ML20211E928

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Amends 156 & 147 to Licenses NPF-10 & NPF-15,respectively, Revising TS 3.4.10, Pressurizer Safety Valves, to Increase as-found Pressurizer Safety Valve Setpoint Tolerances
ML20211E928
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 08/19/1999
From: Stephen Dembek
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20211E933 List:
References
NUDOCS 9908300180
Download: ML20211E928 (10)


Text

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UNITED STATFS g

NUCLEAR REGULATOR ( COMMISSION

't WASHINGTON, D.C. 2055 Hoot 49.....,o SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE. CAllFORNIA THE CITY OF ANAHEIM. CALIFORNIA DOCKET NO. 50-361 SAN ONOFRE NUCLEAR GENERATING STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.156 License No. NPF-10 w

1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Southem Chufomia Edison Company, et al.

(SCE or the licensee), dated September 4, 5998, as supplemented December 8, 1998, end February 16,1999, 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 mgulations 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; j

The is' uance of this amendment will not be inimical to the comn u s defense and D.

s security or to the health and safety of the public; and F..

The issuance of this amendment is in accordance with 10 CFR Part 51 of tha Commission's regulations and all applicable requirements have been satisfied.

I 9908300100 990819 DR ADOCK 050003 1

. 2. -

Accordingly, the license is amended by changes to the Technical Specifications as indicatad 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 rollows:

-(2)

Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.156

, 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 shall be implemented within 30 days of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/

to hen Dembek, Chief, Section 2 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications

.Date of Issuance: August 19, 1999 j

)

s ATTACHMENT TO LICENSE AMENDMENT NO.156 i

FACILITY OPERATING LICENSE NO. NPF-10 DOCKET NO. 50-361 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

REMOVE INSERT 3.4-28 3.4-28 3.4-29 3.4-29 l

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Pressurizer Safety Valves 3.4.10-3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.10 Pressurizer Safety Valves LC0 3.4.10 Two pressurizer safety valves shall be OPERABLE with as-found lift. settings of 2500 psia, +3% or -2%.

APPLICABILITY:

MODES 1, 2, and 3.

_________......_______-N0TE----------------------------

The lift settings are not required to be within LC0 limits during MODE 3 for the' aurpose of setting the pressurizer safety valves under am)ient (hot) conditions.

This exception is allowed for 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> following entry into MODE 3 provided a preliminary cold setting was made prior to heatup.

Each pressurizer safety valve has an as-found tolerance of

+3% or -2%.

Following testing in accordance-with

'TS 5.5.2.10, pressurizer safety valves shall be set within

  • 1% of the specified setpoint.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One pressurizer safety A.1 Restore valve to 15 minutes valve inoperable.

OPERABLE status.

I l

B.

Required Action and B.1 Be in MODE 3, 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion l

Time not met.

AND OR B.2 Be in MODE 4.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Two pressurizer safety valves inoperable.

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SAN ON0FRE--UNIT 2 3.4-28 Amendment No. 156 I

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Pressurizer Safety Valves 3.4.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 Verify ea'cn pressurizer safety valve is In accordance OPERABLE in accordance with inservice with the testing program.

Following testing as-found Inservice lif t settings shall be within +3% or -2%.

Testing Program However, pressurizer safety valves shall be set to within 11% of the specified setpoint.

s SAN ON0FRE--UNIT 2 3.4-29 Amendment No.156

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$t UNITED STATES i

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NUCLEAR REGULATORY COMMISSION g

'g WASHINGTON, D.C. 20555-0001

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SOUTHERN CAllFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE. CALIFORNIA THE CITY OF ANAHEIM. CALIFORNIA DOCKET NO. 50-362 SAN ONOFRE NUCLEAR GENERATING STATION. UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.147 License No NPF-15 l

1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Southern Califomia Edison Company, et al.

(SCE or the licensee) dated September 4,1998, as supplemented December 8, 1998, and February 16,1999, 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; l

B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; i

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.

. 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-15 is hereby amended to read as follows:

(2)

Technical Soecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.147

, are hereby incorporated in the license. Southern California Edison Company shall opcmte 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 shall be implemented within 30 days of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION I

tephen Dembek, Chief, Section 2

)

Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: August 19, 1999 l

t

I ATTACHMENT TO LICENSE AMENDMENT NO.147 FACILITY OPERATING LICENSE NO. NPF-15 DOCKET NO. 50-362 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

REMOVE INSERT 3.4-28 3.4-28 3.4-29 3.4-29 l

4 i

~

Pressurizer Safety Valves 3.4.10 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.10 Pressurizer Safety Valves LC0 3.4.10 Two pressurizer safety valves shall be OPERABLE with as found lift settings of 2500 psia, +3% or -2%.

APPLICABILITY:

MODES 1, 2, and 3.


NOTE----------------------------

The lift settings are not required to be within LC0 limits during MODE 3 for the purpose of setting the pressurizer safetyvalvesunderambient(hot) conditions.

This exc.eption is allowed for 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> following entry into MODE 3 provided a preliminary cold setting was made prior to heatup.

Each pressurizer safety valve has an as-found tolerance of

+3% or -2%.

Following testing in accordance with TS 5.5.2.10, pressurizer safety valves shall be set within 11% of the specified setpoint.

.........................................w..........--

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One pressurizer safety A.1 Restore valve to 15 minutes valve inoperable.

OPERABLE status.

B.

Required Action and B.1 Be in MODE 3.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met.

AND OR B.2 Be in MODE 4.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Two pressurizer safety valves inoperable.

SAN ON0FRE--UNIT 3-3.4-28 Amendment No. 147

f Pressurizer Safety Valves 3.4.10 l

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY l

I SR 3.4.10.1 Verify each pressurizer safety valve is In accordance OPERABLE in accordance with inservice with the testing program. Following testing as-found Inservice lift settings shall be within +3% or -2%.

Testing Program However, pressurizer safety valves shall be set to within *1% of the specified setpoint.

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SAN ON0FRE--UNIT 3 3.4-29 Amendment No. 147 s

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