ML17332A819

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Amends 195 & 181 to Licenses DPR-58 & DPR-74,respectively, Modifying Containment Ventilation System TS & Associated Bases to Allow Limited Purge Operation in Modes 1,2,3 & 4
ML17332A819
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 06/23/1995
From: John Hickman
NRC (Affiliation Not Assigned)
To:
Shared Package
ML17332A820 List:
References
NUDOCS 9506300213
Download: ML17332A819 (12)


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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON> D.C. 2055&0001 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-315 DONALD C.

COOK NUCLEAR PLANT UNIT NO.

1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

195 License No.

DPR-58 l.

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

A.

B.

C.

D.

E.

The application for amendment by Indiana Michigan Power Company (the licensee) dated March 31,

1995, 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;

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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; 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 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.

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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-58 is hereby amended to read as follows:

Technical S ecifications The Technical Specifications contained in Appendices A and B,

as revised through Amendment No. 195, 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 issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

June 23, 1995 Wohn B. Hickman, Project Manager Project Directorate III-I Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation

ATTACHMENT TO LICENSE AMENDMENT NO.

195 TO FACILITY OPERATING LICENSE NO. DPR-58 DOCKET NO. 50-315 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.

The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

REMOVE 3/4 6-9a B 3/4 6-2a INSERT 3/4 6-9a B 3/4 6-2a

3/4 LIMTINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.6 CONTAINIvtENTSYSTEMS CONTAINMEl<T VENTILATIONSYSTEM LIMITINGCONDITION FOR OPERATION 3.6.1.7 The containment purge supply and exhaust system shall be closed except when operation of the containment purge system is required for pressure control, ALARA, and respirable air quality considerations for personnel entry, and for surveillance testing and maintenance activities.

No more than one purge supply path and one purge exhaust path shall be open at a time.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

With one containment purge supply and/or one exhaust isolation valve inoperable, isolate the affected penetration by use of at least one automatic valve secured in the closed position, and, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, either:

1)

Restore the inoperable valve to OPERABLE status, or, 2)

Deactivate the automatic valve secured in the closed position.

Operation may then continue until performance of the next required valve test provided that the automatic valve secured in the closed position is verified to be deactivated in the closed position at least once per 31 days.

c.

Otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

d.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCERE UIREMENTS 4.6.1.7.1 The surveillance requirements of Technical Specification 3/4.6.3.1 apply.

COOK NUCLEAR PLANT-UNIT 1 Page 3/4 6-9a Ai>IEMNIENT66 195

3/4 BASES 3/4.6 CONTAINMENTSYSTEMS 3/4.6.1.7 CONTAINMENTPURGE AND EXHAUST ISOLATIONVALVES This specification ensures that the containment purge supply and exhaust isolation valves are closed for the majority of the time during normal operation.

It allows for containment PURGING to support pressure control, ALARA, and respirable air quality considerations for personnel entry, and for surveillance testing and maintenance activities up to 240 hours0.00278 days <br />0.0667 hours <br />3.968254e-4 weeks <br />9.132e-5 months <br /> each year for each unit.

The containment purge system is designed in accordance with the requirements ofNRC Branch Technical Position CSB &4, Rev. 1. This includes, but is not limited to, an analysis ofthe impact of PURGING on ECCS performance, an evaluation of the radiological consequences of a design basis accident while PURGING, and limiting PURGE operation to using no more than one supply path and one exhaust path at a time. The purge isolation valves have been demonstrated capable of closing against the dynamic forces associated with a losswfwoolant accident and are assured of receiving a Containment Ventilation Isolation signal.

Therefore, the SITE BOUNDARY dose guidelines of 10 CFR 100 would not be exceeded in the event of an accident during containment PURGING operations.

The use of the pressure relief (vent) line is allowed for containment pressure control.

COOK NUCLEAR PLAVI'-UNIT1 Page B 3/4 6-2a ALIEN)IIENT 66 195

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UNITED STATES NUCL'EAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-316 DONALD C.

COOK NUCLEAR PLANT UNIT NO.

2 AMENDMENT TO FACILITY OPERATING LICENSE 4

Amendment No.

181 License No.

DPR-74 l.

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

A.

B.

C.

D.

E.

The application for amendment by Indiana Michigan Power Company (the licensee) dated March 31,

1995, 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 7 The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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; 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 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-74 is hereby amended to read as follows:

Technical S ecifications The Technical Specifications contained in Appendices A and B,

as revised through Amendment No. 181, 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 issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

June 23',

1995 John B. Hickman, Project Manager Project Directorate III-I Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

ATTACHMENT TO LICENSE AMENDMENT NO.

181 FACILITY OPERATING LICENSE NO.

DPR-74 DOCKET NO. 50-316 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.

The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

REMOVE 3/4 6-9a B 3/4 6-2a INSERT 3/4 6-9a B 3/4 6-2a

0 3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIIKMENTS 3/4.6 CONTAINMENTSYSTEMS CONTAINMENTVENTILATIONSYSTEM LIMITINGCONDITION FOR OPERATION 3.6.1.7 The containment purge supply and exhaust system shall be closed except when operation of the containment purge system is required for pressure control, ALAIVandrespirable air quality considerations for personnel entry, and for surveillance testing and maintenance activities.

No more than one purge supply path and one purge exhaust path shall be open at a time.

~CTI ON:

With one containment purge supply and/or one exhaust isolation valve inoperable, isolate the affected penetration by use of at least one automatic valve secured in the closed position, and, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, either:

1)

Restore the inoperable valve to OPERABLE status, or, 2)

Deactivate the automatic valve secured in the closed position.

Operation may then continue until performance of the next required valve test provided that the automatic valve secured in the closed position is verified to be deactivated in the closed position at least once per 31 days.

c.

Othetwise, be in at least HOT STANDBYwithin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

d.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCERE UIREMENTS 4.6.1.7.1 The surveillance requirements ofTechnical Specification 3/4.6.3.1 apply.

COOK NUCLEAR PL< IT-UNIT2 Page 3/4 6-9a AiXIEND~IENTW 181

3/4 BASES 3/4.6 CONTAINMENTSYSTEMS 3/4.6.1.7 CONTAINMENTPURGE AND EXHAUST ISOLATION VALVES This specification ensures that the containment purge supply and exhaust isolation valves are closed for the majority of the time during normal operation.

It allows for containment PURGING to support pressure control, ALARA, and respirable air quality considerations for personnel catty, and for surveillance testing and maintenance activities up to 240 hours0.00278 days <br />0.0667 hours <br />3.968254e-4 weeks <br />9.132e-5 months <br /> each year for each unit.

The containmeat purge system is designed in accordance with the requirements of NRC Braach Technical Position CSB 64, Rev. 1. This includes, but is not limited to, an analysis of the impact of PURGING on ECCS performance, an evaluation of the radiological consequences ofa design basis accident while PURGING, and limiting PURGE operation to using no more than one supply path aad one exhaust path at a time. The purge isolation valves have been demonstrated capable of closing against the dynamic forces associated with a losswfwoolant accideat and are assured of receiving a Containmeat Ventilation Isolation signal.

Therefore, the SITE BOUNDARY dose guidelines of 10 CFR 100 would not be exceeded in the event of an accident during containment PURGING operations.

The use of the prcssure relief (vent) line is allowed for containment pressure control.

COOK iiUCLEARPLANT-UNIT2 Page B 3/4 6-2a AiXIEIDiVIENTW 181

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