ML20041C107
| ML20041C107 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 02/22/1982 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Linder F DAIRYLAND POWER COOPERATIVE |
| References | |
| TASK-05-11.A, TASK-5-11.A, TASK-RR LSO5-82-02-089, LSO5-82-2-89, NUDOCS 8202260198 | |
| Download: ML20041C107 (5) | |
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.y February 22, 1982 A
Docket No. 50-409 LS05-82 089 g
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Mr. Frank Linder 6
General Manager E1 k%7 hl Dairyland Power Cooperative J
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3 ff Lacrosse, Wisconsin 54601 e
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Dear Mr. Linder:
SUBJECT:
SEP TOPIC V-11.A, ISOLATION OF HIGH AND LOW PRESSURE SYSTEMS, REVISED SAFETY EVALUATION REPORT - LACROSSE The enclosed-revised staff safety evaluation is based on a contractor's evaluation that has been made available to you previously and Amendment 24 to your licensee. As a result of these two previous documents, the w^
staff finds that Lacrosse satisfies the acceptance criteria for this topic.
This topic assessment may be revised in the future if your facility design is changed or if NRC criteria relating to this topic are modified before the integrated assessment is completed.
Sincerely,
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Dennis !!. Crutchfield, Chief Operating Reactors Branch Ho. 5:
Division of Licensing
Enclosure:
Safety Evaluation Report 1
(Revised) cc w/ enclosure:
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NRC FORM 3i8 (10-80) NRCM 024c (
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Docket No. 50-409 LS05 Mr. Frank Linder General Manager Dairyland Power Cooperative 2615 East Avenue South Lacrosse, Wisconsin 54601
Dear Mr. Linder:
StBJECT: SEP TOPIC V-ll.A. ISOLATION OF HIGH AND LOW PRESSURE SYSTEMS, REVISED SAFETY EVALUATION REPORT - LACROSSE The enclosed revised staff safety evaluation is based on a contractor's evaluation that has been made available to you previously. This evaluation supports the findings of the enclosed staff safety evaluation on Topic V-ll.A that proposes modifications to the check valve design or institution of a test program.
The need to actually implement these changes will be determined during the integrated plant safety assessment. This topic assessment may be revised in the future if your facility design is changed or if NRC criteria relating to this topic are modified before the integrated asnssment is completed.
Sincerely, Dennis M. Crutchfield, Chief Operating P.eactors Branch f5 Division of i.icensing
Enclosure:
Safety Evaluation Report (Revised) cc w/ enclosure:
See next page
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.t' Mr. Frank Linder i
CC-Fritz Schubert, Esquire U. S. Environmtntal. Protection Staff Attorney Agency Dairyland Power Cooperative Federal Activities Branch 2615 East Avenue South Region Y Office La Crosse, Wisconsin 54601 ATTN: Regional Radiation Representative 230 South Dearbo?n 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 and Licensing Appeal Board U. S. Nuclear Regulatory Commission Mr. R. E. Shimshak Washington, D. C.
20555 La Crosse Boiling Water Reactor Dairyland Power Cooperative Dr. Lawrence R. Quarles 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 Board 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, Washington 98195 U. S. Nuclear Regulatory Commission Resident Inspectors Office Mr. Ralph S. Decker Rural Rcute #1, Box 276 Route 4, Box 190D
. Genoa, Wisconsin 54632 Cambridge, Maryland 21613 Town Chairman Thomas S. Moore Town of Genoa Atomic Safety and Licensing Appeal Board Route 1 U. S. Nuclear Regulatory Commission l
Genoa, Wisconsin 54632 Washington, D. C.
20555 t
l Chairman, Public Service Commission l-of Wisconsin l
Hill Farms State Office Building i
Madison, Wisconsin 53702 Alan S. Rosenthal, Esq., Chairman
. Atomic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Commission Washington, D. C.
20555
. Mr. Frederick Milton Olsen, III 609 North lith Street Lacrosse, Wisconsin 54601 9
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TOPIC:
V-11. A - REQUIREMENTS FOR ISOLATION OF HIGH AND LOW PRESSURE SYSTEP6 I.
INTRODUCTION Several systems. that have a relatively low design pressure are connected to the reactor coolant pressure boundary.
The valves that form the interface between. the.high and low pressure systens must have sufficient redundancy and interlocks to assure that the low pressure systems are not subjected to coolant pressures that exceed design limits. The problem is complicated since under certain operating modes (e.g., shutdown cooling and ECCS injection) these valves must open to assure adequate reactor
, s a fe ty.
II.
REVIEW CRITERIA The~ review criteria are presented in S,ection 2 of EG&G Report 1365.
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 topics. The related topics and the subject matter are identified below. Each of the related topic reports contain the criteria and review guidance for its subject matter.
V-3 Overpressurization Protection V-10.B RHR Reliability VI-4 Containment Isolation XV-16 Radiological Consequences of Small LOCA Outside of Containment Topic V-11.8 is cependent on the present topic information for completi on.
~IV.
- REVIEW GUIDELINES -
The review guidelines are presented in Section 7.3 of the Standard Review Plan.
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4 V.
EVALUATION e
As noted in EG&G~ Report 1365F Lacrosse has one system with a lower design pressure rating than the RCS which is directly' connected to the RCS. The CS system meets current licensing criteria contained in SRP 6.3 for isolation of high and low pressure systems ex. cept for_ the testability requirements for the series check valves in the line from the diesel-driven core spray pumps.
However, Amendment
. 24 dated February 25, 1981 approved a test program for these valves.
VI.
CONCLUSIONS Based on the staff safety evaluation that is a part qf Amendment 24, the staff concludes that the present design and testing program -
satisfies our requireme.nts.
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