ML20073J021
| ML20073J021 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 09/27/1994 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20073J024 | List: |
| References | |
| NUDOCS 9410060176 | |
| Download: ML20073J021 (8) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION
- (s WASHINGTON D C. 20555-4001 SOUTHERN CALIFORNIA EDIS0N COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY r
THE CITY OF RIVERSIDE. CALIFORNIA 5
THE CITY OF ANAHEIM. CALIFORNIA DOCKET NO. 50-361 SAN ON0FRE NUCLEAR GENERATING STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.112 License No. NPF-10 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Southern California Edison Company, et al. (SCE or the licensee) dated October 29, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 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; 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.
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9410060176 940927 PDR ADOCK 05000361 P
. 2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-10 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.112, are hereby incorporated in the license. Southern California Edison Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance and must be fully implemented no later than 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION beh*dl.
M.
Theodore R. Quay, Director Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
Septenber 27, 1994
o i
ATTACHMENT TO LICENSE AMENDMENT 1
AMENDMENT NO.112 TO FACILITY OPERATING LICENSE NO. NPF-10 DOCKET NO. 50-361 i
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 marginal lines indicating the areas I
of change. The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE INSERT 3/4 5-2 3/4 5-2 i
L P
1 i
)
3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 SAFETY INJECTION TANKS LIMITING CONDITION FOR OPERATION 3.5.1 Each reactor coolant system safety injection tank shall be OPERABLE with:
a.
The isolation valve open and power to the valve removed, b.
A contained borated water volume of between 1680 and 1807 cubic
- feet, c.
Between 1850 and 2800 ppm of boron, and d.
A nitrogen cover-pressure of between 615 and 655 psia.
APPLICABILITY: MODES 1, 2 and 3.*
ACTION:
a.
With one safety injection tank inoperable, except as a result of a closed isolation valve, restore the inoperable tank to OPERABLE status within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With one safety injection tank inoperable due to the isolation valve being closed, either immediately open the isolation valve or be in at least HOT STANDBY within one hour and 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 />.
SURVEILLANCE REOUIREMENTS 4.5.1 Each safety injection tank shall be demonstrated OPERABLE:
a.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by:
1.
Verifying that the contained borated water volume and nitrogen cover-pressure in the tanks is within the above limits, and 2.
Verifying that each safety injection tank isolation valve is open.
- With pressurizer pressure greater than or equal to 715 psia.
SAN ONOFRE - UNIT 2 3/4 5-1 AMENDMENT NO. 64 Correction Letter of 10-4-88 j
i
EMERGENCY CORE COOLING SYSTEMS SURVElllANCE RE0VIREMENTS b.
At least once per 31 days and within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after each solution volume increase of greater than or equal to 1% of tank volume by verifying the boron concentration of the safety injection tank solution.
c.
At least once per 31 days by verifying either the disconnect switch is in the open position or the fuses are removed for each safety injection tank vent valve.
d.
At least once per 31 days when the RCS pressure is above 715 psia, by verifying that the isolation valve operator breakers are padlocked in the open position.
At least once per refueling interval by verifying that each safety e.
injection tank isolation valve opens automatically under each of the following conditions:
1.
Before an actual or simulated RCS pressure signal exceeds 715 psia, and 2.
Upon receipt of an SIAS test signal.
SAN ONOFRE - UNIT 2 3/4 5-2 AMENDMENT NO. 73, 112
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e UNITED STATES NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 20555-0001 SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE. CALIFORNIA THE CITY OF ANAHEIM. CALIFORNIA DOCKET NO. 50-362 SAN ONOFRE NVCLEAR GENERATING STATION. UNIT N0. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 101 License No. NPF-15 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Southern California Edison Company, et al. (SCE or the licensee) dated October 29, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 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; 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 baen satisfied.
. 2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-15 is hereby amended to read as follows:
(2)
Technical Specifications i
The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.101, are hereby incorporated in the license.
Southern California Edison Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
i 3.
This license amendment is effective as of the date of its issuance and must be fullr implemented no later than 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION frL E W h-
, Q Theodore R. Quay, Director Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical 1
Specifications Date of Issuance: September 27, 1994
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 101 TO FACILITY OPERATING LICENSE N0. NPF-15 DOCKET NO. 50-362 Revise Appendix A Technical Specifications by removing the pages identified i
below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness.
l REMOVE INSERT 3/4 5-2 3/4 5-2 t
i I
I i
I
a-1
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3/4.5 EMERGENCY CORE COOLING SYSTEMS I
3/4.5.1 SAFETY INJECTION TA!LS i
LIMITING CONDITION FOR OPERATION 3.5.1 Each reactor coolant system safety injection tank shall be OPERABLE with:
l a.
The isolation valve open and power to the valve removed.
b.
A contained borated water volume of between 1680 and 1807 cubic i
feet.
i c.
Between 1850 and 2800 ppm of boron, and d.
A nitroger, cover-pressure of between 615 and 655 psia.
i i
APPLICABILITY: MODES 1, 2 and 3.*
I ACTION:
a.
With one safety injection tank inoperable, except as a result of a closed isolation valve, restore the inoperable tank to OPERABLE status within one hour or be in at least HOT STANDBY within the i
next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
i b.
With one safety injection tank inoperable due to the isolation valve being closed, either immediately open the isolation valve or be in at least HOT STANDBY within one hour and 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 />.
SURVEILLANCE REQUIREMENTS t
4.5.1 Each safety injection tank shall be demonstrated OPERABLE:
a.-
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by:
1.
Verifying that the contained borated water volume and nitrogen cover-pressure in the tanks is within the above limits, and i
2.
Verifying that each safety injection tank isolation valve is f
open.
- With pressurizer pressure greater than or equal to 715 psia.
t SAN ON0FRE - UNIT 3 3/4 5-1 AMENDMENT NO. 53 Correction Letter of 10-4-88
EMERGENCY CORE COOLING SYSTEMS SURVElllANCE RE0VIREMENTS b.
At least once per 31 days and within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after each solution volume increase of greater than or equal to 1% of tank volume by verifying the boron concentration of the safety injection tank solution.
c.
At least once per 31 days by verifying either the disconnect switch is in the open position or the fuses are removed for each safety injection tank vent valve.
d.
At least once per 31 days when the RCS pressure is above 715 psia, by verifying that the isolation valve operator breakers are padlocked in the open position.
e.
At least once per refueling interval by verifying that each safety injection tank isolation valve opens automatically under each of the following conditions:
1.
Before an actual or simulated RCS pressure signal exceeds 715 psia, and 2.
Upon receipt of an SIAS test signal.
i l
l 1
i SAN ON0FRE - UNIT 3 3/4 5-2 AMENDMENT N0. 101