ML20006A137
| ML20006A137 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 01/17/1990 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20006A138 | List: |
| References | |
| NUDOCS 9001250271 | |
| Download: ML20006A137 (8) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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t Pl'BLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATI. ANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272 SALEM GENERATING STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 107 License No. DPR-70 1.
The Nuclear Regulatory Comission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Public Service Electric &
Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated September 28, 1989 complies with the standards and requirements of 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 provisiert of the Act, and the rules and regulations of the Commission; i
C.
There is reasorable 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 set forth in 10 CFR Chapter 1:
D.
The issuance of this amendment will not be inimical to the common defense and security or to the health end safety of the public: end E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Cemission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by cFanges to the Technical Specifica-tions as ir.oicated in the attachr.ent to this license amendment, and paragraph 2.C.(2) of Facility Operatino License No. DPR-70 is hereby arended to read as follows:
9001250271 900117 f #'
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(2) Technical Specifications and Environmental Protect'on Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
107, are hereby incorporated in the licente. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMPIS$10N 1
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w Walter R. Butler Director Froject Directorate 1-2 Division of Reactor Projects 1/11
Attachment:
Changes to the Technical Specifications i
Date of Issuance:
January 17, 1990
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ATTACHMENT TO LICENSE AMENDMENT NO. 107 FACILITY OPERATitlG LICENSE NO. DPR-70
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DOCKET NO. 50-272 i
Revise Apperidix A as follows:
Remove Page Insert Page 3/4 5-Et, 3/4 5-5b i
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.c EMERCENCY CORE COOLINC SYSTEMS SURVEILLANCE RE0ttIREMENTS (Continued) i.
The automatic interlock function of the RMR System shall be verified within the seven (7) days prior to placing the RMR System in service for cooling of the Reactor Coolant System. This shall be done by verifying with a test signal corresponding to a reacter coolant pressure of 375 psig or greater, that the IRH1 and 1RH2 valves cannot be opened.
SALEM UNIT 1 3/4 5 5b Amendment No. 107 1
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7' UNITED STATES 1
g NUCLEAR REGULATORY COMMISSION wassiNotoN,o c.20sss PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLAt: TIC CITY ELECTRIC COMPANY 00Cr.ET NO. 50-311 SALEM GENERATING STATION, UNIT NO. 2 I
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 84 License No. DPR-75 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that.
t A.
The application for amendment filed by the Public Service Electric &
Gas Company, Philadelphia Electric Company,(Delmarva Power a; Company and Atlantic City Electric Company the licer. sees) dated I
September 28, 1989 cornplies with the standards and recuirements 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 M4% in conformity with the application, the i
provisions of the.a t, of the rules and regulations of the c
Commission; C.
There is reesonable assurance: (i) that the activities authorized by this arrendment can be conducted without endangering tbc health and safety of the public, and (ii) that such activities will be conducted ir compliance with the Comission's regulations set forth in 10 CFR i
Chapter 1; 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 emendment is in accordence with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Acccrdingly, the license is emended by changes to the Technical Specifica-tions as irdicated in the attachment to this license amendment, ard paracraph 2.C.(2) of facility Operating License No. DPR-75 is hereby amended to read as fo11cws:
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- l (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 84, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This literse amendment is effective as of its date of issuance.
Implementation shall be before startup from the fifth refueling outage currently scheduled to begin in March 1990.
FOR THE NUCLEAR REGULATORY C0KNISS10N (b
L L L.
Walter R. Butler, Director Project Directorate 1-2 Division of Reactor Projects 1/11
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 17, 1990 j
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ATTACHMENT TO LICENSE AMENDMENT NO. 84 EACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Revise Appendix A as follows:
Remove Page Insert Page i
3/4 5-6a 3/4 5-6a a
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EMERCENCY CORE COOLING SYSTEMS i
SURVEILLANCE REOUIPEMEN'TS (Continued) i.
The automatic interlock function of the RRR System shall be verified i
within the seven (7) days prior to placing the RRR System in service for cooling of the Reactor Coolant System.
This shall be done by verifying with a test signal corresponding to a reactor coolant pressure of 375 ps16 or greater, that the 2RH1 and 2RH2 valves cannot be opened.
- (Footnote from page 3/4 5 6)
Flow balance testing pursuant to Specification 4.5.2.h shall be performed the first time the unit is in COLD SKUTDOWN af ter December 15, 1961.
SALEM L* NIT 2 3/4 5 6a Amendment No P4