JAFP-96-0291, Informs of Util Intent to Install Alternate Dhrs at Plant in Advance of Refueling Outage 12,scheduled to Commence in Oct 1996.Info Encl Provides Details of Sys Design & Safety Considerations Pertinent to Sys Installation & Testing
| ML20116D888 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 07/26/1996 |
| From: | Michael Colomb POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20116D890 | List: |
| References | |
| JAFP-96-0291, JAFP-96-291, NUDOCS 9608050003 | |
| Download: ML20116D888 (3) | |
Text
o James A. FitzPatrick e
Nucle:r P:w;r Plant P.O. Box 41 Lycoming, New York 13093 315-342-3840 A NewYo.rkPower yicnee, s. co,,,,
& Authonty eiemi ueneger July 26,1996 JAFP-96-0291 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop P1-137 Washington, D. C. 20555
Subject:
Installation of the (Alternate) Decay Heat Removal System
References:
1.
NYPA Letter JPN-90-042, J. C. Brons to NRC, " Proposed Changes to the Technical Specifications Regarding Spent Fuel Pool Storage Capacity", dated May 31,1990 2.
NYPA Letter JPN-91-027, R. E. Beedle to NRC, " Request for Additional Information for ' Proposed Changes to the Technical Specifications Regarding Spent Fuel Pool Storage Capacity'", dated June 26,1991 3.
Technical Specification Amendment No.175 for the James A.
FitzPatrick Nuclear Power Plant (and associated Safety Evaluation report), USNRC, dated December 31,1991 4.
NYPA Report No. JAF-RPT-DHR-02413, " Evaluation of the Decay Heat Removal System" Revision 1, dated July 16,1996 j
5.
10 CFR 50.59 Nuclear Safety Evaluation No. JAF-SE-96-039,
" Installation and Acceptance Testing of the Decay Heat Removal System", approved July 16,1996 6.
10 CFR 50.59 Nuclear Sefety Evaluation No. JAF-SE-96-042, "Use of the Decay Heat Removal System in Various Plant Modes and Configurations", approved July 16,1996
Dear Sir:
As was discussed with members of the NRC Staff during a meeting held on July 23,1996 l
at the Region I offices, the Authority intends to install an alternate Decay Heat Removal System (DHR) at FitzPatrick in advance of refueling outage 12, scheduled to commence in October of this year. As detailed below, the Authority has reviewed the current licensing h()O' basis for spent fuel pool cooling and determined the installation of the DHR is not in conflict with the technical and safety bases of the facility, and will, in fact, result in a i
significant improvement in overall decay heat removal capability during refueling outages.
9608050003 960726 PDR ADOCK 05000333 P
i U.S. Nucitar R:gul: tory Commission Attn: Document Control Desk
Subject:
Installation of the (Altemate) Decay Heat Removal System
(
Page The Authority's decision to pursue installation of a DHR will allow specific work activities to be performed during refuel outage 12, while providing additional decay heat removal capability above and beyond that provided by the original plant design. An integral part of 1
our evaluation of the feasibility of installing the DHR was performance of a detailed review of the licensing bases for decay heat removal (during refueling outages) in general, and spent fuel pool cooling, in particular. The current licensing bases for decay heat removal spent fuel pool cooling is documented in Reference Nos.1 and 2 in support of (then) proposed expansion of spent fuel pool storage capacity. NRC review and approval of the l
associated Technical Specification change are documented in Reference No. 3. The j
l Authority's evaluation, documented in Reference No. 4, concluded, in part, installation and operation of the DHR system will: (1) constitute a significant enhancement in decay heat' removal capability, particularly during refueling outages, (2) improve the ability to control refueling cavity and spent fuel pool water temperature during refueling operations, (3) l provide greater flexibility in outage planning. The Authority's evaluation also concluded l
there are no unreviewed safety questions associated with DHR installation and operation and the system can be installed in accordance with our Modification Control Manual and evaluated in accordance with 10 CFR 50.59. DHR installation and Modification l
acceptance testing have been evaluated in Reference No. 5 and system operation l
evaluated in Reference No. 6.
Reference Nos. 4,5, and 6 provide details of the system design and the safety considerations pertinent to system installation, testing, and operation. As detailed in those documents, the DHR is designed to ensure postulated failures of the system would have no adverse effects on safety-related systems and components. The DHR has also been designed to withstand a broad spectrum of postulated component failures while maintaining, with operator action, a heat removal capacity more than four times greater than the existing Fuel Pool Cooling and Cleanup System. The design of the system, coupled with administrative controls specified in Reference No. 6 will ensure redundant means of decay heat removal are maintained during refueling outages (when the DHR is in use).
As requ'ested during the July 23rd meeting, copies of Reference Nos. 4,5, and 6 are attached herewith.
j If you have any questions, please contact Mr. Arthur Zaremba, Licensing Manager, at (315) 349-6365.
Very truly yours, l
w
/*t-MICHAEL J. COLOMB Plant Manager MJC:KV: RAP:las cc:
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Rggional Administrator l
U. S. Nuclear Regulatory Commission 475 Allendale Road l
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Office of the Resident inspector i
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Ms. K. Cotton, Acting Project Manager l
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Washington, DC 20555 Mr. F. William Valentino, President New York State Energy, Research, l
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