ML17334B668
| ML17334B668 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 12/10/1997 |
| From: | John Hickman NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17334B669 | List: |
| References | |
| NUDOCS 9712170229 | |
| Download: ML17334B668 (10) | |
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t UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.O. 2055&4001 INDIANAMICHIGANPOWER COMPANY DOCKET NO. 50-315 DONALD C. COOK NUCLEAR PLANT UNIT NO. I AMENDMENTTO FACILITYOPERATING LICENSE Amendment No. 219 License No. DPR-58 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 September 19, 1997, 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 facilitywill 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-58 is hereby amended to read as follows:
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Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. ~19, 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 ohn 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:
December 10, 1997
ATTACHMENTTO LICENSE AMENDMENTNO. 2>9 TO FACILITYOPERATING LICENSE NO. DPR-58 DOCKET NO. 50-315 Revise Appendix A Technical Specifications by removing the page identified below and inserting the attached page.
The revised page is identified by amendment number and contain vertical lines indicating the area of change.
REMOVE INSERT 3/4 5-5 3/4 5-5
. 3/4 LIMITINGCOND S FOR OPERATION AND SURVEILL REQUIREMENTS 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)
SURVEILLANCERE UIREMENTS Continued d.
At least once per 18 months by:
1.
Verifying the automatic interlock action to prevent opening of the suction of the RHR system from the Reactor Coolant System when the Reactor Coolant System pressure is above 600 psig.
2.
A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or abnormal corrosion.
e.
At least once per 18 months, during shutdown, by:
1.
Verifyingthat each automatic valve in the flowpath actuates to its correct position on a Safety Injection test signal.
2.
Veiifyingthat each of the following pumps start automatically upon receipt of a safety injection signal:
a)
Centrifugal charging pump b)
Safety injection pump c)
Residual heat removal pump By verifying that each of the following pumps'eveloped head. at the test fiow point is greater than or equal to the required developed head when tested pursuant to specification 4.0.5.
1.
Centrifugal charging pumps 2.
Safety injection pumps 3.
Residual heat removal pumps By verifying the correct position of each mechanical stop for the following Emergency Core Cooling System throttle valves:
1.
Within4 hours followingcompletion ofeach valve stroking operation or maintenance on the valve when the ECCS subsystems are required to be OPERABLE.
COOK NUCLEAR PLANT-UNITI Page 3/4 5-5 AMENDMENT407, 4A,
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 INDIANAMICHIGANPOWER COMPANY DOCKET NO. 50-316 DONALDC. COOK NUCLEAR PLANT UNIT NO. 2 AMENDMENTTO FACILITYOPERATING LICENSE Amendment No.203 License No. DPR-74 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
The application for amendment by Indiana Michigan Power Company (the licensee) dated September 19, 1997, complies with the standards and requirements'f 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.
E.
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.
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. 20~, 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 hn 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:
December 10, 1997
ATTACHMENTTO LICENSE AMENDMENTNO. 20>
FACILITYOPERATING LICENSE NO. DPR-74 DOCKET NO. 50-316 Revise Appendix A Technical Specifications by removing the page identified below and inserting the attached page.
The revised page is identified by amendment number and contain vertical lines indicating the area of change.
REMOVE INSERT 3/4 5-5 3/4 5-5
9/4 LIMITINGCONDIT S FOR OPERATION AND SURVEILL
~ REQUIREMENTS 3/4,5 EMERGENCY CORE COOLING SYSTEMS (ECCS)
SURVEILLANCERE UIREMENTS Continued d:
At least once per 18 months by:
1.
Verifying the automatic interlock action to prevent opening of the suction of the RHR system from the Reactor Coolant System when the Reactor Coolant System pressure is above 600 psig.
2.
A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or corrosion.
, e.
At least once per 18 months, during shutdown, by:
1.
Verifying that each automatic valve in the flowpath actuates to its correct position on a Safety Injection test signal.
2.
Verifying that each of the following pumps start automatically upon receipt of a safety injection signal:
a)
Centrifugal charging pump b)
Safety injection pump c)
Residual heat removal pump f.
By verifying that each of the following pumps'eveloped head at the test flow point is greater than or equal to the required developed head when tested pursuant to Specification 4.0.5.I 1.
Centrifugal charging pumps 2.
Safety Injection pumps 3.
Residual heat removal pumps By verifying the correct position of each mechanical stop for the following Emergency Core Cooling System throttle valves:
1.
Within4 hours followingcompletion ofeach valve strohng operation or maintenance on the valve when the ECCS subsystems are required to be OPERABLE.
COOK NUCLEAR PLANT-UNIT2 Page 3/4 5-5 AMENDMENT434, 484, 4$8, 4$Q, 488, 203