Letter Sequence Approval |
---|
CAC:MF2402, Control Room Habitability (Approved, Closed) CAC:MF2403, Control Room Habitability (Approved, Closed) CAC:MF2404, Control Room Habitability (Approved, Closed) CAC:MF2405, Control Room Habitability (Approved, Closed) CAC:MF2406, Control Room Habitability (Approved, Closed) CAC:MF2407, Control Room Habitability (Approved, Closed) CAC:MF2408, Control Room Habitability (Approved, Closed) CAC:MF2409, Control Room Habitability (Approved, Closed) |
|
MONTHYEARML15274A5992015-10-0101 October 2015 10-01-15 Public Phone Call Project stage: Request ML16011A0612016-02-0202 February 2016 Summary of 10/1/15 Meeting with STP Nuclear Operating Company to Discuss Revised Pilot Submittal and Request for Exemptions for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191 at South Texas Project, Units 1 and 2 (CAC MF Project stage: Meeting ML16088A2432016-04-0101 April 2016 2/18/2016, Summary of Public Meeting with STP Nuclear Operating Company Regarding Open Items, Risk-Informed Generic Safety Issue (GSI) 191 Application and Supplements for South Texas Project, Units 1 and 2 (CAC Nos. MF2400-MF2409) Project stage: Meeting ML16082A5072016-04-11011 April 2016 Request for Additional Information, Phased Response Requested, Exemption and License Amendment Request for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191 (CAC Nos. MF2400-MF2409) Project stage: RAI ML16092A0442016-04-11011 April 2016 Summary of 3/3/2016 Public Meeting with STP Nuclear Operating Company Regarding Open Items, Risk-Informed Generic Safety Issue (GSI) 191 Application and Supplements for South Texas Project, Units 1 and 2 (CAC Nos. MF2400-MF2409) Project stage: Meeting ML16095A0102016-04-13013 April 2016 Summary of November 17-19, 2015 Thermal-Hydraulic Review at Texas A&M University; Pilot Submittal and Request for Exemptions for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191 (CAC MF2400-MF2409) Project stage: Other ML16096A0652016-04-13013 April 2016 Summary of February 4 and 16, 2016, Regulatory Audit at Westinghouse in Rockville, MD, Boric Acid Precipitation, Exemption and License Amendment Request, Risk-Informed Approach to Resolve Generic Safety Issue 191 Project stage: Other ML16092A0852016-04-13013 April 2016 3/17/2016 Summary of Public Meeting with STP Nuclear Operating Company Regarding Open Items, Risk-Informed Generic Safety Issue (GSI) 191 Application and Supplements for South Texas Project, Units 1 and 2 (CAC Nos. MF2401-MF2409) Project stage: Meeting ML16103A3442016-04-26026 April 2016 Summary of February 24-26, 2016 Audit, Debris Transport Review at Alion Science and Technology Corporation, Albuquerque, Nm; Pilot Submittal and Exemption Request, Risk-Informed Approach to Resolve GSI 191 Project stage: Other ML16032A4032016-04-26026 April 2016 FRN, Draft Environmental Assessment and Finding of No Significant Impact, Revise Licensing Basis as Documented in the UFSAR and Request for Exemptions, Risk-Informed Approach to Address GSI-191 (CAC MF2400-MF2409) Project stage: Draft Other ML16032A3872016-04-26026 April 2016 Draft Environmental Assessment and Finding of No Significant Impact, Revise Licensing Basis as Documented in the UFSAR and Request for Exemptions, Risk-Informed Approach to Address GSI-191 (CAC MF2400-MF2409) Project stage: Draft Other ML16127A4002016-05-11011 May 2016 Audit Summary, Thermal-Hydraulic Review on February 23-25, 2016 at Texas A&M University; Pilot Submittal and Request for Exemptions for a Risk-Informed Approach to Resolve Generic Safety Issue 191 (CAC MF2400-MF2409) Project stage: Other ML16125A2902016-05-26026 May 2016 Request for Additional Information, Risk Review, Exemption and License Amendment Request for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191 (CAC Nos. MF2400-MF2409) Project stage: RAI ML16141B0812016-05-31031 May 2016 Audit Summary, Risk Audit on April 12-13, 2016, at Alumni Center at the University of Texas, Austin, Tx; Pilot Generic Safety Issue 191 Submittal and Exemption Request, and Draft Request for Additional Information Project stage: Draft RAI ML16175A1082016-06-24024 June 2016 Summary of 4/21/2016 Public Meeting with STP Nuclear Operating Company Regarding Open Items, Risk-Informed Generic Safety Issue (GSI) 191 Application and Supplements for South Texas Project, Units 1 and 2 Project stage: Meeting ML16190A0082016-07-13013 July 2016 Summary of 6/22/2016 Public Meeting with STP Nuclear Operating Company Regarding Open Items, Risk-Informed Generic Safety Issue (GSI) 191 Application and Supplements for South Texas Project, Units 1 and 2 (CAC Nos. MF2400-MF2409) Project stage: Meeting ML16242A0102016-08-23023 August 2016 NRR E-mail Capture - (External_Sender) FW: South Texas Project GSI-191 Draft Risk Responses to Questions for Public Meeting on August 29, 2016 Project stage: Request ML16242A0092016-08-25025 August 2016 NRR E-mail Capture - (External_Sender) South Texas Project GSI-191 Draft thermal-hydraulic Responses to Questions for Public Meeting on August 29, 2016 Project stage: Request ML16238A5272016-09-0101 September 2016 Summary of 7/28/16, Public Meeting with STP Nuclear Operating Company to Discuss the License Amendment and Exemption Requests to Use a Risk-Informed Approach to the Resolution of GSI-191 (CAC Nos. MF2400 - MF2409) Project stage: Meeting ML16258A3672016-09-0606 September 2016 NRR E-mail Capture - (External_Sender) South Texas Project Generic Safety Issue 191 Resolution SNPB-3-2, Bullet 4 16 -inch Bounding Break Clarification for September 14, 2016 Public Meeting Project stage: Request ML16258A1042016-09-12012 September 2016 NRR E-mail Capture - (External_Sender) South Texas Project Generic Safety Issue 191 Resolution RAI SNPB-3-13 Clarification for September 14, 2016 Public Meeting Project stage: Request ML16258A1002016-09-12012 September 2016 NRR E-mail Capture - (External_Sender) South Texas Project Generic Safety Issue 191 Resolution RAI APLA-3-2 Clarification for September 14, 2016 Public Meeting Project stage: Request ML16258A0962016-09-13013 September 2016 NRR E-mail Capture - (External_Sender) South Texas Project Generic Safety Issue 191 Resolution RAI SSIB-3-4 Clarification for September 14, 2016 Public Meeting Project stage: Request ML16258A0982016-09-13013 September 2016 NRR E-mail Capture - (External_Sender) South Texas Project Generic Safety Issue 191 Resolution RAI 33 Clarification for September 14, 2016 Public Meeting Project stage: Request ML16258A2072016-09-14014 September 2016 NRR E-mail Capture - (External_Sender) South Texas Project Generic Safety Issue 191 Resolution RAI 37 Clarification for September 14, 2016 Public Meeting Project stage: Request ML16258A2082016-09-14014 September 2016 NRR E-mail Capture - (External_Sender) South Texas Project Generic Safety Issue 191 Resolution RAI 34 Clarification for September 14, 2016 Public Meeting Project stage: Request ML16246A0222016-10-0505 October 2016 Summary of Public Meeting with STP Nuclear Operating Company Regarding Open Items Related to Risk-Informed Generic Safety Issue (GSI) 191 Application and Supplements for South Texas Project, Units 1 and 2 (CAC Nos. MF2400 - MF2409) Project stage: Meeting ML16279A3312016-10-27027 October 2016 Summary of Public Meeting with STP Nuclear Operating Company Regarding Open Items, Risk-Informed Generic Safety Issue (GSI) 191 Application and Supplements for South Texas Project, Units 1 and 2 (CAC Nos. MF2400-MF2409) Project stage: Meeting ML16302A4532016-12-12012 December 2016 Closeout of Request for Additional Information Questions That Are No Longer Applicable, Resolution of Generic Safety Issue (GSI) 191 (CAC Nos. MF2400-MF2409) Project stage: RAI ML16351A1502016-12-16016 December 2016 Correction Letter Closeout of Request for Information Questions That Are No Longer Applicable Associated with the Resolution of Generic Safety Issue 191 (CAC Nos. MF2400 - MF2409) Project stage: RAI ML16278A5982017-05-0202 May 2017 Letter, Environmental Assessment and Finding of No Significant Impact, Revise Licensing Basis as Documented in the UFSAR and Request for Exemptions, Risk-Informed Approach to Address GSI-191 (CAC MF2400 to MF2409) Project stage: Other ML17037C8762017-07-11011 July 2017 FRN: Exemption from the Requirements of 10 CFR 50.46 and 10 CFR Part 50, Appendix a, General Design Criteria 35, 38, 41 (CAC Nos. MF2402-MF2409) Project stage: Approval ML17037C8712017-07-11011 July 2017 Letter, Exemption from the Requirements of 10 CFR Part 50, Section 50.46 (CAC Nos. MF2402-MF2409) Project stage: Approval NRC-2016-0092, South Texas Project, Units 1 and 2 - FRN: Exemption from the Requirements of 10 CFR 50.46 and 10 CFR Part 50, Appendix a, General Design Criteria 35, 38, 41 (CAC Nos. MF2402-MF2409)2017-07-11011 July 2017 South Texas Project, Units 1 and 2 - FRN: Exemption from the Requirements of 10 CFR 50.46 and 10 CFR Part 50, Appendix a, General Design Criteria 35, 38, 41 (CAC Nos. MF2402-MF2409) Project stage: Approval 2016-05-26
[Table View] |
Letter, Exemption from the Requirements of 10 CFR Part 50, Section 50.46 (CAC Nos. MF2402-MF2409)ML17037C871 |
Person / Time |
---|
Site: |
South Texas ![STP Nuclear Operating Company icon.png](/w/images/9/9c/STP_Nuclear_Operating_Company_icon.png) |
---|
Issue date: |
07/11/2017 |
---|
From: |
Lisa Regner Plant Licensing Branch IV |
---|
To: |
Gerry Powell South Texas |
---|
Regner L, NRR/DORL/LPLIV, 415-1906 |
References |
---|
CAC MF2402, CAC MF2403, CAC MF2404, CAC MF2405, CAC MF2406, CAC MF2407, CAC MF2408, CAC MF2409, NRC-2016-0092 |
Download: ML17037C871 (18) |
|
|
---|
Category:Exemption from NRC Requirements
MONTHYEARML24086A4242024-07-0101 July 2024 FRN: Issuance of Exemption for South Texas Project ML24086A4232024-06-26026 June 2024 Exemption Decision (Attachment) ML24086A4252024-06-24024 June 2024 Email to Chris Warren Availability of Environmental Assessment for the South Texas Project Exemption ML24102A2452024-04-23023 April 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0046 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23324A0102023-11-16016 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23114A0152023-04-28028 April 2023 Exemption from the Requirements of 10 CFR 20.2206 (EPID L-2023-LLE-0009) (FRN) ML23094A2702023-04-27027 April 2023 Exemption from the Requirements of 10 CFR 20.2206 (EPID L-2023-LLE-0009) (Exemption) ML23094A2712023-04-27027 April 2023 Exemption from the Requirements of 10 CFR 20.2206 (EPID L-2023-LLE-0009) (Letter) ML23103A4322023-04-13013 April 2023 Request for Exemption from 10 CFR 20.2206(c) Due to Issues Obtaining Data ML22094A1762022-04-25025 April 2022 Letter, NRC Granting of Exemption to South Texas Project ISFSI from CoC 1032 for 1 MPC ML22070B1402022-03-11011 March 2022 Independent Spent Fuel Storage Installation Request for Exemption from Certificate of Compliance (CoC) Inspection Requirement for One Multipurpose Canister ML20330A3122020-12-10010 December 2020 Exemption from Annual Force-on-Force Exercise Requirement of 10 CFR Part 73, Appendix B, General Criteria for Security Personnel, Subsection VI.C.3(I)(1) (EPID L-2020-LLE-0205 (COVID-19)) ML20304A2862020-11-20020 November 2020 Federal Register Notice for COVID-19 October 2020 Group Exemptions ML20321A3312020-11-16016 November 2020 Request for a One-Time Exemption from 10 CFR 73, Appendix 8, Section VI, Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic NOC-AE-20003767, Request for a One-Time Exemption from 10 CFR 73, Appendix 8, Section VI, Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic2020-11-16016 November 2020 Request for a One-Time Exemption from 10 CFR 73, Appendix 8, Section VI, Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic NOC-AE-20003756, Exemption Request from 10 CFR 50 Appendix E Due to COVID-19 Pandemic2020-08-11011 August 2020 Exemption Request from 10 CFR 50 Appendix E Due to COVID-19 Pandemic ML20224A2112020-08-11011 August 2020 Exemption Request from 10 CFR 50 Appendix E Due to COVID-19 Pandemic ML20177A6452020-07-15015 July 2020 FRN - Notice of Issuance of Multiple Exemptions Regarding Various Parts of 10 CFR Due to COVID-19 Impacts for June 2020 ML20155K6792020-06-18018 June 2020 Temporary Exemption from Certain Requirements of 10 CFR Part 73, Appendix B, General Criteria for Security Personnel, Section VI (EPID L-2020-LLE-0076 (COVID-19)) ML18129A1312018-03-0808 March 2018 Request for Exemption from the Requirements of 10 CFR 50.47 Without Enclosures 3 and 4 ML17037C8712017-07-11011 July 2017 Letter, Exemption from the Requirements of 10 CFR Part 50, Section 50.46 (CAC Nos. MF2402-MF2409) NOC-AE-13002954, Pilot Submittal and Request for Exemption for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-1912013-01-31031 January 2013 Pilot Submittal and Request for Exemption for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191 ML1124206112011-10-28028 October 2011 Letter, Exemption from the Requirements of 10 CFR Section 50.46 and Appendix K to 10 CFR Part 50 to Allow the Use of Optimized Zirlo as Fuel Rod Cladding Material NRC-2011-0233, South Texas Project, Units 1 and 2 - Exemption from the Requirements of 10 CFR Section 50.46 and Appendix K to 10 CFR Part 50 to Allow the Use of Optimized Zirlo as Fuel Rod Cladding Material (TAC Nos. ME5365 and ME5366)2011-10-27027 October 2011 South Texas Project, Units 1 and 2 - Exemption from the Requirements of 10 CFR Section 50.46 and Appendix K to 10 CFR Part 50 to Allow the Use of Optimized Zirlo as Fuel Rod Cladding Material (TAC Nos. ME5365 and ME5366) ML1124206162011-10-27027 October 2011 Exemption from the Requirements of 10 CFR Section 50.46 and Appendix K to 10 CFR Part 50 to Allow the Use of Optimized Zirlo as Fuel Rod Cladding Material ML1016901072010-07-0202 July 2010 Letter, Exemption from Certain Requirements of 10 CFR Part 26 Revised Fitness for Duty Rule Regarding Managing Fatigue During Severe Weather Conditions ML1016901142010-07-0202 July 2010 Exemption from Certain Requirements of 10 CFR Part 26 Revised Fitness for Duty Rule Regarding Managing Fatigue During Severe Weather Conditions NRC-2010-0162, South Texas Project, Units 1 and 2 - Exemption from Certain Requirements of 10 CFR Part 26 Revised Fitness for Duty Rule Regarding Managing Fatigue During Severe Weather Conditions2010-07-0202 July 2010 South Texas Project, Units 1 and 2 - Exemption from Certain Requirements of 10 CFR Part 26 Revised Fitness for Duty Rule Regarding Managing Fatigue During Severe Weather Conditions ML1003213142010-03-0505 March 2010 Cover Letter, Exemption from Schedule for Compliance with 10 CFR Part 73 Physical Security Requirements ML1003213202010-03-0505 March 2010 Exemption from Schedule for Compliance with 10 CFR Part 73 Physical Security Requirements NRC-2010-0060, South Texas Project, Units 1 and 2 - Exemption from Schedule for Compliance with 10 CFR Part 73 Physical Security Requirements (TAC Nos. ME2873 and ME2874)2010-03-0505 March 2010 South Texas Project, Units 1 and 2 - Exemption from Schedule for Compliance with 10 CFR Part 73 Physical Security Requirements (TAC Nos. ME2873 and ME2874) NOC-AE-09002477, Revised Request for Exemption from Certain Requirements of the Fitness for Duty Rule for Managing Fatigue2009-10-14014 October 2009 Revised Request for Exemption from Certain Requirements of the Fitness for Duty Rule for Managing Fatigue NOC-AE-07002210, Request for Exemption from 10 CFR 50.82(a)(8)2007-09-19019 September 2007 Request for Exemption from 10 CFR 50.82(a)(8) ML0429405192004-10-19019 October 2004 Southtexas Exemption: Commission Has Determined That the Granting of Thus Exemption Will Not Have a Significant Effect on the Quality of the Human Environment 2024-07-01
[Table view] Category:Federal Register Notice
MONTHYEARML24086A4242024-07-0101 July 2024 FRN: Issuance of Exemption for South Texas Project ML24086A4232024-06-26026 June 2024 Exemption Decision (Attachment) ML24086A4152024-06-21021 June 2024 FRN: Notice of Availability of EA-FONSI for South Texas Project ML24130A0012024-05-16016 May 2024 April 2024, Issuance of Multiple Exemptions Regarding Security Notifications, Reports, and Recording Keeping ML23279A0382023-10-30030 October 2023 Associated Independent Spent Fuel Storage Installation - Enclosure 1 -Order Approving Indirect Transfer of Licenses and Draft Conforming License Amendments (EPID L-2023-LLM-0004) (Order) ML23279A0342023-10-30030 October 2023 Associated Independent Spent Fuel Storage Installation - Order Approving Indirect Transfer of Licenses and Draft Conforming License Amendments (EPID L-2023-LLM-0004) (Letter) ML23188A1592023-07-14014 July 2023 the Associated ISFSI - Notice of Consideration of Approval of Indirect Transfer of Licenses and Conforming Amendments and Opportunity to Request a Hearing (EPID L-2023-LLM-0004) - FRN ML23114A0152023-04-28028 April 2023 Exemption from the Requirements of 10 CFR 20.2206 (EPID L-2023-LLE-0009) (FRN) ML23094A2712023-04-27027 April 2023 Exemption from the Requirements of 10 CFR 20.2206 (EPID L-2023-LLE-0009) (Letter) ML22293A0022022-11-30030 November 2022 Environmental Assessment and Finding of No Significant Impact Related to Alternate Disposal Procedures for Very Low-Level Radioactive Material - Transmittal Letter ML22293A0032022-11-30030 November 2022 Environmental Assessment and Finding of No Significant Impact Related to Alternate Disposal Procedures for Very Low-Level Radioactive Material - FRN ML22094A1772022-04-25025 April 2022 Federal Register Notice, NRC Granting of Exemption to South Texas Project ISFSI from CoC 1032 for 1 MPC ML20304A2862020-11-20020 November 2020 Federal Register Notice for COVID-19 October 2020 Group Exemptions ML20177A6452020-07-15015 July 2020 FRN - Notice of Issuance of Multiple Exemptions Regarding Various Parts of 10 CFR Due to COVID-19 Impacts for June 2020 ML19238A3692019-09-0303 September 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 09/10/2019 ML19168A0842019-06-26026 June 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 07/02/2019 ML19140A4562019-05-28028 May 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 06/04/2019 NRC-2018-0287, Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 01/02/20192019-01-0202 January 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 01/02/2019 ML18351A0022019-01-0202 January 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 01/02/2019 ML18173A1792018-08-0707 August 2018 OEDO-17-00070 - Notice of Issuance of Director'S Decision, 2.206 Petition for Emergency Enforcement Action Per 10 CFR 2.206 at Listed U.S. Reactors with Forged Components and Parts Manufactured at France'S AREVA-Le Creusot Forge and Japan C ML17146B1672017-09-28028 September 2017 FRN for Issuance of the Renewed Operating Licenses for South Texas Project, Units 1 and 2 ML17138A2762017-09-19019 September 2017 License Renewal Record of Decision ML17198A3292017-08-30030 August 2017 OEDO-17-00070 - Acknowledgement Letter, Paul Gunter, Beyond Nuclear, Petition for Emergency Enforcement Action Per 10 CFR 2.206 at Listed U.S. Reactors with Forged Components and Parts Manufactured at France'S AREVA-Le Creusot Forge and Jap ML17200A0652017-08-30030 August 2017 OEDO-17-00070 - Acknowledgement FRN, Paul Gunter, Beyond Nuclear, 2.206 Petition for Emergency Enforcement Action Per 10 CFR 2.206 at Listed U.S. Reactors with Forged Components and Parts Manufactured at France'S AREVA-Le Creusot Forge and NRC-2016-0092, South Texas Project, Units 1 and 2 - FRN: Exemption from the Requirements of 10 CFR 50.46 and 10 CFR Part 50, Appendix a, General Design Criteria 35, 38, 41 (CAC Nos. MF2402-MF2409)2017-07-11011 July 2017 South Texas Project, Units 1 and 2 - FRN: Exemption from the Requirements of 10 CFR 50.46 and 10 CFR Part 50, Appendix a, General Design Criteria 35, 38, 41 (CAC Nos. MF2402-MF2409) ML17037C8762017-07-11011 July 2017 FRN: Exemption from the Requirements of 10 CFR 50.46 and 10 CFR Part 50, Appendix a, General Design Criteria 35, 38, 41 (CAC Nos. MF2402-MF2409) ML17037C8712017-07-11011 July 2017 Letter, Exemption from the Requirements of 10 CFR Part 50, Section 50.46 (CAC Nos. MF2402-MF2409) ML16278A5992017-05-0202 May 2017 Environmental Assessment and Finding of No Significant Impact, Revise Licensing Basis as Documented in the UFSAR and Request for Exemptions, Risk-Informed Approach to Address GSI-191 (CAC MF2400 to MF2409) NRC-2016-0100, Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: May 24, 20162016-05-13013 May 2016 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: May 24, 2016 ML16131A7952016-05-13013 May 2016 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: May 24, 2016 ML16032A3872016-04-26026 April 2016 Draft Environmental Assessment and Finding of No Significant Impact, Revise Licensing Basis as Documented in the UFSAR and Request for Exemptions, Risk-Informed Approach to Address GSI-191 (CAC MF2400-MF2409) ML16032A4032016-04-26026 April 2016 FRN, Draft Environmental Assessment and Finding of No Significant Impact, Revise Licensing Basis as Documented in the UFSAR and Request for Exemptions, Risk-Informed Approach to Address GSI-191 (CAC MF2400-MF2409) ML15356A5992015-12-29029 December 2015 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: January 5, 2016 ML15218A6252015-08-14014 August 2015 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: August 14, 2015 ML13252A4022013-11-19019 November 2013 STP FSEIS FRN (Update) ML13225A5572013-08-12012 August 2013 Rescission of Certain Security Orders Concerning Spent Nuclear Fuel in Transit ML12321A3112012-12-18018 December 2012 STP Units 1 and 2, LRA Review ML12321A3512012-12-18018 December 2012 Notice of Availability of the Dseis for Lr of STP, Units 1 and 2, for Public Comment ML12320A6032012-12-13013 December 2012 License Renewal Application Review (THC No. 201002271) ML12339A2652012-12-0505 December 2012 Notice of Availability of the Draft Plant-Specific Supplement 48 to the GEIS for License Renewal of Nuclear Plants Regarding South Texas Project, Units 1 and 2, (TAC ME5122, ME5123, ME4938, and ME4939) ML12195A0852012-12-0505 December 2012 Notice of Availability of the Draft Plant-Specific Supplement 48 to the GEIS for License Renewal of Nuclear Plants Regarding South Texas Project, Units 1 and 2, (TAC Nos. ME5122, ME5123, ME4938, and ME4939) NRC-2012-0196, South Texas Project, Units 1 and 2 - FRN - Withdrawal of License Amendment Request to Approve Revision to Fire Protection Program in Fire Hazards Analysis Report Related to Alternate Shutdown Capability (TAC Nos. ME6346 and ME6347)2012-08-14014 August 2012 South Texas Project, Units 1 and 2 - FRN - Withdrawal of License Amendment Request to Approve Revision to Fire Protection Program in Fire Hazards Analysis Report Related to Alternate Shutdown Capability (TAC Nos. ME6346 and ME6347) ML12222A0262012-08-14014 August 2012 FRN - Withdrawal of License Amendment Request to Approve Revision to Fire Protection Program in Fire Hazards Analysis Report Related to Alternate Shutdown Capability ML12222A0232012-08-14014 August 2012 Letter, Withdrawal of License Amendment Request to Approve Revision to Fire Protection Program in Fire Hazards Analysis Report Related to Alternate Shutdown Capability NRC-2012-0067, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status2012-03-12012 March 2012 Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status ML12056A0442012-03-12012 March 2012 Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status ML1124206162011-10-27027 October 2011 Exemption from the Requirements of 10 CFR Section 50.46 and Appendix K to 10 CFR Part 50 to Allow the Use of Optimized Zirlo as Fuel Rod Cladding Material NRC-2011-0233, South Texas Project, Units 1 and 2 - Exemption from the Requirements of 10 CFR Section 50.46 and Appendix K to 10 CFR Part 50 to Allow the Use of Optimized Zirlo as Fuel Rod Cladding Material (TAC Nos. ME5365 and ME5366)2011-10-27027 October 2011 South Texas Project, Units 1 and 2 - Exemption from the Requirements of 10 CFR Section 50.46 and Appendix K to 10 CFR Part 50 to Allow the Use of Optimized Zirlo as Fuel Rod Cladding Material (TAC Nos. ME5365 and ME5366) ML1124113012011-10-0404 October 2011 FRN: General Notice. South Texas Project, Units 1 and 2 - Environmental Assessment and Finding of No Significant Impact, Proposed Exemption from 10 CFR 50.46 and 10 CFR 50 Appendix K to Allow Use of Optimized Zirlo as Fuel Rod Cladding Mate NRC-2011-0187, Biweekly Sholly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations; Fr Publication Date: 8/23/20112011-08-11011 August 2011 Biweekly Sholly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations; Fr Publication Date: 8/23/2011 2024-07-01
[Table view] Category:Letter
MONTHYEARIR 05000498/20240022024-08-0909 August 2024 Integrated Inspection Report 05000498/2024002 and 05000499/2024002 IR 05000498/20240102024-08-0808 August 2024 Biennial Problem Identification and Resolution Inspection Report 05000498/2024010 and 05000499/2024010 NOC-AE-240040, Application for Order Consenting to Direct Transfer of Licenses2024-07-31031 July 2024 Application for Order Consenting to Direct Transfer of Licenses ML24218A1462024-07-26026 July 2024 2. EPA Comments on South Texas Project Exemption Ea/Fonsi ML24207A1782024-07-25025 July 2024 Licensed Operator Positive Fitness-For-Duty Test IR 05000498/20244042024-06-0303 June 2024 Cyber Security Inspection Report 05000498/2024404 (Cover Letter) ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24136A2842024-05-15015 May 2024 Independent Spent Fuel Storage Installation Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance ML24136A2872024-05-15015 May 2024 Submittal of 2024 Nrc/Fema Evaluated Exercise Scenario Manual NOC-AE-240040, Operator Licensinq Examination Schedule Revision 32024-05-15015 May 2024 Operator Licensinq Examination Schedule Revision 3 ML24128A1572024-05-0707 May 2024 Independent Spent Fuel Storage Installation Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance IR 05000498/20240012024-05-0606 May 2024 Integrated Inspection Report 05000498/2024001 & 05000499/2024001 ML24116A3032024-04-25025 April 2024 Operations Quality Assurance Plan Condition Adverse to Quality Definition Change Resulting in a Reduction in Commitment ML24116A2282024-04-25025 April 2024 Annual Environmental Operating Report ML24117A1602024-04-24024 April 2024 2023 Radioactive Effluent Release Report ML24102A2452024-04-23023 April 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0046 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24113A3122024-04-22022 April 2024 Cycle 24 Core Operating Limits Report NOC-AE-240040, Relief Request Number RR-ENG-4-07 – Request for an Alternative to ASME Code Case N-729-6 for Reactor Vessel Head Penetration 752024-04-0606 April 2024 Relief Request Number RR-ENG-4-07 – Request for an Alternative to ASME Code Case N-729-6 for Reactor Vessel Head Penetration 75 NOC-AE-240040, Financial Assurance for Decommissioning - 2024 Update2024-03-28028 March 2024 Financial Assurance for Decommissioning - 2024 Update ML24081A3972024-03-21021 March 2024 Response to Request for Additional Information for Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML24080A2902024-03-19019 March 2024 Nuclear Liability Certificates of Insurance ML24079A1312024-03-0505 March 2024 Nuclear Insurance Protection ML24060A1742024-02-28028 February 2024 Submittal of Annual Fitness for Duty Performance Report for 2023 IR 05000498/20230062024-02-28028 February 2024 Annual Assessment Letter for South Texas Project Electric Generating Station, Units 1 and 2 (Report 05000498/2023006 and 05000499/2023006) IR 05000498/20240132024-02-27027 February 2024 Design Basis Assurance Inspection (Programs) Commercial Grade Dedication IR 05000498/2024013 and 05000499/2024013 ML24050A0082024-02-19019 February 2024 Evidence of Financial Protection ML24045A0922024-02-16016 February 2024 Response to STP FOF Move Letter (2024) NOC-AE-240040, Unit L & 2, Supplement to Modify the Implementation Date for License Amendment Request to Revise Alternate Source Term Dose Calculation2024-02-0808 February 2024 Unit L & 2, Supplement to Modify the Implementation Date for License Amendment Request to Revise Alternate Source Term Dose Calculation ML24039A1112024-02-0808 February 2024 Operator Licensing Examination Schedule Revision 2 ML24038A3342024-02-0707 February 2024 Change to South Texas Project Electric Generating Station (Stepgs) Emergency Plan ML24033A3002024-02-0707 February 2024 Summary of Regulatory Audit Regarding a Proposed Alternative to ASME Code, Section XI Requirements for Containment Building Inspections ML24029A2752024-01-29029 January 2024 Request to Reschedule Evaluated Force-on-Force Drill IR 05000498/20230042024-01-29029 January 2024 Integrated Inspection Report 05000498/2023004 and 05000499/2023004 ML24024A1162024-01-24024 January 2024 STP Unit 2 Request for Information IR 05000498/20230032023-12-28028 December 2023 Acknowledgment of Reply to a Notice of Violation (NRC Inspection Report 05000498/2023003 and 05000499/2023003) ML23360A1692023-12-26026 December 2023 FEMA, Submittal of Radiological Emergency Preparedness Final Report for the South Texas Project Medical Services Drill Evaluated on August 31, 2023 NOC-AE-230040, Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06)2023-12-14014 December 2023 Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06) NOC-AE-230039, Docket Nos. Stn 50-498, Stn 50-499 - Reply to a Notice of Violation, NRC Inspection Report 05000498/2023003 and 05000499/20230032023-12-12012 December 2023 Docket Nos. Stn 50-498, Stn 50-499 - Reply to a Notice of Violation, NRC Inspection Report 05000498/2023003 and 05000499/2023003 ML23339A1902023-12-0505 December 2023 Update Foreign Ownership, Control, or Influence (FOCI) ML23326A2592023-12-0505 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report IR 05000498/20234012023-12-0404 December 2023 Security Baseline Inspection Report 05000498/2023401 and 05000499/2023401 ML23324A0102023-11-16016 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23310A2282023-11-13013 November 2023 Integrated Inspection Report 05000498/2023003 and 05000499/2023003, and Notice of Violation ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23298A0002023-11-0101 November 2023 the Associated Independent Spent Fuel Storage Installation - Issuance of Amendment Nos. 226 and 211 Related to Order Approving Indirect Transfer of Licenses and Conforming License Amendments ML23279A0342023-10-30030 October 2023 Associated Independent Spent Fuel Storage Installation - Order Approving Indirect Transfer of Licenses and Draft Conforming License Amendments (EPID L-2023-LLM-0004) (Letter) ML23303A0782023-10-30030 October 2023 Submittal of Supplemental Information in Response to Order Consenting to License Transfers and Approval of Draft Conforming License Amendments IR 05000498/20234032023-10-26026 October 2023 Material Control and Accounting Program Inspection Report 05000498/2023403 and 05000499/2023403 (Cover Letter) ML23317A1262023-10-12012 October 2023 South. Texas Project Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program Revision 26 ML23279A1382023-10-0505 October 2023 Responses to Requests for Additional Information Related to Application for Order Approving Indirect Transfer of Control of Licenses 2024-08-09
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 11, 201 7 Mr. G. T. Powell Executive Vice President and CNO STP Nuclear Operating Company South Texas Project P.O. Box 289 Wadsworth, TX 77 483
SUBJECT:
SOUTH TEXAS PROJECT, UNITS 1 AND 2, EXEMPTIONS FROM THE REQUIREMENTS OF 10 CFR PART 50, SECTION 50.46 AND 10 CFR PART 50, APPENDIX A, GENERAL DESIGN CRITERIA 35, 38, AND 41 (CAC NOS. MF2402, MF2403, MF2404, MF2405, MF2406, MF2407, MF2408, AND MF2409)
Dear Mr. Powell:
The U.S. Nuclear Regulatory Commission (NRC) has approved the enclosed exemptions from specific requirements of Title 10 of the Code of Federal Regulations (10 CFR) Section 50.46.
"Acceptance criteria for emergency core cooling systems [ECCS] for light-water nuclear power reactors," and 10 CFR Part 50, Appendix A, General Design Criterion (GDC) 35, "Emergency core cooling, GDC 38, "Containment heat removal, and GDC 41, "Containment atmosphere cleanup" for South Texas Project, Units 1 and 2 (STP).
This action is in response to your application dated June 19, 2013 (Agencywide Documents Access and Management System (ADAMS) Package Accession No. ML131750250), as supplemented by letters dated August 20, 2015, and April 13, 2016 (ADAMS Accession Nos. ML15246A125 and ML16111B204, respectively), in which you requested the exemptions, specified above, under 10 CFR 50.12, "Specific exemptions," accompanied by a license amendment request to approve a pilot risk-informed approach to resolve Generic Safety Issue (GSl)-191, "Assessment of Debris Accumulation on PWR [Pressurized Water Reactor]
Sump Performance," at STP.
STP Nuclear Operating Company (STPNOC) chose to implement a risk-informed option to resolve GSl-191 as allowed by Staff Requirements Memorandum SECY-12-0093, "Closure Options for Generic Safety lssue-191, Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance," dated December 14, 2012. A safety evaluation (SE) was prepared to assess the license amendment requests to modify the STP Updated Final Safety Analysis Report and technical specifications to account for the methodology change. The Commission's safety findings are contained in the SE under ADAMS Accession No. ML17019A002.
STPNOC requested exemptions to use the risk-informed analysis in lieu of a bounding calculation or other deterministic analysis to demonstrate that ECCS and containment spray system (CSS) function is not compromised considering the effects of debris following a loss of coolant accident. The NRC staff relied on its SE as part of the basis for granting the exemptions under 10 CFR 50.12.
G. Powell The Commission determined that the exemptions are authorized by law, will not present an undue risk to the public health and safety, are consistent with the common defense and security, and special circumstances are present pursuant to 10 CFR 50.12(a)(2)(ii). Therefore, the NRC has granted STPNOC a one-time exemption from 10 CFR 50.46, and GDCs 35, 38, and 41, specifically to use a risk-informed methodology in lieu of a deterministic methodology to show compliance with the ECCS and CSS performance criteria accounting for debris in containment for hot-leg breaks greater than 16 inches and those breaks that exceed the plant-specific STP testing threshold.
A copy of the exemption is enclosed. The exemption has been forwarded to the Office of the Federal Register for publication.
Sincerf**
~-~-
Lisa M. Regner, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499
Enclosure:
Exemption cc w/encl: Distribution via Listserv
ENCLOSURE FEDERAL REGISTER NOTICE ML17037C876
[7590-01-P]
NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-498 and 50-499; NRC-2016-0092)
STP Nuclear Operating Company South Texas Project, Units 1 and 2 AGENCY: Nuclear Regulatory Commission.
ACTION: Exemption; issuance.
SUMMARY
- The U.S. Nuclear Regulatory Commission (NRC) is granting exemptions from certain portions of the acceptance criteria for emergency core cooling, and the general design criteria for emergency core cooling, containment heat removal, and atmosphere cleanup for the use of a risk-informed analysis to evaluate the effects of debris in containment following a loss-of-coolant accident (LOCA) for the South Texas Project (STP), Units 1 and 2, located in Matagorda County, Texas, Docket Nos. 50-498 and 50-499, respectively. The exemptions are in response to a request dated June 19, 2013, from the STP Nuclear Operating Company (STPNOC, the licensee) related to STPNOC's proposed approach to resolve a generic safety concern for pressurized water reactors (PWRs) associated with potential clogging of emergency core cooling and containment spray system strainers during certain design basis events.
DATES: The exemption was issued on July 11, 2017.
ADDRESSES: Please refer to Docket ID NRC-2016-0092 when contacting the NRC about the availability of information regarding this document. You may obtain publicly-available information related to this document using any of the following methods:
- Federal Rulemaking Web Site: Go to http://www.requlations.gov and search for Docket ID NRC-2016-0092. Address questions about NRC dockets to Carol Gallagher; telephone: 301-415-3463; e-mail: Carol.Gallaqher@nrc.gov. For technical questions, contact the individual listed in the FOR FURTHER INFORMATION CONTACT section of this document.
- NRC's Agencywide Documents Access and Management System (ADAMS):
You may obtain publicly-available documents online in the ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/adams.html. To begin the search, select "ADAMS Public Documents" and then select "Begin Web-based ADAMS Search." For problems with ADAMS, please contact the NRC's Public Document Room (PDR) reference staff at 1-800-397-4209, 301-415-4737, or by e-mail to pdr.resource@nrc.gov. For the convenience of the reader, the ADAMS accession numbers are provided in a table in the "Availability of Documents" section of this document.
- NRC's PDR: You may examine and purchase copies of public documents at the NRC's PDR, Room 01-F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852.
FOR FURTHER INFORMATION CONTACT: Lisa Regner, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington DC 20555-0001; telephone:
301-415-1906, e-mail: Lisa.Reqner@nrc.gov.
2
SUPPLEMENTARY INFORMATION:
I. Background The licensee is the holder of Facility Operating License Nos. NPF-76 and NPF-80, which authorize operation of the STP Units 1 and 2, respectively. The licenses provide, among other things, that the facility is subject to all rules, regulations, and orders of the NRC now or hereafter in effect. The facility consists of two PWRs located in Matagorda County, Texas.
In 1996, the NRC identified Generic Safety Issue (GSl)-191 associated with the effects of debris accumulation on PWR sump performance during design-basis accidents. As part of the actions to resolve GSl-191, the NRC issued Generic Letter (GL) 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized-Water Reactors," dated September 13, 2004, to holders of operating licenses for PWRs. In GL 2004-02, the NRC staff requested that licensees perform an evaluation of their emergency core cooling systems (ECCS) and containment spray system (CSS) recirculation functions considering the potential for debris-laden coolant to be circulated by the ECCS and the CSS after a LOCA or high energy line break inside containment and, if appropriate, take additional actions to ensure system function. The GL required that licensees provide a written response to the NRC, pursuant to title 10 of the Code of Federal Regulations (10 CFR) section 50.54(f), describing the results of their evaluation and any modifications made, or planned, to ensure the ECCS and CSS remain functional.
II. Request/Action By letter dated June 19, 2013, as supplemented by letters dated August 20, 2015, and April 13, 2016, STPNOC submitted requests for exemptions pursuant to 10 CFR 50.12, "Specific exemptions," from the requirements of 10 CFR 50.46, "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors," and 10 CFR part 50, 3
appendix A, General Design Criterion (GDC) 35, "Emergency core cooling," GDC 38, "Containment heat removal," and GDC 41, "Containment atmosphere cleanup," to use a risk-informed methodology instead of the traditional deterministic methodology, to resolve the concerns associated with GSl-191 and respond to GL 2004-02.
Specifically, the licensee requested an exemption from 10 CFR 50.46(a)(1 )(i), which, in part, requires ECCS cooling performance to be calculated in accordance with an acceptable evaluation model, as described in 10 CFR 50.46(a)(1 ), for postulated LOCAs of different sizes, locations and other properties sufficient to provide assurance that the most severe LOCAs are evaluated in order to demonstrate that acceptance criteria in 10 CFR 50.46(b) are met. The NRC staff interprets the section 50.46(a)(1) requirement to calculate ECCS performance for "other properties" as requiring licensees to consider the impacts of debris generation and transport in containment. The most significant form of debris in nuclear power reactor containments is piping and component insulation that becomes debris during LOCAs, is transported and accumulates in the sumps, and clogs the sumps strainers, thus creating resistance to coolant flow. Fibrous debris from this insulation can also enter the reactor core and directly impede heat transfer from the fuel to the coolant. The licensee also requested exemptions from GDC 35, which contain ECCS performance requirements, and GDCs 38 and 41, which respectively set performance requirements for reactor containment heat removal following a LOCA and for containment atmosphere cleanup following postulated accidents.
The approval of a risk-informed methodology would require exemptions from 10 CFR 50.46(a)(1 )(i) and GDCs 35, 38, and 41 because the NRC has interpreted these regulations as requiring a deterministic approach and bounding calculation to show compliance with ECCS and CSS performance criteria in 50.46(b) and GDCs 35, 38 and 41. Issuance of exemptions is an appropriate means to grant relief from the use of a deterministic approach to show compliance with these requirements.
4
The licensee's 10 CFR 50.46 deterministic analysis considered the debris in containment and demonstrated that the debris loading could prevent acceptable ECCS and CSS operation and core cooling for certain pipe ruptures. Based on its analysis, the licensee concluded that the amount of debris in the. STP containment would need to be reduced to demonstrate compliance with 10 CFR 50.46 criteria using a deterministic analysis for certain large-break LOCA sizes because, for those breaks, the plant-specific testing threshold for generation and transport of debris was exceeded.
Additionally, the licensee's deterministic thermal-hydraulic (TH) analysis could not show that hot-leg LOCAs greater than 16 inches could maintain adequate cooling. While not all large-break hot-leg LOCAs resulted in a loss of in-core cooling due to strainer blockage, the licensee categorized all hot-leg breaks greater than 16 inches as assumed to fail in order to simplify the TH analysis.
The licensee requested exemptions from the requirement to use a deterministic analysis for specific scenarios of LOCA breaks producing and transporting debris in excess of the plant-specific tested debris limits and for large hot-leg breaks. Since it determined that the probability of consequences from debris effects is very low, the licensee requested an exemption to use a risk-informed analysis to show adequate assurance of ECCS and CSS functionality, in accordance with the criteria in Regulatory Guide (RG) 1.174, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis." RG 1.174 was developed in consideration of the Commission's Policy Statements on safety goals and the use of probabilistic risk assessment methods in nuclear regulatory activities ("Safety Goals for the Operations of Nuclear Power Plants; Policy Statement," August 4, 1986, 51 FR 30028; and "Use of Probabilistic Risk Assessment Methods in Nuclear Activities; Final Policy Statement," August 16, 1995, 60 FR 42622, respectively).
Therefore, RG 1.174 provides an acceptable method for licensees and NRC staff to use in 5
assessing the impact of licensing basis changes when the licensee chooses to use risk information.
GDC 35, in part, requires that the ECCS safety system functions adequately to transfer heat from the reactor core following a LOCA and in the presence of a worst single failure, at a rate such that (a) fuel and clad damage that could interfere with continued effective core cooling is prevented and (b) clad metal-water reactor is limited to negligible amounts. The licensee stated in its submittal that the function of the ECCS emergency sump is assumed to fail for debris that exceeds the amount determined in acceptable plant-specific testing. Failure of the sump and strainers result in loss of cooling to the core. The licensee requested an exemption from the deterministic requirements of GDC 35 to use a risk-informed approach to show ECCS function for those LOCA breaks that exceed the plant-specific testing debris threshold, and for large hot-leg breaks. The use of a risk-informed analysis, in accordance with the criteria in RG 1.174, would allow the licensee to show that the risk from debris effects is very low.
GDC 38 requires containment heat removal, rapid reduction of containment pressure and temperature, and maintenance of pressure and temperature at an acceptably low level following a LOCA, and in the presence of a single failure, to preserve containment function. The STPNOC proposed that an exemption be granted from the deterministic requirements in GDC 38, for those LOCA breaks that exceed the plant-specific testing debris threshold. Current STP design basis calculations are based on the reactor containment fan coolers functioning in conjunction with the CSS and ECCS, both of which can be affected by debris. Using deterministic assumptions, STPNOC's analysis and testing does not assure that the emergency sump strainers will be available to support the CSS and ECCS function considering the effects of debris produced by those breaks that can generate and transport debris amounts greater than the plant-specific testing threshold. The licensee requested an exemption from the deterministic requirements of GDC 38 to use a risk-informed analysis, in accordance with the criteria in RG 1.174, to show that the risk from debris effects is very low.
6
GDC 41, in part, requires containment atmosphere cleanup to control substances that may be released into the reactor containment, to reduce the concentration and quality of fission products released to the environment following postulated accidents, and to control the concentration of hydrogen or oxygen and other substances in the containment atmosphere following postulated accidents, assuming a single failure. The licensee stated that using deterministic assumptions, STPNOC's analysis and testing cannot demonstrate that the emergency sump strainers will be available to support the CSS function considering the effects of debris produced and transported by breaks not bounded by acceptable plant-specific testing.
The licensee requested an exemption from the deterministic requirements of GDC 41 to use a risk-informed analysis, in accordance with the criteria in RG 1.174, to show that the risk from debris effects is very low.
Ill. Discussion Pursuant to 10 CFR 50.12, the Commission may, upon application by any interested person or upon its own initiative, grant exemptions from the requirements of 10 CFR part 50, when (1) the exemptions are authorized by law, will not present an undue risk. to public health or safety, and are consistent with the common defense and security; and (2) when special circumstances are present. Under 10 CFR 50.12(a)(2)(ii), special circumstances are present "when application of the regulation in the particular circumstances would not serve the underlying purpose of the rule or is not necessary to achieve the underlying purpose of the rule."
The licensee proposed to use a risk-informed methodology instead of a deterministic approach to account for the effects of debris in containment for portions of the LOCA analysis applicable to breaks that exceed the STP plant-specific debris testing threshold and large hot-leg piping breaks. The STPNOC methodology, termed Risk over Deterministic, or Rovero, divides the loss of core cooling design-basis analysis into two portions: the "deterministic analysis" and the "risk-informed analysis." The risk-informed analysis is used by the licensee for 7
breaks that generate and transport debris exceeding the plant-specific testing threshold. These breaks result in low density fiber glass fiber fines estimated to arrive in the ECCS sump post-LOCA in amounts that are equal to or greater than the amount of fines used in acceptable strainer testing. The acceptable limit was determined using testing methods intended to determine the maximum ECCS strainer head loss for the tested condition.
Also, the licensee evaluated the in-core TH aspects of fibrous debris to prevent adequate fuel cooling, finding that hot-leg breaks greater than 16 inches have the potential to prevent adequate in-core cooling. In order to simplify its TH evaluation, the licensee assumed that all large breaks greater than 16 inches in the hot-leg will result in the loss of the cooling function. For ECCS and CSS analyses other than the postulated large-break LOCAs in the hot-leg piping in containment and those breaks that exceed the STP plant-specific testing limit, STPNOC applied a deterministic methodology. If the exemptions were granted for these postulated breaks, the requirement to use a deterministic methodology for all other postulated LOCA breaks would continue to apply.
A. Special Circumstances Under the regulations in 10 CFR 50.12, the Commission may grant exemptions from the requirements of 10 CFR part 50 provided certain findings are made; namely, that special circumstances are present, the exemptions present no undue risk to public health and safety, the exemptions are consistent with the common defense and security, and the exemptions are authorized by law. The exemptions would allow the licensee to use a risk-informed methodology to show compliance with 10 CFR 50.46(b), and GDCs 35, 38, and 41, specifically for the analyses of debris in containment impacting emergency cooling function during postulated large-break hot-leg LOCAs and those breaks that exceed the plant-specific testing threshold.
8
The licensee requested exemptions citing the special circumstances criteria of 10 CFR 50.12(a)(2)(ii), because compliance in the particular circumstances would not serve the underlying purpose of the rule or is not necessary to achieve the underlying purpose of the rule.
The licensee stated that these special circumstances are common to all of the requested exemptions.
The licensee stated that an objective of each of the regulations for which an exemption is proposed is to maintain low risk to the public health and safety through the adequate functioning of the ECCS and CSS safety systems. These systems must be supported by adequate functioning of the containment sumps. The regulations in 10 CFR 50.46(a)(1 )(i) and GDCs 35, 38, and 41 are met when the licensee is able to demonstrate, using a bounding calculation or other deterministic method that the ECCS and CSS are capable of functioning during design basis events. The STPNOC stated that its risk-informed analysis to show adequate functioning of ECCS and CSS considering the impacts of debris during certain LOCA events demonstrates that the risk of failure of these systems is very small. The licensee stated that special circumstances exist because the underlying intent of the regulations, to ensure adequate protection of public health and safety is met when applying a risk-informed approach to address GSl-191 and respond to GL 2004-02. Further, it states that the risk-informed approach is consistent with RG 1.174, and supports operation of those functions with a high degree of reliability. Thus, the licensee concludes that the underlying intent of each regulation is met and the special circumstances described in 10 CFR 50.12(a)(2)(ii) apply to each of the exemptions proposed by STPNOC.
The NRC staff evaluated the STPNOC submittal and supplements, and discussed the details of its evaluation of the risk-informed approach in an NRC safety evaluation available under ADAMS Accession No. ML17019A001. Although 10 CFR 50.46(a)(1) requires a deterministic approach, the GDCs do not specify that a risk-informed methodology may not be used to show compliance; however, because the NRC has interpreted each of these regulations 9
as requiring a deterministic approach, an exemption is an appropriate means to grant the licensee relief to use an alternative approach. The underlying purpose of each regulation is to protect public health and safety in the event of a LOCA by establishing criteria for emergency core cooling, containment cooling and containment atmosphere cleanup system performance.
In its safety evaluation, the NRC staff concluded, in part, that the licensee adequately demonstrated that the change in risk attributable to debris in postulated hot-leg LOCAs greater than 16 inches, and those breaks that exceed the plant specific threshold, is very small. The NRC staff also concluded that the licensee's proposal for demonstrating compliance with the ECCS and CSS performance requirements meet the risk acceptance guidelines in RG 1.174 because the approach is related to a permissible exemption request, is consistent with defense-in-depth philosophy, maintains sufficient safety margins, results in a small increase in risk, and the impact of this approach is monitored by the licensee using performance measurement strategies. Therefore, the licensee's use of the risk-informed analysis to consider the impacts of debris meets the underlying requirements of 10 CFR 50.46 and GDCs 35, 38, and 41, to ensure that a licensee demonstrates that the ECCS and CSS will provide adequate cooling for the reactor core and containment, as well as containment atmosphere cleanup following postulated design-basis accidents.
Based on the above, the NRC staff concludes that special circumstances under 10 CFR 50.12(a)(2)(ii) exist because compliance with the deterministic requirements of 10 CFR 50.46(a)(1 )(i), and GDCs 35, 38, and 41 is not necessary to achieve the underlying purpose of each rule.
B. The Exemption Presents no Undue Risk to Public Health and Safety The provisions of 10 CFR 50.46 and GDCs 35, 38, and 41 establish criteria for the emergency core cooling, containment cooling, and containment atmosphere cleanup system performance. As part of the amendment requests, the STPNOC submitted exemption requests 10
to change its design-basis analysis specified in the Updated Final Safety Analysis Report (UFSAR) to use new risk-informed and deterministic methodologies to specifically account for the impacts of debris in containment. The licensee justified its use of the risk-informed approach by stating that the proposed risk-informed approach meets the key principles in RG 1.174 in that it is consistent with defense-in-depth philosophy, maintains sufficient safety margins, results in a small increase in risk, and is monitored by the licensee using performance measurement strategies.
Additionally, the licensee stated that the proposed exemptions to use the risk-informed method are consistent with Key Principle 1 in RG 1.174 that requires a proposed change to the licensing basis (or amendment) to meet current regulations unless the change is explicitly related to a requested exemption. The licensee's probabilistic risk analysis results provided by the licensee and evaluated by the NRC staff in its safety evaluation, showed that the increase in risk associated with debris generation and transport on ECCS and CSS function following postulated LOCAs is very low, in accordance with the criteria in RG 1.174.
The NRC staff concluded that the risk is consistent with the guidance in RG 1.174 and with the Commission policy statements on safety goals and the use of probabilistic risk assessment methods in nuclear regulatory activities; therefore, the requested exemption presents no undue risk to public health and safety.
C. The Exemption is Consistent with the Common Defense and Security The requested exemptions to use a risk-informed methodology allow STPNOC to resolve a generic safety concern for PWRs associated with potential clogging of the ECCS and CSS strainers during certain design-basis events. The change is adequately controlled by safety acceptance criteria and technical specification requirements and is not related to security issues. Because the common defense and security is not impacted by the exemption, the exemption is consistent with the common defense and security.
11
D. The Exemptions are Authorized by Law The exemptions to use a risk-informed methodology allow STPNOC to show compliance with 10 CFR 50.46(a)(1 )(i), and GDCs 35, 38, and 41, when considering debris in containment generated and transported during postulated hot-leg LOCA breaks greater than 16 inches, and those breaks that exceed the plant-specific testing threshold. These regulations were promulgated under, and are consistent with the Commission's authority under Section 161 of the Atomic Energy Act. Because the application of a risk-informed methodology to show compliance with 10 CFR part 50.46, and GDC 35, 38, and 41 would not violate the Atomic Energy Act of 1954, as amended, or the Commission's regulations, the exemptions are authorized by law provided all requisite findings are made.
E. Environmental Considerations Pursuant to 10 CFR 51.21, "Criteria for and identification of licensing and regulatory actions requiring environmental assessments," the NRC has prepared an Environmental Assessment (EA) summarizing the findings of its review of the environmental impacts of the proposed action under the National Environmental Policy Act. The NRC staff determined that special circumstances under 10 CFR 51.21 exist to warrant preparation of an EA because STP is the pilot plant to propose a risk-informed approach to resolve GSl-191 as recognized in Staff Requirement Memorandum SECY-12-0093, "Closure Options for Generic Safety lssue-191, Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance," dated December 14, 2012. Because this is the first approval of a risk-informed approach, the NRC staff considered preparations of an EA to be a prudent course of action that would further the purposes of the National Environmental Policy Act. Based on its review, the NRC concluded that an environmental impact statement is not required and that the proposed action will have no significant impact on the environment.
12
The NRC published a final EA on the proposed action in the Federal Register on May 9, 2017 (82 FR 21568).
IV. Conclusions Accordingly, the Commission has determined that, pursuant to 10 CFR 50.12, exemptions are authorized by law, will not present an undue risk to the public health and safety, are consistent with the common defense and security, and special circumstances are present pursuant to 10 CFR 50.12(a)(2)(ii). Therefore, the NRC hereby grants STPNOC a one-time exemption from 10 CFR 50.46(a)(1), and 10 CFR part 50, appendix A, GDCs 35, 38, and 41 to use a risk-informed methodology in lieu of a deterministic methodology to show conformance with the ECCS and CSS performance criteria accounting for debris in containment for large-break hot-leg LOCAs and those breaks that exceed the plant-specific STP testing threshold.
V. Availability of Documents The documents identified in the following table are available for public inspection through the NRC's Agencywide Documents Access and Management System (ADAMS).
Title Date ADAMS Accession No.
! NRC Generic Letter 2004-02, Potential Impact of Debris : 9/13/2004 ML042360586 i Blockage on Emergency Recirculation During Design i Basis Accidents at Pressurized-Water Reactors i STPNOC letter to NRC, Revised STP Pilot Submittal 6/19/2013 ML131750250 1
and Requests for Exemptions and License Amendment (Package) for a Risk-Informed Approach to Resolving Generic
- Submittal and Requests for Exemptions and License (Package)
- Amendment for a Risk-Informed Approach to Address
- Generic Safety Issue (GSl)-191 and Respond to
. Generic Letter (GL) 2004-02 13
Title f Date r ADAMS Accession No.
STPNOC letter to NRC, South Texas Project, Units 1 4/13/2016 ML16111B204 I and 2 - Revision to Proposed Exemption to 10 CFR 50.46 Described in Pilot Submittal and Requests for Exemptions and License Amendment for a Risk-Informed Approach to Address Generic Safety Issue I
I (GSl)-191 and Respond to Generic Letter (GL) 2004-02 f Regulatory Guide 1.174, Revision 2, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing J 5/2011 t
I I
ML100910006 Basis" NRC letter to STPNOC, South Texas Project, Units 1 7/11/2017 ML17019A001 and 2 - Issuance of Amendment Nos. 212 and 198 - (Package)
Risk-Informed Approach to Resolve Generic Safety lssue-191 (includes Safety Evaluation)
ICommission SRM-SECY-12-0093, Staff Requirements 12/14/2012 ML12349A378
- SECY-12-0093 - Closure Options for Generic Safety Issue - 191, Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance
-- --
NRC Letter to STPNOC, South Texas Project, Units 1 5/02/2017 ML16278A598 and 2 - Letter, Environmental Assessment and Finding of No Significant Impact, Revise "Licensing Basis as I Documented in the UFSAR and Request for Exemptions, Risk-Informed approach to Address l GSl-191 Dated at Rockville, Maryland, this 11th day of July 2017.
For the Nuclear Regulatory Commission.
Eric J. Benner, Deputy Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.
14
LTR - ML17037C871 Exemp11on f FRN ML17037C876 *by email OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA N RR/DSS/SRXB/BC* N R R/DSS/SS IB/BC*
NAME LRegner PBlechman EOesterle VCusumano DATE 6/20/17 2/9/17 6/26/17 6/23/17 OFFICE NRR/DORL/LPL4/BC OGC (NLO)* NRR/DORL/DD NRR/DORL/LPL4/PM NAME RPascarelli MYoung EBenner LRegner DATE 7/11/17 6/28/17 7/11/17 7/11/17