ML19343A810

Forwards B&W Upgraded Design, Auxiliary Feedwater Sys for Smud. Requests NRC Approval Prior to Design Freeze & Preparation of Equipment Purchase Specs on 801205.Oversize Drawings Available in Central Files

ML19343A810
Person / Time
Site:	Rancho Seco
Issue date:	11/17/1980
From:	Bossenmaier W SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	Reid R Office of Nuclear Reactor Regulation
Shared Package
ML19343A811	List: ML19343A810 ML19343A812
References
TASK-2.E.1.2, TASK-TM TAC-42933, TAC-43190, TAC-44673, NUDOCS 8011210519
Download: ML19343A810 (2)

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SACRAMENTO MUNICIPAL UTILITY DISTRICT C 6201 S Street, Box 15830, sacramento. Calitu.nia 95813; (916) 452-3211 T.*.,

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Director of Nuclear Reactor Regulation Attention: Mr. Robert W. Reid, Chief Operating Reactors, Branch 4 U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Docket No. 50-312 Rancho Seco Nuclear Generating Station, Unit 1 Upgraded Auxiliary Feedwater System Design Submittal

Dear Mr. Reid:

On September 4,1980 a meeting was held with representatives of the Sacramento Municipal Utility District, Arkansas Power and Light, Florida Power, Babcock and Wilcox, and the NRC Staff, to discuss these Utilities' plans to upgrade their auxiliary feedwater systems. As discussed in this meeting, the District is requesting your approval of the conceptual design for this system prior to a design freeze and the preparation of equipment purchase specifications on December 6, 1980. The attached system description has been orepared by the Babcock and Wilccx Company, who is designing this upgraded system for the District, and we are hereby submitting the description for your approval. As discussed during our September 4 meeting, the schedule leading to an early 1982 equipment delivery is tight, and your expeditious review is requested. During the same meeting a reliability assessment was requested, and this work is also being performed by the Babcock and Wilcox Company. The D h trict will submit this assessment as soon as it is completed in the very near futura.

It should be noted, that item II.E.1.2.1.b of NUREG 0737 requires the implemen-tation of safety grade initiatinn of the auxiliary feedwater system by July 1, 1981.

The District does not plan to make this rodification at this time, since the upgraded system, to be implemented during the first extended cutage follow gc)/

3 ing equipment delivery in 1982, includes this concept as well as safety grade control.

Item II.E.1.2.2.c requires the implementation of safety grade flow

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indication, also by July 1,1981.

This effort will proceed independently of the system upgrade.

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In addition, item II.E.1.1.2 of NUREG 0737 requires the implementation of long N(O term improvements to the auxiliary feedwater system by January 1,1982. These imorovements for Rancho Seco, Unit 1, were identified in the reliability analysis 7o 256 of the auxiliary feedwater system shortly after the Three Mile Island Accident.6/a g D/Q 8 011210$h

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AN ELECTRIC 3Y3 TEM S E 4 71 N 0 M09E THAN ^ 10 0. 0 0 0 IN THE HEART of C Alt F O R N I A

Mr. Robert W. Reid Page 2 November 17, 1980 They consist of automatically loading both auxiliary feedwater pumps on the emergency diesel generators, and modifying valve FWS-055, so that both trains of auxiliary feedwater are not taken out of service to perform a system test.

Since the upgraded auxiliary feedwater design includes power for the pumps from new diesel generators, the District does not intend to make this interim improvement on January 1,1982.

Instead, safety grade power will be provided as part of the overall-upgrade later that year. On the other hand, the valve configuration will be modified prior to the overall system upgrade since this modification can be made independently.

If we can provide any additional information to aid in your evaluation of this system, please advise.

Sincerely yours, Nb AMLCL Q&

W. S. Bossenmaier Acting General Manager

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