ML20147F097
| ML20147F097 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 02/24/1988 |
| From: | GULF STATES UTILITIES CO. |
| To: | |
| Shared Package | |
| ML20147F074 | List: |
| References | |
| NUDOCS 8803070235 | |
| Download: ML20147F097 (65) | |
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1988-EMERGENCY PREPAREDNESS EVALUATED EXERCISE FEBRUARY 24,1988 0
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RIVER BEND STA'IlON 1988 EMERGENCY PREPAREDNESS EVALUATED EXERCISE
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TABLE OF CONTENTS Page PARTI GENERAL INFORMATION
1.0 INTRODUCTION
1-1 2.0 SCOPE AND OBJECTIVES 2.1 Scope 2-1 2.2 Objectives 2-1 2.3 Simulations 2 3.0 EXERCISE INFORM ATION 3.1 Conduct of the Exercisc 3-1 3.2 Precautions and Limitations 3-2 4.0 CONTROLLER INFORM ATION 4.1 General Information 4-1 4.E Controller Instructions 4-1 4.3 Evaluation Instructions 4-2 4.4 Personnel Assignments 4-3 5.0 PL AY.7.R INFORMATION 5.1 General Information 5-1 5.2 Player Guidelines 5-1 G0 SCIIEDULE OF EVENTS 6-1 O
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. RIVER BEND STA'I10N -
'1988 EMERGENCY PREPAREDNESS EVALUATED EXERCISE TABLE OF CONTENTS (Cont.)
Page PART II SCENARIO INFORMATION 7.0 EXERCISE SCEN ARIO
' 7.0 7.1 Scenario Timeline 7.2 Master Events Summary 7.3 Trend Sheets 7.4 Assumptions 8.0 MESSAGES AND PLANT DATA SIIEETS 8.0 8.1 Messages 8.2 Supplemental Scenarios 9.0 ONSITE RADIOLOGICAL AND CllEMISTRY DATA 9.0 9.1 Plant Chemistry Data 9.2 Inplant Radiological Data 4
10.0 OFFSITE RADIOLOGICAL DATA 10.0 10.1 Release Data 10.2 Meteorlogical Data 10.3 Survey Data 10.4 Iodine Deposition Data 10.5 Offsite Maps 10.3 Dose Projection and Protective Action Recommendation N
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SECTION
1.0 INTRODUCTION
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INTRODUCTION The' River Bend Station (RBS), owned and operated by Gulf States Utilities (GSU), conducts an annual joint Emergency Plan Evaluated Exercise with the State of Loulslana and the Parishes of East and West Feliciana, East and West -
Baton Rouge, and Pointe Coupee. The evaluated exercise is conducted for the purpose of assuring that the health and safety of the residents of the five parishes can be protected in the event of a radiological emergency at the plant. Federal government agencies have been invited to participate in the exercise.
The evaluated exercise is scheduled to be conducted as outlined in Section 6.
It will include mobilization of the GSU cmcrgency response organization and will demonstrate its capabilitics to respond to an accident at the plant. The evaluated exercise should demonstrate that emergency response organizations are adequately trained to perform according to current plans and procedures, Evaluated exercise participants will not have prior knowledge of the scenario.
Os The evaluated exercisc will be evaluated by GSU and the Nuclear Regulatory Commission. A critique will be conducted following the evaluated exercise to discuss deficiencies identified. The time schedule for the critique is identified in Section 6.0.
It will be attended by exercise Controllers and key exercise participants. All identified deficiencies will be documented and subsequent resolution of emergency preparedness deficiencies shall be assured by management. Federal agency critique schedules are shown in Section 6.
This manual has been prepared to assist exercise Controllers and Observers in the conduct and evaluation of the exercise.
This manual contains all information and data necessary to properly conduct the exercise in an officient and coordinnted manner.
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SECTION 2.0 t
SCOPE AND OBJECTIVES i
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. 2.1 SCOPE-The 1988 River Bend Station Emergency Preparedness Exercise, to be conducted on February. 24,1988, will test and provide -the opportunity to evaluate Gulf States Utilities' emergency plan and procedures. It will also test the emergency response organization's ability to assess and respond to emergency conditions and coordinate efforts with other agencies for protection of the health and safety of the public.
The scenario - will-depict a simulated sequence of events, resulting in sufficiently degraded conditions to warrant the mobilization of GSU, State and local agencies to respond to the emergency. The Evaluated Exercise will have full participation by the GSU cmcrgency response organization, and partial participation by the state of Louisiana and the parishes.. Whenever practical, the exercise will incorporate provisions for "free play" on the part of the participants.
(v 2.2 OBJECTIVES The River Bend Station 1988 Emergency Preparedness Exercise objcetives are based on the Nuclear Regulatory Commission (NRC) requirements delineated in 10 CPR 50.47 and 10 CFR 50, Appendix E. Additional guidance provided in NUREG 0654, FEM A-REP-1, Revision 1.
The major objective of the exercise is to evaluate the integrated capability of a major portion of the basic c!cments existing within the onsite emergency plan and emergency response organization. The specific objectives of the exercise to be demonstrated are listed below.
Demonstrate emergency response integrated capabilities by activating the o
emergency organization and staffing the RBS Emergency Response Facilitics (ERF'r), including the Control Room, Technical Support Center, Operations Support Center, and the Emergency Operations Facility and by implementing access control to these facilitics.
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Demonstrate the adequacy of ERF's and their personnel, documents, and
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equipment to support,' direct, and control emergency operations, Demonstrate - the reliability and effective use of onsite and offsite o
emergency communications equipment and procedures.
Demonstrate the ability of appropriate individuals to direct the required o-emergency organizations and maintain continuity in the implementation of the emergency plan using the emergency implementing procedures.
Demonstrate the ability of the emergency organization to assess the o
initiating conditions for determining which emergency action level has been t eached and properly classifying the accident.
Demonstrate the ability to perform dose calculations utllizing radiological o
and meteorological information to determine the magnitude of and for continuously assessing the impact of the release of radioactive materials to_ the environment and make the appropriate recommendations for offsite U
protective actions utilizing all relevant factors.
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Demonstrate the ability of offsite field monitoring teams to use emergency equipment in performing radiological surveys.
Demonstrate appropriate equipment and procedures for determining onsite o
radiation levcis.
Demonstrate the ability of the RBS emergency organization to provide the o
joint information center with accurate and timely information so reports may be made to the news media.
o Demonstrate the ability to monitor and control exposures to GSU personnel within the plant.
Demonstrate the ability to begin an exercise between midnight and 6:00 o
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2-2
Demonstrate.the ability to obtain and analyze a Post Accident Sample
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o System (PASS) sample, Demonstrate the ability to perform shift turnover by having key personnel -
o turnover and providing a list of personnel for all other positions.
2.3 SIMULATIONS Actual shift turnover will be demonstrated for key positions. Staffing o
rosters will bc ' developed for the balance of the Emergency Response Organization.
Decontamination of onsite emergency workers and equipment will be o
simulated.
Anti-contamination clothing will be worn, as deemed necessary by players, o
in response to simulated scennrio conditions; however SCBAs will be carried and not worn.
Repair activitics will be simulated.
o Recovery actions will be limited to planning discussions, o
Protected Area and Controlled Arca Evacuations will be simulated, o
i Actual plant coolant and Containment Atmosphere samples will not be o
drawn.
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l EXERCISE INFORMATION i
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3.'1 ' CONDUCT- 0F THE EXERCISE-IT The exercise will' simulate an abnormal radiological incident at the River Q)-
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Bend Station. The effectiveness of selected organizations, personnel and-
- functions of the appropriate Emergency Plans and Implementing Procedures will be demonstrated.
The simulated emergency will then be terminated. The Recovery Phase will be initiated, and the Exercise will.then be' termii.ated.
Emergency response actions during the simulated emergency will include:
recognition and classification of emergency conditions; assessment of onsite/offsite radiological consequences; alert / notification and mobilization of emergency response organizations; implementation of in-plant corrective actions, activation / operation of emergency response facilities and equipment; preparation of reports, messages, and recordkeeping; reconnendation of protective actions, and termination of the emergency condition and limited recovery / reentry discussions.
The Control Room will be the central point for distribution of exercise messages and is the key to ensuring that the Exercise progresses on
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schedule. Simulated plant parameters and annunciators will be provided to the Control Room operators using message forms and plant data sheets. A wide variety of plant infonnation is provided so that at no time will the messages prompt the players or provide undue assistance in recognition of events.
Information available on SPOS will also be provided in the TSC and the E0F where output consoles are located. Contingency messages (denoted by an.'x' after the message number) are delivered only when conditions described in the egntroller notes have been met.
Radioloqical and meteorological data presented in Sections 9.0 and 10.0 and information included in the supplemental scenarios will be disseminated by T
controllers when players demonstrate the capability to obtain the information from appropriate sources. At no time, unless noted specifically as an exception, will information be interjected at a point where it would not be available in a real emergency. The Lead Controllers may interject other information or change a message to ensure that the Exercise progresses as planned.
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The Exercise Players are expected to "free play".the scenario to the extent practical If corrective actions are postulated that would terminate the einergency, they should be identified to the Lead Controller in the affected facility, so that the scenario will progress as designed. Notifications of, and contact with, supervisors,. plant management, and offsite agencies will be made in accordance with the Emergency Plan implementing Procedures. No simulations are to be allowed unless specifically noted in the Exercise Manual or directed by a Controller for scenario purposes.
3.2 PRECAUTIONS AND LIMITATIONS This section provides information for all exercise Controllers and Observers related to the rules and guidelines to be followed throughout the conduct of this Exercise. Prior to initiation of the Exercise, a pre-exercise briefing will be held to review the entire exercise process with all the Exercise Controllers and Observers.
Should at any time during the course of the conduct of this Exercise, an o
actual emergency situation arise, all activitics and communications related to the Exercise will be suspended. It will be the responsibility of any Exercise Controller or Observer that becomes aware of an actual emergency to suspend exercise response in his/her immediate area and to inform the Lead Excrcise Controller of the situation. Upon notification (,f an actual emergency, the Lead Exercise Controller may notify all othe' Controllers to suspend all exercise activitics.
Should, at any timo during the course of the conduct of this Exercise, an o
exercise Controller or Observer witness an exercise part cipant undertake any action which would, in the opinion of the Controller, place either an individual or component in an unsafe condition, the Controlice is responsible for intervening in the individual's actions and terminating the unsafe activity immediately.
All repair activitics associated with the scenario will be simulated with o
extreme caution emphasized around operating equipment. Manipulation of any plant operating systems, valves, breakers, or controls in response to.
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this Exercise is to be simulated. There is to be no alteration of any plant
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- Exercise.
No pressurization of fire hoses, discharging of fire extinguishers, or initiation of any fire suppression systems willbe allowed for the Exercise..
All telephone communications, radio transmissions, and public address o
announcements-related to the Exercise must begin and end with the statement, "This is a drill". Should a Controller witness a drill participant not observing this practice, it is the Controller's responsibility to remind the individual of the need to follow this procedure.
Any motor vehicle response to this Excrcise, whether it be ambulance, o
fire fighting equipment, police / security vehicles or field monitoring teams, should observe all normal motor vehicle operating laws including posted speed limts, stop lights / signs, one way streets, etc.
Care must be taken to assure that any non-participating individuals who o
may observe exercise activitics or overhear exercise communications are not misled into believing that an actual emergency exists. Any Exercise Controller who is aware of an individual or group of Individuals in the immediate vicinity who may have become alarmed or confused about the situation, should approach that individual..: group and explain the nature of the Exercise and its intent.
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I SECTION 4.0 CONTROLLER INFORM ATION 1
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'4.1 GENER AL INFORM ATION
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Each Controller should be familiar with the following:
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'Ihe basic objectives of the exercise (Section 2.0).'
The assumptions and precautions being taken (Section 3.0),
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The exercise scenario, including the initiating events and the expected course of action to'be taken (Section 7.0).
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.The various locations that will be involved and the specific items to be obscrved at those locations.
o The evaluation checklists provided.
4.2 CONTROLLER INSTRUCTIONS m.U o
Controllers will position themselves at their assigned locations 30 minutes prior to the activation of the facility fo' which they have responsibility.
-o Communications will be tested prior to exercise commencement.
All watches and clocks will be synchronized with the Lead Exercise Controller as part of the communications testing.
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All Controllers will comply with instructions from the Lead Exercise Controller.
o Each Controller will have copics of the messages controlling the progress of the exercise scenario. No message shall be delivered out of sequence or.other than as written unless specifically authorized by the Lead Exercise Controller.
o Controllers will not provide information to the Players regarding scenario progression or resolution of problems encountered in the course of the l
simulated emergency. The exercise participants are expected to obtain 4-1 l.
d x-(f information through their own organizations and exercise their own h
judgement in determining response actions and resolving problems.
o ' ' Some Players may insist - that certain parts of the scenario are-unrealistic.
'The Controllers have the solo authority to clarify any questions regarding scenario content.
4.3 EVALUATION INSTRUCTIONS Each Controller will take detailed notes regarding the progress of the exercise and response of the exercise participants at their assigned locations. Each Controller should carefully note the arrival and departure times of participants, the times when major activitics or milestones occur, and problem areas encountered.
Controllers' comments will be used for the purpose of reconstructing the Exercise chronology and preparing a written evaluation of the Exercise.
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Controller evaluation forms for each facility / team will be distributed at the pre-Exercise controller briefing.
3 4.4 PERSONNEL ASSIGNMEN'IS The Personnel assignments for the Controller organization are as follows:
Onsite Controllers Main Control Room Operations Support Center Technical Support Center Emergency Operations Facility (LATER)
Dose Assessment (TSC/ EOF)
Offsite Monitoring Teams
.IIC Media Controllers n
Lead Exercise Controller i
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4 Offsite Controllers WFP-E0C EFP-E0C WBRP-E0C EBRP-E0C PCP-E0C (LATER)
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i PLAYER INFORMATION 1
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i-5.1 GENER AL IN FORM ATION (V
This section provides information for all exercise Players. These guidelines should be followed throughout the conduct of the Exercise. A pre-exercisc briefing will be held to review the entire.' exercise process, including "Precautions and Limitations" in Section 3.2, and the following information with all the players.
The success of the Exercise is largely dependent on player performance.
Appropriate reaction to simulated emergency conditions and demonstrated competence in the Emergency Plan and Implementing Procedures are the key criteria by which the players are evaluated. It is imperative, therefore, that all player actions and activities are witnessed by a Controller. Any actions that are to be simulated must be brought to the attention of the Controller to ensure that credit is awarded. The success of the exercise is based on the demonstration of the predetermined exercise objectives.
5.2 PLAYER GUIDELINES a
o Maintain a serious attitude throughout the exercise; this is especially true late in the exercise or when activity is limited.
o Maintain courtesy and professionalism, at all times, Teamwork is essential; do your job and then help other people do theirs; o
for example, if you know certain information should be available, ask for it, this makes you look good and may reduce a deficiency for someone else.
Think; brainstorm and look for all possible solutions or consequences of o
events; maintain the "big picture" of what is happening.
Identify yourself by name and function to the Controllcr/ Evaluator and o
the NRC Evaluator; this will be a big help; always wear your identification O
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If you are entering normal nuclear station radiation areas, observe all o.
rules and procedures; no one (including Controller / Evaluators) is
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exempt from normal station radiological practices and procedures.
v NOTE: DO NOT ENTER HIGH RADIATION AREAS IN THE PLANT: FOLLOW ALARA PRINCIPLES.
o Nonnal station security. procedures must be followed, o.
Elements of exercise play will be introduced through use of controlled exercise message forms and infonnation generated by Players as a result of the particular emergency activity performed.
Therefore, be responsible for initiating actions in accordance with instructions and responsibilities.
o Conmunications should be concise and formal with use of abbreviations minimized; always include "This is a drill".
o Use and demonstrate knowledge of the Emergency Plan and implementing
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procedures, Use all resources and equipment available as you would in an actual o
emergency, o
Transfers of authority should be formal and announced; there should be no doubt as to who is in charge, who is responsible for what and when this responsibility is accepted, o
Show concern for ALARA considerations at all times.
o Utilize status boards, log books, multi-part communication forms, etc.;
document and record your actions, instructions and reports to your co-players, this is important; remember, "put-it-in-writing" and include "This is a drill".
If Federal Evaluators want to initiate actions, test your abilities or o
O give you instructions, they must work through your Controller / Evaluator.
5-2
t fa Keep a list of items which you believe 'will improve.the plan and/or.
.o procedures; provide this to your Controller / Evaluator at the end of the l
Exercise.
!1 Remember, one of the main purposes of an exercise is for you, the Player, o
I t'o' assure yourself that you ~ are adequately prepared.
Areas for 1
i improvement or lessons learned, when identified, will improve your overall'
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4-i SECTION 6.0 i
SCIIEDULE OF EVENTS a
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SCHEDULE OF EVENTS -
Dote-Time Event Location 2/22/88 TBD Player Briefing Training Genter Auditorium t/23/88
- 10 AM Controller Briefing -
Training Center Auditorium 1PM Detailed Scenario Discussion Training Center Auditorium
- 2/24/88 All Day Annual Exercise All facilities 2/24/88 After Facility Critiques All facilitics Termination (RMTs to EOF) 2/24/88 Approx.
Controller De-brief EP Conference Room 1600 4
2/25/88 9AM Consolidated GSU Crltique Training Center Auditorium TBD TBD NRC Exit meeting TBD 4
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. EXERCISE SCEN ARIO SEQUENCE OF EVENTS Scenulo Actuali Summary Timc ~
Time 00/-15 0515 INITIAL CONDITIONS RWCU backwash rocciving tank transfer is scheduled to take place at 01/30 (0700) per SOP-0090 Section 5.8.
B RIIR pump is out of service due to loss of 125 VDC control power to the pump motor breaker; the breaker is opened and the pump has been' declared inoperable. while the problem is being investigated. A 7 day.and a
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72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO have been in effect since 0700 02/22/88.
Reactor Coolant Dose Equivalent lodino (DEI) has been trending upwards for the-past two weeks.
Yesterday's sample results indicates
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.08 uCi/gm DEL RDS management has <*ccided
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to continue operation until DEI reaches.15 uCi/gm DEI.
RBS is operating at 106% power. The core has 376 equivalent full power days and is on a continuo'ts run of 314 days.
LER 87-325-20, which describes the failure of SRV electrical function at the Brunswick Steam Electric Plant (BSEP), has been forwarded to all licensees for review, regardless of the type of valves installed in the plant. The LER describes a condition caused by the hardening of LOCTITE scaler around the actuating solenoids, which prevents electrical functioning of the SRVs, while allowing the mechanical function to remain operabic.
RBS management has decided to continue full power operation while engineering investigates this issue.
00/00 0530 Commence the 1988 Evaluated Exercise.
00/10 0540 A < hart in the IIPCS auto start logic causes a sptalous !n!tiation and injection to the vessel.
(' 'L; Operators override the pump and close the injection valve F004. When the operator attempts 7-i
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' Actual Summary Time.
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to reset the automatic initiation, it does not reset due to the short. As yalve F004 starts to close,_
the pin' falls out of the limit switch rendering it inoperab'e. We valve motor overheats and begins -
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to smoke e, the breaker. falls to trip promptly on
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Loss.of position indication in ' the control room alerts the. operator to -the loss. of -
valve control power when the breaker opens. An NEO is dispatched to Investigate' the-problem.
IIPCS is declared inoperable, thus' requiring the Q.
plant to be in Hot Shutdown in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> per Tech.
M Spec. Section 3.5.1 and 3.0.3.
Plant Shutdown is
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Operators allow the Division III' Diesel to idle for I hour per procedures.
.- UNUSUAL EVENT -
AN UNUSUAL EVENT SIIOULD BE DECLARED PER ~ EIP-2-001,. page 11, No.
9, "Loss of Engineered Safety Feature - Requiring Technical Specification shutdown".
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'0600 The nuclear equipment operator finds the motor operator charred and hot to tl'e touch. He reports this condition to the control room.
De Shift Supervisor directs the NEO to -ensure that the
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valve is closed.
'01/30 0700 RWCU backwash receiving tank transfer to the l
phase separator commences.
01/45 0715 In the radwaste building a flange break occurs at the six way valve in the six way valve room during the backwash rocciving tank transfer causing a leak of high activity radwaste into the radwaste building on elevation 95' and 65'. ARM's alarm, readings exceed 1000 times normal readings, i'
IIcalth ' Physics is dispatched to perform air samples and local surveys. Radwaste operator is dispatched to locate leak.
02/00 0730 IIcalth Physics confirms the high radiation problem in the Radwaste Building.
Ventilation exhaust monitors show
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ALERT AN ALERT SIIOULD DE DECLARED PER EIP 001, page 17. No. 4, "Unexpected l{lgh Radiation Levcls or II_lgh Airborne Radioactivity, or Contamination :
Levels - ' Indicating Severe Degradation in the Control. of Radioactive Materials".
The Radwaste operator investigating the leakage from the six way valve slips and falls, lie is
- seriously injured and. severely - contaminated.
Offsite medical assistance is required. Leak is isolated.
02/30 0800 Annunicator in the control room alerts the operator to vibration of > 3.5 mils in the reactor recirculation pump 'A'.
'the alarm clears and the annunicator can be reset.
02/45 0815 Rectre pump 'A' degrades rapidly, sending metal shavings and debris through the jet pumps and through the core plate into the core. Recire pump
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'A' seizes and instantly trips. Mechanical damage 4,0 to some cladding occurs, causing the release of gap fission gases. 'Ihe main steam isolation valves isolate on 3 times nornial radiation, causing a reactor scram and turbine trip.
Vessel level swells due to Recire trip to level 8, causing the RFPs to trip. Attempts to restart feedwater fall due to a failure 'n the teedwater suction pressure signal.
Operators observe failure of the low-low set logic to control reactor pressure at less than 1064 psig and enter EOP-0101.
SRV's relief function is inoperable due to frozen solenoids however, SRV's safety function remains operable.
RCIC is initiated in CST to CST mode to assist in heat removal.
Drywell and containment atmospherc high radiation annunicators confirm fuel clad damage.
03/15 0845 RCIC Isolates and the turbine trips due to high i
steam flow (DIV 1). 'the RF-1 modification to the
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tubing run has not resolved the instrument problem. Attempts to restart RCIC fall because E519iOV-FM4 trips on overload when the operatoc attempts to open the valve. Attempts to
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manually open F064 fall t>ccause the valve is C'
mechanically bound.
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' Scenario Actual Summary
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SITE ' AREA ' EMERGENCY A SITE AREA EMERGENCY SilOULD BE DECLARED PER EIP-2-001, page 25, No. 6 "INABILITY TO DEPRESSURIZE TI{E REACTOR".
03/30 0900 SRV'S continue to operate in safety modo and CRD flow provides the only ; makeup to the reactor.
Additional decay heat removal is provided by RWCU.
04/30 1000 The RWCU system suction line breaks in the RWCU A' pump room at the suction flange allowing reactor water to be released into the pump room and Auxiliary Building. The RWCU system isolates and the pumps trip except that G33*MOV-F001 and F004 do not go closed. MOV--
F001 starts to stroke closed but the high dp due to the line break binds the valvo dige and the MOV torques out tripping the breaker with the valvo in mid position. F004 fails to close, as well as all other Division 11 isolation valves (outboard) due to a failure. In the leak detection system (falled
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card). Area temperatures and high system flow alarms hlert the opciators to the failure of RWCU
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to isolate. A release to the environment begins via SGTS.
GENERAL EMERGENCY A
GENERAL EMERGENCY SIIOULD DE DECLARED PEP EIP-2-001, page 31, No. 2, "LOSS OF 2 OF 3 FISSION PRODUCT BARRIERS WITl! A POTENTIAL LOSS OF TIIE TillRD B A R RIER".
05/00 1030
'The release continues as the reactor depressurizes through the break in the RWCU pump suction line.
06/00 1130 The release continues, plant teams discover a faulty resistor in the isolation logic card for RWCU leak detection.
06/15 1145 Shutdown cooling interlocks are met. (less than 135 psig).
06/30 1200 RWCU leak is isolated by repair teams.
0G/45 1215 SDC is initiated by control room. Release rate has returned to background.
P 07/15 1245 he RilR A heat exchanger develops a tube leak.
p)
Process radiation monitor RM*REIS A alarms as
(~
reactor water leaks into service water.
7-4 i
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.. /.' g
_J,
-:,9 i'
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= Scenario Actual Summary M
j Time Time
.i 07/30
.1300 RHR A heat. exchanger and service water are.
E isolated.
.08/00 1330 RHR B pump motor control power is restored and Shutdown Cooling is established using the 'B' RHR
. loop.
-i 08/15 ~
1345 Reactor is placed in cold shutdown.
- l 08/30 1400 Exercise is terminated.
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SECTION 7.2 l
MASTER EVENTS
SUMMARY
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7.2 MASTER EVENTS
SUMMARY
REAL SCENARIO MSG MSG MSG EXPECTED TIME TIME N O.
TO
SUMMARY
ACTIONS o Discuss and distribute throughout IC RBS Describe PRIOR Day Initial Conditions Prior Day organization COB MGT 0515
-00/15 IC CR Initial Conditions, drill guidelines o Read and understand
__2 0530 00/00 1
CR Drill announcement + Plant Status o Read announcement on Gaitronies
' g:
m 0540 00/10 1.1 CR HPCS Spurious initiation o Shutdown HPCS and declarc Inop.
- -)
9 o Tech Spec Shutdown o i~ lare HPCS inop K
0542 00/12 1.2X CR Ensure operators close HPCS F004 and see indications of valve failure.
o.See Supplemental Scenario No.1 g
for details o NOUE o Declarc NOUE per EIP-2-001, I,%
NOUE No. 3 implement EIP-2402, Notification -
o of Unusual Event.
Implement EIP-2-006, Notifications o
~
0545 00/15 2
CR Plant Status showing HPCS inop 0550 00/20 2.1 X Ensure Shutdown is commenced per T.S.
o Commence Shutdown to meet conditions for NOUE.
0600 00/30 2.2X CR NOUE Contingency Message 0600 00/30 3
CR Plant Status Update l
0615 00/45 4
CR Plant Status Update showing shut-
~ o Shutdown rate no greater than down has started.
50M We/hr.
l
I o
O
. K+
7.2 MASTER EVENTS
SUMMARY
REAL
- SCEN ARIO MSG MSG MSG EXPECTED TIME TIME N O.
TO SUMM A RY ACTIONS -
Comply with constraints of 0615 00/45 4X CR Shutdown rate constraint o
scenario 0630 01/00 5
CR Plant Status Update o Shutdown continues 0645 01/15 6
CR Pinnt Status Update o DIV III Diesel returned to standby 0700 01/30 7
CR Radwaste transfer commences Dispatch Radwaste Operator 0715 01/45 8
CR ARMS Alarm on DRMS due to pipe o
Dispatch Health Physicist break in Radwaste Building.
o After confirmation by Ifealth Physics, o
declare an ALERT due to 1000 x Norma (
Radiation levels See Supplemental Scenario # 2 o
o-Declare an Alert per EIP-2-001, Alert No. 4 o implement EIP-2-003, ALERT
-l o Implement EIP-2-006, Notifications Implement EIP-2-018, TSC Activation !
o
-o Implement EIP-2-019, TSC Suppert Functions Implement EIP-2-016, OSC Activation. l o
o Impicment EIP-2-017, OSC Support Functions l
i
8 2
7.2 MASTER EVENTS
SUMMARY
EX9ECTED MSG REAL SCENARIO MSG MSG AcilONS
SUMMARY
TIME TIME N O.
TO Call ambalance, rescue and decon-o 0730 02/00 9
CR Spill continues in Radwaste.
taminate the victim Radweste Operator injured and con-See Supplemental Scenario #3 o
tam!nated.
Implement EIP-2-009, Medical o
Emergencies
_o Impicment EIP-2-012, Radiation s
o Exposure Controls implement EIP-2-026, Evacuation g
o y
(Limited) (Simulated)
Implement EIP-2-027, Personnel o
2-Accountability (Simulated) m 0740 02/10 9.1 X CR Alert Contingency Message
~D 0745 02/15 10 CR Plant Status Update Dispatch I&C tech to check indications o
0800 02/30 11 CR Recire Pump 'A' begins to vibrate, Reset alarm & monitor vibration o
implement Reactor Scram procedure o
Rceirc Pump ' A' degrades rapidly, Initiate Suppression Pool Cooling 0815 02/15 12 CR o
sending metallie &bris into the Start RCIC in test mode for pressure core, causing darrage to fuct clad-o Control ding. MSIVs isolate on high Request Reneter Coolant Sample o
radiation and the reactor sc.-ams.
Enter EOP-0101, Pressure Control o
SRVs cycle mechanically.
0820 02/50 12.1 CR SPDS data plant update 0825 02/55 12.2 CR SPDS data plant update u.
f 5
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\\w 7.2 MASTER EVENTS
SUMMARY
REAL SCEN A RIO MSG MSG
-MSC EXPECTED TIME TIME N O.
TO
SUMMARY
ACTIONS 0830 03/00 13 CR Plant data shows 'A' RHR in o' Monitor Reactor conditions Operators have no cicctrical control of Suppression Pool Cooling and o
RCIC operating in test mode to SRVs remove reactor heat.
Adequate heat removal is no longer 9
0845 03/15 14 CR RCIC trips due to an instrument o
problem.
available o Declare a SITE AREA EMERGENCY l
due to inability to depressurize l
the reactor 4
o - Declare a Site Area Emergency per 3
EIP-2-001, SAE No. 6 o implement EXP-2-004, Site Area Emergency Implement EIP-2-006, Notifications
.E o
Implement EIP-2-026, Evacuation g
o (Protected Area)(Simulated)
Implement EIP-2-027, Personnel o
Accountability (Simulated)
Implement EIP-2-620, EOF Activation o
Implement EIP-2-021, EOF Support o
Functions CRD pumps are the only remaining high 0900 03/30 15 CR SRVs continue to cycle in mechnical o
relief mode, pressure makeup sourec 0905 03/35 15.1X TSC Site Area Emergency Contingency Message 0915 03/45 16 CR Plant Status Update c
(
m
- o S'
7.? MASTER EVENTS
SUMMARY
REAL SCENARIO MSG MSG MSG EXPECTED TIME TIME N O.
TO
SUMMARY
ACTIONS 0930 04/00 17 CR Plant Status Update 0945 04/15 18 CR Plant Status Update Attempt remote manual isolation of 3
1000 04/30 19 CR Indications of RWCU pipe break in o
the 'N RWCU pump room, with failure RWCU valves. Enter EOP-0103, g
to automatically isolate. Release Secordary Containment Control and rn to the environment via SGTS begins.
EOP-0104, Radioactive Release Control d
4 Dispatch repair teams to assess and o
correct valve problem.
I See SupplementalScenario #4 o
Dispatch fic1d teams per EIP-2-013/014 2
oo Perform dose assessment / projection per EIP-2-024 o Declare a Cencral Emergency per EIP-2-001, General Emergency No. 2 g
Impicment EIP-2-005, General o
Emergency o Make Protective Action Recommenda-tion per EIP-2-007 1015 04/45 20 CR Release continues through unisolable RWCU break. Reactor begins to de-pressurize.
1020 G4/50 20.1X EOF General Emergency contingency message 1030 05/00 21 CR Pcactor depressurization to Aux Bldg and uncontrolled release via SGTS to environment continues.
(_
v
H TH 8000 4000 1000 1000 1000 1000 RE-213 RER A Area West A.B.70'(mR/hr)
OSH OGH 8000 4000 1000 1000 1000 1000 RE-214 RHR B Area East A.3.70'(mR/hr)
WH OGH 8000 4000 1000 1000 1000 1000 RE-215 RHR C Area A.B.70'(9/hr)
WH WH 8000 4000 1000 1000 1000 1000 RE-216 LICS Area West A.B.70'(mR/hr)
GH WH 8000 4000 1000 1000 1000 1000 PE-217 HIG Penetration East A.B.70'(mR/hr)
OGH OSH 8000 4000 1500 1500 1500 1500 RE-218 LIG Penetration West A.B.70'(mR/hr)
OSH OSH 8000 4000 1000 1000 1000 1000 RE-219 RCIC Area West A.B 70'(mR/hr)
WH TH 8000 4000 1000 1000 1000 1000
u.
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9-(y) : AIEI IGil1GE 11EBE) DRTA
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. Drill T h 08/00 08/15?
08/30-Clock T h 1330 1345
- 1400.
7 Yx T
.ID Ik-har Location (Units)
~
A RE-16A,B Containment PAM R.B.186*(R/hr) 500
' 500..
'500 RE-20A,B Drywell PAM D.W.114*(R/hr) 15 0 150
- 150
^
RE-21A,B Cont. Purge Monitor R.B.141*(R/hr).
OSH GH' OSH
~
RE-139 Inside Annulus 114'(mR/hr)
- OSH.
OSH'
' OGH
.s.
RE-141 Refuel Floor South R.B.186'(mR/hr)
OGH,
OSH OSH RE-146-Containment Airlock F.B.114 * (mR/hr)
OSH OGH
^ GH
~
RE-151 Sample Station Area R.B.162'(mR/hr)
OSH OSH OSH
.i RE-182 Recovery Sample Tank R.W.65'(mR/hr) 0.4
- 0. 4 -
- 0. 4 RE-185 Storage Tank Area R.W.90'(mR/hr) 0.2
- 0. 2
' O.2 RE-106 Floor Drain Suse R.W.65'(mR/hr) 0.5
- 0. 5
- 0.5 a
RE-187 High Cond. Sump Area R.W.65"(mR/hr) 0.3 0.3 0.3
~
RE-192 Refuel Floor South F.B.113'(mR/hr) 40 40 40.
^
RE-193 Refuel Floor North F.B.113'(mR/hr) 40 40 40 RE-194 Support Room Trans.'Ibbe F.B.123'(mR/hr) 20 20 20 RE-195 Sample Sink Area F.B.95'(mR/hr) 10 10 10-RE-196 Equip. Drain Sump F.B.70*(sR/hr) 50 50 50 4
RE-200 North Hoist Area T.B.123'(nR/hr)
- 0. 4 -
0.4 0.4 F
"P b
ab) kh
$:h
-$:h bb RE-203 Turb. Bldg Saaple Room T.B.67 *(mR/hr)
O.1 0.1 0.1 RE-204 Cond Demin Sample Rack T.B.95'(mR/hr) 0.2
- 0. 2.
0.2.
RE-210 PASS Panel A.B.114'(mR/hr) 500 500 500 RE-211 Control Rod Drive A.B.95'(mR/hr) 2000 2000 2000
~,
RE-212 HPG Area East A.B.70'(mR/hr) 1000 1000 1000 RE-213 RM A Area West A.B.70'(mR/hr) 1000 1000 1000-RE-214 RIE B Area East A.B.70*(mR/hr) 1000
- 1000, 1000 RE-215 RHR C Area A.B.70*(mR/hr) 1000' 1000 1000 RE-216 LPCS Area West A.B.70'(mR/hr) 1000 1000 1000
- i' RE-217 HPG Penetration East A.B.70*(mR/hr) 1500 1500 1500-
, e RE-218 LPCS Benetration West A.B.70'(mR/hr) 1000
- 1000 1000 RE-219 RCIC Area West A.B.70*(mR/hr) 1000 1000 1000 u
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ASSUMPTIONS h
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,.x SECTION;7.4 SCENARIO._ASSUMPT.IONE >
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i-Ridi61cgical Parametara
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- s 1.
Radioactive material released (simulated)L wll1J consis t primarilyEof noble-' gases. However. the release-of i
radiciodines will be considered in' emergency response-activities.
2.
The dispersion - factors used to calculate of faite ' data are those derived for use with the'RBS EDP Model conterline value.. Table 110. 6.1 shows the dose rate projections made by the-Model.
3.
No filtering credit'is allowed for noble gases.
Filtering-efficiency for Iodine removal is taken to be'99.9%,.
4.
Stack release concentrations are based upon a release flowrate of 4. 5E+07 cc/sec (9.53E+04 cu.ft./sec) following initiation of the Standby Gas Treatment System.
S.-
Field Survey Data 9
a.The~ downwind gamma doses were determined using EDP Model centerline values.
~
b.The iodine deposition values were calculated as follows:
The gross iodine release was first corrected from the time the release took place back to the time of shutdown to account for decay._
Assuming a release of "C" curies at time "T" after shutdown. the amount of gross iodine at shutdown is determined j
by:
l
/ T Ao : Ae l
where d is a function of the ti ra-af ter shutdown.
It was calculated by considering Ao curies e time D.
Then at time "T" the concentration j T This includec 5 isotopes: so A = Ace
_AT A: Aof(11e f(I)'s are taken from the default values for iodines in containment af ter an accident.:
IUT I-131 f(l)
O
=
I-132 f(2) -
17 1 I-133 f (.S ) -
'!?
1.; 4 f:4)
' W.
1 :
f4
6 f
l i
O 2
Then at time "T"
there are "A" curies, or what we measure.
To calculate the effective decay constant the aggregate decayed is:
_ AT l
A = Aoo 1
!s where A = Ao(f). f being a fraction less than one; j'
_AT l
l this given Ao(f)e 1
IniO solving for d gives:
d:
-T i
i then A can be used to calculate how much iodine was originally j
present at shutdown.
j 1
Gross Iodine deposition was calculated using the formula:
?
D=
(I
- DF) / (X *.3927) where D = the deposition in C1/m2 j
j 1 : the amount of Iodine released in Curies l
l DF : the deposition factor from BEG GUIDE 1.111 Fig.6-9 i
I-X: the distance from the source in meters
.3927 : is the are length in radians of a 22.59 section l
Individual isotopes were determined using the default l
percentages for each isotope, corrected using the individual decay constant.
Gross deposition is the sum of the individual
(
isotopes after decay.
c.Tl+ soil concentration was determined using a depth of one inch and a density of 2100 kg/m3 i
d.The water : oncentra tion assumes the sample is taken one r
inch deep.
[
e.The a r a s.1 and vegetation samples wrre calculated usinc averaa-depos ition fractions anil densities from j
t;U E EG n. n - 4 03 '::. Giv!iL-596 D.
' E miiol ogi c a l Assessment",
f Table t.
1 ' Fraction of Tota) ini tial Iwposition Retained or Veg-- t a t l o n pg. 5-15. S e p t.n mbe r 1963.
i f.The concentration of radin:odino in :ailh was calculated i
utilising the formula:
l i
- 1. M E - 2 + ( EU ( - 0.114 t ) - EXP (- 0. 9 0 t) )
[
C(t>
IDo i
whero Ct**
ceneentration in mi]h at t i me-
- t. ( d a y ) a f t.n r event j
daily for3ce conmmpt ion by th-cow tha/ day) 9 initia]
- a. t.i v i t y pr~sent
.n t he forane- (PCi/lw)
{
I.
i b* n t.
PI' f' M
[
i lh MI, 5.* * ;
h 'ti } i,
A' jj :Ib [G
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g.The PAG preventive and emergency levels are' flagged when the concentration is above the levels given in U.S.
Dept. of Health and Human Services. "Preparedness and Response in Radiation Accidents". HHS Publication FDA 83-8211, AUG 1983.
h.All survey values are rounded off to provide realistic survey meter responses.
Iodine concentrations are used with an air sample volume of 10 cubic feet.
- j. Milk sample results were based upon the assuroption that all downuind dairy herds were removed from the pasture prior to plume arrival and kept on stored feed.
One herd was placed on pusture one day after plume passage for four hours.
The I-131 activity.in the milk sample was determined by NUREG/CR-3332. ORNL-5968, "Radiological Assessment", pp.
S-89,90.
cl.
Inplant Data a.The fractions for the various nuclides are those listed in the EDP Model for LOCA.
b.The Auxillary Building dose rates following the release were
)
developed by calculating a centerpoint immersion dose in a semi-infinite cloud of noble gases, utilising the formula:
D X(1)
- DF(i) where:
Dr camma air dose X(i h concentration of nuclide (i)
DF - dose factor for exposure to a semi-infinite clout of (Li Dose Factors were obtained from REG GUIDE 1.109, Tabla h-1.
Where appropriate, the dose rates include contributions from various i n pl a n t, systems (i.e.
piping, vent ducting, etc.).
The w contributions are also reflected in the area rad i a t. i o n ronitor readings, c.AI] Turbinn Building area nonitors within 100 feet af ths Aux Building reflect a contribution to the dose rate from tha airborne concentration in the Rx Building.
d. Do.w rates from PASE, wore calculated using the Radiological Health !!andbwh ruli of thumb: R/hr at I foot. : 5.A4CE, G
where C is the number of curies and E is the energy in MeV.
E is evnse rva t.iv. ly u sum -d to be (#. 5 for iodin, and
.i r v.b l.- e,,
i -
U 4.
^ <
e.All' Core. damage dependant' ' PASS samples are ' mix decay corrected from time of Rx Shutdown.
All activities account for both isotopic decay and system effects ( i. e.- dilution or leakage).
Postulated Core Damage is approx. 10% based upon RBS Core Damage procedure.
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SECTION 8.0 i
MESSAGES AND PLANT DATA 1
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MESSAGES 4
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wmmm
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.m--
w--y-m-w v------my
, = *-
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=
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d Message _ Number : IC--Day Before Real Time =: 1600
-Soenario Time m 2/23/88 RIVER BEND' STATION
' EMERGENCY-PREPAREDHESS EXERCISE MRRSAGE.'
Message for: ' River Bend Station Management SimulatedLPlant Conditions: See attached' Plant Data Message:
- THIS IS A DRILL *** '
The initial conditions for the exercise are as follows:
o The station is operating at'100%- power. The core has been at power-for 314 - days and has an average exposure of 8000 MWD /t.
o Reactor coolant dose equivalent iodine (DEI) has-
/'l-been ~ trending upwards for _the past two weeks.
k.,/-
Yesterday's sample' results indicated a DEI of.08 uCi/gm. Station management has -decided to continue operation until DEI reaches.15 uCi/gm.
o The "B" Residual Heat Removal (RHR) pump is out of service due to loss of 125 VDC control power to the pump motor breaker.
The breaker is open-and the pump has been declared inoperable while the problem is being investigated.
A 7
Day LCO has been in effect since 0700, 2/22/88.
o LER 87-325-20 was received yesterday concerning the electrical function failure of the Safety Relief Valves at Carolina Power and Lights' Brunswick S ta tion, NBC has requested a
review of all licencees naintenance procedures for all valve manufacturers.
All other systene are operating normally o
h
.~
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-g-4 5
3
- +
z
.+ :,
y
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Hesssge Number-= Conditions Day Before Real-Time -:. 16A0
']
1 Scenario' Time =. 2 /23
~
-i G
RIVER BEND _ STAT. ION _.
3 3c EMERGENGY PREPAREDHESS_ EXERCISE _ MESSAGE'
'i
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Enr Controller Use Oniv:
- CDNTROLLER ' INFORMAT ION;
=
U o-Distribute this information-tolRiver Bend"Station. Management-t l
and-other cognizant personnel to inform them of significant pre existing conditions.for-the scenario.
l j
l Exnected Act. ions c
i '
Review and ^ distribute. this Linformation; throughout. each.
o manager 's organization.-
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. Time:= 1EQu' J
lHessage' Number =; Conditions the day Before.
-+
F Scenario Time = _2/.23/88__
F
- RIVER BEND. STATION i
-EMERGENCY PREPAREDNESS. EXERCISE' PLANT. DATA-j b
I' EANEL_6.01
- EANEL..B63.
1
'1 Sta.tus.
- Eren.
E.Los-
- BHR A
__S R_
0
.Drywell Cooling _
B
_ DOS _ -
.O Fans'A.D.C
__.QP_
. C'
_SR. _
.0....
Fans ~D.E.F.
D:~0P_ l
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.SR 0
- Containment Cooling j
i' Fans A, B C A&B-GP. C-SS I
BCIC
__ S R___.
!O J___
i HPCS SR 0
_0_
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~ A AV
.0
- 0
- SLC B-
._. A V
_._.0 d_
Control Room HVAC F
-AHU A
OP 19.0fL
_1E_.
AHU B
_S S......
l B
.__A L._.
0-OPEN SGTS A SR O
n CLOSE MSIV 0
B_
SGTS B SR I
__16_
0
+
LEVEL ERESS
.l l --
._36 ".
_ LQ1R
!l STATUR
._ PANE LBla l
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Diesel Gen Div I
_ D R _.
Stby Service Wtr A
._.S R 1
~ Diesel Gen Div II SR -
Stby Service Wtr B
_.S.fL
-f l
Diesel Gen Div III JA_
j t
8 l.
l' F
PANEL _808.
PANEL _680_
i t
F i
j TEME EEECS.
Feactor Level 3fi".
b Containment
_. 83
_0.1_
Rosetor Power 100A_APFM Drywell
.122
. 0.1 Beactor Temp
.3 44 i
TEMP LEVEL c, o o n.m
- .1 30
.e w' 4i I-4A,~,,-,.._.-,.-,,-,,.,_._._._-.-__.....-_-,-_..___.,-.-,,__._.__.
.. - _----- -,- - J
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0:.1 I RPV NORliA d C k [,~~ ] [ Q 3 _ ] 's V A R::'lBL ES ICHTMT NORMAL I
~~
CONTRIHMENT
'N lNOT OPERlI I
DG l
RPV 4 DESIGN 14.9D
( SRU LIFT 1103D i
l PRESSB 0.1EPSIG PRESS I l019 l PSIG l
SHUT l
l hh_l U
U 8
f 4 OPER HI 1.68y
( 100'4 BPV 1025 )
~j PRESSI 0.1EPSIG
?%
?O 1
j
( OPER HI 90 D 4 TRIP HI 52 D l
TEMPR 835 F LEVELi 36IIN l
ISOL l
4 OPER HI 135 D (SCRAM LO 9D TEMPI 122I F POWERI 100 E'./
(OPER HIl20- O D LUL 19 FT 10 IN W u/N (OPER LO 19-6 D E
SCRlM l 4 OPER HI 95 D I
N0bE E
i p
op SUPPRESSIGH SUPPRESSIGH POOL POOL I
I__
RIVER BEND 8 8 8 IS FES l'8%
17?oo:00 i
O O
O O :. 3 R 'V C 0
~ R 0 L--l.i.I R / 31.ij R
"'"' """a
E 198 E IN >TAF E
RPV POWER PUMP I I
36lIN CHDS/FU IWATER AVAIL PRESS AVAIL RUN I 60 TRIP HI 521 PUMPI WATER RPU POWER 0-l CRD RUN AVAIL PRESS AVAIL PERl SCRAt1 LO:
91 l WATER RPV POWER PUMP 110T RCIC AVAIL PRESS NA 0FF
-120-RPU POWER PUMPI TAF
' -1621 l WATER HPCS AVAIL PRESS AVAIL OFF l
-180 0 W H) 0 ll$yfphP gg((
PUfgP l RPV PRESS E 1019IPSIG LPCS I
Op gp SHUT I
POOL LD 13501 IWATER RPV POWER PUMP l LPCI IAVAIL PR HI AVAIL OFF I 800-(HEAT CAP 51721 IOPEN COOLING I CLG SHTDN RPU POWER PUf1P t1A PR H1 AVAIL OFF 400-4SRV LIFT! 11031 hggogg gggj{
p p
100 BPV 1025 P
P l
00 (MIID 0 RUCU UI
-1 TURBI'4E I CLG VAC H.PUR VALVEE CONTROL I AVAIL AVAIL AVAIL OPEH l RX POWER I 1001% (RESCALE) l SHUT lI TURBINE I CLG VAC H.PUR VALVE BYPASS IAVAIL AVAIL AVAIL 80-lSCRAli l 4 APRM DHSCL 51 f1SL COOLING V.PWR VALVE HOME DRAINS AVAILABLE HA SHUT 40-LIQUID POWER PUf1P l l AVAILABLE SLC I
AVAIL 0FF I g_0 (MIN) 0
-1 RIVER BEND 8 8 8 z s na ssse a:co:ce
.l f- -':'__fl l
[. ~ - f lO.l.; K. ; ;... -:. ;.,Q$:' _.]
[ _ff;.:'.QY;'.).jf-:) _ ;. ' y)t(s.l t
O O
O l 026
' RPV NORMAL i {l~l. T A '.'
v E Cl 1 R CI_
-l_I 38 E T / L R POOL LEVEL 19 FT 10 IN (RESCALE) l COOLING g NOT AVAIL PUMP l lNOTOPER POOL COOLING POWER DG POOL LD 26 SE AVAIL OFF
. OPER HI 20- 01 DRYWELL I COOLING I
FAN l 19_
COOLING I AVAILABLE l POWER AVAIL RUN u SRV 3
OPER LO 19-61 SHUT I
CNTMT I
C00LINC-POWER FAN l HEAT CAP: 0- 01 COOLING I AVAILABLE AVAIL OFF I ig.-W GIO O CONTROL lE OFF lI lGP0VP g
PRESS VALUE POWER FRN gL SHUT AVAIL CNTMT PRESS I 0.11PSIG l
{g
]
l SCgAy1 VALUE M MAXIMUM l 55.9l SBGT ggg 0
N I
4-( DESIGN 14.9l 0-l PR SUPPRI 9.81
-10 (MIN) O CNTMT TEl1P M 'F DW TEMP l 122] F POOL TEMP I 80E'F N(RPV SAT 15451 M RPV SAT 545]
M HEAT CAP' 157]
155-275-110-
)
4 DESIGN l185l
'4 DESIGN i3301 (SCRM TEMP 110']
)
120-200-95-I A OPER HIl 901 4 0PER Hill 351 OPER HI 951
-1 diDi)0
-10dini)0
-18diDI)^'0 RIVER BEND 8 8 8 Ys~ Eu N tr oa : =
r
+
[
rI
- qy:~.
RIVER 1500 STATION m
't Igrnm 10NI1 TIE j-
./
s 1988 EVAIA14'11tD 10ERCISH Tian = 0630-thanam >=har: -1 t'= 00 M O ID R=br Location (Tnel-ReMina D>it.1 Alarm RE-5A Fuel Bldg. Vent Exhaust F.B.148 *(WRGM)
- 1. 3E+00 uCi/sec RE-6A Radwast'e Bldg. Vent'Exh R.W.166.*(WRGM) 5.7E uCi/sec RE-125 lbin Plant Exhaust Duct A.B.170"(WRGM) 2.9E+01 uC1/sec.
RE-110P Aux.- Bldg. Vent A.B.141*(PAIU)
- 2. OE-12 uCi/cc RE-110G Aux Bldg. Vent A.B.141'(GAS) 3.0E-08 uCi/cc RE-118P Turbine Bldg. Vent T.B.123'(PAIE) 3.OE-10 uCi/cc RE-11BG v. Turbine Bldg. Vent T.B.123'(GAS) 1.0E-09 uCi/cc RE-124P Cond IhminNffgas Bldg. Vent (PAIU) 2.0E-10 uCi/cc 7_
r( -
RE-124G Cond Ihmin Nffgas Bldg. Vent (GAS) 2.0E-08 uCi/cc RE-126P thin Plant Exhaust Ibot A.B.141'(PART) 8.0E-10 uC1/cc RE-126G Ksin Plant Exhaust Dact A.B.141'(GAS) 7.0E-07 uC1/cc RE-111P Containnent Atm:ePMre R.B.162 * (PAfE) 6.SE-10 tCi/cc RE-111G Containnent AtnepMre B. B.162 * (GAS)
- 7. OE-07 uCi/cc RE-112P Drywell AtnepMre R.B.141'(PAIE) 4.9E-09 uCi/cc RE-112G Drywell Atirosphere R.B.141'(GAS) 4.0E-06 uCi/cc RE-103 SGTS Effluent A.B.141'(GAS)
- 2. 0E- 0G uCi/cc RE-116 Containm>nt Purge A. B.141 ~ (GAS)
- 3. OE-(6 uCi/cc
- - Indicates Alarm Wii - Offscale hirJ:
All Otkr Process h3nitors Are As Read b
pr; y a
HIVER LEND STATION
.g,q.
i
-IIts N EI10HS
' J
. Time = 0630
'1988 kVALUA1ED EXXHCISE Mensase Hunter: - 1
.t = 00/U0 u
IDJumber Location _(Typ )
Readina Bilta Alano RE-16A.B Containnent PAM R.B.186 * (DHRBM)
- 0. 8 R/hr' RE-20A B Drywell PAM D.W.114*(DHRRM) 3.O R/hr RE-21A,B Cont. Purge Isol. Monitor R.B.141 * (ARM) 9.O R/hr
' RE-139 Inside Annulus Hear Trans.Tuk 114 *(ARH)0.2 mR/hr
.RE-141 Refueling Floor South R.B.186'(ARM)
- 0. 2 -
nR/hr RE-146 Containnent Airlock F.B.114 *(ARM)'
O.3 nR/hr RE-151 Sample Station Area B.B.162 *(ARM)
- 5. O nR/hr RE-182 Recovery Sample Tank R.W.65'(ARM)
- 0. 4 '
nR/hr-RE-185 Storage Tank Area R.W.90*(ARM) 0.2 nR/hr RE-186 Floor Drain Sump Area R.W.65'(ARM) 0.5 nRAr RE-187 High Cond. Sump Area R.W.65'(ARM)
- 0. 5 nRAr RE-194 Support Room Transfer Tuk F.B.123'(ARM)0.2 nR/hr RE-195 Sample Sink Area F.B.95 * (ARM)
- 0. 5 nR/hr RE-200 North Hoist Area T.B.123 *(ARM)
- 0. 4 nRAr y
RE-201 Cond Air Renoval Pump Area T.B.95 *(ARM) 0.2 nR/hr RE-202 Rx Feedwater Pump Area T.B.67'(ARM)
- 1. 5 nR/hr RE-203 Turbine Ble'z Sample Room T.B 67 *(ARM) 0.1 na/hr RE-204 Cond D3 min Sample Rack T.B 95 *(ARM)
O.1 mR/hr RE-210 PASS Panel A.B.114 *(ARM)
O. 2 mR/hr RE-211 Control Rod Drive A.B.95 *(ARM) 0.1 nB/hr RE-212 HFCS Area East A. B.70 * (ARM) 0.09 nR/hr RE-213 RHR A Area West A.B.70'(ARM) 2.0 nR/hr RE-214 RER B Area East A.B.70 * (ARM) 2.0 nR/hr RE-215 RER C Area A. B. 70 * (ARM)
- 1. 0 nRAr RE-216 LFCS Area West A.B.70'(ARM)
- 0. 0 nRAr RE-217 HFC3 Penetration Area East A.B.70'(ASM) 0.7 nR/hr RE-218 LFCS Penetration Area West A.B.70'(ARM) 0.3 nR/hr RE-219 RCIC Area West A.B.70'(ARM)
- 0. 5 nR/hr
- - Irdicates Alarm CGH - Offscale high All Otler A.% Am As Read l
l O
m I
i I
Carolina Power & Light Cornpany
{
Brunswick Steam Electric Plant P. O. Box 10429 Southport, NC 28461-0429 July 31, 1987 FILE:
B09-13510C 10CF250.73 SERIAL:
BSEP/87-0860 NRC Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 BRUNSVICK STEAM ELECTRIC PLAhT UNIT 1 DOCKET NO. 50-325 LICENSE NO. DPR-71 LICENSEE EVENT REPORT 1-87 020 Gentlemen:
In accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted. This report fulfills the requirement for a written report within thirty (30) days of a reportable occurrence and is in accordance with the format set forth in NUREG-1022, Septe=ber 1983.
I Very truly yours, N wy C. R. Dietz, General Manager Brunswick Steam Electric Plant MJP/jih Enclosure cc:
Dr. J. N. Grace eN
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-