ML20210V235
| ML20210V235 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  (DPR-24-A-105, DPR-27-A-108) |
| Issue date: | 02/02/1987 |
| From: | Colburn T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20210V241 | List: |
| References | |
| NUDOCS 8702180725 | |
| Download: ML20210V235 (7) | |
Text
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g NUCLEAR REGULATORY COMMISSION C-l WASHINGTON, D. C. 20555
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WISCONSIN ELECTRIC POWER COMPANY DOCKET N0. 50-266 POINT BEACH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.105 License No. OPR-24 1.
The Nuclear Regulatory Comdiission (the Commission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated August 29, 1986 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 (1) 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 Comission's regulations and all applicable requirements have been satisfied.
0702100725 070202 DR ADOCK 05000266 PDR
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No.-
DPR-24 is hereby amended to read as follows:
B.
Technical Specifications The Technical ~ Specifications contained in Appendices A and B, i
hs revised through Amendment No.105, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
1 3.
This license amendment is effective 20 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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TimothyG.6lburn,ProjectManager PWR Project Directorate #1 i
Division of PWR Licensing-A
Attachment:
1 Changes to the Technical Specifications Date of Issuance: February 2, 1987 i
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$gY UNITED STATES g
NUCLEAR REGULATORY COMMISSION O
j WASHINGTON, D. C. 20555
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WISCONSIN ELECTRIC POWER COMPANY DOCKET N0. 50-301 POINT BEACH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 108 License No. DPR-27 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (thelicensee)datedAugust 29, 1986 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission; C.
There is reasonable assurance (1) 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 Comission'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 i
l amendment, and paragraph 3.E of Facility Operating License No.
DPR-27 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.108, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective 20 days from the date of issuance.
.FOR THE NUCLEAR REGULATORY COMMISSION fm's#h.A'bYY~
Timothy G. Colburn, Project Manager PWR Project Directorate #1 Division of PWR Licensing-A
Attachment:
Changes to the Technical Specifications Date of Issuance: February 2, 1987 I
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' ATTACHMENT TO LICENSE AMENDMENT NOS.' 105 AND 108 TO FACILITY OPERATING LICENSE NOS. DPR-24 AND DPR-27 DOCKET NOS. 50-266 AND 50-301 Revise Appendix A Technical ~ Specifications by removing the pages identified l
below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines. indicating the area of change.
REMOVE INSERT 15.3.3-4 15.3.3-4 15.3.3-5 15.3.3-5 l
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Any. valve required for the functioning'of the system during accident conditions may be inoperable provided repairs are.
completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Prior to initiating repairs,'all valves in the system that provide the duplicate function shall be tested to demonstrate operability.
(Exception: If a spray.
pump is removed from service per b above, valves associated with that train may be removed from service for the period specified for the pump.)
C.
Component Coolina System Single Unit Operation 1.
One reactor shall not be made critical unless the following condi-tions are met:
a.
The two component cooling pumps assigned to that unit are operable.
b.
Either the component cooling heat exchanger associated with the unit together with one of the shared spare heat exchangers are l
operable or the two shared spare heat exchangers are operable.
c.
All valves, interlocks and piping associated with the above components, and required for the functioning of the system during accident condition, are operable.
2.
During power operation, the requirements of 15.3.3.C-1 may be modi-fied to allow one of each of the following conditions at any one time.
If the system is not restored to meet the conditions of 15.3.3.C-1 within the time period specified, the reactor shall be placed in the hot shutdown condition.
If the requirements of 15.3.3.C-1 are not Unit 1 - Amendment No. 105 15.3.3-4 Unit 2 - Amendment No. 108
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e satisfied within an additional'48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the' reactor shall be placed in t se cold shutdown condition.
a.
One of the assigned component cooling pumps may be out of service provided a pump is restored to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
Two heat exchangers which may be aligned to the operating unit may be out of service provided repairs can be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
Two Unit Operation 1.
Both reactors shall not be made critical unless the following conditions are met:
i a.
Three component cooling pumps are operable.
b.
Three component cooling heat exchangers are operable.
c.
All valves, interlocks and piping required for the functioning of
~
the system during accident conditions and associated with the above components are operable.
J 2.
During power operation, the requirements of 15.3.3.C-l'may be modified to allow one of the following conditions at any one time.
If the system is l
not restored to meet the conditions of 15.3.3.C-1 within the time period l
specified, one reactor shall be placed in the hot shutdown condition.
a' One of the three assigned component cooling pumps may be out of service provided a pump is restored to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
Two heat exchangers may be out of service provided repairs can be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
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Service Water System 1.
Neither reactor shall be made or maintained critical unless the following conditions are met:
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15.3.3-5 Unit 1 - Amendment No. 3, JpJ, 105 Unit 2 - Amendment No. 3, 33, Jpf, 108 4
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