ML20151H971

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Discusses 840217 Memo Re Inconsistencies in Revised Draft SER Input.Deletion of MSIV Leakage Control Sys Was Not Reviewed Until Recently
ML20151H971
Person / Time
Site: Nine Mile Point, 05000000
Issue date: 03/13/1984
From: Novak T
Office of Nuclear Reactor Regulation
To: Muller D
Office of Nuclear Reactor Regulation
Shared Package
ML20150F672 List:
References
FOIA-88-356 NUDOCS 8404050449
Download: ML20151H971 (3)
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. vi MEMORANDUM FOR: Daniel R. Muller, Assistant Director for Radiation Protection Division of Systems Integration FROM: Thomas M. Novak, Assistant Director for Licensing Division of Licensing

SUBJECT:

MSiv LEAKAGE CONTROL SYSTEM FOR NINE MILE POINT 2 Your memorandun of February 17, 1984 concerning f.he Nine Mile Point Unit 2 revised Draft SER input from AEB contained some inconsistencies which appear to need clarification. In your memorandum you indicated that "0L had informed l theapplicantovertwoyearsagothat[anMSIVleakagecontrolsystem)was I not necessary." Attachment I to this memorandum is a copy of the January 2,1981 letter to Niagara Mohawk Power Corporation (NMPC). As you can see from reading this nemorandum deletion of the HSIV leakage control system was not apprnved but NMPC was informed of provisions that would be expected should they decide to delete this system.

The applicant's intention to delete this system was clearly stated in their response to AEB request for infomation 450.2 wh1en was submitted in Amend.aent 5 to the FSAR in October 1983. Deletion of the MSiv leakage control system was not in fact reviewed until recently. The DSER input for Section 6.7 from ASB reviewed and accepted deletion of this system. i l Oricinal signod by l Thomas M. N~ak, Assistant Director ,

for Lice, sing l

Division of Licensing Attachrent:

As stated cc w/ attachment:

R. Mattson J. Read T. Quay L. Hulman

Contact:

M. Haughey, DL x27897 DI.9TRIBUTION:

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Eubject: Prcrcsed Design Chans.e of the Main Stean Isolation Valves for tiine l'.ile Point, Unit 2 In your letters, cated April 3,1979 and Septert-- 6,1960, ycu rauested

> mvd e' 3 mien chanceghe fline hile Point. Unit 2, r..ain steam isclction valves. You prcrosed using a 24-inch positive seal ball valvc cesigned and c.anuf actur ed by the fluid Systems Division, Energy Products Grcup of Gulf and Western f:anuf acturing Ccepany. This valve would be substituted f or the Y-pat crn globe valve with its seal water system described in your P!>#..

Ycu stated that because of the unique design of the positive valve seal, the leakage frca this valve would be negligible. You concluded that a main stcam isolation valve leakage control system would not be necessary. On this basis you stated that you do not plan to install such a system for these valves.

You referenced Culf and Western's lepical Report, fio. GlW-FSD 2538, which i deals with the c.atn steam valve system and enauested coreletion of our review  :

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  • hv Vrerter 31. 1980. in order to maintain ycur current engineering and construct 1c.'. R.ecure. Tne hRC's review of topical reports in general has a l l w priority at present. Specifically, this GLW Topical Report is not scheduled 1

for review before mid-1981. Hewever, it is our position that use of this valve need not bc tontingent on cur review of this topical report.

We see no prcblem if you proceed with the procurement and installation of these valves, based on your detemination that the valve satisfies our acceptance criteria for K5!v's. The basis for our position on this matter is that the integrity of these valves will be ascertained by strict in-service inspection and testing requirements. In particular, you will' be required to check these valves with the same frequency and against the same leakage requirerents as cain steam . I valves with a supplemental leakage control system. If tte leakage a ceeds these I specifications or if our later review of the topical report discloses problems I with the proposed system, we will require you to repair, rnodify, or replace i these valves. It is our further position that you should reserve space and I the appropriate containmeat penetrations in the event that we require backfitting of a leakage control system at a later date.

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. Pr. Gera,1d f.. Rhode M 2 1931 Finally, we note that section A of P.egulatory Guide 1.05, P.evision 1, "Design of P.ain Steam Isolation Valve Leakage Control Systems for Boiling k'ater Peactor fuclear Power Plants," states: "!f an applicant proposes to use a method different from that described in this guide for implementing General Design Criteria 54 with regard to the control or limitation of leakage past the r.iain steam isolatun valves of a boiling water reactor, the acceptability of the alternative net *c4 will be determined by the staf f on a case-by-case basis."

The methed te.ieb ne staff recomends in section D.2 of Degulatory Guide 1.96 is a supplm.enV'. Icakage control system, assuming that one of the more conventional v.SIV's is being used. %ince vmr er*-r 4' " d'arn'tive to thit staM cositten. t.* Mil rau'au n m a case-by-case basis no earlier]

than 1991, 25 no @d above.

Sincerely,

\

Robert L. Tedesco, Assistant Director for Licensing Division of Licensing

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