ML20077S554
| ML20077S554 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 01/18/1995 |
| From: | Michael Case Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20077S557 | List: |
| References | |
| NUDOCS 9501240143 | |
| Download: ML20077S554 (10) | |
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UNITED STATES
'y NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 20666 4 001
%, *..
- f 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. 222 License No. DPR-59 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
TV application for amendment by Power Authority of the State of New York (the licensee) dated June 17, 1994, as supplemented December 2, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulatiors set forth in 10 CFR Chapter I; 8.
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 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:
9501240143 950118 DR ADOCK 05000333 PDR
(2) Technical Snecifications The Technical Specifications contained in Appendices A and B, as i
revised through Amendment No. 222, 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 to be implemented within 90 days.
FOR THE NUCLEAR REGULATORY COMMISSION f e.Y Mic.el J.
ase, Acting Director Prsject Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: January 18, 1995 i
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ATTACHMENT TO LICENSE AMENDMENT N0.222 FACILITY OPERATING LICENSE NO. DPR-59 DOCKET NO. 50-333 Revise Appendix A as follows:
Remove Paaes Insert Paaes 248 248 248a 248a 249 249 250 250 252a 252a 253 253 254-a 254a e
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'JAFNPP 6.3 PLANT STAFF QUALIFICATIONS 6.3.1 The minimum qualifications with regard to educational background and experience for plant staff positions shown in FSAR Figure 13.2-7 shall meet or exceed the minimum
- qualifications of ANSI N18.1 1971 for comparable positions; except for thc Radiological -
and Environmental Services Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.
6.3.2 The Shift Technical Advisor (STA) shall meet or exceed the minimum requirements of either Option 1 (Combined SRO/STA Position) or Option 2 (Continued use of STA Position), as defined in the Commission Policy Statement on Engineering Expertise on Shift, published in the October 28,1985 Federal Register (50 FR 43621). When Invoking Option 1; the STA role may be filled by the Shift Supervisor or Assistant Shift Supervisor. (1) 6.3.3 Any deviations will be justified to the NRC prior to an individual's filling of one of these positions.
NOTE:
(1)
The 13 individuals who hold SRO licenses, and have completed the FitzPatrick Advanced Technical Training Program prior to the issuance of License Amendmer)t 111, shall be considered qualified as dual-role SRO/ STAS.
6.4 RETRAINING AND REPLACEMENT TRAINING A training program shall be maintained under the direction of the Training Manager to assure overall proficiency of the plant staff organization. It shall consist of both retraining and replacement training and shall meet or exceed the minimum requirements of Section 5.5 of ANSI N18.1-1971.
The retraining program shall not exceed periods two years in length with a curriculum designed to meet or exceed the requalification requirements of 10 CFR 55.59.
6.5 REVIEW AND AUDIT Review requirements are accomplished by using designated technical reviewers / qualified safety reviewer and two separate review committees. The Plant Operating Review Committee (PORC) is an onsite review group; the Safety Review i
Committee (SRC) is an independent offsite review and audit group.
6.5.0 BEVIEW AND APPROVAL OF PROGRAMS AND PROCEDURES 6.5.0.1 The procedure review and approval process shall be controlled and implemented by administrative procedure (s).
6.5.0.2 Each program and procedure required by Specification 6.8 and other procedures that affect nuclear safety, and changes thereto, shall be reviewed by a minimum of two designated technical reviewers who are knowledgeable in the affected functional area.
Amendment No. 22, 34, 57, 00, 111, 134, 137, 178, 100, 218, 222 248 t
JAFNPP 6.5.0.3 Designated technical reviewer (s) shall meet or exceed the qualifications described in Section 4 of ANSI N18.1-1971 for applicable positions, with the exclusion of the positions identified in Sections 4.3.2 and 4.5. Individuals whose positions are described in Sections 4.3.2 and 4.5 may qualify as designated technical reviewers provided they meet the qualifications described in other portions of Section 4.
6.5.0.4 The designated technical reviewer shall determine the need for cross-disciplinary reviews. Individuals performing cross-disciplinary reviews shall meet or exceed the qualifications described in Section 4 of ANSI N18.1-1971 for applicable positions.
6.5.0.5 Each program and procedure required by Specification 6.8 and other procedures that affect nuclear safety, and changes thereto, shall be reviewed from a safety perspective by a qualified safety reviewer. Safety and/or environmental Impact evaluations, when required, shall be reviewed by PORC per Specification 6.5.1.6.a.
6.5.0.6 Nuclear safety related procedures and procedure changes shall be reviewed and approved, prior to implementation, by the appropriate member (s) of management.
6.5.1 PLANT OPERATING REVIEW COMMITTEE (PORC) 6.5.1.1 Function PORC shall function to advise the Resident Manager on matters related to nuclear safety and environmental impact.
6.5.1.2 Membership The Plant Operating Review Committee shall be composed of the:
Chairman:
General Manager - Operations Vice-Chairman / Member:
General Manager - Support Services Vice-Chairman / Member:
General Manager - Maintenance Member:
Operations Manager Member:
Maintenance Manager.
Member:
Technical Services Manager Member:
Instrument and Controls Manager Member:
Radiological and Environmental Services Manager Member:
Site Engineering Manager Member:
Reactor Analyst Supervisor Special consultants to provide expert advice may be utilized when the nature of a particular problem dictates.
Amendment No. 04,57.178,222 248a 6
JAFNPP 6.5.1.3 Altemates l
Altemative members shall be appointed in writing by the PORC Chairman to serve on a temporary basis.
l 6.5.1.4 Meeting Frequency l
Meetings will be called by the Chairman as the occasions for review or investigation arise. Meetings will be no less frequent than once a month.
6.5.1.5 Ouorum l
A quorum of the PORC shall consist of the Chairman or one of two Vice-Chairmen and five members including designated attemates. Vice-Chairmen may act as members when not acting as Chairman. A quorum shall contain no more than two attemates.
l 6.5.1.6 Responsibilities The PORC shall be responsible for the:
a.
Review of 10 CFR 50.59 safety and environmental impact evaluations associated with procedures and programs required by Specification 6.8, and changes thereto.
b.
Review of proposed tests and experiments that affect nuclear safety.
c.
Review of proposed changes to the Operating License and Technical Specifications.
d.
Review of proposed changes or modifications to plant systems or equipment that affect nuclear safety.
e.
Investigation of violations of the Technical Specifications. The PORC shall prepare and present a report covering the evaluations and recommendations to prevent recurrence to the Resident Manager, who will then forward the report to the Executive Vice President and Chief Nuclear Officer, the Vice President Regulatory Affairs and Special Projects, and to the Chairman of the Safety Review Committee.
f.
Review of plant operations to detect potential safety hazards.
g.
Performance of special reviews and/or investigations at the request of the Resident Manager.
h.
Review of all reportable events.
i.
Review of the Process Control Program and the Offsite Dose Calculation Manual (ODCM) and changes thereto.
J.
Review the FitzPatrick Fire Protection Program and implementing procedures and changes thereto.
Amendment No. 22, 57, 9','78, 218, 220, 222 249
)
JAFNPP 6.5.1.7 Authority The PORC shall:
a.
Recommend to the Resident Manager, approval or disapproval of those items reviewed under Specificatioits 6.5.1.6.a through 6.5.1.6.d.
b.
Render determinations with regard to whether or not items considered under Specification 6.5.1.6.a through 6.5.1.6.e constitute an Unreviewed Safety Question as defined in 10 CFR 50.59.
c.
In the event of a disagreement between the PORC and Resident Manager, notify the Executive Vice President and Chief Nuclear Officer and the SRC Chairman, or their designated altemates, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and provide written notification by the next business day. The Resident Manager shall have responsibility for resolution of such disagreement pursuant to Section 6.1.
6.5.1.8 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 and Chief Nuclear Officer.
6.5.1.9 Procedures l
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 COMMITTEE (SRC)
FUNCTION 6.5.2.1 The SRC shall function to provide independent review and audit of designated activities in the areas of:
a.
Nuclear power plant operations b.
Nuclear engineering c.
Chemistry and radischemistry d.
Metallurgy e.
Instrumentation and control Amendment No. 50,78,93,9',110, 218, 220,222 250
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JAFNPP l
- c. The results of actions taken to correct deficiencies 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.
- e. Any other area of facility operation considered appropriate by the SRC or the Executive Vice President and Chief Nuclear Officer.-
f.
The Facility Fire Protection Program and implementing procedures at least once per two years.
- g. 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 protection firm.
- h. An inspection and audit of the fire protection and loss prevention program shall be l
performed by an outside qualified fire consultant at intervals no greated than 3 years.
1.
The Radiological Environmental Monitoring Program and the results thereof at least l
once per 12 months.
J. The Offsite Dose Calculation Manual and implementing procedures at least once per l
24 months.
- k. The Process Control Program and implementing procedures for processing and l
l packaging of radioactive wastes at least once per 24 months.
1.
The performance of activities required by the Quality Assurance Program to meet the l
provisions of Regulatory Guide 1.21, Revision 1, June 1974 and Regulatory Guide i
4.1, Revision 1, April 1975 at least once per 12 months.
AUTHORITY
-6.5.2.10 The SRC shall advise the Executive Vice President and Chief Nuclear Officer on those areas of responsibility specified in Section 6.5.2.8 and 6.5.2.9.
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Amendment S0, 00, 05, 78, 03, 04, 220, 222 252a
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JAFNPP 6.6 BEPORTABLE EVENT ACTION The following actions shall be taken for Reportable Events:
(A)
The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and (B)
Each Reportable Event shall be reviewed by the PORC, and the results of this review shall be submitted to the Executive Vice President and Chief Nuclear Officar, the Vice President Regulatory Affairs and Special Projects, and the Chairman of the SRC.
6.7 SAFETY LIMIT VIOLATION (A)
If a safety limit is exceeded, the reactor shall be shut down and reactor operation shall only be resumed in accordance with the provisions of 10 CFR 50.36, (c) (i).
(B)
An immediate report of each safety limit violation shall be made to the NRC by the Resident Manager. The Executive Vice President and Chief Nuclear Officer, the Vice President Regulatory Affairs and Special Projects, and the Chairman of the SRC will be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
(C)
The PORC shall prepare a complete investigative report of each safe'.y limit violation and include appropriate analysis and evaluation of: (I) applicable '
circumstances preceding the occurrence, (2) effects of the occurrence upon facility component systems or structures and (3) corrective action required to prevent recurrence. The Resident Manager shall forward this report to the Executive Vice President and Chief Nuclear Officer, the Vice President Regulatory Affairs and Special Projects, the Chairman of the SRC, and the NRC.
6.8 PROCEDURES (A)
Written procedures and administrative policies shall be established, implemented, and maintained that:
1.
meet or exceed the requirements and recommendations of Section 5 of ANSI 18.7-1972 " Facility Administrative Policies and Procedures."
2.
are recommended in Appendix A of Regulatory Guide 1.33, November 1972.
3.
implement the Fire Protection Program.
4.
include programs specified in Appendix B of the Radiological Effluent Technical Specifications, Saction 7.2.
(B)
Each procedure of Specification 6.8.(A), and changes thereto, shall be approved prior to implementation by the appropriate responsible member of management as specified in Specification 6.5.0.
Amendment No. 50, SO, SS, 78, 03, ' 10, 220, 222 253
JAFNPP (C) Temporary changes to the procedures required by Specification 6.8 (A) may be made provided:
1.
the intent of the original procedure is not altered.
2.
the change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's license.
3.
the change is documented, reviewed and approved by the appropriate member of plant management as required by Specification 6.5.0 within 14 days of implementation.
6.9 REPORTING REQUjREMENTS (A) ROUTINE REPORTS The following reports shall be submitted in accordance with 10 CFR 50 unless otherwise noted.
1.
STARTUP REPORT a.
A summary report of plant startup and power escalation testing shall be submitted following (1) amendment to the license involving a planned increase in power level, (2) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (3) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant. The Startup Report for the initial fuel cycle shall address each of the tests identified in the FSAR and shallinclude a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report. Startup Reports for subsequent fuel cycles shall address startup tests that are necessary to demonstrate the acceptability of changes and modifications.
Amendment No. 7, 22, 32,'10, 212,222 254a