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| | number = ML17181A197 | | | number = ML17181A197 |
| | issue date = 07/10/2017 | | | issue date = 07/10/2017 |
| | title = Non-Acceptance with Supplemental Information Required Letter to Licensee - I4R-01 Request (CAC MF9758 CAC MF9759) | | | title = Non-Acceptance with Supplemental Information Required Letter to Licensee - I4R-01 Request |
| | author name = Vaidya B K | | | author name = Vaidya B |
| | author affiliation = NRC/NRR/DORL/LPLIII | | | author affiliation = NRC/NRR/DORL/LPLIII |
| | addressee name = Hanson B C | | | addressee name = Hanson B |
| | addressee affiliation = Exelon Generation Co, LLC | | | addressee affiliation = Exelon Generation Co, LLC |
| | docket = 05000373, 05000374 | | | docket = 05000373, 05000374 |
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Line 14: |
| | page count = 4 | | | page count = 4 |
| | project = CAC:MF9758, CAC:MF9759 | | | project = CAC:MF9758, CAC:MF9759 |
| | stage = Supplement | | | stage = Other |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:Mr. Bryan C. Hanson Senior Vice President UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 10, 2017 Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO) Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 10, 2017 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO) |
| | Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LASALLE COUNTY STATION, UNITS 1 AND 2, SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE REVIEW OF REQUESTED LICENSING ACTION RE: RELIEF REQUEST RE: FOURTH 10-YEAR INSERVICE INSPECTION INTERVAL PROGRAM RELIEF REQUEST NO. 14R-01 (CAC NOS. MF9758 AND MF9759) | | LASALLE COUNTY STATION, UNITS 1 AND 2, SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE REVIEW OF REQUESTED LICENSING ACTION RE: RELIEF REQUEST RE: FOURTH 10-YEAR INSERVICE INSPECTION INTERVAL PROGRAM RELIEF REQUEST NO. 14R-01 (CAC NOS. MF9758 AND MF9759) |
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| ==Dear Mr. Hanson:== | | ==Dear Mr. Hanson:== |
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| By letter dated May 30, 2017, Exelon Generation Company, LLC (EGC, the licensee) submitted a request for the fourth 10-year inservice inspection (ISi) interval program regarding relief request (RR) for LaSalle County Station (LSCS), Units 1 and 2. The fourth interval of the LSCS ISi program is currently scheduled to begin on October 1, 2017, and end on September 30, 2027, and will comply with the American Society of Mechanical Engineers Boiler and Pressure Vessel (ASME Code) Code, Section XI, 2007 Edition with the 2008 Addenda. EGC requested the following: | | By letter dated May 30, 2017, Exelon Generation Company, LLC (EGC, the licensee) submitted a request for the fourth 10-year inservice inspection (ISi) interval program regarding relief request (RR) for LaSalle County Station (LSCS), Units 1 and 2. The fourth interval of the LSCS ISi program is currently scheduled to begin on October 1, 2017, and end on September 30, 2027, and will comply with the American Society of Mechanical Engineers Boiler and Pressure Vessel (ASME Code) Code, Section XI, 2007 Edition with the 2008 Addenda. EGC requested the following: |
| * 14R-01 requests approval of alternative risk-informed ISi program and examination criteria for Examination Category 8-F, 8-J, C-F-1, and C-F-2, pressure retaining piping welds in accordance with ASME Code Case N-578-1, "Risk-Informed Requirements for Class 1, 2, or 3 Piping, Method B, Section XI, Division 1." The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this RR. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. Pursuant to Sections 50.55a(z)(1) and 50.55a(z)(2) of Title 10 of the Code of Federal Regulations (10 CFR), the applicant shall demonstrate that the proposed alternatives would provide an acceptable level of quality and safety, or that compliance with the specified requirements of Section 50.55a would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety. | | * 14R-01 requests approval of alternative risk-informed ISi program and examination criteria for Examination Category 8-F, 8-J, C-F-1, and C-F-2, pressure retaining piping welds in accordance with ASME Code Case N-578-1, "Risk-Informed Requirements for Class 1, 2, or 3 Piping, Method B, Section XI, Division 1." |
| B. Hanson The NRC staff has reviewed your application and concluded that the information delineated in the enclosure to this letter is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed amendment/relief request in terms of regulatory requirements and the protection of public health and safety and the environment. ln order to make the application complete, the NRC staff requests that EGC supplement the application to address the information requested in the enclosure by July 27, 2017. This will enable the staff to begin its detailed technical review. If the information responsive to the staff's request is not received by the above date, the application will not be accepted for review pursuant to 1 O CFR 2.101, and the NRC will cease its review activities associated with the application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the staff's detailed technical review by separate correspondence. The information requested and associated time frame in this letter were agreed upon during the telephone discussion with your staff on July 10, 2017. If you have any questions, please contact me at (301) 415-3308. Docket Nos. 50-373 and 50-374 | | The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this RR. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. |
| | Pursuant to Sections 50.55a(z)(1) and 50.55a(z)(2) of Title 10 of the Code of Federal Regulations (10 CFR), the applicant shall demonstrate that the proposed alternatives would provide an acceptable level of quality and safety, or that compliance with the specified requirements of Section 50.55a would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety. |
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| | B. Hanson The NRC staff has reviewed your application and concluded that the information delineated in the enclosure to this letter is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed amendment/relief request in terms of regulatory requirements and the protection of public health and safety and the environment. |
| | ln order to make the application complete, the NRC staff requests that EGC supplement the application to address the information requested in the enclosure by July 27, 2017. This will enable the staff to begin its detailed technical review. If the information responsive to the staff's request is not received by the above date, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC will cease its review activities associated with the application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the staff's detailed technical review by separate correspondence. |
| | The information requested and associated time frame in this letter were agreed upon during the telephone discussion with your staff on July 10, 2017. |
| | If you have any questions, please contact me at (301) 415-3308. |
| | Sincerely, Bhalchandra Vaidya, Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374 |
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| ==Enclosure:== | | ==Enclosure:== |
| Request for supplemental Information cc: Distribution via ListServ Sincerely, Bhalchandra Vaidya, Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Background-UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 REQUEST FOR SUPPLEMENTAL INFORMATION NEEDED REGARDING RELIEF REQUEST NO. 14R-01 FOR LA SALLE COUNTY STATION {LSCS), UNITS 1 AND 2 DOCKET NOS. 50-373 AND 50-374 {CAC NOS. MF9758 AND MF9759) After reviewing relief request (RR) No. 14R-01, it is not clear if there have been any probabilistic risk assessment (PRA) upgrades, since 2008. The licensee has properly used their latest PRA model but the U.S. Nuclear Regulatory Commission (NRC) staff was not able to verify if the latest model has been peer reviewed based on the information provided in the RR. It appears that no peer review has been conducted since 2008. Additionally, the 2008 peer review used only Revision O of Regulatory Guide (RG) 1.200, rather than the current Revision 2. The RR states that Exelon Generation Company (EGG, the licensee) pertormed a self-assessment against Revision 1 of AG 1.200, but to date there does not appear to be any documentation verifying that a self-assessment against Revision 2 of AG 1.200 has been completed. Supplemental Information Needed from Licensee-The licensee is using a risk-informed approach to support the inservice inspection interval program. Provide the documentation to demonstrate the technical adequacy of their PAA against Revision 2 of AG 1.200 as described below: | | |
| | Request for supplemental Information cc: Distribution via ListServ |
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| | UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 REQUEST FOR SUPPLEMENTAL INFORMATION NEEDED REGARDING RELIEF REQUEST NO. 14R-01 FOR LA SALLE COUNTY STATION {LSCS), UNITS 1 AND 2 DOCKET NOS. 50-373 AND 50-374 |
| | {CAC NOS. MF9758 AND MF9759) |
| | Background-After reviewing relief request (RR) No. 14R-01, it is not clear if there have been any probabilistic risk assessment (PRA) upgrades, since 2008. The licensee has properly used their latest PRA model but the U.S. Nuclear Regulatory Commission (NRC) staff was not able to verify if the latest model has been peer reviewed based on the information provided in the RR. It appears that no peer review has been conducted since 2008. Additionally, the 2008 peer review used only Revision O of Regulatory Guide (RG) 1.200, rather than the current Revision 2. The RR states that Exelon Generation Company (EGG, the licensee) pertormed a self-assessment against Revision 1 of AG 1.200, but to date there does not appear to be any documentation verifying that a self-assessment against Revision 2 of AG 1.200 has been completed. |
| | Supplemental Information Needed from Licensee-The licensee is using a risk-informed approach to support the inservice inspection interval program. Provide the documentation to demonstrate the technical adequacy of their PAA against Revision 2 of AG 1.200 as described below: |
| * In Enclosure LS-LAR-007 to Attachment 1 of the licensee submission (page 11 of 25), it is stated that "the most recent update of the LaSalle PAA model (designated the LS2014A model) was completed in November 2015 as a regularly scheduled update to the previous LS2011A model." | | * In Enclosure LS-LAR-007 to Attachment 1 of the licensee submission (page 11 of 25), it is stated that "the most recent update of the LaSalle PAA model (designated the LS2014A model) was completed in November 2015 as a regularly scheduled update to the previous LS2011A model." |
| * Provide details of all changes to the PRA model since the version reviewed by the 2008 peer review (you may group changes such as "data refinements," but be specific as to other changes, e.g., changes in model structure or methods), justifying whether or not, the change constitutes PAA upgrade as defined in the ASME/ANS [American Society of Mechanical Engineers/American Nuclear Society) PAA standard -"new should be interpreted as new to the subject PRA even though the methodology in question has been applied in other PRAs" [Section 1-A. 1 of ASME/ANS RA-Sa-2009]. | | * Provide details of all changes to the PRA model since the version reviewed by the 2008 peer review (you may group changes such as "data refinements," but be specific as to other changes, e.g., changes in model structure or methods), justifying whether or not, the change constitutes PAA upgrade as defined in the ASME/ANS [American Society of Mechanical Engineers/American Nuclear Society) PAA standard - "new should be interpreted as new to the subject PRA even though the methodology in question has been applied in other PRAs" [Section 1-A. 1 of ASME/ANS RA-Sa-2009]. |
| * If any changes constitute an upgrade, pertorm a focused scope peer review on the affected technical elements (including affected high level requirements as well as all supporting requirements) and provide the results of the review complete with the Facts and Observations/Findings and dispositions addressing any effect upon the application. Enclosure B. Hanson | | * If any changes constitute an upgrade, pertorm a focused scope peer review on the affected technical elements (including affected high level requirements as well as all supporting requirements) and provide the results of the review complete with the Facts and Observations/Findings and dispositions addressing any effect upon the application. |
| | Enclosure |
| | |
| | B. Hanson |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LASALLE COUNTY STATION, UNITS 1AND2, SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE REVIEW OF REQUESTED LICENSING ACTION RE: RELIEF REQUEST RE FOURTH 10-YEAR NO. 14R-01 (CAC NOS. MF9758 AND MF9759) DATED JULY 10, 2017 DISTRIBUTION: PUBLIC LPL3 R/F RidsNrrPMLaSalle Resource RidsRgn3MailCenter Resource RidsOgcRp Resource RidsNrrOorllp13 Resource ADAMS A ccess1on: ML17181A197 OFFICE NRR/DORL/LPL3/PM NAME BVaidya DATE 07/10/17 OFFICE NRR/DORL/LPL3/BC NAME DWrona DATE 07/10/17 RidsNrrDraApla Resource RidsNrrlASRohrer Resource RidsAcrs_MailCTR Resource LFields, NRR/DRNAPLA RGalucci, NRR/DRNAPLA *N btt'lh o su s an 1a c anoe 1n th eema1 I NRR/DORL/LPL3/LA NRR/DRNAPLNBC SRohrer SRosenberg* 07/05/17 06/27/17 NRR/DORL/LPL3/PM BVaidya 07/10/17 OFFICIAL RECORD COPY | | LASALLE COUNTY STATION, UNITS 1AND2, SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE REVIEW OF REQUESTED LICENSING ACTION RE: RELIEF REQUEST RE FOURTH 10-YEAR NO. 14R-01 (CAC NOS. MF9758 AND MF9759) DATED JULY 10, 2017 DISTRIBUTION: |
| }} | | PUBLIC RidsNrrDraApla Resource LPL3 R/F RidsNrrlASRohrer Resource RidsNrrPMLaSalle Resource RidsAcrs_MailCTR Resource RidsRgn3MailCenter Resource LFields, NRR/DRNAPLA RidsOgcRp Resource RGalucci, NRR/DRNAPLA RidsNrrOorllp13 Resource ADAMS A ccess1on: ML17181A197 *N o su b stant '1al h c anoe 1n th eema1 I OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DRNAPLNBC NAME BVaidya SRohrer SRosenberg* |
| | DATE 07/10/17 07/05/17 06/27/17 OFFICE NRR/DORL/LPL3/BC NRR/DORL/LPL3/PM NAME DWrona BVaidya DATE 07/10/17 07/10/17 OFFICIAL RECORD COPY}} |
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Category:Letter
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Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition
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RS-23-120, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023
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2024-09-06
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24197A0162024-07-12012 July 2024
NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC - Fleet Request - License Amendment Request to Adopt TSTF-591
ML24142A3352024-05-21021 May 2024
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ML23360A6082023-12-27027 December 2023
County Station Request for Information for NRC Commercial Grade Dedication Inspection: Inspection Report 05000373/2024010 and 05000374/2024010
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NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC Fleet Request License Amendment Request to Adopt TSTF-580, Revision 1
ML23208A3182023-07-27027 July 2023
Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and RFI
ML23153A1562023-06-0202 June 2023
NRR E-mail Capture - RAI LaSalle pressure-temperature Limits Report (PTLR) Amendment Request
ML23150A2482023-05-25025 May 2023
NRR E-mail Capture - RAI Re LaSalle Downcomer Analysis Amendment Request
ML23110A3202023-04-21021 April 2023
Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection
ML22361A0792022-12-27027 December 2022
Notification of NRC Baseline Inspection and Request for Information (05000374/2023001)
ML22256A0112022-09-12012 September 2022
NRR E-mail Capture - Request for Additional Information LaSalle County Station, Units 1 and 2 and Quad Cities Nuclear Power Station, Units 1 and 2 License Amendments Related to Fuel Storage
ML22138A4112022-05-18018 May 2022
NRR E-mail Capture - Lasalle 1 and 2 - (RAI) License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Changes to TS Sections 4.3.1 and 5.6.5 (EPID-L-2021-LLA-0124)
ML22126A0392022-05-0606 May 2022
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ML22097A0832022-04-0707 April 2022
County Station Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000373/2022403 and 05000374/2022403
ML22062B0232022-03-0303 March 2022
NRR E-mail Capture - EPID-L-2022-LLR-0028, LaSalle Unit 1, Request for Additional Information (Rai), LaSalle Unit 1, Relief Request I4R-13 Relief from Code Examinations for 1B33-F060A and 1B33-F060B Repairs
ML22041B5362022-02-10010 February 2022
NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541
ML22020A0642022-01-13013 January 2022
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles
ML21292A1782021-10-19019 October 2021
Information Request for a NRC Post-Approval Site Inspection for License Renewal 05000373/2022010
ML21256A1902021-09-10010 September 2021
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application
ML21207A0072021-07-26026 July 2021
NRR E-mail Capture - La Salle Units 1 and 2 - Request for Additional Information (RAI) License Amendment Request to Incorporate Licensing Topical Report NEDE-33885P-A, Revision 1, GNF CRDA Application Methodology(EPID-L-2021-LLA-0016)
ML21190A0192021-07-0808 July 2021
NRR E-mail Capture - Exelon Fleet - Request for Additional Information Regarding Adoption of TSTF-582 and TSTF-583-T
ML21187A2972021-07-0707 July 2021
Information Request for an NRC Triennial 10 CFR 50.59 (Evaluation of Changes, Tests, and Experiments) Baseline Inspection
ML21144A2132021-05-24024 May 2021
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application
ML21117A0342021-05-0505 May 2021
Request for Additional Information Regarding Proposed Alternative to Use ASME Code Case N-893
ML21119A2282021-04-29029 April 2021
NRR E-mail Capture - Request for Additional Information (RAI) - LaSalle, EPID-L-2020-LLA-0018, License Amendment Request (LAR) TSTF-505
ML21077A1902021-03-18018 March 2021
NRR E-mail Capture - Lasalle Units 1 and 2 - Request for Additional Information (RAI) Request for License Amendment Regarding Ultimate Heat Sink, (EPID-L-2020-LLA-0165)
ML21068A2762021-03-0909 March 2021
NRR E-mail Capture - La Salle Units 1 and 2 - Request for Additional Information (RAI) Relief Request I4R-12 Relief from Code Surface Examinations for 2B33-F060B Valve Repair (EPID-L-2020-LLA-0016)
ML21067A6752021-03-0808 March 2021
NRR E-mail Capture - La Salle Units 1 and 2 - Request for Additional Information (RAI) UHS Amendment Request (EPID-L-2020-LLA-0165)
ML21060B4352021-03-0101 March 2021
NRR E-mail Capture - Second Round - Request for Additional Information (Rais) EPID-L-2020-LLA-0018, LaSalle License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2
ML21062A0652021-03-0101 March 2021
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ML21053A0252021-02-20020 February 2021
NRR E-mail Capture - Request for Additional Information (Rais) - LaSalle Request for Exemption from Pre-Access Drug and Alcohol Testing
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Request for Additional Information Byron/Dresden Proposed Changes to Site Emergency Plans to Support Post-Shutdown and Permanently Defueled Conditions (EPID-2020-LLA-0240 & EPID-2020-LLA-0237)
ML21048A0432021-02-16016 February 2021
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ML20364A2452020-12-29029 December 2020
Notification of an NRC Triennial Heat Sink Performance Inspection and Request for Information; Inspection Report 05000373/2021002; 05000374/2021002
ML20346A1042020-12-11011 December 2020
NRR E-mail Capture - LaSalle County Station, Units 1 and 2 - Request for Additional Information Regarding the License Amendment Request to Adopt 10 CFR 50.69
ML20330A1892020-11-25025 November 2020
Request for Information for an NRC Post-Approval Site Inspection for License Renewal; Inspection Report 05000374/2021010
ML20321A0852020-11-16016 November 2020
Notification of NRC Baseline Inspection and Request for Information (05000374/2021001)
ML20247J4082020-09-29029 September 2020
Apla Request for Additional Information LAR 50.69 and TSTF-505 (Epids L-2020-LLA-0017) and
ML20253A3422020-09-17017 September 2020
Correction to Request for Additional Information Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (EPID-2020-LLA-0017)
ML20253A2272020-09-16016 September 2020
Correction to Request for Additional Information Application to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
ML20240A2182020-09-0303 September 2020
Request for Additional Information Regarding Amendment Request for Amendments to Renewed Facility Operating Licenses to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Co
ML20239A7262020-08-27027 August 2020
Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding Request for a License Amendment to Technical Specification 3.7.3, Ultimate Heat Sink
ML20239A7982020-08-25025 August 2020
NRR E-mail Capture - Exelon Generation Company, LLC - Fleet License Amendment Request to Adopt TSTF-568, Revision 2
ML19275H1362019-10-0202 October 2019
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Request to Use ASME Code Case N-879
ML19179A0612019-07-19019 July 2019
Three Mile Point 1 - Supplemental Information Needed to Proposed Alternative to Use ASME Code Case N-879
ML19120A2302019-04-29029 April 2019
Ltr. 04/29/19 LaSalle County Station, Units 1 and 2 - Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team); Inspection Report 05000373/2019012; 05000374/2019012 (DRS-M.Jones)
ML19087A2682019-03-28028 March 2019
NRR E-mail Capture - Request for Additional Information (RAI) - LaSalle 1 and 2, EPID-L-2018-LLA-0162, LAR Removal of Operating Mode Restrictions for Performing Surveillance Testing of the Div 3 Battery and HPCS DG
ML19065A0902019-03-0505 March 2019
NRR E-mail Capture - LaSalle 1 and 2, EPID-L-2018-LLR-0162, LAR Removal of Operating Mode Restrictions for Performing Surveillance Testing of the Div 3 Battery and HPCS DG, Additional Draft Request for Additional Information (RAI)
ML19058A2392019-02-27027 February 2019
Information Request to Support Upcoming Problem Identification and Resolution Inspection at LaSalle County Station, Units 1 and 2
ML19036A6562019-02-0505 February 2019
NRR E-mail Capture - LaSalle 1 and 2, EPID-L-2018-LLR-0123, Relief Request I3R-15, Third Inservice Inspection Interval, Request for Additional Information (RAI)
ML19050A0042019-01-22022 January 2019
NRR E-mail Capture - LaSalle 1 and 2, EPID-L-2018-LLR-0162, LAR Removal of Operating Mode Restrictions for Performing Surveillance Testing of the Div 3 Battery and HPCS DG, Draft Request for Additional Information (RAI)
2024-07-12
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Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 10, 2017 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO)
Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
LASALLE COUNTY STATION, UNITS 1 AND 2, SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE REVIEW OF REQUESTED LICENSING ACTION RE: RELIEF REQUEST RE: FOURTH 10-YEAR INSERVICE INSPECTION INTERVAL PROGRAM RELIEF REQUEST NO. 14R-01 (CAC NOS. MF9758 AND MF9759)
Dear Mr. Hanson:
By letter dated May 30, 2017, Exelon Generation Company, LLC (EGC, the licensee) submitted a request for the fourth 10-year inservice inspection (ISi) interval program regarding relief request (RR) for LaSalle County Station (LSCS), Units 1 and 2. The fourth interval of the LSCS ISi program is currently scheduled to begin on October 1, 2017, and end on September 30, 2027, and will comply with the American Society of Mechanical Engineers Boiler and Pressure Vessel (ASME Code) Code,Section XI, 2007 Edition with the 2008 Addenda. EGC requested the following:
- 14R-01 requests approval of alternative risk-informed ISi program and examination criteria for Examination Category 8-F, 8-J, C-F-1, and C-F-2, pressure retaining piping welds in accordance with ASME Code Case N-578-1, "Risk-Informed Requirements for Class 1, 2, or 3 Piping, Method B,Section XI, Division 1."
The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this RR. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
Pursuant to Sections 50.55a(z)(1) and 50.55a(z)(2) of Title 10 of the Code of Federal Regulations (10 CFR), the applicant shall demonstrate that the proposed alternatives would provide an acceptable level of quality and safety, or that compliance with the specified requirements of Section 50.55a would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety.
B. Hanson The NRC staff has reviewed your application and concluded that the information delineated in the enclosure to this letter is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed amendment/relief request in terms of regulatory requirements and the protection of public health and safety and the environment.
ln order to make the application complete, the NRC staff requests that EGC supplement the application to address the information requested in the enclosure by July 27, 2017. This will enable the staff to begin its detailed technical review. If the information responsive to the staff's request is not received by the above date, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC will cease its review activities associated with the application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the staff's detailed technical review by separate correspondence.
The information requested and associated time frame in this letter were agreed upon during the telephone discussion with your staff on July 10, 2017.
If you have any questions, please contact me at (301) 415-3308.
Sincerely, Bhalchandra Vaidya, Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374
Enclosure:
Request for supplemental Information cc: Distribution via ListServ
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 REQUEST FOR SUPPLEMENTAL INFORMATION NEEDED REGARDING RELIEF REQUEST NO. 14R-01 FOR LA SALLE COUNTY STATION {LSCS), UNITS 1 AND 2 DOCKET NOS. 50-373 AND 50-374
{CAC NOS. MF9758 AND MF9759)
Background-After reviewing relief request (RR) No. 14R-01, it is not clear if there have been any probabilistic risk assessment (PRA) upgrades, since 2008. The licensee has properly used their latest PRA model but the U.S. Nuclear Regulatory Commission (NRC) staff was not able to verify if the latest model has been peer reviewed based on the information provided in the RR. It appears that no peer review has been conducted since 2008. Additionally, the 2008 peer review used only Revision O of Regulatory Guide (RG) 1.200, rather than the current Revision 2. The RR states that Exelon Generation Company (EGG, the licensee) pertormed a self-assessment against Revision 1 of AG 1.200, but to date there does not appear to be any documentation verifying that a self-assessment against Revision 2 of AG 1.200 has been completed.
Supplemental Information Needed from Licensee-The licensee is using a risk-informed approach to support the inservice inspection interval program. Provide the documentation to demonstrate the technical adequacy of their PAA against Revision 2 of AG 1.200 as described below:
- In Enclosure LS-LAR-007 to Attachment 1 of the licensee submission (page 11 of 25), it is stated that "the most recent update of the LaSalle PAA model (designated the LS2014A model) was completed in November 2015 as a regularly scheduled update to the previous LS2011A model."
- Provide details of all changes to the PRA model since the version reviewed by the 2008 peer review (you may group changes such as "data refinements," but be specific as to other changes, e.g., changes in model structure or methods), justifying whether or not, the change constitutes PAA upgrade as defined in the ASME/ANS [American Society of Mechanical Engineers/American Nuclear Society) PAA standard - "new should be interpreted as new to the subject PRA even though the methodology in question has been applied in other PRAs" [Section 1-A. 1 of ASME/ANS RA-Sa-2009].
- If any changes constitute an upgrade, pertorm a focused scope peer review on the affected technical elements (including affected high level requirements as well as all supporting requirements) and provide the results of the review complete with the Facts and Observations/Findings and dispositions addressing any effect upon the application.
Enclosure
B. Hanson
SUBJECT:
LASALLE COUNTY STATION, UNITS 1AND2, SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE REVIEW OF REQUESTED LICENSING ACTION RE: RELIEF REQUEST RE FOURTH 10-YEAR NO. 14R-01 (CAC NOS. MF9758 AND MF9759) DATED JULY 10, 2017 DISTRIBUTION:
PUBLIC RidsNrrDraApla Resource LPL3 R/F RidsNrrlASRohrer Resource RidsNrrPMLaSalle Resource RidsAcrs_MailCTR Resource RidsRgn3MailCenter Resource LFields, NRR/DRNAPLA RidsOgcRp Resource RGalucci, NRR/DRNAPLA RidsNrrOorllp13 Resource ADAMS A ccess1on: ML17181A197 *N o su b stant '1al h c anoe 1n th eema1 I OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DRNAPLNBC NAME BVaidya SRohrer SRosenberg*
DATE 07/10/17 07/05/17 06/27/17 OFFICE NRR/DORL/LPL3/BC NRR/DORL/LPL3/PM NAME DWrona BVaidya DATE 07/10/17 07/10/17 OFFICIAL RECORD COPY
