SOUTHERN CALIFORNIA I. EDISON · EDISON Vice President & Chief Nuclear Officer An ED/SON INTERNA.TIONAL.® Company March 18, 2015 10 CFR 50.90 U. S. Nuclear Regulatory Commission

SOUTHERN CALIFORNIA Thomas I. Palmisano

EDISON Vice President & Chief Nuclear Officer

An ED/SON INTERNA.TIONAL.® Company March 18, 2015 10 CFR 50.90

U. S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, D.C. 20555-0001

Subject: Docket Nos. 50-361 and 50-362Supplement 4 to Amendment Applications 266 and 251Permanently Defueled Technical SpecificationsSan Onofre Nuclear Generating Station, Units 2 and 3

References: 1) Letter from T. J. Palmisano (SCE) to Document Control Desk (NRC)dated March 21, 2014; Subject: Docket Nos. 50-361 and 50-362,Amendment Applications 266 and 251, Permanently DefueledTechnical Specifications, San Onofre Nuclear Generating Station,Units 2 and 3 (ADAMS Accession No. ML14085A141)

2) Letter from T. J. Palmisano (SCE) to Document Control Desk (NRC)dated October 1, 2014; Subject: Docket Nos. 50-361 and 50-362,Supplement 1 to Amendment Applications 266 and 251, PermanentlyDefueled Technical Specifications, San Onofre Nuclear GeneratingStation, Units 2 and 3 (ADAMS Accession No. ML14280A264)

3) Letter from T. J. Palmisano (SCE) to Document Control Desk (NRC)dated February 23, 2015; Subject: Docket Nos. 50-361 and 50-362,Response to a Request for Additional Information and Supplement 2to Amendment Applications 266 and 251, Permanently DefueledTechnical Specifications, San Onofre Nuclear Generating Station,Units 2 and 3 (ADAMS Accession No. ML15058A030)

4) Letter from T. J. Palmisano (SCE) to Document Control Desk (NRC)dated February 25, 2015; Subject: Docket Nos. 50-361 and 50-362,Response to a Request for Additional Information and Supplement 3,Amendment Applications 266 and 251, Permanently DefueledTechnical Specifications, San Onofre Nuclear Generating Station,Units 2 and 3 (ADAMS Accession No. ML15058A033)

5) Letter from T. J. Wengert (NRC) to T. J. Palmisano (SCE) datedSeptember 30, 2015; Subject: San Onofre Nuclear GeneratingStation, Units 2 and 3 - Issuance of Amendments RegardingChanges to the Administrative Controls Section of the TechnicalSpecifications (TAC Nos. MF2954 and MF2955)

Dear Sir or Madam:

By letter dated March 21, 2014 (Reference 1), as supplemented by letters datedOctober 1, 2014 (Reference 2), February 23, 2015 (Reference 3), and February 25,

P.O. Box 128San Clemente, CA 92672(949) 368-6575 PAX 86575Fax: (949) [email protected]

Document Control Desk -2- March 18, 2015

2015 (Reference 4), Southern California Edison (SCE) submitted a License AmendmentRequest (LAR), consisting of Amendment Application Nos. 266 and 251, to FacilityOperating License Numbers NPF-10 and NPF-15 for San Onofre Nuclear GeneratingStation (SONGS), Units 2 and 3, respectively. The LAR proposed to revise theOperating License and the associated Technical Specifications (TS) to reflect thepermanent cessation of reactor operation for SONGS Units 2 and 3.

The SCE request included changes to the NRC findings in the Operating Licenses forUnits 2 and 3. In addition, SCE proposed changes to certain Operating Licenseprovisions to remove reference to "use" of the facility. Upon further review, SCE hasconcluded that these changes are not necessary to reflect permanent cessation ofoperations. Supplement 4 to Reference 1, provided as an Enclosure to this letter,withdraws the proposed changes described above.

Enclosure 2 to this letter provides clean-typed pages for the proposed PermanentlyDefueled Technical Specifications. The clean-typed pages reflect the changes asproposed by Reference 1 and supplemented by References 2, 3, and 4. In addition,Sections 5.1, 5.2, and 5.3 of the clean-typed pages are updated to reflect changes asapproved by License Amendments 227 and 220 for Units 2 and 3, respectively(Reference 5).

This supplement does not affect the conclusions of the No Significant Hazards

Consideration or the Environmental Consideration provided in Reference 1.

There are no new regulatory commitments in this letter or the Enclosure to this letter.

If you have any questions or require any additional information, please contact Ms. AndreaSterdis at (949) 368-9985.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on(ýDate)

Sincerely,

Enclosures: 1. Supplement 4, Permanently Defueled Technical Specifications2. Permanently Defueled Technical Specifications - Clean Typed Pages

cc: M. L. Dapas, Regional Administrator, NRC Region IVT. J. Wengert, NRC Licensing Project Manager, SONGS Units 2 & 3R. L. Kellar, NRC Region IV, Branch Chief, Repository Spent Fuel SafetyS. Y. Hsu, California Department of Public Health, Radiologic Health Branch

ENCLOSURE 1

SUPPLEMENT 4

PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS

SAN ONOFRE UNITS 2 AND 3

Supplement 4

Permanently Defueled Technical Specifications

Background

By letter dated March 21, 2014, Southern California Edison (SCE) submitted a LicenseAmendment Request (LAR) to reflect permanent cessation of operations for the SanOnofre Nuclear Generating Station (SONGS) Units 2 and 3. As part of that LAR, SCEproposed changes to several provisions of the SONGS Units 2 and 3 Operating Licenses,including the initial NRC findings and other license provisions that referred to "use" of thefacility. After further review, SCE has concluded that these changes are not necessaryto reflect permanent cessation of operations. This Supplement 4 to the March 21, 2014LAR withdraws those changes, as specifically described below.

SONGS Unit 2 License Changes

Initial Proposed Change to Unit 2 Paragraphs 1 .B and 1 .J

In the March 21, 2014 LAR, SCE proposed changes to paragraphs 1..B and 1.J of the Unit2 Operating License as follows:

License Condition 1.B

B. Construction Of the- S-an Onofre Nuclear Generating Station, Unit 2 (hfacility), har, been substantially completed in coenformity with ConStructionPermiwt No. CPPR 97 and the application as amended, the prE6oviSio f theAct, and the regulations of the Commission;

This section is proposed for deletion in its entirety. Decommissioning of SONGSUnit 2 is not dependent on the regulations that governed construction of the facility.

This paragraph will read as follows:

B. Deleted;

License Condition 1.J

J. The r•ceipt, posss.sIon and-e of. SoGUre, bypredUct, and special nucleafmaterial as autheozed by this licenise will be in accordance with theGOM.ommsOn'S regulatons in 10 (J1-1 Parts 30, 40 and 7 U.

This section is proposed for deletion in its entirety. The Commission's findingregarding possession and use of byproduct, source, and special nuclear materialfor operating SONGS Unit 2 is not dependent on decommissioning of the facility.Additionally, possession and use of byproduct, source, and special nuclearmaterial at SONGS Unit 2 during decommissioning activities is covered by LicenseCondition 2.B, which will remain in effect. Therefore, License Condition 1.J is notneeded.

1


J. Deleted.

Supplement 4 changes to Paragraphs 1 .B and 1 .J

Because paragraphs 1 .B and 1 .J represent NRC findings in support of initial issuance ofthe license, they are historical in nature and need not be deleted to reflect permanentcessation of operations. This supplement withdraws the proposed changes toparagraphs 1..B and 1.J described above.

Initial Proposed Change to Unit 2 Paragraph 2.B.(2)

In the March 21, 2014 LAR, SCE proposed changes to paragraph 2.B.(2) of the Unit 2Operating License, as follows:

License Condition 2.B.(2)

(2) Southern California Edison Company (SCE), pursuant to Section 103 of theAct and 10 CFR Part 50, "Domestic Licensing of Production and UtilizationFacilities", to possess, use, and operate the facility at the designated locationin San Diego County, California, in accordance with the procedures andlimitations set forth in this license;

The language regarding use and operation is proposed for deletion. The licenseno longer authorizes use and operation of the facility.


(2) Southern California Edison Company (SCE), pursuant to Section 103 of theAct and 10 CFR Part 50, "Domestic Licensing of Production and UtilizationFacilities", to possess the facility at the designated location in San DiegoCounty, California, in accordance with the procedures and limitations set forthin this license;

Supplement 4 changes to Unit 2 Paragraph 2.B.(2)

SCE has re-considered this proposed language. Submittal of the certifications ofpermanent cessation of operations and permanent removal of fuel prohibit SCE fromoperating the reactor or emplacing or retaining fuel in the reactor vessel. It is thereforeappropriate to strike reference of "operation" of the facility from the operating license.SCE will continue, however, to "use" the facility for safe storage of spent fuel. SCE isrevising the proposed language as part of this supplement to retain the word "use."

The supplemented paragraph will read as follows:

(2) Southern California Edison Company (SCE), pursuant to Section 103 of theAct and 10 CFR Part 50, "Domestic Licensing of Production and UtilizationFacilities", to possess and use the facility at the designated location in SanDiego County, California, in accordance with the procedures and limitationsset forth in this license;

2

Unit 3 License Chanqes

Initial Proposed Change to Unit 3 Paragraphs 1 .B and 1.1

In the March 21, 2014 LAR, SCE proposed changes to paragraphs 1 .B and 1.1 of the Unit 3Operating License as follows:

License Condition 1.B

B. Cosrcto f th~e S-an Onofre Nuclear Generating Station, Unit 3 (hfacility), has been substantially completed in con9fomity with CostructionPermit No. CPPR 98 and the application as amended, the provisin sOftAct, and the regulationoftheCommiro; of the

This section is proposed for deletion in its entirety. Decommissioning of SONGSUnit 3 is not dependent on the regulations that governed construction of the facility.


B. Deleted;

License Condition 1.1

1. The receipt, possessin, and ue Of sourc~e, byproduc~t, and special nuc~learmateri al as a-uthorized by this license will be in accordance -with the

Comm ..is.ion's regulations in 10 C..F.R Pa.ts 30, 40 and 70.

This section is proposed for deletion in its entirety. The Commission's findingregarding possession and use of byproduct, source, and special nuclear materialfor operating SONGS Unit 3 is not dependent on decommissioning of the facility.Additionally, possession and use of byproduct, source, and special nuclearmaterial at SONGS Unit 3 during decommissioning activities is covered by LicenseCondition 2.B, which will remain in effect. Therefore, License Condition 1.1 is notneeded.


1. Deleted.

Supplement 4 changes to Unit 3 Paragraphs 1 .B and 1.1

Because paragraphs 1..B and 1.1 represent NRC findings in support of initial issuance ofthe license, they are historical in nature and need not be deleted to reflect permanentcessation of operations. This supplement withdraws the proposed changes toparagraphs 1..B and 1.1 described above.

3

Initial Proposed Change to Unit 3 Paragraph 2.B.(2)

In the March 21, 2014 LAR, SCE proposed changes to paragraph 2.B.(2) of the Unit 3Operating License, as follows:

License Condition 2.B.(2)

(2) Southern California Edison Company (SCE), pursuant to Section 103 of the Actand 10 CFR Part 50, "Domestic Licensing of Production and UtilizationFacilities", to possess, us~e, and operate the facility at the designated location inSan Diego County, California, in accordance with the procedures andlimitations set forth in this license-.,

The language regarding use and operation is proposed for deletion. The license nolonger authorizes use and operation of the facility.


(2) Southern California Edison Company (SCE), pursuant to Section 103 of the Actand 10 CFR Part 50, "Domestic Licensing of Production and UtilizationFacilities", to possess the facility at the designated location in San DiegoCounty, California, in accordance with the procedures and limitations set forthin this license;

Supplement 4 changes to Unit 3 Paragraph 2.B.(2)

SCE has re-considered this proposed language. Submittal of the certifications ofpermanent cessation of operations and permanent removal of fuel prohibit SCE fromoperating the reactor or emplacing or retaining fuel in the reactor vessel. It is thereforeappropriate to strike reference of "operation" of the facility from the operating license.SCE will continue, however, to "use" the facility for safe storage of spent fuel. SCE isrevising the proposed language as part of this supplement to retain the word "use."

The supplemented paragraph will read as follows:

(2) Southern California Edison Company (SCE), pursuant to Section 103 of theAct and 10 CFR Part 50, "Domestic Licensing of Production and UtilizationFacilities", to possess and use the facility at the designated location in SanDiego County, California, in accordance with the procedures and limitationsset forth in this license.

4

ENCLOSURE 2

PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS

CLEAN-TYPED PAGES

Definitions1.1

1.0 USE AND APPLICATION

1.1 Definitions

------------------------- NOTE - ----------------- -----------------The defined terms of this section appear in capitalized type and are applicable throughout theseTechnical Specifications and Bases.

Term Definition

ACTIONS

CERTIFIED FUEL HANDLER

OPERABLE - OPERABILITY

ACTIONS shall be that part of a Specification that prescribesRequired Actions to be taken under designated Conditionswithin specified Completion Times.

A CERTIFIED FUEL HANDLER is an individual who complieswith provisions of the CERTIFIED FUEL HANDLER trainingprogram required by TS 5.3.2.

A system, subsystem, train, component, or device shall beOPERABLE when it is capable of performing its specifiedsafety function(s) and when all necessary attendantinstrumentation, controls, normal or emergency electricalpower, cooling and seal water, lubrication, and other auxiliaryequipment that are required for the system, subsystem, train,component, or device to perform its specified safety function(s)are also capable of performing their related supportfunction(s).

Unit 2 - Amendment XXXUnit 3 - Amendment XXXSan Onofre - Draft 1.1-1

Logical Connectors1.2


1.2 Logical Connectors

PURPOSE The purpose of this section is to explain the meaning of logicalconnectors.

Logical connectors are used in Technical Specifications (TS) todiscriminate between, and yet connect, discrete Conditions, RequiredActions, Completion Times, Surveillances, and Frequencies. The onlylogical connectors that appear in TS are AND and OR. The physicalarrangement of these connectors constitutes logical conventions withspecific meanings.

BACKGROUND Several levels of logic may be used to state Required Actions. Theselevels are identified by the placement (or nesting) of the logicalconnectors and by the number assigned to each Required Action. Thefirst level of logic is identified by the first digit of the number assigned to aRequired Action and the placement of the logical connector in the firstlevel of nesting (i.e., left justified with the number of the Required Action).The successive levels of logic are identified by additional digits of theRequired Action number and by successive indentions of the logicalconnectors.

When logical connectors are used to state a Condition, Completion Time,Surveillance, or Frequency, only the first level of logic is used, and thelogical connector is left justified with the statement of the Condition,Completion Time, Surveillance, or Frequency.

EXAMPLE The following example illustrates the use of logical connectors.

EXAMPLE 1.2-1

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. LCO not met. A.1 Verify...

AND

A.2 Restore...

In this example the logical connector AND is used to indicate that when inCondition A, both Required Actions A.1 and A.2 must be completed.


Completion Times1.3


1.3 Completion Times

PURPOSE The purpose of this section is to establish the Completion Timeconvention and to provide guidance for its use.

BACKGROUND Limiting Conditions for Operation (LCOs) specify minimum requirementsfor ensuring safe storage of fuel assemblies. The ACTIONS associatedwith an LCO state Conditions that typically describe the ways in which therequirements of the LCO can fail to be met. Specified with each statedCondition are Required Action(s) and Completion Time(s).

DESCRIPTION The Completion Time is the amount of time allowed for completing aRequired Action. It is referenced to the time of discovery of a situation(e.g., inoperable equipment or variable not within limits) that requiresentering an ACTIONS Condition unless otherwise specified, providing thefacility is in a specified condition stated in the Applicability of the LCO.Required Actions must be completed prior to the expiration of thespecified Completion Time. An ACTIONS Condition remains in effect andthe Required Actions apply until the Condition no longer exists or thefacility is not within the LCO Applicability.

EXAMPLE The following example illustrates the use of Completion Times.

EXAMPLE 1.3-1

ACTIONS


B. Required B.1 Verify ... 6 hoursAction andassociated ANDCompletionTime not met. B.2 Restore... 36 hours

Condition B has two Required Actions. Each Required Action has its ownseparate Completion Time. Each Completion Time is referenced to thetime that Condition B is entered.

The Required Actions of Condition B are to perform the verification within6 hours AND perform the restoration within 36 hours. A total of 6 hours isallowed for performing the verification and a total of 36 hours (not42 hours) is allowed performing the restoration from the time thatCondition B was entered. If verification is performed within 3 hours, the


Completion Times1.3

1.3 Completion Times

EXAMPLE (continued)

time allowed for performing the restoration is the next 33 hours becausethe total time allowed performing the restoration is 36 hours.

IMMEDIATE When "Immediately" is used as a Completion Time, the Required ActionCOMPLETION should be pursued without delay and in a controlled manner.TIME


Frequency1.4


1.4 Frequency

PURPOSE The purpose of this section is to define the proper use and application ofFrequency requirements.

DESCRIPTION Each Surveillance Requirement (SR) has a specified Frequency in whichthe Surveillance must be met in order to meet the associated LCO. Anunderstanding of the correct application of the specified Frequency isnecessary for compliance with the SR.

The "specified Frequency" is referred to throughout this section and eachof the Specifications of Section 3.0, Surveillance Requirement (SR)Applicability. The "specified Frequency" consists of the requirements ofthe Frequency column of each SR, as well as certain Notes in theSurveillance column that modify performance requirements.

EXAMPLES The following examples illustrate the various ways that Frequencies arespecified. In these examples, the Applicability of the LCO (LCO notshown) occurs whenever any fuel assembly is stored in the fuel storagepool.

EXAMPLE 1.4-1

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

Verify... 7 days

Example 1.4-1 contains the type of SR most often encountered in theTechnical Specifications (TS). The Frequency specifies an interval(7 days) during which the associated Surveillance must be performed atleast one time. Performance of the Surveillance initiates the subsequentinterval. Although the Frequency is stated as 7 days, an extension of thetime interval to 1.25 times the stated Frequency is allowed by SR 3.0.2 foroperational flexibility. The measurement of this interval continues at alltimes, even when the SR is not required to be met per SR 3.0.1 (such aswhen the equipment is inoperable, a variable is outside specified limits, orthe facility is outside the Applicability of the LCO). If the interval specifiedby SR 3.0.2 is exceeded while the facility is in a specified condition in theApplicability of the LCO, then SR 3.0.3 becomes applicable.


Frequency1.4

1.4 Frequency

EXAMPLES (continued)

If the interval as specified by SR 3.0.2 is exceeded while the facility is notin a specified condition in the Applicability of the LCO for whichperformance of the SR is required, the Surveillance must be performedwithin the Frequency requirements of SR 3.0.2 prior to entry into thespecified condition. Failure to do so would result in a violation ofSR 3.0.4.

EXAMPLE 1.4-2



Verify... Prior to moving afuel assembly...

Example 1.4-2 illustrates a one time performance Frequency.

This type of Frequency does not qualify for the 25% extension allowed bySR 3.0.2.

San Onofre - Draft 1.4-2Unit 2 - Amendment XXXUnit 3 - Amendment XXX

LCO Applicability3.0

3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY

LCO 3.0.1 LCOs shall be met during the specified conditions in the Applicability,except as provided in LCO 3.0.2.

LCO 3.0.2 Upon discovery of a failure to meet an LCO, the Required Actions of theassociated Conditions shall be met.

If the LCO is met or is no longer applicable prior to expiration of thespecified Completion Time(s), completion of the Required Action(s) is notrequired, unless otherwise stated.


SR Applicability3.0

3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY

SR 3.0.1 SRs shall be met during the specified conditions in the Applicability forindividual LCOs, unless otherwise stated in the SR. Failure to meet aSurveillance, whether such failure is experienced during the performanceof the Surveillance or between performances of the Surveillance, shall befailure to meet the LCO. Failure to perform a Surveillance within thespecified Frequency shall be failure to meet the LCO except as providedin SR 3.0.3. Surveillances do not have to be performed on inoperableequipment or variables outside specified limits.

SR 3.0.2 The specified Frequency for each SR is met if the Surveillance isperformed within 1.25 times the interval specified in the Frequency, asmeasured from the previous performance or as measured from the time aspecified condition of the Frequency is met.

SR 3.0.3 If it is discovered that a Surveillance was not performed within itsspecified Frequency, then compliance with the requirement to declare theLCO not met may be delayed, from the time of discovery, up to 24 hoursor up to the limit of the specified Frequency, whichever is greater. Thisdelay period is permitted to allow performance of the Surveillance. A riskevaluation shall be performed for any Surveillance delayed greater than24 hours and the risk impact shall be managed.

If the Surveillance is not performed within the delay period, the LCO mustimmediately be declared not met, and the applicable Condition(s) must beentered. The Completion Times of the Required Actions beginimmediately upon expiration of the delay period.

When the Surveillance is performed within the delay period and theSurveillance is not met, the LCO must immediately be declared not met,and the applicable Condition(s) must be entered. The Completion Timesof the Required Actions begin immediately upon failure to meet theSurveillance.

SR 3.0.4 Entry into a specified condition in the Applicability of an LCO shall not bemade unless the LCO's Surveillances have been met within theirspecified Frequency. This provision shall not prevent entry into specifiedconditions in the Applicability that are required to comply with ACTIONS.


Fuel Storage Pool Water Level3.1.1

3.1 PLANT SYSTEMS

3.1.1 Fuel Storage Pool Water Level

LCO 3.1.1 The fuel storage pool water level shall be >_ 23 ft over the top of irradiatedfuel assemblies seated in the storage racks.

APPLICABILITY: During movement of fuel assemblies in the fuel storage pool.

ACTIONS


A. Fuel storage pool water A.1 Suspend movement of fuel Immediatelylevel not within limit, assemblies in fuel storage

pool.



SR 3.1.1.1 Verify the fuel storage pool water level is >_ 23 ft 7 daysabove the top of irradiated fuel assemblies seated inthe storage racks.

Unit 2 - Amendment XXXUnit 3 - Amendment XXXSan Onofre - Draft 3.1.1 -1

Fuel Storage Pool Boron Concentration3.1.2

3.1 PLANT SYSTEMS

3.1.2 Fuel Storage Pool Boron Concentration

LCO 3.1.2

APPLICABILITY:

The fuel storage pool boron concentration shall be _> 2000 ppm.

When any fuel assembly is stored in the fuel storage pool.

ACTIONS


A. Fuel storage pool boron A.1 Suspend movement of fuel Immediatelyconcentration not within assemblies in the fuellimit. storage pool.

AND

A.2 Initiate action to restore fuel Immediatelystorage pool boronconcentration to within limit.



SR 3.1.2.1 Verify the fuel storage pool boron concentration is 7 dayswithin limit.

Unit 2 - Amendment XXXUnit 3 - Amendment XXXSan Onofre - Draft 3.1.2-1

Spent Fuel Assembly Storage3.1.3

3.1 PLANT SYSTEMS

3.1.3 Spent Fuel Assembly Storage

LCO 3.1.3 The combination of initial enrichment and burnup of each SONGS 2 and 3spent fuel assembly stored in Region 1 shall be within the acceptableburnup domain of Figure 3.1.3-1 or Figure 3.1.3-2 or in accordance withTechnical Specification 4.3.1.1.

The combination of initial enrichment and burnup of each SONGS 2 and 3spent fuel assembly stored in Region II shall be within the acceptableburnup domain of Figure 3.1.3-3 or Figure 3.1.3-4, or in accordance withTechnical Specification 4.3.1.1.

Each SONGS 1 uranium dioxide spent fuel assembly stored in Region IIshall be stored in accordance with Technical Specification 4.3.1.1.

Whenever any fuel assembly is stored in of the fuel storage pool.APPLICABILITY:

ACTIONS


A. Requirements of the A.1 Initiate action to bring the ImmediatelyLCO not met. noncomplying fuel

assembly into compliance.



SR 3.1.3.1 Verify by administrative means the initial Prior to moving aenrichment, burnup, and cooling time of the fuel fuel assembly toassembly are in accordance with LCO 3.1.3, or any spent fuelDesign Features 4.3.1.1, or Licensee Controlled pool storageSpecification (LCS) 4.0.100. Rev 2, dated 09/27/07. location

Unit 2 - Amendment XXXUnit 3 - Amendment XXXSan Onofre - Draft 3.1.3-1


FIGURE 3.1.3-1

MINIMUM BURNUP AND COOLING TIME VS. INITIAL ENRICHMENTFOR

UNRESTRICTED PLACEMENT OF SONGS 2 AND 3 FUELIN

REGION I RACKS

25

20

CLa.

- 15

E 10

LL 5

0 -

2.0 2.5 3.0 3.5 4.0 4.5

Initial U-235 Enrichment (w/o)

5.0

E3 0 Years - 5 Years - 10 Years-2- 15 Years---- 20 Years

Unit 2 - Amendment XXXSan Onofre - Draft 3.1.3-2 Unit 3 - Amendment XXX


FIGURE 3.1.3-2


PLACEMENT OF SONGS 2 AND 3 FUEL IN PERIPHERAL POOL LOCATIONSIN

REGION I RACKS

15

C-910

0.

0)U) 5

L-

0

03.0 3.5 4.0 4.5


5.0

- 0 Years - 5 Years I-v 10 Years--•.- 15 Years-s-- 20 Years



FIGURE 3.1.3-3


UNRESTRICTED PLACEMENT OF SONGS 2 AND 3 FUELIN

REGION II RACKS

60

CL

E

~20

01 3

InitIal U-235 Enrichment (wlo)

S-0-- Years -- 5Years Oi 10Years Y 15Years F 20Years



FIGURE 3.1.3-4


PLACEMENT OF SONGS 2 AND 3 FUEL IN PERIPHERAL POOL LOCATIONSIN

REGION II RACKS

40

30

Ew. 20

.EE

UL. !

015 -1.5 2 2.5 3 3.5 4 4.5 5


E9 0Years R 5-Years ) 1P-10Years --- 15Years - 20Years


Design Features4.0

4.0 DESIGN FEATURES

4.1 Site Location

4.1.1 Exclusion Area Boundary

The exclusion area boundary shall be as shown in Figure 4.1-1.

4.1.2 Low Population Zone (LPZ)

The LPZ shall be as shown in Figure 4.1-2.

4.2 Deleted.


Design Features4.0

0,

CA , 1 1

- 3.ftS .

/

20 0 40 SooN

Figure 4.1-1 (page 1 of 1)Exclusion Area Boundary

Unit 2 - Amendment XXXA A n-9 Unit 3 - Amendment XXXSan Onofre - Lrart • -it o •h.# L.

Design Features4.0

Figure 4.1-2 (page 1 of 1)Low Population Zone


Design Features4.0

4.0 DESIGN FEATURES

4.3 Fuel Storage

4.3.1 Criticality

4.3.1.1 The spent fuel storage racks are designed and shall be maintainedwith:

a. Fuel assemblies having a maximum U-235 enrichment of4.8 weight percent;

b. Keff < 1.0 if fully flooded with unborated water, which includes anallowance for uncertainties as described in Section 9.1 of theUFSAR;

c. Keff < 0.95 if fully flooded with water borated to 1700 ppm, whichincludes an allowance for uncertainties as described in Section9.1 of the UFSAR;

d. Three or five borated stainless steel guide tube inserts (GT-Insert)may be used. When three borated stainless steel guide tubeinserts are used, they will installed in an assembly's center guidetube, the guide tube associated with the serial number, and thediagonally opposite guide tube. Fuel containing GT-Inserts maybe placed in Region I or Region I1. However, credit for GT-Insertsis only taken for Region II storage.

A five-finger CEA may be installed in an assembly. Fuelcontaining a five-finger CEA may be placed in either Region I orRegion II. Credit for inserted 5-finger CEAs is taken for bothRegion I and Region I1.

e. A nominal 8.85 inch center to center distance between fuelassemblies placed in Region II;

f. A nominal 10.40 inch center to center distance between fuelassemblies placed in Region I;

g. Prior to using the storage criteria of LCO 3.1.3 and LCS 4.0.100,the following uncertainties will be applied:

(1) The calculated discharge burnup of San Onofre Units 2 and3 assemblies will be reduced by 6.6%.

(2) The calculated discharge burnup of San Onofre Unit 1 fuelassemblies will be reduced by 10.0%.

Unit 2 - Amendment XXXSan Onofre - Draft 4.0-4 Unit 3 - Amendment XXX

Design Features4.0

4.0 DESIGN FEATURES

4.3 Fuel Storage (continued)

h. Units 2 and 3 fuel assemblies with a burnup in the "acceptablerange" of Figure 3.1.3-1 are allowed unrestricted storage inRegion I;

i. Units 2 and 3 fuel assemblies with a burnup in the "acceptablerange" of Figure 3.1.3-2 are allowed unrestricted storage in theperipheral pool locations with 1 or 2 faces toward the spent fuelpool walls of Region I;

j. Units 2 and 3 fuel assemblies with a burnup in the "acceptablerange" of Figure 3.1.3-3 are allowed unrestricted storage inRegion II;

k. Units 2 and 3 fuel assemblies with a burnup in the "acceptablerange" of Figure 3.1.3-4 are allowed unrestricted storage in theperipheral pool locations with 1 or 2 faces toward the spent fuelpool walls of Region II;

1. Units 2 and 3 fuel assemblies with a burnup in the "unacceptablerange" of Figure 3.1.3-1, Figure 3.1.3-2, Figure 3.1.3-3, andFigure 3.1.3-4 will be stored in compliance with LicenseeControlled Specification 4.0.100 Rev. 2, dated 9/27/07; and

m. Each SONGS 1 uranium dioxide spent fuel assembly stored inRegion II shall be stored in accordance with Licensee ControlledSpecification 4.0.100 Rev. 2, dated 9/27/07.

4.3.2 Drainage

The spent fuel storage pool is designed and shall be maintained to preventinadvertent draining of the pool below Technical Specification 3.1.1 value (23 feetabove the top of irradiated fuel assemblies seated in the storage racks).

4.3.3 Capacity

The spent fuel storage pool is designed and shall be maintained with a storagecapacity limited to no more than 1542 fuel assemblies.


Responsibility5.1

5.0 ADMINISTRATIVE CONTROLS

5.1 Responsibility

5.1.1 The corporate officer with direct responsibility for the plant shall be responsiblefor overall management of the San Onofre Nuclear Generating Station, and allsite support functions. He shall delegate in writing the succession to thisresponsibility during his absence.

5.1.2 The Shift Manager shall be responsible for the ultimate command decisionauthority for all unit activities which affect the safety of the plant, site personnel,and/or the general public.



5.2 Organization

5.2.1 Onsite and Offsite Organizations

Onsite and offsite organizations shall be established for plant operation andcorporate management, respectively. The onsite and offsite organizations shallinclude the positions for activities affecting the safety of the nuclear fuel.

a. Lines of authority, responsibility, and communication shall be establishedand defined throughout highest management levels through intermediatelevels to and including all operating organization positions. Theserelationships shall be documented and updated, as appropriate, in the formof organization charts, functional descriptions of departmentalresponsibilities and relationships, and job descriptions for key personnelpositions, or in equivalent forms of documentation. These relationships,including the plant-specific titles of those personnel fulfilling theresponsibilities of the positions delineated in these TechnicalSpecifications, as documented in the UFSAR.

b. The corporate officer with direct responsibility for the plant shall beresponsible for overall safe handling and storage of nuclear fuel and shallhave control over those onsite activities necessary for safe handling andstorage of the nuclear fuel.

c. A specified corporate officer (or officers) shall have corporate responsibilityfor overall plant nuclear safety and shall take any measures needed toensure acceptable performance of the staff in operating, maintaining, andproviding technical support to the plant to ensure safe management ofnuclear fuel.

d. The individuals who train CERTIFIED FUEL HANDLERS, and those whocarry out radiation protection and quality assurance functions may report tothe appropriate onsite manager; however, they shall have sufficientorganizational freedom to ensure their ability to perform their assignedfunctions.

5.2.2 FACILITY STAFF

The facility staff organization shall include the following:

a. Each on duty shift shall be composed of at least the minimum shift crewcomposition shown in Table 5.2.2-1;

b. At least one person qualified as Emergency Coordinator/EmergencyDirector shall be in the Control Room when nuclear fuel is stored in thespent fuel pools.


Organization5.2

5.2 Organization

5.2.2 FACILITY STAFF (continued)

c. Shift crew composition may be less than the minimum requirement of Table5.2.2-1 for a period of time not to exceed 2 hours in order to accommodateunexpected absence of on-duty shift crew members provided immediateaction is taken to restore the shift crew composition to within the minimumrequirements.

d. Oversight of fuel handling operations shall be provided by a CERTIFIED

FUEL HANDLER.

e. The Shift Manager shall be a CERTIFIED FUEL HANDLER.

f. An individual qualified in radiation protection procedures shall be on siteduring fuel handling operations or movement of loads over the storageracks containing fuel.


Organization5.2

5.2 Organization

Table 5.2.2-1Minimum Shift Crew Composition

POSITION MINIMUM STAFFING

CERTIFIED FUEL HANDLER 1*

Certified Operator 1

Note: The Certified Operator position may be filled by a CERTIFIED FUEL HANDLER.* May be shared between Units 2 and 3.


Unit Staff Qualifications5.3


5.3 Facility Staff Qualifications

5.3.1 Each member of the facility staff shall meet or exceed the minimum qualificationsof ANSI N18.1-1971 for comparable positions, except: a) the radiation protectionmanager who shall meet or exceed the qualifications of Regulatory Guide 1.8,September 1975; and b) multi-discipline supervisors who shall meet or exceedthe qualifications listed below.

a. Education: Minimum of a high school diploma or equivalent.

b. Experience: Minimum of four years of related technical experience whichshall include three years power plant experience of which one year is at anuclear plant.

c. Training: Complete the multi-discipline supervisor training program.

An NRC approved training and retraining program for the CERTIFIED FUELHANDLERS shall be maintained.

5.3.2


TS Bases Control5.4


5.4 Technical Specifications (TS) Bases Control

5.4.1 Changes to the Bases of the TS shall be made under appropriate administrativecontrols.

5.4.2 Changes to the Bases may be made without prior NRC approval provided thechanges do not require either of the following:

a. A change in the TS incorporated in the license; or

b. A change to the updated UFSAR or Bases that requires NRC approvalpursuant to 10 CFR 50.59.

5.4.3 The Bases Control Program shall contain provisions to ensure that the Bases aremaintained consistent with the UFSAR.

5.4.4 Proposed changes that meet the criteria of (a) or (b) above shall be reviewed andapproved by the NRC prior to implementation. Changes to the Basesimplemented without prior NRC approval shall be provided to the NRC every24 months.


Procedures, Programs, and Manuals5.5


5.5 Procedures, Programs, and Manuals

5.5.1 Procedures

5.5.1.1 Scope

Written procedures shall be established, implemented, and maintained coveringthe following activities:

a. The applicable procedures recommended in Regulatory guide 1.33,Revision 2, Appendix A, February 1978;

b. Deleted.

c. Quality assurance for effluent and environmental monitoring using theguidance in Regulatory Guide 4.15, Revision 1, 1979;

d. Fire Protection Program implementation; and

e. Programs, as specified in Specification 5.5.2.

5.5.2. Programs and Manuals

The following programs and manuals shall be established, implemented, andmaintained.

5.5.2.1 Offsite Dose Calculation Manual (ODCM)

a. The ODCM shall contain the methodology and parameters used in thecalculation of offsite doses resulting from radioactive gaseous and liquideffluents, in the calculation of gaseous and liquid effluent monitoring alarmand trip setpoints, and in the conduct of the Radiological EnvironmentalMonitoring Program;

b. The ODCM shall also contain the Radioactive Effluent Controls required bySpecification 5.5.2.3 and Radiological Environmental Monitoring programsrequired by LCS, and descriptions of the information that should beincluded in the Annual Radiological Environmental Operating Report andthe Radioactive Effluent Release Report required by Specification 5.7.1.2and Specification 5.7.1.3.

5.5.2.1.1 Licensee-initiated changes to the ODCM:

a. Shall be documented and records of reviews performed shall be retained.This documentation shall contain:



5.5 Procedures, Programs, and Manuals (continued)

5.5.2.1.1 Licensee-initiated changes to the ODCM (continued):

1. Sufficient information to support the change(s) together with theappropriate analyses or evaluations justifying the change(s);

2. A determination that the change(s) maintain the levels of radioactiveeffluent control required by 10 CFR 20.106, 40 CFR 190,10 CFR 50.36a, and 10 CFR 50, Appendix I, and not adversely impactthe accuracy or reliability of effluent, dose, or setpoint calculations.

3. Documentation of the fact that the change has been reviewed andfound acceptable.

b. Shall become effective upon review and approval by the corporate officerwith direct responsibility for the plant or designee.

c. Shall be submitted to the NRC in the form of a complete, legible copy of theentire ODCM as a part of or concurrent with the Radioactive EffluentRelease Report for the period of the report in which any change in theODCM was made. Each change shall be identified by markings in themargin of the affected pages, clearly indicating the area of the page thatwas changed, and shall indicate the date (i.e., month and year) the changewas implemented.

5.5.2.2 Deleted

5.5.2.3 Radioactive Effluent Controls Program

This program conforms to 10 CFR 50.36a for the control of radioactive effluentsand for maintaining the doses to members of the public from radioactive effluentsas low as reasonably achievable. The program shall be contained in the ODCM,shall be implemented by procedures, and shall include remedial actions to betaken whenever the program limits are exceeded. The program shall include thefollowing elements:

a. Limitations on the functional capability of radioactive liquid and gaseousmonitoring instrumentation including surveillance tests and setpointdetermination in accordance with the methodology in the ODCM;

b. Limitations on the concentrations of radioactive material released in liquideffluents to unrestricted areas, conforming to 10 CFR 20, Appendix B,Table II, Column 2;

c. Monitoring, sampling, and analysis of radioactive liquid and gaseouseffluents in accordance with 10 CFR 20.106 and with the methodology andparameters in the ODCM;



5.5 Procedures, Programs, and Manuals (continued)

5.5.2.3 Radioactive Effluent Controls Program (continued)

d. Limitations on the annual and quarterly doses or dose commitment to amember of the public from radioactive materials in liquid effluents releasedfrom each unit to unrestricted areas, conforming to 10 CFR 50, Appendix I;

e. Determination of cumulative and projected dose contributions fromradioactive effluents for the current calendar quarter and current calendaryear in accordance with the methodology and parameters in the ODCM atleast every 31 days;

f. Limitations on the functional capability and use of the liquid and gaseouseffluent treatment systems to ensure that appropriate portions of thesesystems are used to reduce releases of radioactivity when the projecteddoses in a period of 31 days would exceed 2 percent of the guidelines forthe annual dose or dose commitment, conforming to 10 CFR 50,Appendix I;

g. Limitations on the dose rate resulting from radioactive material released ingaseous effluents to areas beyond the site boundary conforming to thedose associated with 10 CFR 20, Appendix B, Table II, Column 1;

h. Limitations on the annual and quarterly air doses resulting from noblegases released in gaseous effluents from each unit to areas beyond thesite boundary, conforming to 10 CFR 50, Appendix I;

i. Limitations on the annual and quarterly doses to a member of the publicfrom iodine-1 31, iodine-1 33, tritium, and all radionuclides in particulate formwith half lives greater than 8 days in gaseous effluents released from eachunit to areas beyond the site boundary, conforming to 10 CFR 50,Appendix I; and

j. Limitations on the annual dose or dose commitment to any member of thepublic due to releases of radioactivity and to radiation from uranium fuelcycle sources, conforming to 40 CFR 190.


5.6


5.6 Deleted


Reporting Requirements5.7


5.7 Reporting Requirements

5.7.1 Routine Reports

In addition to the applicable reporting requirements of Title 10, Code of FederalRegulations, the following reports shall be submitted in accordance with 10 CFR50.4. The reports shall be addressed to U.S. Nuclear Regulatory Commission,Attention: Document Control Desk, Washington, D.C., with a copy to theRegional Administrator of the Regional Office of the NRC, unless otherwisenoted.

5.7.1.1 Deleted

5.7.1.2 Annual Radiological Environmental Operating Report

---------------------------- NOTE -------------------------A single submittal may be made for a multiple unit station. The submittal shouldcombine sections common to all units at the station.

The Annual Radiological Environmental Operating Report covering the operationof the unit during the previous calendar year shall be submitted by May 15 ofeach year. The report shall include summaries, interpretations, and analyses oftrends of the results of the Radiological Environmental Monitoring Program forthe reporting period. The material provided shall be consistent with theobjectives outlined in the Offsite Dose Calculation Manual (ODCM), and in10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

The Annual Radiological Environmental Operating Report shall include theresults of analyses of all radiological environmental samples and of allenvironmental radiation measurements taken during the period pursuant to thelocations specified in the table and figures in the ODCM, as well as summarizedand tabulated results of these analyses and measurements in the format of thetable in the Radiological Assessment Branch Technical Position, Revision 1,November 1979. The report shall identify the thermoluminescent dosimeter(TLD) results that represent collocated dosimeters in relation to the NRC TLDprogram and the exposure period associated with each result. In the event thatsome individual results are not available for inclusion with the report, the reportshall be submitted noting and explaining the reasons for the missing results. Themissing data shall be submitted in a supplementary report as soon as possible.


Reporting Requirements5.7

5.7 Reporting Requirements (continued)

5.7.1.3 Radiological Effluent Release Report

-------------------------NOTE ------------------------A single submittal may be made for a multiple unit station. The submittal shallcombine sections common to all units at the station; however, for units withseparate radwaste systems, the submittal shall specify the releases ofradioactive material from each unit.

The Radioactive Effluent Release Report covering the operation of the unit in theprevious calendar year shall be submitted prior to May 1 of each year. Thereport shall include a summary of the quantities of radioactive liquid and gaseouseffluents and solid waste released from the unit. The report shall also include asummary of the quantities of solid radioactive waste shipped from the unit directlyto the disposal site and quantities of solid radioactive waste shipped from theunit's intermediary processor to the disposal site. The material provided shall beconsistent with the objectives outlined in the ODCM and Process ControlProgram (PCP) and in conformance with 10 CFR 50.36a and 10 CFR 50,Appendix I, Section IV.B.1.


*High Radiation Area5.8


5.8 High Radiation Area

5.8.1 Each high radiation area as defined 10 CFR 20 shall be barricaded andconspicuously posted as a high radiation area, and entrance thereto shall becontrolled by requiring issuance of a Radiation Exposure Permit (REP).

Any individual or group of individuals permitted to enter such areas shall beprovided with or accompanied by one or more of the following:

a. A radiation monitoring device that continuously indicates the radiation doserate in the area,

b. A radiation monitoring device that continuously integrates the radiationdose rate in the area and alarms when a preset integrated dose is received.Entry into such areas with this monitoring device may be made after thedose rates in the area have been determined and personnel have beenmade knowledgeable of them,

c. An individual qualified in radiation protection procedures with a radiationdose rate monitoring device. This individual is responsible for providingpositive radiation protection control over the activities within the area andshall perform periodic radiation surveillance at the frequency specified inthe radiation protection procedures or the applicable REP.

5.8.2 In addition, areas that are accessible to personnel and that have radiation levelsgreater than 1.0 rem (but less than 500 rads at 1 meter) in 1 hour at 30 cm fromthe radiation source, or from any surface penetrated by the radiation, shall beprovided with locked doors to prevent unauthorized entry, and the keys shall bemaintained under the administrative control of the shift manager on duty orradiation protection supervisor. Doors shall remain locked except during periodsof access by personnel under an approved REP that specifies the dose rates inthe immediate work areas and the maximum allowable stay time for individuals inthat area. In lieu of a stay time specification on the REP, direct or remotecontinuous surveillance (such as closed circuit TV cameras) may be made bypersonnel qualified in radiation protection procedures to provide positiveexposure control over the activities being performed within the area.

5.8.3 Individual high radiation areas that are accessible to personnel, that could resultin radiation doses greater than 1.0 rem in 1 hour, and that are within large areaswhere no enclosure exists to enable locking and where no enclosure can bereasonably constructed around the individual area shall be barricaded andconspicuously posted. A flashing light shall be activated as a warning devicewhenever the dose rate in such an area exceeds or is expected to exceed 1.0rem in 1 hour at 30 cm from the radiation source or from any surface penetratedby the radiation.


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SOUTHERN CALIFORNIA I. EDISON · EDISON Vice President & Chief Nuclear Officer An ED/SON INTERNA.TIONAL.® Company March 18, 2015 10 CFR 50.90 U. S. Nuclear Regulatory Commission