ML17275B051

Interim Deficiency Rept Re Annulus Pressurization on Piping Sys Attached to or Supported from Reactor Vessel or Sacrificial Shield Wall,Initially Reported 810122.Deficiency Found Reportable.Final Rept by June 1982

ML17275B051
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, GO2-81-119, NUDOCS 8106020353
Download: ML17275B051 (6)

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ACCESSION'BR; 8106020353. DOC ~ DATE: 81/05/26. NOTARIZED:. NO DOCKET' FACILE:50 397 WPPSS Nucleary ProJecti Unit~ Nashington Public Powe'. 05000397 AUTH',NAME" . AUTHOR AFFILIATION G, Nashington Public Power~ Supply System~ 'ATLOCK>RE RECIP ~ NAMEI RECIPIENT AFFILIATION ENGELKENqR ~ HE Region 5g San Francisco< Office'- of, the Directot (81/03/01) ~

' ' ' ' ~ " V SUBJECT'i'ntei im deficiehcy rept r e', annulus pressur izat$ on,<<on< piping

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sys attached.to or suppor ted from reactor vessel. or sa'cri f f cial, shieldwal < ini tf al y r eported 810122'.Deficiency 1 1 f ound repor tab l e; Final rept" by June~ 1982,

'CODEt B019S COPIES RECE'I/ED!LTR., ENCL: 'ISTRIBUTION SIZE';"

TITLE': Construction Deficiency Report~ (10CFR50 ~ 55E)

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Washington Public Power Supply, System P.Q. Box 968 3000 George Washington Way Richland, Washington 99352 (509) 372-5000 May 26, 1981 G02-81-119 Docket No. 50-397 Mr. R. H. Engelken Office of Inspection of Enforcement Nuclear Regulatory Commission Region V Suite 202, Walnut Creek Plaza 2990 North Ca 1 i forni a Bl vd .

Walnut Creek; California 94596

Subject:

WPPSS NUCLEAR PROJECT NO. 2 POTENTIALLY REPORTABLE DEFICIENCY - 10CFR50.55(e)

ANNULUS PRESSURIZATION EFFECT ON PIPING SYSTEMS

Reference:

Letter flo. 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 deficiency regarding the effect of annulus pressurization on pi ping systems attached to or supported from the reactor vessel or sacrificial shield wall.

Although the analysis of resulting loads on pi pi ng systems and suppor ts 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 safety-related pi ping and supports prior to release for construction.

Final results of the ongoing analysis of piping 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 anticipated that the final revision to the report will be submitted in June 1982. Since this matter was initially raised by the NRC staff in conjunction with their ongoing revieius on the WNP-2 docket (ref. WNP-2 FSAR, question 110.019) the

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Nr. R. H. Engelken Nay 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 yours, k

R. . hRTLOCK Program Director HNP-2 EAF:dm cc: V. Stello - NRC AD Toth - NRC Resident Inspector RC Root - BER Site TA Nangelsdorf - Bechtel Si te RE Snaith - BSR NY HS Chin - BPA WNP-2 Files