ML19225B366
| ML19225B366 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/12/1979 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Arkansas Power & Light Co |
| Shared Package | |
| ML19225B367 | List: |
| References | |
| NPF-06-A-012 NUDOCS 7907250061 | |
| Download: ML19225B366 (6) | |
Text
UNITED STATES
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. *k NUCLEAR REGULATORY CCMMisSION b'M S
WASHINGTON, D. C. 20555 h/
'9.. a...f ARKANSAS POLER AND LIGHT COFPANY DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE, UNIT 2 FACILITY OPERATING LICENSE Amendment No.12 License No. NFF'-6 1.
The Nuclear Regulatory Comission (the Comission) having found that:
A.
The issuance of this license amendment 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; B.
The facility will operate in conformity with the application, 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 Ccmission's regulations; D.
The issuance of this amendment will not be inimical to the ccmmon defense and security or to the health and safety of the oublic; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Ccmission's regulations and all applicable requirements hu e been satisfied.
2.
Accordingly, the license is amended by changing the Technical Scecifications as indicated in the attachment to this license and by amencing Paragrachs 2.C.(2 ), 2.C.(3 )(k) and 2.C.(3 )(m) of Facility Operating License No. NFF-6 as follows.
The second paragraph cf 2.C.(2) has not changed.
- 2. C. (2 ) Technical Scecifications The Technical Scecifications contained in Apcendices A & 3, as revised through ecencment No.12 are hereby incorporated in license NPF-6. Arkansas Power and Light Company shall 3perate the facility in acccrdance with Technical Specifications.
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-2 2.C. (3 ) Core Protection Calculator System (CPCS)
(k)
Items (1), (2) and (3) of paragraph 2.C.(3)(k) have been superceded by the following conditions.
In addition, a copy of the startup report addressed by these conditions shall be submitted to the Director of the Division of Project Management in the Office of Nuclear Reactor Regulation.
(4 )
CPCS Position No.19, Sof tware Change Precedure Qualificaticn The licensee's response to items (1), (2), (3) and (4) as identified in the Summary Subsection of Section D.4.4.6 of Supplement No. 2 to the Safety Evaluacion Reporv has been reviewed and approved.
Therefore, these matters have been resolved and item (4) of Ccadition 2.C.(3)(k) is deleted.
2.C. (3 ) ( m) Redundant Valve Position Indication The condition specified in paragraph 2.C.(3)(m) has been resolved and is, t'ierefore, deleted.
3.
This license amendment is effective as of the date of issuance.
F R THE NUCLEAR REGULATORY COMMISSION f' ~
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John F. Stolz, Chief y/
(Light Water Reactors Brdnch No.1 Division of ?roject Management Attac hment :
Changes to the Technical Speci fications Date of Issuance:
jgg i 2 1979 kJb
ATTACHMENT TO LICENSE AMENDMENT NO.12 FACILITt OPERATING LICENSF NO. NPF-6 DOCKET NO. 50-368 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page.
The revised page is identified bv Amenc., 't number and contains a vertical line indicating the area of change.
The corresponding overleaf page u also provided to maintain document completeness.
Pages 6-5 6-Sa (added) 6-6 4b6 3l9
ADMINISTRATIVE CONTROLS 6.3 UNIT STAFF OUALICICATICNS 6.3.1 Each member of the unit staff snall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the Health Physics Supervisor who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the General Manager and shall meet or exceed the requirements ar.d recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.
6.4.2 A training program for the Fire Brigade shall be maintained under the directicn of the General Manager and shall meet or exceed the requirements of Section 27 of the NFPA Code - 1975, except for Fire Brigade training sessions which shall be held at least quarterly.
6.5 REVIEW AND AUDIT 6.5.1 PLANT SAFETY CCMMITTEE (PSC)
FUNCTION 6.5.1.1 The Plan Safety Cermittee shall function to 'dvise the General Manager on all matters related to nuclear safety.
CCMPOSITICN 6.5.1.2 The Plant Safety Cormittee shall be compcsec 'f the:
Chairman:
Operations and Maintenance Manager Member:
Operatiens Superintendent Member:
Technical Analysis Superintendent Member:
Maintenar.ce Superir.tendent Member:
Instrumentation & Controls Superintendent Member:
Plant Analysis Superintendent Member:
Health Physics Supervisor Member:
Nuclear Software Expert
- l The General Manager shall appoint in writing an acting chairman in the absence of the Operations and Maintenance Manager.
- See page 6-5a ARKANSAS - UNIT 2 6-5 Amendment No. 5,12 t+ 5 6
ADMINISTRATIVE CONTROLS ALTERNATES 6.5.1.3 All alternate members shall be appointed in wri.ing by the PSC Chairaan to serve on a temporary basis; however, no more than two lalternates shall participate as voting members in PSC activities at any one time.
MEETING FREQUENCY 6.5.1.4 The PSC shall meet at least or.re per calendar month and as convened by the PSC Chairman or his designated alternate.
CUORUM 6.5.1.5 The minimum quorum of the PCS necessary for the performance of the PSC responsibility and authority provisions of these technical specifications shall consist of the Chairman or his designated alternate and three members including alternates.
RESPONSIBILITIES 6.5.1.6 The Plant Safety Committee shall be responsible for:
a.
Review of 1) all procedures required by Specification 6.8 and changes thereto, 2) any ;.ther proposed procedures or changes thereto as determined by the General Manager to affect nuclear l
safety.
b.
Review of all proposed tests and expc-iments that affect nuclear safety.
Review of all proposed changes to Apper.cix "A" Technical Specit' cations.
d.
Review of all proposed changes or modifications to unit systen.s or equipment that affect nuclear safety.
e.
Investigation of all violations of the Tecnnical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the General Manager and to the Chairman of the Safety Review Ccmmittee. l ARXANSAS - UNIT 2 6-6 Amendment No, y,12.
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