ML20004B917

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Forwards Request for Addl Info in Support of Review of SEP Topic VI-04 Re Containment Isolation Sys.Response Requested within 30 Days.Distribution List Encl
ML20004B917
Person / Time
Site: La Crosse File:Dairyland Power Cooperative icon.png
Issue date: 05/26/1981
From: Crutchfield D
Office of Nuclear Reactor Regulation
To: Linder F
DAIRYLAND POWER COOPERATIVE
References
TASK-06-04, TASK-6-4, TASK-RR LSO5-81-05-053, LSO5-81-5-53, NUDOCS 8106010308
Download: ML20004B917 (6)


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UNITED STATES NUCLEAR REGULATORY COMMISSION

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,f May 26, 1981 Docket No. 50-409 LS05 05-053 Mr. Frank Linder General Manager Dairyland Power Cooperative 2515 East Avenue South Lacrosse, Wisconsin 54601

Dear Mr. Linder:

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR SEP TOPIC VI-4, CONTAINMENT ISOLATION SYSTEMS (LACROSSE)

During our review of SEP Topic VI-4, Containment Isolation Systems, we found that additional information (see enclosed) is needed to complete our review.

Please provide your response witnin 30 days of receipt of this letter so that our evaluation can be completed in a timely manner.

, Sincerely, Dennis M. Crutchileid, hief Operating Reactors Bra ch No. 5 Division of Licensing

Enclosure:

Request for Additional Information cc w/ enclosure:

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Mr. Frank Linder cc Fritz Schubert, Esquire Director, Standards and Criteria Staff Attorney Division Dairyland Power Cooperative Office of Radiation Programs 2615 East Avenue South (ANR-460)

La Crosse, Wisconsin 54601 U. S. Environmental Protection Agency

0. S. Hei stand, J r., Esquire Washington, D. C.

20460 Morgan, Lewis & Bockius 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 ATTH: EIS COORDINATOR P. O. Box 135 230 South Dearborn Street Genoa, Wisconsin 54632 Chicago, Illinois 60604 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.

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La Crosse Public Library Dr. George C. Anderson 800 Main Street Department of Oceanography la Crosse, Wisconsin 54601 University of Washington Seattle, Washingtci. 98195 U. S. Nuclear Replatory Commission Resident Inspectors Office Mr. Ralph S. Oecker Rural Route #1, Box 225 Pr.'te 4, Box 1900 Genoa, Wisconsin 54632 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 Commission Atomic Safety and Licensing Appeal Boad of Wisconsin U. S. Nuclear Regulatory Cornission Hill Farms State Office Building Washington, D. C.

20555 Madison, Wi tonsin 53702 Mr. John H. Buck Alan S. Rosenthal, Esq., Chairman Atomic Safety and Licensing Appeal Boant Atomic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Commission U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Washington, D. C.

20555 U. S. Nuclear Regulatory Commission Mr. Frederick Milton Olsen, III Resident Inspectors Office 609 North lith Street Rural Route #1, Box 225

-LaCresse, Wisconsin Genoa, Wisconsin 54632 a

Request for Additional Informaticn SEP Topic VI-4 Containment Isolation Re ferences:

Lacrosse Boiling Water Reactor, Application for Operating License. October 1974 LAC 3WR Responses to IE Bulletin 79-08:

LAC-6256, April 27,1979 LAC-6262, May 2, 1979 LAC-6297, May 18,1979 LAC-6315, May 23, 1979 LAC-6319, May 29,1979 LAC-6474, August 16, 1979 LACBWR Responses to TMI-2 Lessons Learned:

LAC-6680, De'cember 6,1979

  • LAC-6769, January 31, 1980

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  • " Info Required for NRC Generic Report on BWRs and In Response to NRC 7/17 and 7/27/79 letters," September 7,1979 d

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1.

General Design Criteria 55 and 56 of 10 CFR Part 50, Appendix A, state f

that lines penetrating containment, either as part of the reactor coolant pressure boundary or that connect directly to the containment atmosphere.

-hould be provided with isolation valves both inside and outside contain-ment. The following non-essential systems / penetrations do not appear to have the dual isolation barriers:

Penetration System Existing C. I. V.

Inside M-13 Station Air Check M-17 Decay Heat Removal A0 Globe - Inside Inside M-18 Seal Injection Check M-21 Vent Exhaust Damper A0 Butterfly (2) -

Inside Outside 11-23 Resin Sluice Check M-22, 25, 27 Waste Water A0 Globe - Inside f

M-28 Reactor Cavity Purge Air Check + Outside M-29 Off-Gas Vent Chimney A0 Globe - Inside (Remote-Manual-

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M-31 Ventilation Supply A0 Butterfly - Inside If there are other containment isolation valves on these lines not listed in the above tabulation which enable the lines to meet GDC 55 and/or 56, please provide them in an updated list of containment isolation valves f

similar to that of your September 7,1979 transmittal for " Lessons Learned." Otherwise, justify the deviation from' these GDCs.

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Penetration l A on Allis-Chalmers Draw:ing Number 41-300-088 contains local 3.

manual valves on the containment building drain suction line and instrument l

lines through penetrations M-14,16, lA and 23. SRP Section 6.2.4.11.3 states that thise valves should be locked closed and under administrative l

control.

Demonstrate that this is the case or justify why not.

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4.

SRP Section 6.2.4.II.3.e states that containment isolation for E.S.F.

or E.S.F. related systems may consist of only one isolation valve, if it can be shown that system reliability is greater with only one isola-tion valve and if a single active failure can be accommodated with only one isolation valve in the line. However, this valve should be located outside containment. The following systems contain one isolation valve inside and none outside containment.

Penetration System M-19 Shutdown Vent Off-gas M-11 Demineralized Water

, M-8 High Pressure Service Water Clarify if isolation valves exist for thdse lines outside containment.

L-5.

LAC-6319 states that the failure position for the main steam hydraulic,

plug-cock isolation valve on loss of motive

  • power is "as is."

How would this valve be isolated in the event of loss of m'o'Iive power?

6.

Closed loop lines such as those in penetrations M-9 and M-10 should be provided with an automatic isolation or remote manual valve outside con-tainment or be locked closed, according to GDC 57.

It does not appear that these penetrations meet this provision. Clarify this point and justify any deviation from GDC 57.

7.

Allis-Chalmers Drawing Number 41-300-088, " LAC 5WR Reactor Plant Contain-ment Vessel Penetrations Diagram" refers to two additional drawings:

41-503431 and 41-503432. Please provide 2 copies of these drawings.

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Test connections such as those lines through penetrations M-ll and M-12 need to be under administrative control to assure that they are not in-advertently opened or left open.

Discuss the administrative controls that apply to all test connections.

9.

Penetration M-34 does not appear to have any designated isolation valves.

Please indicate the isolation vaives on the " shutdown condenser steam -

at.mosphere" line, if any.

Justify not having containment isolation on this line if that is the case.

10.

Discuss the provisions for leakage monitoring for all remote manual and local manual containment isolatic. valves.

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