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| {{#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}} |
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Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML19130A1952019-05-0808 May 2019 Letter - FEMA Review of Proposed Changes to DBNPS Emergency Plan for Permanently Defueled Condition ML17142A3152017-05-16016 May 2017 Proposed Changes to Cyber Security Plan, Implementation Schedule Completion Date ML16355A0142016-12-15015 December 2016 Amendment Applications 225, 272, and 257 ISFSl-only Technical Specifications ML16172A0752016-06-16016 June 2016 Amendment Applications 271 and 256 - Proposed Changes to Cyber Security Plan - Implementation Schedule Completion Date - San Onofre Nuclear Generating Station, Units 2 and 3 ML15246A4652015-08-27027 August 2015 License Amendment Request (LAR) for Revision to Cyber Security Plan Implementation Schedule Completion Date, Supplement 1 to Amendment Application Numbers 269 and 254 ML14321A0152014-11-12012 November 2014 License Amendment Request (LAR) for Revision to Cyber Security Plan Implementation Schedule Completion Date Amendment Application Numbers 269 and 254 ML13296A0132013-10-21021 October 2013 Amendment Application Numbers 265 and 250 Responsibility, Organization, and Qualifications ML13098A0432013-04-0505 April 2013 License Amendment Application Number 263, Revise Technical Specifications to Require Compliance ML13091A1482013-04-0101 April 2013 Draft License Amendment Regarding Steam Generator Program ML13168A5902013-03-27027 March 2013 License Amendment Requests 262 and 248, to Revise the Fire Protection Licensing Basis to NFPA 805 Per 10 CFR 50.48(c) ML11252B1102011-09-0202 September 2011 Amendment Applications 258 and 244, Revision 1, Technical Specifications Applicable to Movement of Fuel Assemblies ML11251A1012011-07-29029 July 2011 Attachment 1, Volume 8, San Onofre Nuclear Generating Station - Improved Technical Specifications Conversion - ITS Section 3.5, Emergency Core Cooling Systems (ECCS) ML11251A1062011-07-29029 July 2011 Attachment 1, Volume 12, San Onofre Nuclear Generating Station - Improved Technical Specifications Conversion - ITS Section 3.9, Refueling Operations ML11251A1052011-07-29029 July 2011 Attachment 1, Volume 11, San Onofre Nuclear Generating Station - Improved Technical Specifications Conversion - ITS Section 3.8, Electrical Power Systems ML11251A1032011-07-29029 July 2011 Attachment 1, Volume 10, San Onofre Nuclear Generating Station - Improved Technical Specifications Conversion - ITS Section 3.7, Plant Systems ML11251A1022011-07-29029 July 2011 Attachment 1, Volume 9, San Onofre Nuclear Generating Station - Improved Technical Specifications Conversion - ITS Section 3.6, Containment Systems ML11251A1072011-07-29029 July 2011 Attachment 1, Volume 13, San Onofre Nuclear Generating Station - Improved Technical Specifications Conversion - ITS Chapter 4.0, Design Features ML11251A0992011-07-29029 July 2011 Attachment 1, Volume 6, San Onofre Nuclear Generating Station - Improved Technical Specifications Conversion - ITS Section 3.3, Instrumentation ML11251A0982011-07-29029 July 2011 Attachment 1, Volume 5, San Onofre Nuclear Generating Station - Improved Technical Specifications Conversion - ITS Section 3.2, Power Distribution Limits ML11251A0972011-07-29029 July 2011 Attachment 1, Volume 4, San Onofre Nuclear Generating Station - Improved Technical Specifications Conversion - ITS Section 3.1, Reactivity Control Systems ML11251A0962011-07-29029 July 2011 Attachment 1, Volume 3, San Onofre Nuclear Generating Station - Improved Technical Specifications Conversion - ITS Section 3.0, LCO and SR Applicability ML11251A0952011-07-29029 July 2011 Attachment 1, Volume 2, San Onofre Nuclear Generating Station - Improved Technical Specifications Conversion - ITS Chapter 2.0, Safety Limits ML11251A0832011-07-29029 July 2011 License Amendment Requests (LAR) 260 & 246 Technical Specifications Conversion to NUREG-1432, Rev. 3.0 Plus Selected Approved Travelers. Attachment 1 - SONGS ITS Submittal, Volumes 1 - 15 ML11251A1132011-07-29029 July 2011 License Amendment Requests (LAR) 260 & 246 Technical Specifications Conversion to NUREG-1432, Rev. 3.0 Plus Selected Approved Travelers. Attachment 2 - SONGS ITS Conversion Submittal, Volumes 1 - 15 ML11251A1002011-07-29029 July 2011 Attachment 1, Volume 7, San Onofre Nuclear Generating Station - Improved Technical Specifications Conversion - ITS Section 3.4, Reactor Coolant System (RCS) ML11251A1092011-07-29029 July 2011 Attachment 1, Volume 15, San Onofre Nuclear Generating Station - Improved Technical Specifications Conversion - Generic Determination of No Significant Hazards Considerations and Environmental Assessment ML11251A0862011-07-29029 July 2011 License Amendment Requests (LAR) 260 & 246 Technical Specifications Conversion to NUREG-1432, Rev. 3.0 Plus Selected Approved Travelers ML11251A1122011-07-29029 July 2011 License Amendment Requests (LAR) 260 & 246 Technical Specifications Conversion to NUREG-1432, Rev. 3.0 Plus Selected Approved Travelers. Attachment 2 - Commitment List ML11251A1082011-07-29029 July 2011 Attachment 1, Volume 14, San Onofre Nuclear Generating Station - Improved Technical Specifications Conversion - ITS Chapter 5.0, Administrative Controls ML1022900732010-08-16016 August 2010 Re-submittal of License Amendment Requests 259 and 245, One-Time Technical Specification (TS) Changes Applicable to TS 3.8.1, AC Sources - Operating. ML1002102002010-01-14014 January 2010 Submittal of Amendment Applications 258 and 244, Technical Specifications Applicable to Movement of Fuel Assemblies ML0934102512009-11-23023 November 2009 Amendment Application Numbers 257 and 243, Proposed Change Number 595 Cyber Security Plan ML0916300612009-06-10010 June 2009 License Amendment Request for Adoption of TSTF-51 1, Rev. 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26. ML0902204872009-01-13013 January 2009 Amendment Application Numbers 253 and 239 Proposed Change Number NPF-10/15-588 Physical Security Plan Change for SG Replacement ML0808705202008-03-19019 March 2008 SONGS Unit 2, Request to Revise Operating License by Removing Pages and Inserting the Enclosed Pages. Includes Unit 2 TS Amendment 213, B08-001 and B08-002, and Unit 2 LCS L08-001 and L08-002 ML0726810942007-09-24024 September 2007 Amendment Application No. 236 Proposed Change Number (PCN) 582 Technical Specification (TS) 5.5.2.15 Containment Leakage Rate Testing Program ML0725503042007-09-11011 September 2007 Amendment Application Numbers 243, Supplement 2 and 227, Supplement 2, Proposed Change Number (PCN) 556, Revision 2 ML0711402092007-04-17017 April 2007 Proposed Change Number 549, Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Rev. 3, Using the Consolidated Line Item Improvement Process ML0709305972007-03-30030 March 2007 Proposed Change Number (PCN) - 577 Lovs Relay Replacement ML0709501922007-03-30030 March 2007 Proposed Change Number (PCN)-548, Revision 2, Battery and DC Sources Upgrades and Cross-Tie ML0704400462007-02-0808 February 2007 Proposed Change Number (PCN) - 574 Degraded Voltage Setpoints ML0629003322006-11-15015 November 2006 Issuance of License Amendment Nos. 207 and 199 Regarding Revision of Administrative Controls ML0629704442006-11-0909 November 2006 Issuance of Amendments 206 and 198 Change, Define Extent of the Required Tube Inspections, and Repair Criteria within the Tubesheet Region of the Steam Generators ML0631701292006-11-0707 November 2006 Proposed Change Number 576, Request to Revise Main Steam Safety Valve Requirements and Actions (Technical Specification 3.7.1) ML0626203832006-09-19019 September 2006 Issuance of Amendments Tech Spec Improvement Regarding Steam Generator Tube Integrity Based on Tech Spec Task Force (TSTF) Standard Tech Spec Change Traveler, TSTF-449 (TAC Nos. MC9236/MC9237) ML0623401462006-08-15015 August 2006 Response to Request for Additional Information and Submittal of Supplement 2 to Proposed Change Number NPF-10/15-585 License Amendment Request, Proposed Technical Specification.... ML0619900142006-07-14014 July 2006 Proposed Change Number (PCN) 563 Request to Revise Administrative Controls ML0615903192006-06-0202 June 2006 Proposed Change Number (PCN) 567 Emergency Diesel Generator Fuel Oil Volume Requirements ML0612207012006-04-28028 April 2006 Amendment Application Numbers 243 and 227, Proposed Change Number (PCN) 556 Request to Revise Fuel Storage Pool Boron Concentration ML0611001392006-04-17017 April 2006 Proposed Change No. NPF-10/15-568, Application to Eliminate License Condition 2.G, Requiring Reporting of Violations of Section 2.C of Operating Licenses 2019-05-08
[Table view] |
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