ML20035F638
| ML20035F638 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 04/16/1993 |
| From: | Gody A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20035F639 | List: |
| References | |
| NUDOCS 9304220119 | |
| Download: ML20035F638 (11) | |
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,h UNITED STATES O
[h[dj NUCLEAR REGULATORY COMMISSION e
j WAsHtNGTON, D.C. 20555-0M1
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i WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT. UNIT NO. 1 AMEN 9 MENT TO FACILITY OPERATING LICENSE Amendment No. 138 License No. DPR-24 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company.
(the licensee) dated December 7, 1989, 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;'
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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 l
i 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 i
Specifications as indicated in the attachment to this license amendment, i
and paragraph 3.B of facility Operating License No. DPR-24 is hereby l
amended to read as follows:
i 9304220119 930416 i
ADOCK0500g6 DR
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. B.
Technical Specifications i
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 138, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective immediately upon issuance. The Technical Specifications are to be implemented within 20 days from the-date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION dl Anthony 1. Gody, Jr.
Project Manager Project Directorate III-3 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical l
Specifications Date of issuance:
April 16,1993
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UNITED STATES g
NUCLEAR REGULATORY COMMISSION c
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e,E W AsHINGTON. D. C. 20555
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W WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 142 License No. DPR-27 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated December 7, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules ar.d 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 t,
the Commission; C.
There is reasonable assurance (i) that the activities authorized by this smendment 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 amandment will not'be inimical to the common i
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
!. ave been-satisfied.
2.
Accordingly, the license is amended by changes to the Technical l
Specifications as indicated in the attachment'to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-27 is hereby amended to read as follows:
4
_g-B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 142, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective immediately upon issuance. The Technical Specifications are to be implemented within 20 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION y
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Anthony T. G&ly, Jr., Pr ct Manager Project Directorate III-3 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
April 16,1993 t
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4 ATTACHMENT T0 llCENSE AMENDMENT N05.138 AND 142 TO FAClllTY OPERATING LICENSE NOS. DPR-24 AND DPR-27 f
i DOCKET N05. 50-266 AND 50-301 i
i Revise Appendix A Technical Specificatiot.-; by removing the pages identified below and inserting the enclosed pages.
The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 15.3.3-2 15.3.3-2 15.3.3-2a 15.3.3-2a 15.3.3-3 15.3.3-3 15.3.3-3a 15.3.3-3a 15.3.3-4 15.3.3-4 15.3.3-7 15.3.3-7 l
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The isolation valves in the discharge header of the high head i
safety injection system are in the open position.
g.
All valves, interlocks, and piping associated with the above components and required to function during accident conditions are operable.
h.
During conditions of operation with reactor coolant system pressure in excess of 1,000 psig, the source of AC power shall be removed from the accumulator isolation valves MOV-841A and B at the motor l
control center and the valves shall be open.
i.
Power may be restored to MOV-841A and B for the purpose of valve testing or maintenance providing the testing and maintenance is completed and power is removed within four hours.
I 2.
During power operation, the requirements of 15.3.3.A.1, Items b and c, may be modified to allow one of each of the following components to be inoperable at any one time.
If the system is not restored to meet the requirements of 15.3.3.A.1 within the time period specified, the t
reactor shall be placed in the hot shutdown condition.
If the require-ments of 15.3.3.A.1 are not 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 the cold shutdown condition.
a.
One accumulator may be isolated for a period of up to one hour to permit a check valve leakage test.
Before isolating an accumulator, the other accumulator isolation valve shall be checked open, b.
One safety injection pump may be out of service, provided the 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 />.
The other safety injection pump shall be operable.
c.
Any valve in these systems required to function 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 t
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that provide the duplicate function shall be operable.
3.
During' power operation, the requirements of 15.3 3.A.1, Items d and e, may-be modified to allow one of each of the following components to be j
inoperable at any one time.
If the component is not restored to meet i
I Unit 1 Amendment 66,138, 15.3.3-2 Unit l2 Amendment'77,142,
the requirements o. 15.3.3.A.1 within the time specified, the reactor shall be placed in the hot shutdown condition.
If the requirements of 15.3.3.A.1 are not 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 maintained in a condition with reactor coolant temperatures between 500 and 350 F, unless one residual heat removal loop is being relied upon to provide redundancy for decay heat removal.
In this case the reactor shall be maintained between 350 F and 140 F.
One residual heat removal pump may be out of service, provided the pump a.
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 />.
The other residual heat removal pump shall be operable.
l b.
One residual heat exchanger may be out of service for a period of no more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
Any valve in the system, required to function during accident conditions, c.
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 operable.
Unit 1 Amendment f 6,138 15.3.3-2a Unit 2 Amendment 7J,142
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B.
Containment Cooling and Iodine Removal Systems 1.
A reactor shall not be made critical, except for low temperature physics tests, unless the following conditions associated with that reactor are met:
a.
The spray additive tank contains not less than 2675 gal.
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of solution with a sodium hydroxide concentration of not less than 30% by weight.
b.
Two containment spray pumps are operable.
c.
Four accident fan-cooler units are operable.
d.
All valves and piping, associated with the above components and required to function during accident conditions, are
-l operable.
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2.
During power operation, the requirements of 15.3.3.B-1 may be
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modified to allow any one of the following components to be
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inoperable at any one time.
If the system is not restored to meet the requirements of 15.3.3.B-1 within the time period specified, the reactor shall be placed in the hot shutdown condition.
If the J
requirements of 15.3.3.B-1 are not 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 the cold shutdown condition.
a.
One accident fan cooler may be out of service provided that cooler-is returned to operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. The other j
accident fan coolers shall be operable before initiating maincanance on the inoperable accident fan cooler.
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i Unit 1 Amendment No. 60, 138 l
Unit 2 Amendment No. 65, 142 15.3.3-3
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1 b.
One containment spray pump may be out of service provided the pump is restored to operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
The remaining containment spray pump shall be operable before initiating maintenance on the inoperable pump.
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Unit 1 Amendment No.- g,138 I
Unit 2 Amendment No.' M.142 15.3.3-3a
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c.
Any valve required fcr the functioning of the system during accident conditions may be inoperable provided repairs are
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completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Prior tc initiating repairs, all valves in the system that provide the dtplicate function shall be operable.
(Exception: If a spray put? is removed from l
service per b above, valves associated wit 5 that train may be j
removed from service for the period specified for the pump.)
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C.
Component Cooling System Single Unit Operation
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1.
One reactor shall not be made critical unless the following condi-i tions are met:
a.
The two component cooling pumps assigned to that unit are l
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b.
Either the component cooling heat exchanger associated with the unit together with one of the shared spare heat exchangers are operable or the two shared spare heat exchangers are operable.
t c.
All valves, interlocks and piping associated with the above components, and required for the functioning of the system I
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
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hot shutdown condition.
If the requirements of 15.3.3.C-1 are not 1
i Unit 1 - Amendment No. 705.138 15.3.3-4
.l Unit 2 - Amendment.No. JOB,142 l.i
4 The operable status of the various systems and components is to be demonstrated by periodic tests, defined by Specification 15.4.5.
A large fraction of i
these tests will be performed while the reactor is operating in the power range.
If a component is found to be inoperable it will be possible in most cases to effect repairs and restore the system to full operability within a relatively short time.
For a single component to be inoperable
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does not negate the ability of the system to perform its function, but it reduces the redundancy provided.in the reactor design and thereby limits the ability to tolerate additi'nal equipment failures.
If it develops that l_
(a) the inoperable component is not repaired within the specified allowable time period or (b) a second component in the same or related system is i
found to be inoperable, the reactor will initially be put in the hot l
shutdown condition to provide for reduction of the decay heat from the fuel, and consequent reduction of cooling requirements after a postulated loss-of-coolant accident.
This will also permit improved access for repairs in some cases.
After a limited time in hot shutdown, if the malfunction (s) are not corrected, the reactor will be placed in the cold shutdown condition, utilizing normal shutdown and cooldown procedures.
In the cold shutdown condition there is no possibility of an accident that would release fission products or damage the fuel elements.
The specified repair times do not apply to regularly scheduled maintenance of j
ine engineered safety systems, which is normally to be performed during refueling shutdowns.
The limiting times to repair are based on:
1)
Assuring with high reliability that the safety system will function properly if required to do so.
I 2)
Allowances of sufficient time to effect repairs using safe and proper procedures.
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Unit 1 - Amendment No.138 Unit 2 - Amendment No.142 15.3.3-7
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