ML20138A825

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Amends 35 & 24 to Licenses NPF-10 & NPF-15,respectively, Modifying Tech Spec 3.2.6, Reactor Coolant Cold Leg Temp, Re Cold Leg Temp Limits at Power Levels Less than 70%
ML20138A825
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 09/25/1985
From: Knighton G
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20138A804 List:
References
TAC-57297, TAC-57298, NUDOCS 8510110094
Download: ML20138A825 (10)


Text

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j#' "*%*, UNITED STATES NUCLEAR REGULATORY COMMISSION

SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CALIFORNIA THE CITY OF ANAHEIM, CALIFORNIA 4

DOCKET NO. 50-361 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 35 License No. NPF-10

1. The Nuclear Regulatory Comission (the Comission) has found that:

A. The application for amendment to the license for San Onofre Nuclear Generating Station, Unit 2 (the facility) filed by the Southern California Edison Company on behalf of itself and San Diego Gas and Electric Com California (pany The City licensees) of Riverside dated October 11, and the City 1984, of Anaheim, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I;

8. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the 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 set forth in 10 CFR Chapter I; D. The issuance of this license amendment will not be inimical to the comon defense and security or to the health and safety of the public; 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.

8510110094 050924 PDR ADOCK 05000361 P PDR 1

2. Accordingly, the license is amended by changes to the Technical Specifications 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. 35, are hereby incorporated in the license.

4 SCE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3. This amendment is effective immediately and is to be fully implemented within 30 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION George W ' nighton, f Licensi 'g Branch N  ;

Division of Licensing

Attachment:

Changes to the Tecnnical Specifications Date of Issuance: September 25, 1985 l

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September 25, 1985 ATTACHMENT TO LICENSE AMENDMENT NO. 35 FACILITY OPERATING LICENSE NO. NPF-10 DOCKET NO. 50-361 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. Also to be replaced are the following overleaf pages to the amended pages.

Amendment Pages Overleaf Pages 3/4 2-10 3/4 2-9

POWER DISTRIBUTION LIMITS 3/4.2.5 RCS FLOW RATE LIMITING CONDITION FOR OPERATION 3.2.5 The actual Reactor Coolant System total flow rate shall be or equal to 148 x 106 lbm/hr, and less than or equal to 177.6 x 10 greater lbm/hr. than APPLICABILITY: MODE 1.

ACTION:

WiththeactuaiReactorCoolantSystemtotalflowratedeterminedtobeoutside the above limits, reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.2.5 Trie actual Reactor Coolant System total flow rate shall be determined to be within its limit at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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SAN ONOFRE-UNIT 2 3/4 2-9 L

POWER DISTRIBUTION LIMITS I

REACTOR COOLANT COLD LEG TEMPERATURE LIMITING CONDITION FOR OPERATION 3.2.6 The Reactor Coolant Cold Leg Temperature (Tc) shall be maintained within:

a) 535*F < Tc < 558*F for less than or equal to 70% of RATED THERMAL

~

POWER ~

b) 544*F $ Tc $ 558*F for greater than 70% RATED THERMAL POWER.

APPLICABILITY: MODE 1 above 30% of RATED THERMAL POWER.

ACTION:

With the Reactor Coolant Cold Leg Temperature exceeding its limit, restore the temperature to within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less than 30% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.2.6 The Reactor Coolant Cold Leg Temperature shall be determined to be within its limit at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SAN ONOFRE-UNIT 2 3/4 2-10 AMENDMENT NO. 35

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-' UNITED STATES NUCLEAR REGULATORY COMMISSION h

j WASHINGTON, D, C. 20555 e

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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 ON0FRE NUCLEAR GENERATING STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 24 License No. NPF-15

1. The Nuclear Regulatory Comission (the Commission) has found that:

A. The application for amendment to the license for San Onofre Nuclear Generating Station, Unit 3 (the facility) filed by the Southern California Edison Company on behalf of itself and San Diego Gas and Electric Company, The City of Riverside and the City of Anaheim, California (licensees), dated October 11, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the 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 set forth in 10 CFR Chapter I; D. The issuance of this license amendment will not be inimical to the comon defense and security or to the health and safety of the public; 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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- 2-1 l 2. Accordingly, the license is amended by changes to the Technical i Specifications 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 The Technical Specifications contained in Appendix A and the i

Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 24, are hereby incorporated in the license.

i SCE shall operate the facility in accordance with the Technical

( Specifications and the Environmental Protection Plan.

3. This amendment is effective immediately and is to be fully implemented
within 30 days of the date of issuance.

! FOR THE NUCLEAR REGULATORY COMMISSION l

i l George / nighton, ief .

i Licer. sing Branch No. 3 l j Division of Licensing l

Attachment:

}

Changes to the Technical l Specifications 4

Date of Issuance: September 25, 1985 i

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September 25, 1985 ATTACHMENT TO LICENSE AMENDMENT NO. 24 FACILITY OPERATING LICENSE NO. NPF-15 DOCKET NO. 50-362 Replace the following pages of the Appendix A' Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. Also to be replaced are the following overleaf pages to the amended pages.

Amendment Pages Overleaf Pages 3/4 2-10 3/4 2-9

d POWER DISTRIBUTION LIMITS

( / 3/4.2.5 RCS FLOW RATE LIMITING CONDITION FOR OPERATION 3.2.5 The actual Reactor Coolant System total flow rate shall be greater than or equal to 148 x 108 lbm/hr, and less than or equal to 177.6 x 106 lbm/hr.

APPLICABILITY: MODE 1.

ACTION:

With the actual Reactor Coolant System total flow rate determined to be outside the above Ilmits, reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.2.5 The actual Reactor Coolant System total flow rate shall be determined to be within its limit at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, k

4 I

1 SAN ONOFRE-UNIT 3 3/4 2-9 1

[ POWER DISTRIBUTION LIMITS q REACTOR COOLANT COLD LEG TEMPERATURE

! LIMITING CONDITION FOR OPERATION 3.2.6 The Reactor Coolant Cold Leg Temperature (Tc) shall be maintained within:

a) 535*F $ Tc $ 558*F for less than or equal to 70% of RATED THERMAL POWER b) 544*F $ Tc 1558*F for greater than 70% RATED THERMAL POWER.

APPLICABILITY: MODE 1 above 30% of RATED THERMAL POWER.

ACTION:

With the Reactor Coolant Cold Leg Temperature exceeding its limit, restore the temperatur9 to within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less than 30% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SURVEILLANCE RE0VIREMENTS 4.2.6 The Reactor Coolant Cold Leg Temperature shall be determined to be within its limit at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

4 SAN ONOFRE-UNIT 3 3/4 2-10 AMEN 0 MENT NO. 24