ML19209B203
| ML19209B203 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 10/02/1979 |
| From: | Early P POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML19209B192 | List: |
| References | |
| NUDOCS 7910090320 | |
| Download: ML19209B203 (11) | |
Text
BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION In the Matter of
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POWER AUTHORITY OF THE STATE OF NEW YORK
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Docket No. 50-333
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James A. FitzPatrick Nuclear Power Plant
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APPLICATION FOR AMENDMENT TO OPERATING LICENSE Pursuant to Section 50.90 of the regulations of the Nuclear Regulatory Commission (NRC), the Power Authority of the State of New York, as holder of Facility Operating License No. DPR-59, hereby applies for an Amendment to the Technical Specifications contained in Appendix A and B of this license.
The proposed changes to the James A. FitzPatrick Technical Specifications seek to simplify the management organizatio-charts and to correct the titles of certain positions which appear in Section 6 of Appendix A and Section 5 of Appendix B, to those currently being used by the Authority and to modify the reporting requirements of the Resident Managers.
The proposed changes to the Technical Specifications are presented in Attachment I to this Application.
The proposed changes to the Environmental Technical Specification are presented in Attachment II to this Application.
The Safety Evaluation is included in Attachment III.
POWER AUTHORITY OF THE STATE OF JEWfYOR' By bb-,
Paul A. Early AssiptantChjefEngineer-Projects Subscribed and Sworn to before gdayof Ctha, 1979 me this
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e ATTACHMENT I PROPOSED TECHNICAL SPECIFICATIONS CHANGES RELATED TO MANAGEMENT TITLE CHANGES (APPENDIX A)
POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A.
FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 SEPTEMBER 28, 1979 3 7
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6.0 3DMINISTRATIVE CONTROLS Administrative Controls are the means by which plant opera-tw' ns are subject to management control.
Measures specified in this section provide for the assignment of responsibilities, plant organization, staffing qualifications and related re-quirements, review and audit mechanisms, procedural controls and reporting requirements.
Each of these measures are neces-sary to ensure safe and efficient facility operation.
6.1 RESPONSIBILITY The Resident Manager is responsible for safe operation of the plant.
During periods when the Resident Manager is un-available, the Superintendent of Power will assume his respon-sibilities.
In the event both are unavailable, the Resident Manager may delegate this responsibility to other qualified supervisory personnel.
The Resident Manager reports directly to the Executive V.
P.
and Director of Power Operations for l
administrative matters and functionally to the Manager -
Nuclear Operations for operationEl related matters, as shown in Fig.
6.1-1.
6.2 PLANT STAFF ORGANIZATION The plant staff organization is shown graphically in Fig.
6.2-1 and functions as follows:
1.
A licencad senior reactor operator shall be on site at all times when there is fuel in the reactor.
2.
Il addition to item 1 above, a licensed reactor ope _ator shall be in the control room at all times when there is fuel in the reactor.
3.
In addition to items 1 & 2 above, a licensed reactor operator shall be readily available on rite whenever the reacto
' ' in other than cold condition.
4.
Two licensed reactor operators shall be in the con-trol room during start-ups and scheduled shutdowns.
5.
A licensed senior re~ actor operator shall be respon-sible for all movement of new and irradiated fuel within the site boundary.
A licensed reactor operator will be required to manipulate or directly supervise the manipulation of the controls of all fuel no'cing en- 'pment, except the reactor building crane.
All fuel movements by the reactor building crane, except new fuel movements from receipt through dry storage, shall be under the direct supervision of a licensed reactor operator.
All fuel movements within the core shall be directly monitored by a member of the reactor analyst group.
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n i pt i a Amendment No.
247
It is recognized that expertise of the SRC members col-lectively may not encompass all of the areas listed in ANSI 18.7-1972.
Therefore, special consultants to provide expert advice may be utilized when the nature of a particular problem dictates.
The Chairman shall be appointed by the President and Chief Operating Officer.
The Vice Chairman shall be appointed by the Chairman.
(B)
Alternates Alternates shall be appointed in writing by the Chairman.
No more than two alternates shall participate in SRC activities at any one time.
(C)
Meeting Frequency Meetings of the SRC will be called as the occasions for review arise.
Meetings will be held at least once per six months.
(D)
Quorum Chairman or Vice Chairman and two members, including designated alternates, shall consitute a quorum.
(E)
Responsibilities 1.
Review proposed changes and/or modifications to nrocedures, equipment or systems which may involve an unreviewed safety question as defined in 10 CFR 50.59 as identified to SRC by the Resident Manager or the headquarters' Technical Staff.
2.
Review proposed tests and experiments which involve an unreviewed safety question as defined in 10 CFR 50.59 as identified to SRC by the Resident Manager or the headquarters' fechnical Staf f.
3.
Review the safety evaluations for changes and/or modifications to procedures, equipment or systems completed under the provisions of 10 CFR 50.59 to verify that such actions did not constitute an unreviewed safety guestion.
4.
Review the safety evaluations for test and/or experiments conducted under the provisions of 10 CFR 50.59 to verify that such actions did not constitute an unreviewed safety question.
Amendment No.
251
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5.
Review proposed changes in the Operating License and Technical Specifications.
6.
Make or cause to be made periodic audits of plant operation to verify conformance with the facility operating license and other regulatory requirements.
7.
Review reports and minutes of PORC.
8.
Review violations of applicable statutes, codes, regulations, orders, Technical Specifications, license requirements or of internal procedures or instructions having nuclear safety significance.
9.
Review NRC inspection reports, reporatable occurrence submittals, and related correspondence.
10.
Review aspects of plant design and operation w ich may result in an unacceptable environmental effect.
11.
Review the Facility Fire Protection ProgrEnt and implementing procedures at least once per two years.
(F)
Audits The SRC shall provide an independent review and audit function of safety-related aspects of plant activities which shall encompass:
1.
The conformance of facility operation to all pro-visions contained within the Technical Specifications and applicable license requirements.
2.
The performance of the entire facility staff relative to nuclear safety.
3.
The results of all act'.ons taken to correct anomalies occurring in the facility, equipment, structures, systems or method of operations.
4.
The adequacy of the Quality Assurance Program to meet the criteria specified in 10 CFR 50, Appendix B.
5.
The Emergency Plan and implementing procedures.
6.
The Security Plan and implementing procedures.
7.
Any other area of facility operation cons 1 Cered l
appropriate by the SRC or the President.
(G)
Authority The Safety Review Committee shall be advisory to the President and Chief Operating Officer.
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Amendment No.
252
(H) Records Records will be maintained in accordance with ANSI 18.7-1972 and in accordance with the SRC Charter.
(I) Charter Conduct of the committee will be in accordance with a charter, approved by the President and Chief Operating Officer setting forth the mechanism for implementation of the committee's responsibilities and authority.
REPORTABLE OCCURRENCE ACTION (A) In the event of a Rcportable Occurrence, the NRC shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.
(B) Each Reportable Occurrence requiring 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />' notification to the NRC shall be reviewed timely by the PORC and a report submitted by the Reside.it Manager to the Manager-Nuclear Operations and the SRC.
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) (1) (1).
(B) An immediate report of each safety limit violation shall be made to the NRC by the Resident Manager.
The Manager-Nuclear Operations and 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 safety limit violation and include appropriata analysis and evaluations of:
(1) applicable circumstances preceding the occurrences, (2) effects of the occurrence upon facility components, system or structures and (3) corrective actic., required to prevent recurrence.
The Resident Manager shall for..ard this report to the Manager-Nuclear Operations, Chairman of the SRC and the NRC.
PROCT
'RES (A) Written procedures and administrative policies shall be established, implemented and maintained that meet or exceed the rec,uire-ments anc recommendations of Section 5 " Facility Administrative Policies and Procedures" of ANSI 18.7-1972 and Appendix A of Regulatory Guide 1.33, November 1972.
In addition, procedures shall be established implemented and maintained for the Fire Protection Program.
(B) Those procedures affecting nuclear safety shall be reviewed by PORC and approved by the Resident Manager prior to implementation.
(C) Temporary changes to nuclear safety related procedures may be made provided:
- 1. The intent of the original procedure is not altered.
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253
PRESIDENT &
CHIEF OPERATING y
0FFICER L'
E SAFETY REVIEW H
COMMITTEE 5
EXECUTIVE V.P.
EXECUTIVE V.P.
& CHIEF ENGINEER
& DIRECTOR OF l
POWER OPERATIONS l
l DIRECTOR OF SAFETY / SECURITY
- l MANAGER NUCLEAR OPERATIONS l
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- RESPONSIBLE FOR POWER AUTHORITY RESIDENT
__ __ _J DIRECTION OF FIRE PROTECTION PROGRAF 1 MANAGER
ADMINISTRATIVE FIGURE 6.1-1 POWER AUTHORITY OF THE STATE OF
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FUNCTIONAL NEW YORK
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JAMES A.
FITZPATRICK NUCLEAR POWER PLANT MANAGEMENT ORGANIZATION CHART
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ATTACHMENT II PROPOSED ENVIRONMENTAL TECHNICAL SPECIFICATION CHANGES MANAGEMENT TITLE CHANGES (APPENDIX B)
POWER AUTHORITY OF 'IJE G RATE OF NEW YORK JAMES A.
FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 SEPTEMBER 28 1979 1117
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PRESIDENT & CHIEF 3
pj OPERATING OFFICER 8
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SAFETY REVIEW COMMITTEE EXECUTIVE VICE PRESIDENT EXECUTIVE VICE PRESIDENT
& CHIEF ENGINEER
& DIRECTOR OF POWER OPERATIONS DIRECTOR OF iE ENVIRONMENTAL
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PROGRAMS STAFF L-:
FIGURE 3.2-2
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POWER AUTHORITY OF THE STATE OF NEW YORK
-4 f1ANA^EMENT ORGANIZATION ENVIRONf1 ENTAL CD
a ATTACHMENT III SAFETY EVALUATION RELATED TO MANAGEMENT TITLE CHANGES f
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POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A.
FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 SEPTEMBER 28, 1979 fi) f
Section I - Description of the Modification The position of General Manager and Chief Engineer has been retitled President and Chief Operating Officer.
The position of Assistant General Manager-Engineering has been retitled Executive Vice President and Chief Engineer.
The position of Director of Power Operations has been changed to Executive Vice President and Director of Power Operations.
The Resident Managers will now report administratively to the Executive Vice President and Director of Power Operations.
The functional relationship between the Resident Manager and the Manager-Nuclear Operations remains unchanged.
Section II - Purpose of Modification The purpose of this modification is ts comply with the require-raent of 10 CFR 50.59 (c) to report all changes to the operating license.
Section III - Impact of the Change These changes in management titles will not alter the conclusion reached in the FSAR and SER Accident Analysis.
Section IV - Implementation of the Modification The modification as proposed will not impact the ALARA or Fire Protection Program at JAF.
Section V - Conclusions The incorporation of this modification:
a) will not increase the probability nor the consequences of an accident or mal-function of equipment important to safety as previously evalu-ated in the Safety Analysis Report; b) will not increase the possibility for an accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report; and c) will not reduce the margin of safety as defined in the basis for any Technical Specification.
Section VI - References (a)
JAF FSAR (b)
JAF SER 7
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