ML20203F876
| ML20203F876 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 02/10/1999 |
| From: | Bill Dean NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20203F882 | List: |
| References | |
| NUDOCS 9902180336 | |
| Download: ML20203F876 (5) | |
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UNITED STATES g
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. Samaa aaat
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PUBLIC SERVICE ELECTRIC & GAS COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-354 HOPE CREEK GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.115 j
License No. NPF-57 1.
The Nuclear Regulatory Commission (the Commission) has found that j
I A.
The application for amendment filed by the Public Service Electric & Gas Company (PSE&G) dated April 28,1998, as supplemented September 29,1998, J
and December 8,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; I
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B.
The facility will operate in conformity with the application, the provisions of the Act, j
and the rules and regulations of the Commission; e
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 Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of th!s amendment will not be inimical to the comtr>n defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in acconiance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license 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. NPF-57 is hereby amended to read as follows:
9902180336 990210 PDR ADOCK 05000354 P
2 (2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.115, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into the license. PSE&G shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The license amendment is effective as of its date of issuance, to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION William M. Dean, Director l
Project Directorate 1-2 l
Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation 1
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Attachment:
Changes to the Technical Specifications Date of issuance: February 10, 1999 1
ATTACHMENT TO LICENSE AMENDMENT NO.115 FACILITY OPERATING LICENSE NO. NPF-57 DOCKET NO. 50-354 Replace the following pages of the Appendix "A" Technical Specircations with the attached pages. The revised pages are identified by Amendment number and contain verticallines indicating the area of change.
Remove IDAgri W4 &7 W4 &7 w4 u w4 u J
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REACTOR COOLANT SYSTEM 3/4.4.2 SAFETY / RELIEF VALVES SAFETY / RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.2.1 'The safety valve. function of at'least 13 of the following reactor coolant system safety / relief valves shall be OPERABLE *# with the specified code safety valve function lift settings:**
4 safety-relief valves e 1100 psig 13%
5 safety-relief valves 9 1120 psig 13%
5' safety-relief valves e 1130 psig 13%
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.
i ACTION:
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l a.
With the safety valve function of two or more of the above listed f
fourteen safety / relief valves inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
I b.
With one or more safety / relief valves stuck open, provided that i
suppression pool average water temperature is less than 110*F, close the I
stuck open. safety relief valve (s); if unable to close the stuck open valve (s) within 2 minutes or if suppression pool average water temperature is 110*F or greater, place the reactor mode switch in the i
Shutdown position.
c.
With one or more of the above required safety / relief valve acoustic monitors-inoperable, restore the inoperable monitors to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- SRVs which perform as ADS. function must also satisfy the OPERABILITY requirements of Specification 3.5.1, ECCS-Operating.
- The lift setting pressure shall correspond to ambient conditions of the valves at nominal operating temperatures and pressures.
- SRVs which perform a low-low set function must also satisfy the OPERABILITY requirements of Specification 3.4.2.2, Safety / Relief Valves Low-Low Set Function.
1 MOPE CREEK 3/4 4-7 Amendment No.115 l
REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS 4.4.2.1 The acoustic monitor for each safety / relief valve shall be demonstrated OPERABLE with the setpoint verified to be s 30% of full open noise level ** by performance of as a.
CHANNEL FUNCTIONAL TEST at least once per 31 days, and a b.
CHANNEL CALIBRATION at least once per 18 months *.
4.4.2.2 At least M of the safety relief valve pilot stage assemblies shall be removed, set pressure tested and reinstalled or replaced with spares that have been previously set pressure tested and stored in accordance with manufacturer's recommendations at least once per 18 months, and they shall be rotated such that all 14 safety relief valve pilot stage assemblies are removed, set pressure tested and reinstalled or replaced with spares that have been previously set pressure tested and stored in accordance with manufacturer's recommendations at least once per 40 months. All safety relief valves will be re-certified to meet a tit tolerance prior to returning the valves to service after setpoint testing.
l 4.4.2.3 The safety relief valve main (mechanical) stage assemblies shall be l
set pressure tested, reinstalled or replaced with spares that have been l
previously set pressure tested and stored in accordance with manufacturer's recommendations at least once every 5 years, l
I
(
The provisions of Specification 4.0.4 are not applicable provided the l
Surveillance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure is adequate to perform the test.
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Initial setting shall be in accordance with the manufacturer's l
recommendations. Adjustment to the valve full open noise level shall be accomplished after the initial noise traces have been analyzed.
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l HOPE CREEK 3/4 4-8 Amendment No. 115 l
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