ML20207S208
| ML20207S208 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 03/03/1987 |
| From: | Colburn T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20207S209 | List: |
| References | |
| NUDOCS 8703190127 | |
| Download: ML20207S208 (10) | |
Text
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UNITED STATES g
NUCLEAR REGULATORY COMMISSION 5
- j WASHINGTON, D. C. 20555
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WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT, UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.106 License No. DPR-24 1.
The Nuclear Regulatory Comission (the Comission) has found that:
e A.
The application for amendment by Wisconsin Electric Power Company (thelicensee)datedAugust 26, 1986 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 Comiss'on'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 f
E.
The issuance of this amendment is in accordance with 10 CFR Part j
51 of the Comission's regulations and all applicable requirements have been satisfied.
i C703190127 870303 PDR ADOCK 05000266 P
PDR u
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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-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.106, 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
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jOW b Y%w Timothy G. y lburn, Project Manager Co PWR Project Directorate #1 Division of PWR Licensing-A
Attachment:
Changes to the Technical Specifications Date of Issuance: March 3, 1987 l
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pe ur,[g UNITED STATES
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NUCLEAR REGULATORY COMMISSION L
j WASHINGTON, D. C. 20555
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WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 109 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 26, 1986 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 (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 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 have been satisfied.
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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 Specifications contained in Appendices A and B, as revised through Amendment No.109, 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 v
f N hy h 0 bhu w Timothy G. Colburn, Project Manager PWR Project Directorate #1 Division of PWR Licensing-A
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 3, 1987 l
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ATTACHMENT TO XICENSE AMENDMENT N05.106 AND 109 c,
TO FACILITY OPERATING LICENSE NOS. DPR-24 AND DPR-27 DOCKET NOS. 50-266 AND 50-301 Revise Appendix A Technical Specifications b removing the pages identified below and inserting the enclosed pages. Th'e revised pages are identified by the captioned amendment number and centain marginal lines indicating the area of change.
REMOVE INSERT TABLE 15.4.1-2 TABLE 15.4.1-2 page 15.4.7-1 page 15.4.7-1 6-
f.
TABLE 15.4.1-2 MINIMUM FREQUENCIES FOR EQUIPMENT AND SAMPLING TEST Test Frequency 1.
Reactor Coolant Samples Gross Beta-gamma 5/ week (7) activity (excluding tritium)
Tritium activity Monthly Radiochemical E Semiannually (2)(11)
Determination Isotopic Analysis for Every two weeks (I)
Dose Equivalent I-131 Concentration Isotopic Analysis for a) Once per 4 Iodine including I-131, hours whenever I-133, and I-135 the specific activity exceeds 1.0 pCi/ gram Dose Equivalent pCi/ gram,g/E I-131 or b) One sample be-tween 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following a thermal power change exceeding 15% of rated power in a one-hour period.
Chloride Concentration 5/ week (8)
Diss. Oxygen Conc.
5/ week (6)
Fluoride Conc.
Weekly 2.
Reactor Coolant Boron Boron Concentration Twice/ week IO) 3.
Refueling Water Storage Boron Concentration Weekly Tank Water Sample 4.
Boric Acid Tanks Boron Concentration Twice/ week I
j, 5.
Spray Additive Tank Na0H Concentration Monthly 6.
Accumulator Boron Concentration Monthly 7.
Spent Fuel Pit Boron Concentration Monthly Unit 1 - Amendment No. AB, n',, 106 Unit 2 - Amendment No. 23, 7F 10'9 Page 1 of 4
TABLE 15.4.1-2 (Continued) t Test Frequency Gross Beta gamma Activity Weekly (0) 8.,
Secondary Coolant or gamma isotopic analysis Iodine concentration Weekly when gross Beta gamma activity equalsoreggjeds 1.2 pCi/cc 9.
Control Rods Rod drop times of all Each refueling or full length rods (8) after maintenance that could affect proper functioning (4)
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10.
Control Rod Partial movement of Every 2 weeks all rods
)
11.
Pressurizer Safety Valves Set point Every five years Every five years (12) l
- 12. Main steam Safety Valves Set Point
- 13. Containment Isolation Trip Functioning Each refueling shutdown
- 14. Refueling System Interlocks Functioning Each refueling shutdown 15.
Service Water System Functioning Each refueling shutdown Monthly (0)
- 16. Primary System Leakage Evaluate
- 17. Diesel Fuel Supply Fuel inventory Daily Monthly (
I
- 18. Turbine Stop and Governor Functioning Valves
- 19. LowPressureTurbg Visual and magnetic Every five years Rotor Inspection particle or liquid penetrant 20.
Boric Acid System Storage Tank Daily i
Temperature 21.
Boric Acid System Visual observation Daily of piping temperatures (all > 145'F) f 22.
Boric Acid Piping Heat Electrical circuit Monthly Tracing operability 23.
PORV Block Valves Complete Valve Cycle Quarterly ( }
Unit 1 - Amendment No. 64, $5, 77, 53, /$5, 106 Unit 2 - Amendment No. $9s 7@o 76r $7s J@Jo 109 Page 2 of 4
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TABLE 15.4.1-2 (Continued)
Test Frequency 24.
Integrity of Post Accident Evaluate Each refueling cycle Recovery Systa-s 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 6
functions.
27.
Reactor Trip Bypass Breakers
- a. Verify operability Prior to of the undervoltage breaker use i
trip function.
- b. Verify operability Each refueling of the shunt trip shutdown functions.
- c. Verify operability Each refueling of the manual trip ahutdown to undervoltage trip 3
functions.
(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 primary coolant gross radioactivity of a filtered esaple increases by more than >10pci/cc.
(3) Drop test shall be conducted at rated reactor coolant flow. Rods shall be 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.
(6) Not required during periods of refueling shutdown.
(7) At least once per week during periods of refueling shutdown.
(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 ataples) 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 EFFD and 20 days power operation 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, j
Unit 1 - mmenament No. $A, 65, 7J, 33,100/, los Unit 2 - Amendment No. 69.-79, 76, 87. 107, lospage 3 of 4
f.
TABLE 15.4.1-2 (Continued)
An approximately equal number of valves shall be tested each refueling outage 12) such that all valves will be tested within a five year period.
If any valve -
fails its test, an additional. number of valves equal to the number originally tested shall be tested.
If any of the additional tested valves fail, all remaining valves shall be tested.
6-l Page 4 of 4 Unit 1 Amendment No. 106 Unit 2 - Amendment No. 109
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15.4.7 MAIN STEAM STOP VALVES Applicability Applies to periodic testing of the main steam stop valves.
Objective To verffy the ability of the main steam stop valves to close upon signal.
Specification The main steam stop valves shall be tested under icw flow conditions during
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reactor shutdowns for major fuel reloading. Closure time of five seconds or less shall be verified. The five seconds shall be measured from the time of signal initiation until the valve disc is brought to a halt by the dashpot.
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Basis t
The main steam stop valves serve to limit an excessive reactor coolant system cooldown rate and resultant reactivity insertion following a main steam break incident. Their ability to close upon signal should be verified at each scheduled refueling shutdown. A closure time of five seconds was selected as being consistent with the expected response time for instrumentation as detailed l
in the steam line break incident analysis. The test procedure need not require steam to be flowing in the pipe. Static conditions are acceptable. The presence of flowing steam or a pressure difference will seat the valve tight.
References l
l FSAR - Section 10.4 FSAR - Section 14.2.5 Unit 1-Amendment No. 106 Unit 2-Amendment No. 109 15.4.7-1
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