ML17262B079

Suppls Response to GL 90-06,stating That Pressurizer PORVs Would Be Environmentally Qualified for Potential Post Accident Environ.No Change to Reactor Operating Mode Should Be Made as Result of Having Inoperable PORV

ML17262B079
Person / Time
Site:	Ginna
Issue date:	11/03/1992
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
GL-90-06, GL-90-6, NUDOCS 9211090158
Download: ML17262B079 (4)

Text

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ACCESSION alBR '9211090158 DOC ~ DATE'2/ll/03 NOTARIZED NO DOCKET I FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME . AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas 6 Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION JOHNSONiA.R. Project Directorate I-3

SUBJECT:

Suppls response to GL 90-06,stating that pressurizer PORVs would be environmentally qualified for potential post accident- environ.No change to reactor operating mode should I be made as result of having inoperable PORV.

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TITLE: Generic"Ltr 90-06 Resolution of GE 70N94 PORVs 6 Block Valve Reliabil g NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-3 LA PD1-3 PD JOHNSON,A INTERNAL: KIRKWOOD,R.NLS3 NRR/EMEB

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ZiPiijjSi IIIJIIIII 8 izzuvz ROCHESTER GAS AND ELECTRIC CORPORATION 4 89 EAST AVENUE, ROCHESTER N.Y. 14649-0001 ROBERT C. MECREDY TELEPHONE Vice President hREA COOE 71B 546 2700 Clnne Nudeer Production November 3, 1992 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Allen R. Johnson Project Directorate I-3 Washington, D.C. 20555

Subject:

Response to Generic Letter 90-06 R.E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Johnson:

In RG&E's response to Generic Letter 90-06, we stated that the pressurizer PORV's would be environmentally qualified for any potential post-accident (e.g., steam generator tube rupture) environment. This commitment was made despite .the NRC's assessment that classification and qualification of this equipment as safety-related was not justified (Section 2 of Enclosure A to Generic Letter 90-06). RG&E has performed a more detailed review of the benefits and costs associated with this modification, relative to the entire spectrum of proposed Ginna Station capital expenditures.

We have concluded (consistent with the NRC's assessment) would not be cost-effective to upgrade this equipment.

that it The Technical Specifications we proposed in our September 15, 1992 are not affected by this change. As noted in Attachment B to that letter, second page, item 2, RG&E contends that no change of Reactor Operating Mode should be made as a result of having an inoperable PORV due to causes other than excessive seat leakage.

This is because the PORV's are needed to perform specified functions during all Reactor Operating Modes, from "Operating" to "Cold Shutdown". No other sections of our September 15 submittal are affected by our decision not to modify the PORVs.

Ver truly yours, Ac Robert C. Mecredy GJW/261 osooa'-

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'DR P:PDR 9211090158 921103 ADOCK'05000244,

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xc: Mr. Allen R. Johnson (Mail Stop 14Dl)

Project Directorate I-3 Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector