ML20059F197
| ML20059F197 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 01/03/1994 |
| From: | Black S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059F201 | List: |
| References | |
| NUDOCS 9401130194 | |
| Download: ML20059F197 (5) | |
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NUCLEAR REGULATORY COMMISSION
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WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482 AMENDMENT TO FACILIT) OPERATING LICENSE Amendment No. 70 License No. NPF-42
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Wolf Creek Generating Station (the facility) Facility Operating License No. NPF-42 filed by the Wolf Creek Nuclear Operating Corporation (the Corporation), dated October 21, 1993, 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, as amended, 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 ruch activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this license amenJment 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.
9401130194 940103 PDR ADOCK 0500 2
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Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-42 is hereby amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 70, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license. The Corporation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The license amendment is effective as of its date of issuance and is to be implemented within 30 days of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Suzanne. Black, Director Project Directorate IV-2~
Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: January 3,1994 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 70 FACILITY OPERATING LICENSE NO. NPF-42 DOCKET NO. 50-482 Revise Appendix A Technical Specifications by removing the page identified below and inserting the enclosed page.
The revised page is identified by amendment number and contains marginal lines indicating the area of change.
The corresponding overleaf page is also provided to maintain document completeness.
REMOVE INSERT 6-7 6-7 i
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t ADMINISTRATIVE CONTROLS 6.3 UNIT STAFF OVALIFICATIONS (Continued) b.
The position of Radiation Protection Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, c.
The NSRC members shall meet or exceed the requirements of ANSI /ANS 3.1-1981.
d.
The position of Manager Operations shall hold or have previously held a senior reactor operator license for a similar unit (PWR).
6.4 TRAINING t
6.4.1 A retraining and replacement training program for the unit staff shall' be maintained under the direction of the Manager Training and shall meet or exceed the requirements and recommendations of Section 5 of ANSI /ANS 3.1-1978 with the following exceptions:
a.
The training program for Licensed Operators and Senior Operators shall meet or exceed the requirements and recommendations of Section 5 of ANSI /ANS 3.1-1981 as endorsed by Regulatory Guide 1.8, Revision 2, and 10 CFR Part 55.
b.
Training shall include familiarization with relevant industry operational experience identified by the ISEG or another plant group.
6.5 REVIEW AND AUDIT 6.5.1 PLANT SAFETY REVIEW COMMITTEE (PSRC)
FUNCTION 6.5.1.1 The PSRC shall function to advise the Vice President Plant Operations on all matters related to nuclear safety.
COMPOSITION 6.5.1.2 The Vice President Plant Operations shall designate in writing the Chairman and Alternate Chairman of the PSRC.
PSRC membership shall include between six and eight additional members appointed by the Chairman and an additional member appointed by the Vice President Engineering.
Selected members shall include, at a minimum, management responsible for the following areas of expertise:
operations, maintenance, instrumentation and controls, chemistry, health physics and engineering.
A single individual may cover multiple disciplines.
ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the PSRC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PSRC activities at any one time.**
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- Except for the alternate for Engineering who is appointed by the Vice President Engineering.
WOLF CREEK - UNIT 1 6-7 Amendment No. 20,25,45,51,55,58,70
ADMINISTRATIVE CONTROLS 4
MEETING FRE0VENCY 6.5.1.4 The PSRC shall meet at least once per calendar month and as convened by the PSRC Chairman or his designated alternate.
DUORUM 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 his designated alternate and four members including alternates.
RESPONSIBILITIES 6.5.1.6 The PSRC shall be responsible for:
a.
Review of: (1) all procedures required by Specification 6.8 and changes thereto, (2) all programs required by Specification 6.8 and changes thereto, and (3) any other proposed procedures or changes thereto as determined by the Vice President Plant Operations to affect nuclear safety; b.
Review of all proposed changes, tests and experiments which may involve an unreviewed safety question as defined in Section 50.59, 19 TFR; c.
Review of all proposed changes to Technical Specifications or the Operating License; d.
Review of all safety evaluations performed under the provision of Section 50.59(a)(1), 10 CFR, for changes, tests and experiments; e.
Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Vice President Plant Operations, and to the Nuclear Safety Review Committee (NSRC);
f.
Review of all REPORTABLE EVENTS; g.
Review of reports of operating abnormalities, deviations from expected performance of plant equipment and of unanticipated deficiencies in the design or operation of structures,. systems or components that affect nuclear safety; h.
Performance of special reviews, investigations or analyses and reports thereon as requested by the Chairman, NSRC; i.
Review of the plant Security Plan and implementing procedures and shall submit recommended changes to the NSRC; j.
Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the NSRC; WOLF CREEK UNIT 1 6-8 Amendment No. 4,457 58
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