ML20107M016
| ML20107M016 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/29/1984 |
| From: | John Miller, Stolz J Office of Nuclear Reactor Regulation |
| To: | Arkansas Power & Light Co |
| Shared Package | |
| ML20107M018 | List: |
| References | |
| DPR-51-A-085, NPF-06-A-057 NUDOCS 8411130740 | |
| Download: ML20107M016 (10) | |
Text
I UNITED STATES y
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ARKANSASP0$ER&LIGHTCOMPANY DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE, UNIT 1 AMEN 0 MENT TO FACILITY OPERATING LICENSE
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Amendment No. 85 i
License'No. DPR-51 y,
31.
The Nuclear Regulatory Commissinn (the Commission) has found that:
e A.
The application for amendment by Arkansas Power and Light Company (the licensee) dated March 16, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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, anc the rules and regulations of the Commission; C..
.There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and
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safety of the public, and (ii) that such activities will be conducted in compliance with the Connission's regulations; D.
The issuance of this amendment will not be. inimical to the common defense and security or tc lthe health and safety o' the public; and E.
The issuance-of this amendme'nt is in accordance with 10 CFR Part 51 of the Comission's.regir.,'nions and all applicable recuirements have been satisfied.
s 2.
Accordingly, the license is anen'ded 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. DPR-51 is hereby amended to read as follows:
8411130740 841029 PDR ADOCK 05000313 P
. Tech 5icalSpecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment flo. 85, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSI0ri T />.,
John [ & M. j G. U -6 J.
F. Stolz, Chief 3
-0pepating deactors Branch #4 D Wision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 29, 1984 N
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ATTACHMENT TO LICENSE AMENDftENT NO. 85 FACILITY OPERATING LICENSE NO. DPR-51 i
DOCKET NO. 50-313 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contains a vertical line indicating the area of change.
Remove Insert 117 117 117a T
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6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The ANO General fian.iger shall be responsible for overall facility cperation.and shall delegate in writing the succession to this responsibility during his.aosence.
6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for facility management and technical support shall be as shown on Figure 6.2.-l.
FACILITY STAFF 6'. 2. 2 -
The Facility organization shall be as shown on Figure 6.2.-2.
Each on duty shift shall be composed of at least the minimun shift crew composition shown in Table 6.2.-l.
6.2.2.1 Administrative controls shall be established to limit the amount of overtime worked by plant staff performing safety related functions. These administrative controls shall be in accordance with the guidance prcvided by the NRC Policy Statement on working hours (Generic Letter No. 82-12).
6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for compar=ble position, except for (1) the Health Physics Superintendent who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975 ind (2) the Shift Technical Advisor who shall have a bachelor % degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysi.s of the plant for transients and accidents ~.
6.4 TRAINING l
6.4.1 A retraining and replacement training program for the facility staff shall be maintained and shall meet or exceed the require-ments and 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 fire protection training shall be maintained ard shall meet or exceed the requirements of Section 27 of the NFPA Code-1975 with the exception of frequency of training which shall be held at least quarterly.
Amendment No. 7%, #, #, U,
-117-A7, g, p, g, n, 85
6.5 REVIEW AND AUDIT 6.5.1 Plant Safety Committee (PSC) Function 6.5.1.1 The Plant Safety Committee shall function to advise the ANO General Manager on all matters related to nuclear safety.
1 COMPOSITION
- 6. 5.1. 2 The ' Plant Safety Committee shall be composed of the:
(See Page 121)
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I Amendment No.
85
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./ i NUCLEAR REGULATORY COMMISSION 3
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_13,r ARKANSAS POWER & LIGHT COMPANY 00CKET NO. 50-368 ARKANSAS NUCLEAR ONE, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 57 License No. NPF-6 1.
The Nuclear Regulatory Commission (the Commis ion) has found that:
A.
The application for amendment by Arkansas Power and Light Company (the licensee) dated March 16, 1984, 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 (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; D.
The issuance of this amendment will not be' inimical to the ccmmon defense and security or to the health and safety of the public; and E.
The issuance of this anendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirenents Pave l
been satisfied.
l 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, l
and paragraph 2.C.(2) of Facility Operating License No. f!PF-6 is hereby amended to read as follows:
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Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 57, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
2.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION James R. Miller, Chief Operating Reactors Branch 43 Division of Licensing
Attachment:
Changes to the-Technical Specifications Date of Issuance:
October 29, 1984 l-i l-r
ATTACHMENT TO LICENSE AMENDMENT N0. 57 FACILITY OPERAT:NG LICENSE NO. NPF-6 DCCKET NO. 50-368 Replace the following page of the Appendix "A" Technical Speci#ications with the enclosed page. The revised page is identified by Amenoment number and contains vertical lines indicating the area of change.
The enrresponding overleaf page is provided to maintain document completeness.
Remove Page Insert Page 6-1.
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6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 lhe ANO General Manager shall be responsible for overall facility operation and shall delegate in writing the succession to this responsi-bility during his absence.
6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for facility management and technical support shall be as shown on Figure 6.2-1.
FACILITY STAFF 6.2.2 The Facility organization shall be as shown on Figure 6.2-2 and:
a.
Each on duty shift shall ue composed of at least the minimum shift crew composition shown in Table 6.2-1.
b.
At least one licensed Operater shall be in the control room when fuel is in the reactor.
c.
At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.
d.
An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor. -
e.
All CORE ALTERATIONS shall be directly supervised by either a i
licensed Senior Reactor Operator or Senior Reactor Operator l
Limited to Fuel Handling who has no other concurrent responsibilities during this operation.
f.
A site Fire Brigade of at least 5 members shall be maintained onsite at all times. The Fire Brigade shall not' include 3 members of the minimum shift crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency.
l Administrative controls shall be established to limit the amount g.
of overtime worked by plant staff performing safety related functions. These administrative controls shall be in accordance with the guidance provided by the NRC Policy Statement on working hours (Generic Letter No. 82-12).
ARKANSAS-UNIT 2 6-1 Amendment No. E, 57 l
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ENERGY SUPPLY SENIOR g
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VICE PRESIDENT l
DIRECTOR l
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DIRECTOR COMMITTEE l
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QUALITY A
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NUCLEAR AN0 N
SERVICES GENERAL MANAGER MANAGER I
E E. S. ADMIN.
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CORPORATE PLANT SERVICES SERVICES SERVICES g
HEALTH SAFETY GENERAL GENERAL GENERAL
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(1) The Energy Supply Senior Vice President is on a temporary leave of absence from AP&L, serving as the y
Senior Vice President of Nuclear Operations for Louisiana Power and Light Company.
During this absence, Mr. J. D. Phillips, Senior Vice President will assume senior management of the Energy Supply Department g
reporting directly to the President and Chief Executive Officer.
h (2) In the absence of the Energy Supply Senior Vice President, the Nuclear Operations Vice President will report directly to the President and Chief Executive Officer.
w (3) The Quality Assurance Manager will report (dashed line function) to the Vice President, Nuclear Operations during the absence of the Energy Supply Senior Vice President.
Figure 6.2-1 Management Organization Chart
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