APRM ! o 41 Drywell Dow,,n /c 10 Reactor Pressure (psia) 75 o Turbine Bldg. Sample l 11 Rosetor Level (in) /vo '
42 Station ,1-12 Main Stack Flow Race (scfa) y s.eep 43 SJAE A (aR/hr) to i !' . Turbine Bldg. Roof Vent " 44 SJAE B (aR/hr) 7 E 13 Flow (scia) /r o00 .Rz. Sidg. Ventilation ' Rx. Bldg. Roof Vent Flow ' 45 Monitor (aR/hr) <4 14 (sefa)' F ood Service Water Rad Monitor ;
- Rx, Bldg. Negative Press ~ / 46 (cos) P/ ;
15 (inches of water vacuum) . 7 5' i 16 Suppression Pool Level (in) - f :t OTHER UNIT 17 Drywell Pressure (psia) /, y Turbine Bldg. Roof Vent- ! 18 SBGT Flow A (scfa) -2eso 47 Flow (scia) / .Foo ci , l 19 SBGT Flow B (sefs) 29.o Turbine Bldg. Roof l 20 21 Drywell Drywell H, H: 4409 4410 (1 cone.) ,er 48 Vent Monitor (uCi/sec.) L3e# l (% conc.) ,yr 22 Drywell O! 4409 ' i (% conc.) 2 . a* ' l 23 Dryvell 0: 4410 (% cone.) 2. y 24 A0G Systen Flc,w (sefs) a 25 Off-Site Power Available v ? Main Stack Gas Monitor ' 26 (uci/sec) 3. fs " # Turbine Bldg. Vent Monitor 27 (uci/sec) 6, O E'I DRYWELL HIGH RAD MONITOR R/hr ' i 28 D22-RM-4195 - 30 de El. a, l 29 D22-RM-4196_- 57 de El. 4 ,
- 30 D22-RM-4197 - 23 de El. .:t 31 D22-RM-4198 - 57 fe El. r 32 Drywell Temp ('F) / dr c) 33 Suppression Pool Temp ("F) />&
RX. BLDG. ROOF VENT RAD MONITOR 34 Particulate (cpa) Goo
- 35 Iodine (cpa) 600 36 Noble Gas (cpa) 900 '
O PEP-02.6.21 Rev. 20 Page 22 of 34 ,
i UNIT 0 . l PEP-02.6.21 4 Attachment 6
. EIMIBIT 2.6.21-6 SAFETY PARAMETER DISPLAY SYSTEM (UNIT / )
0,2erable },noperable S,tandby Running Yes No Jeolated NA - Not available Tims ' h r r ; l
- 1 HPCI Flow-(apa) "T e ARIA RAD MONI"0RS mR/hr !
' 2 Core S' pray A Flow (apa) .c 37 Rs. B;.da. 20 lt Airlock i ; 3 RER A ' low (apu) u rou As..B;,ds. 50 de Sample !
~
4 RCIC Flow (apa) r 38 Stat'.on J~ S" ' i
$ Core Saray B F;.ow (apa) s 39 Rx. : C,da. 50 fC Airlock 1 !
6 RHR B flow (apa) s Rs. B;,dg. North of Fuel 7 SLC Injecetus N 40 Pool :L
- 8 CRD F;.ow (apa) , ,ae Between Fuel Fool and 9 APRM N o 41 Drywell 0,w uc /a 10 Reactor Pressure (peta) rze Turbine Bldg. Sample. , '
11 Reactor LeveA (in) /vr 42 Station .2 , j l 12 Main Stack F:,ow Rate (scia) 74, cap 43 SJAE A (aR/hr) /o j Turbine Bldg. Roof Vent 44 SJAE B (aR/hr) 7 l 13 Flow (scfa) /rooc) Rs. Bldg. Ventilation i Rx. Bldg. Roof Vent Flow ' 45 Monitor (aR/hr) ,4 , i 14 (scle)- WOOO Service Water Rad Monitor i l Rx.. Bldg. Negative Press ' 46 (cos) J~/ 15 (inches of water vacuus) . J f" 16 Suppression Poel Level (in) .. f / OTHER UNIT 2 17 Drywel,1 Pressure (psis) /, r Turbine Bldg. Roof Vent 18 SBGT Plow A (scfa) .t o o o 47 Flow (scia) /5"c o o ! i 19 SBGT Flow B (sefs) 7mav Turbinsi Bldg. Roof ! 20 Drvwell H, 4409 (I cone.) ,yr 48 Vent Monitor (uci/sec.) A. Y e , ; I 21 Drywell H" 4410 (I cone.) ,w , 22 Drywell 0: 4409 (I conc.) 2,r i 23 Drywell O! 4410 (I cone.) a. e i 24 A0G Syste5 Flow (sefs) a 25 Off-Site Power Available v i Main Stack Gas Monitor ' i 26 (uci/sec) 3, TE " # Turbine Bldg. Vent Monitor 27 (uci/sec) 6. 0 E ~# DRYWELL HIGH RAD MONITOR R/hr 28 D22-RM-4195 - 30 fe El. 2 29 D22-RM-4196 - 57 ft El. 4 - l 30 D22-ig-4197 - 23 fc El. 2 ; 31 D22-RM-4198 - 57 fe El. r 32 Drywell Temp ('F) , f g <- 33 Suppression Pool Temp ('F) f2y RX. BLDG. ROOF VENT RAD MONITOR 34 Particulate (cpa) dro , 35 lodi.ie (com) 43 L s 36 Noble Gas (cpa) /4. o 0 i 0 PEP-02.6.21 Rev. 20 Page 22 of 34 ; l
UNIT 0 PEP-02.6.21 Attachment 6 Page 1 of 1 EXHlBIT 2.6.21-6 SAFETY PARAMETER DISPLAY SYSTEM (UNIT / ) 02 erable Inoperable Standby R,unning Yes No Isolated NA - Not available
~ Ties 12 30 w 1 HPCI Flow (aps) T:s ARIA RAD MONI"0R5 mR/hr 2 Cora Spray A f;,ow (aps) g 37 Rs. 8:,da. 20 Jt Airlock 1 3RiR A Flow (apu) A -
Rs. B.,ds. 50 it Sample 4 RCIC Flow (apa) . T 38 Station f 5"' 5 Core Spray B F:,ow (ass) 4 39 Ex. BLda. 50 f t A:,rl,ock s' 6 RER B Flow (aps) a Rx. B;,dg. North od Puel 7 SLC Injectina v 40 Pool 2.
. 8 CRD Flow (apa) Psee Between Fuel Fool and 9 APRM % o 41 Drywell h u. /e 10 Reactor Pressure (psia) yae Turbine Bldg. Sample 11 Reactor Love,, (in) cp 42 Station 1 12 Main Stack F ,ow Rate (scfa) po boa 43 SJAE A (mR/hr) io Turbine Bldg. Roof Vent 44 SJAE B (mR/hr) 'r 13 Flow ~(scia) if ooo Rs. Bldg. Ventilation Rx. Bldg. Roof Vent Flow 4518cnitor (aR/hr) , 5"'
14 (scfa) O' Service Water Rad Monitor Rx. Bldg. Negative Press
- 46 (cos) f/
15 (inches of water vacuus) . 3 .5" 16 Suppression Pool level (in) -n OTHER UNIT 17 Drywel;. Pressure (isia) /, S' Turbine Bldg. Roof Vent 18 SBGT F:,ow A (ucfa) Jeeo 47 Plow (sefa) / 5've v 19 SBGT Flow B (sefa) 3000 Turbine Bldg. Roof 20 Drywell H, 4409 (% conc.) ,vr 48 Vent Monitor (uC1/sec.) A. ? s , D rywell H; 4410 (% cone.) ,vr 22 Drywell O!.4409 (% conc.) 2 . fr 23 Drywell O' 4410 (1 cone.) 1.& _24 A0G Syste5 Flow (scfa) e 25 Ott-site Pcver Available V Main Stack Gas Monitor # 26 (uci/sec) L s s '# Turbine Bldg. Vent Monitor 27 (uci/sec) f, OE '# DRYWELL HIGH RAD MONITOR R/hr 28 D22-RM-4195 - 30 fe El, 1 29 D22-RM-4196 - 57 ft E1. 4 _ 30 D22-RM-4197 - 23 fe EL.- 1 31 D22-RM-416 - 57 fe El. r-32 Drywell Temp l'F) / ii 33 Suppression Pool Temp ('F) e i_ 6 RX. BLDG. ROOF VENT RAD MONITOR 1 34 Particulate (cpa) .75 35 Iodine (cpa) ps I 36 Noble Gas (cpa) 7J O PEP-02.6.21 Rev. 20 Page 22 of 34 e. i
UNIT 0 PEP-02.6.21 l g Attachment 6 t Page 1 of i , EXHIBIT 2.6.21-6 l SAFETY PARAMETER DISPLAY SYSTEM (UNIT / ) , op,erable },noperable S,tandby Running Yes No. Jo,olated s N,,A A - Not available Time M W~
! kPCI Flow (smal r3 ARIA RAD MONITORS mR/hr !
2 Core Saray A E,ow (aps)- # 37 Rs. 5:.da. 20 fe Airlock fa
~3 RiR A Flow (aps) m .
Rs. 8: dg. 50 f t Sample
- 4 RCIC F.,0w (apa) T 38 Station Ao 5 Core Spray B Flow (aps) 39 Ex. 5 ,da. 5T ft Airlock M a, o 6 RHR B Flow (mos) R Rx. 5 dg. North of Fuel 7 SLC Injectina u .40 Pool A- ,
j - 8 CRD F ,ow (apa) > /ee Between Fuel Fool and 9 APRM c2 41 Drywell com.n o (g ; i 10 Reactor Pressure (psia) d.s v Turbine Bldg. Sample i 11 Reactor Love,, (in) - 40 42 Stanton *1 12 Main Stack F:,ow Rate (scfs) sc oo, 43 SJA ;A (aR/hr) to : Turbine Bldg. Roof Vent ' 44 SJAll B (mR/hr's 7 [ 13 Flow (scia) /fpeo Rs. Bldg. Ventilation 4 Rx. Bldg. Roof Vent Flow ' 4$ Monitor (mR/hr) , - 5~ 14 (scia) . O Service Water Rad Monitor : . Rx. Bldg. Negative Press 46 (eps) f/ > j 15 (inches of water vacuus) . Af . j 16 Suppression Pool Level (in)
-9 OTHER UNIT' i 17 Drywel;. Pressure (psia) /, .f' Turbine Bldg. Roof Vent ;
18 SBGT F:,ow A (seft) Jm 47 Flow (scfa) / F'u cw , 19 SBGT F ,ow B (scia) vooo Turbine Bldg. Roof , 20 Drvwel . H,4409 (% conc.) ,yr 48 Vent Monitor (uCi/sec.) AJ E ,
~
l 21 Drywell H: 4410 (I conc.) ,w 22 Drywell 0; 4409 (% conc.) 1. ar 23 Drywell 0; 4410 (% conc.) A . fr 24 A0G Syste5 Flow (scfa) e i l 25 Off-Site Power Available V Main Stack Gas Monitor ' l 26 (9C1/sec) .2 .f"/r * # l Turbine Bldg. Vent Monitor 27 (aci/sec) _ 6,O G ~# D;tYWEU., HIGH RAD MONITOR ; R/hr 28 D22-RM-4195 - 30 fe El. 9 se ! 29 D22-RM-4196 - 57 ft El. /r o 30 D22-RM-4197 - 23 ft El. F7 ' 31 D22-RM-4198 - 57 ft El. // 7 1 32 Drywell Temp ('F) i 19f ' l 33 Suppression, Pool Temp ("F) ta y ' RK. BLDG. ROOF VENT RAD MONITOR
- 34 Particulate (cpa) ys j 35 lodine (eps) sc 36 Noble Gas (eps) ._
#5 '
O PEP-02.6.21 Rev. 20' Page 22 of 34 J 6
. ..n,, . . . . , . 4 y , . . . . - . . . , . _ . - . _ _ . , . ,+
. )
1 UNIT 0 1
-PEP-02.6.21 l Attachment 6 i Page 1 of 1 l EKRIBIT 2.6.21-6 )
SAFETY PARAMETER DISP 1.AY SYSTEM (UNIT / ) Ogetable J,,noperable 8,tandby Running Yes No Isolated l t M - Not available Time 4 _3 0 v l i
! KPCI Flow (apa) r3 AREA RAD MONI"0RS mR/hr !
2 Core Saray A F;,ow (ass) s 37 Rs. BLda. 20 it Airlock fe ! 3 RRR A ' low (apu) A Rs. B;,ds. 50 dt Sample ! 4 RCIC F,,0w (a03.1 E' 18 Stat,on Ao
- 5 Core Spray B F;,ow (ass) a.o A -M_ Ra . . C.da. 50 it Air!,ock 6 RHR B Flow (mos) A Rx. b;,dg. North of ; Fuel ,
- 7 SLC Injectina u 40 Pool A l 8 CRD Flow (ass) wrov- Between Fuel Fool and '
9 APRM I o 41 Drywell D o w n.r a (4 1 l 10 Reactor fressure (peta) do o Turbine Bldg. Sample i 11 Reactor ..e ve,, (in) - 6 5" 42 Station 1 - 12 Main Stack F ,ow Rate (scia) 7 6, cco 43 SJAE A (aR/hr) to i Turbine Bldg. Roof Vent " 44 SJAE B (aR/hr) , 13 Flow (sefs) /r a,o Rs. Bldg. Ventilation Ax. Blds. Roof Vent Flow 45 Monitor (nR/hr) ,T 1 14 (sefs) O Service Water Rad Monitor
- l Rx. Bads. Negative Press 46 (cos) f/ i 15 (inches of. water vacuus) ~1 5" I 16 Suppressson Pool Level (in) -g 0 TREK UNIT I 17 Drywel ,, 'ressure (psia) / , J- Turbine Bldg. Root Vent 18 SBGT ":,0w A (scia) po.. 47 Flow (scfa)
/5o*O 19 StGT Low B (scia) Jee Turbine Bldg. Roof 20 Drvwell H, 4A09 (I cone.) ,vr 48 Vent Monitor-(uci/sec.) 1. ) # #
21 Drywell H! 4410 (% cone.) . vs-~ 22 Drvwell O! 4409 (ilenc.) 2., br 23 Drywell 0; 4710 (I cone.) l ~. k l l- 24 A0G Systet Flow (sefs) a 25 Off-Site Power Available v : Main Stack Gas Monitor 26 (uci/sec) i . ,73 f*,/ f S $ /b, d f Turbine Bldg. Vent Monitor ' 27 (uci/sec) f', 0 6 ' f - " l DRYWELL HIGH RAD MONITOR R/hr-l 28 D22-RM-4195 - 30 ft El. pro l 29 D22-RM-4196 - 57 ft E ,. Y.5 0 4 30 D22-RM-4197 - 23 ft E; .. A. 7o ; i 31 D22-RM-4198 - 57 ft E:.. 9/o 32 Drywe11 Temp ('F) /ff 33 Suppression Pool Temp ("F) /.a-k- ' i RX. BLDG. ROOF VENT LAD 1 MONITOR ! 34 Particulate (cpa) 2 _r 35 lodine (cpsi) st 36 Noble Gas (cpa) TJ , i i l 0 PEP-02.6.21 Rev. 20 Page 22 of 34 - i
i UNIT 0 I PEP-02.6.21 ; Attachment 6' ! Page 1 of 1 EKH111T 2.6.21-6 SAFETY PARAMETER DISPLAY SYSTTM (UNIT / )
,0,gerable ,1,noperable Standby R,,unning Yes No Isolated-NA - Not available Tims "A 7 / P - ,
t 1 HPCI Flow (apa) rs AREA RAD M0 WITORS mR/hr ; 2 Core Spray A Flow (apa) a 37 Rs. 5 ,da. 20 ft Airlock /u i
, 3 RER A Flow (zoa) A Rs. 5:,ds. 50 f t Sa:aple 4 RCIC Flow (apa) T 38 Station 2o <
5 Core Spray B Flow (Ep )- a , 39 Ex. 3 ,da. 50 fe Air l,ock uo i 6 kHR 8 Flow (apa) A Rs. 5,ds. North of ;'uel , [ 7 SLC Injectina v 40 Pool 1. _ j i . 8 CRD Flow (apa) aru. Between Fuel Fool and ; 41 Drywe11 I 9 APRM % o Dow,u,4 /t i 10 Reactor Pressure (psia) 3so Turbine 51ds. Sample ;
'11 Reactor Levek (in) - s o S- 42 Station ,1 i 12 Main Stack F:,ow Rate (scia) 7t, c o o 43 SJAE A (aR/hr) so Turbine Bldg. Roof Vent 44 SJAE 8 (mR/hr) 7 13 Flow (scia) /r eco Ra. Bldg. Ventilation L Rx. Bldg. Roof Vent Flow '
45 Monitor (mR/hr) . 5~
.!_4 (scfa) O Service Water Rad Monitor -
l Rx. Bldg. Negative Pres's 46 (cpe) _ T/ 4 15 (inches of water vacuda) ,13' i
- 16 Suppression Pool Level (in) -y OTHER UNIT [
- 17 Drywell Pressure (psia) /, s- Turbine Bldg. Roof Vent
- 18 SBGT Flcw A (scia) eee. 47 Flow (sefs) /fd o o i l 19 SBGT Flow B (sefs) 1 oso Turbine Bldg. Roof 20 Drywell H, 4409 #
l (% conc.) 1. r 48 Vent Monitor (uci/sec.) A. 3 K - l_ 21 Drywell H: 4410 (% conc.) A.9 ; I 22 Drvwell O! 4409 (% conc.) 2,7 23 Drywell O! 4410 (% cone.) Jr . 3 24 t,0G Systet Flow (sefs) a 25 Off-Site Power Available y Main Stack Gas Monitor / G e 26 (uci/sec) -5"r H M 7 IO b Turbine Bldg. Vent Monitor
- 27 (uci/sec) [, C'E 'I DRWELL HIGH RAD MONITOR R/hr 28 D22-RM-4195 - 30 fe F1. 21po l 29 DI2-RM-4L96 - 57 ft El. avaa r 30 D22-RM-4197 - 23 fe El. 2Aeo i 31 D22-RM-4198 - 57 ft El. a ye o 32 Drywell Temp ('F) _
loc > > 33 Suppression Pool Teufi 'F)
~ r a.9 .
RX. BLDG. ROOF VENT RALE MONITOR 34 Particulate-(cpa) 35 Iodine (cpa)
%r - 1 rs i 36 Noble Gas (cpa) 55 l
O PEP-02.6.21 Rev. 20 Page 22 of 34 j
7
-l
.i UNIT 0 . i i
PEP-02.6.21 l Attachment 6 i Page 1 of 1 l
- EXEIBIT 2.6.21-6 t j SAFETY PARAMETER DISPLAY SYSTEM (UNIT / ) j i
Ogerable 1,noperable S,tandby R,unning Yes. No Isolated .; NA - Not available Time 3df0 f I RPCI Flow (apa) d .5 AREA MD MONITORS aR/hr i 4 T Core Spray A Flow (apa) v d a r- 37 Rs. B;,q.a. 20 ft Airlock 0,54 i 3 RER A rlow (apa) inoo Rs. B;,sg.-50 fc Sample l ! 4 RCIC F,.ow (apa) 'r 38 Station- 688 i l $ Core Spesy & Flow (ass) v 4 3. T 39 Rx. B;,da. 50 ft Airlock o5e i ! 6 RHR 8 Flow (apa) / 7,a o Rx. B;,dg. North of Fuel ! ! 7 SLC Injectina 'u 40 Pool A i
- . 8 CRD Flow (apa) > /a , Between Fuel Pool and !
_9 APRM I- o 41 Drywell Obw.u. (a , l 10 Reactor Pressure (psia) no Turbine Bldg. Sample 11 Reactor Level (in) { l vr 42 Station . 2. ; ) 12 Main Stack Flow Rate (scia) 76 o00 43 SJAE A (aR/hr) io ' Turbino Blds. Roof Vent
- 44 SJAE . I (aR/hr) 7 i 13 Flow (sefs) /foap Rs. B;,ds. Ventilation ' ,
, Rx. Bldg. Roof Vent Flow 45 Monitor (aR/hr) , .5' ' 14 (sefs) O Service Water Rad Monitor ' I Rx. Bldg. Negative Press 46 (cos) ' S'/ ~ , ! 15 (inches of water vacuum) ,ar # 16 Suppression Pool Level (in) -ra OTHER UNIT-i 17 Drywe;.a Pressure (poin) /, r Turbine Blds. Roof Vent i ! 3 SBGT l'..ow A (scia) Joe, 47 Flow (sefs) /rca v i l _19 SBGT Flow B (scia) Joes Turbine Bldg. Roof ; j 20 Drvve11 H, 4409 (1; conc.) 7, G 48 Vent Monitor (WCi/sec.) a..? F
- 21 Drvwell H: 4410 (1; cone.) 7. p 22 Drvve11 O! 4409 (); conc . ) 7. /
23 Dryvell 0: 4410 (); conc.) 2. i 24 AOG Systei Flow (scla) o- ! 25 off-Site Power Avai;.able - Main Stack Gas Monitor / V 08 M o g*,' ! 26 (uci/sec) 3,fe d M} / 1 Turbine Bldg. Vent Monitor 27 ( Ci/sec) ~/,o ( ~# ' DltYWELL HIGH RAD MONITOR R/hr 28 D22-RM-4195 - 30 ft El. yooo , 29 D22-RM-4196 - 57 tt El. ytoo 30 D22-RM-4197 - 23 ft El. Y,e, I 31 D22-AM-4198 - 57 fe El. Yaao 32 Drywell Temp ('F) 2ar 33 Suppression Pool Temp ('F) s19 RX. BLDG. ROOF VEPT RAD
~
MONITOR 34 Particulate (cpa) If 35 Iodine (cpa) JJ 36 Noble Gas (cpa) TJ j 0 PEP-02.6.21 Rev. 20 Page 22 of 34
'I 4
UNIT 0 ) PEP-02.6.21 .l Attachment 6 ! i Page 1 of 1 EXMIBIT 2.6.21-6 i SAFETY PARAMETER DISPLAY SYSTEM (UNIT / ) i l 02erable Inoperable Standby Running Yes No Isolated i JLA - Not available Time- M T3 ' I 1 HPCI Flow (ass;l rs AREA RAD MONI"0RS mR/hr ! 2 Core Spray A F;.ow (aps) Mo o 37 Bs. B;,da. 20 lt Airlock o3 a ! 3 RRR A Flow (apu) e Rs. B;,ds. 50 de Sample i 4 RCIC Flow (apgll 1 38 Stat!,on O J r/
$ Core Spray B F;,ow (ass) e 39 Rs. : L,da. 50 fc Air. .ock oan i 6 RER B Flow (aps) 6 Rs. 3;,dg. North of Juul l 7 SLC Injectina Ar 40 Fool 1 - 8 CRD Flow (193) F/*v Between Fuel Fool and !
9 APRM 1 a 41 Drywell Douwra /a 10 Reactor Pressure (psia) /o Turbine Bldg. Sample ; 11 Reactor Level (in) 1an 42 Stanion^ ,? 12 Main Stack F;,ow Rate (scia) n, e , 43 SJA 'A , (mR/hr) ,o
- Turbine Bldg. Roof Vent '
44 SJA tB (aR/hr) 7 , 13 Flow (scfs) /7000 Rs. Bldg._ Ventilation i Rx. Bldg. Roof Vent Flow ' 45 Monitor (aR/hr) , 3~
~~
14 (scia) O Service Water Rad Monitor Rx. Bldg. Negative Press 46 (cos) f/ 15 (inches of water vacuus) , a s~ -l 16 Suppression Pool Level (in) -n OTdER UNIT t Turbine Bldg. Roof Vent 17 Drywell Pressure (psta) /, r 18 SBGT Flow A (scfe) sono 47 Flow (sefs) ~ / $~, voo 19 SBGT Flow B (sefa) Jeoo Turbine Bldg. Roof 20 Drywell H, 4409 (1 cone.) Af , 7 48 Vent Monitor (uci/sec.) A, f E 21 Drywell H: 4410 (I cone.) n/ . r 22 Drywell 0; 4409 (% conc.) 2. o ' 23 Drywell O! 4410 (% cone.) J, i O j g .- p, cpg g 24 A0G Systet Flow (scfa) o g,/,f , } 25 Off-Site Power Available V
- Main Stack Gas Monitor #
,f l 26 (pC1/sec)
~ 3.fE u Turbine Bldg. Vent Monitor 27 (;Ci/sec) 9. O G ~
DitYWELL HIGH RAD MONITOR R/hr 28 D22-RM-4195 - 30 ft El. Yr s e 29 D22-RM-4196 - 57 ft El. vroo 30 D22-RM-4197 - 23 ft El. YS** I 31 D22-RM-4198 - 57 ft El. YF e o 32 Drywell Temp ('F) A u f-33 Suppression Pool Temp ('F) / a. 9 4 RX. BLDG. R00F VENT RAD MONITOR 34 Particulate (cpa) sr5 : 35 lodine (cpa) 51 36 Noble Gas (cpa) El ' O PEP-02.6.21 Rev. 20 Page 22 of 34 s .
, , - _ . - m ... , , , . ~ . . . . - _. .____..m-- - . - + _ _ _ _ _ - - - - _ - - - - -
- - - - _ - . ~ . - - . . _ - - . . . -__ _ .. . ._ - _ _ _ _ _ _
'i i
UNIT 0 ! PEP-02.6.21 j Attachment 6 ! Page 1 of 1 ) EIMIBIT 2.6.21-6 SAFETY PARAMETER DISPLAY SYSTEM (UNIT / )
- 'i I 0,gerable Inoperable S,tandby R,,unning Yes No Isolated
- N,A, - Not available Time AVeO i
! ! HPCI Flow (apa) m AREA RAD MONI'70R8 mR/hr > 4 i 2 Core Spray A F;,ow (aps) /rev 37 Rs. Blda. 20 Jt Airlock o.5 y 3 RER A Flow (apu) o Am.: Bldg. 50 de Sample , ! 4 RCIC Faow (apa i r 38 Station 0,54/ ! 5 Core Sprey B F;,ow (apa) a 39 Rx. Blda. 50 ft Air l,ock mu l 6 RHR 8 Flow (Epa) o Rs. Bldg. North of fuel 7 SLC Injectina a 40 Pool _ 1 8 CRD Flow (103) > /aa Between Fuel Fool and + 9 APRM 3 o 41 Drywell Dowan te l 10 Reactor: Pressure (psia) to Turbine Bldg. Sample ! 11 Reactor .evea (in) /9r '42 Station ,7 :
- 12 Main Stack F;.ow Rate (sefs) noso 43_SJAE A (aR/hr) to l Turbine Bldg. Roof Vent . 44 SJAE B (aR/hr) p
- 13 Flow (sefs) /J ap0 Rs. Bldg. Ventilation 1
,I '
- Rx. Bldg. Roof '/ent Flow 45 Monitor (aR/hr) $
j- 14 (scia) o Service Water Rad Monitor
- Rx. Bldg. Negative Press 46 (cos) T/
' 15 (inches of water vacuum) .2T ' 16 Suppression Pool Level (in) -n OTHER UNIT 17 Drywel , Pressure (psia) /. r Turbine Bldg. Roof Vent i
- 18 SBGT F;,0w A (sefa) reoo -47 Flow (sefs) / 5'v 0 0 '
19 SBGT Flow B (sefa) Jo,o Turbine Bldg. Roof , i 20 Drvwell H., 4609 (1 cone.) //._5- 48 Vent Monitor (uC1/sec.) A lf , i- 21 Drywell H: 4410 (I cone.) s/ , y ! 22 Drywell 0; 4409 (I conc.) .y , a / i 23 Dryvell O! 4410 (% conc.) 7, o O ~ # # "' O 'j " , 24 A0G Systen Flow (scfa) a 25 Off-Site Power Available v Main Stack Gas Monitor / , 26 (uCi/sec) a , OE "" Turbine Bldg. Vent Monitor i' 27 (uci/sec) 9. O p ' ' DRYWELL HIGH RAD MONITOR R/hr l 28 D22-RM-4195 - 30 fe El. Vroo 29 D22-RM-4196 - 57 fe El. Woo , 30 D22-RM-4197 - 23 ft El. 4r o, 5 l 31 D22-RM-4198 - 57 fe El. v&oo , 32 Drywell Temp ('F) sor ! 33 Suppression Pool Temp ('F) iA, 1 RX. BLDG. ROOF VENT RAD l MONITOR I
- _34 Particulate (cpa) Tr 1
35 Iodine (com) 3:5 ( 36 Noble Gas (cpa) .I 5 l i 1: l 1
- O PEP-02.6.21 Rev. 20 Page 22 of 34 i
l
-UNIT 0
' PEP-02.6.21 ;
Attachment 6 ; Page 1 of 1 l EERIBIT 2.6.21-6 !
- SAFETY PARAMETER DISPLAY SYSTEM-(UNIT / ) >
02 erable ,1,noperable Standby Running Yes No- Isolated i 1 i jjA - Not available Time OC / $~ ! . 1 HPCI Flow (apa) r5 AREA RAD MONITORS -mR/hr ; 2 Core Spray A Flow (apa) frav 37 Rx. Blda. 20 ft Airlock i c.s 4 3 RER A Flow (apa) 73 ov Rs. Bldg. 50 ft Sample . 4 RCIC Flow (apa) r 38 Station 05 h' ' . j _5 Core Spray B F:.ow (apa) a 39 Ax. B1 La. 50 f t - Airlock m# ! 6 RER R Flow (mos) 0 Rs. Bic,g. North . of Fuel l [ 7 SLC Injectina - A/ 40 Pool 1- + l - 8 CRD F:.ow (apa) e/oo Between Fuel Fool and , 9 APRM " o ~ 41 Drywell 00 Way.s /e. I ' -10 Reactor Pressure (psia) 19 . Turbine Bldg. Sample- , 11 Reactor Level (in) ,? ' if f 42 Station 12 Main Stack Flow Rate (sefs) n eda 43 SJAE A (aR/hr) to i Turbine Bldg. Rocf Vent 44 SJAE B (aR/hr) 7 :
- _1.3 Flow (scfe) /$~o 00 ,Rs. Bldg. Ventilation. '
} Rx. Blds. Roof Vent Flow , 45 Monitor (aR/hr) *I- i 14 (sefs) O Service Water Rad Monitor ? I Rx. Bldg. Negative Press 46 (cos) ,$'/ ' ! 15 ($nches of water vacuus) .AT ' 16 Suppression Pool Level (in) -/i OTHER UNIT '
- 17 Drywel;. Pressure (psia) / , 5- Turbine Blds, Roof Vent i 18 SBGT F;.ow A (scia) 7oea 47 Flow (scfa) /.Caov i
- 19 SBGT Flow B (sefs) Joao Turbine Bldg. Roof- '
t ! 20 Drywall H, 4409- (I conc.) i v. # 48 Vent Monitor (uci/sec.) 2. lf '. ' 21 Drywell H: 4410 (% conc.) / v. 4" _ I 'M Drywell 0; 4409 (% conc.) 7. 0 23 Drywell 0: 4410 (% cone.) 3, o " Og g . ,g,,,u r, g,/ ( 24 A0G Systei Flow (sefa) a 25 Off-Site Power Available v j Main Stack Gas Monitor / 26 (uCi/sec) 1, O FP' Turbine Bldg. Vent Monitor 27 (uCi/sec) 7, DE '# DRYWELL HIGH RAD MONITOR R/hr 28 D22-RM-4195 - 30 ft El. yreo ' 29 D22-RM-4196 - 57 ft El. Ysoa 30 D22-RM-4197 - 23 ft El. trea 31 D22-RM-4198 - 57 ft El. ytoo ' 32 Drywell Temp ('F)- .s us 33 Suppression Pool Temp ("F) s A. S RX. BLDG, ROOF VENT RAD ' MONITOR 34 Particulate (cpa) rt 35 Iodine (cpa) rr 36 Noble Gas (cpa) TI r 0 PEP-02.6.21 Rev. 20 Page 22 of 34 1; l'
i e P
-P SAFETY PARAMETER DISPLAY SYSTEM-UNIT 2 ,-
s t u b 4 6 i i , , , -, r
i WIT O i PEP-02.6.21 l 1 Attachment 6 l Page 1 of 1 '
)
EKHIBIT 2.6.21-6 , SAFETY PARAMETER DISP!AY SYSTEM (UNIT 1) f 02 erable Inoperable Stendby R,unning Yes No Isolated : i NA - Not available Time /80 0 1 H'CI Flow (apa) Tu AREA RAD MON 1MORS mR/hr , 2 Core Spray A Flow (apa) e 37 Rx. B;,da. 20 :.t Airlock 1o i , 3 k!!A A Flow (apu) Ss Rx. B;,ds. 50 d t St.aple :
- j. 4 9CIC Flow (apa) - rw 38 Station /,T l t 5 Core S > ray B F;.ow (apa) o 39 Rx. B;.da. 50 ft Air, ,ock i,o l 6 RHR B Plow (apa) 6osa Rx. B;,dg. North of ;' vel l 7 SLC Injectina v 40 Pool % /, v l l . 8 CRD Flow (apa) do Between Fuel Fool and I i 9 APRM 1 a 41 Drywell hun n (s. !
l 10 Reactor Pressure (psia) o Turbine Bldg. Sample j 11 Reactor Level (in) >ue 42 Station ,/ .. i 12 Main Stack Flow Rate (scfa) 7p, ee p 43 SJAE A (aR/hr) L Turbine Bldg. Roof Vent 44 SJAE B- (aR/hr) i i 13 Flow-(scfa) _ /E 000 Rs. Bldg. Ventilation
- 1. Rx. Bldg. Roof Vent flow 45 Monitor-(aR/hr) O. r 14 (scia) to 00a Service Water Rad Monitor ,
Rx. Bida. Negative Press " 46 (cos)- /O l 15 (inches of water vacuus) , ,7 2. - 16 Suppression Pool Level (in) -1 v 5- OTHER UNIT 17 Drywell Pressure (psia) er Turbine Bldg. Roof Vent 1 i 18 SBGT Flow A (scia) e 47 Flow (sefs) /6' 0 * # [ i 19 SBGT Flow 6 (sefs) e Turbine Bldg. Roof ' 20 Drywell H., 4409 (1 conc.) ~f O 48 Vent Monitor (uC1/sec.) [, o F [ 21 Drywell H; 4410 (1 conc.) 0 22 Drvwell 0" 4409 (% conc.) Ae,r 23 Drywell 0: 4410 (% cone.) a o. 5-24 A0G Systen Flow (sefs) 6o 25 off-Site Power Available V f1 Main Stack Gas Monitor / 26 (uci/sec) 2. o a d Turbine Bldg. Vent Monitor 27 (uci/sec) 2 . 3 p ' [ DRYWELL HIGH RAD MONITOR R/hr 28 D22-RM-4195 - 30 ft El. oow,m /. 29 D22-RM-4196 - 57 fe El. zh- u (, 30 D22-RM-4197 - 23 ft El. po .ec.c, 31 D 2 2-RM-4198 - 5 7 f t El . a. wa,, (4, 32 Drywell Temp ('F) sy 33 Suppression Pool Temp ('F) Far RX. BLDG. ROOF VENT RAD MONITOR 34 Particulate (cpa) 700 35 lodine (cpa) aoo 36 Noble Gas (cpa) Wo 0 PEP-02.6.21 Rev. 20 Page 22 of 34 j
]
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, ~
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V'
.c . UNIT.OL
-PEP-02.6.21 _
Attachment 6. Page 1 of 1- j EXHIBIT 2.6.21-6 ! SAFETY PARAMETER DISPLAY SYSTEM .(UNIT A )
- 0,y,erable I,noperable ; S,tandby R,unning Yes: No . Isolated ,.,
.NA,- Not available. LTime J/F/3{
1 HPCI Flow (apa) Tu AREA RAD MONITORS mR/hr 2 Core Spray A Flow (apa) e 37 Rx. Bidt. 20 ft Airlock f,o : 3 RRR A Flow (apa) SJ . Rx. 81ds. 50 f t Sample 3
-4 RCIC Flow (apa) xu 381Stacion /)T i 5 Core Spray B Flow (apa) o- 139 Rx. Blda. 50 ft Airlock 1,o l
_6 RHR 8 Flow-(apa) 6 oao .Rx.; Bldg.: North.ot: Fuel-7 SLC Injectina A/ 40 Pool- /, O
- 8 CRD Flow (apa) 6o -Between Fuel Pool and .,
9 APRM % 6- -41 Drywell o m c d a. 1 10 Reactor Pressure (psia) o Turbine Bldg. Sample I 11-Reactor Level tin) > ar e 42 Station-i/ :l 12 Main Stack Flow Rate (scfa) 7e, oo, 43 SJAE-A -(aR/hr)- 2 ] Turbine Bldg. Roof Vent- ' 44 SJAE B (aR/hr) i ? 13 Flow (sefs)- _
/ f, co o - Rx. Bldg.; Ventilation:
Rx. Bldg. Roof Vent FLN 45-Monitor-(aR/hr) oe4 14 (sefs)- 80 'ooa Service Water' Rad Monitor Rx. Bids. Negative. Press '
-. 46'(eps)- / O. 'l
'15'(inches of water vacuum) s'32. .
i 16 Suppression Pool Level-(in) 1v,5 i , 'OTHER' UNIT', 17 Drywell Pressure (psia)- o Turbine Bldg. Roof Vent. I 18-SBGT Flow A (scia) e 47 Flow (sefa) /6 08W ' 19 SBGT Flow B (scfa) o . Turbine-Bldg. Roof (% conc.) o
~
20 Drywell Hv 4409 -48 Vent Monitor (uCi/sec.) boF' . ; 21 Drywell H: 4410 (% conc.) o ' 22 Drvwell 0; 4409 (% conc.) .le.r ,
- 23 Drywell O! 4410 (% conc.) a o 5" 24 A0G Systen Flow (sefa)- 60 1 25 Off-Site Power Available V-L Main Stack Gas Monitor- /-
l 26 (uC1/sec) 2 ,~ o a * # Turbine Bldg. Vent Monitor 27 (uci/re:) 2 . ) p ' DRYWELL HIGH RAD MONITOR- R/hr-28 D22-RM-4195 - 30 ft El. o o w ,. u . /. 29 D22-RM-4196 - 5 7 f e El. h ,g tg 30 D22-RM-4197 - 23 fe El. o m.,. u .c, 31 D22-RM-4 L98 - 57 f t El. a.was t4 32 Drvwell Teen ('F)- Jir v .. l 33 Suppression Pool Temp (*F) P&- RX. BLDG. ROOF VENT RAD
- MONITOR I 34-Particulate (cpa) y oo 35 Iodine-(cpa) .s.oo 36 Noble Gas (cpa) i s'a 0 PEP-02.6.21 Rev. 20 Page 22 of 34 g.-
-1 l
.e UNIT 0-L ,
PEP-02.6.21 L Attachment 6 - Page' i of ~ 1 EXHIBIT 2.6.21-6 SAFETY PARAMETER DISPI.AY SYSTEM _(UNIT L) 20 erable Inoperable Standby R,unning Yes . No Isolated-NA - Not available Tina -- /33O A \ v 1 MPCI Flow (aps). Tu- AREA RAD MONITORS' aR/hr-2 Core Spray A Flow (apa) cp 17 Rx. Bida. 20 ft Airlock i;o r 3 RHR A Flow (apa) Es Rx. Bids. 50-ft Sample 3jlStation l 4 RCIC Flow (apa) zu ./<f 5 Core S > ray: B- Flow (Eps) O 39 Rx. Blda.=50 ft Airlock 1.o 1 6 RHR B Plow (aps) 6 oea- Rx. Bldg._ North of Fuel . 7 SLC Injacting y- 40 Pool '/. O
- 8 C_RD Flow (apa) do Between Fuel-Pool and
-9 APRM % o ,
41 Dryvell o w n e d a. ' 10 Reactor Pressure (psis) a : Turbine. Bldg.. Sample 1 11- Reactor Level (in) > as e 4J Station-
,/ , _
12 Main Stack Flow Rate (sefm) 7e,' oc o 43 SJAE A (mR/hr) .L
. Turbine Bldg. Roof Vent
. 44 SJAE B -(mR/hr) i 13 Flow (sefs) /T,000- Rx. Bldg. Ventilation Rx. Bldg. Root Vent Flow 45 ' Monitor (mR/hr) o i s-14 (scfa) 80 000 Service Water Rad Monitor Rx. Bldg. Negative Preas '
/46 (cos) / O.
15 (inches of water-vacuum) 31 16 Suppression Pool Level (in) '
-s e.S- OTHER' UNIT
- 17 Drywell Pressure (psia) o Turbine Bldg. Roof _ Vent-
/$ 0*#
18 SBGT Flow A (scia) e 47 Flow-(scfm) ~ O' j 19 SBGT Flow B (sefs) e Turbine Bldg. Roof ') 20 Dryvell H., 4409- (% conc.) 0-
~ f 48 Vent' Monitor (uCi/sec.) I, O F l 21 Drywell H: 4410 (% conc.)- o -
22 Drvwell O' 4409 -l (% conc.) .le , s - ! s 23 Drywell O' 4410 24 A0G Systei Flow (sefm)
-(% cone.) a o, 5-60
]
l 25 Off-Site Power Ava11hble y-Main Stack Gas Monitor / 26 (uci/sec) 2 ,o a *#: Turbine Bidg. Vent Monitor 27 (uci/sec) 2. 3 # ' ' DRYWELL HIGH RAD MONITOR R/hr ' 28 D22-RM-4195 - 30 ft El. o o w,.s c. & 2 h,. .r c e tg 29 D22-!?.".4196 30 D22-d?
- 5fe7 El.
4197 - 23 f t El. ou ,. e c.u 31-D22-RM-4198 - 57 fe El.
'j a.w r.,<4 32 Drywell Temp (*F) XY !
33 Suppression Pool Temp (*F) 6'8 -
)
RX. BLDG. ROOF VENT RAD MONITOR 34 Particulate (cpm) 70o ' 35 Iodine (cpm) s.oo 36 Noble Gas (cpm) fra 0 PEP-02.6.21 Rev. 20 Page 22-of 34
- 1. < *
,, t; T <
g . c. s . UNIT 0: i
~
PEP-02.6.21-2s Attachment 6 : T- Page 1 of 1-
- EXHIBIT 2.6.21 '
SAFETY PARAHETER DISPLAY SYSTEM (UNIT 1 ) -- e .
^
O i l erable Inoperable ' Standby Running . Y,es lNo- holated
~
i NA - Not. 1 available- Time- / F 9'$r
~
l 1 HPCI Flow (apa)- T A/ - AREA RAD MONITORS -mR/hr I L 2 Core Spray A ~Flow (apa) e 37 Rx. Bida. 20 ft Airlock f,o l_ 3 RHR A Flow (Apa) SJ , Rx.: Bldg. 50 ft Staple ! i 4 RCIC Flow (apa)- zu ' 38 Station /6 5 Core Spray B Flow-(apa) o- 3,,9,__Rx. Bida.'50 ft Airlock 1,o-6 RER B Flow (apa) 4 oso . tRx. Bldg. North of Fuel . 7 SLC Injectina. y 40 Pool '
'/,O- >
- 8 CRD-Flow (apa) 6o- Between Fuel Pool'and
-9 APRM % o- - 41'Drywell-Bown a la.
10 Reactor Pressure-(psia) a 1 Turbine Bldg. Sample : 11 Reactor Level-(in) _
> as e 42-Station'
// 1 12 Main Stack Flow Rate (scia) 70, oo 0 - 43 SJAE A- (mR/hr) 1,, ;
. Turbine Bldg. Roof Vent- '. 44 SJAE B (mR/hr)- 1
- 13 Flow (scfa) / f, 00 0 -- Rx, Bldg.-Ventilation-Rx. Bldg. Roof Vent: Flow -45 Monitor:(mR/hr) o . s- -
14 (sefa) So 00a ., . Service Water Rad. Monitor Rx.-Bldg. Negative-Press ' = 46 (cos)' l'O ' 15 (inches'of water vacuum) . 31' ' 16 Suppression Pool Level.(in) 3 v,S- OTHER UNIT.-
- 17 Drywell Pressure (psia) o TurbiIs Bldg. Roof Vent 4 08# .
18 SBGT Flow A (scia) e -47 Flow (scfa) 19 SBGT Flow B (scfm) o Turbine-Bldg. Riof 20-Drvwell-H,c 4409 ;j. (% cone.) c- - 48 Vent Monitor'(uC1/sec.)' [, O F ., 21 Drywell H: 4410 (% conc.) o g 22 Drywell 0; 4409- -(% cont.) 2e . s- I l- . 23 Drywell 0" 4410 (% cone.) ao. f 24 A0G Systen Flow (sefs): 60' ! 25 Off-Site Power Available- 'V= Main Stack Gas Monitor / l 26-(uci/sec) 2 , o a ' p Turbine Bldg. Vent Monitor 27 (uCi/sec) 2.)#*
' DRYWELT HIGH RAD MONITOR R/hr 28 D22-RM-4L95 - 30 ft El. o o w,.g u t, 29 D22-RM-4196 '57 ft El. - N - see4 30 D22-RM-4197 - 23 ft El. po ,.fc.c, 31 D22-RM-4198 - 57 fe El. ~
a,w as,#4 32 Dryvell Temp (*F) sv I 33 Suppression Pool Temp (*F) &g ' RX. BLDG. ROOF VENT RAD 4 MONITOR 34 Particulate (cpa) y oo 35 lodina (cpa) aoo 36 Noble Gas (cpa) s 5'o 4 4 0 PEP-02.6.21 Rev. 20 Page 22 of 34
' l i , ,
.m. .-- ..t - -, - ep .,.c . , - , , , - - . , . , ..,_..-.~4. -e,m... - - , , - .
1
'o, UNIT 0 . _
i PEP-02.6.21 2 Attachment 6 j Page-1 of 1 ' - l
' EXHIBIT 2.6.21-6 '-
SAFETY PARAMETER DISPLAY SYSTEM (UNIT 1 )_ i 02 erable Inoperable' S,tandby, Running Yes No- lsolated N_A,- A Noe'available' Time / 90C ' 1 HPCI Flow (apa)- -Tu AREA RAD MONITORS mR/hr 2 Core Spray A Flow (apa) e -37 Rx. Bida. 20 ft Airlock 1, o E 3 RHR A Flow (apa) 55 Rx. Blds. 50 ft Sample 4 RCIC Flow (apa) zu ?38 Station- /<T . 5 Core Spray B Flow (apa)- o 39 Rx.s Blda. 50 ft Airlock s,o >
. ,6 RHR B Flow (apa) 6 coo- Rx. Bldg. North of Fuel; 7 SLC Injecting A/ i40 Pool- /, 0 -
. - 8 CRD Flow (apa) 60 .. Between Fuel Pool.and 9 APRM 1 o 41 Drywell1 hoe rn's.
- 10 Reactor Pressure (psia)- c Turbine Bldg. Sample ]
11 Reactor Levels (in) > as o :42 Station ~ ,/ , l 12 Main Stack Flow Rate (scia) 7e, oo o
'43 SJAE A (aR/hr) a. ,
l Turbine Bldg. Roof Vent 44 SJAE B '(aR/hr) i 13 Flow (scfa) /F,000 . -Rx. Bldg. Ventilation-Rx. Bldg. Roof: Vent Flow- -45 Monitor-(aR/hr) c, r 14 (sef.m) d'o 000' Service Water Rad Monitor q Rx. Bldg. Negative-Press - '- 46 (cos) '/ 0 1 15-'(inches of watet escuum)? , 3 2. . t , 16 Suppression Pool Level (in) sy,S- 'OTHER UNIT-17 Drywell Pressure (psia) o . Turbine Bldg. Roof Vent 18 SBGT Flow A (scfa) e 47 Flow (sefa) /$ 08 # - ' 19 SBGT Flow B (scfa) o Turbine Bldg. Roof 20 Drvwell H, 4409- (% conc.) o 48 Vent Monitor-(uC1/sec.): [, 0 p ' ' 21 Drvwell H; 4410 (% cone.) o l- 22 Drvwell 0; 4409 (% conc.) - a e , s-l 23 Drywell 0; 4410 (% cone.) a o,5-24 A0G Systen Flow (scfa) 60 l 25 Off-Site Power Available y-I Main Stack Gas Monitor :/-- 'l' 26 (uCi/sec) 2, o a d Turbine Bldg. Vent Monitor
. 27 (uci/sec) 2 . 3 # #
DRYWELL HIGH RAD. MONITOR R/hr
- 28 D22-RM-4195-- 30 fe El.= o c,wm. (,
29 D22-RM-4196 - 57 fe El. m , ,,. .i t . g 30 D22-RM-4197 - 23 ft El. o,., , . u ,, c., 31 D22-RM-4198 - 57 ft El. a. wa,, u I 32 Drvwell Temp (*F) sy I I 33 Suppression Pool Temp ("F) Gg
~j l RX. BLDG.' ROOF VENT RAD -
MONITOR- l , 34 Particulate (cpa) yoo i { 35 lodine (cpa) aoo 36 Noble Gas fcpa) l l s s's 1 l l O PEP-02.6.21 Rev. 20 Page 22 of 34 4 4
. . _ - _ _ _ _ _ . ___ __ __ . . _ _ . . ~ . - . . . . . . . _ - _ _ . -_. . . .u .
(j .
~
UNIT O
. PEP-02.6.21 -l Attachment 6 c' i
.Page 1 of 1 EXHIBIT 2.6.21-6 .
l !
' SAFETY PARAMETER DISPLAY- SYSTEM (UNIT A )
O,gerable Inoperable S,,,tandby - R,,,unning Yes No Isolated NA,- Not available- Time '/9/f'- 1, t
- 1 HPCI Flow-(Epa) .T v AREA RAD MONITORS aR/hr 37 Rx. Blda. 20 ft Airlock 2 Core Spray A Flow (apa) o- /. o
- . 3 RHR A Flow (apa) ry Rx..Blds. 50 fc
- Sample ,
j ' 4 RCIC Flow (apa) Iu- ;38-Station /. f 5 Core Spray-B Flow (apa) o 39 Rx. Blda. 50 ft Airlock s,o 6 RHR B Flow (apa) como- RK. Rids. North of Fuel-- . 4 [ 7 SLC Injectina- e 40 Pool i /,o' c i, l - 8 CRD Flow (apa) 60 . Between Fuel Pool'and 9 APRM %- e ,,,,, 41 Drywell. Oow.u.44 ; 10 Reactor Pressure (psta) o Turbine Bldg. Sample " , 11 Reactor Level (in)- pato- '42 Station ./ l l 12 Main Stack Flow Rate 4(scfa) 768o, 43 SJAE<A (mR/hr) 2 4 , Turbine Bldg. Roof Vent 44 SJAE B (mR/hr) /- 13 Flow (scfa)- /.r o e o Rx. Bldg. Ventilation A Rx. Bldg. Roof. Vent Flow 45 Monitor'(mR/hr) O . S'- 14'(scfm) FO. # # c' Service Water Rad Monitor - 1 ! Rx.-Bldg. Negative, Press ' 46'(cos)- -/o' ! 15'(inches of water vacuum)~ . 7.2 . l 16 Suppression Pool Level (in) - a 8.f OTHER UNIT-17-Dryvell Pressure (psia) e . Turbine'Bidg. Roof Vent' [ 18 SBGT Flow A (scfm)- 6 47 Flow (sefa)- /r occ) , 19 SBGT Flow B (scia) o Turbine Bldg. Roof- . 20 Drwell H, 4409 (% conc.) o [ 21 Drywell H 4410 48 Vent Monitor'(uC1/sec.) .6. 0 F ' # (% conc.) 0 22 Drvwell 0: 4409- (% conc.) .to.S 23 Drywell 0" 4410 (% cone.)- J.e, r i 24 A0G Systen Flow (scfa) go- ' 25 Off-Si,te Power Available- y Main Stack Gas Monitor ' 26 (uCi/sec) 2, o e ' # ! Turbine Bldg. Vent Monitor 27 (uci/sec) #
"1. 3 E '
DRYWELL HIGH RAD MONITOR- R/hr - 28 D22-RM-4 L95 - 30 f t El. oo m. m /. 29 D22-RM-4196 - 5 7 f t El. o w <.. e I l 30 D22-RM-4197 --23 fe El. o,aA L 31 D22-RM-4198 - 57 fe E1. omm t e !- 32 Drywell Temp (*F) J/ l 33 Suppression Pool Temp (*F) s,' <s-i RX. BLDG. ROOF VENT RAD a MONITOR 34 Partic.ulate (cpa) Joo 35 Iodine (cpa) soo 36 Noble Gas (cpa) s f t/ l 0 PEP-02.6.21 Rev. 20 Page 22 of 34 l-l [ !
. _ . _ . _ _ . .._.,__.._z__. , _ _.. _ . _ _ . __ _
UNIT 0 1 l PEP-02.6.21-Attachment 6 - ] Page-1_of 1-EXHIBIT 2;6.21-6 Li SAFETY PARAMETER DISP 1.AY SYSTEM (UNIT ..A. ) , 02 erable Jnoparable.S_tandby R_unning.. Yes No Isolated' NA,- Not'available Time- /93O ; 1 HPCI-Flow (apa) .r a/ AREA RAD MONITORS mR/hr 2 Core Spray A Flow (apa) o 37 Rx. Bida. 20 ft Airlock /. o - 3 RHR A Flow (aps). Iy Rx. Bids. 50 fe Sample 4 RCIC Flow (apa) ru 38 Station = /.f ' 5 Core Spray B Flow (apa) e 39 Rx.-Bida. 50 ft Airlock = 1,o
31 D22-RM-4198 - 57 fe El. o. m. t a 32 Drywell Temp t'F) n 33 Suppression Pool Temp (*F) pp .; RX. BLDG. ROOF VENT RAD I MONITOR f 34 Particulate (cpa) Joo l .i 35 Iodine (cpa) soo I 36 Noble Gas (cpm) iS v 4 0 PEP-02.6.21 Rev. 20 Page 22 of 34
- - = - - - ~ ' * ^ ' - ~ ~ '
,l 4
. UNIT:0' . ,
PEP-02.6.21' l Attachment 6 o Page 1 of l' E EIH181T 2.6.21-6 SAFETY PARAMETER DISPLAY SYSTEN (UNIT'.."L ) L -
)
L 02erable ,1,noperable S,,tandby R_unning Yes No Isolated j NA - Not.available Time /eyefy-
~
1 HPCI Flow (apa) T A/ AREA RAD MONITORS- mR/hr 1 2 Core Spray A Flow (apa) -o ,37 Rx. B;.da. 20 ft Airlock /. o . ! l 3 RHR A Flow (aps) Iy Rx. B;.dg. 50: f t Sample l l 4 RCIC Flow (apa) ru .38 Station /. T :j l 5 Core Spray B Flow (apa) -o 39 Rx. Blda. 50 fC Airlock s,o S 6 RHR B Flow (apa) goeo .
.Rx. Bids. North of Fuel; 7 SLC Injectina . . ,/ o-8 CRD Flow (apa)
_ a __ 40' Pool
- 40 Between Fuel Pool.and, d 9 APRM % o 41-Drywell. Ou we c. /4,_- ;
10 Reactor Pressure (psis) 0- ' Turbine Bldg. Sample .' 11 Reactor Level (in) p a. t o '. 4 2 S tation --- ./ l 12 Main Stack Flow Rate (sefs) y6ao, -43 SJAE A= (mR/hr) -2 ] Turbine' Bldg. Roof Vent 44 SJAE.B: , (mR/hr) / j 13 Flow (scfa) /S o e u Rx..Bidg.'. Ventilation . Rx. Bldg. Roof Vent Flow .' .45 Monitor (mR/hr)- .O . S"'. l 14 (sefs) FO,deo Service Water Rad Monitor . .
~
Rx. Bldg. Negative Press ' 46 (cos)' L/o 15 (inches of- water vacuum) ~ , 72 ^ q 16 Suppression Pool Level (in) a 8,7 OTHER UNIT '
~ .
17 Drywell Pressure (psia)- e , Turbine Bldg. Roof Vent l 18 SBGT Flow, A (scia) e 47 Flow'(sefa) /S~ ood j
- 19 SBGT Flow B (scfa) '
o Turbine Bldg. Roof .' ~#. l 20 Drvve11 H, 4409 (% cone.) o 48 Vent Monitor (uC1/sec.) 6.O,c 21 Drvwell H: 4410 (% cone.) 0- . l 22 Drywell 0" 4409 (% conc.) :Lo.5 23 Drywell 0" 4410 (% conc.) 2.e, 3-
- 24 A0G Systeil Flow (sefs) go 25 Off-Site Power Available- -y Main Stack Gas Monitor-
26 (uci/sec) 2. O s_ ' # ! Turbine Bldg. Vent Monitor . i 27 (uci/sec) 2. 3 E "# DRYWELL HIGH RAD MONITOR R/hr
- '28 D22-RM-4195 fe El. oowau 4 3
29 D22-RM-4196 - 57 ft El. o mm e 30 D22-RM-4197 - 23 ft El. o m <u, A
- 31 D22-RM-4198 - 57 ft El. o.mru t e i 32 Drvve11 Temp-(*F) y </ -
33 Suppression Pool Temp -( *F) 5, p RX. BLDG. ROOF VENT RAD. ] MONITOR j 34 Particulate (cpm) Joo 4 35 Iodine (cpm) a.c o j 36 Noble Gas (cpm) s.f t/ 5 p 0 PEP-02.6.21 Rev. 20 .Page 22 of 34 l
t i UNIT 0-PEP-02.6.21- -
' Attachment 6 :
Page'1 of 1
. EXHIBIT 2.6.21-6-. -
SAFETY PARAMETER DISPLAY SYSTEM.(UNIT A ) Operable I_noperableL Standby ;R_unning Yes . No. Isolated: ; 3 - Not available Time- <Koo0 1 HPCI Flow (apa) .T A/ AREA RAD MONITORS- "aR/hr 2 Core Spray A Flow (apa) o- 37 Rx. Bida. 20 ft Airlock /. 0- , 3 RHR A Flow (apa) Iy Rx. Blds. 50:ft Sample. 38' Station-4 RCIC Flow (apa) ru /.f 5 Core Spray B Flow (apa)- o 39 Rx. 81da.-50 ft: Airlock s,o 6 RHR 8 Flow (apa) g oe o - Rx. Bldg. North-of Fuel' 40 Pool' 7 SLC Injecting a /. o
- 8 CRD Flow (apa)- 60 Between Fuel Pool-and- -!
9 APRM % o 41 Drywell Oo w, _r u /,,4_,% 10 Reactor Pressure (psia) O . Turbine; Bldg. Sample; , 11 Reactor Level (in) p a. / o - .42 Station ./ 12 Main Stack Flow Race (scfa) 43 SJAE A (aR/hr) 768o,- 2-Turbine Bldg. Roof-Vent , 44 SJAE B (aR/hr), /- 13 Flow (scfe,_) /S oe a Rx.-Bldg.. Ventilation-
- Rx. Bldg. Roof Vent flow .' 45' Monitor (aR/hr) 0 , .S~ - 1 14 (scfa) 70, # # 8' . Service Water. Rad Monitor .
Rx. Bldg. Negative Press 46 (cos) /o 15 (inches of water vacuum)- , 72 - 16 Suppression Pool Level (in) . 28,5 -0THER' UNIT
~t 17 Drywell Pressure (psia)-- e .
- Turbine Bldg.' Roof Vent 18 SBGT Flow A (scfa)- e 47 Flow (scfa) /S' ood 19 SBGT Flow B (sefa) o Turbine Bldg. Roof-20 Drvve11 H, 4409- (1 conc.) o 48 Vent Monitor-(uC1/sec.) 6. O g ~ #
21 Drywell H: 4410 (% conc.)- o 22 Drvve11 0: 4409 (% cone.) ap.y 23 Drywell 0: 4410 (% cone.) 2.c., r 24 A0G Systen Flow (scfa) 40 25 off-Site Power Available y Main Stack Gas Monitor ' 26 (uC1/sec). 2, of v # Turbine Bldg. Vent Monitor 27 (uci/sec) 't . 3 E " DRYWELL HIGH RAD MONITOR R/hr 28 D22-RM-4195 ~ 30-ft El. oe w.ve, te 29 D22-RM-4196 - 57 ft'El. o - , c. e 30 D22-RM-4197 - 23 ft El. o .m us _ 31 D22-RM-4198 - 57 ft El. o ,e I a 32 Drywell Temp (*F) yy l 33 Suppression Pool Temp ('F) 9t, _ RX. BLDG. ROOF VENT RAD MONITOR 34 Particulate (cpa) .70o l 35 Iodine (cpa) soo 36 Noble Gas (cpa) / f'u 0 PEP-02.6.21 Rev. 20 Page 22 of 34 i-
UNIT 0 PEP-02.6.21 _ .l Attacha3nt.6 ~ ' Page 1 of 1 - EXHIBlT 2.6.21-6 - , SAFETY Pl>RAMETER: DISPLAY SYSTEM-(UNIT d , )- , 02 erable- Inoperable Shandby R_unning Yes '
'No Isolated ,
l
- NA - Not available Time A o / f' #
1 HPCI Flow- (apa)- .ry AREA RAD MONITORS mR/hr 2 Core Spray A Flow (apa) o 37 Rx. B;.da. 20 fe Airlock /. o I ^ 3 RHR A Flow (aps) Iy- . Rx. 8.dg. 50 ft. Sample -! 4 RCIC Flow (apa) ru 38 Station /. 7 '; E 5 Core Spray B Flow (apa) a 39 Rx. Blda. 50 fe Airlock s,o 6 RER B Flow (apa) doeo .Rx. Bldg. North of Fuel 7 SLC Iniectina a . 40 Pool '
/, o I
- . 8 CRD Flow (apa) 60 . Between Fuel Pool and Li
- 9 APRM 2 a- 41 Drywell' oow,,c. 44 ! ,
l 10 Reactor Pressure (psis) 0- . Turbine Bldg. Sample' ,
.11 Reactor Level (in) J42 Station.
, pato- ./ ,
- 12 Main Scack Flow Rate (scfa) 76*oo
- 43 SJAE A (sR/hr) r Turbine Bldg... Roof Vent l44 SJAE B. teR/hr) /,
13 11ow (sefs)
/. r o e o
<Rx. Bldg. Ventilation l Rx. Bldg. Roof Vent Flow 45. Monitor (aR/hr) 0 . .S~ ;
- 14 (sefe) Fv;de o L S ervice Water Rad Monitor Rx. Bldg. Negative Press '
~46'(cos) -/o' i
-15 (inches of water vacuum)~ , '
L 16 Suppression Pool Level (in) . a 4', y OTHER UNIT' 'I L 17 Drywell Pressure (psia) e Turbine-Bldg. Roof-Vent .. -! 18 SBGT Flow A (sefe) _ 47 Flow (sefa) 6 ~
/r occ) 19 SBCI Flow B (scfa) o *
-_ Turbine Bldg. Roof '
20 Dtvwell-H, 4409* (% conc.) o 48 Vent Monitor (uCi/sec.) S. 0 F ' b 21 Drywell H: 4410- (% conc.) 0 22 Drywell O! 4409 (% conc.) 1o,5 23 Drywell O! 4410 (% conc.) 2.e s-24 A0G SysteeTi Flow (sefa) go 25 Off-Site Power Available y Main Stack Gas Monitor ' N 26 (uCi/sec) 2. O s * # Turbine Bldg. Vent Monitor 27 (uci/sec) 2 ;3 E " DRYWELL HIGH RAD MONITOR R/hr. 28 D22-RM-4195 - 30 fe-El. com.m /. 29 D22-RM-4196 - 57 ft El. o m m t, 30 D22-RM-4197 - 23 fe El. o,ag 31 D22-RM-4198 57 fe El.- c.mm ( e 32 Dryvell Temp (*F) ha </ 33 Suppression Pool Temp (*F) 5, p RX. BLDG. POOF VENT RAD MONITOR 34Partie[ ate (35a) .7 a o _ 35 lodinr Jcy ), _ 2co 3f> Noble As ic*.ar if- v 0 PEP-02.6.21 Rev. 20 r*ge 22 of 34 } .. : . . -. . i
' UNIT'O ,
PEP-02.6.21; Attachment 6 - p Page 1 of 1 ; EXHIBIT 2.6.21-6-- SAFETY PARAMETER DISPLAY SYSTEM (UNIT .,;lL )
-1 l 0,y,erable I,noperable S,tandby R,unning Yes' No- ' Isolated' j NA - Not available_ ; Time .'LU S 0 ' ,
1 HPCI Flow-(apa) .T v AREA RAD MONITORS mR/hr
-2 Core Spray A Flow (apa) o 37 Rx. Blda. 20 ft Airlock /. o 3 RHR A Flow (apa) ry ;Rx. Bids. 50 fe Sample -
~ '
38' Station-4 RCIC Flow (apa) - ru / . S' .1 5 Core Spray 8: Flow (apa) e- 39 Rx. Blda. 50 fe-Airlock s,o .; _6 RHR B Flow (Era) domo- ., Rx. Bldg.-North of Fuel. ,
,J SLC Injectina u .40 Pool ' /,o
. ~
- 8 CRD Flow (apa) 60 Between Fuel Pool and 7J APRM %- =a 41'Drywell' oc w m (.e.s '
! 10 Reactor-Pressure-(psia) -0 Turbine _ Bldg.-Sample. {
- 11 Reactor Level (in) p a. io -42 Station .- /
12 Main Stack Flow Rate-(scfa) vaso, 43 SJAE A (aR/hr)- r l Turbine _ Bldg. Roof Vent 44 SJAE B (aR/hr) / : 13 Flow (scfa): /roeo Rx.~ Bldg. Ventilation- *
- _ Ex. Bldg.- Roof Vent. Flow '
. 45 Monitor-(aR/hr) 0. 5- !
! 14 (scfa) ' fo # 8 8' t Service Water. Rad Monitor i Rx. Bldg. Negative Press ~ L 46 (cos) - '/o . 15 (inches of water vacuum) , ~ 7.:t ' 116 Suppression Pool Level (in) j - 28.5 OTHER UNIT' ' L 17 Drywell Pressure (psta) e Turbine Bldg. Roof Vent-18 SBGT Flow A (scfa)- e 47 Flow (scfa) /S~ coc) 19 SBGT Flow B-(scfa) o Turbine. Bldg. Roof ' 20 Drvve11 H, 4409 -(% conc.) o ~# l 48-Vent Monitor"(uCi/sec.)' 4. O f ~ L 21 Drvwell H 4410 (% cone.) o i 22 Drywell 0" 4409 (% conc.) ao.5 ! 23 Drywell O! 4410 -(% conc.) J.o, 5- ! ~
.24 A0G Syste&-Flow (sefs)-- ga 25 Off-Site Power Available y Main Stack Gas Monitor. '
26-(uC1/sec) 2, 0 9 * # Turbine Bldg. Vent Monitor 27 (uci/sec) 2,3 E " i DRYWELL HIGH RAD MONITOR R/hr
- j. 28 D22-RM-4195 - 30 fe El. com.m 4 29 D22-RM-4196 - 57 ft El. o o . m u . t,
!. 30 D22-RM-4197 - 23 fe El. o . m ,. . A l 31 D22-RM-4198 - 57 fe El. c.wm t a j 32 Drywell Temp ('F) y </ I- 33 Suppression Pool Temp t*F) 5,, t L RX. BLDG, ROOF VENT RAD l MONITOR !' 34 Particulate (cpa) 300 (_ 35 Iodine (cpa) soo
- l. 36 Noble. Gas (cpa) erv I
O PEP-02.6.21 Rev. 20 Page 22 of 34 l 1 _ - _ _ ~
[
-liNIT 0t l PEP-02.6.21
+
Attachment 6 j
- l. . Page 1 of l EKHIBIT 2.6.21-6' '
;SAFETT PARAMETER DISP 1.AY SYSTEM (UNIT :A. )
l L ogerable Jnoperable S,tandby _R_unning 'Yes No Isolated I i NA - Not available Time A o </J'
~
, 1 HPCI T'ow (apa) 2v AREA RAD MONITORS mR/hr- 4 g 2 Core Spray A Flow (apa) o '37 Rx.-Bida. 20 fC Airlock /o j 3 RHR A ilow (aps)- Iy kx, Bidt. 50 fe Sample ;
- 4 RCIC Flow (apa) ru 38 Station / .T -
- -5 Core Spray B-Flow (apa) e 39 Rx.=Blda. 50 fC Airlock 1,o 6 RHR B Flow (apa) doeo Rx. Bldg. North of. Fuel 7 SLC Injectina- -u 40 Pool- / o- ~, .
p - 8 CRD Flow (spa) 60 Between Fuel Pool andT l 9 APRM % ' e- 41 Drywell Oow._ra 4e 1 l l 10 Reactor Pressure,(psia) 11 Reactor Level-(in) o p a. t o Turbine Bldg. Sample.
- 42 Station-
.. j
, /: u 12 Main Stack Flow Race (scia) 16 a o_,_ 43 SJAE A- (aR/hr) 2-
. Turbine Bldg. Roof. Vent 44 SJAE B .(aR/hr) /- 1 -13 Flow (scia)- /f o p o -- Rx. Bldg. Ventilation . .Rx. Bldg. Roof Vent Flow
~
445 Monitor'(aR/ht) ~ 0, T - 14'(scfa)- FO,dev Service Water Rad Monitor .
- .Rx. Bldg.-Negative Press '
46-(cos)- - (/o l 15 (inches of-water vacuum)- , 72 16 Suppression Pool Level-(in) - a 5.7 OTHER' UNIT' 17,,_Drywell Pressure (psia) e Turbine Bldg. Roof Vent-
- IS SBGT Flow A (scfa) 6 47 Flow (scfa)- - /r occ) l l 19 SBGT Flow B (sefa) o Turbine-Bldg. Roof 20 Drywell H, 4409 (% conc.) o- 48 Vent Monitor (uCi/sec.) ,s.'O g ' #
21 Drywell H: 4410 (% cone.) o
, 22 Drywell 0; 4409 (% conc.) to.r.
l 23 Drywell O! 4410 (% conc.) j act r i 24 A0G SysteA Flow (scfa) go 25 Off-Site Power Available y Main Stack Gas Monitor ' I 26 (uci/sec) 2. o ts * # l Turbine Bldg. Vent Monitor l h 27 (uci/sec) # 2.36 l l DRYWELL-HIGH RAD MONITOR R/hr
- l. 28 D22-RM-4195 - 30 ft El. oo w.a., /=
1 29 D22-RM-4196 - 57 ft El. o _ u.6 30 D22-RM-4197 - 23 ft El. or <. .n__ 31 D22-RM-4198 - 57 ft El. o- ru t e ; 32 Drywell Temp (*F) Fv ' { 33 Suppression Pool Temp ('F) 9t RX. BLDG. ROOF VENT RAD I MONITOR . i 34 Particulate (cpm) 300 l 35 Iodine (com) soo l 36 Noble Gas (cpm) &v I
- j. l 0 PEP-02.6.21 Rev. 20 Page 22 of 34 t
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- POST ACCIDENT SAMPLING SYSTEM (PASS) RESULTS.
l The following information : will' be applicable ' for . any PASS samples:obtained after 2245 RADIATION-READINGS FOR 7ARIOUS TYPE 8 OF SAMPLES Reactor Coolant Samples Small (diluted) vial.- unshielded: 100lmR/hr contact
-1 mR/hr~ contact-Small'(diluted)-vial - shielded-
;2 mR/hr contact ',
"As read" 9.1 Foot 1
.l Large (undiluted) vial - unshielded 5000 mR/hr,. contact
' 75 mR/hr 91 Foot' Large (undiluted) vial '.shieldedI 150!aR/hr contact
- 1 mR/hr 9.1 Foot Drywell Air Samples 1 Gas - 1800'mR/hr 9' Contact.
Particulate Iodine- 10'mR/hr 9'ilFoot. .i Particulate' MPC'Value - 1000 l- Iodine Radiation Monitor Readings on Pass Panel.During Sampling. Area Monitor (RI-507) 2S mR/hr Liquid Monitor.(RI-665) 5000 mR/hr j Cartridge Monitor (RI-704) 1800-mR/hr 1 Sample results are valid after 2245 (post fuel-' failure)
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SUMMARY
' RADIOLOGICAL CONDITIONS IN UNIT 1 REACTOR BUILDING WILL BE AS READ" PRIOR TO -
2115. FOLLOWING THE TAILURE OF THE REACTOR BUILDING TO SUPPRESSION CHAMBER , VACUUM BREAKERS; RADIOLOGICAL' CONDITIONS. RISE-IN THE REACTOR BUILDING DUE.TO A~- LEAK TO SECONDARY CONTAINMENT. -FOLLOWING FUEL DAMAGE; RADIATION' LEVELS TAKE-A-SIGNIFICANT INCP. EASE IN THE AREA 0F SBGT, AND THOSE ECCS SYSTEMS THAT ARE : < - INJECTING. RADIATIONLEVELSTAKE'ASIGNIFICANT'INCREA{EyNTHEUNIT1 TURBINE
BUILDING FOLLOWING' REACTOR DEPRESSURIZATION.
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t _'. l IN-PLANT RADIOLOGICAL CONDITIONS '! 2115 --2230 q I
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L. ERUNSWICK STEAM ELECTRIC PLANT seqvgy y;; RADIOLOGICAL SURVEY. RWP NC, ,, REACTOR BUILDING ~#2 u 20 GENERAL AREA CATE @ 3~ N TIMEMll6" O 005E RATE CONTAMINATION INST. TYPE' INST.' TYPE SURVEYOR SERIAL NO.' -SERIAL ND. ~ RX POWER
' EFFICIENCY _ ,,
REVIEWED BACMCROUND SHEAR RESULT 5
'" IN OPM/100cm a -i I-h ' 8*0 ETA"IN MRAD /HR/100cm' 4 PolNT RESULTS -j s
#- _- . 5 -
a C:lll: p- - i 4 lD Y NoetM s & -
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~ 10 - 28 T 5-r0 -
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- 3. CCNTAct c gg GATES Af + h>
mR/HR, 4 BETA DOSE RATE ]N FRAD/ht I LAe b VO C.tlu rT 1 bfla NT '"'"^~
'oM S4RCk OOen l J I BSEP/vCL. v111/EL40 :::: '
L'
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' _8RUNSWICK STEAM ELECTRIC' PLANT SURVEY NO. RADIOLOGICAL SURVEY , g RWP NO. REACTOR BUILDING.#1'
~
'50' GENERAL AREA-OATE4 2-9D TIME OllE 0030 00SE RATE' CONTANINATION
' INST. TYPE '!NST. TYPE
' SURVEYOR SER!AL No.- SERIAL NO.
RX POWER : EFFICIENCY REVIEWE0 'SACMGROUND
. SMEAR RESULTS.
IN OPN/100cea I ~~ 9*8 ETA IN mRA0/P/100ema g POINT *EEULTS q EBIB ' uuu.t . - IIIfB 5 , 10 = I- i' ea - g a g- __D. L r m - 5 o _ 3
. __. s- i
- a o -
s_ a, r, g - I ,
, i i
0 0 0 ** i i ! i i, kAir Ac4vi4 1. o E - 9 @l. 3 , ef.on4ansm&n : 4 ace dem -
@cOU ;
NOTE '. OAtA 3 td l\ Skod MnY ns'o$- j',INEg3MQ" mR/MR. ram "
- 3. CONTACT 0088 RATES AT
- IN mR/HR. , \'
- 4. ORTA DOSE RATE IN mRAO/HR e Yo c. ti t t 6is brea ko r ha n .A dac k. '"** *' '* * ~
g J aser/va vits/saRe-anoo-
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4 ; BRUNSWICK' STEAM ELECTRIC PLANT ' SURVEY NO. RADIOLOGICAL SURVEY RWP M0. REACTOR SUILDING #1 9' & 20' NORTH'AND SOUTH RHR ROOMS DATE Md0 TINE N - M 80 00SE RATE: CONTANANATION INST. TYPE INST. TYPE __ .- SURVEYOR SERIAL NO.- SERIAL, NO. - 1 RX POWER -EFFICIENCY- -. i REVIEWED SACNGROLee -
. SMEAR RESULTS- 1
' 20' N.RHR IN OPM/100ama -1 30' S. RMR - g,g g.. IN MRAD />tU100am' )
, , Py),4Y REStn.TS
,/ o -
f 06. - 9
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o c. - [ 'I 1 4 l 1 l
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O ' 7_O b .- l l I (- 9' N.RHR .S*'E.RHR 'l ' g - s 9.OE' ' LA
$h p' g tw w m < - ,
50
~ S* I
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- 1. MEAR LOCAT11BI CIRCLED L 000E RATE AT LOCATION TAMEN i
y lD
*""" lO (17 1N nRAst.
! m - IAL 1 3. CM TACT ODOE RATES AT
- IN sithst.
- 4. BETA 0084 RATE IN mRAC/HR I NORTH INDICATED BY A *t*
l~ SSEP/VIL. VI!!/ESAC-0100
-,-*,w. ,iw, -,,,y-c-- , _ - - - ,,, _ _ _ , ~ . -
l ?<' BRUNSWICK STEAM ELECTRIC PLANT SURVEY NO. L RADIOLOGICAL SURVEY RWP NO.
. REACTOR ~ BUILDING #1
)
-17' NORTH R.H.R. 1 L
DATE bl4dTIME SIT-1230 00SE RATE CONTANINATION-INST. TYPE - -INST. TYPE SURVEYOR SERIAL NO.- SERIAL NO. 3 RX POWER - EFFICIENCY- I REVIEWED. SACKGROUND' g g ej - SMEAR RESULTS M E6_ TC
+8;,je{yl[h: ggk j(-
'IN DPN/100cm a 0-eETA IN MRAD /HR/100cm8 b, n ko mi natim - ,
/00 K.. g ,n s POINT .j AINDICATES ELECTRICAL QU LET bf h/ RESULTS ;
NORTH ? -- b e CRO PUMP A CR0 PUMP 8 l l j ! e ~ b
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CT W AT bD RHR I
/
So
- 1. SIEAR LOCAT!We CIRCLED I I .2. 00$E RATE AT LOCAf!WI TAMEN
, IN aft /Mt.
i
- 3. CIBITACT 000E RATES AT
- IN
( mR/Mt.
- 4. MTA DOSE RATE IN mRAC/NR I
J4 hO d t u'J ~r>1 hf t-hg f'
" s bO . ha c k OC#M J 5 esar/vot. vitt/Eanc-atoo i-
BRUNSWICK STEAM ELECTRIC PLANT- SURVEY NO. RADIOLOGICAL SURVEY RWP NO.
-REACTOR BUILDING #1'
-17' SOUTH R.H.R.
DATE D 3* NIME SI N D O DOSE RATE CONTAMINATION INST.- TYPE- INST. TYPE SURVEYOR SERIAL NO. SERIAL =NO. _RX POWER- EFFICIENCY REVIEWE0 BACKGROUND - j.
#A*, r Ac4, 4 inc<c u es h- '
. SMEAR RESULTS I' I O . g~ Mg. / - IN OPM/100cma 9= BETA IN MRAD /HR/100cm a POINT RESULTS A INDICATES ELECTRICAL OUTLET or1 hon 3n4kori- /00$ "b lb0Cm Q NORTH ?- @ ~\
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- 3. CONTACT DOSE RATES AT
- IN mR/NR.
4 9 ETA 00SE RATE IN mAAD/HR
^ ^
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I BRUNSWICK STEAM ELECTRIC PLANT SURVEY NO. RADIOLOGICAL SURVEY RWP NO. REACTOR: BUILDING #1 -
-17' HPCI ROOM OATEb 3'N TIME 4llIS" A230 00SE RATE CONTAMINATION INST. TYPE .
INST. TYPE
. SURVEYOR SERIAL NO.. - SERIAL _NO.
RX POWER- EFFICIENCY-REVtEWE0 OACKCAOUNO kher Ch V eN ~-
- bb C. C. IN OPN/100cm a i 9=9 ETA IN . RAD /HR/100cm a OOhrnihcho("); l00( d pry) h POINT RESUt.TS
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- 4. GETA CCSE 4 Aft IN ad40/a4 k W Y6etlL4m b(f(A f Q'e rm hjek b(en J .sima. n o.we.=
i BRUNSWICK STEAM'ELECTRfC PLANT
~
SURVEY NO.- 1 RADIOLOGICAL SURVEY _. RWP. NO. REACTOR BUILDING #1 D' -AND -17 NORTH CORE SPRAY. DATE i'b~90 TIME Ell 6 E EIO 00SE RATE CONTAMINATION' INST. TYPE- INST. TYPE , SURVEYOR ~ SERIAL NO. SERIAL NO. RX POWER EFFICIENCY REVIEWE0 -BACKGROUND [ SMEAR RESULTS, IN OPM/100cm a- r go 00h 8-BETA IN' MRAD /HR/100cm?' POINT- RESULTS , i
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= -
. NORTH _
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i i BR'JNSWICM- STEAM ELECTRIC PL ANT- SURVEY NO. RADIOLOGICAL SURVEY RWP NO.
. REACTOR BUILDING.#1 0'-AND -17' SOUTH CORE SPRAY DATE 4*3*iO TIME M *A A 3 0 DOSE RATE CONTAMINATION INST.' TYPE INST. TYPE SURVEYOR SERIAL N04 -SERIAL NO.
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]NST ' TYPE. INST.' TYPE . _
i SURVEYOR SERIAL NO. ' SERIAL NO. _ i RX power _ EFFICIENCY. . REVIEWED- BACKCROUND .__ _ l' SMEAR. RESULT 5-IN OPM/]D0cm'! ' 0= BETA IN MRAD /HR/100cm' POINT RESULTS -p _- / . 8:: n - p _ t __ 3
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BRUNSWICK STEAM ELECTRIC PLANT survey NO. ! RA010 LOGICAL $URVEY RWP N0. t REACTOR BUILDING #1 50' GENERAL AREA l i DATE b I*90f!NEM/M330 00$E RATE CONTAN!NAt!0N { INST. TYPE INST. TYPE SURVEYOR SERIAL NO. --- SERIAL NO. l RX POWER EFFICIENCY ! REVIEWED SACNGROUND l SMEAR RESULTS j IN OPN/100cm 8 - 9*SETA !N mRA0/HR/100em l 3 ._.1 PolNT RESULfs ; EifffB'uuur . - EfB t 3 ' i i
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-I SMEAR RESULTS.
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BRUNSWICK STEAM ELECTRIC PLANT SURVEY NO. , RADIOLOGICAL-SURVEY RWP NO. REACTOR ~ BUILDING #1
~l7' NORTH R.H.R.
DATE 4*340 TIMEM8/ **78N DOSE RATE CONTAMINATION INST. TYPE INST. TYPE SURVEYOR SERIAL NO. SERIAL NO. RX POWER -- EFFICIENCY REVIEWE0 SACMGROUND gh(
- b.9 SMEAR RESULTS chV,hqO / IN DPN/100cm' ;
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-17' SOUTH R.H.R.
DATE4 " 3-9 Or!ME *?m7 3/ =7 8 8 0 DOSE RATE CONTAMINATION INST. TYPE INST. TYPE , SURVEYDR .- - SERIAL NU. SERIAL NO. RX POWER EFFICIENCY-REVIEWED BACMCROUND
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BRUNSWICK STEAM ELECTRIC PLANT SURVEY NO. RADIOLOGICAL SURVEY RWP NO. REACTOR ~ BUILDING #1 1
-17' HPCI ROOM ~
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- _ EFFICIENCY REv!Ewt0 SACxCROUNO 1 i N ft*f C h '/i ( ;. 'Ob- "
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BRUNSWICK STEAM ELECTRIC PLANT SURVEY NO. RADIOLOGICAL SURVEY RWP NO. REACTOR BUILDING #1 0' AND -17' NORTH CORE SPRAY , CATE4-3*iO TIMEM11-J38D DOSE RATE -CONTAMINATION INST. TYPE INST. TYPE , SURVEYOR SERIAL NO. SERIAL NO. ! RX POWER EFFICIENCY ; REVIEWE0 GACMCROUNO
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4 BETA 00SE RATE IN mRA0/HR IN0!CATED BY A *O' h h v a c. u. a n , bwakey be,n 54u k.BSEP/R. v!!1/MRC-0100 open uf. % h .Ie d -fucj
BRUNSWICK STEAM ELECTRIC PLANT SURVEY NO.' i RADIOLOGICAL SURVEY RWP NO.- l REACTOR BUILDING #1 i O' AND -17' SOUTH CORE SPRAY h l DATE M M O TIMEM3/*EM 005E RATE CONTAMINAT10N INST. TYPE INST. TYPE SURVEYOR SERIAL NO. SERIAL NO. RX POWER EFFICIENCY _ REVIEWED BACKCROUND j
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IN-PLANT RADIOLOGICAL CONDITIONS AFTER'2330
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I ERUNSWICK'5 TEAM ELECTRIC PLANT sveyty u- ! RA010 LOGICAL SURVEY RWP NO. ! REACTOR BUILDING #2 ! 20' CENERAL AREA t DAtt 4-8"9071ME A D 330 00SE RATE CONTAMINAI!CN lNS T. TYPE I NE T. TYPE . SURVEYOR SERIAL NO. SERIAL NO. _ - ! RX POWER EFFICIENCY , REvltvCD BACKCROUND - i SMEAR RESULTS [ IN OPM/100cma 1 S*SETA IN MRAD /HR/lDoem , POINT _RESULTS I E in - _ . 5 t _= ,=_
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BRUNSW3CK STEAM ELECTRIC PLANT SURVEY NO. RADIOLOGICAL SURVEY RWP NO. REACTOR BUILDING #1 50' GENERAL AREA DATE 4 ~ 3* DIME NMOO '00SE RATE CONTAMINATION INST. . TYPE INST. TYPE _ SURVEYOR SERJAL NO. SERIAL NO. i RX P0tER . EFFICIENCY REVIEWE0 BACMGROUND SMEAR RESULTS RCS IN DPMd 00cm8 f"-_ - 1 Samh 6'd 9=9 ETA IN mRA0/HR/100ema POINT RESULTS Ull.ll.L ' ' i i m 7--'- MO
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- 2. DOSE RATE AT LOCATION TAKEN IN mR/Mt.
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- IN ,
mR/NR.
'4 BETA DOSE RATE IN MRAD /HR INDICATED BY A *B' esE#/VOL.:VI!!/ELRC-0100 t .1.n c r t O S 6 du c. k YAcu.M,m brf alm r be i; t,4u c4 l h ;p , , gn, l,g4 '
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7 BRUNSWICK STEAM ELECTRIC PLANT SURVEY NO. RA010 LOGICAL SURVEY Rue No. REACTOR IBUILDING #1 9' & 20' NORTH AND SOUTH RHR ROOMS DATE M S TINE AN KE33D 00$t RAff CONTAMINATION INST. TYPE INST. TYPE SURVEYOR SERIAL NO. SERIAL NO. -- RX POWER EFFICIENCY - REY!tWED BA W " SMEAR RESULTS 20' N.RHR 80' S. RPM IN (FM/lha gggg gg ggjgga , r , 1 POINT RESULTS=
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BRUNSWICK STEAM ELECTRIC PLANT SURVEY NO. RADIOLOGICAL. SURVEY RWP NO. REACTOR BUILDING'#1
-17' NORTH R; H. R.
DATE b3-Y0rlME d#Th J30 DOSE RATE CONTAMINATION INST. TYPE - l NS T. TYPE
--SURVEYOR SERIAL NO. . SERIAL NO.
RX F0WER EFFICIENCY REVIEWED BACKGROUNO gh ,d . O E - i gCi SMEAR RESULTS-- y',]j~ g j IN O F '100 cme
/ 9=9 ETA IN mRA0/HR/100 cme A INDICATES ELECTRICAL QUTLET / POINT RESULTS- $ Ot k ryh 13 6 h EFT . 7l dEM -
4 ~iooce,4-NA1 NORTH -> Q( b 7rn00\ .) *Eoo S CRO PUMP- ! A CR0 PUMP O 000 o ,
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- IN mR/HR.
i 4 DETA DOSE RATE IN edtAD/HR INDICATED BY A *O* l T M Cf(CL M d LLC. b \CLc.u,R f m bfcA, b t' h'sn $4gc k I
- II
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BRUNSWICK' STEAM ELECTRIC PLANT SURVEY NO.
. RADIOLOGICAL SURVEY RWP NO.
REACTOR. BUILDING #1
-17 SOUTH R.H.R.
DATE.4-4*90 TIMENTE4 E3S - DOSE RATE 'CONTAMINAT!DN INST. TYPE }NST. TYPE. SURVEYOR SERIAL NO. SERIAL NO. RX POWER EFFICIENCY REVIEWED BACKCROUND Air /cey;ft :. R. JE 'ipji/ c, - SMEAR RESULTS
- IN DPM/100cma.
\ bt1 at,,1Jh y = 7 _
g B=9 ETA IN MRAD /HR/100cm'
\ 60CM PDINT RESULTS-
\
A INDICATES ELECTRICAL DUTLET Wikd , ( hr , Q NORTH > 00 - l/ I' l RetOf 1
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I 1
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- IN mR/HR.
4 DETA DOSE RATE IN MRAD /HR INDICATED SY A *t*' BSEP/VOL. V111/E&RC-0100 I ANer R5+5 Reduce. Rad Leveb g,' s ; t u ni n i ics, v
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l GRUNSWICK STEAM ELECTRIC PLANT SURVEY NO. RADIOLOGICAL SURVEY RWP NO. REACTOR BUILO!NG #1
-17' HPCI ROOM OATE b3*N T!wg /#tarr. 433D DOSE RATE CONTAMINATION INS T. TYPE INS T, SURVEYOR
_. TYPE SERIAL NO. SERIAL NO. - RX POWER REv!EWED -- - EFFICIENCY - SACMCRouMD - SMEAR RESULTS IN OPN/100cm a BatETA IN e4AD/HR/100c= 8 POINT 4ESULTS 6$ & a ,
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/ 0 0, 60 $60
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- IN
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T BQUNSdlCK STEAM ELECTRIC PLANT RADIOLOGICAL SURVEY $URvtY no. -. RWP NO. REACTOR BUILDING #2 0' AND -17' NORTH CORE SPRAY DATE .k"F90 TIME law ~ AJJD 005E RATE CONTAMINATION INST. TYPE INST. TYPE SURVEYCR SERIAL NO. SERIAL NO. RX POWER --- EFFICIENCY REVIEWE0 BACRCR0VNO k l [ SMEAR-RESULTS IN DPM/100cm a B=0 ETA IN MRAD /HR/100e, P0lNT RESULTS Z3 % _= NORTH
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ace ' + M U
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- 1. CONTACT CC$t RAT (5 AT * !N mR/HR.
4 BETA 00$t RA!2 in =RAC/r4
!N0!CATED SY A "B" f k h Yott tLLLrd Df MLKO I De in A 6hrCh 0$tP/v0L VI!!/ttRC.C;CC ofe n og operah c d% $6kd h(,f %daC%<9wJ
BRUNSWICK SidAM ELECTRIC PLANT SURVEY NO. RADIOLOGICAL SURVEY RWP NO. REACTOR BUILDING #1 0' AND -17' SOUTH CORE SPRAY t DATE 4* I *90 TIME bEm 433D DOSE RATE CONTAMINATION INST. TYPE INST. TYPE SURVEYOR SERIAL NO. SERIAL NO. _ RX POWER EFFICIENCY REVIEWED BACKCROUND _y SMEAR RESULTS
=( ./'*'y * 'y k. ); 44b'[cc,,
IN DPM/100cm8 B BETA IN MRAD /HR/100cm8 {1A PDINT RESULTS O t N 'l n i - 1 > s ' *
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= NORTH
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= 19 %
=
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=
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600
/
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- IN mR/HR.
g N 4. BETA 00SE RATE 2N MRAD /HR
!NDICATED BY A *8*
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- Mfer u s 4r. Pvmes Mof v l
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I r BRUNSWICK. STEAM ELECTRIC PLANT SURVEY NO. f RA010 LOGICAL SURVEY- RWP NO. l UNIT 1 TURBINE BUILDING 20' CONDENSER BAY - OATE +*3'TO TIME W O '/ DOSE RATE CONTAMINATION INST. TYPE INST. TYPE { SURVEYOR SERIAL NO. SE8%!AL NO. - [ RX POWER EFFICIENCY j REVIEWED SACKGROUND { SMEAR RESULTS IN DPM/100em8 f 0 9 ETA IN MRAD /Wt/100ess . POINT RESLt.,TS ,
- a. -_ :-
O' $5
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- IN anna. .!
- 3. ClptTACT ININ RATES AT
- IN -l anna. 1 I IIII ,,,,,,, 4. gETA 000E RATE IN mRADam . .l 3 Ile!CATED BY A *t'
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SED /YOL. Yl!!/EERC-CIOD 4 I
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l BRUNSWICK STEAM ELECTR2C PLANT SURVEY NO. RADIOLOGICAL SURVEY RWP NO. ; UNIT 1-TURBINE BUILDING ; 45' CONDENSER BAY DATE M
- N INE A 9 00SE RATE CONTAM] NATION INST. TYPE INST.. TYPE . , -
SURVEYDR SERIAL NO. SERIAL NO. -- RX POWER EFFICIENCY ; REVIEWED BACMOROUNO l SMEAR RESULTS -; N ! $!! 1N OPM/100ca' 9 8 ETA IN MRAD /NR/100cm8 j i EHC POINT REsais 0 ogoo = 3
.J . . -l Ecco -
2000 Accc) -- O a I j- /\ 4 NDRTH \ l CONDENSER l l l 8 l- d ELECTRICAL OUTLET " l kgT [cMy; --
'3 ' 'I6 ~ a0)
( l. SutAR LOCATION Cl#CLED I
- 2. DOSE RATE AT LOCAf tlM TAMEN O MJOdhC()L OO k d f01
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U/1 T4 20' Roces Off treeseway j l - l l DATE: ' '/ T d - TIME: 13'IC MSE RATE: CONTAMINATION: I INST. TYPE: INST: 1-SURVEY BY: _ _ _ _ SERIAL N0: EFF ; REVIEWED BY: REACTOR POWER: BKG: j l IIIIIIII1II SNr.AR RESULTS' ) l
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NOTES: (1) Dose Rate Readings: General Area Readings are to be indica. l ted in mR/hr at the location taken. Contact readings are j
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(2) Contamination Results: Recorded in DPM/100 cm'. ~ Indicate
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j BSEP/Vol. VIII/E&RC-0100
. . - ~. . . . , _ . - _ _ . _ . . . . _ _ . . _ _ . _ . . . . , . . _ . _ . , . _ _ - .
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SRUNSWICK STEAM E1.ECTRIC PLANT Surysy No. . RWP No. l RADIOLOGICAL SURVEY i Unit i 70' Turbine Bay j DATE: Y"3 #1 O TIME: 7 3 3 C +D0st RATE: CONTAMINATION: INST. TYPE: INST. 4
, SURVEY BY: SERIAL WO EFPt !
I . REVIEWED BY REACTOR POWER: BKG ! 4 5 SMEAR RESULTS i j -Foint DFN/ID0ca8 L. P. - -
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h t I NOTES: (1) Dose Rate Readings General Area Readings are to'be indica- l ted in mR/hr at the location taken. Contact readings are j l to be indicated in mR/hr and denoted with an asterisk (*). I I (2) Contamination Results: Recorded in DPM/100 cm . Indicate 8 and circle location. i BSEP/Vol. VIII/E&RC-0100 .j l :- ,
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- BRUNSVICK CTT.AM ELECTRIC P1. ANT !
Surv2y No. ! RADIOLOGICAL SURVEY RWP No _. ! 70' Turbine Deck Interface { t DATE: h3-40 TDE: ' 233C+D0$t RATE: COIrTAMIIKTries_ INST. TTFEt INST. ! SCIftY BY: SERIAL N0t EFFt IETIEVED BY . REACTOR POWERt .SECr
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- I 4 i I ' NOTES: (1) Dose Rate Readings: General Area Readings are to be indica-ted in mR/hr at the location taken. Contact readings are to be indicated in mR/hr and denoted with'an asterisk (*). (2) Contamination Results: Recorded in DPM/100 cm' . Indicate, and circle location.
' 1 1
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BRUNSWICK STEAM ELECTRIC PLANT Survoy No. RADIOLOGICAL SURVEY P No. Unit 1 Turbine Building -- Heater Drain Pump Room DATE: k 9 C) TIME: U d O iOSE RATE: CONTAMINATION: INST. TYPE: INST: _ SURVEY SY SERIAL NO: ' _ EFF RAVIEWED $Y: REACTOR POWER: BKG: ) ef L */ e ) ".,* , . he h {. j t i SMEAR RESULTS-boiko m'i na Nhn 7 I M , g ,' Point .DPM/100 CM8 )- b{ . 1 i i l0,Na -g
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brunswdN' REP Revisi:3 20- . TABLE 5.7-2 AREA RADIATION NONITORING STSTEM CHANNEL IDENTIFICATION & METR.R RANGES Range Detector 70 d ' t ' . , Channel (mR/hr) Designation Location'(Blda.) p ; 1-1* 0.01 - 100 Control Room Operating Area Control 1-2* 0.01 - 100 U-2 Electronic Equipment Roos ** Control 1-3* 0.01 - 100 U-1 Electronic Equipment Room ** Control l-4* 0.0 - 100 Stack Filter House Stack i 1-5* 0.01 - 100 Service Bids. Radiochemical Lab. Service 1-6* 0.01 - 100 Service Bldg. Locker Room Service l 1-7* 0.1 - los Hot Machine Shop Service -l 1-8* 0.01 - 100 Service Bids. Laundry Service
. I 1-9* 0.01 -'100 U-1 Turb. Hall Control Access Turbine. 1 Corridor 1-10* 0.01 - 100 U-1 FW Heater Bay Accosa Corridor Turbine !
1-11 0.1 - 100 U-l Turb. Bids. Sampling Station Turbine *1 .a j i 1-12 0.1 - 10s U-1 Turb. W Moist Sep. Dran Tanks Turbine' .Q. l l l-13 0.1 U-l Turb. F Molst Sep. Drain Tanks Turbine i1
- 108 -
1-14 0.1 - los Uel Turb. Rotor Washdown Area Turbine I J j 1-15 0.1 - 108 1A Core Spray Pump Room ESS I Reactor M l 1-16 0.1 - 108 IB Core Spray Pump Room ESS II ' Reactor M 1-17 0.1 - 108 1A RHR System.Hx and Pump Room Reactor A0 ESS I ] 1-18 0.1 - 10s 1B RHR System HX and Pump Roon Reactor RO - ESS II ! 1-19 0.01 - 100 U-1 Rx BIdg. Airlock EL 20 ft. Reactor 5 . 1-20 0.01 - 100 U-l'Drywell Entrance Reactor 10 1 1-21 1.0 - 10 4 U-1 TIP Room Reactor k5 bo d i ,
- Radiation level signals supplied to common area recorders, i
** Detectors are located in mechanical equipment room (Control Building 'j ventilation air incake casing) l; 5- 14
. . . . . . . . . . _ _ .. .. 9
Bru= wick REP Revisisn 20' TABLE 5.7-2 (cont'd) AREA RADIATION MONITORING SYSTEN [ CHANNEL IDENTIFICATION & METER RANGE 8 Ru, ' Range Detector - Channel (aR/hr) Desianation Location (51da.)l7, 7 1-22 0.01 - 100 U-1 Decontas. Room EL 20 ft. Reactor 5 - 1-23 0.01 - 100 U-1 Equipment Entry EL 20 ft. Reactor $ i 1-24 0.01 - 100 U-1 Rx Bldg. Sampling Station' Reactor- lD , 1-25 C.01 - 100 U-1 Rx Bldg. Air Lock EL 50 ft.. Reactor .tO 8 in. > ! 1-26 0.01 - 100 U-1 New Fuel Vaulq EL 98 ft;, Reactor A5 6:;) 9 in. . . 1-27 0.01 - 100 U-1 North of Fuel Storage Fool Reactor AS k[ 1-28 108 - 106 U-1 Betvean Rx and Fuel Fool Reactor % u.)n g ;. L EL 117 ft., 4 in . " 1-29 0.01 - 100 U-1 Cask Wash Area Refuel Floor Reactor k5 ' h C l 1-30 0.01 - 100 U-1 Spent Fuel Fool Cooling Reactor . bs EL , ' Systes l
. l t
i {
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.O 5-15
q 8 tun: wick REP i Revis1c:2 20- .i TABLE 5.7-2 . AREA RADIATION NDNITORING STSTEN l CHANNEL IDENTIFICATION & METER RANGES I Range Detector i I Channel (aR/hr) Desianation Location (Blda.) t
'i 1-1* 0.01 - 100 Control Room Operating Area Control' l
1-2* 0.01 - 100 U-2 Electronic Equipment Room ** Control 1-3* 0.01 - 100 U-1 Electronic Equipment Room ** Control-1-4* 0.0 - 100 Stack Filter House : Stack l 1-$* 0.01 - 100 Service Bids. Radiochemical Lab. Service j 3 1-6* 0.01 - 100 Service Bids. Locker Room Service 1-7* 0.1 - 10s Hot Machine Shop Service l
- 1-8* 0.01 - 100 Service Bldg. Laundry . . Service .
1-9* 0.01 - 100 U-1 Turb. Hall Control Access Turbine
- Corridor 1-10* 0.01 - 100 U-1 FW Heater Bay Access Corridor -Turbina 1-11 0.1 - 100 U-1 Turb. Blds. Sampling Station Turbine *Q '
1-12 0.1 - 10s U-1 Turb.=W Meist.Sep. Dran Tanka Turbine
- C.
1-13 0.1 - 10s U-1 Turb. E Moist Sep. Drain Tanks .Turbina ' S . 1-14 0.1 - los U-1 Turb. Rotor Washdown Area Turbine T 1-15 0.1 - 108 1A Core Spray Pump Roon ESS I Reactor kO 3 1-16 0.1 - lo s l'B Core Spray Pump Room ESS II Reactor -40 1-17 0.1 - 108 1A RRR Systen Hx and Pump Room Reactor 4O ' ESS I 1-18 0.1 - los 1B RER System EX and Pump Roon ESS II Reactor hO 1-19 0.01 - 100 U-1 Rx Bldg. Airlock EL 20 ft. Reactor 10 1-20 0.01 - 100 U-1 Drywell Entrance Reactor 10 1-21 1.0 - 104 U-1 TIP Room Reactor k h@d -
- Radiation level signals supplied to common area recorders.
** Detectore are located in mechanical equipment room (Control Building ;
ventilation air-intake casing)
- 1 ,
- i 5-14 j'
i l - -
W 3] ~*dOO U j Brunswick REP l Revisica 20 t ! TABLE 5.7-2 (cont'd) ARIA RADIATION MONITORING SYSTEN [ CEANNEL IDENTIFICATION & NETER RANGE 8 Range Detector Channel (aR/hr) Desianation Location (Blda.) l 1-22 0.01 - 100 U-1 Decontaa. Room EL 20 ft. Reactor I0 t . ! 1-23 0.01 - 100 U-1 Equipment Entry EL 20 f t. Reactor l0 l
- 1-24 0.01 - 100 U-1 Rx Bldg. Sampling Station Reactor {f 1-25 0.01 - 100 U-1 Rx Bldg. Air Lock EL 50 f t.. Reactor iI j 8 in.
1-26 0.01 - 100 U-1 New Fuel Vaulg. EL 98 f t. , Reactor kS.b6 i 9 in.
- 1-27 0.01 - 100 U-1 North of Fuel Storage Fool' Reactor k*
1-28 108 - 10' U-1 Between 'Rx and Fuel Fool Reactor )CWr) SCo , EL 117 f t. 4 in.
- 1-29 0.01 - 100 U-l' Cask Wash Area Refuel Floor Reactor 6 had
- 1-30 0.01 - 100 U-1 Spent Fual' Fool Cooling Reactor ksh/1 l System ,
i I l i , l l \ l il 6 5-15
bruiswick REP ! Revisisa 20 'l TABLE 5.7-2 l . AREA RADIATION MONITORING SYSTEN ; CHANNEL IDENTIFICATION & METER RANGES . Range Detector blo dl . .o j l Channel (aR/hr) Desfanstion Location (Blda. J (,4 { 1-1* 0.01 - 100 Control Room Operating Area Control ; ~ 1-2* 0.01 ,100 U-2 Electronic Equipment Room ** Control-1-3* 0.01 - 100' U-1 Electronic Equipment Room ** Control f 1-4* 0.0 .100 Stack Filter House Stack' 1-5* 0.01 - 100 Service 51ds. Radiochemical Lab. Service 'i 1-6* 0.01 - 100 Service Blds. Lcc,ker Room Service i 1-7* 0.1 - 108 Hot Nachine Shop Service -j i 1-8* 0.01 - 100 Service Bids. Laundry . . Service , _i 1-9* 0.01 - 100 U-1 Turb. Hall Control Access Turbine - 4 Corridor 1-10* 0.01 - 100 U-1 FW Hester Bay Access Corridor Turbine ; t l 1-11 0.1 - 100 U-1 Turb. Bids. Sampling Station Turbine
- 3~ .;
j 1-12 0.1 - 10s U-1 Turb. W Moist Sep. Dran Tanka Turbine 3 av s U-1 Turb. E Meist Sep. Drain Tanks Turbine ~1. 0 0 i 1-13 0.1 - lo 1-14 0.1 - 10s U-1 Turb. Rotor.Washdown Area Turbine 3 t k, r';c.. l 1-15 0.1 - 108 1A Core Spray Pump Room ESS 1 Reactor 06W ; 1-16 0.1 - los 18 Core Spray Pump Roca ESS II- Reactor C S R ; 1-17 0.1 - 10s 1A RHR Systen Rx and Pump Room Reactor osy ESS I l l 1-18 0.1 - 10s 1B RHR Systen HX and Pump Room Reactor OW .
- ESS II l
1-19 0.01 - 100 U-1 Rx Bldg. Airlock EL 20 ft. Reactor OSk q l 1-20 0.01 - 100 U-1 Drywell Entrance Reactor 0LH l
'l-21 1.0 - 10" U-1 TIP Room Reactor A s- 4 tom )
- Radiation level signals supplied to common area recorders.
** Detectors are located in mechanical equipment' room (Control Building ventilation sir intake casing)
, p 4
5-14 li
Revisitai20 TABLE 5.7-2 '(csnt 'd) AREA RelilATION NONITORING SYSTEN
,i( .
CliANNEL IDENTIFICATION & METER RANGES . Range _ . Detector ] pod;, q Channel (aR/hr) Desianation~ Location (BIda.)(Mkl 1-22 0.01 '100. U-1 Decontaa. Room EL.20 ft.- . Reactor Cys 4 1-23 0.01~--100 U-l'2quipment Entry EL 20.ft. Reactor o sq 1-24: 0.0' s 190 U-1 Rx Bldg. Sampling Station- . Reactor ~ 656.} 1-25 0.01 100 U-1 Rx Bldg.-Air Lock EL 50 ft., Reactor ~ C f44 8 in. 1-26 0.01 - 100 U-1 New Fuel Vault EL 98 ft., Reactor, ds h 9 in. 0.01 - 100 U-1~ North of Fuel Storsge Fool' Reactor' kb b ol.c
~
1-27 Reactor' h t4n co.a
~
1-28 108 - 106- U-1 Between Ex and Fuel Pool' EL 117 ft., 4 in. 1-29 0.01 - 100. ~U-1 Cask Wash' Area Refuel Floor Reactor'Ns h - 1-30 0.01 - 100- U-1l Spent Fuel Pool Cooling Reactor- A.. Read Systen-o 5 * = J P'f* *I* #1Y' U 5-15
, - . . . ~ ~ ~- - - - . ,
WEATHER SCENARIO e A stationary front is located south of the Brunswick Plant today.- This front - stretches' from the central, coast of South Carolina to a weak low pressure- s center in eastern Tennessee'
~
Weak high pressure. is located in New England.. Variably cloudy skies previal- in the plant vicinity. as' southeast winds north'
~
of the stationary front continue to pump _ moisture inland. - Although moisture: will increase, no' precipitation is~ expected since the front is weak and little-motion is expected for the next twenty-four hours.. h
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Carolina Power & i.ight Company : ONSITE METEOROLOG IC A L DATA Date: Acr;) I / 990 Brunswic t Time (EDT) / Roo /*'/5 /ffSO /8'yS~ . c Upper Speed (mph) h. 7 / h, / / /O, O/' f,9 / J apper Direc. (Dro) 97 $Y iY 7d
~
Lower Speed (mph). d, k / [r O / (( ,3/' Lower Direc. (DEC) kb 77- f} p/ p
- a remp. c r) 60. P 62.9 62.O 6/,6 '
l r ( c/toom) -/.49 7/,37 -/ . 2 3 -/./9 1 stability class O h O O une (Ear) 1900 l9/r 1930 l9 4r Upper Speed (mph) 7. 9 / 7[/ 7,3 / /0.0 / . Upper Direc. (DEG) 90 93 7 '/ 93 i Lower Speed (mph) 4.3 - 3 . o' f.3 E/
- tower Direc. (Dro) '70 9O 73- fO_
m Temp. < r) 40, b bo. 4
- . '59.9 D.s j T ( c/ loom) 0.97 ~ D. % -0,7 ? 0. ToS
! Stability class b O b b i !- l
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Carolina Power & Light Company j ONSITE METEOR OLOG IC A L . DATA ;
; Dates Anr;) 3. /990 A ruu w se k. '
Time (&ff 2000 2O lb l2030 .20 Yf l Upper Speed (mph) h,7 / 9,7 / h, 7 / 8, f / Upper Dirac. (DEG) 9f kh _ Lower Speed (mph). 3.4 / - d.de/ 3,3/ :
- 7. O i _
Lower Direc. (DEG) 93 ) 7h ,y[ _ m Temp. ( r) 58.6 89. / ff,2 SP. / r ( c/ loom) - D. 59 O,60 - O, 6 /, ' -o,7c Stability Class O O O O Time (G f 0}D O 2) }[ Ql3D Q)yf l Upper Speed (mph) /M 0/ . . _ $7/ k, p / f,[/ Upper Direc. (DEG) /0 (O [h f //[ Lower Speed (mph) 3.f O,F 3.0 3.2 Lower Direc. (DEG) kh /O Y 'k7- /Cf a remp. < r) d. 4 M,o (7, / (f. O f T ( c/ loom > 'O . 73 -O,11 - D% - 0,9f
- Scability class D D l) O F
e w = w -e-w,. -,--,..--*#,i, e-. --,-...-,e-.-+aw *P-ve'r-w'- e'w"*=v-e ergye- ~ww'
b
~
Carolina Power & Light Company ONSITE METEOROLOGIC A L DATA Date: M/)t i i 8, /9hO ' Bruntoick. Time (EDT) 22O O 22lh~' 2D3O 22 Yh
~
Upper Speed (mph) Y/ ,Y / f.3/ /O. O / Upper Dirac. - (DEG) //9 //7 f.T ' /3O-Lower Speed (mph). 3. 3 / 3.3 / F. o / 3.6/ _ Lower Direc. (DEC) / // //h' h7 /27 am Temp. ( r) 69, Y 59. 6 59.7' , 59.9 ' T ( c/100m) ~[ O[ -/,OC ~/, O 7 '/, O 6 Stability Class b- _ [] b Time (E0n ,-2 3o o 23/f _ J 3 30_ 0 3 f'o'~ Upper Speed (mph) ' 9. 6 / /O,0/ 9.3/ 9. 7 / - . i Upper Direc. (DEG) /39 B9 /24 /29 . l Lower Speed (mph) 3.9 . 3.3 /, k j-i tower Direc. (DEG) /33 /25 ' // 7 /s/ j l AMB Temp. ( F) , hd. k [o D. 2 ' [g b , O hO,2 1
- T ( c/100m) ' /, /D -~/, D / -D, 97 '/, D O ll j
s Stability Class b b b b _ 4
~ Carolina Power & Light Company ONSITN METEOR OLOG IC A L DATA O
Dates Anr;} 41990 LG,wa n k. Time (Go n o000 in u .cou r o10 0 Upper Speed (mph) (m/s)' h.//- 7, /
/03/ /J3/
1
- Upper Direc. . (DEG) -/3 V 33 /3f /n
- Lower Speed (mph).'(m/s) /. 3 / OS/ 2.3 / 2. (t
/57 Lower Direc. (DEG) ) O (o /.1h -/38~
l ' AMB Temp. ( F) /50.Y b, i }
- h. Nh, l T ( C/100m) - O . 9[o ~C.6/ ~'
. Y2 -A.O/
{ Stability Class O _ D E~ $ i Time ( ) Upper Speed (mph) (m/s) / / / / . Upper Direc. (DEG) Lower Speed (mph) (m/s) l l Lower Direc. (DEG) -
- AMB Temp. ( F) i T ( C/100m)
! Stability Class i 1 l l
L CD&L Carolina Power & Light Company r METEORG LOGICAL- FORECAST FORM Date: Of[ , /hkO Time issued: /hddhDE
~l Issued By: Received By:-
l Forecast Locattont f'A A6 u)il N i ? l A) Next 1 Hour ! 1) Wind Direction: Sector Deg. DhF
- 2) Winds Should Remain Shifting; Variable)
! -2a) Variation Should Be $ /O Deg.
- 3) Wind Velocity: h- to /O (MPH) b
- 4) Stability Class
- 5) Precipitation Activity Will Be Scattered, Steady) '
- 6) Precipitation Type (Rain, Rainshowers, Thunderstorms, Ice, Snow)
- 7) Precipitation Intensity (Light, Moderate, Severe)
B) Next 3 Hours: k);mde E-ESE* D9f* 7 -/O m ck ' 5+d;}L I D fhf2Oa - , . b -- l-C) Remarks: h e h k o,p y- {}}hpm [jg f Qwg c
- ~
4 A e
--
- r t e v+--ww----+----w -vw =* *.-ww- '-v v+ -e.--ee-e,*e=<=.. . - . , = * =~-a.-*i. . - - - , - - - * , . * * - ----*-+s
~'
Carolina Power & Light Company METEO RO LOGIC A L FORECAST FORM Date: l M) '
, NfC Time Issued: //dO EDF i
\
Issued By: _ Received Byt Forecast Lo:ations flJrMf23lfY A) Next 1 Hour
- 1) Wind Direction: Sector Deg. hhD ,
- 2) Winds Should Remain Shifting; Variable) j 2a) Variation Should Be f/O Deg. "
- 3) Wind Velocity: 7 to /O WPH) )
- 4) Stability Class. O
- 5) Precipitation Activity Will Be Scattered, Steady)
- 6) Precipitation Type (Rain, Rainshowers, Thunderstorms, Ice, Snow)
- 7) Precipitation Intensity (Light, Moderate, Severe)
-i B) Next 3 Hours:
u>;nd: E-sE //o
- 2-tompk SM: Mv: D Penio': A%e C) Remarks: f (.A.)W he $y91 blr h/)G) h
.}
Carolina Power & Ligitt Company: } METEO R O L O GIC A L: FORECAST. FORM I i
'l Date:
r Br) 1/hb
.c Time Issued: VM'EDT '
J Issued By: . Received By: t Forecast Location: rum 36d[LN 1 r A) Next 1 Hour
- 1) Wind Direction
- Sector [ Deg. h
- 2) Winds should Remain (Steady; '
2a) Variation Should /O: Be I (hifti3 Variable) D eg'. - i
- 3) Wind Velocity: h to- /O _(MPH) l
- 4) Stability Class O ,
! 5) Precipitation Activity Will Be Scattered,-Steady)
- 6) Precipitation Type (Rain,.Rainshowers, Thunderstorms, Ice, Snow)
- 7) Precipitation Intensity (Light, Moderate, Severe)
B) Next 3 Hours: - v e nd '. ESE- CE M* P-/D mp h \ $+oML : D i Prec;b : Ano l \ C) Remarks: h$ (A)$f $6 GVM .MK De w n l t
-, .-- ...s_.. . . . , - . _ _ . , _ , . . _ . . . . . . . . , ,.-.-,.,v,..-.. . . . , . . . . . . , ,
Sp&L Carolina Power & Light Company l
. ME TEO R O L.O GIC A L FORECAST FORM Dates for q
31r 990 Time Issued: 2/coEcr i Issued By: Received-By.: Forecast Location: b h > Mali)[6 k - i A) Next 1 Hour
- 1) Wind Direction: Sector -E-ESE -Deg.: //O
- 2) Winds Should Remain -(Steady; Variable) 2a) Variation Should Be I/[ Deg.
- 3) '.Jind Velocity: h tc j O _ (MPH)
O t
- 4) Stability Class l 5) Precipitation Activity Will Be Scattered, Steady) E l
- 6) Precipitation Type (Rain, Rainshowers, Thunderstorms, Ice, Snow)
- 7) Precipitation Intensity (Light, Moderate, Severe)
B) Next 3 Hours: V;ad i ESE- s'E mf 9-/om,A 6tnan : D -
- (
i l c> R arus, Mco t % user Modom 1.;,, k Dou> n c , 4 O
Carolina Power & Light Company i METEO RO L OGICA L FORECAST FORM u Date: /)/i h. fhhO Time Issuedt. MOO [Of I Issued By: Received By: Forecast Location: r(J/Klu[Lb
'l A) Next 1 Hour
- 1) Wind Direction: Sector [ $ d - $ [ Deg. /2D
- 2) Winds Should Remain (Steady, Variable)
/C 2a) Variation Should Be Deg..
- 3) Wind Velocity: k to /O (MPH)
- 4) Stability Class , O
- 5) Precipitation Activity Will Be Scattered, Steady)
- 6) Precipitation Type (Rain, Rainshowers. Thunderstorms, Ice, Snow)'
- 7) Precipitation Intensity (Light, Moderate, Severe) !
B) Next 3 Hours: khd : S E' /3s 9- 12 mp h Akhkr D-E I ' I8 C OI bdb I C) Remarks: ffl9Y fbb}9r h pp% [jg f y,jn 1 1 1
(W Carolina Power & Light Company I METEO RO L OGICAL FORECAST FORM Dates' M b h, /990 Time Issued:. [3008Of I f Issued By: Received By: ' i Forecast Locations fuM t2j /LM : i i i l
- A). Next 1 Hour '
c
- 1) Wind Direction: Sector SE Deg. 13 O
- 2) Winds Should Remain (Steady; (hif tinD Variable) l 2a) Variation Should Be I /0 Deg.
l 3) Wind Velocity: [ to /b (MPH)
- 4) Stability Class O
- 5) Precipitation Activity Will Be Scattered, Steady)
- 6) Precipitation Type (Rain, Rainshowers, Thunderstorms, Ice, Snow).
- 7) Precipitation Intensity (Light, Moderate, Severe)
B) Next 3-Hours: Vlind : SE MO * (f"/3 nw h s+ob;My : D- E
&eclc: Alone C) Remarks: h fou.)Pf kb @pf1 )nkDAu)n 4
Carolina Power & Liglet Conspany METEO R O L O GIC A L FORECAST FORM: Date #$ f :h, /970 __ Time Issued: OddC gD{ f ./ Issued By: Received By: j l
' Forecast Location: T/1HS&J [6b i
.l A) Next 1 Hour
- 1) Wind Direction: Sector b[ Deg, ') 3 f~ ,
- 2) Winds Should Remain
=
Shifting; Variable) 2a) Variation Should.Be f/O 'Deg. I
- 3) Wind Velocity: to /2 (MPH)
- 4) Stability Class S-[
- 5) Precipitation Activity Will Be cattered, Steady)
- 6) Precipitation Type (Rain, Rainshowers, Thunderstorms, Ice, Snow)=
q
- 7) Precipitation Intensity (Light, Moderate, Severe) ~'
i B) Next 3 Hours: Ah SE- SSE Iys' V/Ymph
%khL r E- 5 i
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, , F. Sunny Point Pump Station, Mwy 47 N .
testme88 2 , c. Plume :enterline, Nwy 87
,g \ / l H. Morth Side of Nwy 8?, .1 al N of Hwy 133 i % / a 1. South Side of Nwy $7, .7 si N of Hwy 133 g#/ e Mvy 07, .5 mi 18 cf bridge g,% e' j J.
K. Acrose from trurovick Middle School 9 Inter of 04tewebe Rd.
'- L. End of dir? Ad acrose frr's Middle School s e j M. Intersection of Fifty takes Dr. 6 Hwy 87 v 8 N. Plume centerline, .1 mi free intersection Hwy 87
# 8,- 8 C. Intersectiert of Hwy 07 6 Fairway Rd.
,g, P. Intersection et lTairway Rd & Windemore Dr.
@ uus # Q. Plume Centerline, Inter. W Deiling Springs Rd.
, . , W 4J#,
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$ ,O ,,, S. Brunswick County water tower
,\ Hwy 87 9 Mill Creek taptist Miss. Ch.
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