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| | issue date = 11/19/2010 | | | issue date = 11/19/2010 |
| | title = Request for Additional Information, Related to the Use of Neutron Absorbing Inserts | | | title = Request for Additional Information, Related to the Use of Neutron Absorbing Inserts |
| | author name = Brown E A | | | author name = Brown E |
| | 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 | | | addressee affiliation = Exelon Nuclear |
| | docket = 05000373, 05000374 | | | docket = 05000373, 05000374 |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 19, 2010 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 |
| November 19, 2010 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 LASALLE COUNTY STATION, UNITS 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE USE OF NEUTRON ABSORBING INSERTS (T AC NOS. ME2376 AND ME2377) | | |
| | ==SUBJECT:== |
| | LASALLE COUNTY STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE USE OF NEUTRON ABSORBING INSERTS (TAC NOS. ME2376 AND ME2377) |
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| ==Dear Mr. Pacilio:== | | ==Dear Mr. Pacilio:== |
| By letter to the Nuclear Regulatory Commission (NRC) dated October 5, 2009 (Agencywide Documents Access and Management Systems Package No. ML092810278),as supplemented in a letter dated June 10, 2010 (ADAMS Accession No. ML 101650229), Exelon Generation Company, LLC submitted a request to revise Technical Specification (TS) Section 4.3.1, "Criticality," to address a non-conservative TS, for the LaSalle County Station, Units 1 and 2. The proposed change addresses the Boraflex degradation issue in the Unit 2 spent fuel storage racks by revising TS Section 4.3.1 to allow the use of NETCO-SNAP-IN rack inserts in Unit 2 spent fuel storage rack cells as a replacement for the neutron absorbing properties of the existing Boraflex panels. 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 Mr. Ken Nicely of your staff on November 19, 2010, it was agreed that a response would be provided within 30 days from the date of this letter. | | |
| M. Pacilio -Please note that if you do not respond to this letter within the prescribed response time, or provide an acceptable alternate date in writing, we may reject your application for amendment under the provisions of 10 CFR Section 2.108. Should you need to contact me, I can be reached at (301) 415-2315. | | By letter to the Nuclear Regulatory Commission (NRC) dated October 5, 2009 (Agencywide Documents Access and Management Systems Package No. ML092810278),as supplemented in a letter dated June 10, 2010 (ADAMS Accession No. ML101650229), Exelon Generation Company, LLC submitted a request to revise Technical Specification (TS) Section 4.3.1, "Criticality," to address a non-conservative TS, for the LaSalle County Station, Units 1 and 2. |
| Sincerely, IRA! Eva A. Brown, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and Request for Additional cc w/encl: Distribution via Listserv REQUEST FOR ADDITIONAL INFORMATION NETCOINSERTS EXELON GENERATION COMPANY, LLC LASALLE COUNTY STATION, UNITS 1 AND 2 DOCKET NOS. 50-373 AND 50-374 Technical Specification (TS) 4.3.1.a states: "keff s 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.1.2 of the UFSAR; ... " Explain the controls that exist or that will be developed so that recent and proposed changes to Updated Final Safety Analysis Report Section 9.1.2 and associated analyses will be comprehensively evaluated to ensure that such changes do not challenge the inputs, assumptions, and methods, which form the bases for this license amendment request. Identify the major parameters, values, uncertainties and/or assumptions in the criticality analysis that ensures that keff s 0.95 if fully flooded with unborated water. Provide a list of those analyses/calculations which were used to establish compliance with the requirements of 10 CFR 50.68(b)(4). Section 4.3.1 of NUREG-1433, "Standard Technical Specifications, General Electric Plants, BWRl4," includes a description of the assembly maximum U-235 enrichment limit. Address why a similar limit was not included with the proposed change. The current license amendment request indicates the NETCO-SNAP-IN rack inserts will not be installed in all useable storage cells until 2016. In the interim, the licensee will continue to credit BORAFLEXTM in those storage modules that do not have SNAP-IN rack inserts. Some of the cells for which the licensee intends to continue crediting BORAFLEXTM and fuel assemblies have degraded below the minimum B-10 areal density of 0.020 gm/cm used in the analysis of record as described in the June 15,1989, safety evaluation (ADAMS Accession No. ML021140183). | | The proposed change addresses the Boraflex degradation issue in the Unit 2 spent fuel storage racks by revising TS Section 4.3.1 to allow the use of NETCO-SNAP-IN rack inserts in Unit 2 spent fuel storage rack cells as a replacement for the neutron absorbing properties of the existing Boraflex panels. |
| With respect to the crediting of degraded BORAFLEXTM, provide the following information: A description of the nuclear criticality safety analysis performed to demonstrate the acceptability of storing fuel in cells with BORAFLEX Ž below the a B-10 areal density of 0.020 gm/cm 2; A description of the measures to be used to account for unknowns or uncertainties in a. above; and A description of the measures to prevent a misloading during fuel handling or a justification explaining why the consequences of such an event would be acceptable.
| | 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 Mr. Ken Nicely of your staff on November 19, 2010, it was agreed that a response would be provided within 30 days from the date of this letter. |
| ' Section 50.36( c)(4 ) to Title 10 of the Code of Federal Regulations, requires that the Design Features section of the TS shall include" ... features of the facility such as materials of construction and geometric arrangements, which, if altered or modified, would have a significant effect on safety and are not covered in categories described in paragraphs (c) (1), (2), and (3) of this section." Given LaSalle's plans to rely on the 8-10 content of the rack inserts in the Unit 2 spent fuel pool, provide a description of those administrative controls that will be put in place to ensure that 8-10 content of the NETCO-SNAP-IN rack inserts will be consistent with what is assumed in the rack inserts and analyses.
| | |
| M. Pacilio Please note that if you do not respond to this letter within the prescribed response time, or provide an acceptable alternate date in writing, we may reject your application for amendment under the provisions of 10 CFR Section 2.108. Should you need to contact me, I can be reached at (301) 415-2315.
| | M. Pacilio - 2 Please note that if you do not respond to this letter within the prescribed response time, or provide an acceptable alternate date in writing, we may reject your application for amendment under the provisions of 10 CFR Section 2.108. Should you need to contact me, I can be reached at (301) 415-2315. |
| Sincerely, IRA! Eva A. Brown, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374
| | Sincerely, IRA! |
| | Eva A. Brown, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374 |
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| ==Enclosure:== | | ==Enclosure:== |
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| |
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| Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION: | | Request for Additional Information cc w/encl: Distribution via Listserv |
| PUBLIC LPL3-2 RlF RidsNrrPMLaSalie Resource RidsNrrLA THarris Resource RidsOgcRp Resource RidsRgn3MailCenter Resource RidsAcrsAcnw_MailCTR Resource ADAMS Accession No ML 103210499 NRR-088 RidsNrrDorlLpl3-2 Resource RidsNrrDorlDpr Resource ABiloch, NRR *via email dated OFFICE LPL3-2/PM LPL3-2/LA SRXB/BC LPL3-2/BC LPL3-2/PM NAME EBrown THarris AUlses* RCarlson EBrown DATE 11/18/10 11/18/10 11/18/10 11/19/10 11/19/10 OFFICIAL RECORD}}
| | |
| | REQUEST FOR ADDITIONAL INFORMATION NETCOINSERTS EXELON GENERATION COMPANY, LLC LASALLE COUNTY STATION, UNITS 1 AND 2 DOCKET NOS. 50-373 AND 50-374 |
| | : 1. Technical Specification (TS) 4.3.1.a states: |
| | "keff s 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.1.2 of the UFSAR; ... " |
| | : a. Explain the controls that exist or that will be developed so that recent and proposed changes to Updated Final Safety Analysis Report Section 9.1.2 and associated analyses will be comprehensively evaluated to ensure that such changes do not challenge the inputs, assumptions, and methods, which form the bases for this license amendment request. |
| | : b. Identify the major parameters, values, uncertainties and/or assumptions in the criticality analysis that ensures that keff s 0.95 if fully flooded with unborated water. |
| | : c. Provide a list of those analyses/calculations which were used to establish compliance with the requirements of 10 CFR 50.68(b)(4). |
| | : 2. Section 4.3.1 of NUREG-1433, "Standard Technical Specifications, General Electric Plants, BWRl4," includes a description of the assembly maximum U-235 enrichment limit. Address why a similar limit was not included with the proposed change. |
| | : 3. The current license amendment request indicates the NETCO-SNAP-IN rack inserts will not be installed in all useable storage cells until 2016. In the interim, the licensee will continue to credit BORAFLEXTM in those storage modules that do not have NETCO SNAP-IN rack inserts. Some of the cells for which the licensee intends to continue crediting BORAFLEXTM and storin~ fuel assemblies have degraded below the minimum B-10 areal density of 0.020 gm/cm used in the analysis of record as described in the June 15,1989, safety evaluation (ADAMS Accession No. ML021140183). With respect to the crediting of degraded BORAFLEXTM, provide the following information: |
| | : a. A description of the nuclear criticality safety analysis performed to demonstrate the acceptability of storing fuel in cells with BORAFLEX ' below the a B-10 areal density of 0.020 gm/cm 2 ; |
| | : b. A description of the measures to be used to account for unknowns or uncertainties in a. above; and |
| | |
| | -2 |
| | : c. A description of the measures to prevent a misloading during fuel handling or a justification explaining why the consequences of such an event would be acceptable. ' |
| | : 4. Section 50.36( c) (4 ) to Title 10 of the Code of Federal Regulations, requires that the Design Features section of the TS shall include" ... features of the facility such as materials of construction and geometric arrangements, which, if altered or modified, would have a significant effect on safety and are not covered in categories described in paragraphs (c) (1), (2), and (3) of this section." Given LaSalle's plans to rely on the 8-10 content of the rack inserts in the Unit 2 spent fuel pool, provide a description of those administrative controls that will be put in place to ensure that 8-10 content of the NETCO-SNAP-IN rack inserts will be consistent with what is assumed in the rack inserts and analyses. |
| | |
| | ML103210499 NRR-088 *via email dated SRXB/BC LPL3-2/PM OFFICE LPL3-2/PM LPL3-2/LA LPL3-2/BC AUlses* RCarlson EBrown NAME EBrown THarris 11/18/10 11/18/10 11/18/10 11/19/10 11/19/10 DATE}} |
Letter Sequence RAI |
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MONTHYEARRS-09-133, Attachment 6, LaSalle, Unit 2, Nuclear Power Station Spent Fuel Storage Pool Criticality Safety Analysis with Neutron Absorbing Inserts and Without Boraflex2009-08-31031 August 2009
Attachment 6, LaSalle, Unit 2, Nuclear Power Station Spent Fuel Storage Pool Criticality Safety Analysis with Neutron Absorbing Inserts and Without Boraflex
Project stage: Request
ML0931705992009-12-0202 December 2009
Request for Withholding Information from Public Disclosure by Letter Dated 10/5/09
Project stage: Withholding Request Acceptance
ML1009802092010-04-26026 April 2010
Request for Additional Information Related to License Amendment Request Regarding the Use of Neutron Absorbing Inserts in Unit 2 Spent Fuel Pool Storage Racks
Project stage: RAI
ML1011904862010-05-0303 May 2010
Notice of Meeting with Exelon, LaSalle, Units 1 and 2, to Discuss Response to Request for Additional Information License Amendment Request Regarding the Use of Neutron Absorbing Inserts in Spent Fuel Pool Storage Racks
Project stage: RAI
ML1016502292010-06-10010 June 2010
Additional Information Supporting License Amendment Request Regarding the Use of Neutron Absorbing Inserts in Unit 2 Spent Fuel Pool Storage Racks
Project stage: Other
ML1016502862010-06-23023 June 2010
June 1, 2010, Summary of Meeting with Exelon Generation Co., LLC, on Responses to Request for Information License Amendment Request for the Use of Netco-SNAP-In Rack Inserts
Project stage: RAI
ML1028003592010-10-0707 October 2010
Notice of Public Meeting with Exelon Generation Company, LLC, Regarding LaSalle Netco Insert Request
Project stage: Meeting
ML1030004242010-10-28028 October 2010
Notice of Meeting with Exelon Genertion Company to Discuss the License Amendment Request to Allow Full Recovery of Spent Fuel Storage Rack Cells That Are Unusable Due to Boraflex Neutron Absorber Degradation
Project stage: Meeting
ML1030704842010-11-19019 November 2010
Summary of Public Meeting with Exelon Generation Company, LLC Regarding LaSalle Netco Insert Request
Project stage: Meeting
ML1030903782010-11-19019 November 2010
Licensee Handouts for LaSalle Meeting with Exelon to Discuss Netco Inserts
Project stage: Meeting
ML1032104992010-11-19019 November 2010
Request for Additional Information, Related to the Use of Neutron Absorbing Inserts
Project stage: RAI
RS-10-202, Additional Information Supporting License Amendment Request Re Use of Neutron Absorbing Inserts in Unit 2 Spent Fuel Pool Storage Racks2010-11-23023 November 2010
Additional Information Supporting License Amendment Request Re Use of Neutron Absorbing Inserts in Unit 2 Spent Fuel Pool Storage Racks
Project stage: Request
ML1034304232010-12-10010 December 2010
Request for Additional Information Related to the Use of Nuetron Absorbing Inserts
Project stage: RAI
RS-10-210, Additional Information Supporting License Amendment Request Regarding the Use of Neutron Absorbing Inserts in Unit 2 Spent Fuel Pool Storage Racks2010-12-14014 December 2010
Additional Information Supporting License Amendment Request Regarding the Use of Neutron Absorbing Inserts in Unit 2 Spent Fuel Pool Storage Racks
Project stage: Request
ML1034904622010-12-16016 December 2010
Notice of Meeting with Exelon Generation Company, LLC Regarding LaSalle Netco Insert Request
Project stage: Meeting
RS-10-216, Additional Information Supporting License Amendment Request Regarding the Use of Neutron Absorbing Inserts in Unit 2 Spent Fuel Pool Storage Racks2010-12-22022 December 2010
Additional Information Supporting License Amendment Request Regarding the Use of Neutron Absorbing Inserts in Unit 2 Spent Fuel Pool Storage Racks
Project stage: Request
ML1100503592010-12-29029 December 2010
NRC Meeting Slides for December 29, 2010, Public Conference Call with Exelon Generation Company Regarding LaSalle Netco Insert Request
Project stage: Meeting
ML1101300742011-01-11011 January 2011
Additional Information Supporting License Amendment Request Regarding the Use of Neutron Absorbing Inserts in Unit 2 Spent Fuel Pool Storage Racks
Project stage: Request
ML1100502552011-01-17017 January 2011
December 29, 2010, Summary of Public Conference Call with Exelon Generation Company, LLC, Regarding LaSalle Netco Insert Request
Project stage: Other
ML1101803312011-01-24024 January 2011
Proposed License Conditions Related to Use of Neutron Absorbers
Project stage: Other
RS-11-009, Additional Information Supporting License Amendment Request Regarding the Use of Neutron Absorbing Inserts in Unit 2 Spent Fuel Pool Storage Racks2011-01-24024 January 2011
Additional Information Supporting License Amendment Request Regarding the Use of Neutron Absorbing Inserts in Unit 2 Spent Fuel Pool Storage Racks
Project stage: Request
ML1102500512011-01-28028 January 2011
Issuance of Amendments Concerning Spent Fuel Neutron Absorbers
Project stage: Approval
RS-11-014, Additional Information Supporting License Amendment Request Regarding the Use of Neutron Absorbing Inserts in Unit 2 Spent Fuel Pool Storage Racks2011-01-28028 January 2011
Additional Information Supporting License Amendment Request Regarding the Use of Neutron Absorbing Inserts in Unit 2 Spent Fuel Pool Storage Racks
Project stage: Request
ML1104606172011-03-0404 March 2011
Request for Additional Inforamtion Related to the Use of Neutron Absorbing Inserts
Project stage: Other
RS-11-067, Response to Request for Additional Information Regarding Unit 2 Spent Fuel Pool Storage Racks2011-04-18018 April 2011
Response to Request for Additional Information Regarding Unit 2 Spent Fuel Pool Storage Racks
Project stage: Response to RAI
RS-11-109, Completion of License Condition 2.C.(30) Associated with Unit 2 Spent Fuel Pool Storage Racks2011-07-13013 July 2011
Completion of License Condition 2.C.(30) Associated with Unit 2 Spent Fuel Pool Storage Racks
Project stage: Other
RS-11-170, Completion of License Condition 2.C.(31) Associated with Unit 2 Spent Fuel Pool Storage Racks2011-10-20020 October 2011
Completion of License Condition 2.C.(31) Associated with Unit 2 Spent Fuel Pool Storage Racks
Project stage: Other
2010-04-26
[Table View] |
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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
ML23360A6082023-12-27027 December 2023
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
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
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
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
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)
ML19022A2552019-01-22022 January 2019
NRR E-mail Capture - LaSalle Units 1 and 2, EPID-L-2018-LLA-0035, Amendment Request to Adopt TSTF-334-A, Status of Revised Draft RAIs Sent to You on December 13, 2018
2024-07-12
[Table view]
Category:Letter
MONTHYEARIR 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
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
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
IR 05000373/20240102024-05-29029 May 2024
County Station - Commercial Grade Dedication Inspection Report 05000373/2024010 and 05000374/2024010
ML24142A3352024-05-21021 May 2024
Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes
RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024
2023 Corporate Regulatory Commitment Change Summary Report
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
ML24108A1562024-04-15015 April 2024
Updated Final Safety Analysis Report (Ufsar), Revision 26 and Fire Protection Report (Fpr), Revision 11
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
RS-23-120, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023
Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information
ML23317A1192023-11-10010 November 2023
Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums
IR 05000373/20230032023-11-0909 November 2023
County Station Integrated Inspection Report 05000373/2023003, 05000374/2023003, and 07200070/2023001
ML23286A2602023-11-0808 November 2023
Issuance of Amendment Nos. 260 and 245 to Renewed Facility Operating Licenses Relocation of Pressure and Temperature Limit Curves to the Pressure Temperature Report
IR 05000373/20234012023-11-0707 November 2023
County Station Security Baseline Inspection Report 05000373/2023401 and 05000374/2023401
RS-23-103, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023
Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans
IR 05000374/20230102023-10-11011 October 2023
NRC Inspection Report 05000374/2023010
IR 05000373/20233012023-09-15015 September 2023
Errata to NRC Initial License Examination Report 05000373/2023301; 05000374/2023301
RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023
Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs
RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023
Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor
ML23212A9012023-08-0303 August 2023
Regulatory Audit Report to Support the Review of the Amendments to Relocation of the Pressure Temperature Limit Curves to the Pressure and Temperature Limits Report
IR 05000373/20230022023-08-0101 August 2023
County Station - Integrated Inspection Report 05000373/2023002 and 05000374/2023002
ML23208A3182023-07-27027 July 2023
Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and RFI
RS-23-084, Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis2023-07-24024 July 2023
Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis
ML23192A5272023-07-12012 July 2023
NRC Initial License Examination Report 05000373/2023301; 05000374/2023301
ML23186A2062023-07-0606 July 2023
Information Request for a NRC Post-Approval Site Inspection for License Renewal 05000374/2023010
ML23181A1502023-06-30030 June 2023
Combined Response to Request for Additional Information and Supplemental Information in Support of LAR to Relocate Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report
ML23178A2422023-06-28028 June 2023
Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III
IR 05000373/20230112023-06-26026 June 2023
County Station - Quadrennial Fire Protection Team Inspection Report 05000373/2023011 and 05000374/2023011
RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023
Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations
ML23167A0352023-06-16016 June 2023
Registration of Use of Cask to Store Spent Fuel
ML23171A9562023-06-12012 June 2023
Post Exam Ltr
RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023
Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling
IR 05000373/20230012023-05-10010 May 2023
County Station - Integrated Inspection Report 05000373/2023001 and 05000374/2023001
ML23123A2202023-05-0303 May 2023
Relief Request I4R-14 for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection
ML23118A3472023-05-0101 May 2023
County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Correction of Amendment No. 193 Adoption of TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration EPID L-2022-LLA-0143
ML23121A1612023-05-0101 May 2023
Information Meeting (Open House) with a Question-and-Answer Session to Discuss NRC 2022 End-of-Cycle Plant Performance Assessment of LaSalle County Station, Units 1 and 2
ML23114A2522023-04-28028 April 2023
Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI
2024-08-09
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 19, 2010 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
LASALLE COUNTY STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE USE OF NEUTRON ABSORBING INSERTS (TAC NOS. ME2376 AND ME2377)
Dear Mr. Pacilio:
By letter to the Nuclear Regulatory Commission (NRC) dated October 5, 2009 (Agencywide Documents Access and Management Systems Package No. ML092810278),as supplemented in a letter dated June 10, 2010 (ADAMS Accession No. ML101650229), Exelon Generation Company, LLC submitted a request to revise Technical Specification (TS) Section 4.3.1, "Criticality," to address a non-conservative TS, for the LaSalle County Station, Units 1 and 2.
The proposed change addresses the Boraflex degradation issue in the Unit 2 spent fuel storage racks by revising TS Section 4.3.1 to allow the use of NETCO-SNAP-IN rack inserts in Unit 2 spent fuel storage rack cells as a replacement for the neutron absorbing properties of the existing Boraflex panels.
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 Mr. Ken Nicely of your staff on November 19, 2010, it was agreed that a response would be provided within 30 days from the date of this letter.
M. Pacilio - 2 Please note that if you do not respond to this letter within the prescribed response time, or provide an acceptable alternate date in writing, we may reject your application for amendment under the provisions of 10 CFR Section 2.108. Should you need to contact me, I can be reached at (301) 415-2315.
Sincerely, IRA!
Eva A. Brown, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION NETCOINSERTS EXELON GENERATION COMPANY, LLC LASALLE COUNTY STATION, UNITS 1 AND 2 DOCKET NOS. 50-373 AND 50-374
- 1. Technical Specification (TS) 4.3.1.a states:
"keff s 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.1.2 of the UFSAR; ... "
- a. Explain the controls that exist or that will be developed so that recent and proposed changes to Updated Final Safety Analysis Report Section 9.1.2 and associated analyses will be comprehensively evaluated to ensure that such changes do not challenge the inputs, assumptions, and methods, which form the bases for this license amendment request.
- b. Identify the major parameters, values, uncertainties and/or assumptions in the criticality analysis that ensures that keff s 0.95 if fully flooded with unborated water.
- c. Provide a list of those analyses/calculations which were used to establish compliance with the requirements of 10 CFR 50.68(b)(4).
- 2. Section 4.3.1 of NUREG-1433, "Standard Technical Specifications, General Electric Plants, BWRl4," includes a description of the assembly maximum U-235 enrichment limit. Address why a similar limit was not included with the proposed change.
- 3. The current license amendment request indicates the NETCO-SNAP-IN rack inserts will not be installed in all useable storage cells until 2016. In the interim, the licensee will continue to credit BORAFLEXTM in those storage modules that do not have NETCO SNAP-IN rack inserts. Some of the cells for which the licensee intends to continue crediting BORAFLEXTM and storin~ fuel assemblies have degraded below the minimum B-10 areal density of 0.020 gm/cm used in the analysis of record as described in the June 15,1989, safety evaluation (ADAMS Accession No. ML021140183). With respect to the crediting of degraded BORAFLEXTM, provide the following information:
- a. A description of the nuclear criticality safety analysis performed to demonstrate the acceptability of storing fuel in cells with BORAFLEX ' below the a B-10 areal density of 0.020 gm/cm 2 ;
- b. A description of the measures to be used to account for unknowns or uncertainties in a. above; and
-2
- c. A description of the measures to prevent a misloading during fuel handling or a justification explaining why the consequences of such an event would be acceptable. '
- 4. Section 50.36( c) (4 ) to Title 10 of the Code of Federal Regulations, requires that the Design Features section of the TS shall include" ... features of the facility such as materials of construction and geometric arrangements, which, if altered or modified, would have a significant effect on safety and are not covered in categories described in paragraphs (c) (1), (2), and (3) of this section." Given LaSalle's plans to rely on the 8-10 content of the rack inserts in the Unit 2 spent fuel pool, provide a description of those administrative controls that will be put in place to ensure that 8-10 content of the NETCO-SNAP-IN rack inserts will be consistent with what is assumed in the rack inserts and analyses.
ML103210499 NRR-088 *via email dated SRXB/BC LPL3-2/PM OFFICE LPL3-2/PM LPL3-2/LA LPL3-2/BC AUlses* RCarlson EBrown NAME EBrown THarris 11/18/10 11/18/10 11/18/10 11/19/10 11/19/10 DATE
