ML20212J122
| ML20212J122 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 02/26/1987 |
| From: | Noonan V Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20212J125 | List: |
| References | |
| NUDOCS 8703060322 | |
| Download: ML20212J122 (8) | |
Text
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o UNITED STATES
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PUPl.IC SERVICE El.ECTRIC AND GAS COMPANY PHIl.ADEl.PHIA El.ECTRIC COMPANY del.MARVA POWER AND 1IGHT COMPANY 77f7FTTTC CITY El.ECTPIC COMPANY DOCKET NO. 50-???
SAI.EM NUCf.EAP GENEPATING STATION, UNIT NO. 1 AMENDMENT TO FACII.ITY OPERATING l.ICENSE Amendment No. 76 f.icense No. OPR-70 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Public Service Electric and Gas Company, Philadelphia Electric Company, Delmarva Power and t.ight Company and Atlantic City Electric Ccmpany (the licensees) dated October 3, 1986, complies with the standards and require-ments of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and reculations set forth in 10 CFR Chapter I; P.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and reculations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endanoering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; 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 recuirements have been satisfied.
2.
Accordingly, the license is amended by chances to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph ?.C.(2) of Facility Operating 1.icense.
No. DPR-70 is hereby amended to read as follows:
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(2) Technical Specifications The. Technical Specifications contained in Appendices A and B, as revised +.hrough Amendment No. 76, are hereby incorporated in the license. The licensee shall operate the facility in accorderce with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCl.EAP R,EGUI.ATORY COMMISSION s'
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Tlo a,~ 1 rector
'PWR Project Directorate No. 5 Division ofjPWR I.icensino-A
Attachment:
Cheroes to the Technical Specifications Date of Issuance: February 26, 1987 h
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ATTACPMENTO l.ICENSE AMENDMENT NO. 76 T
FACII.ITY OPEPATING l.iCENSE NO. DPP-70.
DOCKET NO. 50-972 Revise Appendix A as_follows:
Remove Paoes Insert Paces 54 5-4 a
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DESIGN FEATURES DESIGN PRESSURE AND TEMPERATURE 5.2.2 The reactor containment building is designed and shall be maintained for a maximum internal pressure of 47 psig and an air temperature of 271 F.
5.3 REACTOR CORE FUE L ASSEMB LIES 5.3.1 The reactor core shall contain 193 fuel assemblies with each fuel assembly normally containing 264 fuel rods clad with Ziracloy-4 except that limited substitution of fuel rods by filler rods consisting of Ziracioy-4 or stainless steel or by vacancies may be made if justified by a cycle specific reload analysis. Each fuel rod shall have a nominal active fuel length of 143.7 inches and cortain a maximum total weight of 1766 grams uranium. The initial core loading shall have a maximum enrichment of 3.35 weight percent U.235.
Reload fuel shall be similar in physical design to the core loading and shall' have a maximum enrichment of 4.05 weight percent U-236.
CONTROL R0D ASSEMB LIES 5.3.2 The reactor core shall contain 53 full length and no part length control rod assemblies. The full length control rod assemblies shall contain a nominal 142 inches of absorber material. The nominal values of absorber material shall be 80 percent silver,15 percent indium and 5 percent cadmium. All control rods shall be clad with stainless steel tubing.
5.4 REACTOR COOLANT SYSTEM DESIGN FEATURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained:
SALEM - UNIT 1 54 Amendment No. 76 I
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UNITED STATES y
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,o rUAI.IC SERVICE El.ECTRIC AND GAS COMPANY PHJf.ADEl.PHIA El.ECTRIC COMPANY DElMARVA POWER AND 1.IGHT COPPANY ATI.AETIC CITY ELECTRIC COMPANY DOCVET NO. 50-311 SAI.EM NUCl. EAR GENERATING STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING l.} CENSE Amendment No. 50 f.icense No. DPR-75 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Public Service Electric and Gas Company, Philadelphia Electric Company, Delmarva Power and I.ight Company and Atlantic City Electric Company (the licensees) dated October 3, 1986, complies with the standards and require-ments of the Atomic Enerov Act of 1954, as amended (the Actl and the Commission's rules and reaulations 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 (i) that the activities authorized by this amendment can be conducted without endancering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; 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 reoufrements have been satisfied.
2 Accordinolv, the license is amended bv changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 7.C.(2) of Facilf tv Operating 1.icense No. DPR-75 is hereby amended to read as follows:
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(?) Technical Specifications The. Technical Specifications contained in Appendices A and B, as revised through Amendment No. 50, are hereby incorporated in the licerse. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCl. EAR REGUI.ATORY COMMISSION
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,4WD Project, Directorate No. 5 Division of PWR I.icentino A
Attachment:
Charces to the Technical Specifications Date of Issuance: February 26, 1987
m ATTACHMENT TO I.ICENSE AMENDMENT NO. 50 FACTI.ITY OPERATING l.ICENSE NO. DPR-75 00CKET NO. 50-311 Revise Appendix A as follows:
Renove Paaes QsertPaaes 5-4 5-4 1
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C' DESIGN FEATURES '
DESIGN PRESSURE AND TEMPERATURE 5.2.2 The reactor containment building is designed and shall be maintained for a maximum internal pressure of 47 psig and an air temperature of 271 F.
5.3 REACTOR CORE FUE L ASSEM3 LIES 5.3.1 The reactor core shall contain 193 fuel assemblies with each fuel assembly normally containing 264 fuel rods clad with Ziracioy-4 except that limited. substitution of fuel rods by filler rods consisting of Ziracioy-4 or stainless steel or oy vacancies may be made if justified by a cycle specific reload analysis. Each fuel rod shall have a nominal active fuel length of 143.7 inches and contain a maximum total weight of 1766 grams uranium. 'The initial core loading shall have a maximum enrichment of 3.55 weight percent U-235.
Reload fuel shall be similar in physical design to the core loading and shall have a maximum enrichment of 4.05 weight percent U-235.
CONTROL R0D ASSEMB LIES 5.3.2 The reactor core shall contain 53 full length and no part length control rod assemblies. The full length control rod assemblies shall contain a nominal 142 inches of absorber material. The nominal values of absorber material shall be 80 percent silver,15 percent indium and 5 percent cadmium. All control rods shall be clad with stainless steel tubing.
5.4 REACTOR COOLANT SYSTEM DESIGN FEATURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained:
In accordance with the code requirement specified in Section 4.1 of a.
the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements, b.
For a pressure of 2485 psig, and For a temperature of 650 F, except for the pressurizer which is c.
680 F.
VO LU1E 5.4.2 The total water and steam volure of the reactor coolant system is 12,811 + 100 cubic feet at a noninal Tavg of 581.0'F.
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