ML17254A581

Provides Proposed Schedule for Meeting Requirements of ATWS Rule & Brief Description of Tentative Design Being Considered,Per Generic Ltr 85-06.Util Will Use Design Presented in Section 4.0 of WCAP-10858

ML17254A581
Person / Time
Site:	Ginna
Issue date:	10/11/1985
From:	Kober R ROCHESTER GAS & ELECTRIC CORP.
To:	Zwolinski J Office of Nuclear Reactor Regulation
References
GL-85-06, GL-85-6, NUDOCS 8510210050
Download: ML17254A581 (6)

Text

REGULATOR NFORMATION DISTRIBUTION S EM (RIDS)

ACCESSION NBR e 8510210050. DOC ~ DATE: 85/10/11 NOTARIZED: NO DOCKET FACIL':50 BYNAME244 Robert Emmet Ginna Nuclear Plant< Unit 1g Rochester G 05000244 AUTH AUTHOR AFFILIATION KOBKRiR,W, Rochester Gas R Electric Corp.

RECIPe NAME" "RECIPIENT AFFILIATION ZWOLI NSKI i 0-, A ~ Operating Reactors" Branch 5

SUBJECT:

'rovides proposed schedule for meeting requirements of ATWS rule 8 br,ief description of tentative design, being considered<per. Generic Ltr 85 06,Util will use:, design presented in Section 4.0 of WCAP 10858.

DISTRIBUTION CODEe '055D COPIES RECEIVED:L~TR ENCL 0 'IZE' TITLE: OR/Licensing Submittal: Salem ATWS Events GL~83 28 NOTES:NRR/DL/SKP 05000244 09/19/69 icy'L

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ZZIII ZZIIIII'll(zziillrf liz~ixa)(sz SIA'II ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649.0001 ROGER W. KOBER VICE PRCSIDSNT TELCPHONC ELECTRIC & STEAM PRODVCTION AREA COD& Tle 546.2700 October ll< 1985 Director of Nuclear Reactor Regulation Attention: Hr. John A. ZwolinskiI Chief Operating Reactors Branch No. 5 U.S. Nuclear Regulatory Commission Washingtonr D.C. 20555

Subject:

ATWS Rule 10 CFR 50.62 R. E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Hr. Zwolinski:

The Commission has published 10 CFR 50.62 regarding the reduction of risk from anticipated transients without scram (ATWS) events at light-water cooled nuclear power plants. Section 50.62(d) requires each licensee to develop and submit a proposed schedule for meeting the requirements of the rule within 180 days after the issuance of the QA guidance for non-safety related components. NRC Staff QA guidance was issued April 16I 1985 by Generic Letter 85-06. The purpose of this letter is to provide a proposed schedule for meeting the requirements of the ATWS rule and to provide a brief description'f the tentative design being considered to meet the requirements of the rule as Ginna.

it applies to Section 50.62(c)(l) of the rule requires each pressurized water reactor (PWR) to have equipment from sensor output to final actuation devicer that is diverse from the reactor trip systemI to automatically initiate the auxiliary feedwater system and to initiate a turbine trip under conditions indicative of an ATWS.

Xn a letter from L. D. Butterfield to C. O. Thomas dated July 25I 1985 (OG-156)I the Westinghouse Owners Group (WOG) submitted Topical Report WCAP-10858I "AHSAC Generic Design Package"I which describes three conceptual designs that meet this requirement at Westinghouse-designed PWRs. RGSE is a member of the WOG and participated in the development of the Topical Report.

RGGE tentatively proposes to use a design similar to that presented in Section 4.0 of WCAP-10858 (Logic 2: AHSAC Actuation on Low Hain Feedwater Flow). Turbine trip and auxiliary feedwater flow will be initiated on appropriate indication of low main feedwater flow. The logic will sense conditions indicative of an ATWS event with loss of heat sinkI but will not actuate until ~6 after the reactor protection system should have completed its safety action. po 8510210050 85iOii 'I PDR ADOC5, .05000244 I 'nag

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ROCHESTER GAS AND ELECTRIC CORP.

4 SHEET NO. 2 DATE October 11 I 1985 To Nr. John A. Zwolinski Design and procurement for the system will be scheduled to provide for installation during the 1988 refueling outage. This schedule is contingent upon timely Staff review and acceptance of the logic presented in WCAP 10858 and upon completion of other major modifications required by the NRC Staff at Ginna Station in the 1986-1987 time period. Hajor projects include SPDS installa-tioni Appendix R modifications> reactor vessel level indication systemi detailed Control Room Design Review modificationsI structural upgrade and other issues.

V truly yours>

~cd Kober Roger W.

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