ML19343A605
| ML19343A605 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 09/26/1980 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Linder F DAIRYLAND POWER COOPERATIVE |
| 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-6-8, TASK-RR NUDOCS 8011190112 | |
| Download: ML19343A605 (5) | |
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UNITED STATES v
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.7 Docket No. 50-409 p;.;;
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Mr. Frank Linder tn General Manager Dairyland Power Cooperative 2615 East Avenue South La Crosse, Wisconsin 54601
Dear Mr. Linder:
By letter dated Noveraber 16, 1979, we sent you the list of topics which would not be reviewed by your plant in the Systematic 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) related generic NRC activities and 2) non-applicability of topics to certain facilities.
The following is a list of such topics and indicates their disposition:
Topic Categorization Disposition Il-2.B Generic Conpliance with Appendix E is being evaluated under the Emergency Prepardness Program Office (EPPO) effort.
Conpliance with Appendix I is being evaluated as part of the NRC Appendix I review effort.
11-2.0 Generic Compliance is being evaluated under the EPP0 effort.
a III-8.B Deleted The review published as NUREG-0479,
" Report on BWR Control Rod Drive Failures" fulfills the intent of this topic.
VI-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 l'.-l.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 801uno IIS
i Mr. Frank Linder September 26, 1980 1
part of Topic XV-13. However, the topic of reference should be Topic XV-8,
" Control Rod Misoperation" and accordingly the references for Topic kV-8 should include Standard Review Plans 15.4.1 and 15.A.2.
Also, the dovember
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16, 1979, letter states that DBE Group X, " Inadvertent Operation of ECCS or CVCS Malfunction that Causes an increase in Reactor Coolant Inventory" i
i 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 BPR's.
! to this letter includes a revised listing of the DBE Ar.cident 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
.of Fuel Handling Accidents in Group Vill.
Sincerely, Dennis M. Crutchfield, ief Operating Reactors Branch #5 Division of Licensing
Enclosure:
4 As stated cc w/ enclosure:
See next page J
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. September 26, 1980 Mr. Frank Linder cc
, Fritz Schubert, Esquire Director, Technical Assessment Staff Attorney Division Dairyland Power Cooperative Office of Radiation Programs 2615 East Avenue South (AW-459)
La Crosse, Wisconsin 54601 U. S. Environmental Protection Agency G. S. Heistand, J r., Esquire Crystal Mall #2 Morgan, Lewis & Bockius Arlington, Virginia 20460 1800 M Street, N. W.
Washington, D. C.
20036 U. S. Environmental Protection Agency Mr. R. E. Shimshak Federal Activities Branch La Crosse Boiling Water Reactor Region V Office Dairyland Power Cooperative ATTN: EIS C0ORDINATOR P. O. Box 135 230 South Dearborn Street Genoa, Wisconsin 54632 Chicago, Illinois 60604 Coulee Region Energy Coalition Charles Bechhcefer, Esq., Chairman ATTN: George R. Nygaard Atomic Safety and Licensing Board P. O. Box 1583 U. S. Nuclear Regulatory Comission La Crosse, Wisconsin 54601 Washington. D. C.
20555 La Crosse Public Library Dr. George C. Anderson 800 Main Street Department of Oceanography La Crosse, Wisconsin 54601 University of Washington Seattle, Washington 98195 Mrs. Ellen Sabelko Society Acainst Nuclear Energy Mr. Ralph S. Decker 929 Cameron Trail Route 4, Box 1900 Eau Claire, Wisconsin 54701 Cambridge, Maryland 21613 Town Chairman Dr. Lawrence R. Quarles Town of Genoa Kendal at Longwood, Apt. 51 Route 1 Kenneth Square, Pennsylvania 19348 Genoa, Wisconsin 54632 Thomas S. Moore Chairman, Public Service Comission Atomic Safety and Licensing Appeal Board of Wisconsin U. S. Nuclear Regulatory Comission Hill Farms State Office Building Washington, D. C.
20555 Madison, Wisconsin 53702 Ms.' Anne K. Horse Alan S. Rosenthal, Esq., Chairman Coulee Region Energy Coalition Atomic Safety and Licensing Appeal Board Post Office Box 1583 U. S. Nuclear Regulatory Comission Lacrosse, Wisconsin 54601 Washington, D. C.
20555 U. S. Nuclear Regulatory Comission Mr. Frederick Milton Olsen, III Resident Inspectors Office 609 North lith Street Rural Route #1, Box 225 Lacrosse, Wisconsin Genoa, Wisconsin 54632 i
BWR DBE TOPIC LIST Accident and Transient Groups RELATED TOPIC DESIGN BASIS EVENT SRP I
XV-1 Decrease in feedwater temperature 15.1.1 Grou$
(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 4
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 pressure regulatory f ailure 15.2.5 XV-5 Loss of feedwater flow 15.2.7 Group III XV-18' Radiological Consequences of a 15.6.4 Main Steam Line Failure Outside Containment Group IV XV-4 Loss of AC power to station 15.2 6 auxiliaries XV-24 Loss of all AC power Group 'l XV-7 Loss of forced coolant flow 15.3.1 XV-7 Primary pump rotor seizure 15.3.3 XV-7 Primary pump shaft break 15.3.4 Group VI XV-8 Uncontrolled rod assembly withdrawal 15.4.2 at power XV-8 Uncontrolled rod as!.embly 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 outside containment) o Group IX XV-15 Inadvertent opening of BWR safety /
15.6.1 relief valve 4roup X XV-14 Inadverter,t Operation of ECCS 15.5.1 Group XI XV-11 Inadvertent loading and operation of 15.4.7 a fuel assembly in an improper position Group XII Not applicable to BWRs
SRP RELATED GROUP SEP TOPIC DESIGN BASIS EVENT _
SECTION VI XV-8 Uncontrolled rod assembly withdrawal 15.4.2 at power Uncontrolled rod assembly withdrawal 15.4.1 XV-8 low power start-up XV-8 Control rod misoperaticn 15.4.3 15.4.9 XV-13 Spectrum of rod drop accidents VII XV-19 Spectrum of rod drop accicents 15.6.5 VIII XV-20 Radiological consequences of fuel 15.7.4 damaging accidents (inside and outsiae containment)
XV-21 Drop of cask or heavy equipment 15.7.5 IX XV-15 Inadvertent opening of BSR safety /
15.6.1 relief valve X
XV-14 Inadvertent operation of ECCS 15.5.1 XI XV-11 Inadvertent loading and operation of 15.4.7 a fuel assembly in an improper position Not applicable to BWR's XII PWR DBE LIST GROUP RELATED SRP SECTION SEP TOPIC _DESIGt BASIS EVENT 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 XV-10 System malfunction causing a 15.4.6 decrease in boron concentration 11 XV-3 Loss of external load 15.2.1 f
15.2.2 XV-3 Turbine trip XV-3 Loss of condenser vacuum 15.2.3 XV-3 Steam pressure regulatory failure 15.2.5 XV-5 Loss of feedwater flow 15.2.7 XV-6 Feedwater system pipe break 15.2.8
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