ML15082A017

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Supplement 4 to Amendment Applications 266 and 251, Permanently Defueled Technical Specifications
ML15082A017
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 03/18/2015
From: Thomas J. Palmisano
Southern California Edison Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
TAC MF2954, TAC MF2955
Download: ML15082A017 (41)
v • d • e


Text

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 Commission ATTN: Document Control Desk Washington, D.C. 20555-0001

Subject:

Docket Nos. 50-361 and 50-362 Supplement 4 to Amendment Applications 266 and 251 Permanently Defueled Technical Specifications San 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 Defueled Technical 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, Permanently Defueled Technical Specifications, San Onofre Nuclear Generating Station, 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 2 to Amendment Applications 266 and 251, Permanently Defueled Technical 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 Defueled Technical 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) dated September 30, 2015;

Subject:

San Onofre Nuclear Generating Station, Units 2 and 3 - Issuance of Amendments Regarding Changes to the Administrative Controls Section of the Technical Specifications (TAC Nos. MF2954 and MF2955)

Dear Sir or Madam:

By letter dated March 21, 2014 (Reference 1), as supplemented by letters dated October 1, 2014 (Reference 2), February 23, 2015 (Reference 3), and February 25, P.O. Box 128 San Clemente, CA 92672 (949) 368-6575 PAX 86575 Fax: (949) 368-6183 Tom.Palmisano@sce.comn

Document Control Desk March 18, 2015 2015 (Reference 4), Southern California Edison (SCE) submitted a License Amendment Request (LAR), consisting of Amendment Application Nos. 266 and 251, to Facility Operating License Numbers NPF-10 and NPF-15 for San Onofre Nuclear Generating Station (SONGS), Units 2 and 3, respectively. The LAR proposed to revise the Operating License and the associated Technical Specifications (TS) to reflect the permanent cessation of reactor operation for SONGS Units 2 and 3.

The SCE request included changes to the NRC findings in the Operating Licenses for Units 2 and 3. In addition, SCE proposed changes to certain Operating License provisions to remove reference to "use" of the facility. Upon further review, SCE has concluded that these changes are not necessary to reflect permanent cessation of operations. Supplement 4 to Reference 1, provided as an Enclosure to this letter, withdraws the proposed changes described above. to this letter provides clean-typed pages for the proposed Permanently Defueled Technical Specifications. The clean-typed pages reflect the changes as proposed 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 as approved 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.

Ifyou have any questions or require any additional information, please contact Ms. Andrea Sterdis 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 Specifications
2. Permanently Defueled Technical Specifications - Clean Typed Pages cc: M. L. Dapas, Regional Administrator, NRC Region IV T. J. Wengert, NRC Licensing Project Manager, SONGS Units 2 & 3 R. L. Kellar, NRC Region IV, Branch Chief, Repository Spent Fuel Safety S. 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 License Amendment Request (LAR) to reflect permanent cessation of operations for the San Onofre Nuclear Generating Station (SONGS) Units 2 and 3. As part of that LAR, SCE proposed 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 the facility. After further review, SCE has concluded that these changes are not necessary to reflect permanent cessation of operations. This Supplement 4 to the March 21, 2014 LAR 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 Unit 2 Operating License as follows:

License Condition 1.B B. Construction Of the- S-an Onofre Nuclear Generating Station, Unit 2 (h facility), har, been substantially completed in coenformity with ConStruction Permiwt No. CPPR 97 and the application as amended, the prE6oviSio f the Act, and the regulations of the Commission; This section is proposed for deletion in its entirety. Decommissioning of SONGS Unit 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 nucleaf material as autheozed by this licenise will be in accordance with the GOM.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 finding regarding possession and use of byproduct, source, and special nuclear material for operating SONGS Unit 2 is not dependent on decommissioning of the facility.

Additionally, possession and use of byproduct, source, and special nuclear material at SONGS Unit 2 during decommissioning activities is covered by License Condition 2.B, which will remain in effect. Therefore, License Condition 1.J is not needed.

1

This paragraph will read as follows:

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 of the license, they are historical in nature and need not be deleted to reflect permanent cessation of operations. This supplement withdraws the proposed changes to paragraphs 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 2 Operating License, as follows:

License Condition 2.B.(2)

(2) Southern California Edison Company (SCE), pursuant to Section 103 of the Act and 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities", to possess, use, and operate the facility at the designated location in San Diego County, California, in accordance with the procedures and limitations set forth in this license; The language regarding use and operation is proposed for deletion. The license no longer authorizes use and operation of the facility.

This paragraph will read as follows:

(2) Southern California Edison Company (SCE), pursuant to Section 103 of the Act and 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities", to possess the facility at the designated location in San Diego County, California, in accordance with the procedures and limitations set forth in this license; Supplement 4 changes to Unit 2 Paragraph 2.B.(2)

SCE has re-considered this proposed language. Submittal of the certifications of permanent cessation of operations and permanent removal of fuel prohibit SCE from operating the reactor or emplacing or retaining fuel in the reactor vessel. It is therefore appropriate 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 is revising 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 the Act and 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities", to possess and use the facility at the designated location in San Diego County, California, in accordance with the procedures and limitations set 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 3 Operating License as follows:

License Condition 1.B B. Cosrcto f th~e S-an Onofre Nuclear Generating Station, Unit 3 (h facility), has been substantially completed in con9fomity with Costruction Permit No. CPPR 98 and the application as amended, the provisinsOft Act, and the regulationoftheCommiro; of the This section is proposed for deletion in its entirety. Decommissioning of SONGS Unit 3 is not dependent on the regulations that governed construction of the facility.

This paragraph will read as follows:

B. Deleted; License Condition 1.1

1. The receipt, possessin, and ue Of sourc~e, byproduc~t, and special nuc~lear materi 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 finding regarding possession and use of byproduct, source, and special nuclear material for operating SONGS Unit 3 is not dependent on decommissioning of the facility.

Additionally, possession and use of byproduct, source, and special nuclear material at SONGS Unit 3 during decommissioning activities is covered by License Condition 2.B, which will remain in effect. Therefore, License Condition 1.1 is not needed.

This paragraph will read as follows:

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 of the license, they are historical in nature and need not be deleted to reflect permanent cessation of operations. This supplement withdraws the proposed changes to paragraphs 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 3 Operating License, as follows:

License Condition 2.B.(2)

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

The language regarding use and operation is proposed for deletion. The license no longer authorizes use and operation of the facility.

This paragraph will read as follows:

(2) Southern California Edison Company (SCE), pursuant to Section 103 of the Act and 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities", to possess the facility at the designated location in San Diego County, California, in accordance with the procedures and limitations set forth in this license; Supplement 4 changes to Unit 3 Paragraph 2.B.(2)

SCE has re-considered this proposed language. Submittal of the certifications of permanent cessation of operations and permanent removal of fuel prohibit SCE from operating the reactor or emplacing or retaining fuel in the reactor vessel. It is therefore appropriate 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 is revising 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 the Act and 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities", to possess and use the facility at the designated location in San Diego County, California, in accordance with the procedures and limitations set forth in this license.

4

ENCLOSURE 2 PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS CLEAN-TYPED PAGES

Definitions 1.1 1.0 USE AND APPLICATION 1.1 Definitions

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

The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.

Term Definition ACTIONS ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.

CERTIFIED FUEL HANDLER A CERTIFIED FUEL HANDLER is an individual who complies with provisions of the CERTIFIED FUEL HANDLER training program required by TS 5.3.2.

OPERABLE - OPERABILITY A system, subsystem, train, component, or device shall be OPERABLE when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment 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 support function(s).

Unit 2 - Amendment XXX San Onofre - Draft 1.1-1 Unit 3 - Amendment XXX

Logical Connectors 1.2 1.0 USE AND APPLICATION 1.2 Logical Connectors PURPOSE The purpose of this section is to explain the meaning of logical connectors.

Logical connectors are used in Technical Specifications (TS) to discriminate between, and yet connect, discrete Conditions, Required Actions, Completion Times, Surveillances, and Frequencies. The only logical connectors that appear in TS are AND and OR. The physical arrangement of these connectors constitutes logical conventions with specific meanings.

BACKGROUND Several levels of logic may be used to state Required Actions. These levels are identified by the placement (or nesting) of the logical connectors and by the number assigned to each Required Action. The first level of logic is identified by the first digit of the number assigned to a Required Action and the placement of the logical connector in the first level of nesting (i.e., left justified with the number of the Required Action).

The successive levels of logic are identified by additional digits of the Required Action number and by successive indentions of the logical connectors.

When logical connectors are used to state a Condition, Completion Time, Surveillance, or Frequency, only the first level of logic is used, and the logical 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 in Condition A, both Required Actions A.1 and A.2 must be completed.

Unit 2 - Amendment XXX San Onofre - Draft 1.2-1 Unit 3 - Amendment XXX

Completion Times 1.3 1.0 USE AND APPLICATION 1.3 Completion Times PURPOSE The purpose of this section is to establish the Completion Time convention and to provide guidance for its use.

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

DESCRIPTION The Completion Time is the amount of time allowed for completing a Required Action. It is referenced to the time of discovery of a situation (e.g., inoperable equipment or variable not within limits) that requires entering an ACTIONS Condition unless otherwise specified, providing the facility is in a specified condition stated in the Applicability of the LCO.

Required Actions must be completed prior to the expiration of the specified Completion Time. An ACTIONS Condition remains in effect and the Required Actions apply until the Condition no longer exists or the facility is not within the LCO Applicability.

EXAMPLE The following example illustrates the use of Completion Times.

EXAMPLE 1.3-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required B.1 Verify ... 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Action and associated AND Completion Time not met. B.2 Restore... 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Condition B has two Required Actions. Each Required Action has its own separate Completion Time. Each Completion Time is referenced to the time that Condition B is entered.

The Required Actions of Condition B are to perform the verification within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND perform the restoration within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. A total of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> is allowed for performing the verification and a total of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> (not 42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br />) is allowed performing the restoration from the time that Condition B was entered. If verification is performed within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, the Unit 2 - Amendment XXX San Onofre - Draft 1.3-1 Unit 3 - Amendment XXX

Completion Times 1.3 1.3 Completion Times EXAMPLE (continued) time allowed for performing the restoration is the next 33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br /> because the total time allowed performing the restoration is 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

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

TIME Unit 2 - Amendment XXX San Onofre - Draft 1.3-2 Unit 3 - Amendment XXX

Frequency 1.4 1.0 USE AND APPLICATION 1.4 Frequency PURPOSE The purpose of this section is to define the proper use and application of Frequency requirements.

DESCRIPTION Each Surveillance Requirement (SR) has a specified Frequency in which the Surveillance must be met in order to meet the associated LCO. An understanding of the correct application of the specified Frequency is necessary for compliance with the SR.

The "specified Frequency" is referred to throughout this section and each of the Specifications of Section 3.0, Surveillance Requirement (SR)

Applicability. The "specified Frequency" consists of the requirements of the Frequency column of each SR, as well as certain Notes in the Surveillance column that modify performance requirements.

EXAMPLES The following examples illustrate the various ways that Frequencies are specified. In these examples, the Applicability of the LCO (LCO not shown) occurs whenever any fuel assembly is stored in the fuel storage pool.

EXAMPLE 1.4-1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify... 7 days Example 1.4-1 contains the type of SR most often encountered in the Technical Specifications (TS). The Frequency specifies an interval (7 days) during which the associated Surveillance must be performed at least one time. Performance of the Surveillance initiates the subsequent interval. Although the Frequency is stated as 7 days, an extension of the time interval to 1.25 times the stated Frequency is allowed by SR 3.0.2 for operational flexibility. The measurement of this interval continues at all times, even when the SR is not required to be met per SR 3.0.1 (such as when the equipment is inoperable, a variable is outside specified limits, or the facility is outside the Applicability of the LCO). If the interval specified by SR 3.0.2 is exceeded while the facility is in a specified condition in the Applicability of the LCO, then SR 3.0.3 becomes applicable.

Unit 2 - Amendment XXX San Onofre - Draft 1.4-1 Unit 3 - Amendment XXX

Frequency 1.4 1.4 Frequency EXAMPLES (continued)

If the interval as specified by SR 3.0.2 is exceeded while the facility is not in a specified condition in the Applicability of the LCO for which performance of the SR is required, the Surveillance must be performed within the Frequency requirements of SR 3.0.2 prior to entry into the specified condition. Failure to do so would result in a violation of SR 3.0.4.

EXAMPLE 1.4-2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify... Prior to moving a fuel assembly...

Example 1.4-2 illustrates a one time performance Frequency.

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

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

LCO Applicability 3.0 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 the associated Conditions shall be met.

If the LCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required, unless otherwise stated.

Unit 2 - Amendment XXX San Onofre - Draft 3.0-1 Unit 3 - Amendment XXX

SR Applicability 3.0 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY SR 3.0.1 SRs shall be met during the specified conditions in the Applicability for individual LCOs, unless otherwise stated in the SR. Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the LCO. Failure to perform a Surveillance within the specified Frequency shall be failure to meet the LCO except as provided in SR 3.0.3. Surveillances do not have to be performed on inoperable equipment or variables outside specified limits.

SR 3.0.2 The specified Frequency for each SR is met ifthe Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.

SR 3.0.3 If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the LCO not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified Frequency, whichever is greater. This delay period is permitted to allow performance of the Surveillance. A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the risk impact shall be managed.

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

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

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

Unit 2 - Amendment XXX San Onofre - Draft 3.0-2 Unit 3 - Amendment XXX

Fuel Storage Pool Water Level 3.1.1 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 irradiated fuel assemblies seated in the storage racks.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Fuel storage pool water A.1 Suspend movement of fuel Immediately level not within limit, assemblies in fuel storage pool.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.1.1 Verify the fuel storage pool water level is >_23 ft 7 days above the top of irradiated fuel assemblies seated in the storage racks.

Unit 2 - Amendment XXX San Onofre - Draft 3.1.1 -1 Unit 3 - Amendment XXX

Fuel Storage Pool Boron Concentration 3.1.2 3.1 PLANT SYSTEMS 3.1.2 Fuel Storage Pool Boron Concentration LCO 3.1.2 The fuel storage pool boron concentration shall be _>2000 ppm.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Fuel storage pool boron A.1 Suspend movement of fuel Immediately concentration not within assemblies in the fuel limit. storage pool.

AND A.2 Initiate action to restore fuel Immediately storage pool boron concentration to within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.2.1 Verify the fuel storage pool boron concentration is 7 days within limit.

Unit 2 - Amendment XXX San Onofre - Draft 3.1.2-1 Unit 3 - Amendment XXX

Spent Fuel Assembly Storage 3.1.3 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 3 spent fuel assembly stored in Region 1 shall be within the acceptable burnup domain of Figure 3.1.3-1 or Figure 3.1.3-2 or in accordance with Technical Specification 4.3.1.1.

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

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

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.1 Initiate action to bring the Immediately LCO not met. noncomplying fuel assembly into compliance.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.3.1 Verify by administrative means the initial Prior to moving a enrichment, burnup, and cooling time of the fuel fuel assembly to assembly are in accordance with LCO 3.1.3, or any spent fuel Design Features 4.3.1.1, or Licensee Controlled pool storage Specification (LCS) 4.0.100. Rev 2, dated 09/27/07. location Unit 2 - Amendment XXX San Onofre - Draft 3.1.3-1 Unit 3 - Amendment XXX

Spent Fuel Assembly Storage 3.1.3 FIGURE 3.1.3-1 MINIMUM BURNUP AND COOLING TIME VS. INITIAL ENRICHMENT FOR UNRESTRICTED PLACEMENT OF SONGS 2 AND 3 FUEL IN REGION I RACKS 25 20 a.

CL

- 15 E 10 LL 5 0 -

2.0 2.5 3.0 3.5 4.0 4.5 5.0 Initial U-235 Enrichment (w/o)

E3 0 Years - 5 Years - 10 Years 15 Years---- 20 Years Unit 2 - Amendment XXX San Onofre - Draft 3.1.3-2 Unit 3 - Amendment XXX

Spent Fuel Assembly Storage 3.1.3 FIGURE 3.1.3-2 MINIMUM BURNUP AND COOLING TIME VS. INITIAL ENRICHMENT FOR PLACEMENT OF SONGS 2 AND 3 FUEL IN PERIPHERAL POOL LOCATIONS IN REGION I RACKS 15 C-910 0.

0)

U) 5 L-0 0

3.0 3.5 4.0 4.5 5.0 Initial U-235 Enrichment (w/o)

- 0 Years - 5 Years I-v 10 Years--*.- 15 Years-s-- 20 Years Unit 2 - Amendment XXX San Onofre - Draft 3.1.3-3 Unit 3 - Amendment XXX

Spent Fuel Assembly Storage 3.1.3 FIGURE 3.1.3-3 MINIMUM BURNUP AND COOLING TIME VS. INITIAL ENRICHMENT FOR UNRESTRICTED PLACEMENT OF SONGS 2 AND 3 FUEL IN REGION II RACKS 60 CL E

~20 0

1 3 InitIal U-235 Enrichment (wlo)

S-0-- Years -- 5Years Oi 10Years Y 15Years F 20Years Unit 2 - Amendment XXX San Onofre - Draft 3.1.3-4 Unit 3 - Amendment XXX

Spent Fuel Assembly Storage 3.1.3 FIGURE 3.1.3-4 MINIMUM BURNUP AND COOLING TIME VS. INITIAL ENRICHMENT FOR PLACEMENT OF SONGS 2 AND 3 FUEL IN PERIPHERAL POOL LOCATIONS IN REGION II RACKS 40 30 E

w. 20

.E E

UL.  !

015-1.5 2 2.5 3 3.5 4 4.5 5 Initial U-235 Enrichment (w/o)

E9 0Years R 5-Years ) 1P-10Years --- 15Years - 20Years Unit 2 - Amendment XXX San Onofre - Draft 3.1.3-5 Unit 3 - Amendment XXX

Design Features 4.0 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.

Unit 2 - Amendment XXX San Onofre - Draft 4.0-1 Unit 3 - Amendment XXX

Design Features 4.0 0,

CA ,1 1

- 3.ftS .

/

20 0 40 SooN Figure 4.1-1 (page 1 of 1)

Exclusion Area Boundary Unit 2 - Amendment XXX San Onofre - Lrart AA n-9

  • -it o *h.# L. Unit 3 - Amendment XXX

Design Features 4.0 Figure 4.1-2 (page 1 of 1)

Low Population Zone Unit 2 - Amendment XXX San Onofre - Draft 4.0-3 Unit 3 - Amendment XXX

Design Features 4.0 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 maintained with:

a. Fuel assemblies having a maximum U-235 enrichment of 4.8 weight percent;
b. Keff < 1.0 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.1 of the UFSAR;
c. Keff < 0.95 if fully flooded with water borated to 1700 ppm, which includes an allowance for uncertainties as described in Section 9.1 of the UFSAR;
d. Three or five borated stainless steel guide tube inserts (GT-Insert) may be used. When three borated stainless steel guide tube inserts are used, they will installed in an assembly's center guide tube, the guide tube associated with the serial number, and the diagonally opposite guide tube. Fuel containing GT-Inserts may be placed in Region I or Region I1. However, credit for GT-Inserts is only taken for Region II storage.

A five-finger CEA may be installed in an assembly. Fuel containing a five-finger CEA may be placed in either Region I or Region II. Credit for inserted 5-finger CEAs is taken for both Region I and Region I1.

e. A nominal 8.85 inch center to center distance between fuel assemblies placed in Region II;
f. A nominal 10.40 inch center to center distance between fuel assemblies 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 and 3 assemblies will be reduced by 6.6%.

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

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

Design Features 4.0 4.0 DESIGN FEATURES 4.3 Fuel Storage (continued)

h. Units 2 and 3 fuel assemblies with a burnup in the "acceptable range" of Figure 3.1.3-1 are allowed unrestricted storage in Region I;
i. Units 2 and 3 fuel assemblies with a burnup in the "acceptable range" of Figure 3.1.3-2 are allowed unrestricted storage in the peripheral pool locations with 1 or 2 faces toward the spent fuel pool walls of Region I;
j. Units 2 and 3 fuel assemblies with a burnup in the "acceptable range" of Figure 3.1.3-3 are allowed unrestricted storage in Region II;
k. Units 2 and 3 fuel assemblies with a burnup in the "acceptable range" of Figure 3.1.3-4 are allowed unrestricted storage in the peripheral pool locations with 1 or 2 faces toward the spent fuel pool walls of Region II;
1. Units 2 and 3 fuel assemblies with a burnup in the "unacceptable range" of Figure 3.1.3-1, Figure 3.1.3-2, Figure 3.1.3-3, and Figure 3.1.3-4 will be stored in compliance with Licensee Controlled Specification 4.0.100 Rev. 2, dated 9/27/07; and
m. Each SONGS 1 uranium dioxide spent fuel assembly stored in Region II shall be stored in accordance with Licensee Controlled Specification 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 prevent inadvertent draining of the pool below Technical Specification 3.1.1 value (23 feet above 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 storage capacity limited to no more than 1542 fuel assemblies.

Unit 2 - Amendment XXX San Onofre - Draft 4.0-5 Unit 3 - Amendment XXX

Responsibility 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The corporate officer with direct responsibility for the plant shall be responsible for overall management of the San Onofre Nuclear Generating Station, and all site support functions. He shall delegate in writing the succession to this responsibility during his absence.

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

Unit 2 - Amendment XXX San Onofre - Draft 5.0-1 Unit 3 - Amendment XXX

5.0 ADMINISTRATIVE CONTROLS 5.2 Organization 5.2.1 Onsite and Offsite Organizations Onsite and offsite organizations shall be established for plant operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear fuel.

a. Lines of authority, responsibility, and communication shall be established and defined throughout highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These relationships, including the plant-specific titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications, as documented in the UFSAR.
b. The corporate officer with direct responsibility for the plant shall be responsible for overall safe handling and storage of nuclear fuel and shall have control over those onsite activities necessary for safe handling and storage of the nuclear fuel.
c. A specified corporate officer (or officers) shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure safe management of nuclear fuel.
d. The individuals who train CERTIFIED FUEL HANDLERS, and those who carry out radiation protection and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their ability to perform their assigned functions.

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 crew composition shown in Table 5.2.2-1;
b. At least one person qualified as Emergency Coordinator/Emergency Director shall be in the Control Room when nuclear fuel is stored in the spent fuel pools.

Unit 2 - Amendment XXX San Onofre - Draft 5.0-1 Unit 3 - Amendment XXX

Organization 5.2 5.2 Organization 5.2.2 FACILITY STAFF (continued)

c. Shift crew composition may be less than the minimum requirement of Table 5.2.2-1 for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.
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 site during fuel handling operations or movement of loads over the storage racks containing fuel.

Unit 2 - Amendment XXX San Onofre - Draft 5.0-2 Unit 3 - Amendment XXX

Organization 5.2 5.2 Organization Table 5.2.2-1 Minimum 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 2 - Amendment XXX San Onofre - Draft 5.0-3 Unit 3 - Amendment XXX

Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Facility Staff Qualifications 5.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except: a) the radiation protection manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975; and b) multi-discipline supervisors who shall meet or exceed the qualifications listed below.

a. Education: Minimum of a high school diploma or equivalent.
b. Experience: Minimum of four years of related technical experience which shall include three years power plant experience of which one year is at a nuclear plant.
c. Training: Complete the multi-discipline supervisor training program.

5.3.2 An NRC approved training and retraining program for the CERTIFIED FUEL HANDLERS shall be maintained.

Unit 2 - Amendment XXX San Onofre - Draft 5.0-4 Unit 3 - Amendment XXX

TS Bases Control 5.4 5.0 ADMINISTRATIVE CONTROLS 5.4 Technical Specifications (TS) Bases Control 5.4.1 Changes to the Bases of the TS shall be made under appropriate administrative controls.

5.4.2 Changes to the Bases may be made without prior NRC approval provided the changes 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 approval pursuant to 10 CFR 50.59.

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

5.4.4 Proposed changes that meet the criteria of (a) or (b) above shall be reviewed and approved by the NRC prior to implementation. Changes to the Bases implemented without prior NRC approval shall be provided to the NRC every 24 months.

Unit 2 - Amendment XXX San Onofre - Draft 5.0-5 Unit 3 - Amendment XXX

Procedures, Programs, and Manuals 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Procedures, Programs, and Manuals 5.5.1 Procedures 5.5.1.1 Scope Written procedures shall be established, implemented, and maintained covering the 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 the guidance 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, and maintained.

5.5.2.1 Offsite Dose Calculation Manual (ODCM)

a. The ODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the Radiological Environmental Monitoring Program;
b. The ODCM shall also contain the Radioactive Effluent Controls required by Specification 5.5.2.3 and Radiological Environmental Monitoring programs required by LCS, and descriptions of the information that should be included in the Annual Radiological Environmental Operating Report and the Radioactive Effluent Release Report required by Specification 5.7.1.2 and 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:

Unit 2 - Amendment XXX San Onofre - Draft 5.0-6 Unit 3 - Amendment XXX

Procedures, Programs, and Manuals 5.5 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 the appropriate analyses or evaluations justifying the change(s);
2. A determination that the change(s) maintain the levels of radioactive effluent control required by 10 CFR 20.106, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
3. Documentation of the fact that the change has been reviewed and found acceptable.
b. Shall become effective upon review and approval by the corporate officer with direct responsibility for the plant or designee.
c. Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was 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 effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable. The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM;
b. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to 10 CFR 20, Appendix B, Table II, Column 2;
c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the ODCM; Unit 2 - Amendment XXX San Onofre - Draft 5.0-7 Unit 3 - Amendment XXX

Procedures, Programs, and Manuals 5.5 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 a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas, conforming to 10 CFR 50, Appendix I;
e. Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days;
f. Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2 percent of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I;
g. Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the site boundary conforming to the dose associated with 10 CFR 20, Appendix B, Table II, Column 1;
h. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I;
i. Limitations on the annual and quarterly doses to a member of the public from iodine-1 31, iodine-1 33, tritium, and all radionuclides in particulate form with half lives greater than 8 days in gaseous effluents released from each unit 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 the public due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.

Unit 2 - Amendment XXX San Onofre - Draft 5.0-8 Unit 3 - Amendment XXX

5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Deleted Unit 2 - Amendment XXX San Onofre - Draft 5.0-9 Unit 3 - Amendment XXX

Reporting Requirements 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 Reporting Requirements 5.7.1 Routine Reports In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted in accordance with 10 CFR 50.4. The reports shall be addressed to U.S. Nuclear Regulatory Commission, Attention: Document Control Desk, Washington, D.C., with a copy to the Regional Administrator of the Regional Office of the NRC, unless otherwise noted.

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 should combine sections common to all units at the station.

The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table 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 TLD program and the exposure period associated with each result. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.

Unit 2 - Amendment XXX San Onofre - Draft 5.0-10 Unit 3 - Amendment XXX

Reporting Requirements 5.7 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 shall combine sections common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

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

Unit 2 - Amendment XXX San Onofre - Draft 5.0-11 Unit 3 - Amendment XXX

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

a. A radiation monitoring device that continuously indicates the radiation dose rate in the area,
b. A radiation monitoring device that continuously integrates the radiation dose 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 the dose rates in the area have been determined and personnel have been made knowledgeable of them,

c. An individual qualified in radiation protection procedures with a radiation dose rate monitoring device. This individual is responsible for providing positive radiation protection control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified in the radiation protection procedures or the applicable REP.

5.8.2 In addition, areas that are accessible to personnel and that have radiation levels greater than 1.0 rem (but less than 500 rads at 1 meter) in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 30 cm from the radiation source, or from any surface penetrated by the radiation, shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the shift manager on duty or radiation protection supervisor. Doors shall remain locked except during periods of access by personnel under an approved REP that specifies the dose rates in the immediate work areas and the maximum allowable stay time for individuals in that area. In lieu of a stay time specification on the REP, direct or remote continuous surveillance (such as closed circuit TV cameras) may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area.

5.8.3 Individual high radiation areas that are accessible to personnel, that could result in radiation doses greater than 1.0 rem in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, and that are within large areas where no enclosure exists to enable locking and where no enclosure can be reasonably constructed around the individual area shall be barricaded and conspicuously posted. A flashing light shall be activated as a warning device whenever the dose rate in such an area exceeds or is expected to exceed 1.0 rem in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 30 cm from the radiation source or from any surface penetrated by the radiation.

Unit 2 - Amendment XXX San Onofre - Draft 5.0-12 Unit 3 - Amendment XXX

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