JPN-92-016, Withdraws 900116 Application for Amend to License DPR-59, Revising TS Surveillance Requirements Associated W/Primary Containment Leak Rate Testing Due to NRC Issuance of Generic Ltr 91-04

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Withdraws 900116 Application for Amend to License DPR-59, Revising TS Surveillance Requirements Associated W/Primary Containment Leak Rate Testing Due to NRC Issuance of Generic Ltr 91-04
ML20094N287
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 03/31/1992
From: Ralph Beedle
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-91-04, GL-91-4, JPN-92-016, JPN-92-16, NUDOCS 9204060268
Download: ML20094N287 (2)


Text

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93 Won Sveet Wrote Pirns. NeMbrk 10(G 914 661084t, 48% NewYorkPower um.. .

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March 31,1992 JPN 92-016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1 137 Washington, D.C. 20555

SUBJECT:

James A. RtzPatrick Nuclear Power Plant Docket No. 50-333 Withdrawal of Amendrnent Application (JPTS-84-012)

Reference:

NYPA letter, J.C. Brons to the NRC, dated January 16,1990, (JPN 90-008), " Proposed Change to the Technical Specifications Regarding Containment Leak Rate Testing Requirements (JPTS 012)."

Dear Sir:

The New York Power Authority withdraws the Technical Specification amendment application contained in the referenced letter. The proposed changes would have revised the surveillance requirements associated with primary containment leak rate testing at the James A. FitzPatrick Nuclear Power Plant.

Since the Technical Specification amendment application was filed, new L circumstances have developed which affect two of the changen proposed in it. First, the NRC issued Generic Letter 91-04, which provides now guidance for exceeding the 24 monih maximum surveillance interval for Type B and C leak rate testing. It requires that several evaluations be performed to consider the effects of a 24-month 125% Type B and C surveillance test interval. These evaluations will be performed to support the 24 month operating cycle amendment application, expected to be submitted in early 1993.

Second, the Authority determ:ned that the two low pressure coolant injection (LPCI) independent power supply charger / inverters were not designed to withstand the 30-day post accident dose associated with the existing containment leak rate test acceptance criterion. A modification is being installed which will resolve this issue. However, additional evaluations must be performed to ensure that the proposed containment leak rate acceptance critorion would not adversely affect other equipment. Following these evaluations, the Authority may revise and resubmit this Technical Specification amendment request.

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l If you have any questions, please contact Mr. J. A. _Graf, Jr.

Very truly yours,

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Ralph E. Boodle U Exocutivo Vice Pros dont Nuclear Generation ec: Regiona! Administrator U.S. Nuclear Rogulatory Commission

- 475 Allendale Road -

King of Prussia, PA 19406 Office of the Resident inspector U.S. Nuclear Regulatory Commission P.O. Box 136 -

.Lycoming,NY 13093 Mr. Brian C. McCabe -

- Project Directorato 1-1 Division of Reactor Projects 1/11 U.S. Nuclear Regulatory Commission

- Mall Stop 14 B2 Washington,DC 20555 o

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