ML20041F830
| ML20041F830 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 03/11/1982 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Linder F DAIRYLAND POWER COOPERATIVE |
| Shared Package | |
| ML20041F831 | List: |
| References | |
| TASK-07-02, TASK-7-2, TASK-RR LSO5-82-03-069, LSO5-82-3-69, NUDOCS 8203170461 | |
| Download: ML20041F830 (6) | |
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March 11,1982
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co Docket No. 50-409
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Mr. Frank Linder g
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General Manager Dairyland Power Cooperative 2615 East Avenue South 4
Lacrosse, Wisconsin 54601
Dear Mr. Linder:
SUBJECT:
SEP TOPIC VII-2, ENGINEERED SAFETY FEATURES SYSTEM CONTROL LOGIC AND DESIGN, DRAFT SAFETY EVALUATION REPORT FOR LACROSSE BOILING WATER REACTOR
, is our contractor's draft technical evaluation of the subject for your plant. is the staff's draft safety evaluation and it is based on Enclosure 1.
The staff notes that the differences from current licensing criteria that our contractor identified in the report on SEP Topic VII-l.A are the same ones identified in Topic VII-2. Accordingly, we will address resolution of these differences in Topic VII-1.A and consider SEP Topic VII-2 to have been completed for Lacrosse.
Sincerely,
$M Dennis M. Crutchfield, Chief
.s Operating Reactors Branch No. 5 j
Division of Licensing
Enclosures:
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=,,1 Docket No. 50-409 LS05 Mr. Frank Linder General Manager Dairyland Power Cooperative 2615 East Avenue South Lacrosse, Wisconsin 54601
Dear Mr. Linder:
SUBJECT:
SEP TOPIC VII-2, ENGINEERED SAFETY FEATURES SYSTEM CONTROL LOGIC AND DESIGN, DRAFT SAFETY EVALUATION REPORT FOR LACROSSE BOILING WATER REACTOR
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l is our contractor's draft technical evaluation of the subju for your plant. is the staff's draft safety evaluation and i
it is based on Enclosure 1.
The staff notes that the defects that our contractor identified in the j
report on SEP Topic VII-1. A are the sanie ones identified in Topic VII-2.
i Accordingly, we will pursue these defects where they were first noted and l
consider SEP Topic VII-2 to have been completed for Lacrosse.
Sincerely, l
l Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing
Enclosures:
As stated cc w/ enclosures:
See next page E
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' Lacrosse
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Docket No. 50-409 l
~.Rev. 2/8/82' Mr. Frank Linder s
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Fritz Schubert,. Esquire U. 3. ~.Eavironmental ~ Protection Staff Attorney Agency Dairyland Power Cooperative Federal Activities Branch 2615 East Avenue South Region V Office La Crosse, Wisconsin 54601 ATTN:
Regional Radiation Representative 230 South Dearscrn Street O. S. Heistand, Jr., Esquire Chicago, Illinois 60604 Morgan, Lewis & Bockius 1800 M Street, N. W.
Mr. John H. Buck Washington, D. C.
20036 Atomic Safety anc Licensing Appeal Board U. S. Nuclear Regulatory Commission Mr. R. E. Shimshak Washington, D. C.
20555 La Crosse Boiling Water Reactor Dairyland Pow'er Cooperative Dr. Lawrence R. Quar.les P. O. Box 135 Kendal at Longwood, Apt. 51 Genoa, Wisconsin 54632 Kenneth Square, Pennsylvania 19348 Ms. Anne K. Morse Charles Bechhoefer, Esq., Chairman Coulee Region Energy Coalition Atomic Safety and Licensing Coard P. O. Box 1583 U. S. Nuclear Regulatory Commission 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, Washing +an 98195 U. S. Nuclear Regulatory Commission Resident Inspectors Office Mr. Ralph S. Decker Rural Route #1, Box 276 Route 4, Box 1903
. Genoa, Wisconsin 54632 Cambridge, Maryland 21613 1
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Town Chairman Thomas S. Moore Town of Genoa Atomic Safety and Licensing Appeal Board Route 1 U. S. Nuclear Regulatory Commission Genoa, Wisconsin 54632.
Washington, D. C.
20555 l
Chairman,'Public Service Commission Mr. George R. Nygaard of Wisconsin Couiee Region Energy Coalition Hill Farms State Of fice Building 2307 East Avenue
. Madison, Wisconsin 53702 Lacrosse, Wisconsin 54601 l
Alan S. Rosenthal, Esq., Chairman James G. Keppler, Regional Administrator Atomic Safety and Licensing Appeal Board Nuclear. Regulatory Commission, Region III U. S. Nuclear Regulatory Commission Office of Inspection & Enforcement Washington, D. C.
20555 799 Roosevelt Road Glen Ellyn, Illinois 60137 Mr. Frederick Milton Olsen, III 609 North lith Street Lacrosse, Wisconsin 54601
SYSTEMATIC EVALUATION PROGRAM TOPIC VII-2 LACROSSE Mb ty, VII-2, Engineered Safety Features (ESF) Systen Control Logic and Design 0:
TOPIC:
I.
INTRODUCTION D;rinc.the staff review cf the Safety Injection System (SIS) reset (issue (4 in I:UT.EG-0138) the staff determined that the Engineered Safety Features A:tuation Systems (E5FAS) at both Fi?Rs and B'..'Rs may have design features that raise cuestions abcut the independence of redundant channels, the intcracticn ci rese; f eat.res and 'ndividual equiprent centrois, and the interaction of the ESFAS logic that centrcis transf ers between en-site Review of the as-built logic diagrams and ard c'f-site pcuer sources.
schtmatics, cperatcr action requirec ;c supplement the ESFAS aut:matic actiens, the startup and surveillan:e testing precedures for de=cnstrating ESF.A5 performance appeared to be required.
e Several specific centerns exist with recard to the manual SIS reset feat-ure followine a LO~A.
They are:
(1) If a loss of offsite power occurs af ter reset, operator action would be required to remove normal shutdown cocling leads from the emergency bus and re-establish emergency coolin Time would be critical if the loss of offsite power occurred (2) If 1 css of offsite power oc-loacs.
within a few minutes following a LOCA. restart some essential loads such as cu-s t'ter rese:, s: e plants may ne(3) The pian; may suffer a loss. of ECCS d diesel coeling ca:er.
It fer sone time period before emercen:y power picks up th was als:
cl.:ir.; bypasses, ress; features and interactions with transfers between ensi e and cffsite ;;<er sources.
for re-
. Sin:e these cetisions were.ade in early 1977, the staff's plansTwo c sciving these issues have changed.
f t
tenera:Or prebiens have been conducted by Inspection and En orcemen.
In ad-in:1u:es censideration of typasses and resets.
ine se::nd revien is inv:1ved with reset anc by-titi:n, Test A::itn Flan Generic Task 5-2:
ce m:dified to reduce
- -di ;iy, :-is SE: -::i has ::
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de;iitatier, of effort.
cf ine staff's review of the s:cpe cf the severai related generic efforts and the other SEP Topics, it was decided that the As a resui:
area that had not been covered was the indepen the use of cc= mon controls such as mode switches, reset switches, trains.
locic test facilities.
4-
-2' II.
REVIEW CRITERIA The current licensing criteria are presented in Section 2 of EG&G Report 0072J. "ESF System Control Logic and Design."
III.
RELATED SAFETY TOPICS AND INTERFACES The scope of review for this topic was limited to avoid. duplication of effort since some aspects of the review were performed under related The reisted topics and the subject matter are identified below.
tcpics.
Ea;F cf the related 1 pic rep:rts centain the acceptan:e criteria and revieu cuidance fer its subjc:t matter.
!!!-E Scismi: Quali ficatier-131-11 Seismic Qualification 111-12 Environrental Qualificaticn Operatien with less than All Lceps in Operation IV-1.A Bypass and Reset of Engineered Safety Features (B-24)
VI-4 VI-7.A.3 ECCS Actua, tion System VI-7.E ESF Switchover from Injection to Recirculation VI-7.C.1 Independence of Onsite Power VI-7.C.2 Failure Mede Analysis-ECCS effect of loop isolation valve closu~re on ECCS performance VI-7.C.3 The Yi-7.D Leng Term Cooling Passive Failurec (e.g. ficoding)
Y]-7.T A:cumulat:r Isclatien Valves VI-10.A Testin; cf Reactor P,rotection Systems VI-10.5 Shared Systems V!:-i A Eeatter Trip System Isolation V::-3 Systers Eequited fer Safe Shutdown VI:!-2 Cnsite Emergency Fewer Systems VIII-3 Emergency d: Fewer Systems VIII 4 Electrical Fenetrations IX-3 Ventilation IT-f Fire Frctettien Tne c:r;igsien tr.it su.itarie isciEtien devi:es are previced is a basi:
ass. ;ti:r f:r T:;ic! Y:-7.C.2 and VI'-3.
IV.
REVIEW GUIDELINES The review guidelines are presented in Section 3 of EG&G. Report 0072J.
V.
EVALUATION A description of.the isolation devices employed in Lacrosse and a compari-son with current design criteria are presented in EG&G Report 0072J.
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VI.. CONCLUSION As a result of our review of our contractor's work the sta'ff concludes that-Lacrosse conforms to current licensing criteria for electrical isolation of redundant safety features, except for those items noted previously in SEP Topic VII-1.A.
Because no new issues have been pre-sented and.the old issues are being, pursued under SEP Topic VII-1.A,
..the staff considers SEP Topic VII-2 to have been completed.
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