ML20052A208
| ML20052A208 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 03/26/1982 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20052A209 | List: |
| References | |
| TAC-48064, NUDOCS 8204280008 | |
| Download: ML20052A208 (4) | |
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'A UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D. C. 20555 g
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WISCONSIN ELECTRIC POWER COMPANY g
DOCKET NO. 50-301 a
POINT BEACH NUCLEAR PLANT, UNIT NO. 2
.1 AMENDMENT TO FACILITY OPERATING t.ICENSE
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Amendment No. 63 License No. OPR-27
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1.
The Nuclear Regulatorj Commission (the Commission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated March 4,1982, complies with the stindards 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;
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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 amendmerit can be conducted without endangering the health
.2 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;
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and I
E.
The issuance 'of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements
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2.
Accordingly, the license is amended by changes to the Technical
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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 Specifications contained in Appendices A and B, as revised Ohrough Amendment No. 63, are
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hereby incorporated in the license. The licensee shall l
operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the dr.te of its issuance.
.l FOR THE NUCLEAR REGULATORY COMMISSION
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Robert A. Clark, Chief
,j Operating Reactors Branch #3 Division of Licensing j
Attachment-Changes to the Technical Specifications
-; l Date of Issuance:
March 26, 1982 c
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,ATTACHENT TO LICENSE AENDENT
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AENDENT NO. 63 TO FACILITY OPERATING LICENSE NO. DPR-27 DOCKET NO. 50-301 Revise Appendix A as.follows:-.....
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Table 15.4.1-2 (continued)
Table 15.4.1-2 (continued) e 8-14 l
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t TABLE.15.4.1-2 *(CONTINUED)
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Test Frequency
. 14.
. Refueling System Interlocks Functioning Each refueling shutdown 15.
Service Water System Functioning Each refueling shutdown 16, Primary System Leakage Evaluate Monthly (6) 17.
Diesel Fuel Supply Fuel inventory Daily 18.
Tuzhine Stop and Functioning Monthly (6) (9) l
Governor Valves 19.
Low Pressure Turbine Visual and magnetic Every five years Rotor' Inspection (5) particle or liquid penetrant 20.
Boric Acid System Storage Tank Daily Temperature 21.
Boric Acid System Visual observation Daily of piping temperatures (all 3,145'F) 22.
Boric Acid Piping Heat Electrical circuit Monthly Tracing operability 4
23.
PORV Block Valves Complete Valve Cycle Quarterly (6) 24.
Integrity of Post Accident Evaluate Yearly Recovery Systems Outside Containment J:
(1)
A radiochemical analysis for this purpose shall consist of a quantative measure-i ment. of each radionuclide with half life of >30 minutes such that at least 95%
of total activity of primary coolant is accounted for.
l (2)
E determination will be started when the gross activity analysis of a filtered sample indicates 3,10 pc/cc and will be redetermined if.the primary coolant gross radioactivity of a filtered sample increases by more than 10 uc/ce.
(3)
Drop tests shall be conducted at rated reactor coolant flow. Rods shall be dropped under both cold and hot conditions, but cold drop tests need not be n
timed.
(4)
Drop tests will be conducted in the hot condition for rods on which maintenance was performed.
-(5) '
As accessible without disassembly of rotor.
l (6)
Not required during periods of refueling shutdown.
(7)
At least once per week during periods of refueling shutdown.
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(8)
At least three times per week (with maximum time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> between samples) during periods of refueling shutdown.
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(9)
Effective in March 1982, the time limit for completing the monthly functional test for Poinc Beach Unit 2 is extended until the start of the eighth refueling outage.
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Unit 1-Amendment No. 32, #5, 55 Unit 2-Amendment No. 50, 53, 6G, 63
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