ML20071J168
| ML20071J168 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/05/1982 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Arkansas Power & Light Co |
| Shared Package | |
| ML20071J172 | List: |
| References | |
| DPR-51-A-064 NUDOCS 8204260406 | |
| Download: ML20071J168 (9) | |
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UNITED STATES y
NUCLEAR REGULATORY COMMISSION g.,
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ARKANSAS POWER & LIGHT COMPANY DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE - UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendnent No. 64 License No. DPR-51 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Arkansas Power and Light Company (the licensee) dated October 8,1981, 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 confomity with the application, the provisions of the Act, and the rules and regulations of the Comissi,on; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without enda.ngering 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 comon 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 Comission's regulations and all applicable requirements t ye been satisfied.
820426O M
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. DPR-51 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 64, 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 the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION n
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John ~F.<Stolz, Chief
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Operating Reactors Branch #4
\\<._ Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: April 5,1982
ATTACHMENT TO LICENSE AMENDMENT NO. 64 FACILITY OPERATING LICENSE NO. DPR-51 DOCKET NO. 50-313 i
Replace the following pages of the Appendices "A" and "B" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Appendix A 117 119 120 121 129 Appendix B 5-9 s
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6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The General Manager shall be responsible for overall facil'ity operation and shall delegate in writing the succession to this responsibility during his absence.
6.2 ORGANIZATION 0FFSITE 6.2.1 The offsite organization for facility management and technical support shall be as shown on Figure 6.2.-l.
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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 minimum shift crew composition shown in Table 6.2.-l.
6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the i
minimum qualifications of ANSI N18.1-1971 for comparable l
position, except for (1) the Health Physics Superintendent who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975 and (2) the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.
6.4 TRAINING 6.4.1 A retraining and replacement trairiing 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 prcgram for fire protection training shall be l
maintained and 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.
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 General Manager on all matters related to nuclear safety.
COMPOSITION j
6.5.1.2 The Plant Safety Committee shall be composed of the:
i (See Page 121)
Amendment No. 15,30,34,37
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- LSO-SENIOR OPERATOR LICENSE REQUIRED czm LO - OPERATOR LICENSE REQUIRED 4
- 0NSITE RESPONSIBILITY IVR FIRE PROTECTION PROGRAM z
(1) 'Ihe Hec.lth Physics Superintendent reports to the Manager, Engineering and Technical Support in ad:ainistrative matters and routine health physics concerns and he reports to the General Manager in mat ters of radiological health, safety and policy.
w7 (2)
'lhe llealth Physics Superintendent has direct interface with the Corporate Health Physicist in matters of radiological health and safety. The Corporate llcalth Physicist reports to the Manager,
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Nuclear Services. lie will help formulate Corporate llealth I'hysics Policy and ensure that it is properly lioplemented, cn a
FIGURE 6.2-2 FUNCTIONAL ORGANIZATION FOR PLANT OPERATION
Chairman: Manager of Special Projects Member:
Operations Manager Member:
Maintenance Manager Member:
Engineering and Technical Support Manager Member:
Administrative Manager Member:
Technical Analysis Superintendent Member:
Plant Analysis Superintendent Member:
Plant Engineering Superintendent Member:
Health Physics Superintendent The General Manager shall designate in writing the Alternate Chairman in the absence of the Chairman.
ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the PSC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PSC i
activities at any one time.
'l MEETING FREQUENCY 6.5.1.4 The PSC shall meet at least once per calendar month and as convened by the PSC Chairman or his designated alternate.
QUORUM
- 6. 5.1. 5 The minimum quorum of the PSC 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 four 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 revisions thereto, 2) any other proposed procedures or revisions thereto as determined by the General Mcnager to affect nuclear safety.
b.
Review of all proposed tests and experiments that affect nuclear safety, c.
Review o'f all proposed changes to the Appendix "A" Tech-nical Specifications.
d.
Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.
e.
Investigation of all violations of the Technical Specifi-cations, including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the General Manager.
f.
Review of those Reportable Occurrences requiring 24-hour notification of the Commission.
Amendment No. 28,34,37, 121 47, 64
h.
Records of in-service insp;ctions p;rformed pursuint to th se Technical Specifications.
i.
Records of Quality Assurance activities required by Section 17 of the Quality Assurance Manual for Operations.
j.
Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
k.
Records of meetings of the PSC and the SRC.
1.
Records for Environmental Qualification which are covered under the provisions of paragraph 6.13.
6.10 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consis-tent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations, involving personnel radia-tion exposure.
6.11 HIGH RADIATION AREA 6.11.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area (as defined in 20.202(b)(3) of 10 CFR 20) in which the intensity of radiation is 1000 mrem /hr or less shall be barricaded and conspicuously posted as a high radiation area and shall be controlled by requiring the issuance of a radiation work permit. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
a.
A radiation monitoring device which continuously indicates the radiation dose rate in the area.
b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a Dre-set integrated dose is received.
Entry into such arets with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made know-ledgeable of them.
c.
An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified in the radiation work permit.
6.11.2 The requirements of 6.11.1 above, shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 mrem /hr.
In addition, locked doors shall be provided to prevent unauth-orized entry into such areas and access to these areas shall be main-tained under the administrative control of the Shift Supervisor on duty l
and/or the Health Physics Superintendent.
I Amendment No. 16, 24, 9/dd/
- 129-(Next page is 140) did 9tfdW4/ 24,1988, EA,64
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ARKANSAS NUCLEAR ONE ORGANIZATION CHART 5-1 5-9 AMENDMENT NO. 31, ff, f7, 58,64
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