ML19341C810

Forwards Request for Addl Info for App J Review Re Containment Leakage Rate Testing

ML19341C810
Person / Time
Site:	Millstone
Issue date:	02/02/1981
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:	Counsil W NORTHEAST NUCLEAR ENERGY CO.
References
LSO5-81-02-001, LSO5-81-2-1, NUDOCS 8103040221
Download: ML19341C810 (4)

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Mr. W. G. Counsil, Vice President RTedesco Nuclear Engineering and Operations Glainas

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Dear Mr. Counsil:

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SUBJECT:

CONTAINMEilT LEAKAGE RATE TCSTING - APPENDIX J REVIEW (MILLSTONE UNIT 1 ) We are continuing our review of your July 29, 1977 and September 20, 1978 submittals and request that you submit the information described in the enclosure to this letter within 30 days. Sincerely. Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing

Enclosure:

As stated cc w/ enclosure: See next page 'i 1 .i 1 1 l I r F 3 810304029' i 4.. ,f, j 5'"at); JShea;.qc L.) '. DCr.chfield! .i. .l. IV8 em)l .)/ ..4.4 I l .. /. Jl. 3 a: ca.. r: : n.a.:. a. : C 7?lCl.AL P.ECC P.D CC PY ' m w-= >

ffpa ts:u,o, UNITED STATES NUCLEAR REGULATORY COMMISSION y .( g wAsMNG TON, D. C. 20656 %,.....f February 2,1981 Docket No. 50-245 LS05-81-02-001 Mr. W. G. Counsil, Vice President Nuclear Engineering and Operations Northeast Nuclear Energy Company Post Office Box 270 Hartford, Connecticut 06101

SUBJECT:

CCNTAINMENT LEAKAGE RATE TESTING - APPENDIX J REVIEW (MILLSTONE UNIT 1 ) f We are continuing our review of your July 29, 1977 and September 20, 1973 submittals and request that you submit the information described in the enclosure to this letter within 30 days. Sincerely, Od Cennis M. Crutchfield, Chdf Operating Reactors Branch #5 Division of Licensing

Enclosure:

As stated cc w/ enclosure: See next page

Mr. W. G. Counsil February 2,1981 i cc w/ enclosure: William H. Cuddy, Esquire Connecticut Energy Agency Day, Berry & Howard ATTN: Assistant Director Counselors at Law Research and Policy One Constitution Plaza Development Hartford, Connecticut 06103 Department of Planning and Energy Policy Natural Resources Defense Council 20 Grand Street 91715th Street, N. W. Hartford, Connecticut 06106 Washington, D. C. 20005 Director, Criteria and Standards Division Northeast Nuclear Energy Company Office of Radiation Progracs ATTN: Superi ntendent (ANR-460) l Millstone Plant U. S. Environmental Protection .1 P. O. Box 123 Agency j Waterf ord, Connecticut 06385 Washington, D. C. 20460 } Mr. James R. Hier.elwright U. S. Environmental Protection i Northeast Utilities Service Company - Agency P. O. Box 270 Region 1 Office Hartford, Connecticut 06101 ATTN: EIS COORDINATOR JFK Federal Building l-Resident Inspector Boston, Massachusetts 02203 c/o U. S. NRC P. O. Box Orawer KX Niantic, Connecticut 06357 Waterford Public Library Rope Ferry Road, Route 156 Waterford, Connecticut 06335 First Selectman of the Town of Waterford Hall of Records 200 Boston Post Road Waterford, Connecticut 06385 John F. Opeka Systems Superintendent Northeast Utilities Service Cocpany P. O. Box 270 Hartford, Connecticut 06101 t i

t l REQUEST FOR ADDITIONAL INFORMATION CONTAINMENT LEAKAGE RATE TESTING NORTHEAST NUCLEAR ENERGY COMPANY MILLSTONE UNIT 1 NRC DOCKET NO. 50-245 NRC TAC NO. 10137 i i e 1 6 'I I l

1. BACY. GROUND in letters dated July 29, 1977 and Septecher 20, 1978, Northeast Nuclear Energy Co=pany (NICO) provided certain information in support of previously requested exe=ptions from the requirements of 10CFF.50, Appendix J. Contain-mnt Leakage Testing. 2. INFOR.MATION REQUIRED 2.1 AIRLOCK TESTING Item (2)a of NECO's July 29, 1977 letter regarding a request for exe=p-tion fro: the airlock-testing requirements of Appendix J stated : hat tirlock door seals would be tested a: 10 psig within 72 hours of the first of a series of openings between 6-month tests. Provide the method you propose to use to correlate the leakage rate of 10 psig to the leakage ra:e of 43 psig when perfor=ing these tests. 2.2 REVIP.SE DIRECTION -'ESTING NECO's letter of September 20, 1978 states that valves LP-44A and 3 cannot be = edified to meet the requirements for reverse direction testing; however, imediately adjacent valves LP-43A and 3 can be tested in the correct direction if test connections are added to each line. Wi:h respect to this

proposal, i.e., to designate valves LP-43A and 3 as containment isolation valves in lieu of valves LP-44 A and 3, provide a comparison of valves LP-43A and 3 to wives LP-44A and 3 with regard to safety classification, seismic and environmental qualification, and automatic actuation features. Ad di tionally, j

any differences in design classification of the piping between the 43 valves l and 44 valves should be iden:ified and discussed. i / --h .... FranWin Research Center % e N n~ m.}}