ML19346A331

Interim Deficiency Rept,Initially Reported 810122,re Annulus Pressurization Effect on Piping Sys.Final Analysis Will Be Included in Plant Design Assessment Rept for Safety-Related Valve & LOCA Loads in June 1982

ML19346A331
Person / Time
Site:	Columbia
Issue date:	05/26/1981
From:	Matlock R WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
10CFR-050.55E, 10CFR-50.55E, G2-81-119, GO2-81-119, NUDOCS 8106190147
Download: ML19346A331 (2)

Text

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O Washington Public Power Supply System P.O. Box 968 3000 George W9shington Way Richland, Washington 99352 (509)372-5000 tiay 26,1981 G02-81-119 Doc ket No. 50-397 Mr. R. H. Engel ken -

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.Y s d Office of Inspection of Enforcement Nuclear Regulatory Commission Q r 4-g p g Region V Suite 202, Walnut Creek Plaza h p

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Walnut Creek, California 94596 [ ,

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Dear Mr. Engelken:

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Subject:

WPPSS NUCLEAR PROJECT NO. 2 '. e ,N' POTENTIALLY REPORTABLE DEFICIENCY - 10CFR50.55(e}.'h.

ANNULU3 PRESSURIZATION EFFEC.T ON PIPING SYSTEMS /7 r

Reference:

Letter No. G02-81-13, dated January 22, 1981, RG Matlock, The Supply System, to RH Engelken, NRC Region V The Reference letter informed your staff of a potentially reportable defic;ency regarding the effect of annulus pressurization on piping systems attached to or supported from the reactot vessel or sacrificial shield wall .

Although the analysis of resulting loads on piping systems and supports is not completed at this time, the Supply System has concluded that ,

this condition is a reportable deficiency under the terms of 10CFR50.55(e),

since it is a safety concern requiring extensive analysis which should have been, but 'was not, considered in the design of se.fety-related piping and supports prior to release for construction.

Final results of the ongoing analysis of p1 ping systems and supports, by the architect-engineer, will be included in the " Plant Design Assessment Report for SRV and LOCA Loads", for the WNP-2 facility. It is aaticipated that the final revision to the report will be subnitted in June 1982. Since this matter was initially raised by the NRC staff in conjunction with their ongoing reviews on the WNP-2 docket (ref. WNP-2 FSAR, question 110.019) the ll pn g,M

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i Mr. R.-H. Engelken itay - 26, 1981

. Page Two G02-81-119 Supply System will address'this concern in that forum, and does not anticipate providing_ a duplicate or supplementary report to NRC Region V.

Very truly~ycurs, W W_--

R. K. ?!ATLOCK Program Director WNP-2 EAF:dm cc: V. Stello. - NRC AD Toth - NRC Resident Inspector RC Root - - B&R' Site TA Mangelsdorf - Bechtel Site RE Snaith- -

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