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| number = ML11251A112
| number = ML11251A112
| issue date = 07/29/2011
| issue date = 07/29/2011
| title = San Onofre Nuclear Generating Station, Units 2 & 3, License Amendment Requests (LAR) 260 & 246 Technical Specifications Conversion to NUREG-1432, Rev. 3.0 Plus Selected Approved Travelers. Attachment 2 - Commitment List
| title = License Amendment Requests (LAR) 260 & 246 Technical Specifications Conversion to NUREG-1432, Rev. 3.0 Plus Selected Approved Travelers. Attachment 2 - Commitment List
| author name =  
| author name =  
| author affiliation = Edison International Co, Southern California Edison Co
| author affiliation = Edison International Co, Southern California Edison Co
Line 13: Line 13:
| document type = License-Application for Facility Operating License (Amend/Renewal) DKT 50
| document type = License-Application for Facility Operating License (Amend/Renewal) DKT 50
| page count = 4
| page count = 4
| project =
| stage = Request
}}
}}


=Text=
=Text=
{{#Wiki_filter:Docket Nos. 50-361 and 50-362 Attachment 2   Page 1 of 4  ATTACHMENT 2 COMMITMENT LIST AMENDMENT APPLICATIONS 260 AND 246 SAN ONOFRE NUCLEAR GENERATING STATION UNITS 2 AND 3 TECHNICAL SPECIFICATIONS CONVERSION TO NUREG-1432, REV. 3.0 PLUS SELECTED APPROVED TRAVELERS The following list identifies those actions committed to by Southern California Edison (SCE) for the San Onofre Nuclear Generating Station (SONGS) Units 2 and 3 in this document. Any other actions discussed in the submittal represent intended or planned actions; they are described only for information and are not regulatory commitments. Please contact Ms. Linda T. Conklin at (949) 368-9443 for any questions regarding this document or any associated regulatory commitments. No. Commitment Due Date/Event 1 SCE will establish the Technical Specification Bases for LCO 3.0.4, as modified, with the applicable license amendment. Upon Implementation 2 SCE will ensure that if LCO 3.0.4.b is used, the risk assessments will be conducted using the procedures and guidance endorsed by Regulatory Guide 1.182, "Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants." Regulatory Guide 1.182 endorses the guidance in Section 11 of NUMARC 93-01, "Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants." Upon Implementation 3 SCE will establish the Technical Specification Bases for LCO 3.0.8, as adopted, with the applicable license amendment. Upon Implementation 4 SCE will ensure that when LCO 3.0.8a is used, appropriate plant procedures and administrative controls are revised to implement the following Tier 2 Restriction: At least one AFW train (including a minimum set of supporting equipment required for its successful operation) not associated with the inoperable snubber(s), Upon Implementation Docket Nos. 50-361 and 50-362 Attachment 2   Page 2 of 4  No. Commitment Due Date/Event must be available 5 SCE will ensure that when LCO 3.0.8b is used, appropriate plant procedures and administrative controls are revised to implement the following Tier 2 Restriction: At least one AFW train (including a minimum set of supporting equipment required for its successful operation) not associated with the inoperable snubber(s), or some alternative means of core cooling (e.g., F&B, firewater system or "aggressive secondary cooldown" using the steam generators) must be available. Upon Implementation 6 SCE will ensure that when LCO 3.0.8 is used appropriate plant procedures and administrative controls are revised to implement the following Tier 2 Restriction: Every time the provisions of LCO 3.0.8 are used SCE will confirm that at least one train (or subsystem) of systems supported by the inoperable snubbers would remain capable of performing their required safety or support functions for postulated design loads other than seismic loads. LCO 3.0.8 does not apply to non-seismic snubbers. In addition, a record of the design function of the inoperable snubber (i.e., seismic vs. non-seismic), implementation of any applicable Tier 2 restrictions, and the associated plant configuration shall be available on a recoverable basis. Upon Implementation 7 SCE will revise the UFSAR or TS Bases to describe the restrictions in commitments 4 and 5. In Accordance with 10CFR50.71(e) 8 SCE will ensure that when using end state changes being adopted as part of TSTF-422 incorporation, appropriate plant procedures and administrative controls are revised to perform a Upon Implementation Docket Nos. 50-361 and 50-362 Attachment 2   Page 3 of 4  No. Commitment Due Date/Event risk assessment in accordance with 10 CFR 50.65(a)(4), regardless of whether maintenance is being performed. The risk assessment will follow Regulatory Guide 1.182, "Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants," which endorses NUMARC 93-01, "Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants," Section 11 guidance for implementation of 10 CFR 50.65(a)(4). SCE will also follow the industry-developed implementation guidance, WCAP-16364-NP, Rev. 0, "Implementation Guidance for Risk Informed Modification to Selected Required Action End States at Combustion Engineering NSSS Plants (TSTF-422)," November 2004. 9 For all Frequencies being moved to the Surveillance Frequency Control Program, SCE will ensure both the current Frequencies and the basis for the Frequencies are included in the Program. SCE will also ensure that any changes to the Frequencies will be in accordance with NEI 04-01, "Risk-Informed Method for Control of Surveillance Frequencies," Rev. 1. Upon Implementation 10 SCE will ensure that appropriate administrative procedures are in place when using the LCO 3.9.3 Note that allows penetration flow path(s) providing direct access from the containment atmosphere to the outside atmosphere to be unisolated under administrative controls. The administrative procedures will ensure that in the event of a refueling accident, the open penetration(s) can and will be promptly closed. Upon Implementation Docket Nos. 50-361 and 50-362 Attachment 2   Page 4 of 4  11 SCE will ensure procedures are in place to require the continuing performance of the Hazardous Cargo Traffic Report in accordance with Regulatory Guide 1.78, "Evaluating the Habitability of Nuclear Power Plant Control Room During a Postulated Hazardous Chemical Release." The report will include hazardous cargo traffic on Interstate 5 and the Atchison, Topeka, and Santa Fe Railway and be submitted to the NRC regional administrator every three years. Upon Implementation}}
{{#Wiki_filter:Docket Nos. 50-361 and 50-362 Attachment 2 ATTACHMENT 2 COMMITMENT LIST AMENDMENT APPLICATIONS 260 AND 246 SAN ONOFRE NUCLEAR GENERATING STATION UNITS 2 AND 3 TECHNICAL SPECIFICATIONS CONVERSION TO NUREG-1432, REV. 3.0 PLUS SELECTED APPROVED TRAVELERS The following list identifies those actions committed to by Southern California Edison (SCE) for the San Onofre Nuclear Generating Station (SONGS) Units 2 and 3 in this document. Any other actions discussed in the submittal represent intended or planned actions; they are described only for information and are not regulatory commitments.
Please contact Ms. Linda T. Conklin at (949) 368-9443 for any questions regarding this document or any associated regulatory commitments.
No.                       Commitment                             Due Date/Event SCE will establish the Technical Specification 1    Bases for LCO 3.0.4, as modified, with the             Upon Implementation applicable license amendment.
SCE will ensure that if LCO 3.0.4.b is used, the risk assessments will be conducted using the procedures and guidance endorsed by Regulatory Guide 1.182, "Assessing and Managing Risk Before Maintenance Activities at Nuclear Power 2                                                          Upon Implementation Plants." Regulatory Guide 1.182 endorses the guidance in Section 11 of NUMARC 93-01, "Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants."
SCE will establish the Technical Specification 3    Bases for LCO 3.0.8, as adopted, with the             Upon Implementation applicable license amendment.
SCE will ensure that when LCO 3.0.8a is used, appropriate plant procedures and administrative controls are revised to implement the following Tier 2 Restriction:
4                                                          Upon Implementation At least one AFW train (including a minimum set of supporting equipment required for its successful operation) not associated with the inoperable snubber(s),
Page 1 of 4
 
Docket Nos. 50-361 and 50-362 Attachment 2 No.                     Commitment                             Due Date/Event must be available SCE will ensure that when LCO 3.0.8b is used, appropriate plant procedures and administrative controls are revised to implement the following Tier 2 Restriction:
At least one AFW train (including a 5        minimum set of supporting equipment           Upon Implementation required for its successful operation) not associated with the inoperable snubber(s),
or some alternative means of core cooling (e.g., F&B, firewater system or "aggressive secondary cooldown" using the steam generators) must be available.
SCE will ensure that when LCO 3.0.8 is used appropriate plant procedures and administrative controls are revised to implement the following Tier 2 Restriction:
Every time the provisions of LCO 3.0.8 are used SCE will confirm that at least one train (or subsystem) of systems supported by the inoperable snubbers would remain capable 6        of performing their required safety or       Upon Implementation support functions for postulated design loads other than seismic loads. LCO 3.0.8 does not apply to non-seismic snubbers. In addition, a record of the design function of the inoperable snubber (i.e., seismic vs.
non-seismic), implementation of any applicable Tier 2 restrictions, and the associated plant configuration shall be available on a recoverable basis.
SCE will revise the UFSAR or TS Bases to             In Accordance with 7
describe the restrictions in commitments 4 and 5. 10CFR50.71(e)
SCE will ensure that when using end state 8  changes being adopted as part of TSTF-422           Upon Implementation incorporation, appropriate plant procedures and administrative controls are revised to perform a Page 2 of 4
 
Docket Nos. 50-361 and 50-362 Attachment 2 No.                     Commitment                           Due Date/Event risk assessment in accordance with 10 CFR 50.65(a)(4), regardless of whether maintenance is being performed. The risk assessment will follow Regulatory Guide 1.182, "Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants," which endorses NUMARC 93-01, "Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants," Section 11 guidance for implementation of 10 CFR 50.65(a)(4). SCE will also follow the industry-developed implementation guidance, WCAP-16364-NP, Rev. 0, "Implementation Guidance for Risk Informed Modification to Selected Required Action End States at Combustion Engineering NSSS Plants (TSTF-422)," November 2004.
For all Frequencies being moved to the Surveillance Frequency Control Program, SCE will ensure both the current Frequencies and the basis for the Frequencies are included in the Program.
9                                                      Upon Implementation SCE will also ensure that any changes to the Frequencies will be in accordance with NEI 04-01, "Risk-Informed Method for Control of Surveillance Frequencies," Rev. 1.
SCE will ensure that appropriate administrative procedures are in place when using the LCO 3.9.3 Note that allows penetration flow path(s) providing direct access from the containment atmosphere to 10  the outside atmosphere to be unisolated under       Upon Implementation administrative controls. The administrative procedures will ensure that in the event of a refueling accident, the open penetration(s) can and will be promptly closed.
Page 3 of 4
 
Docket Nos. 50-361 and 50-362 Attachment 2 SCE will ensure procedures are in place to require the continuing performance of the Hazardous Cargo Traffic Report in accordance with Regulatory Guide 1.78, "Evaluating the Habitability of Nuclear Power Plant Control Room During a 11                                                    Upon Implementation Postulated Hazardous Chemical Release." The report will include hazardous cargo traffic on Interstate 5 and the Atchison, Topeka, and Santa Fe Railway and be submitted to the NRC regional administrator every three years.
Page 4 of 4}}

Latest revision as of 16:05, 12 November 2019

License Amendment Requests (LAR) 260 & 246 Technical Specifications Conversion to NUREG-1432, Rev. 3.0 Plus Selected Approved Travelers. Attachment 2 - Commitment List
ML11251A112
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 07/29/2011
From:
Edison International Co, Southern California Edison Co
To:
Office of Nuclear Reactor Regulation
References
NUREG-1432, Rev. 3.0
Download: ML11251A112 (4)
v • d • e


Text

Docket Nos. 50-361 and 50-362 Attachment 2 ATTACHMENT 2 COMMITMENT LIST AMENDMENT APPLICATIONS 260 AND 246 SAN ONOFRE NUCLEAR GENERATING STATION UNITS 2 AND 3 TECHNICAL SPECIFICATIONS CONVERSION TO NUREG-1432, REV. 3.0 PLUS SELECTED APPROVED TRAVELERS The following list identifies those actions committed to by Southern California Edison (SCE) for the San Onofre Nuclear Generating Station (SONGS) Units 2 and 3 in this document. Any other actions discussed in the submittal represent intended or planned actions; they are described only for information and are not regulatory commitments.

Please contact Ms. Linda T. Conklin at (949) 368-9443 for any questions regarding this document or any associated regulatory commitments.

No. Commitment Due Date/Event SCE will establish the Technical Specification 1 Bases for LCO 3.0.4, as modified, with the Upon Implementation applicable license amendment.

SCE will ensure that if LCO 3.0.4.b is used, the risk assessments will be conducted using the procedures and guidance endorsed by Regulatory Guide 1.182, "Assessing and Managing Risk Before Maintenance Activities at Nuclear Power 2 Upon Implementation Plants." Regulatory Guide 1.182 endorses the guidance in Section 11 of NUMARC 93-01, "Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants."

SCE will establish the Technical Specification 3 Bases for LCO 3.0.8, as adopted, with the Upon Implementation applicable license amendment.

SCE will ensure that when LCO 3.0.8a is used, appropriate plant procedures and administrative controls are revised to implement the following Tier 2 Restriction:

4 Upon Implementation At least one AFW train (including a minimum set of supporting equipment required for its successful operation) not associated with the inoperable snubber(s),

Page 1 of 4

Docket Nos. 50-361 and 50-362 Attachment 2 No. Commitment Due Date/Event must be available SCE will ensure that when LCO 3.0.8b is used, appropriate plant procedures and administrative controls are revised to implement the following Tier 2 Restriction:

At least one AFW train (including a 5 minimum set of supporting equipment Upon Implementation required for its successful operation) not associated with the inoperable snubber(s),

or some alternative means of core cooling (e.g., F&B, firewater system or "aggressive secondary cooldown" using the steam generators) must be available.

SCE will ensure that when LCO 3.0.8 is used appropriate plant procedures and administrative controls are revised to implement the following Tier 2 Restriction:

Every time the provisions of LCO 3.0.8 are used SCE will confirm that at least one train (or subsystem) of systems supported by the inoperable snubbers would remain capable 6 of performing their required safety or Upon Implementation support functions for postulated design loads other than seismic loads. LCO 3.0.8 does not apply to non-seismic snubbers. In addition, a record of the design function of the inoperable snubber (i.e., seismic vs.

non-seismic), implementation of any applicable Tier 2 restrictions, and the associated plant configuration shall be available on a recoverable basis.

SCE will revise the UFSAR or TS Bases to In Accordance with 7

describe the restrictions in commitments 4 and 5. 10CFR50.71(e)

SCE will ensure that when using end state 8 changes being adopted as part of TSTF-422 Upon Implementation incorporation, appropriate plant procedures and administrative controls are revised to perform a Page 2 of 4

Docket Nos. 50-361 and 50-362 Attachment 2 No. Commitment Due Date/Event risk assessment in accordance with 10 CFR 50.65(a)(4), regardless of whether maintenance is being performed. The risk assessment will follow Regulatory Guide 1.182, "Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants," which endorses NUMARC 93-01, "Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants," Section 11 guidance for implementation of 10 CFR 50.65(a)(4). SCE will also follow the industry-developed implementation guidance, WCAP-16364-NP, Rev. 0, "Implementation Guidance for Risk Informed Modification to Selected Required Action End States at Combustion Engineering NSSS Plants (TSTF-422)," November 2004.

For all Frequencies being moved to the Surveillance Frequency Control Program, SCE will ensure both the current Frequencies and the basis for the Frequencies are included in the Program.

9 Upon Implementation SCE will also ensure that any changes to the Frequencies will be in accordance with NEI 04-01, "Risk-Informed Method for Control of Surveillance Frequencies," Rev. 1.

SCE will ensure that appropriate administrative procedures are in place when using the LCO 3.9.3 Note that allows penetration flow path(s) providing direct access from the containment atmosphere to 10 the outside atmosphere to be unisolated under Upon Implementation administrative controls. The administrative procedures will ensure that in the event of a refueling accident, the open penetration(s) can and will be promptly closed.

Page 3 of 4

Docket Nos. 50-361 and 50-362 Attachment 2 SCE will ensure procedures are in place to require the continuing performance of the Hazardous Cargo Traffic Report in accordance with Regulatory Guide 1.78, "Evaluating the Habitability of Nuclear Power Plant Control Room During a 11 Upon Implementation Postulated Hazardous Chemical Release." The report will include hazardous cargo traffic on Interstate 5 and the Atchison, Topeka, and Santa Fe Railway and be submitted to the NRC regional administrator every three years.

Page 4 of 4

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