ML20062G684
| ML20062G684 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 07/27/1982 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20062G685 | List: |
| References | |
| TAC-48373, TAC-48374, NUDOCS 8208130132 | |
| Download: ML20062G684 (8) | |
Text
8
'o UNITED STATES g
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.y WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 62 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 April 27, 1982, as supplemented June 30,1982, 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; i
B. 'The facility will operate in confonnity 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; l
and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements l
have been satisfied.
1 DESIGNAIED ORIGINAL Cortified By
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8208130132 820727 PDR ADOCK 05000266 P
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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 0
5 No. DPR-24 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 62, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective 60 days from the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 27, 1932 i
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27 WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 67 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 April 27, 1982, as supplemented June 30,1982, complies with the standards and requirements of the Atomic Er.ergy 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, l
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 ufety cf 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 s,ecurity 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.
LESIG:' TED ORIGINAL Cortified 3
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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-27 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specification's contained in Appendices A and B, as revised through Amendment No. 67, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective 60 days from the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION obert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: July 27, 1982 O
e M
e ATTACHENT TO LICENSE AENDENTS i,___.
AENDENT. NO. 62 TO FACILITY CPERATING LICENSE NO. OPR-24 ___
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- E AENDENT NO. 67 TO FACILITY OPERATING LICENSE NO. OPR-27
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. g j DOCKET NOS. 50-266 AND 50-301 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area.of change.
Remove
- Insert 15.3.471 15.3.4-1 15.3.4-2 15.3.4-2 15.3.4-2a 15.3.4-2a
- Changes on the revised TS pages do not become effective until 60 days after the date of issuance.
In the interim, the existing TS pages are in effect and should be retained.
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15.3.4 STEAM AND POWER CONVERSION SYSTEM
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Applicability Applies to the operating status of steam and power conversion system.
Obiective To. define conditions of the steam and power conversion system steam-relieving capacity. Auxiliary Feedwater System and Service Water. System operation is necessary to ensure the espability to remove decay heat from the core.
Specification A.
When the reactor coolant is heated above 350*F the reactor shall not be taken critical unless the following conditions are met:
1.
A minimum steam-relieving capability of eight (8) main steam safety valves available, except for low power physics testing.
2.
Auxiliary Feedwater System a.
Two Onit Operation
- All four auxiliary feedwater pumps together with their associated flow paths and essential instrumentation shall be operable.
b.
Single Unit Operation - Both motor driven auxiliary feedwater pumps and the turbine driven auxiliary feedwater pump associated with that unit together with their associated flow paths and essential instrumenta-tion shall be operable.
s Unit 1 - Amendment No. 62 Unit 2 - Amendment No. 67 15.3.4-1 p
's 3.-
A minimum of 10,000 gallons of water per operating unit in
-the condensate storage tanks and an unlimited water supply from
.a the lake via either leg of the plant Service Water System.
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4.
System piping and valves required to function during accident
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conditions directly associated with the above components operable.
B.
The iodine-131 activity on-the secondary side of the steam generator shall not exceed 1.2 pCi/cc.
C.
During power operation the requirements of 15.3.4.A.2.a and b may be modified to allow the following components to be inoperable for a specified time.
If the system is not restored to meet the requirements of 15.3.4.A.2.a and b within the time period specified, the specified action must be taken.
If the requirements of 15.3.4.A.2.a and b 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 appropriate reactor (s) shall be cooled down to less than 350*F.
1.
Two Unit Operation - One of the four operable auxiliary feedwater pumps may be out-of-service for the below specified times.
A turbine driven auxiliary feedwater pump may be out of service for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
If the turbine driven auxiliary feedwater pump cannot be restored to service within the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> time period the associated reactor shall be shut down and in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. A motor driven auxiliary feedwater pump may be out of service for up to 7 days.
If the inoperable motor driven auxiliary feedwater pump cannot be restored to service within the 7 day time period both of the reactora shall be shut down and in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Unit 1 - Amendment No. 26, 62 Unit 2 - Amendment No. 31, 67 15.3.4-2 l
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2.
Single Unic Operation - The turbine driven auxiliary feedwater pump may be out-of-service for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
If the turbine 2f driven auxiliary feedwater pump cannot be restored to service within that 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> time period, the reactor shall be shut down and in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Either one of the two motor driven auxiliary feedwater pumps may be out-of-service for up to 7 days.
If the motor driven auxiliary feedwater pump cannot be restored to service within that 7 day period the operating unit shall be shut down and in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Basis A reactor shutdown from power requires removal of core decay heat.
Immediate decay heat removal requirements are normally satisfied by the steam by pass to the condenser.
Therefore, core decay heat can be continuously dissipated via the steam bypass to the condenser as feedwater in the steam generator is converted to steam by heat absorption.
Normally, the capability to return feedwater flow to the steam generators is provided by operation of the turbine cycle feedwater system.
The eight main steam safety valves have a total combined rated capability of 6,664,000 lbs/hr.
The total full power steam flow is 6,620,000 lbs/hr, therefore eight (8) main steam safety valves will be able to relieve the total full-power steam flow if necessary.
In the unlikely event of complete loss of electrical power to the station, decay heat removal would continue to be assured for each unit by the availability of either the steam-driven auxiliary feedwater pump or one of the two motor-driven auxiliary steam' generator feedwater pumps, and steam discharge to the atmosphere via the main steam safety valves or ttmospheric relief valves.
One motor-driven auxiliary feedwater pump can supply snfficient feedwater for removal of decay heat from a unit.
The minimum amount of water in the condensate storage tanks is the amount needed for 25 minutes of operation / unit, which allows sufficient time for operator action.
An unlimited supply is available from the lake via either leg of the plant service water system for an indefinite time period.
Unit 1 - Amend' ment No. 26, 62
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Unit 2 - Amendment No. 31, 67 15.3.4-2a
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