ML20093H798
| ML20093H798 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 10/16/1995 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Public Service Electric & Gas Co, Atlantic City Electric Co |
| Shared Package | |
| ML20093H801 | List: |
| References | |
| NPF-57-A-084 NUDOCS 9510200350 | |
| Download: ML20093H798 (5) | |
Text
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-4 *4 UNITED STATES j
j NUCLEAR REGULATORY COMMISSION 4
2 WASHINGTON, D.C. 20066-0001
- ,o PUBLIC SERVICE ELECTRIC & GAS COMPANY j
ATLANTIC CITY ELECTRIC COMPANY
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DOCKET NO. 50-354 i
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HOPE CREEK GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.84 License No. NPF-57 1.
The Nuclear Regulatory Comission (the Comission or the NRC) has found that:
i A.
The application for amendment filed by the Public Service Electric &
Gas Company (PSE&G) dated May 4, 1995, complies with the standards.
and requirements of the Atomic Energy Act of 1954, as amended (the i i
Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; j
B.
The facility will operate in conformity with the application, the i
provisions of the Act, and the rules and regulations of the i
Comission; C.
There is reasonable assurance:
(1) that the activities authorized i
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 set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 i
of the Commission's regulations and all applicable requirements have l
been satisfied.
a l
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:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 84, 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.
- no"n8st M68b e
- j 3.
The license amendment is effective as of its date of issuance, to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION J n F. Sto z, Directo oject Directorate -
Division of Reactor Projects - I/II Office of Nuclear Reactor' Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October 16, 1995
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4 ATTACHMENT TO LICENSE AMENDMENT NO. 84 FACILITY OPERATING LICENSE NO. NPF-57 DOCKET NO. 50-354
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Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert 3/4 6-11 3/4 6-11 i
8 3/4 6-2 8 3/4 6-2 1
b 2
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s CONTAINMENT SYSTEMS DRYWELL AND SUPPRESSION CHAMBER PURGE SYSTEM LIMITING CONDITION FOR OPERATIONS 1
3.6.1.8 The drywell and suppression chamber purge system, including the 6-inch nitrogen supply line, may be in operation for up to 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> each 365 l
days with the supply and exhaust isolation valves in one supply line and one exhaust line open for containment prepurge cleanup, inerting, deinerting, or pressure control
- APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2 and 3.
ACTION:
- a. With a drywell or suppression chamber purge supply and/or exhaust isolation valve and/or the nitrogen supply valve open, except as permitted above, close the valves (s) or otherwise isolate the penetration (s) within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 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 />.
- b. With a drywell purge supply or exhaust isolation valve, or a suppression chamber purge supply or exhaust isolation valve or the nitrogen supply valve, with resilient material seals having a measured leakage rate exceeding the limit of Surveillance Requirement 4.6.1.8.2, restore the inoperable valve (s) to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 />.
SURVEILLANCE. REQUIREMENTS J
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4.6.1.8.1 Before being opened, the drywell and suppression chamber purge supply and exhaust, and nitrogen supply butterfly isolation valves shall be verified not to have been open for more than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> in the previous 365 l
days.*
l 4.6.1.8.2 At least once per 6 months **, but no more than once per 92 days ***,
the 26-inch drywell purge supply and exhaust isolation valves and the 24-inch q
suppression chamber purge supply and exhaust isolation valves and the 6-inch nitrogen supply valve with resilient material seals shall be demonstrated OPERABLE by verifying that the measured leakage rate is less than or equal to 7
48.1 psig.
0.05 La per penetration when pressurized to Pa Valves open for pressure control are not subject to the 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> per 365 l
days limit, provided the 2-inch bypass lines are being utilized.
Provided that the valve has not been operated since the previous test.
i Applies only to a valve which has been operated since the previous test.
i HOPE CREEK 3/4 6-11 Amendment No.84 l
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CONTAINMENT SYSTEMS BASES
) 1.6.1.5 PRIMARY CONTAINMENT STRUCTURAL INTEGRITY
'This limitation ensures that the structural integrity of the containment 1
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- will be maintained comparable to the original-design standards for the life of
.the unit.
Structural integrity is required to ensure that the containment-will withstand the maximum pressure of 48.1 psig in the event of"a LOCA. A t
visual inspection in conjunction with Type A leakage. tests is sufficient to j
demonstrate.this capability.
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3/4.6.1.6 DRYWELL AND SUPPRESSION CHAMBER INTERNAL PRESSURE.
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-The' limitations on drywell and suppression chamber internal pressure ensure that the containment peak pressure of 48.1 psig does not exceed the i
design pressure of 62 psig during LOCA conditions or that the external
-~ pressure differential.does not exceed the design maximum external pressure differential of-3 paid. The limit of -0.5 to +1.5 psig for initial positive j containment pressure will limit the total pressure to 48.1 peig which is less than the design pressure and is. consistent with the safety analysis.
3/4.6.1.7 DRYWRff. AVERAGE AIR' TEMPERATURE i'
l The limitation on drywell average air temperature ensures that the containment peak air temperature does not exceed the design temperature of 340'F during LOCA conditions and is consistent with the safety analysis. The 135'F average temperature is conducive to normal and long term operation.
3/4.6.1.8 DRYWRf7. AND SUPPRESSION CHApnen PURGE SYSTEM The 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> /365 days limit for the operation of the purge valves and l
the 6" nitrogen supply valve during plant operational Conditions 1, 2 and 3 is intended to reduce the probability of a LOCA occurrence during the above operational conditions when the applicable combination of the above valves are open Blow-out panels are installed in the CPCS ductwork to provide additional assurance that the FRVs will be capable of performing its safety function subsequent to a LOCA.
HOPE CREEK-B 3/4 6-2 Amendment No. 84 l