ML20054L905
| ML20054L905 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 06/30/1982 |
| From: | Emch R Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8207090052 | |
| Download: ML20054L905 (14) | |
Text
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June 30, 1982 So-I6 LISENSEE: CONSUMERS POWER COMPANY FACILITY: Big Rock Point Plant
SUBJECT:
SumARY OF MEETING UITH CONSUMERS POWER C0"PANY ON JUNE 28, 1982 On June 20, 1982, representatives of Consumers Power Company (CPC) net with the t'RC staff in Bethesda, Maryland (attendence list attached) to discuss the subject of minimum shift staffing at Big Rock Point.
F. Bucknan of CPC introduced the meeting and D. VandeWalle de. scribed their use of the Probablistic Rick Assessment (PRA) in licensing activities for Bio Rock Point. Then D. Blanchard presented the Operator Action Event Tree Analysis for Big Rock Point, and the CPC proposal for minimum shift staffing requirements at Big Rock Point. The operator a l'
action event tree analysis is based on the PRA, and CPC believes that i
the analysis supports their claim that they do not need on shift (1) a second Senior Reactor Operator (SRO), (2) a Shift Technical Advisor (STA),
or (3) a second rad /chen, technician at Big Rock Point. They propose that the STA be on-call and that the STA be SR0 trained and qualified, but not licensed. The slides from CPC's presentation are attached.
D. Hoffman provided a brief discussion of the cost-effectiveness of continuing to operste Big Rock Point.
CPC has submitted a proposal on minimun shift staffing. That recommendation along with the operator action event thee analysis is under review by Division of Hunan Factors and Division of Safety Technology in MRR and Division of Energency Preparedness in IE.
B. Grimes asked CPC how they would perform all the steps necessary to fully implenent the plant emergency plan (i.e., offsite notifications, comunications, dose assessment) if all of the shift people were busy trying to maintain the plant in a safe condition. After some discussion, F. Buckman indicated that CPC would provide a more detailed answer to that question at a later date.
Original signed by Richard Emch, Project Manager Operating Reactors Branch #5 8207090052 820630 PDR ADOCK 05000155 Division of Licensing P
PDR Attachments:
QN As stated cc w/ attachments:
pC# df5 gg See next page OFFICE )... t...h..h....h..
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outy OFFICIAL RECORD COPY usaronsu-us-oea unc ronu sis oo. son nacu o24a
. June 30, 1982 cc Mr,. Paul A. Perry, Secretary U. S. Environmental Protection Consumers Power Company Agency 212 West Michigan Avenue Federal Activities Branch Jackson, Michigan 49201 Region V Office ATTN:
Regional Radiation Representative Judd L. Bacon, Esquire 230 South Dqarborn Street Consumers Power Company Chicago, Illinois 60604-212 West Michigan Avenue
' Jackson, Michigan 4920i, Peter B. Bloch, Chairman Atomic Safety and Licensing Board Joseph Gallo, Esquire U. S. Nuclear Regulatory Commission Isham, Lincoln & Beale Washington, D. C.
20555 1120 Connecticut Avenue Room 325 Dr. Oscar H. Paris Washington, D. C.
20036 AAomic Safety and Licensing Board U. 5, Nuclear Regulatory Commission Peter W: Steketee, Esquire Washington, D. C.
20555 505 Peoples Building Grand Rapids, Michigan 49503 Mr. Frederick J. Shon Atomic Safety and Licensing Board
. Alan S. Rosenthal, Esq., Chairman U. S. N0 clear Regulatory Commission
~~~
Atomic Safety & Licensing Appeal Board Washington, D. C.
20555 U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Sig RosLPoint Nuclear Power Plant 9*
ATTN:
Ex.C. J. Hartman
.r.
Mr. John O'Neill, II FTant Superintendent Route 2, Box 44 Charlevoix, Michigan 49720
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Maple City, Michigan 49664
,e Christa-Maria
'"' MF. J im E. Mill s Route 2, Box 108C Route.2, Box 108C Charlevoix, Michigan -49720 Charlevoix, Michigan 49720 William J. Scanlon, Esquire Chairman 2034 Pauline Boulevard County Board of Supervisors Ann Arbor, Michigan 48103 Charlevoix County Charlevoix, Michigan 49720 Resident Inspector TE Big Rock Point Plant
'0'ffice'of the Governor (2) c/o U.S. NRC Room 1 - Capitol Building RR #3, Box 600
,. Lansing, Michigan 48913 Charlevoix, Michigan 49720
~~
~ Herbert Semmel Hurst & Hanson
_;c-Counsel for Christa Maria, et al.
311 1/2 E. Mitchell Urban Law Institute Petoskey, Michigan 49770 Antioch School of Law 2633 16th Street, NW Washington, D. C.
20460 a
A.,
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.-L 1-s 3-June 30, 1982 CC Dr. John H. Buck Atomic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Ms. JoAnn Bier 204 Clinton Street Charlevoix, Michigan 49120 Thomas S. Moore Atomic Safety and Licensing Appeal Board
. U. S. Nuclear Regulatory Commission Washington, D. C.
20555 James G. Keppler, Regional Administrator Nuclear Regulatory Commission, Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 I
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- Attachment 1 L
NRC/CPC MEETING 6/28/82 Name ORG.
R. Huston CPC
~
R. Scholl NRC-D. Blanchard CPC G. Lainas NRC H. Thompson NRC R. Benedict NRC L. Crocker NRC R. DeFayette NRC W. Axelson Region III B. Grimes NRC T. Bordine CPC F. Buckman CPC R. Emch NRC D. Crutchfield NRC D. Hoffman CPC D. VandeWalle CPC
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9
Probabilistic Risk
- Assessment Status and Plans Review by Staff and Consultants (EG&G, Brookhaven) Is Nearly Co=plete e
Continuing Risk Manage =ent Program (CRMP) Is In Place e
Regulatory Issues Identified for Resolution with PRA o
e Recirculation Pu=p Trip e Wide Range Reactor Vessel Level e Plant Shielding e Post Accident Sa=pling Capability Isolation of E=ergency Condensor on High Radiation e
.e Interlockson Recire Pu=p Loop Isolation Valves e TSC and Control Roo=s Habitability e Heavy Loads (NUREG-0612) e i
e Systematic Evaluation Program Integrated Assessment e Shift Manning e Diverse Scram Du=p Tank Level Instrumentation e Fire Protection (1DCFR50 Appendix R) e Regulatory Issues Being Considered for Resolution with PRA e-i e Electrical E.quipment Qualification
/
e Seismic Design e Other PRA Applications 1
Accident and Transient Response Training for Operations Personnel e
l Training in Recognition and Classification of Emergencies for Plant e
Management Personnel
^
3,s peeg*pe,jr^ RAM'T M iainuxi Smer i
0MPL EMEN7~
j Geaceic l.ErrEe 81-10 i
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Sillri SUPERVt6cR (SRO) l 2
CourRot OpsRAroRs CRo) 2 AUxILLtARY O PERATbR$
6 TOTAL PLUS AS Ol=
.JANo4RY 1981 ~
l SHIFT TECHHtc4L Avvisse I
l-IP/ CHEM TEcHNiltAN VALL l981 i
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' DEVELOPE DAET 'S
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SEl.EcT MOST U ELY ACCIDEh A ND
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SEQUENCES FROM THE BIG ROCK ktMT PRA.
2.
TDENrtff PLANT CONDirtoHS AT EACH BRANCH
...I OF THE SELECTEb SEQUEAJCES.
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EkpAND EACH SELECTED SEQUENCE BY INCLUbjd6 IN SOME DETAll OPERAroR Acricas Watch Cout.D TERMINATE OR MITIGATE THE TRANSIENT i
AT EACH 8eANCH.
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Z'DENTIFY SWICT STAfr/Ns REQ 0IREMENrS
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'DETE2MtME 7tME FRAME * /N WHICH Or-ERATot ACTioW MUST TAKE ~ PLACE tN ORDER To BE
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THAT THESE SKILLS ARE REQUIRED.
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SAFETIES CONDENSER COOLING AUTOMAT-VALVES LIFT HAKEUP (REPAIRS ICALLY PIS)
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Tablo 3.2 BRP SHIFT STAFFING REQUIREMENTS FOR OAET SEQhENCES SEQUENCE STAFFING REQUIREMENTS 1.
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- for long-term actions
- HP possibly needed to monitor airborne activity. (HP may not be essential as biopacks are required for these situations).
Auxiliary Operator A
Reactor Operator Numbers indicate different individuals R
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t SRO - Senior Reactor Operator HP - Health Physicist M
- Maintenance 23 w
1 ComptereNess of CAETh I.
OPERATOR bCTIONS IDENTIStED /N TN/S STUDY /NCLUDE
- Acricas iceNrivieD iH OPERATING, OFF-NORNIAL, AND ErAEEGENCY PRcLEDO.EES Acrions iDeNrtfiED As IMpoRTANT '/N THE '
8/G ROCK PC/WY PRA ACTtoNS CONSERVATIVELY /GNORED IN TH E ~PRA OR hf67 tHClubEb /N ExtSTiNG ~PeoCEbo&ES WHICH DOTENTIALLY COOLD E?E MITtG ATIVE
- 2. DEVELopEMENT OV THE
,OAET's NA s AN ITERATIVE PROCESS.
- PLANT STAFF, OPERArtoNs, AHb
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MAINTENAhlCE PERSONNEL WERE INVOLVEb IN OAET DEVELOPElviENT 3.
T//E OA'ET 3
/NCLubE 4LL '7tMSIENT AHb ACLtDENT IHsTiATOQ$
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OPERATbR AC.TioMS MUST TAKE PLACE A.
THE
~DotArM AMT ACCIDEHr SEQUENCES IDENTiFiEb IN THE 8is ELCid ~PorHT PRA WERE RE EkAMENEb AND CATEGO9ttED UNDEe THE CAET's 70 INSORE
- thE OAET 3 INCluDEb All *PCTENTIAL.
OPERATOR Ac7tetJ5
- A_CornEETE RANGE of 'rtME_ FRAMES 569 JENCHLPERA752 ACTibN WA6 IbENTfffEb
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LOCA INStbE CcNTAiHMENT WHICd tN Lj Di.5ABLE5 CORC SPRAT t
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MEETING
SUMMARY
DISTRIBUTION Docket NRC PDR l
Local PDR ORB Reading f; SIC DCrutchfield HSmith REmch OELD OI&E i
ACRS (10)
SEPB i'
SVarga DVassallo RClark JStolz' HDenton DEisenhut.
HThompson BGrimes 1
JZwolinski LCrocker RDeFayette RBenedict Glainas t
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