ML20204K009
| ML20204K009 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 07/30/1986 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20204J983 | List: |
| References | |
| TAC-61624, NUDOCS 8608110258 | |
| Download: ML20204K009 (5) | |
Text
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g UNITED STATES NUCLEAR REGULATORY COMMISSION o
.,E WASHINGTON, D. C. 20555
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MISSISSIPPI POWER & LIGHT COMPANY MIDDLE SOUTH ENERGY, INC.
SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION DOCKET NO. 50-416 GRAND GULF NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 14 License No.-NPF-29 1.
The Nuclear Regulatory Commission (the Comission) has found that A.
The application for amendment by Mississippi Power & Light Company, Middle South Energy, Inc., and South Mississippi Electric Power Association, (the licensees) dated June 4, 1986, 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 (1) that the activities authorized by this amendn> nt 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; 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.
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. NPF-29 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 14
, are hereby incorporated into this license..
Mississippi Power & Light Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
8608110258 860730 PDR ADOCK 05000416 P
. 3.
This license amendment-is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
%IW by Walter R. Butler, Director BWR Project Directorate No. 4 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: July 30, 1986 Y
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ATTACHMENT TO LICENSE AMENDMENT NO. 14 FACILITY OPERATING LICENSE N0. NPF-29 DOCKET NO. 50-416 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
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E FIGURE 6.2.2-1 UNIT ORGANIZATION M
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ADMINISTRATIVE CONTROLS PLANT SAFETY REVIEW COMMITTEE (PSRC) (Centinued)
COMPOSITION j
l 6.5.1.2 The PSRC shall be composed of the:
Chairman:
Manager, Plant Support i
Vice Chairman / Member:
Manager, Plant Operations Member:
Manager, Plant Maintenance Member:
Operations Superintendent Member:
Technical Support Superintendent Member:
Manager, Nuclear Site QA Member:
Chemistry / Radiation Control Superintendent Member:
I&C Superintendent Member:
Plant Licensing Superintendent ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the GGNS General Manager to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PSRC activities at any one time.
MEETING FREQUENCY 6.5.1.4 The PSRC shall meet at least once per calendar month and as convened by the PSRC Chairman or Vice Chairman.
QUORUM 6.5.1.5 The quorum of the PSRC necessary for the performance of the PSRC responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or Vice Chairman and four members including alternates.
RESPONSIBILITIES 6.5.1.6 The PSRC shall be responsible for review of:
a.
Station administrative procedures and changes thereto.
I b.
The safety evaluations for (1) procedures, (2) changes to procedures, equipment or systems, and (3) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question and all programs required by Specification 6.8 and changes thereto.
c.
Proposed procedures and changes to procedures, equipment or systems which may involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
d.
Proposed tests or experiments which may involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
Proposed changes to Technical Specifications or the Operating License.
e.
GRAND GULF-UNIT 1 6-7 Amendment No. 14 l
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