ML20113A112
| ML20113A112 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 04/01/1985 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20113A114 | List: |
| References | |
| TAC-56819, NUDOCS 8504090487 | |
| Download: ML20113A112 (7) | |
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UNITED STATES
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j 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. 2 License No. NPF-29 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Grand Gulf Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-29 filed by the Mississippi Power and Light Company acting for itself, Middle South Energy. Inc., and South Mississippi Electric Power Association (the licensees),datedJanuary 30, 1985, 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; 8.
The facility will operate in conformity with tlie application, as amended, the provisions of the Act, and the regulations of the Comission; 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 Comission'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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is hereby amended by page 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:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through g4090487850401 ADOCK 05000416 p
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. Amendment No.2 and the Environmental Protection Plan contained in Appendix B 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.
3.
This ifcense amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION E u J. A Elinor G. Adenssm, Chief Licensing Branch No. 4 Division of Licensing
Enclosure:
Technical Specification Changes Date of Issuance:
April 1, 1985 m
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ATTACHMENT TO LICENSE AMENDMENT NO. 2 FACILITY OPERATING LICENSE NO. NPF-29 DOCKET NO. 50-416 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change. Th6 corresponding over-leaf pages are also provided 'to maintain document completeness.
Amended Overleaf Page Page 6-3 6-4 6-7 6-8 s
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FIGURE 6.2.1-1 0FFSITE ORGANIZATION
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UNIT ORGANIZ ATION FIGURE 6.2.2-1 UNIT ORGANIZATION
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ACMINISTRATIVE CONTROLS PLANT SAFITY REVIEW COMMITTEE (PSRC) (Continued)
COMPOSITt_0_N 6.5.1.2 The PSRC shall be composed of the:
Chairman:
Manager, Plant Operations Vice Chairman:
Manager, Plant Maintenance Member:
Operations Superintendent Member:
Technical Support Superintendent Member:
Manager, Nuclear Site QA l
Member:
Chemistry / Radiation Control Superintendent Member:
I&C Superintendent Member:
Technical Engineering Supervisor 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.
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QUORUM 6.5.1.5 The quorum of the PSRC necessary for the performance of the PSRC responsibility and tuthority 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.
l b.
The safety evaluations for (1) procedures, (2) changes to procedures, equipment or systems, and (3) tests or experiments completed under i
the provision of Section 50.59, 10 CFR, to verify that such actions l
did not constitute an unreviewed safety question and all programs required by Specification 6.8 and changes thereto.
l c.
Proposed procedures and changes to procedures, equipment or systems which may involve an unreviewed safety testion as defined in i
Section 50.59, 10 CFR.
L d.
Proposed tests or experiments which may involve an unreviewed safety i
question as defined in Section 50.59, 10 CFR.
Proposed changes to Technical Specifications or the Operating License.
e.
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GRAND GULF-UNIT 1 6-7 Amendment No. 2
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ADMINISTRATIVE CONTROLS I'
RESPONSIBILITIES (Continued) f.
Reports of violations of codes, regulations, orders, Technical Specifications, or Operating License requirements having nuclear safety significance or reports of abnormal degradation of systems designed to contain radioactive material.
g.
Reports of significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear.
safety.
h.
Review of all REPORTABLE EVENTS.
All recognized indi, ations of an unanticipated de'ficiency in some 1.
c aspect of design or operation of safety related structures, systems, or components.
J.
The plant Security Plan and changes thereto.
k.
The Emergency Plan and changes thereto.
Items which may constitute a potential nuclear safety hazard as 1.
identified during review of facility operations.
Investigations or analyses' of special subjects as requested by the m.
Chairman of the Safety Review Committee.
Changes to the PROCESS CONTROL PROGRAM, OFFSITE DOSE CALCULATION MANUAL, n.
and radwaste systems.
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AUTHORITY 6.5.1.7 ThePSRCsh[ll:
Recommend in writing to the GGNS General Manager approval or disapproval a.
of items considered under 6.5.1.6.a. c, d, e, j, and k, above.
b.
Render determinations in writing to the GGNS General Manager with regard to whether or not each item considered under 6.5.1.6.a. c and d, above, constitutes an unreviewed safety question.
Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the SRC of disagreement c.
between the PSRC and the GGNS General Manager; however, the GGNS General Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
RECORDS 6.5.1.8 The PSRC shall maintain written minutes of each PSRC meeting that, at a minimum, document the results of all PSRC activities performed under the responsibility and authority provisions of these Technical Specifications.
Copies shall be provided to the SRC.
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GRAND GULF-UNIT 1 6-8
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