ML20076N051

Amend 218 to License DPR-59,revising TS to Relocate Fire Protection Requirements from TS to Plant Fire Protection Program

ML20076N051
Person / Time
Site:	FitzPatrick
Issue date:	11/03/1994
From:	Marsh L Office of Nuclear Reactor Regulation
To:
Shared Package
ML20076N056	List: ML20076N051 ML20076N062
References
GL-86-10, GL-88-12, NUDOCS 9411090168
Download: ML20076N051 (15)

Text

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k UNITED STATES

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NUCLEAR REGULATORY COMMISSION t

WASHINGTON, D.C. 205!% 0001

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POWER AUTHORITY OF THE STATE OF NEW YORK DOCKET NO. 50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLANT l

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 218 License No. DPR-59 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Power Authority of the State of New York (the licensee) dated July 21, 1994, as supplemented September 26, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, 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 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 i

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 i

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:

9411090168 941103 DR ADOCK 05000333

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PDR i

' (2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 218, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

Accordingly, pages 3 and 3a of Facility Operating License No. DPR-59 are hereby amended to read as follows:*

2.C.(3)

Fire Protection The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility and as approved in the SER dated November 20, 1972; the SER Supplement No. I dated February 1, 1973; the SER Supplement No. 2 dated October 4, 1974; the SER dated August 1, 1979; the SER Supplement dated October 3, 1980; the SER Supplement dated February 13, 1981; the NRC Letter dated February 24, 1981; Technical Specification Amendments 34 (dated January 31, 1978), 80 (dated May 22, 1984), 134 (dated July 19, 1989), 135 (dated September 5, 1989), 142 (dated October 23, 1989), 164 (dated August 10, 1990), 176 (dated January 16, 1992), 177 (dated February 10, 1992), 186 (dated February 19, 1993), 190 (dated June 29, 1993), 191 (dated July 7, 1993), 206 (dated February 28, 1994) and 214 (dated June 27, 1994); and NRC Exemptions and associated safety evaluations dated April 26, 1983, July 1, 1983, January 11, 1985, April 30, 1986, September 15, 1986 and September 10, 1992 subject to the following provision:

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

. j 4.

This license amendment is effective as of the date of its issuance to be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION

.[

Ledyard B.

arsh, Director Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

i 1.

Pages 3 and 3a of License DPR-59 2.

Changes to the Technical Specifications Date of Issuance:

November 3, 1994 i

• Pages 3 and 3a are attached, for convenience, for the composite license to 4

reflect this change.

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(3)

Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use, at any time, any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)

Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use, at any time, any byproduct, source and special nuclear material without restriction k

to chemical or physical form, for sample analysis or instrument calibration; or associated with radioactive apparatus, components or tools.

(5)

Pursuant to the Act and 10 CFR Parts 30 and 70, to g

possess, but not separate, such byproduct and special u*

nuclear materials as say be produced by the operation j

of the facility.

C.

The license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter

)

in effect; and is subject to the additional conditions specified or incorporated below:

(1)

Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2436 megawatts (thermal).

(2)

Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.

are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

• Each amendment updates this paragraph to indicate the latest amendment to the License.

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-3a-

.(3)-

Fire Protection The licensee s' hall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis-Report for the facility-and as approved in the SER dated November 20, 1972; the SER Supplement No. 1 dated February 1, 1973; the SER Supplement No. 2 dated October 4, 1974; the SER dated August 1, 1979; the SER Supplement dated October 3,.1980;-the-SER Supplement dated February 13, 1981; the NRC Letter dated g

February 24, 1981; Technical Specification Amendments e

34 (dated January 31, 1978), 80 (dated May 22, 1984),

• l 134 (dated July 19, 1989), 135 (dated September 5, 1989), 142 (dated October'23,1989), 164 (dated August 10, 1990), 176 (dated January 16, 1992),

y 177 (dated February 10, 1992), 186 (dated February 19, 1993),-190 (dated' June 29, 1993), 191 (dated July 7, 1993), 206 (dated February 28, 1994) and 214~(dated June 27, 1994); and NRC Exemptions and associated safety evaluations dated April 26, 1983, July 1, 1983, January 11, 1985, April 30, 1986, September 15, 1986 and September 10, 1992 subject to l

the following provision:

The licensee may make changes to the approved fire-protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

(4)

Systems Intecrity The licensee shall implement a program to reduce leakage from the systems outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as practical levels.

This program shall include the'following:

f 1.

Provisions establishing maintenance and periodic visual inspection requirements, and 2.

Leak test requirements for the systems at a f

frequency not to exceed operating cycle intervals.

3 (5)

Iodine Monitorina j

The licensee shall implement a' program which will m

ensr.re the capability to accurately determine the 4

airborne iodine concentration in areas vital to the mitigation of or recovery from an accident.

This i

program shall. include the following:

1.

Training of personnel, i

2.

Procedures for monitoring, and 3.

Provisions for maintenance of sampling and i

analysis equipment.

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ATTACHMENT TO LICENSE AMENDMENT NO. 218 FACILITY OPERATING LICENSE NO. DPR-59 DOCKET NO. 50-333 Revise Appendix A as follows:

j Remove Paaes Insert Paces 111 111 vi vi 6

6 244a 244a 244b Page deleted 244c Page deleted 244d Page deleted 244e Page deleted 244f Page deleted 244g Page deleted 244h Page deleted 2441 Page deleted 244j Page deleted 244k Page deleted 2441 Page deleted 244m Page deleted 244n Page deleted 244o Page deleted 244p Page deleted 244q Page deleted 244r Page deleted 244s Page deleted 244t Page deleted 244u Page deleted 244v Page deleted 244w Page deleted 247a 247a 248 248 l

249 249 250 250 254g 254g e

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JAFNPP TABLE OF CONTENTS (Cont'd)

Eage D.

Emergency Service Water System 240 E.

Intake Deicing Heaters -

242 DELETED 244a j

5.0 Design Features 245 5.1 Site.

245 5.2 Reactor 245 5.3 Reactor Pressure Ve.ssel 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 Organization 247 6.2.1~ Facility Management and Technical Support 247 6.2.2 Plant Staff 247a 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 253-6.7 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. 7, 22, 32, 34, 37, 03, 110, 100,107,218 iii

JAFNPP LIST OF TABLES Table Iille Eage 4.2-8 Minimum Test and Calibration Frequency for Accident Monitoring 86 Instrumentation 4.6-1 Snubber Visual Inspection Intental 161 4.6 2 Minimum Test and Calibration Frequency for Drywell Continuous 162a Atmosphere Radioactivity Monitoring System 4.7-1 (DELETED) 210 4.7 2 Exception to Type C Tests 211 3.12-1 (DELETED) 244a 3.12-2 (DELETED) 244a-3.12-3 (DELETED) 244a 4.12-1 (DELETED) 244a.

4.12 2 (DELETED) 244a 4.12-3 (DELETED) 244a 6.2 1 Minimum Shift Manning Requirements 260a 6.10-1 Component Cyclic or Transient Limits 261 I

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Amendment No. 20, 22, 02, 111, 130, 134, 150, 173, 180, 181, 210,218 vi

JAFNPP 1.0 (cont'd)

U.

Ih0HDal Parameters V.

Electrically Disarmed Control Rod 1.

Minimum critical power ratio (MCPR)- Minimum value To disarm a rod drive electrically, the four amphenol type of the ratio of that power in a fuel assembly which is plug connectors are removed from the drive insert and calculated to cause some point in that fuel assembly to withdrawal solenoids rendering the rod incapable of experience boiling transition to the actual assembly withdrawal. This procedure is equivalent to valving out the operating power for all fuel assemblies in the core.

drive and is preferred. Electrical disarming does not elirninate position indication.

2.

Fraction of Umiting Power Density - The ratio of the linear heat generation rate (LHGR) existing at a given W.

Deleted

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location to the design LHGR.

X.

Slaggered Tast Basis 3.

Maximum Fraction of Umiting Power Density - The Maximum Fraction of Umiting Power Density (MFLPD)

A Staggered Test Basis shall consist of:

is the highest value existing in the core of the Fraction of Umiting Power Density (FLPD).

a.

A test schedule for "n" systems, subsystems, trains or other designated components obtained 4.

Transition Boiling - Transition boiling means the boiling by dividing the specified test interval into "n" region between nucleate and film boiling. Transition equal subintervals.

boiling is the region in which both nucleate and film boiling occur intermittently with neither type being b.

The testing of one system, subsystem, train or completely stable.

Other designated component at the beginning of each subinterval.

Y.

Bated Recirculation Flow That drive flow which produces a core flow of 77.0 x 108 l

lb/hr.

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l Amendment No. 4k64d2-74-lO9-134-162-188,218 6

JAFNPP Pages 244a - 244w DELETED l

Amendment No. 34;-80 434r435, 218 7

244a

JAFNPP e

4 2.

An SRO or an SRO with a license limited to fuel handling shall directly superva6 si Core Alterations. This person shall have no other duties during this time; 3.

DELETED

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l' 4.

In the event of illness or unexpected absence, up to two (2) hours is allowed to restore the shift crew to the minimum complement.

l 5.

The Operations Manager, Assistant Operations Manager, Shift Supervisor and Assistant Shift Supervisor shall hold a SRO license and the Senior Nuclear Operator and the Nuclear Control Operator shall hold a RO license or an SRO license.

6.

Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions; e.g., senior reactor operators, health physicists, auxiliary operators, and maintenance personnel who are working on safety-related systems.

Adequate shift coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating personnel work a normal 8-hour day, 40-hour week while the plant is operating.

However, in the svent that unforeseen problems require substantial amounts of overtime to 1

be used or during extended periods of shutdown for refueling, major maintenance or major modifications, on a temporary basis, the following guidelines shall be followed:

An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, a.

excluding shift tumover time.

j b.

An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any seven day period, all excluding shift tumover time.

A break of at least eight hours should be allowed between work periods, including c.

shift tumover time.

d.

Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.

Any deviation from the above guidelines shall be authorized by the Resident Manager or the General Manager - Operations, or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation.

Controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the Resident Manager or his designee to assure that excessive hours l

have not been assigned. Routine deviation from the above guidelines is not authorized.

I Amendment No. 49, " 1, 120, 127,479, 190,218 247a

JAFNPP l

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 i

qualifications of ANSI N18.1-1971 for comparable positions; except for the 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 i

Supervisor. (1) 4 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 1

Advanced Technical Training Program prior to the issuance of Ucense Amendment i

111, shall be considered qualified as dual-role SRO/ STAS.

6.4 RETRAINING AND REPLACEMENT TRAINING l

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 J

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.

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6.5 REVIEW AND AUDIT Two separate groups for plant operations have been constituted. One of these, the Plant Operating Review Committee (PORC), is an onsite review group. The other is an independent review and audit group, the offsite Safety Review Committee (SRC).

l Amendment No. 22, 31, 57, 00, ' *, 134, 137, #78, 100,218 248 l

JAFNPP (B) Altemates Altemative members shall be appointed in writing by the PORC Chairman to serve on a temporary basis; however, no more than two altemates shall participate in PORC activities at any one time.

(C) Meeting Frequency 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.

(D) Quorum A quorurn of the PORC shall consist of the Chairman or one of three Vice-Chairmen and five members including designated attemates. Vice-Chairmen may act as members when not acting as Chairman.

(E) Responsibilities 1.

Review plant procedures, and changes thereto, required by Specification 6.8.

2.

Review proposed tests and experiments that affect nuclear safety.

1 3.

Review proposed changes to the Operating Ucense and Technical Specifications.

4.

Review proposed changes or modifications to plant systems or equipment that affect 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.

l 6.

Review plant operations to detect potential safety hazards.

7.

Review the Security Plan (including the Safeguards Contingency Plan) and implementing i

procedures annually.

8.

Review the Emergency Plan and implernenting procedures annually.

9.

Perform special review and/or investigations at the request of the Resident Manager.

10. Review of all reportable events.

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.

13. Review the FitzPatrick Fire Protection Program and implementing procedures and changes thereto.

Amendment No. 22,57,04,173,218 249

-JAFNPP I

(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 6.51E (1) through (4) and determine if items considered in 6.51E (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 attemates, 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.

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6.5.2 SAFETY REVIEW COMMITTEE (SRC)

FUNCTION i

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 radiochemistry d.

Metallurgy e.

Instrumentation and control i

Amendment No. 50, 78, 03,94-440,218 250

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JAFNPP (B) SPECIAL REPORTS 1.

Fifteen copies of the Evaluation Report of the results of the first five years of <

performance of the non-destructive 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 Reactors, within three months of the completion of the fifth year of the program.

2.

DELETED 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.

2.

Records and logs of principal raintenance activities, inspections, repair and replacement of principalite-equipment related to nuclear safety.

3.

All Reportable Events.

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.

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. Amendment No. 24,410,#7S,218 254g 4

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