ML17139B516
| ML17139B516 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 04/14/1983 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17139B517 | List: |
| References | |
| NUDOCS 8304260157 | |
| Download: ML17139B516 (4) | |
Text
PENNSYLVANIA POWER 5 LIGHT COMPANY SUSQUEHANNA S AN A IOH, UNIT 1 Amendment Ho. 13 License Ho. NPF-14 1.
The Nuclear Regulatory Commission (the Commission or the HRG) having found that:
G.
The application for an amendment filed by the Pennsylvania Power 5 Light Company dated March 14, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission (except as exempted from compliance in Section 2.E. below);
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 (except as exempted from compliance in Section 2.E. below);
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 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 in paragraphs 2,D and 2.E.
of the Facility Operating License No. NPF-14 to rea'd as follows:
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PP&L shall maintain in effect and fully implement all provisions of the Commission approved physical security, and guard training and qualification plans; including amendments made pursuant to the authority of 10 CFR 550.54(p).
The approved plans, which contain 10 CFR 73.21 information, are collectively entitled:
"Susquehanna Steam Electric Station Physical Security Plan" (which includes response to security contjngencies as Chapter
- 11) dated Inarch 14, 1978 with the following changes; Change A dated July 31, 1978, Change 8 dated February 15, 1979, Change G dated August 15, 1979, Change D dated September 28, 1979, Change E dated May 22, 1980, Change F dated Itarch 27, 1981, Change G dated May 29, 1981, Change H dated June 26,
- 1981, Change I dated March 19, 1982, Change J dated April 1, 1982, and Change K dated I'1ay 4, 1982, Change L dated July 9, 1982, Change III dated October 15, 1982, and including Chapter 11 revision dated June 5, 1981; and "Susquehanna Steam Electric Station Security Training and OFFICE/
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NRC FORM 318 (10.80) NRCM 0240 OFFICIAL RECORD COPY USGPO: 1981~960
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E.
Exemptions from certain requirements of Appendices G and H to 10 CFR Part 50 are described in the Safety Evaluation Report and Supplements 1 and 2 to the Safety Evaluation Report.
In addition, an exemption vias reques'ted until receipt of nevi fuel for first refueling from the requirements for criticality monitors in the spent fuel pool area, 10 CFR Part 70.24.
Also, an exemption vias requested from the requirements of Appendix J of 10 CFR Part 50 for the first fuel cycle vihen performing local leak rate testing of Residual Heat Removal (RHR) relief valves in accordance with Technical Specification 4.6.1.2.
This latter exemption is described in the safety evaluation of License Amendment No. 13.
These exemptions are authorized by law and will not endanger life or property or the common defense and security and are otherwise in the public interest and have been granted pursuant to 10 CFR 50.12.
Except as here exempted, the facility will operate, to the extent authorized herein, in conformity with the application, as
- amended, and the rules and regulations of the Commission and the provisions of the Act.
3.
This, amendment, is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COÃIISSION Date of Issuance:
APR 1 4 1983 Darrel G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation
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'NRC FORM 318 (10.80) NRCM 0240 OFFlClAL RECORD COPY US0FOi 1981~960 E.
Exemptions from certain requirements of Appendices G and H to 10 CFR l
Part 50 are described in the Safety Evaluation Report and Supplements 1 and 2 to the Safety Evaluation Report.
In addition, an exemption was requested until receipt'of new fuel for first refueling from the requirements for criticality monitors in the spent fuel pool area, 10 CFR Part 70.24.
Also, an exemption was requested from the requiremen~ts of Appendix J of-10 CFR Part 50 for the first fuel cycle when pqrforming local leak rate testing of Residual Heat Removal (RHR) relief valves in accordance with Technical Specification 4.6.1.2.
This 1'atter exemption is described in the safety evaluation of License Amendment No.
These exemptions are authorized by law and will not endanger life.or property or the common defense and security d
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dfd he facility will operate, to the extent, authorized ere n, in conformity <<ith the application, as amended, and the rules and regulations of the Commission d
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3.
This amendment is effective as of the date of issuance.
FOR THE NUCL'EAR REGULATORY CORCISSION Date of Issuance:
Darrell G. Eisenhut ~Director Division of Licensing '.,
Office of Nuclear Reactor, Regulation OFFICEI SURNAME$
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/83 NRC FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY USGPO: 1991~5.960