ML20213D993
| ML20213D993 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 02/09/1982 |
| From: | Parr O Office of Nuclear Reactor Regulation |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| CON-WNP-0456, CON-WNP-456 NUDOCS 8203020259 | |
| Download: ML20213D993 (2) | |
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.o FES 9 1992 Uccket llo: 50-397
!;E!;0RA!!DUI.1 FOR: Albert Schwencer, Chief, Licensing Branch llo. 2. GL FR0t1:
Olan D. Parr, Chief, Auxiliary Systeus Branch, DSI SUCJECT:
SER IllPUT OPE;l ITEllS - WASilIllGT0fl PUBLIC POWE h3 SYSTEM - WASHIllGT0:1 fiUCLEAR PF0 JECT i;0 2 j
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n Plant flar.;e: 'lashington fluclear Project ilo. 2 3 c. 'i.,
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Responsible Branch: Licensing Branch tio. 2 0,?@-
Project fianager:
R. Auluck
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TsTTW ASG F.evicuer:
J. itidgely Requested Coupletion Date: February 12, 1982 Rav ist Status: Awaiting Infomation To date, in our rqview of the !!fiP-2 FSAR for our preparation of the ASB SER input, We liave identified the open iteras listed belo.s. The purpose of this ueuoranduo is to raka you aware of these items prior to receiving our SE:',
input. We were of the opinion that the applicant. would submit infcmation in January to close out most of these matters. Me have received and revic'.ed this submittal and the following natters remin as op::n itern for ul.ich no official docur..entation has been recieved frr,m the applicant or for which the infomation is inczplete:
1.
Applicant's re-evaluation of ruissile cources, both inside an't outside of containment (SRP 3.5.1.1 0,nd 3.5.1.2);
E.
Verification that.nain stean isolation valve leakage used in safety analyses is as specified in the Standard Technical Specifications (SRP6.7);
3.
Verifit.ation that decay heat loads arp based on 3 ranch Technical Position ASB 9-2 (SRP 9.5.3); and 4
Evaluation of cha consequences of dropping loads over spent fuel which could have a higher kinetic energy than tne dropping of a fuel bundle With its channel and handling togl;
Contact:
John Ridgely Er 2 r 3 p M M N D'
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Cormitment to comply with the requirements of UUEEG-0612 which was requested by the generic letter dated December 10, 1980 (SRP 9.1.4);
6.
Evaluation of the effect of losing the diesel generator area cable cooling system air handler as a single failure concurrent with a tornado (SRP9.4.8);and 7.
The review of the applicant's response to the generic AE00 safety concern of a pipe break in the CRDS (which was received January 25, 1932). This review has not yet been completed since it involves the coordination of review efforts by several branches in addition ~ to ASB.
tie are trying, by means of telephone conference calls, to close out as many of these items as possible in order to meet your dato for our SER input.
Odginel Signed by Olan Parr Olan D. Parr, Chief Auxiliary Systems Branch Division of Systems Integration' cc:
R. l'attson L. Rubenstein R. Tedesco R. Label J. Ridgely R. Auluck Distribution:
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