ML19341B731
| ML19341B731 | |
| Person / Time | |
|---|---|
| Site: | Salem |
| Issue date: | 02/02/1981 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19341B732 | List: |
| References | |
| NUDOCS 8102270253 | |
| Download: ML19341B731 (4) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION
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PUBLIC SERVICE ELECTRIC AND GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272 SALEM NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 33 License No. DPR-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 Light Company and Atlantic City Electric Company (the licensees) dated November 18, 1977 as revised on February 14, 1978 and supple-mented by letters dated December 13,1977, May 17, July 31, August 22, October 13 and 31, November 20 and December 22, 1978, January 4 and December 10, 1979 and December 31, 1980, 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 (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 regulatio'ns; 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.
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. 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. DPR-70 is hereby amended to read as follows:
-(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amudment No. 33, are hereby incorporated in the license. 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.
FQR THE NUCLEAR EGULATORY COMMISSION
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arga, Ch e Operating Reactors B ch #1 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: February 2,1981
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i ATTACHMENT TO LICENSE AMENDMENT NO. 33 i
1 FACILITY OPERATING LICENSE NO. DPR-70 1
DOCKET NO. 50-272
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Revise Appendix A as follows:
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DESIGN FEATURES a.
In accordance with the code requirements specified in Section 4.1 of the FSAR, with allowance for normal degradation pursuant to +,ne applicable Surveillance Requirements, b.
For a pressure of 2485 psig, and c.
For a temperature of 650*F, except for the pressurizer which is 680'F.
VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 12,811 + 100 cubic feet at a nominal T of 576.7 F.
3yg 5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
5.6 TUEL STORAGE CRITICALITY 5.6.1 The new and spent fuel storage racks are designed and shall be maintained with a nominal 21 inch center-to-center distance between new fuel assemblies and a nominal 10.5 inch center-to-center distance between spent fuel assemblies placed in the storage racks to ensure a k [# equivalent T8 k o
.to < 0.95 with the storage pool filled with unborated water.
< 0795 includes a conservative allowance of 3.3% ak/k for uncert DRAINAGE l
5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 124'8".
CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1170 fuel assemblies.
Each-assembly is limited to 44.7 grams or less of U-235 per axial centimeter.
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SALEM - UNIT 1 5-5 Amendment 33 i
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