ML20070N914

Application for Amend to License DPR-59,revising TS Bases Re Design Basis of Emergency Svc Water Sys

ML20070N914
Person / Time
Site:	FitzPatrick
Issue date:	04/29/1994
From:	Josiger W POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20070N916	List: JPN-94-022, Proposed Tech Spec Bases Re Design Bases of Emergency Svc Water Sys ML20070N914
References
JPN-94-022, JPN-94-22, NUDOCS 9405100210
Download: ML20070N914 (2)

Text

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123 Main Street

- White Plains, New York 10601 914 EA16200

1. b NewYorkPower 4# Authority April 29,1994 JPN-94-022 U.S. Nuclear Regulatory Comrnission Mail Station P1-137 Washington, D.C. 20555 ATTN: Document Control Desk

SUBJECT:

James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Proposed Change to the Technical Specification Bases Regarding the Design Basis of the Emergency Service Water Svstem

REFERENCES:

1. JAF-SE-90-067, Rev. 4 dated May 5,1993, " Clarification of Design Basis Requirements for the JAFNPP Emergency Service Water System (46)."

2. NRC letter, M.W. Hodges to H.P. Salmon, dated June 11, 1992, "NRC Inspection Report 50-333/92-81."

Dear Sir:

This letter proposes a change to the James A. FitzPatrick Technical Specifications Bases Section 3.11.D, " Emergency Service Water System." The change to the Technical Specification Bases reflects the information provided in the Updated Final Safety Analysis Report (UFSAR). Attachments I and il of this application contain the proposed change to the Technical Specification Bases, and a markup of the current Technical Specification Bases, respectively.

The proposed change removes the reference to "ECCS Pumps"in Technical Specification Bases Section 3.11.D on page 243. This change will update the Bases of the Emergency Service Water (ESW) System to be consistent with the analysis performed in safety evaluation JAF-SE-90-067 (Reference 1). In this safety evaluation, the Residual Heat Removal (RHR) pump seal water coolers have been re-classified as non safety related. As a result, these coolers were isolated from ESW in part to provide additional ESW water flow to other components. The safety evaluation documented that the RHR System would be able to perform its intended safety function with ESW isolated. This conclusion is also supported by vendor documentation which states that the isolation of the ESW Systern would not inhibit RHR pump operation during accident conditions. Therefore, the Authority proposes to revise the Technical Specification Bases section 3.11.D to reflect that the RHR pumps seal coolers are no longer a safety-related load on the ESW System.

This change will revise the Bases by removing the reference to "ECCS Pumps" in Technical Specification Bases Section 3.11.D. This change is consistent with )(

9405100210 940429 PDR ADOCK 05000333 I A u f ' -- PDR

.n the recommendation made in NRC Inspection Report 50-333/92-81 (Reference )

. 2),

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

Very truly.yours,

,/05  %

W. A os' er

$ctIng E ecut' e Vice President Nuclear eneration

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cc: Regional Administrator U.S. Nuclear Regulatory 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 Directorate I-1 Division of Reactor Projects - 1/11 U.S. Nuclear Regulatory Commission Mail Stop 14 B2 Washington, DC 20555 Ms. Donna Ross New York State Energy Office 2 Empire State Plaza 16'" Floor Albany, NY 12223 i

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