ML20154B662
| ML20154B662 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 10/01/1998 |
| From: | Capra R NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20154B666 | List: |
| References | |
| NUDOCS 9810050273 | |
| Download: ML20154B662 (5) | |
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A uco UNITED STATES j
NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 20ss6-0001 44.....,o PUBLIC SERVICE ELECTRIC & GAS COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-354 HOPE CREEK GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.112 Ucense No. NPF-57 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by the Public Service Electric & Gas Company (PSE&G) dated May 13,1998, 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; B.
The facility will operate in conforrrity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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 this amendment will not be inimical to the common 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 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:
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9810050273 981001
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PDR ADOCK 05000354 P
PDR 1
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2-l (2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.112 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 500 0-.0Q Robert A. Capra, Director Project Directorate 1-2 Division of Reactor Projects - 1/11 i
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications
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Date of issuance: October 1, 1998
ATTACHMENT TO LICENSE AMENDMENT NO.112 FACILITY OPERATING LICENSE NO. NPF-57 DOCKET NO. 50-354 Repla::e the following page of the Appendix "A" Technical Specifications with the attached page.
The revised page is identified by Amendment number and contains vertical lines indicating the areas of change. An overleaf page has been provided.*
Remove 1012d 3/4 10-7*
3/4 10-7*
3/4 10-8 3/4 10-8
SPECIAL TEST EXCEPTIONS 3/4.10.9 INSERVICE LEAK AND HYDROSTATIC TESTING LIMITING CONDITION FOR OPERATION I
3.10.8 When conducting inservice leak or hydrostatic testing, the average reactor coolant temperature specified in Table 1.2 for OPERATIONAL CONDITION 4 may be increased to 212*F, and operation considered not to be in OPERATIONAL CONDITION 3, to allow performance of an inservice leak or hydrostatic test provided the following OPERATIONAL CONDITION 3 LCO's are mets a.
3.3.2,
" ISOLATION ACTUATION INSTRUMENTATION", Functions 2.a, 2.c, l
2.d and 2.e of Table 3.3.2-1; b.
3.6.5.1,
" SECONDARY CONTAINMENT INTEGRITY";
c.
3.6.5.2,
" SECONDARY CONTAINMENT AUTOMATIC ISOLATION DAMPERS"; and d.
3.6.5.3,
" FILTRATION, RECIRCULATION AND VENTILATION SYSTEM."
APPLICABILITY:
OPERATIONAL CONDITION 4, with average reactor coolant temperature > 200*F.
ACTION:
With the requirements of the above specification not satisfied, immediately enter the applicable condition of the affected specification or immediately suspend activities that could increase the average reactor coolant temperature or pressure and reduce the average reactor coolant temperature to s 200*F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REQUIREMENTS
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4.10.8 Verify applicable OPERATIONAL CONDITION 3 surveillances for specifications listed in 3.10.8 are met.
i HOPE CREEK 3/4 10-8 Amendment No.112 l
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$PECIAL TEST EXCEPTIONS 3/4.10.7 SPECIA* INSTRUMENTATION
- INITIAL CORE LOA 0!NG LIMITING CONDITION FOR OPERATION 3/4.10.7 with the issuance of Amendment No.14.The material originally contained reference to this section, Section 3/4.10.7 is intentionally left blank.Howe
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