ML17328A369
| ML17328A369 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/03/1990 |
| From: | Pierson R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17328A370 | List: |
| References | |
| GL-89-14, NUDOCS 9008160044 | |
| Download: ML17328A369 (11) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-315 DONALD C.
COOK NUCLEAR PLANT UNIT NO. I AMENDMENT TO FACILITY OPERATItIG LICENSE Amendment No.
143 License No. DPR-58 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company (the licensee) dated February 7, 1990, 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 COIrmission's regulations; D.
The issuance of this amendment wi 11 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.
9008i60044 900803 PDR ADOCK 050003i5 P
P13C 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. 143., 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.
FOR THE NUCLEAR REGULATORY COl"NlISSION
Attachment:
Changes to the Technical Specifications Date of. Issuance:
Agust 3, gggp Robert Piersoe, Director Project Directorate III-1 Division of Reactor Projects - III, IV, V Im Special Projects Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AfjEHDMENT NO.
143 FACILITY OPERATING LICENSE NO. DPR-58 DOCKET NO. 50-315 Pevise 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 marginal lines indicating the area of change.
RENOVE 3/4 0-2 B 3/4 0-4 INSERT 3/4 0-2 B 3/4 0-4
3 4.0 APPLICABILITY SURVEILLANCE RE UIREMENTS 4.0.1 Surveillance requirements shall be applicable during the GPERATIONAL MODES or other.conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.
4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 254 of the specified surveillance interval.
4.0.3 Performance of a Surveillance Requirement within the specified time interval shall constitute compliance with OPERABILITY requirements for a Limiting Condition for Operation and associated ACTION statements unless otherwise required by the specification.
Surveillance requirements do not have to be performed on inoperable equipment.
4.0.4 Entry into an OPERATIONAL MODE or other specified applicability condition shall not be made unless the Surveillance Requirement(s) associated with the Limiting Condition for Operation have been performed within the stated surveillance interval or as otherwise specified.
4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1,
2, and 3 components shall be applicable as follows:
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Inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1,
2 and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g),
except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).
COOK NUCLEAR P~'~PT
-. UNIT 1 3/4 0-2 AMENDMENT NO. $$,143
APPLICABILITY BASES 4.0.1 This specification provides that surveillance activities necessary to insure the Limiting Conditions for Operation are met and will be performed during the OPERATIONAL MODES or other conditions for which the Limiting Conditions for Operation are applicable.
Provisions for additional surveillance activities to be performed without regard to the applicable OPERATIONAL MODES or other conditions are provided in the individual Surveillance Requirements.
4.0.2 This specification establishes the limit for which thy specified time interval for Surveillance Requirements may be extended.
It permits an allowable extension of the normal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance, e.g., transient conditions or other ongoing surveillance or maintenance activities. It also provides flexibilityto accommodate the length of a fuel cycle for surveillances that are performed at each refueling outage and are specified with an 18-month surveillance interval. It is not intended that this provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillances that are not performed
, during refueling outages.
The limitation of Specification 4.0.2 is based on engineering judgment and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the Surveillance Requirements.
This provision is sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance
- interval, 4.0.3 The provisions of this specification set forth the criteria for determination of compliance with the OPERABILITY requirements of the Limiting Conditions for Operation.
Under this criteria, equipment, systems or components are assumed to be OPERABLE if the associated surveillance activities have been satisfactorily performed within the specified time interval.
Nothing in this provision is to be construed as defining equipment, systems or components OPERABLE, when such items are found or known to be inoperable although still meeting the Su'rveillance Requirements.
4.0.4 This specification ensures that the surveillance activities associated with a Limiting Condition for Operation have been performed within the specified time interval prior to entry into an OPERATIONAL MODE or other applicable condition.
The intent of this provision is to ensure that surveillance activities have been satisfactorily demonstrated on a current basis as required to meet the OPERABILITY requirements of the Limiting Condition for Operation.
Under the terms of this specification, for example, during initial plant startup or following extended plant outages,. the applicable surveillance activities must be performed within the stated surveillance interval prior to placing or returning the system or equipment into OPERABLE status.
COOK NUCLEAR PLANT - UNIT 1 B 3/4 0-4 AMENDMENT NO.
$$,143.
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-316 DONALD C.
COOK NUCLEAR PLANT~ UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment tlo. 130 License No. DPR-74 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company (the licensee) dated February 7, 1990, 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 wi 11 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-58 is hereby amended to read as follows:
The Technical Specifications contained in Appendices A and'B, as revised through Amendment No.
$ 3Q', 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.
FOR THE NUCLEAR REGULATORY COflMISSION
Attachment:
Changes to the Technical Specifications Project Directorate III-I Division of Reactor Projects - III, IV, V & Special Projects Office of Nuclear Reactor Regulation August 3
$ 99Q
ATTACHMENT TO LICENSE AHENDt1ENT NO.
130 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 marginal lines indicating the area of change.
RENOVE 3/4 0-2 B 3/4 0-3 INSERT 3/4 0-2 B 3/4 0-3
3 4.0 APPLICABILITY SURVEILLANCE RE UIREMENTS 4.0.1 Surveillance Requirements shall be applicable during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.
4.0.2 Each Surveillance Requirement shall, be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.
4.0.3 Performance of a Surveillance Requirement within the specified time interval shall constitute compliance with OPERABILITY requirements for a Limiting Condition for Operation and associated ACTION statements unless otherwise required by the specification.
Surveillance requirements do not have to be performed on inoperable'equipment.
4.0.4 Entry into an OPERATIONAL MODE or other specified applicability condition shall not be made unless the Surveillance Requirement(s) associated with the Limiting Condition for Operation have been performed within the stated surveillance interval or as otherwise specified.
4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, and 3 components shall be applicable as follows:
Inservice inspection of ASME Code Class 1,
2, and 3 components and inservice testing of ASME Code Class 1,
2 and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicpble Addenda as required by 10 CFR 50, Section 50.55a(g),
except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).
.COOK NUCLEAR PLANT - UNIT 2 3/4 0-2 AMENDMENT NO.
PP
],3P
APPLICABILITY 0
BASES 3.0.5 (Continued) consistent with the ACTION statement for the inoperable normal power sources
- instead, provided the other specified conditions are.satisfied.
In this
- case, this would mean that for one division the emergency power source must be OPERABLE'(as must be the components supplied by the emergency power source) and all redundant
- systems, subsystems,
- trains, components and devices in the other. division must be OPERABLE, or likewise satisfy Specification 3.0.5 (i.e.,
be capable of performing their design functions and have an emergency power source OPERABLE). In other words, both emergency power sources must be OPERABLE and all redundant
- systems, subsystems,
- trains, components and devices in both divisions must also be OPERABLE. It these conditions are not satisfied, action is requiied in accordance with this specification.
In MODES 5 or 6, Specification 3.0.5 is not applicable,
.and thus the indivi'dual ACTION statements for each applicable Limiting Condition for Operation in these MODES must be adhered to.
4.0.1 This specification provides that surveillance activities necessary to insure the Limiting Conditions for Operation are met and will be performed during the OPERATIONAL MODES or other conditions for which the Limiting Conditions for Operation. are applicable.
Provisions for additional surveillance activities to be performed without regard to the applicable OPERATIONAL MODES or other conditions are provided in the individual Surveillance Requirements.
4.0.2 This specification establishes the limit for which the specified time interval for Surveillance Requirements may be extended.
It permits an allowable extension of the normal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance, e.g., transient conditions or other ongoing surveillance or maintenance activities. It also provides flexibilityto accommodate the length of a fuel cycle for surveillances that are performed at each refueling outage and are specified with an 18-month surveillance interval. It is not intended that this provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillances that are not performed during refueling outages.
The limitation of Specification 4.0.2 is based on engineering
]udgment and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the Surveillance Requirements.
This provision. is sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval.
I 4.0.3 The provisions of this specification set forth the criteria for determination of compliance with the OPERABILITY requirements 'of the Limiting Conditions for Operation.
Under this criteria, equipment, systems or components are assumed to be OPERABLE if the associated surveillance activities have been satisfactorily performed within the specified time interval.
Nothing in this provision is to be construed as defining equipment, systems or components OPERABLE, when such items are found or known to be. inoperable although still meeting the Surveillance Requirements.
COOK NUCLEAR PLANT - UNIT 2 B 3/4 0-3 AMENDMENT NO. 'PP,13P