NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. … · ME2134) Dear Mr. Ridenoure: The Commission...

UNITED STATES NUCLEAR REGULATORY COMMISSION

WASHINGTON, D.C. 20555-0001

June 30, 2010

Mr. Ross 1. Ridenoure Senior Vice President and Chief Nuclear Officer Southern California Edison Company San Onofre Nuclear Generating Station P.O. Box 128 San Clemente, CA 92674-0128

SUBJECT: SAN ONOFRE NUCLEAR GENERATING STATION, UNITS 2 AND 3 ISSUANCE OF AMENDMENTS REVISING TECHNICAL SPECIFICATION 3.7.5, "AUXILIARY FEEDWATER (AFW) SYSTEM" (TAC NOS. ME2133 AND ME2134)

Dear Mr. Ridenoure:

The Commission has issued the enclosed Amendment No. 223 to Facility Operating License No. NPF-10 and Amendment No. 216 to Facility Operating License No. NPF-15 for San Onofre Nuclear Generating Station (SONGS), Units 2 and 3, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated August 10, 2009.

The amendments revise Technical Specification 3.7.5, "Auxiliary Feedwater (AFW) System," to allow a 7-day Completion Time for the turbine-driven AFW pump if the inoperability occurs in MODE 3 following a refueling outage, and if MODE 2 had not been entered. This change is based on the U.S. Nuclear Regulatory Commission (NRC) approved Technical Specification Task Force (TSTF) traveler, TSTF-340, Revision 3.

A copy of our related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.

Sincerely,

&~/t 7W

o es R. Hall, Senior Project Manager lant Licensing Branch IV

Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Docket Nos. 50-361 and 50-362

Enclosures: 1. Amendment No. 223 to NPF-10 2. Amendment No. 216 to NPF-15 3. Safety Evaluation

cc w/encls: Distribution via Listserv



SOUTHERN CALIFORNIA EDISON COMPANY

SAN DIEGO GAS AND ELECTRIC COMPANY

THE CITY OF RIVERSIDE, CALIFORNIA

DOCKET NO. 50-361

SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 2

AMENDMENT TO FACILITY OPERATING LICENSE

Amendment No. 223 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 August 10, 2009, 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.

Enclosure 1

- 2

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. 223, 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 60 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

~<A~ Michael T. Markley, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment: Changes to the Facility

Operating License No. NPF-10 and Technical Specifications

Date of Issuance: June 30, 2010

ATTACHMENT TO LICENSE AMENDMENT NO. 223

FACILITY OPERATING LICENSE NO. NPF-10

DOCKET NO. 50-361

Replace the following pages of the Facility Operating License No. NPF-10 and 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.

Facility Operating License

REMOVE INSERT

3 3

Technical Specifications

REMOVE INSERT

3.7-11 3.7-11

-3

(3) SCE, pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended;

(4) SCE, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required;

(5) SCE, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and

(6) SCE, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of San Onofre Nuclear Generating Station, Units 1 and 2 and by the decommissioning of San Onofre Nuclear Generating Station Unit 1.

C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level

Southern California Edison Company (SCE) is authorized to operate the facility at reactor core power levels not in excess of full power (3438 megawatts thermal).



Amendment No. 223

AFW System3,.7.5

3.7 PLANT SYSTEMS

3.7.5 Auxiliary Feedwater (AFW) System

LCO 3.7.5 Three AFW trains shall be OPERABLE.

---------------------------NOTES--------------------------~-1. Only one AFW train~ which includes a motor driven pump,

is required to be uPERABLE in MODE 4. 2. The steam driven AFW pump is OPERABLE when running and

controlled manually to support plant start-ups, plantshut-downs, and AFW pump and valve testing.

APPLICABILITY: MODES 1, 2, and 3,MODE 4 when steam generator is relied upon for heat removal.

ACTIONS

CONDITION REQU IRED ACTI ON COMPLETION TIME

A. One steam sUPP1~ toturbine driven FW pump inoperable.

OR

-----------NOTE-----------Onl t ap~licable if MOD 2 as not been entered followingrefueling

-------------------------One turbine driven AFW ~um~ inoperable in

OD 3 followingrefueling

A.1 . Restore affected equipment to OPERABLE status.

7 days

AND

10 days from'··· discover1of failure 0 meet the LCO

.'

B. One AFW train inoperable for reasons

B.1 Restore AFW train to OPERABLE status.

72 hours

other than Condition A in MODE 1, 2, or 3.

AND

10 days from discover~ offa; lure a meet the LCO

C. Two AFW trains with two motor driven ~um~sinoperable in MOD S ,2, or 3.

C.1 Restore one AFW train to OPERABLE status.

48 hours

(continued)

SAN ONOFRE--UNIT 2 3.7-11 Amendment No. 223






DOCKET NO. 50-362

SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 3

AMENDMENT TO FACILITY OPERATING LICENSE

Amendment No. 216 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 August 10, 2009, 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.

Enclosure 2

- 2

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:


The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix S, as revised through Amendment No. 216, 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 60 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

Michael T. Markley, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment: Changes to the Facility

Operating License No. NPF-15 and Technical Specifications

Date of Issuance: June 30, 2010

ATTACHMENT TO LICENSE AMENDMENT NO. 216

FACILITY OPERATING LICENSE NO. NPF-15

DOCKET NO. 50-362

Replace the following pages of the Facility Operating License No. NPF-15 and 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.

Facility Operating License

REMOVE INSERT

3 3

Technical Specifications

REMOVE INSERT

3.7-11 3.7-11

-3

(3) SCE, pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended;

(4) SCE, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source and special nuclear materials as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required;

(5) SCE, pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and

(6) .SCE, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of San Onofre Nuclear Generating Station, Units 1 and 3 and by the decommissioning of San Onofre Nuclear Generating Station Unit 1.

C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level

Southern California Edison Company (SCE) is authorized to operate the facility at reactor core power levels not in excess of full power (3438 megawatts thermal).



Amendment No. 216

--------------------------

AFW System3.7.5

3.7 PLANT SYSTEMS

3.7.5 Auxiliary Feedwater (AFW) System

LCO 3.7.5 Three AFW trains shall be OPERABLE.

---------------------------NOTES--------------------------- 1. Only one AFW train

6 which includes a motor driven pump,

is required to be PERABLE in MODE 4. 2. The steam driven AFW pump is OPERABLE when running and

controlled manually to support plant start-ups, plantshut-downs, and AFW pump and valve testing.

APPLICABILITY: MODES I, 2. and 3. MODE 4 when steam generator is relied upon for heat removal.

ACTIONS REQUIRED ACTION COMPLETION TIMECONDITION

A.1 Restore affected 7 daysA. O~e ,steam suppll to equipment to OPERABLEturbine driven FW

pump inoperable. status. AND

OR 10 days from>' discovery of failure to meet

Onlf ap~licable if -----------NOTE----------

the LCO MOD 2 as not been entered followingrefueling

One turbine driven AFW ~um~ inoperable in

00 3 followingrefueling

B. One AFW tra"in B.1 Restore AFW train to 72 hours inoperable for reasons OPERABLE status. other than Condition A AND in MODE 1. 2. or 3.

10 days from discovery offailure to meet the LCO

C.1 Restore one AFW train 48 hours two motor driven ~um~s

C. Two AFW trains with to OPERABLE status.

inoperable in MOD S • 2. or 3.

(continued)

SAN ONOFRE--UNIT 3 3.7-11 Amendment No. 216



SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION

RELATED TO AMENDMENT NO. 223 TO FACILITY OPERATING LICENSE NO. NPF-10

AND AMENDMENT NO. 216 TO FACILITY OPERATING LICENSE NO. NPF-15




SAN ONOFRE NUCLEAR GENERATING STATION, UNITS 2 AND 3

DOCKET NOS. 50-361 AND 50-362

1.0 INTRODUCTION

By letter dated August 10, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML092230590), Southern California Edison Company (SCE, or the licensee), submitted a license amendment request for changes to the Technical Specifications (TS) for the San Onofre Nuclear Generating Station (SONGS), Units 2 and 3. The proposed TS changes would adopt Technical Specification Task Force (TSTF) Improved Standard Technical Specification Change Traveler TSTF-340, Revision 3, approved by the U.S. Nuclear Regulatory Commission (NRC) on March 16, 2000 (ADAMS Accession No. ML003694199). Specifically, the proposed amendment would revise TS 3.7.5, "Auxiliary Feedwater (AFW) System," to allow the turbine-driven auxiliary feedwater (TDAFW) pump to be inoperable for up to 7 days under certain conditions.

SONGS, Units 2 and 3, are Combustion Engineering (CE) pressurized-water reactors; thus, the applicable improved standard technical specifications (STS) for SONGS, Units 2 and 3, are provided in NUREG-1432, "Standard Technical Specifications - Combustion Engineering Plants." Consistent with TSTF-340, Revision 3, the licensee proposes to revise TS 3.7.5 by adding a provision to allow the TDAFW pump to be inoperable for up to 7 days while in MODE 3, following a refueling outage, if MODE 2 has not been entered. The purpose of the change is to allow sufficient time for repair and testing of the TDAFW pump during startup from a refueling outage, thereby reducing the number of unnecessary mode changes to complete these actions.

The NRC staff has reviewed the licensee's regulatory and technical analyses in support of the proposed license amendment. This safety evaluation supports the conclusion that: (1) there is

Enclosure 3

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reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

2.0 REGULATORY EVALUATION

The NRC staff considered the following regulatory requirements and guidance in its review of the licensee's application.

The Commission's regulatory requirements related to the content of the TS are set forth in 10 CFR 50.36. Specifically, 10 CFR 50.36(c)(2)(ii)(B) requires that limiting conditions for operation (LCOs) be established for a process variable, design feature, or operating restriction that is an initial condition of a design basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier. The NRC staff evaluated the proposed change to the current LCO for the TOAFW pump in accordance with the 50.36(c)(2)(ii)(B) requirements. In addition, the NRC staff considered the guidance in NUREG1432 on content and format of TS for CE plants in its review of the proposed TS changes.

Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Appendix A, General Oesign Criterion (GOG) 34, "Residual heat removal," and GOC 44, "Cooling water," reflect the design basis for the SONGS, Units 2 and 3 AFW systems with respect to decay heat removal. GOC 34 specifies, in part, that the "system safety function shall be to transfer fission product decay heat and other residual heat from the reactor core at a rate such that specified acceptable fuel design limits and the design conditions of the reactor coolant pressure boundary are not exceeded." GOC 44 specifies, in part, that a system shall be provided "to transfer heat from structures, systems, and components important to safety, to an ultimate heat sink."

The regulations in 10 CFR 50.63, "Loss of all alternating current power," require all licensees to assess the capability of their plants to maintain adequate core cooling and appropriate containment integrity during a station blackout (SBO) and to have procedures to cope with the event.

3.0 TECHNICAL EVALUATION

The safety-related design bases of the SONGS, Units 2 and 3 AFW systems are to supply sufficient water to the steam generators (SGs) to remove decay heat upon the loss of normal feedwater during accident conditions and normal operation. The limiting design-basis accidents and transients for the AFW system are: feedwater line break, loss of normal feedwater, and small break loss-of-coolant accident (LOCA) analysis, which considers a minimum available AFW flow. The AFW system, in conjunction with the seismic Category I condensate storage tank, provides a means of pumping sufficient feedwater to remove sufficient reactor coolant system (RCS) heat to prevent over-pressurization and opening of a pressurizer relief valve. The AFW system also provides a means to cool down the RCS at a normal rate of 75 degrees Fahrenheit CF) per hour to a temperature between 350 OF and 400 of, at which point the shutdown cooling system can operate.

The SONGS, Units 2 and 3 AFW systems provide redundant, independent, and diverse means of supplying feedwater to the SGs for cooling the RCS under emergency conditions. Each unit's

- 3

AFW system consists of two motor-driven pumps and one steam turbine-driven pump, configured into three trains. Each pump has the capability of supplying 100 percent of the feedwater requirements for safe cooldown of the RCS. Each motor-driven AFW (MDAFW) pump feeds one SG and is capable of delivering 500 gallons per minute (gpm) at an SG pressure of 1,097 pounds per square inch absolute (psia) to meet accident analysis flow requirements, and 700 gpm at an SG pressure of 890 psia to support cooldown requirements. Each MDAFW pump is powered from an independent Class 1E power supply. The TDAFW pump is identical to the MDAFW pumps, except that the TDAFW pump is driven by a steam turbine. The TDAFW pump is independent of alternating current (AC) power and can feed both SGs through direct current-powered valves.

In the event the TDAFW pump is unavailable, system redundancy is still provided by two independent, AC-powered, MDAFW pump trains, one dedicated to each SG. Each of the ACpowered trains utilizes a separate diesel generator as a backup power source. The pumps independently take suction from the condensate storage tank and each pump discharge is connected to an AFW line, which discharges to a corresponding main feedwater line and SG. Therefore, even with the TDAFW pump unavailable, the plant maintains two redundant and independent trains of AFW to meet the required safety functions for AFW for the design-basis accidents.

TSTF-340, Revision 3, builds upon the design requirements stated in the STS for CE plants, NUREG-1432. The NRC staff identified one area where the SONGS, Units 2 and 3 AFW system design differs slightly from the standard CE design plant in the STS. Although the AFW system for SONGS, Units 2 and 3 is similar to the STS AFW system in the respect that each MDAFW pump feeds one SG, the STS assume that each MDAFW pump has the capability to be re-aligned from the control room to feed the opposite train SG. For SONGS, Units 2 and 3, each of the MDAFW pumps can only be locally re-aligned to pump to the other SG.

Operator actions for the AFW system are described and credited in the Updated Final Safety Analysis Report (UFSAR) for SONGS, Units 2 and 3, for normal and emergency situations. During startup and cooldown, operators at SONGS are allowed to use the AFW pumps under manual control to supply water from the condensate storage tank to the SGs. Also, the UFSAR credits operator actions to be employed to mitigate the consequences of postulated piping failures. The feasibility of carrying out operator actions is judged on the basis of ample time, availability of necessary equipment, and adequate access to that equipment for the proposed actions. The SONGS, Units 2 and 3, AFW system design has a 4-inch cross-tie line, 140-4"inch-D-GKO, with two manual valves, 4"-634-D-GKO and 4"-635-D-087, on the MDAFW pump discharge lines that would allow operators to direct flow to the opposite SG. The ability to cross-tie the two MDAFW pumps by manually manipulating the cross-tie isolation valves is addressed in an abnormal operating procedure. Based on the system design and the existing procedure, the NRC staff considers these manual operator actions to be feasible for SONGS, Units 2 and 3. Therefore, even though the AFW system design for SONGS, Units 2 and 3 differs in this respect from the standard AFW system design for CE plants assumed in NUREG-1432, the SONGS design has an acceptable cross-tie capability that allows operators to locally re-align one MDAFW pump to provide flow to the opposite SG.

Another functional requirement of the AFW system is to supply water to the SGs in the event of an SBO scenario, when AC power is not available. The TDAFW pump performs this second function. The proposed amendment would extend the allowed outage time for the TDAFW

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pump from 72 hours to 7 days while in MODE 3. During an SBO event, the operators are assumed to follow procedures and take the appropriate steps to mitigate and recover from the accident. Plant operators would respond to an SBO event in the same manner, whether the Limiting Condition for Operation (LCO) allows the TDAFW pump to be inoperable for 72 hours or 7 days. The licensee's Individual Plant Examination of External Events report for SONGS Units 2 and 3, dated December 15, 1995 (not publicly available), submitted to NRC in response to Generic Letter 88-20, Supplement 4, "Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities," dated June 28, 1991, takes probabilistic credit for the capability of a diesel generator cross-tie to the opposite unit and specifies that the cross-tie is established to restore power to the unit experiencing an SBO in approximately 55 minutes (available mission time equal to SG dry-out time plus the time to uncover the core). This capability significantly increases the availability of on-site AC power for a single unit SBO scenario, and would enable the use of the MDAFW pumps, as necessary, if the event were to occur with the TDAFW pump inoperable.

The licensee's proposed TS changes are identical to the changes identified in TSTF-340, Revision 3 and the CE STS. Specifically, the licensee proposes to add a provision to Condition A in TS LCO 3.7.5, and to revise the wording in Required Action A.1, which currently states, "Restore steam supply to OPERABLE status," as follows (changes in bold):

CONDITION REQUIRED ACTION COMPLETION TIME

A. One steam supply to turbine drive AFW pump inoperable

A.1 Restore affected equipment to OPERABLE status.

7 days

AND

OR

- - - - - - - - NOTE - - - - - - - Only applicable if MODE 2 has not been entered following refueling

10 days from discovery of failure to meet the LCO

One turbine drive AFW pump inoperable in MODE 3 following refueling

In addition, although not within the scope of the NRC staff's review of this amendment request, the licensee proposed to make conforming changes to the TS Bases that are also identical to the corresponding changes identified in TSTF-340, Revision 3.

In summary, the NRC staff concludes that the licensee's justification for the extension of the completion time to restore the TDAFW pump to operability in MODE 3 following a refueling outage is reasonable and acceptable. This finding is based on: 1) the availability of the two redundant, 100 percent capable, MDAFW pumps, which are sufficient to mitigate the consequences of a design basis accident; 2) the low probability of occurrence of an event

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requiring the TDAFW pump during the additional time that the pump may be inoperable; and 3) the small amount of decay heat in the RCS following a refueling outage and prior to entering MODE 2.

Based on the information provided and the considerations discussed above, the NRC staff concludes that the licensee's proposed TS changes for SONGS, Units 2 and 3 are consistent with TSTF-340, Revision 3, and NUREG-1432, are in compliance with the applicable regulatory requirements, and are acceptable.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the California State official was notified of the proposed issuance of the amendments. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding published in the Federal Register on November 17, 2009 (74 FR 59263). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 FR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.

6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: S. Gardocki

Date: June 30, 2010

June 30, 2010

Mr. Ross T. Ridenoure Senior Vice President and Chief Nuclear Officer Southern California Edison Company San Onofre Nuclear Generating Station P.O. Box 128 San Clemente, CA 92674-0128

SUBJECT: SAN ONOFRE NUCLEAR GENERATING STATION, UNITS 2 AND 3 ISSUANCE OF AMENDMENTS REVISING TECHNICAL SPECIFICATION 3.7.5, "AUXILIARY FEEDWATER (AFW) SYSTEM" (TAC NOS. ME2133 AND ME2134)

Dear Mr. Ridenoure:

The Commission has issued the enclosed Amendment No. 223 to Facility Operating License No. NPF-10 and Amendment No. 216 to Facility Operating License No. NPF-15 for San Onofre Nuclear Generating Station (SONGS), Units 2 and 3, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated August 10, 2009.

The amendments revise Technical Specification 3.7.5, "Auxiliary Feedwater (AFW) System," to allow a 7-day Completion Time for the turbine-driven AFW pump if the inoperability occurs in MODE 3 following a refueling outage, and if MODE 2 had not been entered. This change is based on the U.S. Nuclear Regulatory Commission (NRC) approved Technical Specification Task Force (TSTF) traveler, TSTF-340, Revision 3.

A copy of our related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.

Sincerely,

IRA!

James R. Hall, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Docket Nos. 50-361 and 50-362

Enclosures: 1. Amendment No. 223 to NPF-10 2. Amendment No. 216 to NPF-15 3. Safety Evaluation

cc w/encls: Distribution via Listserv DISTRIBUTION: PUBLIC RidsNrrDorlDpr Resource RidsNrrLAJBurkhardt Resource LPLIV rtf RidsNrrDorlLpl4 Resource RidsOgcRp Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDssSbpb Resource RidsRgn4MailCenter Resource RidsNrrDirsltsb Resource RidsNrrPMSanOnofre Resource SGardocki, NRRtDSStSBPB ADAMS Accession No ML101320168 "concurrence via SE

OFFICE NRRlLPL4/PM NRRlLPL4/LA DSS/SBPB/BC DIRS/ITSB/BC OGC NRRlLPL4/BC NRR/LPL4/PM

NAME JRHall JBurkhardt GCasto' RElliolt LSubin NLO MMarkley JRHall

DATE 6/8/10 6/7/10 3/26/10 6/8/10 6/8/10 6/29/10 6/30/10

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