ML20195K363
| ML20195K363 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick |
| Issue date: | 11/17/1998 |
| From: | Chris Bajwa NRC (Affiliation Not Assigned) |
| To: | James Knubel POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| Shared Package | |
| ML20195K368 | List: |
| References | |
| TAC-MA0096, TAC-MA96, NUDOCS 9811270002 | |
| Download: ML20195K363 (4) | |
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UNITED STATES p
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. soseM001 g
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November 17, 1998 Mr. James Knubel Chief Nuclear Officer Power Authority of the State of New York 123 Main Street White Plains, NY 10601
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT - THIRD INTERVAL INSERVICE TESTING PROGRAM AND RELIEF REQUESTS (TAC NO. MA0096)-
Dear Mr. Knubel:
The NRC staff has completed its evaluation of the third 10-year intervalinservice testing (IST)
- program for pumps and valves for the James A. FitzPatrick Nuclear Power Plant, submitted by the New York Power Authority (NYPA) on October 21,1997. This submittalincluded 11 requests for relief from the requirements of Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code pursuant to Section 50.55a of Part 50 to Title 10 of the Code of Federal Regulations. The NRC staff requested additionalinformation regarding these relief requests on April 30,1998. NYPA provided the requested information on July 30,1998.
The NRC staff's safety evaluation is enclosed, and includes the conclusions summarized below.
The staff conducted a limited review of the licensee's IST program. The standby liquid control, core spray, and high pressure coolant injection systems were reviewed in detail. The staff believes that it may be appropriate to include the closure function of the core spray pump discharge piping keep-fill check valves (14-CSP-63A and 14-CSP-63B) in the scope of the licensee's IST program. The staff did not identify any other possible IST program scope issues as a result of its limited review.
The proposed attemative in relief request VRR-05 is authorized pursuant to i
10 CFR 50.55a(a)(3)(i) based on a determination that the proposal provides an acceptable level of quality and safety. The proposed altemative in relief requests PRR-01, PRR-02R1, PRR-03, PRR-04, VRR-02, VRR-03, and VRR-04 are authorized pursuant to 10 CFR 50.55a(a)(3)(ii) based on determinations that the proposals provide reasonable assurance of operational j-readiness and that compliance with the Code would result in a hardship without a compen:;ating increase in the level of quality and safety. Relief requests PRR-05R1 and VRR-01 are granted
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a'nd the altemative imposed pursuant to 10 CFR 50.55a(f)(6)(i) based on the determination that compliance with the Code requirements is impractical. The testing as described in the JAF IST l
program will provide reasonable assurance of the operational readiness of the pumps and valves
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to perform their safety-related functions.
I The standby liquid control system pump testing attemative PRR-02R1 is authorized for an interim compliance with the requirements would result in a hardship without a compen period of 1 year pursuant to 10 CFR 50.55a(a)(3)(ii) based on the determination that immediate
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the level of quality and safety. This interim period will provide the licensee sufficient time to adequately address flow rate measurement accuracy. The licensee should either 1) resubmit l
this relief request with a more detailed description of how pumping time and human factors considerations preclude meeting the Code flow rate accuracy requirement (e.g., limitations
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-9911270002 981117 PDR ADOCK 05000333
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J. Knubel,
associated with the sight glass design, graduation, orientation, or temporary test tank level instrumentation) and provide an indication of the flow rate accuracy that can reasonably be achieved with the installed system configuration or 2) install a flow rate instrument that directly measures the pump flow rate to the level of accuracy required by the Code.
All of the other relief requests that are granted and attematives that are authorized in this safety evaluation are valid for the remainder of the third 10-year inservice testing interval for FitzPatrick.
If you have any questions regarding this matter, please contact Joe Williams at (301) 415-1470.
Sincerely, S. Singh Bajwa, Dire or Project Directorate -1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket No. 50-333
Enclosure:
Safety Evaluation cc w/ encl: See next page
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assested with the sight glass design, graduation, orientation, or temporary test tank level c.
instrumentation) and provide an indication of the flow rate accuracy that can reasonably be achieved with the installed system configuration or 2) install a ficw rate instrument that directly
' measures the pump flow rate to the level of accuracy required by the Code.
J All of the other relief requests that are granted and altamatives that are authorized in this safety evaluation are valid for the remainder of the third 10-year inservice testing interval for FitzPatrick.
If you have any questions regarding this matter, please contact Joe Williams at (301) 415-1470.
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Sincerely, l
original signed by G.Vissing for-S. Singh Bajwa, Director Project Directorate 1-1 Division of Reactor Projects - 1/11 l
Office of Nuclear Reactor Regulation Docket No. 50-333
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Enclosure:
Safety Evaluation i
l cc w/ encl: See next page
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DISTRIBUTION:
Docket File T. Harris (TLH3, e-mail SE only) -
PUBLIC OGC
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PDI-1 R/F G. Hill (2) l
. J. Zwolinski ACRS l
S. Bajwa B. McCabe i
S. Little
. J. Williams l
l DOCUMENT NAME: G:\\FITZ\\MA0096.LTR l
- To ree:lve a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with tit:chment/ enclosure, "N" = No copy m 0FFICE.
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- James Knubel James A. FitzPatrick Nuclear 1
Power Authority of the State Power Plant of New York cc:
Mr. Gerald C. Goldstein Mr. F. William Valentino, President Assistant General Counsel New York State Energy, Research, Power Authority of the State and Development Authority of New York Corporate Plaza West l
1633 Broadway 286 Washington Avenue Extension New York, NY 10019 Albany, NY 12203-6399 Resident inspector's Office Mr. Richard L. Patch, Director U. S. Nuclear Regulatory Commission Quality Assurance r
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- P.O. Box 136 Power Authority of the State i
l Lycoming, NY 13093 of New Yo*
123 Main Street Mr. Hany P. Salmon, Jr.
White Plains, NY 10601 Vice President - Engineering Power Authority of the State Mr. Gerard Goering of New York 28112 Bayview Drive i
123 Main Street Red Wing, MN 55066 White Plains, NY 10601 Mr. James Gagliardo Ms. Charlene D. Faison Safety Review Committee Director Nuclear Licensing 708 Castlewood Avenue Power Authority of the State Arlington, TX 76012 of New York 123 Main Street Mr. ArthurZaremba, Licensing Manager 2
1 White Plains, NY 10601 James A. FitzPatrick Nuclear 1
i Power Plant 4
j Supervisor P.O. Box 41 Town of Scriba Lycoming, NY 13093 Route 8, Box 382 Oswego, NY 13126 Mr. Paul Eddy -
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New York State Dept. of Mr. Eugene W. Zeltmann Public Service i
President and Chief Operating 3 Empire State Plaza,10th Floor
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Officer Albany, NY 12223 Power Authority of the State of New York Michael J. Colomb i
99 Washington Ave., Suite No. 2005 Site Executive Officer 4
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Albany, NY 12210-2820 James A. FitzPatrick Nuclear Power Plant o
P.O. Box 41 Charles Donaldson, Esquire Lycoming, NY 13093 Assistant Attomey General New York Department of Law 120 Broadway New York, NY 10271 1
Regional Administrator, Region l l
U.S. Nuclear Regulatory Commission j
475 Allendale Road King of Prussia, PA 19406 1
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