ML20211H949
| ML20211H949 | |
| 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 | |
| ML20211H953 | List: |
| References | |
| DPR-59-A-100 NUDOCS 8606260132 | |
| Download: ML20211H949 (5) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION s
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- j WASHINGTON, D C. 20555
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POWER AUTHORITY OF THE STATE OF flew YORK DOCKET NO. 50-333 i
JAMES A. FITZPATRICK NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 100 License No. DPR-59 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the Power Authority of the State of New York (the licensee) dated January 21, 1986 complies with the standards and requirements of the Atomic Energy Act of 1954, I
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
'l Commission; b
C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangerir.g 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 common j
defense and security or to the health and safety of the public; and e
E.
The issuance of this amendment is in accordance with 10 CF9 Part 51 of the Commission's regulations and all applicable 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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. s (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
100, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMTJ ION w
Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: June 20, 1986 m
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ATTACHME.iT TO LICENSE AMENDMENT N0.100 s
FACILITY OPERATING LICENSE NO. DPR-59 DOCKET NO. 50-333 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
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f.
Rndiolcgical safety g.
Mechnnical cnginscring h.
Electrical engineering
- i. Administrative controls and quality assurance practices J.
Environment k.
Civil / Structural Engineering 1.
Nuclear Licensing a.
Emergency Planning Other appropriate fields associated with the unique characteristics n.
of a nuclear power plant MEMBERSHIP 6.5.2.2 The SRC shall be craposed of the following voting members:
Chairman:
Manager-Nuclear Safety Evaluation Vice-Chairman: Director-Quality Assurance Member:
Vice President Nuclear Support-BWR Member:
Vice President Nuclear Support-PWR Member:
Vice President-Generic Nuclear Support Member:
Vice President-Design and Analysis Member:
Resident Manager-IP3 Member:
Resident Manager-JAF Member:
Consultant ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the SRC chairman. An Alternate Vice-Chairman shall be appointed in writing by the Executive Vice President - Nuclear Generation if necessary.
However, no more than two alternates shall participate as voting members in SRC activities at any one time.
CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the SRC Chairman to provide expert advice to the SRC.
MEETING FREOUENCY 6.5.2.5 The SRC shall meet at least once per calendar quarter during the initial year of facility. operation following initial fuel loading and at least once per six months, thereafter.
Amendment No. %, pd, ps, /, %,100 251 t
OUORUM 6.5.2.6 A quorum of SRC shall consist of the Chairman, Vico-Chairmsn or Alternate Vice-Chairman and four members, including alternates. No more than a minority of the quorum shall have a direct line responsibility for the operation of the plant.
REVIEW 6.5.2.7 The SRC shall review:
- a. The safety evaluation for 1) changes to procedures, equipment or systems and 2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.
- b. Proposed' changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
- c. Proposed tests or experiments which involve an unreviewed safety question as, defined in Section 50.59, 10 CFR.
- d. Proposed changes to Technical Specifications of this Operating License.
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- e. Violations of code, regulations, orders. Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.
- f. Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety.
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- g. Events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the commission.
- h. All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety related structures, systems or components.
- i. Reports and meetings minutes of the Plant Operating Review Committee.
6.5.2.8 Audits of facility activities shall be performed under the cognizance of the SRC. These audits shall encompass:
- a. The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.
- b. The performance, training and qualifications of the entire facility staff at least once per 12 months.
1 AmendmentNo.[.p6,/,100 252 i
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