ML19339C276
| ML19339C276 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 09/26/1980 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| TASK-02-02.B, TASK-02-02.D, TASK-03-08.B, TASK-06-08, TASK-15-08, TASK-15-14, TASK-15-8, TASK-2-2.B, TASK-2-2.D, TASK-3-8.B, TASK-6-8, TASK-RR NUDOCS 8011180019 | |
| Download: ML19339C276 (5) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION 3
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September 26, 1980 Docket No. 50-155 g
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Mr. David P. Hoffman s
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Nuclear Licensing Administrator O
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Consumers Power Conpany 212 West Michigan Avenue Jacison, Michigan 49201
Dear Mr. Hoffman:
By letter dated November 16, 1979, we sent you the list of topics which would not be reviewed by your plant in the Systes..atic Evaluation Program (SEP).
These topics were deleted from the SEP review because they were not applicable to your plant or they were being reviewed as part of an ongoing generic issue outside the SEP.
The following topics should be added to the November 16 listing.
Removal of these additional topics from the SEP review results from 1) i elated generic NRC activities and 2) non-applicability of topics to certain f acilities.
The following is a list of such topics and indicates their disposition:
Topic Categorization Disposition 11-2.B Generic Compliance with Appendix E is being evaluated under the Emergency Prepardness Program Office (EPPO) effort.
Compliance with Appendix I is being evaluated as part of the NRC Appendix I review effort.
11-2.0 Generic Conpliance is being evaluated under the EPPO effort.
1
%III-8.B Deleted The review published as NUREG-0479,
" Report on BWR Control Rod Drive i
- Failures" fulfills the intent of this topic.
=
UJ-8 Generic Will be reviewed by NRC as part of TMI Task Action Plan (NUREG-0660) as specified in May 7, 1980 letter to all operating reactor licensees.
Those parts of Topic II-1.B " Population Distribution" relating to emergency plans will be evaluated,by EPPO.
In addition, the original DBE review list indicated that DBE group VI events " Uncontrolled Rod Assembly Withdrawal at Power and " Uncontrolled Rod Assembly Withdrawal - Low Power Startup" are a.
801118 0Ol7 12
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Mr. David P. Hoffman September 26, 1980 j
part of Topic XV-13'.
However, the topic of reference should be Topic XV-8,
" Control Rod Misoperation" and accordingly the references for Topic XV-8 should include Standard Review Plans 15.4.1 and 15.4.2.
Also, the November 16, 1979, letter states that DBE Group X, " Inadvertent Operation of ECCS 1
or CVCS Malfunction that Causes an Increase in Reactor Coolant Inventory" should be deleted as it applies only to PWR's.
However, Group X will be included in the SEP review since inadvertent operation of ECCS should be evaluated for BWR's.
. to this letter includes a revised listing of the DBE Accident and Transient Groups applicable to BWR's. Of note should be.the' inclusion of Group XI, " Inadvertent Loading and Operation of a Fuel Assembly in an Improper Position", revision' to Group III to include " Radiological Conse-quences Of a Main Steam Line Failure Outside Containment", and the Inclusion l
of' Fuel Handling Accidents in Group VIII.
Sincerely, t
lY
. Crutchfield, @ fef 7 ennis Operating Reactors Branch #5 Division of Licensing
Enclosure:
As stated cc w/ enclosure:
See next page i
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1 Mr. David P. Hoffman September 26, 1980 1
CC Mr. Paul A. Perry, Secretary V. S. Environmental Protection Consumers Power Company Agency 212 West Michigan Avenue Federal Activities Branch i
Jackson, Michigan 49201 Region V Office ATTN:
EIS C0ORDINATOR Judd L. Bacon, Esquire 230 South Dearborn Street Consumers Power Conpany Chicago, Illinois 60604 212 West Michigan Avenue Jackson, Michigan 49201 Herbert Grossman, Esq., 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 Atomic Safety and Licensing Board U. S. 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 Sheldon, Harmon and Weiss V. S. Nuclear Regulatory Commission 1725 I Street, N. W.
Washington, D. C.
20555 Suite 506 Washington, D. C.
20006 Big Rock Point Nuclear Power Plant ATTN:
Mr. C. J. Hartman Mr. John O'Neill,11 Plant Superintendent Route 2, Box 44 Charlevoix, Michigan 49720 Maple City, Michigan 49664 Chri sta-Maria Charlevoix Public Library Route 2, Box 108C 107 Clinton Street Charlevoix, Michigan 4972L Charlevoix, Michigan William J. Scanlon, Esquire Chai rman 2034 Pauline Boulevard County Board of Supervisors Ann Arbor, Michigan 48103 Charlevoix County Charlevoix, Michigan 49720 Resident Inspector Big Rock Point Plant Office of the Governor (2) c/o U.S. NRC Room 1 - Capitol Building RR #3, Box 600 Lansing, Michigan 48913 Charlevoix, Michigan 49720
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Director, Technical Assessment Division Office of Radiation Prograns (AW-459)
U. S. Environmental Protection Agency Crystal Mall #2 Arlington, Virginia 20460
l BWR D8E TOPIC LIST Accident and Transient Groups RELATED TOPIC DESIG'l BASIS EVE *!T SRP Group I XV-1 Decrease in Taedwater temperature 15.1.1
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(BWR)
XV-1 Increase in feedwater flow 15.1.2 XV-1 Increase in steam flow 15.1.3 XV-9 Start-up of inactive loop and flow 15.4.4, 5 controller malfunction XV-3 Inadvertent closure of main steam 15.2.4 isolation valve Group II XV-3 Loss of external load 15.2.1 XV-3~
Turbine trip 15.2.2 XV-3 Loss of condenser vacuum 15.2.3 XV-3 Steam pres.ure reculatory failure 15.2.5 XV-5 Loss of feedwater flow 15.2.7 l
l Croup III XV-18 Radiological Consequences of a 15.6.4 Main Steam Line Failure Outside i
l Containment Group IV XV-4 Loss of AC power to station 15.2.6 auxiliaries XV-24 Loss of all AC power Grouc V XV-7 Loss of forced coolant flow 15.3.1 XV-7 Primary pump rotor seizure 15.3.3 XV-7 Primary pu :p shaft break 15.3.4 Group VI XV-8 Uncontrolled rod assembly withdrawal 15.4.2 at power XV-8 Uncontrolled rod assembly withdrawal 15.4.1 low power start-up XV-8 Control rod misoperation 15.4.3 XV-13 Spectrum of rod drop accidents 15.4.9 Group VII XV-19 Spectrum of loss of coolant accidents 15.6.5 Group VIII XV-21 Drop of cask or heavy equipment 15.7.5 XV-20 Radiological Consequences of Fuel 15.7.4 Damaging Accidents (inside and l
outside containment) l l
Group IX XV-15 Inadve: tent opening of BWR safety /
15.6.1 relief valve broup X XV-14 Inadvertent operation of ECCS 15.5.1 Group XI XV-ll Inadvertent loading and operation of 15.4.7 l
a fuel assembly in an improper
-position Group XII Not applicable to BWRs a
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l 2-BWR DBE LIST _ (continued)'
-RELATED SECTION GROUP SEP TOPIC DESIGN BASIS EVENT _
Uncontrolled rod assembly withdra. val 15.4.2 VI XV-8 at power Uncontrolled rod assembly withdrawal 15.4.1 XV-u low power start-up XV-8 Control rod misoperation 15.4.3 15.4.9 XV-13 Spectrum of rod drop accidents 15.6.5 i
VII XV-19 Spectrum of rod drop accioents l
VIII XV-20 Radiological consequences of fuel 15.7.4 damaging accidents (inside and j
outside containment) 15.7.5 Drop of cask or heavy equipment XV-21 IX XV-15 Inadvertent opening of BSR safety /
15.6.1 relief valve j
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XV-14 Inadvertent operation of ECCS 15.5.1 XI XV-11 Inadvertent loading and operation of 15.4.7 a fuel assemoly in an improper position Not applicable to BWR's XII
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GROUP RELATED SRP SEP TOPIC _ DESIGN BASIS EVENT SECTION i
I XV-1 Decrease in feedwater temperature 15.1.1 XV-1 Increase in'feedwater flow 15.1.2 XV-1 Increase in steam flow 15.1.3 XV-1 Inadvertent opening of steam 15.1.4 generator relief / safety valve XV-9 Start-up of inactive loop 15.4.4 i
XV-10 System malfunction causing a 15.4.6
-decrease in boron concentration II XV-3 Loss of external load 15.2.1
.XV-3 Turbine trip 15.2.2 XV-3 Loss of condenser vacuum 15.2.3 XV-3 steam pressure regulatory failure 15.2.5 3
XV-5 Loss of feedwater flow 15.2.7 XV-6 Feedwater system pipe break 15.2.8 x--
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