ML20078R846
| ML20078R846 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 12/16/1994 |
| From: | Michael Case Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20078R849 | List: |
| References | |
| NUDOCS 9412270301 | |
| Download: ML20078R846 (7) | |
Text
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UNITED STATES g
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NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. - -1 k...../
December 16, 1994 Mr. William J. Cahill, Jr.
Executive Vice President - Nuclear Generation Power Authority of the State of New York 123 Main Street White Plains, NY 10601
SUBJECT:
ISSUANCE OF AMENDMENT FOR JAMES A. FITZPATRICK NUCLEAR POWER PLANT (TAC NO. M90592)
Dear Mr. Cahill:
The Commission has issued the enclosed Amendment No.219 to Facility Operating License No. DPR-59 for the James A. FitzPatrick Nuclear Power Plant. The amendment consists of changes to the Technical Specifications (TSs) in response to your application transmitted by. letter dated October 7, 1994.
The amendment revises TS 4.6E.4 and the associated Bases to establish that the manual cycling of reactor coolant system safety / relief valves (SRVs) during j plant startups is to be accomplished within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after steam pressure and flow are adequate to perform the testing. TS 4.6E.4 had previously required that this testing be performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of continuous power operation at a reactor steam dome pressure of at least 940 psig. The amendment also e
makes several editorial changes to clarify the intent of TSs involving SRV testing and performance requirements.
A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission's next regular biweekly Federal Reaister notice.
Sincerely, 5 S.
Nicola F. Conicella, Acting Project Manager Project Directorate I-l Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-333
Enclosures:
1.
Amendment No. 219to DPR-59 2.
Safety Evaluation cc w/encis: See next page 9412270301 941216
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PDR ADOCK 05000333 i
P PDR
i William J. Cahill, Jr.
James A. FitzPatrick Nuclear Power Authority of the State of New York Power Plant cc:
Mr. Gerald C. Goldstein Ms. Donna Ross Assistant General Counsel New York St'*e Energy Office Power Authority of the State 2 Empire State Plaza of New York 16th Floor 1633 Broadway Albany, NY 12223 New York, NY 10019 Mr. Richard L. Patch, Director Resident Inspector's Office Quality Assurance U. S. Nuclear Regulatory Commission Power Authority of the State P.O. Box 136 of New York Lycoming, NY 13093 123 Main Street White Plains, NY 10601 Mr. Harry P. Salmon, Jr.
Resident Manager James A. FitzPatrick Nuclear Power Plant P.O. Box 41 Lycoming, NY 13093 Ms. Charlene D. Faison Director, Nuclear Licensing Power Authority of the State of New York 123 Main Street White Plains, NY 10601 Supervisor Town of Scriba Route 8, Box 382 Oswego, NY 13126 Mr. Robert G. Schoenberger, First Executive Vice President and Chief Operating Officer Power Authority of the State of New York 123 Main Street White Plains, NY 10601 Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406
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q UNITED STATES
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NUCLEAR REGULATORY COMMISSION f.
WASHINGTON, D.C. 20vedH)o01
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POWER AUTHORITY OF THE STATE OF NEW YORK DOCKET NO. 50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 219-License No. OPR-59 1.
The Nuclear Regulatory Commission (the Comission) has found that:
' e application for amendrrent by Power Authority of the State A.
of New York (the licensee) hted October 7,1994, complies with the standards and requirements d the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon hfense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordane.e with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the licen se is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-59 is hereby amended to read as follows:
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(2) Technical Snecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 219, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION i
Michael J.
se, Acting Director Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 16, 1994
ATTACHMENT TO LICENSE AMENDMENT NO.219 FACILITY OPERATING LICENSE NO. DPR-59 DOCKET NO. 50-333 i
Revise Appendix A as follows:
Remove Paaes Insert Paaes 142a 142a 143 143 152 152 1
l i
JAFNPP 3.6 (cont'd) 4.6 (cont'd)
E.
Safetv/ Relief Valves E.
Safetv/ Relief Valves
- 1. During reactor power operating conditions and prior to startup
- 1. At least 5 of the 11 safety / relief valves shall be bench from a cold condition, or whenever reactor coolant pressure checked or replaced with bench checked valves once is greater than atmosphere and temperature greater than each operating cycle. All valves shall be tested every 212 F, the safety mode of at least 9 of 11 safety / relief valves two operating cycles." The testing shall demonstrate shall be operable. The Automatic Depressurization System that each valve tested actuates at 1110 psig 13%.
valves shall be operable as required by specification 3.5.D.
Following testing, lift settings shall be 1110 psig 11%
- The current surveillance interval for bench checking safety / relief valves is extended until the end of R11/C12 refueling outage scheduled for January,1995. This is a one-time extension,-
effective only for this surveillance interval. The next surveillance interval will begin after the completion of the bench check testing and after the safety / relief valves are declared operable.
Amendment No. 40, 28, 56, 70, 400, 404, 495, B+7, 219 142a
JAFNPP 3.6 (cont ~d) 4.6 (cont'd)
- 2. If Specification 3.6.E.1 is not met, the reactor shall be placed in
- 2. At least one safety / relief valve shall be disassembled and a cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
inspected once/ operating cycla.*
- 3. Low power physics testing and reactor operator training shall
- 3. The integrity of the nitrogen system and components which be permitted with inoperable components as specified in provide manual and ADS actuation of the safety / relief valves Specification 3.6.E.1 above, provided that reactor coolant shall be demonstrated at least once every 3 months.
temperature is s212 *F and the reactor vessel is vented or the reactor vessel head is removed.
- 4. The provisions of Specification 3.0.D are not applicable.
- 4. Manually open each safety / relief valve while bypassing steam to the condenser and observe a 210% closure of the turbine bypass valves, to verify that the safety / relief valve has opened.
This test shall be performed at least once each operating cycle while in the RUN modo and within the first 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after steam pressure and flow are adequate to perform the test.
- 5. The safety and safety / relief valves are not required to be operable during hydrostatic pressure and leakage testing with reactor coolant temperatures between 212 F and 300 F and irradiated fuel in the reactor vessel provided all control rods are inserted.
The current surveillance interval for disassembling and inspecting at least one safety / relief valve is extended until the end of R11/C12 refueling outage scheduled for January,1995. This is a one-time extension, effective only for this surveillance interval. The next surveillance interval will begin upon completion of this surveillance.
Amendment No. 40,70,400,484,479,495,247, 219 143
JAFNPP 3.6 and 4.6 BASES (cont'd)
E.
Safetv/ Relief Valves The safety / relief valves (SRVs) have two modes of operation; with the HPCI and RCIC turbine overspeed systems and the the safety mode or the relief mode. In the safety mode (or Mark I torus loading analyses. Based on safety / relief valve spring mode of operation) the spring loaded pilot valve opens testing experience and the analysis referenced above, the when the steam pressure at the valve inlet overcomes the spring safety / relief valves are bench tested to demonstrate that force holding the pilot valve closed. The safety mode of in-service opening pressures are within the nominal pressure operation is required during pressurization transients to ensure setpoints 13% and then the valves are returned to service with vessel pressures do not exceed the reactor coolant pressure opening pressures at the nominal setpoints 11%. In this manner, safety limit of 1,375 psig.
valve integrity is maintained from cycle to cycle.
In the relief mode the spring loaded pilot valve opens when the The analyses with NEDC-31697P also provide the safety basis spring force is overcome by nitrogen pressure which is provided for which 2 SRVs are permitted inoperable during continuous to the valve through a solenoid operated valve. The solenoid power operation. With more than 2 SRVs inoperable, the margin operated valve is actuated by the ADS logic system (for those to the reactor vessel pressure safety limit is significantly reduced, SRVs which are included in the ADS) or manually by the therefore, the plant must enter a cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> operator from a control switch in the main control room or at the once more than 2 SRVs are determined to be inoperable. (See remote ADS panel. Operation of the SRVs in the relief mode for reload evaluation for the current cycle).
the ADS is discussed in the Bases for Specification 3.5.D.
A manual actuation of each SRV is performed to demonstrate l
Experiences in safety / relief valve testing have shown that failure that the valves are mechanically functional and that no blockage or deterioration of safety / relief valves can be adequately detected exists in the valve discharge line. Valve opening is confirmed by l
if at least 5 of the 11 valves are bench tested once per operating monitoring the response of the turbine bypass valves and the cycle so that all valves are tested every two operating cycles.
SRV acoustic monitors. Adequate reactor steam dome pressure Furthermore, safety / relief valve testing experience has must be availah'e to avoid damaging the valvo. Adequate steam demonstrated that safety / relief valves which actuate within 13%
flow is required to ensure that reactor pressure can be of the design pressure setpoint are considered operable (see maintained during the test. Testing is performed in the RUN ANSI /ASME OM-1-1981). The safety bases for a single nominal mode to reduce the risk of a reactor scram in response to small valve opening pressure of 1110 psig are described in pressure flucuations which may occur while opening and NEDC-31697P, " Updated SRV Performance Requirements for reclosing the valves.
I the JAFNPP." The single nominal setpoint is set below the reactor vessel design pressure (1250 psig) per the requirements Low power physics testing and reactor operator training with of Article 9 of the ASME Code - Section lil, Nuclear Vessels.
inoperable components will be conducted only when the The setting of 1110 psig preserves the safety margins associated safety / relief valves are l
Amendment No. 40,404, 247, 219 152
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