ML20134D079
| ML20134D079 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 08/09/1985 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Power Authority of the State of New York |
| Shared Package | |
| ML20134D082 | List: |
| References | |
| DPR-59-A-094 NUDOCS 8508190056 | |
| Download: ML20134D079 (7) | |
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UNITED STATES
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WASHINGTON, D. C. 20555
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4 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. 94 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 February 22, 1985, 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, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) 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 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 y
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission'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 licente amendment and paragraph 2.C(2) of Facility Operating License No.
DPR-59 is hereby amended to read as follows:
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1 2_
4 (2) Technical Specifications The Technical Specifications contained in Appendices A-and B, as revised through Amendment No. 94, are hereby incot:0 rated in the license..The licensee shall operate the facility in accordance with the Technical Specifications.
2 3.
This license amendment is effective as of the date of its issuance.
FOR THE NVCLEAR REGULATORY COMMISSION 9cuii O..i Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: August 9,1985 g,
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ATTACHMENT TO LICENSE AMENDMENT NO. 94 FACILITY OPERATING LICENSE NO. DPR-59 DOCKET NO. 50-333 s
l Revise the Appendix "A" Technical Specifications as follows:
Remove Insert 249 249 i
250 250 1
251 251 252a 252a i
The revised areas are identified by vertical. lines.
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j (B) Alternates Alternative members shall be appointed in writing by the PORC Chairman to serve on a temporary basis; however, no more than two alternates shall participate in PORC activities at any one time.
(C) Meeting Frequency Beetings will be called by the Chairman as the occasions for review or investigation arise. Meetings will be no less i
frequent than once a month.
I j.
(D) Quorum
_ The_ Chairman or Vice Chairman and four members, including
_. designated alternates, shall constitute a quorum.
(E) Responsibilities i
1.
Review plant procedures, and changes thereto, required by Specification 6.8.
2.
Review proposed tests and experiments that affect nuclear 1
l safety.
j i
3.
Review proposed changes to the Operating License and j
Technical Specifications.
4.
Review proposed changes or modifications to plant systems or equipment that sffect nuclear safety.
5.
Investigate violations of the Technical Specifications and prepare and forward a report covering evaluation and recommendations to prevent recurrence to the Resident Manager, who will forward the report to the Manager -
Nuclear Operations and to the chairman of the safety Review Committee.
1 6.
Review plant operations to detect potential safety hazards.
7.
Review the Security plan (including the Safeguards Contingency plan) and implementing procedures annually.
249 Amendment No. J U [, 94 l
8.
Review the Emergency Plan and implemsnting procedures annually.
9.
Perform special review and/or investigations at the request of the Resident Manager.
10.
Review of those reportable occurrences requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the NRC, in accordance with Specification 6.9.
11.
Review the Offsite Dose Calculation Manual (ODCM) an implementing procedures at least once per 24 months. -
12.
Review the Process Control Program (PCP) at least once per 24 months.
(F)
Authority The PORC shall function to advise the Resident Manager on all matters related to nuclear safety and environmental operations.
The PORC shall recommend approval or disapproval to the Resident Manager of those items considered in 6.5 IE (1) through (4 ) and determine if items considered in 6.5 IE (1) through (5) constitute unreviewed safety questions, as defined in 10 CFR 50.59.
in the event of a disagreement between the PORC and the Resident Manager, the Chairman of the SRC and the ~ Executive Vice President-Nuclear Generation or their designated alternatives, shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and written notification provided on the next business day; however, the Resident Manager shall have responsibility for resolution of such disagreement pursuant to Section 6.1.
(G)
Records Minutes of all meetings of the PORC shall be recorded and numbered.
Copies will be retained in file.
Copies will be forwarded to the Chairman of the SRC and the Executive Vice President-Nuclear Generation.
(H)
P ro'ce db'res Conduct of the PORC and the mechanism for implementation of its responsibilities and authority are defined in the pertinent Administrative Procedures.
6.5.2 SAFETY REVIEW COMNITTEE (SEC)
FUNCTION 6.5.2.1 The SEC shall function to provide indeper. dent review and audit of designated activities in the areas of:
a.
Nuclear power plant operations
~ ].
b.
Nuclear engineering c.
Chentstry and radiocheatstry d.
Metallurgy j
e.
Instrumentation and control Amendment No. J, J4', M 94 250
- f. Radiological safety
- g. Mechanical engineering
- h. Electrical engineering
- 1. Administrative controls and quality assurance practices J. Environment s
- k. Civil / Structural Engineering
- 1. Nuclear Licensing
- m. Emergency Planning
- n. Other appropriate fields associated with the unique characteristics of a nuclear power plant MEMBERSHIP 6.5.2.2 The SRC shall be composed 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; 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.
MEETINC FREQUENCY 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. jHf", fg!(, fgf, 7% 94 251
c.
The results of octions taken to correct d2ficiencion occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months.
d.
The performance of activities required by the operational Quality Assurance Program to meet the criteria of Appendix
- B", 10 CFR 50, at least once per 24 months, s
The Facility Emergency Plan and implementing e.
procedures at lease once per 12 montes.
f.
The Facility Security Plan (including the Safeguards Contingency Plan) and implementing procedures at least once per 12 months.
1 g.
Any other area of facility operation considered I
appropriate by the SRC or the Executive Vice President-Nuclear Generation.
h.
The Facility Fire Protection Program and implementing procedures at least once per two years.
1.
An independent fire protection and loss of prevention inspection and audit shall be performed annually utilizing either qualified offsite licensee personnel or an outside fire i
protection firm.
An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years.
k The Radiological Environmental. Monitoring Program and the results thereof at least once per 12 months.
1.
The offsite pose calculation Manual and implementing procedures at least once per 24
- months, The Process Control Program and implementing m.
procedures for processing and packaging of radioactive wastes at least once per 24 months.
The performance of activities required by the n.
i Quality Assurance Program to meet the provisions I
of Regulatory Guide.l.21, Revision 1, June 1974 and Regulatory Guide 4.1, Revision 1,sApril 1975 at least once per 12 months.
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AUTHORITY 6.5.2.9 The SEC shall report to and advise the Executive Vice president-Nuclear Generatlos on those areas of responsibility specified la i
section 6.5.2.7 and 6.5.2.8 Amendment No.,MT, f(f, g, J4.,W, 252a 94
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