ML17334B649
| ML17334B649 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/08/1997 |
| From: | John Hickman NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17334B650 | List: |
| References | |
| NUDOCS 9708130457 | |
| Download: ML17334B649 (9) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&0001 INDIANAMICHIGANPOWER COMPANY DOCKET NO. 50-315 DONALD C. COOK NUCLEAR PLANT UNIT 1 AMENDMENTTO FACILITYOPERATING LICENSE Amendment No. 217 License No, DPR-58 The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company (the licensee) dated December 20, 1996, 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 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:
9708'i30457 970808 PDR ADQCK 05000Si5.
P PDR Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
217, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
This license amendment is effective as of the date of issuance, with full implementation within 45 days.
FOR THE NUCLEAR REGULATORY COMMISSION John B. Hickman, Project Manager Project Directorate I II-3 Division of Reactor Projects I II/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance.
Au8ust 8, 1997
ATTACHMENTTO LICENSE AMENDMENTNO. 217 TO FACILITYOPERATING 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 INSERT 3/4 4-33 3/4 4-33
3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.10 STRUCTURAL INTEGRITY ASME CODE CLASS 1
2 and 3 COMPONENTS LIMITINGCONDITION FOR OPERATION 3.4.10.1 The structural integrity of the ASME Code Class 1, 2 and 3 components shall be maintained in accordance with Specification 4.4.10.1.
APPLICABILITY:
ALLMODES
~CTtON:
With the structural integrity of any ASME Code Class 1 component(s) not conforming to the above requirements, restore the structural integrity ofth affected component(s) to within its limit or isolate the affected compottent(s) prior to increasing the Reactor Coolant System temperature more than 50'F above the minimum temperature required by NDT considerations.
With the structural integrity of any ASME Code Class 2 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature'bove 200'F.
With the structural integrity of any ASME Code Class 3 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) from service.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCERE UIREMENTS 4.4.10.1 In addition to the requirements of Specification 4.0.5, each reactor coolant pump flywheel shall be inspected by either qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (magnetic particle testing and/or penetrant testing) of exposed surfaces defined by the volume of the disassembled flywheels once every 10 years.
COOK NUCLEAR PLANT-UNITI Page 3/4 4-93 AMENDMENT98, 217
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 INDIANAMICHIGANPOWER COMPANY DOCKET NO. 50-316 DONALD C. COOK NUCLEAR PLANT UNIT 2 AMENDMENTTO FACILITYOPERATING LICENSE Amendment No. 201 License No. DPR-74 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company (the licensee) dated December 20, 1996, 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 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.
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. 201, 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, with full implementation within 45 days.
FOR THE NUCLEAR REGULATORY COMMISSION p4 John B. Hickman, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 8, 1997
ATTACHMENTTO LICENSE AMENDMENTNO. 201 FACILITYOPERATING 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 INSERT 3/4 4-31 3/4 4-31
t i
3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS
~
3/4.4 REACTOR COOLANT SYSTEM 3/4.4.10 STRUCTURAL INTEGRITY ASME CODE CL'ASS 1
2 Bnd 3 COMPONENTS LIMITINGCONDITION FOR OPERATION 3.4.10.1 The structural integrity of ASME Code Class 1, 2 and 3 components shall be maintained in accordance with Specification 4.4.10.1.
APPLICABILITY:
ALLMODES
~CT ION:
al With the structural integrity of any ASME Code Class I c mponent(s) not conforming to the above requirements, restore the structural integrity ofthe affected component(s) to within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature snore than 50'F above the minfmum temperature required by NDT considerations.
With the structural integrity of any ASME Code Class 2 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature above 200'F.
With the structural integrity of any ASME Code Class 3 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) from service.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCERE UIREMENTS 4.4.10.1 In addition to the requirements of Specification 4.0.5, each reactor coolant pump flywheel shall be inspected by either qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-h=". the outer radius or a surface examination (magnetic particle testing and/or penetrant testing) of exposed surfaces defined by the volume of..e disassembled flywheels once every 10 years.
COOK NUCLEAR PLAÃf-UNIT2 Page 3/4 4-91 AMENDMENTBQ, 201