ML19320D462

Forwards 36A93, OPS Responses to Post-TMI NRC Requirements, Revision 1.Rept Represents Vast Majority of New Info Required to Support Issuance of Mgt License. Requests Meeting W/Nrc at Earliest Possible Convenience

ML19320D462
Person / Time
Site:	Atlantic Nuclear Power Plant
Issue date:	07/15/1980
From:	Haga P OFFSHORE POWER SYSTEMS (SUBS. OF WESTINGHOUSE ELECTRI
To:	Youngblood B Office of Nuclear Reactor Regulation
Shared Package
ML19320D463	List: ML19320D462 ML19320D473
References
RTR-NUREG-0660, RTR-NUREG-660 FNP-PAL-101, NUDOCS 8007210395
Download: ML19320D462 (3)

Text

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j g FNP-PAL-101 Off shore Power Systems July 15, 1980 Mr. B. J. Youngblood, Chief Licensing Branch No. 1 Division of Licensing U. S. Nuclear Regulatory Comission 7920 Norfolk Avenue Bethesda, MD 20852

.Re: Docket No. STN 50-437; 3,g" Offshore Power Systems' Responses to NUREG-0660

Dear Mr. Youngblood:

Enclosed are four copies of Offshore Power Systems' Topical Report No. 36A93, Revision 1, " Offshore Power Systems' Responses to Post-TMI NRC Requirements",

July 1980. An ;dditional thirty-six copies have been shipped to you via United Parcel Service.

Revision 1 to Topical Report 36A93 is a complete rewrite of the document first submitted in December 1979. The original report addressed the recommendations of the Bulletins and Orders Task Force and the Lessons-Learned Task Force. Revision 1 addresses NUREG-0660 which was issued in May 1980 and which defines the post-TMI requirements resulting from the reuommendations of all *he various groups which have investigated the accident at TMI.

In Revision 1 we have responded to all but one of the NUREG-0660 action items. The single item remaining is the degraded accident rulemaking for which a response must await the publica', ion of a draft (or possibly interim) rule presently expected to occur during the sumer of 1980. Offshore Power Systems will respond to the proposed (or interim) rule as soon as possible following its publication. Our response will be in the form of a revision to Topical Report 36A93. It is worthy of note that the Floating Nuclear Plant has already received substantial design review based on degraded accident assumptions. The design flexibility B0072103M

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Page Two Mr. B. J. Youngblood July 15, 1980 inherent in the FNP concept was recently demonstrated by the addition of a refractory core ladle to retard containment basemat penetration. Because of this flexibility and because of attention already given to degraded accident mitigation, we are confident of our ability to satisfy whatever new requirements may crystalize from the forthcoming rulemaking proceeding.

In a meeting on April 30, 1980, representatives of Offshore Power Systems and the NRC Staff previewed NUREG-0660 and in the process agreed on the appli-cability to the manufacturing license application of each action plan item. This agreement was documented in my letter to Mr. R. L. Baer, FNP-PAL-088, dated May 6, 1980. The responses in Revision 1 to 36A93 conform to the agreements reached during the meeting of April 30, 1980.

Offshore Power Systems is submitting Revision 1 at this time because it presents the vast majority of the new information required to support issuance of the Manu-facturing License. Offshore Power Systems would like to meet with the Staff at its earliest convenience to discuss the adequacy of these responses in Revision 1 to 36A93 and to establish the schedule for completion of the Staff review of the FNP application.

Ve q truly youps, Lf i - -

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4 P. B. Haga CC: A. R. Collier V. W. Campbell Erclosure

Instructions for Entering Revision 1 i in offshore Power Systems Topical Report 36A93 J

NOTE: Revision 1 is a complete rewrite of Topical Report 26A93. )

1. Remove the Title Card fra the plastic pocket of the ring binder and replace with the Revision 1 Title Card.

2. Remove all pages from the ring binder and replace with the j attached package of pages. '

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