ML20084G078
| ML20084G078 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 05/25/1995 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Public Service Electric & Gas Co, Atlantic City Electric Co |
| Shared Package | |
| ML20084G083 | List: |
| References | |
| NPF-57-A-073 NUDOCS 9506020425 | |
| Download: ML20084G078 (7) | |
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NUCLEAR REGULATORY COMMISSION 2
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PUBLIC SERVICE ELECTRIC & GAS COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-354 HOPE CREEK GENERATING STATION AMENOMENT TO FACILITY OPERATING LICEt$1 Amendment No. 73 License No. NPF-57 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
s A.
The application for amendment filed by the Public Service Electric &
Gas Company (PSE&G) dated August 30, 1994, 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 conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance:
(1) 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 Conmiission'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:
j (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 73, and the Environmental Protection Plan I
contained in Appendix B, are hereby ir.corporated into the license.
l PSE&G shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
l 9506020425 950525 DR ADOCK 050003 4 1
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. - 3.
The license amendment is effective as of its date of issuance and shall be implemented within 60 days.
FOR THE NUCLEAR REG LATORY COMMISSION 0/'
n F. Stolz, Dire or P oject Directorate I-2 ivision of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications s
Date of Issuance:
May 25, 1995
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ATTACHMENT TO LICENSE AMENDMENT NO. 73 FACILITY OPERATING LICENSE NO. NPF-57 DOCKET NO. 50-354 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 ix ix xviii xviii 3/4 3-90 3/4 3-90 s
B 3/4 3-6 B 3/4 3-6
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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAQE Table 3.3.7.4-1 Remote Shutdown Monitoring Instrumentation.......................
3/4 3-75 Table 3.3.7.4-2 Remote Shutdown Systems Controla......
3/4 3-77 Table'4.3.7.4-1 Remote Shutdown Monitoring Instrumentation Surveillance Requirements..........................
3/4 3-82 Accident Monitoring Instrumentation.....................
3/43 84 Table 3.3.7.5-1 Accident Monitoring Instrumentation...
3/4 3-85 Table 4.3.7.5-1 Accident Monitoring Instrumentation Surveillance Requirements.............
3/4 3-87 Source Range Monitors...................................
3/4 3-88 Traversing In-Core Probe System.........................
3/4 3-89 Radioactive Liquid Effluent Monitoring Instrumentation..
3/4 3-91 Table 3.3.7.9-1 Radioactive Liquid Effluent Monitoring Instrumentation......
3/4 3-92 Table 4.3.7.9-1 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements..........................
3/4 3-94 Radioactive Gaseous Effluent Monitoring Instrumentation.
3/4 3-96 Table 3.3.7.10-1 Radioactive Gaseous Effluent Monitoring Instrumentation...........
3/4 3 97 Table 4.3.7.10-1 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements...
3/4 3-100 3/4.3.8 TURBINE OVERSPEED PROTECTION SYSTEM..
3/4 3-103 3/4.3.9 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION.
3/4 3-105 s
Table 3.3.9-1 Feedwater/ Main Turbine Trip System Actuation Instrumentation.
3/4 3-106 HOPE CREEK ix Amendment No.73
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INDEX
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BASES l
.............u..........................................................
SECTION PAQg INSTRUMENTATION (Continued) i' Seismic Monitoring Instrumentation.................
B 3/4 3-4 Meteorological Monitoring Instrumentation..........
B 3/4 3-4 Remote Shutdown Monitoring Instrumentation a'nd Controls.
B 3/4 3-5 Accident Monitoring Instrumentation................
B 3/4 3-5 Source Range Monitors..............................
B 3/4 3-5 3
Traversing In-Core Probe System....................
B 3/4 3-5 Radioactive Liquid Effluent Monitoring g
i Instrumentation..................................
B 3/4 3-6 Radioactive Gaseous Effluent Monitoring s
Instrumentation....................................
B 3/4 3-6 x
I 3/4.3.8 TURBINE OVERSPEED PROTECTION SYSTEM................
B 3/4 3-7 3/4.3.9 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION.................................
B 3/4 3-7 Figure B3/4 3-1 Reactor Vessel Water Level.........
B 3/4 3-8 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM...............................
B 3/4 4-1 3/4.4.2 SAFETY / RELIEF VALVES...............................
B 3/4 4-la 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems..........................
B 3/4 4-3 Operational Leakage................................
B 3/4 4-3 3/4.4.4 CHEMISTRY..........................................
B 3/4 4-3 3/4.4.5 SPECIFIC ACTIVITY..................................
B 3/4 4-4 3/4.4.6 PRESSURE / TEMPERATURE LIMITS........................
B 3/4 4-5 t
Table B3/4.4.6-1 Reactor vessel Toughness..........
B 3/4 4-7 i
l Figure B3/4.4.6-1 Fast Neutron Fluence (E>1Mev) at (1/4)T as a i
Function of Service life.........
B 3/4 4-8 i
4 I
HOPE CREEK xviii Amendment No.73 1
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PAGE 3/4 3-90 IS DELETED l
1 HOPE CREEK 3/4 3-90 Amendment No.73
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INSTRUMENTATION BASES a..............................................
MONITORING INSTRUMENTATION (Continued) 3 / 4. 3. 7 '. 8 The material originally contained in Section 3/4.3.7.8 was deleted with the issuance of the Full Power license. HOwever, to maintain numerical continuity between'the succeeding sections and existing station procedural references to those Technical Specifications Sections 3/4.3.7.8 has been intentionally left blank.
3/4.3.7.9 LOOSE-PART DETECTION SYSTEM THIS SECTION DELETED 3/4.3.7.10 RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents.
The alarm / trip points for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20.
The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.
3/4.3.7.11 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents.
The alarm / trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM.
This will ensure the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20.
This instrumentation also includes provisions for monitoring and controlling the con entrations of potentially explosive gas mixtures in the main condenser offgas treatment system.
The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR part 50.
i HOPE CREEK B 3/4 3-6 Amendment No.73 i