ML20091F293
| ML20091F293 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 04/08/1992 |
| From: | Samworth R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20091F294 | List: |
| References | |
| NUDOCS 9204210101 | |
| Download: ML20091F293 (7) | |
Text
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NUCLEAR REGULATORY COMMISSION
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FISCONSIN ELECTRIC POWER COMPANY DOCKET NQub0-266 POINT BEACH NUCLEM' PLAHI. UNIT NO.1 AMENDMENT TO FACILITY OPERATil4G LICENSE Amendment No. 130 License No. OPR-24 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated April 24, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
1 and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The faci: ty 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 (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 compilance with the Comission'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.
l 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-24 is hereby amended to read as follows:
B, Technical jioecifications L
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 130, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
9204210101 920408 PDR ADOCK 05000266 P
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2 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 RL'GULATORY COMMISSION
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Robert B. Samwnrtn, Sr. Project Manager Project Directorate III-3 Division of Reactor Projects Ill/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Techniral Specifications Date of issuance:
April 8, 1992 i
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WISCONSIN ELECTRIC _ P0FER COMPRtY DOCKETji0. 50-301 POINT BEACH NUCLEAR Plat [T. UNIT NO. 2 Ati[NDHENT 10 FACIUJLQITRATING LICERSI Amendment No. 134 License No. DPR-27 1,
The Nuclear bgulatory ' omission (the Commission) has found that:
A.
The application for amend. rent by Wisconsin Electric Power Company (the licensee) dated Sril 24, 1991, complies with the standards and recuirements of the Atomic Energy Act of 1954, as amended (the Act),
anc the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will aperate in conformity with the aspitcation, the provisions of the Act, and the rules and regu'ations of the Commission; C.
There is reasonable assurance (i) that the activities authorized b/
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 beer, satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this ;icense amendment, and paragraph 3.B of ~acility 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 Amendtrant No.
134, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
2 3.
This Itcense amendment is effective immediately upon issuance.
The Technical Specifications are to be implemented within 20 days from the da$e of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION A k l Y < fa - w n Y Robert B. Samworth, Sr. Project Manager Project Directorate 111-3 Division of Reactor Projects !!!/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: April 8, 1992 l
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ATTACHMENT 10 LICEt(1E_Mll@MMT N05.130 AND 134 10 FAClllTY OPEA&LWO_ LICENSE N05. UPR-24 AND QP_R-21.
00CKLI NOS. 50-266 AND 50-101 0
Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosad p'ges. The revised pages are identified by amendment number and contain marginal.ines indicating the area of change.
BLMEI 1hiERI 15.3.4-2 15.3.4-2 15.3.4-2a 15.3.4-2a ef
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3.
A minimum of 13.000 gallons of water per operating unit in the condensate storage tanks and an unlimited water supply from the lake via either leg of the plant Service Water System.
4.
System piping and valves required to function during accident 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 pC1/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 testored to meet the require-ments 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 a8 hours, the appropriate reactor (s) shall be cooled dewn 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 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 reactors shall be 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 />.
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Unit 1 - Amendment No. 16.62.91.130 15.3.4-4 Unit 2 - Amendment No. 31.fl U 134 J
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p 2.
Single Unit 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 driven auxiliary feedwater pump cannot be restored to service within that j
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 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 auxi'.iary 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 in hot shutdcwn 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 af core decay heat.
Inunediate decay heat removal requirements are nonnally 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 con-verted to st.eam by heat absorption.
Normally, the capability to return feed-water flow to the steam generators is provided by operation of tne turbine cycle feedwater system.
l The eight main steara safety valves have a total combined rated capability of i
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 conplete loss of electrical power to the station, decay heat removal would continue to be assured for each unit by the avail-c ility 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 atmospheric relief valves.
One motor-driven auxiliary feedwater pump can supply surficient feedwater for removal of decay heat _from a unit.
The minimum amount of' water in the condensate storage tanks ensures the ability to maintain each unit in a hot shutdown condition for at least one hour concurrent with a loss of all AC power.
Unit 1 - Amendment No. 26/62,91,130
.3.62a Unit 2 - Amendment No. 31.67,95.134