JPN-92-021, Forwards Application for Amend to License DPR-59,changing TS Table 4.2-1, Min Test & Calibr Frequency for PCIS to Reflect Plant Mod to Deactivate Reactor Vessel Head Spray Portion of RHR Sys

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Forwards Application for Amend to License DPR-59,changing TS Table 4.2-1, Min Test & Calibr Frequency for PCIS to Reflect Plant Mod to Deactivate Reactor Vessel Head Spray Portion of RHR Sys
ML20096G672
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 05/21/1992
From: Ralph Beedle
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20096G674 List:
References
JPN-92-021, JPN-92-21, NUDOCS 9205260199
Download: ML20096G672 (2)


Text

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i a4 May 21,1992 JPN 92-021 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1 137 Washington, D.C. 20555 l_

SUBJECT:

James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Proposed Technical Specification Change Regarding the l

Hemoval of Reactor Vessel Head Spray Portion of RHR Piping and Associated Valves (JPTS-92-016)

Reference NRC letter, Ngoc Le to Lynn Eury, damd January 9,1991, " Issuance of Amendment 151 and Amendmet 181 Regarding Removal RHR Head Spray Flow Transmitter - Brunswick Steam Electric Plant, Units 1 and 2."

Dear Sir:

This application for an amendment to the James A. FitzPatrick Technical Specifications proposes to change Table 4.21 entitled, " Minimum Test and Calibration F;equency far PCIS' to reflect a plant modification which will deactivate the reactor vessel head spray portion of the Residual Heat Removal (RHR) System.

This modification involvos the elimination of the reactor vessel head spray function by removing and capping portions of the head spray piping and associated valves.

The head spray is an optional capability and credit is not taxen for it in the accident analysis. Curveillance of this unused portion of the RHR system contributes unnecessa.ly to pusonnel radiation exposure. This amendment request is similar to a license amendment the NRC approved for Brunswick Units 1 and 2 in the above reference.

Enclosed for filing is the signed original of a document entitled " Application for Amendment to Operating Ucense ' with Attachments I,11 and Ill, thereto, comp-ising the current Technical Specifications to be changed, a statement of the proposed changes to the Technical Specifications and the associated Safety Evaluation.

in accordance with 10 CFR 50.91, a copy of this application and the associated attachments are being provided to the designated New York State cincial 9205260199 920521 PDR ADOCK 05000333 g6/

P PDR 1

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I If you have any questions, please contact Mr.J. A. Gray, Jr.

Very truly yours, d ' C. '

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Ralph E. Beedle Escutive Vice President Nuclear Generction cc:

Regional Administrator U.S. Nuclear Regulatory Commissico 475 Allendale Road King of Prussia, PA 19406 OfSce of the Resident inspector U.S. Nuclear Regulatory Commission P.O. Box 136 Lycoming, NY 13093 Mr. Brian C. McCabe e

Project Directorate 11 Division of Reactor Projects-t/ll U.S. Nuclear Regulatory Commission Mail Stop 14 B2 Washington, D.C. 20555 Ms. Donna Ross New York State Energy Office 2 Empire State Plaza th 16 Floor Albany,NY 12223 i

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