JAFP-98-0046, Forwards Revised Amend to DPR-59,revising TS Table 3.2-2 & 4.2-2, Core & Containment Cooling Sys Initiation & Control Instrumentation Operability Requirements. W/Revised TS Pages & Safety Evaluation

Forwards Revised Amend to DPR-59,revising TS Table 3.2-2 & 4.2-2, Core & Containment Cooling Sys Initiation & Control Instrumentation Operability Requirements. W/Revised TS Pages & Safety Evaluation

ML20202G810
Person / Time
Site:	FitzPatrick
Issue date:	02/06/1998
From:	Michael Colomb POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20202G816	List: JAFP-98-0046, Forwards Revised Amend to DPR-59,revising TS Table 3.2-2 & 4.2-2, Core & Containment Cooling Sys Initiation & Control Instrumentation Operability Requirements. W/Revised TS Pages & Safety Evaluation ML20202G855 ML20202G884 ML20202G908
References
JAFP-98-0046, JAFP-98-46, NUDOCS 9802200226
Download: ML20202G810 (3)

Text

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e .e- James A. Fit 2 Patrick

%b b Nucle:r Power Piant M8 Loe Ho d F o. Don 41 Lycoming, New York 13093 31t> 342-3840 4 NewYorkPower an..u. coiome tv Authority sne t=uwe o=*

February 6,1998 J'.M 98-0046 United States Nuclear Regulatory Commission Attn: Document Control Desk Mail Station P1 137 Washington, D.C. 20555 0UBJECT: James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Response to Request for Additionalinformation Regarding Changing Technical Specification Table 3.2 2," Core & Containment Cooling System initiation & Control Instrumentation Operability Requirements" (JPTS 96 002)

References:

1. USNRC letter, Karen R. Cotton to James Knubel, dated August 21, 1997

2. JPN 96-010,

• Proposed Change to the Technical Specifications Regarding Core and Containment . siing System Initiation and Control Instrumentation (JPTS-96-002), dated March 22,1996

Dear Sir:

This letter transmits the Authority's response to a recent request for additional information (Reference 1) pertaining to a proposed Technical Specification Amendment to revise Technical Specification (TS) Table 3.2 2 and TS Table 4.2 2, " Core & Containment Cooling System Instrumentation Test and Calibration Requirements." This letter also transmits a change to the previour submittal regardir,3 Core Spray and RHR pump start timers and Containment High Pressure trip function instrumentation requirements.

Attachment I provides a response to the requests for additional information for specific examples to support the replacement of the generic actions for inoperable instrument channels with function-specific actions and the replacernent of generic test AOTs with function specific AOTs. Attachment ll provides the sa s information contained in the original submittal but is reformatted to show how each function specific change in Table 3.2-2 was accomplished. I In the original TS amendment submittal, regarding Core Spray and RHR pump start timers .

(Number 11, page 12 of 24, in attachment 11 of reference 2) the required LCO action i ,g statements would have required:

j\

• B. With both start timers in the same LPCI subsystem inoperable, immediately rack out the circuit breakers for the affected RHR pumps and declare that LPCI

'9'G subsystem inoperable.

9805200226 900206 DR ADOCK 050003 l[l( l ll {ly,j l1 l

, . s' Unit:d St:t:s Nucl:ar R:gul: tory Comn ission Attn: Docum:nt Control Desk Response to RAI Regarding Changing T.S. Table 3.2 2 (JPTS 96-002)

Page 2 C. With one start timu inoperable, restore the timer to an operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or rack out the circuit breaker for the affected pump and declare the affected pump inoperable."

Racking out the breaker of the affected pumps has been determined not to be the most conservative action. An engineering evaluation and review of past performance records has determined that the simultaneous start of two of the ECCS pumps on the same emergency bus would not affect the availability of the emergency buses. Therefore, the required actions are being revised to remove the requirement to rack out affected ECCS pump breakers. This was discovered during the ongoing effort to convert the current JAFNPP Technical Specifications to improved Standard Technical Specifications that are based on NUREG 1433, Revision 1, " improved Standard Technical Specifications" (STS). These revised actions are ennsistent with STS section 3.3.5.1.

The original submittal requested that th .ontainment High Pressure trip function that prevents inadvertent operation of containment spray during accident conditions be moved from the technical specifications to a plant controlled procedure. The basis for the removal of the .

trip function was that it did not meet the criterion set forth in 10 CFR 50.36. The authority will retain the trip function in the technical specifications based on the information provided in NEDO-31466, Supplement 1 (reference 8). NEDO 31466 originally concluded that the trip function did not need to be retained. This position was reversed in the supplement.

Attachment lll contains the proposed TS amendment submittal as revised. Attachment IV contains the revised Safety Evaluation that contains the description of the changes. The conclusion reached in the no significant hazards evaluation of the Safety Evaluation are unchanged by this revision. Attachment V contains the mark-up of the proposed amendment as revised. Attachment VI lists the commitment contained in this submittal.

If you have any questions, please contact Mr. Robert Steigerwald at (315) 349-6209.

Very trul y urs, V

MICHAEb. COLOMB Site Executive Officer MJC:RS:las Att. As stated Cc: next page o

g.

• ,Jl' cc: U.S. Nucle:r Regul: tory C:mmission -

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. Daniel Dorman, Project Manager Project Directorate 11

- Division of Reactor Projects 1/ll U.S. Nuclear Regulatory Commission Mail Stop 14 B2 Washington, DC 20555 Mr. F. William Valentino, President New York State Energy, Research and Development Authority Corporate Plaza West 286 Washington Avenue Extension Albany, NY 12203-6399

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