ML20211H888
| ML20211H888 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 06/20/1986 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Power Authority of the State of New York |
| Shared Package | |
| ML20211H891 | List: |
| References | |
| DPR-59-A-099 NUDOCS 8606260109 | |
| Download: ML20211H888 (4) | |
Text
o UNITED STATES 8
~g NUCLEAR REGULATORY COMMISSION o
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WASHINGTON, D. C. 20555
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POWER AUTHORITY OF THE STATE OF NEW YORK DOCKET NO. 50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 99 License No. DPR-59 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Power Authority of the State of New York (the licensee) dated October 1, 1985, 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 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 soplicable requirements have been satisfied.
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-59 is hereby amended to read as follows:
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. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 99, 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.
F R THE NUCLEAR REGULATORY C0 SION Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing 4
Attachment:
Changes to the Technical Specifications Date of Issuance: June 20, 1986 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 99 FACILITY OPERATING LICENSE NO. DPR-59 i
DOCKET NO. 50-333 l
Replace the following page of the Appendix A Technical Specifications with the enclosed page.
The revised area is indicated by margin line.
fa21 248 i
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ig 6.
In addition to items 1, 2 & 3 above, two additional operators shall be readily available on site whenever the reactor is in other than
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cold shutdown. During cold shutdown, an additional operator shall be
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readily available on site.
7.
An individual qualified in radiation protection procedures shall be 1
on site when fuel is in the reactor.
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8.
In the event of illness or absenteeism up to two (2) hours is allowed
.j to restore the shif t crew or fire brigade to notiaal complement.
9.
A Fire Brigade of five (5) or more members shall be maintained on
.j site at all times.
This excludes two (2) members of the minimum shift crew necessary for safe shutdown and any personnel required for 1
other essential functions during a fire emergency.
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- 10. A Shift Technical Advisor shall be on site and readily available to j
the control room except during the cold shutdown or refuel mode, j
j 6.3 PLANT STAFF OUALIFICATIONS l
i The minimum qualifications with regard to educational background and j
experience for plant staff positions shown in Fig. 6.2-1 shall meet or
,1 exceed the minimum qualifications of ANSI NI8.1-1971 for comparable
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positions; except for the Radiation and Environmental Services b
Superintendent who shall meet or exceed the qualifications of Regulatory
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Guide 1.8, September 1975 and the Shift Technical Advisor who shall have 7,,{
a bachelor's degree or equivalent in a scientific or engineering 4
discipline with specific training in plant design, and response and Y
analysis of the plant for transients and accidents. Any deviations will be justified to the NRC prior to an individual's filling of one of these positions.
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6.4 RETRAINING AND REPLACEMENT TRAINING A training program shall be maintained under the direction of the
!g Training Coordinator to assure overall proficiency of the plant staff if organization.
It shall consist of both retraining and replacement O
training and shall meet or exceed the minimum requirements of Section 5.5 j
of ANSI NI8.1-1971.
The escraining program shall not exceed periods two years in length with a curriculum designed to meet or exceed the requalification requirements
,d of 10 CFR 55, Appendix A.
In addition fire brigade training shall meet
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or exceed the requirements of NFPA 27-1975, except for Fire Brigade
- /j training sessions which shall be held at least quarterly. The effective date for implementation of fire brigade training is March 17, 1978.
J 6.5 REVIEW AND AUDIT Two separate groups for plant operations have been constituted. One of these, the Plant Operating Review Committee (PORC), is an onsite review group. The other is an independent review and audit group, the offsite Safety Review Committee (SRC).
Amendment No. p, 34,.'y( 99 248 i
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