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| | {{#Wiki_filter:License Amendment Request Pre-Submittal Meeting Integrated Leak Rate Test Interval Extension Exelon Generation Company, LLC Braidwood Station, Unit 2 |
| | |
| | September 19, 2013 |
| | |
| | Agenda 1 I.History / Background II.Problem Statement III.Proposed Request IV.Justification V.Conclusions VI.Proposed Schedule VII.Additional Insights VIII.NRC Feedback / Questions |
| | |
| | History / Background 2 *On April 2, 2008, the NRC issued an amendment for Braidwood and Byron Stations approving a one |
| | -time Integrated Leak Rate Test (ILRT) interval extension of 5 years (i.e., from 10 to 15 years) |
| | *The revised Technical Specification (TS) 5.5.16, "Containment Leak Rate Testing Program," notes a specific date by which each unit's next ILRT (i.e., Type A test) must be performed |
| | -The last Braidwood Unit 2 ILRT was performed on May 4, 1999 |
| | -For Braidwood Unit 2, TS 5.5.16 states: "-Type A test shall be performed no later than May 4, 2014" |
| | *TS Limiting Condition of Operation (LCO) 3.6.1 states that the "Containment shall be OPERABLE," in MODES 1, 2, 3, and 4 |
| | - Containment operability is demonstrated by performing testing in accordance with TS 5.5.16 as specified in surveillance requirement (SR) 3.6.1.1 |
| | |
| | Problem Statement 3 *TS 5.5.16 specifies that for Braidwood Unit 2, "-Type A test shall be performed no later than May 4, 2014" |
| | -Unit 2 is scheduled to shutdown for refueling on May 3, 2014 |
| | -Unit 2 ILRT is scheduled to be performed during the refueling outage; however, will not be completed by May 4, 2014 |
| | -TS 5.5.16 (strictly applied) would still be violated given this timeline |
| | *Braidwood Unit 2 will be out of the MODE of Applicability for TS 3.6.1 which requires an OPERABLE containment (i.e., the unit will be in MODE 5) by end of day May 3, 2014 (prior to the TS 5.5.16 requirement to perform the ILRT) |
| | *Exelon Generation Company, LLC (EGC) is requesting a license amendment to preclude violating TS 5.5.16 |
| | - The latitude afforded by SR 3.0.1; i.e., "SRs shall be met during the MODES or other specified conditions in the Applicability for individual LCOs-" will not be utilized |
| | |
| | Proposed Request 4 *EGC requests NRC approval of a change to the ILRT date specified in TS 5.5.16 to ensure the TS ILRT date is consistent with the ILRT date in the outage schedule |
| | *Specifically, it is requested that the NRC approve an extension of the Braidwood Unit 2 ILRT performance date as noted below: |
| | |
| | Justification 5 *The Unit 2 refueling outage is scheduled to begin on May 3, 2014 |
| | *The Unit 2 ILRT, assuming target dates are met, will be performed on |
| | ~May 21, 2014; a 17 |
| | -day extension from the current TS due date |
| | *Given the planned schedule, Unit 2 will be out of the MODE of Applicability of TS 3.6.1 which requires an OPERABLE containment (i.e., the unit will be in MODE 5 or 6) during the entire period of the requested extension |
| | *TS 5.5.16 states that the Containment Leakage Rate Testing Program is conducted in accordance with NEI 94 |
| | -01, "Industry Guideline for Implementing Performance |
| | -Based Option of 10 CFR Part 50, Appendix J" |
| | -NEI 94-01, Section 9.2.2, "Initial Test Intervals," states: |
| | "If the test interval ends while primary containment integrity is either not required or it is required solely for shutdown activities, the test interval may be extended indefinitely. However, a successful Type A test shall be completed prior to entering the operating mode requiring primary containment integrity." |
| | - Extending the Unit 2 ILRT interval past May 4, 2014, while the unit is in an outage, is consistent with this NEI guidance |
| | |
| | Conclusions 6 *As shown in the previous discussion, an extension to the ILRT date specified in TS 5.5.16 does not challenge containment integrity and meets the intent of the one |
| | -time 5 year ILRT extension |
| | *Extending the ILRT date will not: |
| | -involve a significant increase in the probability or consequences of an accident previously evaluated |
| | -create the possibility of a new or different kind of accident; or |
| | -involve a significant reduction in a margin of safety |
| | *There is reasonable assurance that the health and safety of the public will not be endangered by the proposed action as containment integrity is not required during the requested extension period |
| | *Issuance of the proposed amendment will not be inimical to the common defense and security |
| | *The proposed action would meet the criteria for a categorical exclusion set forth in 10 CFR 51.22(c)(9); and not require an environmental assessment |
| | |
| | Proposed Schedule 7 *EGC will submit the proposed LAR on or before October 18, 2013 |
| | *Based on the current ILRT date specified in TS 5.5.16 (May 4, 2014), EGC respectfully requests NRC approval of the requested change by May 2, 2014 |
| | |
| | Additional Insights 8 *Based on the previous information, specifically: |
| | -Containment operability is demonstrated by performing testing in accordance with SR 3.6.1.1 (which references TS 5.5.16) |
| | -If the ILRT is treated as a SR, the latitude of SR 3.0.1 could be applied (i.e., SRs shall be met during the MODES or Conditions specified in the TS Applicability for the LCO) |
| | -Given the projected schedule, Unit 2 will not be in the MODE of Applicability during the entire period of the requested extension |
| | -Extending the ILRT interval is consistent with NEI 94 |
| | -01 guidance |
| | -As long as the unit is out of the MODE of Applicability prior to the required ILRT date, the intent of TS 5.5.16 is met |
| | *As an alternative, EGC would be amenable to submitting a letter to the NRC committing to complete the Unit 2 ILRT prior to entering MODE 4 (i.e., the MODE of Applicability for containment operability) following the May 2014 refueling outage |
| | |
| | NRC Feedback / Questions 9}} |
|
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Category:Slides and Viewgraphs
MONTHYEARML24100A7672024-04-11011 April 2024 Meeting Slides - Preapplication with Constellation on Planned Fleet Alternative Request to Adopt OMN-2 ML24089A2612024-04-0909 April 2024 Slides - Constellation - Pre-Application Regarding Hooded Masks 4/9/2024 Meeting Slides (L-2024-LLM-0041) ML24060A1692024-03-0707 March 2024 NRC Slides for March 7, 2024 Regulatory Conference with Constellation Nuclear Regarding Braidwood ML24057A3032024-02-26026 February 2024 Attachment 1: Braidwood Station Regulatory Conference Information ML24029A1742024-01-30030 January 2024 Constellation Pre-Application January 30, 2024, Meeting Slides - Proposed Alternative to Utilize Code Case N-932, Alternative Requirements for Acceptance of Containment Base Metal Corrosion or Erosion ML24003A1812024-01-0808 January 2024 Handout - Byron-Braidwood Core Monitoring and Support System LAR Pre-Submittal Meeting January 8,2024 ML23345A0362023-12-11011 December 2023 ATWS Uet December 11, 2023 Pre-submittal Meeting Slides ML23317A0712023-11-14014 November 2023 NRC Pre-Submittal Meeting on November 14th, 2023 - 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U.S Nuclear Regulatory Commission (NRC) - Four Element Risk-Informed Approach ML20170B0212020-06-23023 June 2020 NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections ML20169A5592020-06-16016 June 2020 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections (Rev 1) ML20163A6552020-06-16016 June 2020 6-16-20 Byron Unit 2 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections ML20091L0432020-04-0101 April 2020 Public Meeting Handout for Braidwood, Unit 2, April 1, 2020 ML18347B3142018-12-19019 December 2018 Bwrvip/Asme Relief Request Discussion December 19, 2018 ML18334A2162018-11-30030 November 2018 Presentation Slides: Exelon BWR MSIV (Boiling-Water Reactor - Main Steam Isolation Valve) Leakage Optimization for NRC Pre-Submittal Meeting of December 6, 2018 ML18319A1272018-11-19019 November 2018 Slides for 11/19/18 Public Meeting - Exelon Fleet LAR for Common Language for TS 5.7 High Radiation Areas ML18218A1122018-08-0808 August 2018 Reactor Pressure Vessel Head Penetration Nozzle Post Peening Follow-up Inspection Relief Requests for Byron Unit 2 and Braidwood Unit 1 ML18054B3592018-02-27027 February 2018 Slide: NRC Pre-Submittal Meeting for Exelon Fleet LAR to Relocate TS Unit Staff Qualification ANSI Requirements to the QATR, February 27, 2018, Profile Info: Submitted by Frank Mascitelli ML17132A1772017-05-25025 May 2017 LAR for Control Room Cooling at Byron and Braidwood Stations ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards ML16062A4222016-03-0202 March 2016 Meeting Slides for March 7, 2016 Public Meeting to Discuss Backfit Appeal ML15232A6832015-08-27027 August 2015 Stations Auxiliary Feedwater System - Unit Cross-tie License Amendment Request ML15209A9722015-07-30030 July 2015 Alloy 600 PWSCC Mitigation Plan for Reactor Vessel Head Penetration Nozzles Utilizing Cavitation Peening at Byron and Braidwood ML15204A4932015-07-23023 July 2015 Bb Station Requests for Relief for Alternate Examination Frequency ML15204A5052015-07-23023 July 2015 EPRI Tech Basis for Brd-Byr Head RR ML15133A4732015-05-20020 May 2015 Digital Upgrades of the Non-Safety Related NSSS Control Systems at Byron and Braidwood Stations ML15135A4262015-05-19019 May 2015 EOC Public Meeting Slides ML15104A4932015-04-14014 April 2015 Preliminary Site-Specific Results of the Environmental Review for Braidwood Station License Renewal ML14342A8122014-12-10010 December 2014 Presentation Slides for December 10, 2014 Meeting on Alloy 600 PWSCC Mitigation for Rvh Nozzles ML14261A1112014-09-22022 September 2014 2014 NEI Fire Protection Information Forum NRC Public Slides ML14251A4852014-09-10010 September 2014 Byron/Braidwood Auxiliary Feedwater Cross-Tie ML14177A6412014-06-23023 June 2014 UHS Pre-submittal Meeting Presentation ML13249A1892013-09-0404 September 2013 ILRT Extension LAR Pre-submittal Meeting Slides ML13224A2882013-08-12012 August 2013 2012 Braidwood Station End-of-Cycle Public Meeting Licensee Presentation 2024-04-09
[Table view] Category:Meeting Briefing Package/Handouts
MONTHYEARML24100A7672024-04-11011 April 2024 Meeting Slides - Preapplication with Constellation on Planned Fleet Alternative Request to Adopt OMN-2 ML24089A2612024-04-0909 April 2024 Slides - Constellation - Pre-Application Regarding Hooded Masks 4/9/2024 Meeting Slides (L-2024-LLM-0041) ML24060A1692024-03-0707 March 2024 NRC Slides for March 7, 2024 Regulatory Conference with Constellation Nuclear Regarding Braidwood BW240007, Attachment 5: BW-MISC-062 Rev. 0 - Braidwood Station Unit 2 Diesel Driven AFW MAAP Calculations2024-02-29029 February 2024 Attachment 5: BW-MISC-062 Rev. 0 - Braidwood Station Unit 2 Diesel Driven AFW MAAP Calculations ML24057A3032024-02-26026 February 2024 Attachment 1: Braidwood Station Regulatory Conference Information ML24057A3062024-02-24024 February 2024 Attachment 4: BW-SDP-006 Rev. 0 - Braidwood 2B AF Pump Fuel Oil Leak SOP Sensitivities ML24029A1742024-01-30030 January 2024 Constellation Pre-Application January 30, 2024, Meeting Slides - Proposed Alternative to Utilize Code Case N-932, Alternative Requirements for Acceptance of Containment Base Metal Corrosion or Erosion ML24057A3042024-01-22022 January 2024 Attachment 2: EC 640630 Rev. 000 - Documentation of Test Results with Diluted Lube Oil from Fuel In-Leakage - 28 AF Diesel Engine Past Operability ML24003A1812024-01-0808 January 2024 Handout - Byron-Braidwood Core Monitoring and Support System LAR Pre-Submittal Meeting January 8,2024 ML24057A3052023-12-12012 December 2023 Attachment 3: EC 640287 Rev. 000 - Past Operability Test Plan Acceptance Related to 2AF01PB-K ML23345A0362023-12-11011 December 2023 ATWS Uet December 11, 2023 Pre-submittal Meeting Slides ML23317A0712023-11-14014 November 2023 NRC Pre-Submittal Meeting on November 14th, 2023 - TSTF-591 and Selected 50.69 License Condition Updates (EPID L-2023-LLM-0098) (Slides) ML23272A0622023-09-29029 September 2023 Ultimate Heat Sink Temperature Tech Spec Limit Change ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23163A1642023-06-12012 June 2023 2022 Braidwood/Byron End-of-Cycle Meeting Presentation ML23033A6662023-02-0909 February 2023 Summary of Public Meeting with Constellation Energy Generation, LLC (Constellation) to Discuss Its Request for Alternatives for Certain Steam Generator Weld Inspections for Calvert Cliffs 1 & 2, Byron 1 & 2, Braidwood 1 & 2, and Ginna ML23033A6672023-01-30030 January 2023 Public Call with Constellation January 30, 2023 (Slides) ML22159A3332022-06-0909 June 2022 Presentation Slides for Braidwood and Byron 2021 End of Cycle Meeting ML21320A0672021-11-17017 November 2021 NRC Pre-Submittal Meeting - Braidwood, Unit 2, LAR for Removal of Unit 2 License Condition for Closure Stud Hole Location No. 35 (EPID L-2021-LRM-0089) (Slides) ML21314A4472021-11-10010 November 2021 Slides for Presubmittial Meeting for Proposed Alternative to Adopt ASME Code Case N-921 to Extend the Inservice Inspection Interval ML21166A3722021-06-15015 June 2021 End-of-Cycle Meeting Presentation ML21130A6252021-05-12012 May 2021 NRC Pre-Submittal Meeting - Braidwood LAR for Ultimate Heat Sink (EPID L-2021-LRM-0040) (Slides) ML21078A0952021-03-0808 March 2021 Session W20 - James Petty - Slide Deck 3 ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a ML20209A5322020-07-24024 July 2020 2019 Braidwood and Byron End-of-Cycle Presentation ML20178A4202020-06-30030 June 2020 NEI Slides for June 30, 2020, Public Meeting on COVID-19 Response ML20170B0212020-06-23023 June 2020 NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections ML20175A8722020-06-23023 June 2020 Risk-Informed Inservice Inspection - U.S Nuclear Regulatory Commission (NRC) - Four Element Risk-Informed Approach ML20169A5592020-06-16016 June 2020 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections (Rev 1) ML20163A6552020-06-16016 June 2020 6-16-20 Byron Unit 2 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections ML20091L0432020-04-0101 April 2020 Public Meeting Handout for Braidwood, Unit 2, April 1, 2020 ML19318F9512019-11-20020 November 2019 Presentation Slides for November 20, 2019, Pre-Application Meeting - Request for Revision to Quality Assurance Program Internal Audit Frequency ML19317C9952019-11-12012 November 2019 In-Service Testing Supplemental Position Indication Relief Request NRC Pre-Application Meeting November 18, 2019 ML19161A2572019-06-0404 June 2019 BWR Fleet Msv/Srv - Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19151A6602019-05-31031 May 2019 BWR Fleet Mssv/Srv Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19022A2002019-01-23023 January 2019 Request for Use of ASME Code Case N-879 for Exelon Nuclear Power Plants ML18347B3142018-12-19019 December 2018 Bwrvip/Asme Relief Request Discussion December 19, 2018 ML18334A2162018-11-30030 November 2018 Presentation Slides: Exelon BWR MSIV (Boiling-Water Reactor - Main Steam Isolation Valve) Leakage Optimization for NRC Pre-Submittal Meeting of December 6, 2018 ML18319A1272018-11-19019 November 2018 Slides for 11/19/18 Public Meeting - Exelon Fleet LAR for Common Language for TS 5.7 High Radiation Areas ML18218A1122018-08-0808 August 2018 Reactor Pressure Vessel Head Penetration Nozzle Post Peening Follow-up Inspection Relief Requests for Byron Unit 2 and Braidwood Unit 1 ML18054B3592018-02-27027 February 2018 Slide: NRC Pre-Submittal Meeting for Exelon Fleet LAR to Relocate TS Unit Staff Qualification ANSI Requirements to the QATR, February 27, 2018, Profile Info: Submitted by Frank Mascitelli ML18018B4432018-01-25025 January 2018 Summary of December 17, 2017, Closed Meeting with Exelon Generation Company, LLC, Regarding Tvel Lead Test Assemblies to Be Placed in the Braidwood Reactor (EPID 000976/05000456/L-2017-LRM and 000976/05000457/L-2017-LRM-0047 ML17142A2382017-05-25025 May 2017 OEDO-17-00280 - Briefing Package for Drop-In Visit on June 9, 2017, by Senior Management of Exelon Generation Company, LLC with Chairman Svinicki, Commissioner Baran, and Commissioner Burns ML17132A1772017-05-25025 May 2017 LAR for Control Room Cooling at Byron and Braidwood Stations ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards ML16075A3292016-03-16016 March 2016 OEDO-16-00165 - Briefing Package for Drop-In Visit on March 23, 2016, by Senior Management of Exelon Generation Company, LLC with the NRC Executive Director for Operations ML16062A4222016-03-0202 March 2016 Meeting Slides for March 7, 2016 Public Meeting to Discuss Backfit Appeal ML15232A6832015-08-27027 August 2015 Stations Auxiliary Feedwater System - Unit Cross-tie License Amendment Request ML15209A9722015-07-30030 July 2015 Alloy 600 PWSCC Mitigation Plan for Reactor Vessel Head Penetration Nozzles Utilizing Cavitation Peening at Byron and Braidwood ML15133A4732015-05-20020 May 2015 Digital Upgrades of the Non-Safety Related NSSS Control Systems at Byron and Braidwood Stations 2024-04-09
[Table view] |
Text
License Amendment Request Pre-Submittal Meeting Integrated Leak Rate Test Interval Extension Exelon Generation Company, LLC Braidwood Station, Unit 2
September 19, 2013
Agenda 1 I.History / Background II.Problem Statement III.Proposed Request IV.Justification V.Conclusions VI.Proposed Schedule VII.Additional Insights VIII.NRC Feedback / Questions
History / Background 2 *On April 2, 2008, the NRC issued an amendment for Braidwood and Byron Stations approving a one
-time Integrated Leak Rate Test (ILRT) interval extension of 5 years (i.e., from 10 to 15 years)
-The last Braidwood Unit 2 ILRT was performed on May 4, 1999
-For Braidwood Unit 2, TS 5.5.16 states: "-Type A test shall be performed no later than May 4, 2014"
- TS Limiting Condition of Operation (LCO) 3.6.1 states that the "Containment shall be OPERABLE," in MODES 1, 2, 3, and 4
- Containment operability is demonstrated by performing testing in accordance with TS 5.5.16 as specified in surveillance requirement (SR) 3.6.1.1
Problem Statement 3 *TS 5.5.16 specifies that for Braidwood Unit 2, "-Type A test shall be performed no later than May 4, 2014"
-Unit 2 is scheduled to shutdown for refueling on May 3, 2014
-Unit 2 ILRT is scheduled to be performed during the refueling outage; however, will not be completed by May 4, 2014
-TS 5.5.16 (strictly applied) would still be violated given this timeline
- Braidwood Unit 2 will be out of the MODE of Applicability for TS 3.6.1 which requires an OPERABLE containment (i.e., the unit will be in MODE 5) by end of day May 3, 2014 (prior to the TS 5.5.16 requirement to perform the ILRT)
- Exelon Generation Company, LLC (EGC) is requesting a license amendment to preclude violating TS 5.5.16
- The latitude afforded by SR 3.0.1; i.e., "SRs shall be met during the MODES or other specified conditions in the Applicability for individual LCOs-" will not be utilized
Proposed Request 4 *EGC requests NRC approval of a change to the ILRT date specified in TS 5.5.16 to ensure the TS ILRT date is consistent with the ILRT date in the outage schedule
- Specifically, it is requested that the NRC approve an extension of the Braidwood Unit 2 ILRT performance date as noted below:
Justification 5 *The Unit 2 refueling outage is scheduled to begin on May 3, 2014
- The Unit 2 ILRT, assuming target dates are met, will be performed on
~May 21, 2014; a 17
-day extension from the current TS due date
- Given the planned schedule, Unit 2 will be out of the MODE of Applicability of TS 3.6.1 which requires an OPERABLE containment (i.e., the unit will be in MODE 5 or 6) during the entire period of the requested extension
- TS 5.5.16 states that the Containment Leakage Rate Testing Program is conducted in accordance with NEI 94
-01, "Industry Guideline for Implementing Performance
-Based Option of 10 CFR Part 50, Appendix J"
-NEI 94-01, Section 9.2.2, "Initial Test Intervals," states:
"If the test interval ends while primary containment integrity is either not required or it is required solely for shutdown activities, the test interval may be extended indefinitely. However, a successful Type A test shall be completed prior to entering the operating mode requiring primary containment integrity."
- Extending the Unit 2 ILRT interval past May 4, 2014, while the unit is in an outage, is consistent with this NEI guidance
Conclusions 6 *As shown in the previous discussion, an extension to the ILRT date specified in TS 5.5.16 does not challenge containment integrity and meets the intent of the one
-time 5 year ILRT extension
- Extending the ILRT date will not:
-involve a significant increase in the probability or consequences of an accident previously evaluated
-create the possibility of a new or different kind of accident; or
-involve a significant reduction in a margin of safety
- There is reasonable assurance that the health and safety of the public will not be endangered by the proposed action as containment integrity is not required during the requested extension period
- Issuance of the proposed amendment will not be inimical to the common defense and security
- The proposed action would meet the criteria for a categorical exclusion set forth in 10 CFR 51.22(c)(9); and not require an environmental assessment
Proposed Schedule 7 *EGC will submit the proposed LAR on or before October 18, 2013
- Based on the current ILRT date specified in TS 5.5.16 (May 4, 2014), EGC respectfully requests NRC approval of the requested change by May 2, 2014
Additional Insights 8 *Based on the previous information, specifically:
-Containment operability is demonstrated by performing testing in accordance with SR 3.6.1.1 (which references TS 5.5.16)
-If the ILRT is treated as a SR, the latitude of SR 3.0.1 could be applied (i.e., SRs shall be met during the MODES or Conditions specified in the TS Applicability for the LCO)
-Given the projected schedule, Unit 2 will not be in the MODE of Applicability during the entire period of the requested extension
-Extending the ILRT interval is consistent with NEI 94
-01 guidance
-As long as the unit is out of the MODE of Applicability prior to the required ILRT date, the intent of TS 5.5.16 is met
- As an alternative, EGC would be amenable to submitting a letter to the NRC committing to complete the Unit 2 ILRT prior to entering MODE 4 (i.e., the MODE of Applicability for containment operability) following the May 2014 refueling outage
NRC Feedback / Questions 9