ML20206B447
| ML20206B447 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 04/03/1987 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Power Authority of the State of New York |
| Shared Package | |
| ML20206B451 | List: |
| References | |
| DPR-59-A-110, GL-83-043 NUDOCS 8704090155 | |
| Download: ML20206B447 (12) | |
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UNITED STATES
.8 NUCLEAR REGULATORY COMMISSION.
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4.....,o POWER AUTHORITY OF THE STATE OF NEW YORK DOCKET N0. 50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLANT-AMENDMENT TO FACILITY OPERATING LICENSE.
Amendment No.110 License No. OPR-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 September 19, 1985, complies with the standards and re as amended (the Act)quirements of the Atomic Energy Act of 1954,, and the C 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 (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 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 Specificetions 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.110, 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 COMMISSION k4d W
pg, Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: April 3,1987 f
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ATTACHMENT TO LICENSE AMENDitENT NO.110 FACILITY OPERATING LICENSE NO DPR-59 DOCKEfNO.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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250 252 253 254-a 254-b 254-c thru 254-f 254-g i
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- s JAFKPP TABLE OF CONTENTS (cont'd)
E.3%*.
D.
Emergency Service Water System 240 E.
Intake Deicing Heaters 242 3.12 Fire Protection Systems 244a 5.0 Design Features 245 5.1 Site 245 5.2 Reactor 245 5.3 Reactor Pressure Vessel 245 5.4 Containment 245 5.5 Fuel Storage 245 5.6 Seismic Design 246 6.0 Administrative Controls 247 6.1 Responsibility 247 6.2 Plant Staff Organization 247 6.3 Plant Staff Qualifications 248 6.4 Retraining and Replacement Training 248 6.5 Review and Audit 248 6.5.1 Plant Operating Review Committee (PORC) 248a 6.5.2 Safety Review Committee (SRC) 250 6.6 Reportable Event Action 253 l
6.7 Safety Limit Violation 253 6.8 Procedures 253 6.9 Reporting Requirements 254a 6.10 Record Retention 254g 6.11 Radiation Protection Program 255 6.12 Industrial Security Program 258 6.13 Emergency Plan 258 6.14 Fire Protection Program 258 6.15 Environmental Qualification 258a Amendment No. Xg, E, M, F,,.se,110 iii
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JAFNPP TECHNICAL SPECIFICATIONS 1.0 DEFINITIONS The succeeding frequently used terms are explicitely defined so that a uniform interpretation of the specifications may be achieved.
A.
Reportable Event - A reportable event shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.
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i B.. Core Alteration - The act of moving any' component in the region above the core support plate, below
.the.. upper grid. and within the shroud.
Normal control rod movement with the - control rod drive
. hydraulic system 'is not defined as a core alteration.
Normal movement of in-core instrumentation is not defined as. a core alteration.
Amendsent No. E, E,110 1
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R2vicw tha Emergsncy Plen end iNplcmenting pecesduras ennually.
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Perform special review and/or investigations at the request of the-Resident Manager.
- 10. Review of all Reportable Events.
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- 11. Review the Offsite Dose Calculation Manual (ODCM) and' 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 disappreval to the Resident Manager of those items considered in 6.5 1E (1) through (4) and determine if items considered in 6.5 1E (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 alternates, 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) Procedures 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 i
b.
Nuclear engineering c.
Chemistry and radiochemistry d.
Metallurgy e.
Instrumentation and control l
Amendment No, M 3F, M R 110 250
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OUORUN 6.5.2.6 A quorum of SRC shall consist of the Chairman, Vice-Chairman or No Alternate Vice-Chairman and four members, including alternates.
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.
- 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. All Reportable Events.
- 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.
j AUDIT Audits of facility activities shall be performed under the cognizance i
6.5.2.8 of the SRC.
These audits shall encompass:
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- a. The conf ormance of f acility operation to provisions contained within the Technical Specifications and applicable license conditions at 1 east once per 12 months.
- b. The performance, training and qualifications of the entire facility staff at least once per 12 months.
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Amendment No. E,.f>4r,JB*, p, 110 252
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CHARTER 6.5.2.11 Conduct of the committee will be in accordance with a charter approved by the Executive Vice President-Nuclear Generation setting forth the mechanism for implementation of the' committee's responsibilities and authority.
6.6 REPORTABLE 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 SRC and the Executive Vice President - Nuclear Generation.
6.7 SAFETY LIMIT VIOLATION i
(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).
(B) An immediate report of each safety limit violation shall be made to the NRC by the Resident Manager. The Executive Vice President-Nuclear Generation 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 appropriate analysis and evaluation of:
(1) 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-Nuclear Generation, Chairman of the SRC and the NRC.
6.8 PROCEDURES (A) Written procedures and administrative policies shall.be estatlished, implemented ana maintained that meet or exceed the i
requirements and 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 and other programs, as specified in Appendix B of the Radiological Effluent Technical Specifications, Section 7.2.
l (B) Those procedures affecting nuclear safety-shall be_ reviewed by PORC and approved by the Resident Manager prior to implementation.
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(C) Temporary changes to nuclear related procedures may be made provided:
1.
The intent of the original procedure is not altered.
Amendment No. HT, Mr,.W. Je, EHr 110 253 f
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- 2. the chcngs is cppecysd by two memb:rs of tho-plcnt manes: ment stcff, at 1sest cn2 of whoa hsids a Sonice R3cctor Operator's licsnse cn tha unit affected.
- 3. The change is documented, reviewed by the PORC and approved by the Resident Manager within 14 days of implementation.
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6.9 REPORTING REOUIREM.?NTS (A) ROUTINE REPORTS l
In addition to the applicable reporting requirements of Title 10 Code of Federal Regulations, the following reports shall be submitted to the Director of the Regional Office of Inspection and Enforcement unless otherwise noted.
- 1. STARTUP REPORT a.
A summary report of plant startup and power escalation testing shall be submitted following (1) taendment 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 report shall address each of the tests identified in the FSAR and shall include 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.
Amendment No. #, M. x, 110 254-a
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(A) ROUTINE REPORTS (Cantinu d) l
- 1. STARTUP REPORT (Continued) b.
Startup Reports shall be submitted within (1) 90 days following completion of the startup test program, or (2) 90 days following resumption or commencement of commercial power operation, or~whichever is earliest.
If the Start-up Report does not cover both events,.i.e... completion of-startup test program and resumption or commencement of commercial power operation, supplementary reports shall be submitted at least every three months until both events are completed.
- 2. ANNUAL OCCUPATIONAL EXPOSURE TABULATION A tabulation on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 meem/yr and_their associated man rem exposure according to work and job functions, 1/ e.g., reactor operations and surveillance, in-service inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD,' or film badge measurements. Small exposures totaling less than 20%
of the individual total dose need not be accounted for.
In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major _ work functions.
- 3. MONTHLY OPERATING REPORT A report providing a narrative summary of facility operating experience, major safety-related maintenance, and other pertinent information, should be submitted no later than_the 15th of each month following the calendar month covered to the USNRC Director Office of Management Information and Program Control.
l 1/ This tabulation supplements the requirements of o 20.407 of 10 CFR Part 20.
Amendment No. 3ff 110 254-b
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Amendment No. x, 110
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l (B) SPECIAL REPORTS
- 1. Fifteen copies of the Evaluation Report of the results of the first five years of performance of the non-destructive l
l inspection listed in Table 4.6-1 of Technical Specifications 4.6.F. Structural Integrity, relating to the FitzPatrick in-service inspection program shall be submitted to the NRC, Director of Operating R'esctors, within three months of the completion of the fifth year of the program.
- 2. Special reports relating to fire protection equipment and systems shall be submitted to the NRC in accordance with Specifications 3.12.A.1.c. 3.12.A.1.d.2, 3.12.B.2, 3.12.C.2 and 3.12.E.2.
6.10 RECORD RETENTION (A) The following records shall be retained for at least five years:
- 1. Records and logs of facility operation covering time intervals at each power level.
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- 2. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.
- 3. All Reportable Events.
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- 4. Records of surveillance activities, inspections and calibrations required by these Technical Specifications.
- 5. Records of reactor tests and experiments.
- 6. Records of changes made to Operating Procedures.
- 7. Records of radioactive shipments.
- 8. Records of sealed source leak tests and results.
- 9. Records of annual physical inventory of all source material of record.
Amendment No..x 110 i
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