ML20206N059
| ML20206N059 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 06/17/1986 |
| From: | Colburn T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20206N064 | List: |
| References | |
| TAC-53186, TAC-53187, NUDOCS 8607010365 | |
| Download: ML20206N059 (9) | |
Text
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'o UNITED STATES 8"
o NUCLEAR REGULATORY COMMISSION e E WASHINGTON, D. C. 20555 g
/
WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT, UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 100 License No. DPR-24 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated August 8, 1985 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 4
have been satisfied.
8607010365 860617 PDR ADOCK 05000266 P
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, as revised through Amendment No. 100, 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 Timothy G. Tolburn, Project Manager PWR Project Directorate #1 Division of PWR Licensing-A
Attachment:
Changes to the Technical Specifications Date of Issuance: June 17, 1986.
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UNITED STATES 8 *'
NUCLEAR REGULATORY COMMISSION o
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- , a WASHINGTON, D. C. 20555 49*
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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. 103 s
License No. DPR-27 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated August 8, 1985 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.
Thereisreasonableassurance(i)thattheactivitiesauthorized 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 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.
i 1
_ l 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attach. ment to this license amendment, and paragraph 3.B of Facility Operating License No.
DPR-27 is hereby amended to read as followsr.
B.
Technical Specificatio_ns The Technical Specifications containad in Appendices A and B 3 as revised through Amendment No.103, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effe'etive 20 driys from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION M
^
Timothy G. Colburn, Project Manager PWR Project Directorate #1 Division of PWR Licensing-A
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 17, 1986.
W
.~.
ATTACHMENT TO LICENSE AMENDMENT NOS. 100 AND 103 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 below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain narginal lines indicating the area of change.
REMOVE INSERT Table 15.4.1-2 page 2 of 3 Table 15.4.1-2 page 2 of 3 Table 15.4.1-2 page 3 of 3 Table 15.4.1-2 page 3 of 3 15.6.8-3 15.6.8-3 15.6.9-5 15.6.9-5 O
TABLE 15.4.1-2 (Continued)
Test Frecuency 9.
Control Rods Rod drop times of all Each refueling or full length rods (3) after maintenance that could affect proper functioning (4) 10.
Control Rod Partial movement of Every 2 weeks (0) all rods 11.
Pressurizer Safety Valves Set point Each refueling shutdown 12.
Main Steam Safety Valves Set point Each refueling shutdown 13.
Containment Isolation Trip '*-
Functioning Each refueling shutdown 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.
Turbine Stop and Covernor Functioning Monthly (6)(10)
Valves 0,
19.
Low Pressure Turbine Visual and magnetic Every five years Rotor Inspection (5) particle or liquid penetrant 20.
Boric Acid System Storage Tank temperature Daily 21.
Boric Acid System Visual observation of Daily piping temperatures (all > 145'F) 22.
Boric Acid Piping Heat Tracing Electrical c1rcuit Monthly operability 23.
PORV Block Valves Complete Valve Cycle Quarterly (6)
Unit 1 - Amendment No. 64, f),fi, S3, 100 Unrt 2 - Amendment No. if, 70,16. 87, 103 page 2 of 3
t j
TABLE 15.4.1-2 (Continued)
Test Frequency 24.
Integrity of Post Accident Evaluate Each refueling cycle Recovery Systems Outside Containment 25.
Containment Purge Supply Verify valves are Monthly (9) and Exhaust Isolation Valves locked closed
- 26. Reactor Trip Breakers
- a. Verify independent Monthly (9) operability of automatic shunt and undervoltage trip functions.
- b. Verify independent Each refueling operability of man-shutdown ual trip to shunt and undervoltage trip functions.
27.
Reactor Trip Bypass Breakers
- a. Verify operability Prior to of the undervoltage breaker use trip function.
- b. Verify operability Each refueling of the shunt trip shutdown functions.
- c. Verify operability Each refueling of the manual trip shutdown j
to undervoltage trip i
functions.
I (1) Required only during periods of power operation.
(2) E determination will be started when the gross activity analysis of a filtered sample indicates >10pci/cc and will be redetermined if the g
primary coolant gross radioactivity of a filtered sample increases by more than >10pCi/ce, g
i (3) Drop test shall be conducted at rated reactor coolant flow. Rods shall be i
dropped under both cold and hot condition, but cold drop tests need not be 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.
(8) At leaht 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.
(9) Not required during periods of cold or refueling shutdown.
(10) During end-of-cycle period of operation when boron concentration is less than 100 ppa, this test may be waived due to operational limitations.
(11) Sample to be taken after a minimum of 2 EFPD and 20 days power operation j
since the reactor was last suberitical for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or longer.
t Unit 1 - amenament No. 6A, 65, 71, 83,100 Unit 2 - Amendment No. 69,-70, 76, 87, 103 page 3 of 3
15.6.8 PLANT OPERATING PROCEDURES (Continued) 15.6.8.4 The following programs shall be established, implemented, and maintained.
A.
Post-Accident Sampling
- A program **which will ensure the capability to obtain and analyze reactor coolant, containment atmosphere, and in-plant gaseous effluent samples under accident conditions. The program shall include the following:
(1)
Training of personnel; (ii) Procedures of sampling and analysis; and (iii) Provisions for maintenance of sampling and and analysis equipment.
t
- Post-Accident Coolant Sampling and Post-Accident Containment Atmospheric Sampling Systems.
- It is acceptable if the licensee maintains details of the program in plant operation manuals.
4 Unit 1 Amendment No. 92, 100 15.6.8-3 Unit 2 Amendment No. 96,103
.I E.
Failure of Containment High-Range Radiation Monitor A minimum of two in-containment radiation-level monitors with 8
7 a maximum range of 10 rad /hr (10 /hr for photons only) should l
l be operable at all times except for cold shutdown and refueling j
outages.
This is specified in Table 15.3.5-5, item 7.
If the minimum number of operable channels are not restored to operable condition within seven days after failure, a special report shall be submitted to the NRC within thirty days following the event outlining the action taken, the cause of the inoperability I
and the plans and scheduld for restoring the system to operable status.
F.
Failure of Main Steam Line Radiation Monitors If a main steam line radiation monitor (SA-11) fails and cannot be restored to operability in seven days, prepare a special report outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the channel to operable status within thirty days of the event.
l I
j l
l t
Unit 1 - Amendment No. 77, 92, 97, 100 Unit 2 - Amendment No. 76, 96, J0J, 103 15-6.9-5
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