ML20066G626
| ML20066G626 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 11/12/1982 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20066G629 | List: |
| References | |
| NUDOCS 8211220475 | |
| Download: ML20066G626 (5) | |
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SOUTH CAROLINA ELECTRIC & GAS COMPAllY SOUTH CAROLIHA PUBLIC SERVIC6 AUTHORITY DOCKET NO. 50-395 VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 5 License No. HPF-12 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application, as amended for a license filed by the South Carolina Electric & Gas Company acting for itself and South Carolina Public Service Authority (the licensees) complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Comission; 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 Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; E.
The issuance of this license amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Paragraph 2C(1) is hereby modified to read as follows:
Maximum Power Level SCE&G is authorized to operate the facility at reactor core power levels not in excess of 2775 megawatts thermal in accordance with the conditions specified herein and in Attachaent 1 to this license. The preoperational tests, startup tests and other items identified in Attachment 1 to this I
license shall be completed as specified. Attachment 1 is hereby incorporated into this license.
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Paragraph 2C(6) is hereby amended to read as follows:
Design Verification Program (Section 3.7.4, SSEP #5)
Prior to December 31, 1982 SCE&G shall provide a final report to the NRC staff delineating the final resolution of the actions taken to satisfy the recomendations of the independent design verification conducted by Stone & Webster Engineering Corporation.
4 Paragraph 2C(7) is hereby amended to read as follows:
Thernal Sleeves (Section 3.9.3, SSER #5)
Prior to startup after the first refueling outage, SCE&G shall provide, for NRC staff review and approval, justification for continued operation with the thermal sleeves renoved from selected nozzles in the reactor coolant system.
5.
Paragraph 2C(14) is hereby amended to read as follows:
Model 0-3 Steam Generator (Section 5.4.2, SSER #5)
Prior to operation in excess of 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> at power levels in excess of 5%
of full power or operation at power levels in excess of 50% of full power, SCE&G shall satisfy the HRC staff that appropriate hardware modifications and appropriate surveillance measures have been impleoented with respect to steam generator tube vibration.
6.
Paragraph 2C(33) has been added to read as follows:
Emergency Preparedness Exercise (Section 13.3, SSER #5) l Prior to March 31, 1983, SCEAG shall conduct sn emergency exercise similar l
to that ccaducted on May 5,1982 but which includes full participation of the local governments and partial State participation.
7.
Paragraph 20 is hereby amended to read as follows:
An exemption to the requirements of Paragraph III.B.4 of Appendix G to 10 CFR Part 50 is described in Section 5.3.1 of Supplement No.1 to the Office of Nuc1 car Reactor Reculation's Safety Evaluation Report. A limited exemption to the requirements of Section IV.F.1(b) of Appendix E to 10 CFR Part 50 1s described in a letter from B. J. Youngblood, HRC to 0. W. Dixon, Jr.,
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dated Hovember 2, 1982. These exemptions are authorized by law and will not endanger life or property or the comon defense and security and are otherwise in the public interest. The facility will operate, to the extent I
authorized herein, in conformity with the application, as anended, the provisions of the Act, and the rules and regulations of the Commission.
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Paragraph 2G(1) is hereby amended to read as follows:
SCE&G shall report any violations of the requirements contained in Section 2, Itens C(1), C(3) through (33), E and F of this license within twenty-four (24) hours by telephone and confirn by telegram, mailgrao, or facsimile transmission to the NRC Regional Adninistrator, Region II, or designee, not later than the first working day following the violation, with a written followup report within fourteen (14) working days.
9.
Paragraph 21 is designated 2J and a new paragraph 21 has been added to read as follows:
In accordance with the Commission's direction in its Statement of Policy, Licensing and Regulatory Policy and Procedures for Environmental Protection; Uranium Fuel Cycle Impacts, October 29, 1982, this license is subject to the final resolution of the pending litigation involving Table S-3.
See, !!atural Resources Defense Council v. flRC, No. 74-1586 (April 27, 1982).
- 10. This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY C0'tilSS1011 Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation Date of Issuance: NOV 121982
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8.
Paragraph 21 is designated 2J and a new paragraph 21 has been added to read as follcws:
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In accordance with the Comission's direction in its Statement of Policy, Licensing and Renulatory Policy and Procedures for Environmental Protection; Uranturn Fuel Cycle Irnpacts, October 29, 1982, this license is subject to the final resolution of the pending litigation involving Table S-3.
See, Natural Resources Defense Council v. HRC, No. 74-1586/(Apr11 27, 1982).
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9.
This license amendment is effective as of its date of issuance.
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FOR THE !!UCLEAR REGULATORY C05t11SSION Darrell G. Eisenhut, Director Division of Licensing
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Office of Nuclear Reactor Regulation Date of Issuance:
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. 3.
Paragraph 2C(7) is hereby amended to read as follows:
Thermal Sleeves (Section 3.9.3, SSER #5)
Prior to startup after the first refueling outage, SCC &G shall provide, for NRC staff review and approval, justification for continued operation with the thermal sleeves removed from selected nozzles in the reactor coolant system.
4 Paragraph 2C(14) is hereby amended to read as follows:
Model D-3 Steam Generator [ Section 5.4.2. SSER #5)
Prior to operation in excess of 2000 ours at power levels in excess of 5% of full power or operation at p'oder levels in excess of 50% of full power, SCEAG shall satisfy the NR0 staff that appropriate surveillance measures and remedial action plan's have been implemented with respect to steam generator tube vibratidn.
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5.
Paragraph 2C(33) has been added to read as follows:
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Emergency Preparedness Exercise (Section 13.3, SSER #5) 31,1983,!SCE&G shall conduct an emergency exercise similar Prior to March to that conducted on 1(ay 5,1982 but which includes full participation of the local government and partial State participation.
6.
Paragraph 2D is hereby amended to read as follows:
/
An exemption to the requirements of Paragranh III.B.4 of Appendix G to 10 CFR Part 50 is described in Section 5.3.1 of Supplenent No. I to the Office of Nuclear Reactor Regulation's Safety Evaluation Report. A limited exenption to the requirements of Section IV.F.1(b) of Appendix E to 10 CFR Part 50 is described in a letter from B. J. Youngblood, NRC to 0. W. Dixon, Jr.,
f iated Hoventjer 2,1982. These exemptions are authorized by law and will not endang life or property or the comon defense and security and are otherwise n the public interest. T M r:S r;, it x t',c.;..
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The facility will operate, to the extent authorized herein, in conformi y with the application, as amended, the provisions of the Act, and the rul.s and regulations of the Comission.
7.
Parag aph 2G(1) is hereby anended to read as follows:
SCE 2 shall rer. ort any violations of the requirenents contained in Section 2,
tens C(1), C(3) through (33), E and F of this license within twer.ty-four (24) hours by telephone and confirm by telegram, nallgram, or facsimile j
transmission to the flRC Regional Administrator, Region II, or designee, not later than the first working day following the violation, with a written followup report within fourteen (14) working days.
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