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| | number = ML120110167 | | | number = ML120110167 |
| | issue date = 01/19/2012 | | | issue date = 01/19/2012 |
| | title = LaSalle County Station, Unit 1, Request for Additional Information, Regarding Proposed Technical Specification Safety Limit Minimum Critical Power Ratio Changes | | | title = Request for Additional Information, Regarding Proposed Technical Specification Safety Limit Minimum Critical Power Ratio Changes |
| | author name = DiFrancesco N J | | | author name = Difrancesco N |
| | author affiliation = NRC/NRR/DORL/LPLIII-2 | | | author affiliation = NRC/NRR/DORL/LPLIII-2 |
| | addressee name = Pacilio M J | | | addressee name = Pacilio M |
| | addressee affiliation = Exelon Nuclear, Exelon Generation Co, LLC | | | addressee affiliation = Exelon Nuclear, Exelon Generation Co, LLC |
| | docket = 05000373 | | | docket = 05000373 |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 January 2012 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 LASALLE COUNTY STATION, UNIT 1 -REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED TECHNICAL SPECIFICATION SAFETY LIMIT MINIMUM CRITICAL POWER RATIO CHANGES (TAC NO. ME7331) | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 19, 2012 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 |
| | |
| | ==SUBJECT:== |
| | LASALLE COUNTY STATION, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED TECHNICAL SPECIFICATION SAFETY LIMIT MINIMUM CRITICAL POWER RATIO CHANGES (TAC NO. ME7331) |
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| ==Dear Mr. Pacilio:== | | ==Dear Mr. Pacilio:== |
| By letter dated October 12,2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 112860067), Exelon Generation Company, LLC submitted a license amendment request proposing to modify the safety limit minimum critical power ratios contain in Section 2.1 of the technical specifications at LaSalle County Station (LSCS), Unit 1. The basis for the proposed revision was a cycle-specific analysis performed to support operation of LSCS, Unit 1, in the upcoming Cycle 15. The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on January 19, 2012, it was agreed that you would provide a response by February 10, 2012. Please note that if you do not respond to this letter by the agreed-upon date or provide an acceptable alternate date in writing, we may reject your request for approval under the provisions of Title 10 of the Code of Federal Regulations, Section 2.108. The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. Please contact me at 301-415-1115 if you have any questions. '. . / J icholas DiFrancesco, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear reactor Regulation Docket No. 50-373 | | |
| | By letter dated October 12,2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML112860067), Exelon Generation Company, LLC submitted a license amendment request proposing to modify the safety limit minimum critical power ratios contain in Section 2.1 of the technical specifications at LaSalle County Station (LSCS), Unit 1. |
| | The basis for the proposed revision was a cycle-specific analysis performed to support operation of LSCS, Unit 1, in the upcoming Cycle 15. |
| | The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on January 19, 2012, it was agreed that you would provide a response by February 10, 2012. |
| | Please note that if you do not respond to this letter by the agreed-upon date or provide an acceptable alternate date in writing, we may reject your request for approval under the provisions of Title 10 of the Code of Federal Regulations, Section 2.108. |
| | The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. |
| | Please contact me at 301-415-1115 if you have any questions. |
| | incerel \~ |
| | ~ |
| | . /J ~-u---- |
| | icholas DiFrancesco, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear reactor Regulation Docket No. 50-373 |
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| ==Enclosure:== | | ==Enclosure:== |
| As stated cc w/encl: Distribution via ListServ REQUEST FOR ADDITONAL INFORMATION LASALLE COUNTY STATION, UNIT 1 LICENSE AMENDMENT REQUEST REGARDING PROPOSED SAFETY LIMIT MINIMUM CRITICAL POWER RATION CHANGE DOCKET NO. 50-373 By letter dated October 12, 2011 (Agencywide Documents Access and Management System Accession (ADAMS) Accession No. ML 112860067), Exelon Generation Company LLC (Exelon, the licensee) submitted a license amendment request (LAR) proposing to modify technical specification (TS) Section 2.1, "Safety Limits," for LaSalle County Station (LSCS), Unit 1. The requested change involved revised safety limit minimum critical power ratios (SLMCPRs) calculated as a result of the cycle-specific analysis performed by Global Nuclear Fuel (GNF) to support operation in the upcoming LSCS, Unit 1, Cycle 15. The U.S. Nuclear Regulatory Commission (NRC) staff has been reviewing the submittal and has determined that additional information is needed to complete its review. In the LAR, Attachment 6, Tables RAI-06-1 and RAI-06-2, provide core map to show those bundles experienced 0.1 boiling transition criterion of limiting cases for single-loop operation (SLO) and two-loop operation (TLO). Please provide identification of bundle group and number of bundles in the Figure 1, Attachment 5, corresponding to their burnup status (once-burned, twice-burned, or fresh fuel) for Cycle 15. Core design is an iterative process designed to develop an optimal configuration that meets operational requirements. In the LAR, Attachment 7, for the slides titled "Pre-Estimation -Linear Reactivity," please provide the most current updated parameters applicable to LSCS, Unit 1! Cycle 15. Also, provide the details of a plant-specific final core loading pattern as shown in Figure 1 including core design procedures, guidelines, criteria, and approved methodologies used for this Cycle 15 analysis with respect to a mixed core application. GNF2 fuel deviates from traditional 1 Ox1 0 design through the introduction of a length rod configuration, the use of higher linear power, and the use of mixing vanes. NRC staff considers this a new fuel design with regards to the four restrictions identified in safety evaluation of General Electric (GE) Licensing Topical Reports NEDC-32601 P, 32694, and Amendment 25 to NEDE-24011-P-A. Given that LSCS, Unit 1, Cycle 15, uses core loading pattern which includes GNF2 fuel, provide the following: (1) an evaluation of four restrictions in NEDC-32601 P, NEDC-32694 and Amendment 25 to NEDE-24011-P-A the applicability to mixed core with ATRIUM 10 fuel; (2) a description that explains what conditions the methodologies listed in Section 1.0 of Attachment 5 are sufficient applied to the LSCS, Unit 1, Cycle15, application; and (3) a clarification for the statement new GNF2 fuel designs are being introduced in LSCS, Unit 1, Cycle 15," in Section 2.5 Attachment 4. The LSCS, Unit 1, Cycle 15, is a mixed core with once and twice burned ATRIUM 10 Please provide: (1) a detailed description of the methodologies used and procedures to the LSCS, Unit 1, Cycle 15, calculation for the proposed SLMCPR values based on Figure 3, Attachment 5; and (2) justification that the methodologies related to ATRIUM 10 fuel may not be needed in this application because none is listed in Section 1.0, Attachment 5. Please identify the breakdown of the 1 Ox1 0 data shown in Attachment 5, Figure 5, by fuel type (Le., GE14, GNF2). because Figure 5 only shows combined data points for the two fuel types. Also, provide: (1) details of the application of Figure 5 data to a mixed core with ATRIUM 10 fuel; and (2) justification that the estimation formula for SLMCPR value is still valid for LSCS, Unit 1, Cycle 15, application. Please clarify that there is no effect of GNF2 bent spacer wing to LSCS, Unit 1, Cycle 15, operation. If there is an adverse impact, please provide an assessment of the impacts , operations and fuel thermal Please provide an updated version of power/flow map for Cycle 15 operation including stability Option III features of scram region and controlled entry region for backup stability protection based on the Boiling-Water Reactor Owners Group position stated in NEDO-31960A for SLO and TLO.
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| January 19, 2012 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 LASALLE COUNTY STATION, UNIT 1 -REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED TECHNICAL SPECIFICATION SAFETY LIMIT MINIMUM CRITICAL POWER RATIO CHANGES (TAC NO. ME7331)
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| ==Dear Mr. Pacilio:==
| | As stated cc w/encl: Distribution via ListServ |
| By letter dated October 12,2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 112860067), Exelon Generation Company, LLC submitted a license amendment request proposing to modify the safety limit minimum critical power ratios contain in Section 2.1 of the technical specifications at LaSalle County Station (LSCS), Unit 1. The basis for the proposed revision was a cycle-specific analysis performed to support operation of LSCS, Unit 1, in the upcoming Cycle 15. The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on January 19, 2012, it was agreed that you would provide a response by February 10, 2012. Please note that if you do not respond to this letter by the agreed-upon date or provide an acceptable alternate date in writing, we may reject your request for approval under the provisions of Title 10 of the Code of Federal Regulations, Section 2.108. The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. Please contact me at 301-415-1115 if you have any questions. Sincerely, IRA! Nicholas DiFrancesco, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear reactor Regulation Docket No. 50-373 | | |
| | REQUEST FOR ADDITONAL INFORMATION LASALLE COUNTY STATION, UNIT 1 LICENSE AMENDMENT REQUEST REGARDING PROPOSED SAFETY LIMIT MINIMUM CRITICAL POWER RATION CHANGE DOCKET NO. 50-373 By letter dated October 12, 2011 (Agencywide Documents Access and Management System Accession (ADAMS) Accession No. ML112860067), Exelon Generation Company LLC (Exelon, the licensee) submitted a license amendment request (LAR) proposing to modify technical specification (TS) Section 2.1, "Safety Limits," for LaSalle County Station (LSCS), Unit 1. The requested change involved revised safety limit minimum critical power ratios (SLMCPRs) calculated as a result of the cycle-specific analysis performed by Global Nuclear Fuel (GNF) to support operation in the upcoming LSCS, Unit 1, Cycle 15. The U.S. Nuclear Regulatory Commission (NRC) staff has been reviewing the submittal and has determined that additional information is needed to complete its review. |
| | : 1. In the LAR, Attachment 6, Tables RAI-06-1 and RAI-06-2, provide core map to show those bundles experienced 0.1 boiling transition criterion of limiting cases for single-loop operation (SLO) and two-loop operation (TLO). Please provide identification of bundle group and number of bundles in the Figure 1, Attachment 5, corresponding to their burnup status (once-burned, twice-burned, or fresh fuel) for Cycle 15. |
| | : 2. Core design is an iterative process designed to develop an optimal configuration that meets operational requirements. In the LAR, Attachment 7, for the slides titled "Pre-Estimation |
| | - Linear Reactivity," please provide the most current updated parameters applicable to LSCS, Unit 1! Cycle 15. Also, provide the details of a plant-specific final core loading pattern as shown in Figure 1 including core design procedures, guidelines, criteria, and approved methodologies used for this Cycle 15 analysis with respect to a mixed core application. |
| | : 3. GNF2 fuel deviates from traditional 1Ox1 0 design through the introduction of a partial length rod configuration, the use of higher linear power, and the use of mixing vanes. The NRC staff considers this a new fuel design with regards to the four restrictions identified in the safety evaluation of General Electric (GE) Licensing Topical Reports NEDC-32601 P, NEDC 32694, and Amendment 25 to NEDE-24011-P-A. Given that LSCS, Unit 1, Cycle 15, uses a core loading pattern which includes GNF2 fuel, provide the following: (1) an evaluation of the four restrictions in NEDC-32601 P, NEDC-32694 and Amendment 25 to NEDE-24011-P-A and the applicability to mixed core with ATRIUM 10 fuel; (2) a description that explains under what conditions the methodologies listed in Section 1.0 of Attachment 5 are sufficient and applied to the LSCS, Unit 1, Cycle15, application; and (3) a clarification for the statement "no new GNF2 fuel designs are being introduced in LSCS, Unit 1, Cycle 15," in Section 2.5 of Attachment 5. |
| | : 4. The LSCS, Unit 1, Cycle 15, is a mixed core with once and twice burned ATRIUM 10 fuel. |
| | Please provide: (1) a detailed description of the methodologies used and procedures applied |
| | |
| | -2 to the LSCS, Unit 1, Cycle 15, calculation for the proposed SLMCPR values based on Figure 3, Attachment 5; and (2) justification that the methodologies related to ATRIUM 10 fuel may not be needed in this application because none is listed in Section 1.0, Attachment 5. |
| | : 5. Please identify the breakdown of the 1Ox1 0 data shown in Attachment 5, Figure 5, by fuel type (Le., GE14, GNF2). because Figure 5 only shows combined data points for the two fuel types. Also, provide: (1) details of the application of Figure 5 data to a mixed core with ATRIUM 10 fuel; and (2) justification that the estimation formula for SLMCPR value is still valid for LSCS, Unit 1, Cycle 15, application. |
| | : 6. Please clarify that there is no effect of GNF2 bent spacer wing to LSCS, Unit 1, Cycle 15, operation. If there is an adverse impact, please provide an assessment of the impacts on |
| | , operations and fuel thermal performance. |
| | : 7. Please provide an updated version of power/flow map for Cycle 15 operation including stability Option III features of scram region and controlled entry region for backup stability protection based on the Boiling-Water Reactor Owners Group position stated in NEDO-31960A for SLO and TLO. |
|
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| ==Enclosure:==
| | '.. ML120110167 NRR-088 OFFICE LPLlII-2/PM LPLlII-2/LA SRXB/BC LPLlII-2/BC LPLlII-2/PM NAME NDiFrancesco SRohrer TUlyses JZimmerman NDiFrancesco DATE 1/10/12 1/19/12 1/10/12 1/19/12 1/ 19/12}} |
| As stated cc w/enci: Distribution via ListServ DISTRIBUTION: PUBLIC LPL3-2 R/F RidsOgcRp Resource RidsAcrsAcnw_MailCTR Resource RidsNrrSrxb Resource RidsRgn3MailCenter Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl3-2 Resource RidsNrrPMLaSalie Resource RidsNrrLASRohrer Resource ADAMS Accession No'.. ML 120110167 NRR-088 OFFICE LPLlII-2/PM LPLlII-2/LA SRXB/BC LPLlII-2/BC LPLlII-2/PM NAME NDiFrancesco SRohrer TUlyses JZimmerman NDiFrancesco DATE 1/10/12 1/19/12 1/10/12 1/19/12 1/ 19/12 OFFICIAL RECORD COPY
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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
Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes
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County Station Request for Information for NRC Commercial Grade Dedication Inspection: Inspection Report 05000373/2024010 and 05000374/2024010
ML23264A7992023-09-21021 September 2023
NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC – Fleet Request – License Amendment Request to Adopt TSTF-580, Revision 1
ML23264A1512023-09-21021 September 2023
Notification of Upcoming Biennial Problem Identification and Resolution Inspection LaSalle and RFI
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
NRR E-mail Capture - Lasalle 1 and 2 Draft (RAI) License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Proposed Changes to TS Sections 4.3.1 and 5.6.5
IR 05000373/20224032022-04-0707 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
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting
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
ML21049A2572021-02-18018 February 2021
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
County Station - Notification of NRC Design Bases Assurance Inspection (Programs) and Initial Request for Information - Inspection Report 05000373/2021011 and 05000374/2021011
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
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Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding Request for a License Amendment to Technical Specification 3.7.3, Ultimate Heat Sink
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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)
2024-07-12
[Table view]
Category:Letter
MONTHYEARIR 05000373/20243012024-10-31031 October 2024
Initial License Examination Report 05000373/2024301 05000374/2024301
IR 05000373/20244042024-10-23023 October 2024
County Station – Security Baseline Inspection Report 05000373/2024404 and 05000374/2024404
RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024
Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests
05000373/LER-2023-001-01, Air Circuit Breaker (Acb) Mechanically Operated Contacts (MOC) Switch Failed to Actuate2024-10-0909 October 2024
Air Circuit Breaker (Acb) Mechanically Operated Contacts (MOC) Switch Failed to Actuate
ML24275A2442024-10-0303 October 2024
Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing
IR 05000373/20244012024-09-27027 September 2024
County Station – Security Baseline Inspection Report 05000373/2024401 and 05000374/2024401
ML24263A2062024-09-19019 September 2024
Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for LaSalle County Station - Holtec MPC-68MCBS
ML24260A0492024-09-16016 September 2024
Operator Licensing Examination Approval - Lasalle County Station, Unit 1 and 2, September 2024
RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024
Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds
ML24255A8642024-09-0606 September 2024
Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification
ML24249A1362024-09-0404 September 2024
EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21
IR 05000373/20240052024-08-29029 August 2024
Updated Inspection Plan and Assessment Follow-Up Letter for Lasalle County Station (Report 05000373/2024005; 05000374/2024005)
IR 05000373/20244022024-08-28028 August 2024
County Station - Cyber Security Inspection Report 05000373/2024402 and 05000374/2024402
ML24239A3972024-08-23023 August 2024
Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243
05000373/LER-2024-004-01, Emergency Diesel Generator Auto-Start and Load Due to Loss of System Auxiliary Transformer2024-08-22022 August 2024
Emergency Diesel Generator Auto-Start and Load Due to Loss of System Auxiliary Transformer
IR 05000373/20240022024-08-13013 August 2024
County Station - Integrated Inspection Report 05000373/2024002 and 05000374/2024002
ML24222A6772024-08-0909 August 2024
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
IR 05000373/20244202024-08-0505 August 2024
County Station - Security Baseline Inspection Report 05000373 2024420 and 05000374 2024420
05000373/LER-2024-003-01, Supplement to Technical Specification (TS) Limiting Condition for Operation (LCO) 3.6.1.3 Completion Time Exceeded2024-07-31031 July 2024
Supplement to Technical Specification (TS) Limiting Condition for Operation (LCO) 3.6.1.3 Completion Time Exceeded
ML24208A0962024-07-25025 July 2024
57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification
RS-24-064, Nuclear Radiological Emergency Plan Document Revisions2024-06-28028 June 2024
Nuclear Radiological Emergency Plan Document Revisions
ML24178A2522024-06-27027 June 2024
County Station – Acknowledgement of Response to NRC Inspection Report 05000373/2024001 and 05000374/2024001 and Disputed Non-Cited Violation
05000373/LER-2024-004, Emergency Diesel Generator Auto-Start and Load Due to Loss of Station Auxiliary Transformer2024-06-19019 June 2024
Emergency Diesel Generator Auto-Start and Load Due to Loss of Station Auxiliary Transformer
RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024
Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations
05000373/LER-2024-003, Technical Specification (TS) Limiting Condition for Operation (LCO) 3.6.1.3 Completion Time Exceeded2024-06-0606 June 2024
Technical Specification (TS) Limiting Condition for Operation (LCO) 3.6.1.3 Completion Time Exceeded
IR 05000373/20240102024-05-29029 May 2024
County Station - Commercial Grade Dedication Inspection Report 05000373/2024010 and 05000374/2024010
ML24079A0762024-05-23023 May 2024
Issuance of Amendments to Adopt TSTF 264
ML24142A3352024-05-21021 May 2024
Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes
05000373/LER-2024-002, Reactor Protection System Half Scram Due to Motor Generator Set Electric Power Monitoring Assembly Output Breaker Trip2024-05-17017 May 2024
Reactor Protection System Half Scram Due to Motor Generator Set Electric Power Monitoring Assembly Output Breaker Trip
RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024
2023 Corporate Regulatory Commitment Change Summary Report
ML24131A1512024-05-13013 May 2024
County Station - Integrated Report 05000373/2024001 and 05000374/2024001
IR 05000373/20240012024-05-13013 May 2024
County Station - Integrated Report 05000373/2024001 and 05000374/2024001
RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024
Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds
RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024
Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests
05000373/LER-2024-001, Core Operating Limits Report Thermal Limits Exceeded2024-04-26026 April 2024
Core Operating Limits Report Thermal Limits Exceeded
ML24108A1562024-04-15015 April 2024
Updated Final Safety Analysis Report (Ufsar), Revision 26 and Fire Protection Report (Fpr), Revision 11
ML24103A2042024-04-12012 April 2024
Constellation Energy Generation, LLC, 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
RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024
Constellation Energy Generation, LLC - Annual Property Insurance Status Report
ML24071A2122024-03-12012 March 2024
County Station - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection
IR 05000373/20230062024-02-28028 February 2024
Annual Assessment Letter for Lasalle County Station, Units 1 and 2 (Report 05000373/2023006; 05000374/2023006)
RS-24-014, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-02-22022 February 2024
Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
ML24018A0682024-02-0909 February 2024
Issuance of Amendment Nos. 262 and 247 Revised Design Bases of Lower Downcomer Braces
IR 05000373/20230042024-01-24024 January 2024
County Station - Integrated Inspection Report 05000373/2023004 and 05000374/2023004
ML24024A1332024-01-24024 January 2024
Confirmation of Initial License Examination
IR 05000373/20230122024-01-18018 January 2024
County Station - Biennial Problem Identification and Resolution Inspection Report 05000373/2023012 and 05000374/2023012
ML23354A2902024-01-0505 January 2024
Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0028 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
ML23360A6082023-12-27027 December 2023
County Station Request for Information for NRC Commercial Grade Dedication Inspection: Inspection Report 05000373/2024010 and 05000374/2024010
ML23278A1292023-12-14014 December 2023
Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines
ML23305A1402023-12-13013 December 2023
Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580
05000373/LER-2023-002, Turbine Stop Valve Limit Switch Failure Due to Lubricant Degradation2023-12-0404 December 2023
Turbine Stop Valve Limit Switch Failure Due to Lubricant Degradation
2024-09-06
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 19, 2012 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
LASALLE COUNTY STATION, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED TECHNICAL SPECIFICATION SAFETY LIMIT MINIMUM CRITICAL POWER RATIO CHANGES (TAC NO. ME7331)
Dear Mr. Pacilio:
By letter dated October 12,2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML112860067), Exelon Generation Company, LLC submitted a license amendment request proposing to modify the safety limit minimum critical power ratios contain in Section 2.1 of the technical specifications at LaSalle County Station (LSCS), Unit 1.
The basis for the proposed revision was a cycle-specific analysis performed to support operation of LSCS, Unit 1, in the upcoming Cycle 15.
The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on January 19, 2012, it was agreed that you would provide a response by February 10, 2012.
Please note that if you do not respond to this letter by the agreed-upon date or provide an acceptable alternate date in writing, we may reject your request for approval under the provisions of Title 10 of the Code of Federal Regulations, Section 2.108.
The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources.
Please contact me at 301-415-1115 if you have any questions.
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icholas DiFrancesco, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear reactor Regulation Docket No. 50-373
Enclosure:
As stated cc w/encl: Distribution via ListServ
REQUEST FOR ADDITONAL INFORMATION LASALLE COUNTY STATION, UNIT 1 LICENSE AMENDMENT REQUEST REGARDING PROPOSED SAFETY LIMIT MINIMUM CRITICAL POWER RATION CHANGE DOCKET NO. 50-373 By letter dated October 12, 2011 (Agencywide Documents Access and Management System Accession (ADAMS) Accession No. ML112860067), Exelon Generation Company LLC (Exelon, the licensee) submitted a license amendment request (LAR) proposing to modify technical specification (TS) Section 2.1, "Safety Limits," for LaSalle County Station (LSCS), Unit 1. The requested change involved revised safety limit minimum critical power ratios (SLMCPRs) calculated as a result of the cycle-specific analysis performed by Global Nuclear Fuel (GNF) to support operation in the upcoming LSCS, Unit 1, Cycle 15. The U.S. Nuclear Regulatory Commission (NRC) staff has been reviewing the submittal and has determined that additional information is needed to complete its review.
- 1. In the LAR, Attachment 6, Tables RAI-06-1 and RAI-06-2, provide core map to show those bundles experienced 0.1 boiling transition criterion of limiting cases for single-loop operation (SLO) and two-loop operation (TLO). Please provide identification of bundle group and number of bundles in the Figure 1, Attachment 5, corresponding to their burnup status (once-burned, twice-burned, or fresh fuel) for Cycle 15.
- 2. Core design is an iterative process designed to develop an optimal configuration that meets operational requirements. In the LAR, Attachment 7, for the slides titled "Pre-Estimation
- Linear Reactivity," please provide the most current updated parameters applicable to LSCS, Unit 1! Cycle 15. Also, provide the details of a plant-specific final core loading pattern as shown in Figure 1 including core design procedures, guidelines, criteria, and approved methodologies used for this Cycle 15 analysis with respect to a mixed core application.
- 3. GNF2 fuel deviates from traditional 1Ox1 0 design through the introduction of a partial length rod configuration, the use of higher linear power, and the use of mixing vanes. The NRC staff considers this a new fuel design with regards to the four restrictions identified in the safety evaluation of General Electric (GE) Licensing Topical Reports NEDC-32601 P, NEDC 32694, and Amendment 25 to NEDE-24011-P-A. Given that LSCS, Unit 1, Cycle 15, uses a core loading pattern which includes GNF2 fuel, provide the following: (1) an evaluation of the four restrictions in NEDC-32601 P, NEDC-32694 and Amendment 25 to NEDE-24011-P-A and the applicability to mixed core with ATRIUM 10 fuel; (2) a description that explains under what conditions the methodologies listed in Section 1.0 of Attachment 5 are sufficient and applied to the LSCS, Unit 1, Cycle15, application; and (3) a clarification for the statement "no new GNF2 fuel designs are being introduced in LSCS, Unit 1, Cycle 15," in Section 2.5 of Attachment 5.
- 4. The LSCS, Unit 1, Cycle 15, is a mixed core with once and twice burned ATRIUM 10 fuel.
Please provide: (1) a detailed description of the methodologies used and procedures applied
-2 to the LSCS, Unit 1, Cycle 15, calculation for the proposed SLMCPR values based on Figure 3, Attachment 5; and (2) justification that the methodologies related to ATRIUM 10 fuel may not be needed in this application because none is listed in Section 1.0, Attachment 5.
- 5. Please identify the breakdown of the 1Ox1 0 data shown in Attachment 5, Figure 5, by fuel type (Le., GE14, GNF2). because Figure 5 only shows combined data points for the two fuel types. Also, provide: (1) details of the application of Figure 5 data to a mixed core with ATRIUM 10 fuel; and (2) justification that the estimation formula for SLMCPR value is still valid for LSCS, Unit 1, Cycle 15, application.
- 6. Please clarify that there is no effect of GNF2 bent spacer wing to LSCS, Unit 1, Cycle 15, operation. If there is an adverse impact, please provide an assessment of the impacts on
, operations and fuel thermal performance.
- 7. Please provide an updated version of power/flow map for Cycle 15 operation including stability Option III features of scram region and controlled entry region for backup stability protection based on the Boiling-Water Reactor Owners Group position stated in NEDO-31960A for SLO and TLO.
'.. ML120110167 NRR-088 OFFICE LPLlII-2/PM LPLlII-2/LA SRXB/BC LPLlII-2/BC LPLlII-2/PM NAME NDiFrancesco SRohrer TUlyses JZimmerman NDiFrancesco DATE 1/10/12 1/19/12 1/10/12 1/19/12 1/ 19/12
