ML17264B054

Provides Update to Response to NRC RAI Re Adequacy & Availability of Design Bases Info Per 10CFR50.54(f)

ML17264B054
Person / Time
Site:	Ginna
Issue date:	09/30/1997
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	Vissing G NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9710080012
Download: ML17264B054 (6)

Text

CATEGORY 1 REGULATOR INFORMATION DISTRIBUTIOtlSTEM (RIDE)

I ACCESSION NBR:9710080012 DOC.DATE: 97/09/30 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME i AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas 6 Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION VISSINGF G. S.

SUBJECT:

Provides update to response to NRC RAI re adec(uacy 6 DISTRIBUTION CODE: A0740 TITLE: Responses NOTES:License Exp date to 50.54(f)

COPIES RECEIVED:LTR Req.

j availability of design bases info per 10CFR50.54(f).

ENCL for Design Basis Info 1

in accordance with 10CFR2,2.109(9/19/72).

SIZE:

05000244

/ E RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PDl-1 PD 1 1 VISSING G.

F 1 1 INTERN ': FILE CENTER 01 1 1

1 1

NRR/DRPM/PGEB PDR-2/THOMAS,K 1

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T NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 9 ENCL 9

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AND I

ROCHESTER GAS AND EIECTR1C CORI/ORATION ~ 89 FAST AVEhlUE, ROCHESTER, N. Y IrI6494001 AREA CODE 716 &f6-2700 ROBERT C. MECREDY Vice President Nvcteor Operotions September 30, 1997 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directorate I-1 Washington, D.C. 20555

Subject:

Update to Response to NRC Request for Information Pursuant to 10CFR50.54(f) regarding Adequacy and Availability of Design Bases Information R. E. Ginna Nuclear Power Plant Docket No. 50-244 Ref.(a): RG&E letter R.E. Smith to U.S. NRC dated 2/7/97, re: Response to NRC Request for Information Pursuant to 10CFR50.54(f) regarding Adequacy and Availability of Design Bases Information

Dear Mr. Vissing:

On February 7, 1997, Rochester Gas & Electric (RG&E) responded to the Nuclear Regulatory Commission's request for information pursuant to 10CFR50.54(f) regarding adequacy and availability of design bases information.

In its response, RG&E made a commitment to collate and validate selected information for specific systems and topics and link this information electronically with the UFSAR.

Further, RG&E stated that its schedule for completion of the above examination and verification of system and topical design bases information had not been established yet, that it intended to develop a firm schedule in the third quarter of 1997, and that it would provide the schedule to the NRC at that time.

RG&E has recognized the need to put in place an information technology (IT) infrastructure to support continued maintenance of the data collected from the UFSAR verification and design basis documentation projects, both of which are in progress. The UFSAR verification project uses the same resources (System Engineers) as does the design basis documentation project, so it is RG&E's intention to concentrate on the UFSAR verification until 10/18/98 iwhile in parallel developing the IT infrastructure) i "f

and then shift focus to the design basis documentation project. This will cause the design basis documentation project's completion date to be extended by one year, until 12/01.

The attached schedule contains the systems and topics RG&E intends to pursue (there may be some substitution).

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PDR ADGCK' 05000244 P -PDR L(

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2. RG&E also stated that it had scheduled, and incorporated into its business plan for 1997, the performance of two internal SSFIs (on the Component Cooling Water and the Service Water systems) and that, based on the results of these SSFIs, it would assess the need to conduct additional SSFIs in conjunction with the other design bases efforts described in the 10CFR50.54(f) response. In June, RG&E performed a Service Water SSFI in preparation for an NRC Architect-Engineer (A/E) inspection. The systems chosen by the NRC A/E Team were Component Cooling Water and Safety Injection. RG&E considers their in-depth review to have satisfied the need to perform any other SSFIs in 1997.

3. RG&E has also reviewed its Configuration Management processes and concluded that additional enhancements to existing processes, such as calculation control and Vendor Technical Manual (VTM) control, are warranted. RG&E has recently completed a major upgrade to the VTM program, including strengthening the vendor recontact process.

Improvements in the calculation control processes are being performed at this time.

Very truly yours, Robert C. Mecredy EJF 7480 xc: Mr, Guy S. Vissing (Mail Stop 14B2)

Project Directorate I-1 Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 US NRC Ginna Senior Resident Inspector

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