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Category:Meeting Briefing Package/Handouts
MONTHYEARML24100A7672024-04-11011 April 2024 Meeting Slides - Preapplication with Constellation on Planned Fleet Alternative Request to Adopt OMN-2 ML24089A2612024-04-0909 April 2024 Slides - Constellation - Pre-Application Regarding Hooded Masks 4/9/2024 Meeting Slides (L-2024-LLM-0041) ML24029A1742024-01-30030 January 2024 Constellation Pre-Application January 30, 2024, Meeting Slides - Proposed Alternative to Utilize Code Case N-932, Alternative Requirements for Acceptance of Containment Base Metal Corrosion or Erosion ML23317A0712023-11-14014 November 2023 NRC Pre-Submittal Meeting on November 14th, 2023 - TSTF-591 and Selected 50.69 License Condition Updates (EPID L-2023-LLM-0098) (Slides) ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML22311A5112022-11-0707 November 2022 Pool Swell License - Amendment Request ML21314A4472021-11-10010 November 2021 Slides for Presubmittial Meeting for Proposed Alternative to Adopt ASME Code Case N-921 to Extend the Inservice Inspection Interval ML21194A1582021-07-13013 July 2021 and Lasalle Nuclear Generating Stations 2020 Annual Assessment Meeting Slides ML21141A0102021-05-21021 May 2021 La Salle County Station, Units 1 and 2, May 27, 2021 Pre Submission Public Meeting Slides (EPID-L-2021-LRM-0052) ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a ML20238B8662020-08-25025 August 2020 Hq Online EOC Slides ML20178A4202020-06-30030 June 2020 NEI Slides for June 30, 2020, Public Meeting on COVID-19 Response ML20170B0212020-06-23023 June 2020 NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections ML20163A6552020-06-16016 June 2020 6-16-20 Byron Unit 2 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections ML20169A5592020-06-16016 June 2020 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections (Rev 1) ML19318F9512019-11-20020 November 2019 Presentation Slides for November 20, 2019, Pre-Application Meeting - Request for Revision to Quality Assurance Program Internal Audit Frequency ML19161A2572019-06-0404 June 2019 BWR Fleet Msv/Srv - Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19151A6602019-05-31031 May 2019 BWR Fleet Mssv/Srv Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19022A2002019-01-23023 January 2019 Request for Use of ASME Code Case N-879 for Exelon Nuclear Power Plants ML18347B3142018-12-19019 December 2018 Bwrvip/Asme Relief Request Discussion December 19, 2018 ML18334A2162018-11-30030 November 2018 Presentation Slides: Exelon BWR MSIV (Boiling-Water Reactor - Main Steam Isolation Valve) Leakage Optimization for NRC Pre-Submittal Meeting of December 6, 2018 ML18319A1272018-11-19019 November 2018 Slides for 11/19/18 Public Meeting - Exelon Fleet LAR for Common Language for TS 5.7 High Radiation Areas ML18054B3592018-02-27027 February 2018 Slide: NRC Pre-Submittal Meeting for Exelon Fleet LAR to Relocate TS Unit Staff Qualification ANSI Requirements to the QATR, February 27, 2018, Profile Info: Submitted by Frank Mascitelli ML17142A2382017-05-25025 May 2017 OEDO-17-00280 - Briefing Package for Drop-In Visit on June 9, 2017, by Senior Management of Exelon Generation Company, LLC with Chairman Svinicki, Commissioner Baran, and Commissioner Burns ML16194A0062016-07-12012 July 2016 Pre-Application Meeting Presentation Regarding LaSalle County Station License Amendment Request for Revision of Suppression Pool Swell Design Analysis ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards ML16077A3492016-03-17017 March 2016 NRC Briefing Slides for LaSalle Dseis Public Meeting March 22, 2016 ML16075A3292016-03-16016 March 2016 OEDO-16-00165 - Briefing Package for Drop-In Visit on March 23, 2016, by Senior Management of Exelon Generation Company, LLC with the NRC Executive Director for Operations ML15062A3642015-03-0303 March 2015 Environmental Scoping Briefing for March 10th Meetings ML15058A6322015-02-27027 February 2015 LSCS Scoping Briefing Prepared 2-27-15 for March 10th Meeting ML13212A3372013-07-31031 July 2013 NRC NEI-01-01 Meeting Presentation on 7/31/13 Digital I&C Meeting NEI 01-01, NRC NEI-01-01 Meeting Presentation on 7/31/13 Digital I&C Meeting2013-07-31031 July 2013 NRC NEI-01-01 Meeting Presentation on 7/31/13 Digital I&C Meeting ML13211A3782013-07-30030 July 2013 7/31/2013 NRC Public Meeting Presentation on NEI 01-01 NEI 01-01, 7/31/2013 NRC Public Meeting Presentation on NEI 01-012013-07-30030 July 2013 7/31/2013 NRC Public Meeting Presentation on NEI 01-01 ML13164A3792013-06-24024 June 2013 Summary of Public Meeting with Exelon Generation Company, LLC, Regarding the Proposed Extended Power Uprate License Amendment Request for LaSalle County Station, Units 1 and 2 ML12159A2662012-06-11011 June 2012 County Generating Station Pre-Application Meeting Extended Power Uprate: Replacement Steam Dryers. June 11, 2012 ML12130A0442012-06-0707 June 2012 Summary of Public Meeting with Exelon Generation Company, LLC, Regarding Proposed Extended Power Uprate License Amendment Request for LaSalle County Station, Units 1 and 2 ML1209306162012-04-0202 April 2012 Enclosure - 04/04/2012 Exelon Nuclear Meeting Presentation LaSalle Count Station Pre-Application Meeting Extended Power Uprate. ML1209006542012-03-30030 March 2012 Slides for April 4 Public Meeting on LaSalle Extended Power Uprate ML1208701402012-03-27027 March 2012 Licensee Slides for Exelon Fleet Pre-Submittal Public Meeting 4-10-12 Licensed Operator Eligibility Requirements LAR ML1208806542012-03-27027 March 2012 Non-Proprietary Slides for LaSalle Prnm Meeting ML1200303212012-01-19019 January 2012 12/7/2011 - Summary of Public Meeting with Exelon Regarding the Proposed Extended Power Uprate License Amendment Request for LaSalle, Units 1 and 2 ML13014A1002011-09-12012 September 2011 Sprinkler Clogging LaSalle Exelon - Presentation During September 2011 NEI Fire Protection Information Forum RS-11-096, Intent to Submit License Amendment Request to Install Power Range Neutron Monitor (Prnm) in Accordance with Interim Staff Guidance, Digital I & C-ISG-062011-06-0707 June 2011 Intent to Submit License Amendment Request to Install Power Range Neutron Monitor (Prnm) in Accordance with Interim Staff Guidance, Digital I & C-ISG-06 ML1100502552011-01-17017 January 2011 December 29, 2010, Summary of Public Conference Call with Exelon Generation Company, LLC, Regarding LaSalle Netco Insert 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 ML1030903782010-11-19019 November 2010 Licensee Handouts for LaSalle Meeting with Exelon to Discuss Netco Inserts ML1030704842010-11-19019 November 2010 Summary of Public Meeting with Exelon Generation Company, LLC Regarding LaSalle Netco Insert Request ML1032601422010-11-10010 November 2010 Handouts for November 10, 2010 Public Conference Call with Exelon Regarding LaSalle Insert Request ML0919803632009-08-20020 August 2009 Summary of Licensing Counterparts Meeting with Exelon Generation Company, to Discuss Licensing Practices and Processes 2024-04-09
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24100A7672024-04-11011 April 2024 Meeting Slides - Preapplication with Constellation on Planned Fleet Alternative Request to Adopt OMN-2 ML24089A2612024-04-0909 April 2024 Slides - Constellation - Pre-Application Regarding Hooded Masks 4/9/2024 Meeting Slides (L-2024-LLM-0041) ML24029A1742024-01-30030 January 2024 Constellation Pre-Application January 30, 2024, Meeting Slides - Proposed Alternative to Utilize Code Case N-932, Alternative Requirements for Acceptance of Containment Base Metal Corrosion or Erosion ML23317A0712023-11-14014 November 2023 NRC Pre-Submittal Meeting on November 14th, 2023 - TSTF-591 and Selected 50.69 License Condition Updates (EPID L-2023-LLM-0098) (Slides) ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout NEI 99-01, Slides - Constellation - Pre-Application EP 2/23/2023 Meeting Slides2023-02-21021 February 2023 Slides - Constellation - Pre-Application EP 2/23/2023 Meeting Slides ML22311A5112022-11-0707 November 2022 Pool Swell License - Amendment Request ML21314A4472021-11-10010 November 2021 Slides for Presubmittial Meeting for Proposed Alternative to Adopt ASME Code Case N-921 to Extend the Inservice Inspection Interval ML21194A1582021-07-13013 July 2021 and Lasalle Nuclear Generating Stations 2020 Annual Assessment Meeting Slides ML21162A3322021-06-11011 June 2021 BWR Fleet Relief Request Associated with RPV Instrument Nozzle Repairs ML21141A0102021-05-21021 May 2021 La Salle County Station, Units 1 and 2, May 27, 2021 Pre Submission Public Meeting Slides (EPID-L-2021-LRM-0052) ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a ML20238B8662020-08-25025 August 2020 Hq Online EOC Slides ML20178A4202020-06-30030 June 2020 NEI Slides for June 30, 2020, Public Meeting on COVID-19 Response ML20170B0212020-06-23023 June 2020 NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections ML20163A6552020-06-16016 June 2020 6-16-20 Byron Unit 2 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections ML20169A5592020-06-16016 June 2020 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections (Rev 1) ML18347B3142018-12-19019 December 2018 Bwrvip/Asme Relief Request Discussion December 19, 2018 ML18334A2162018-11-30030 November 2018 Presentation Slides: Exelon BWR MSIV (Boiling-Water Reactor - Main Steam Isolation Valve) Leakage Optimization for NRC Pre-Submittal Meeting of December 6, 2018 ML18319A1272018-11-19019 November 2018 Slides for 11/19/18 Public Meeting - Exelon Fleet LAR for Common Language for TS 5.7 High Radiation Areas ML18054B3592018-02-27027 February 2018 Slide: NRC Pre-Submittal Meeting for Exelon Fleet LAR to Relocate TS Unit Staff Qualification ANSI Requirements to the QATR, February 27, 2018, Profile Info: Submitted by Frank Mascitelli ML17339A1812017-12-0707 December 2017 NRC Hq Pre-Submittal LaSalle CSCS LAR 12-7-2017 Final ML16194A0062016-07-12012 July 2016 Pre-Application Meeting Presentation Regarding LaSalle County Station License Amendment Request for Revision of Suppression Pool Swell Design Analysis ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards ML16077A3492016-03-17017 March 2016 NRC Briefing Slides for LaSalle Dseis Public Meeting March 22, 2016 ML15062A3642015-03-0303 March 2015 Environmental Scoping Briefing for March 10th Meetings ML15058A6322015-02-27027 February 2015 LSCS Scoping Briefing Prepared 2-27-15 for March 10th Meeting ML13212A3372013-07-31031 July 2013 NRC NEI-01-01 Meeting Presentation on 7/31/13 Digital I&C Meeting NEI 01-01, NRC NEI-01-01 Meeting Presentation on 7/31/13 Digital I&C Meeting2013-07-31031 July 2013 NRC NEI-01-01 Meeting Presentation on 7/31/13 Digital I&C Meeting ML13211A3782013-07-30030 July 2013 7/31/2013 NRC Public Meeting Presentation on NEI 01-01 NEI 01-01, 7/31/2013 NRC Public Meeting Presentation on NEI 01-012013-07-30030 July 2013 7/31/2013 NRC Public Meeting Presentation on NEI 01-01 ML13164A3792013-06-24024 June 2013 Summary of Public Meeting with Exelon Generation Company, LLC, Regarding the Proposed Extended Power Uprate License Amendment Request for LaSalle County Station, Units 1 and 2 ML12200A3652012-07-27027 July 2012 County Station UHS Pre-Application Mtg 6-28-12 - Final ML12188A5122012-07-0606 July 2012 IEMA HAB Lessons Learned_rev1 ML12159A2662012-06-11011 June 2012 County Generating Station Pre-Application Meeting Extended Power Uprate: Replacement Steam Dryers. June 11, 2012 ML12130A0442012-06-0707 June 2012 Summary of Public Meeting with Exelon Generation Company, LLC, Regarding Proposed Extended Power Uprate License Amendment Request for LaSalle County Station, Units 1 and 2 ML1209306162012-04-0202 April 2012 Enclosure - 04/04/2012 Exelon Nuclear Meeting Presentation LaSalle Count Station Pre-Application Meeting Extended Power Uprate. ML1209006542012-03-30030 March 2012 Slides for April 4 Public Meeting on LaSalle Extended Power Uprate ML1208701402012-03-27027 March 2012 Licensee Slides for Exelon Fleet Pre-Submittal Public Meeting 4-10-12 Licensed Operator Eligibility Requirements LAR ML1208806542012-03-27027 March 2012 Non-Proprietary Slides for LaSalle Prnm Meeting ML1200303212012-01-19019 January 2012 12/7/2011 - Summary of Public Meeting with Exelon Regarding the Proposed Extended Power Uprate License Amendment Request for LaSalle, Units 1 and 2 ML13014A1002011-09-12012 September 2011 Sprinkler Clogging LaSalle Exelon - Presentation During September 2011 NEI Fire Protection Information Forum ML11201A2132011-07-20020 July 2011 Summary of Public Meeting to Discuss Exelon'S Plans for Implementing an Electronic Document Control System (Edocs) for Use by NRC Inspectors with U.S. Nuclear Regulatory Commission (NRC) Region III Staff ML1100502552011-01-17017 January 2011 December 29, 2010, Summary of Public Conference Call with Exelon Generation Company, LLC, Regarding LaSalle Netco Insert 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 ML1030704842010-11-19019 November 2010 Summary of Public Meeting with Exelon Generation Company, LLC Regarding LaSalle Netco Insert Request ML1030903782010-11-19019 November 2010 Licensee Handouts for LaSalle Meeting with Exelon to Discuss Netco Inserts ML1032601422010-11-10010 November 2010 Handouts for November 10, 2010 Public Conference Call with Exelon Regarding LaSalle Insert Request ML0929400522009-10-22022 October 2009 Meeting Power Uprate Meeting Slides ML0917502262009-07-0707 July 2009 Summary of Pre-Application Meeting with Exelon Generation Company, License Amendment Request for LaSalle and Limerick Measurement Uncertainty Recapture Power Uprates 2024-04-09
[Table view] |
Text
Nuclear LaSalle County Station Pre-Application Meeting License Amendment Request Ganged Rod Drive Capability Enclosure 2
Introduction ExelIn Nuclear Objective of Meetinq
> Review the technical and regulatory aspects of a planned License Amendment Request (LAR) for Ganged Rod Drive Capability at LaSalle County Station (LSCS).
> Review an outline of a draft LAR with respect to the required scope and level of detail.
> Confirm that current LAR outline, including any identified enhancements, satisfy required scope.
> Discuss the Regulatory Finding that would be necessary for LAR approval.
2
Introduction Exeuleanr Nuclea-r Topics and Presenters
>Review of Issue - Terry Simpkin, Regulatory Assurance Manager, LSCS Review of LAR Outline - Darin Benyak, Licensing and Regulatory Affairs SProposed Regulatory Finding - Darin Benyak SCurrent Project Status - Bob Fredricksen, Lead Design Engineer, LSCS 3
Issue Review Exel' [flsm Nuclear Rod Control Management System EGC is replacing the current LSCS Reactor Manual Control System (RMCS) with a new design called the Rod Control Management System (RCMS).
The current RMCS uses discrete digital electronics and dynamic logic to control rod motion. The replacement RCMS will be a digital microprocessor-based system.
The RCMS will retain all of the system-level functions of the existing RMCS and Rod Worth Minimizer (RWM), as well as add additional capabilities.
The replacement system is classified as non-safety-related, and has been designed to the same regulatory criteria and standards as the existing system, 4
Issue Review Nuclear Added Functionality of RCMS
> Enhanced implementation and documentation of control rod maintenance and surveillance activities.
> Improved control rod movement operations that are required for control rod drive functionality.
> Enhanced the confirmation of reactor shutdown following a scram.
Added the capability to move multiple rods (up to four) in a single gang (i.e., Ganged Rod Drive Capability).
The RCMS is being installed in accordance with the requirements of 10 CFR 50.59, with the exception of Ganged Rod Drive Capability.
5
Issue Review IS.
Nuclear Operational and Safety Benefits With Ganged Rod Drive Capability, the RCMS will:
Reduce operational challenges by reducing the amount of time that the reactor is in the Intermediate and Startup range power levels during startups. These power levels require a heightened level of reactivity management attention and resources.
Enhance SCRAM avoidance by allowing the rapid insertion of CRAM rods (rods specified in analyzed sequences for the purpose of significantly reducing reactor power rapidly) during plant transients.
6
Issue Review ExelIn Nuclear Ganged Rod Drive Capability
- Low Power," does not address or consider simultaneous movement of multiple rods.
> EGC proposes to revise the LSCS Licensing Basis to include, in the UFSAR, the description of a potential multiple rod withdrawal error at low power event as an "infrequent incident," similar to the description of a potential single rod withdrawal error event (i.e., UFSAR Section 15.4.1.2, "Continuous Rod Withdrawal Error").
7
Issue Review Exekons.
Nuclear September 19, 2006 Pre-Application Meeting
> Objective was to identify the specific scope and level of detail of information needed to complete a review of an LAR for Ganged Rod Drive Capability at LSCS.
SMeeting Summary was issued on November 28, 2006 with nine specific information requirements.
8
Issue Review Nuclear September 19, 2006 Meeting: LAR Information Requirements
- 1. Describe intent of LAR
- 2. Describe internal and external communication interfaces
- 3. Describe hardware and software controls that restrict rod movement
- 4. Describe cyber security
- 5. Describe component qualification
- 6. Address Regulatory Guide 1.97 and Emergency Operating Procedure applicability
- 7. Describe the processing of Rod Block signals
- 8. Provide a Failure Analysis (three sub-items)
- a. Analysis of Single Failures and submittal of Failure Modes and Effects Analysis
- b. Characterization of likelihood of common-mode software failure, including description of software development and testing
- c. Description of the consequences if the low probability event were to occur (i.e., failures leading to uncontrolled withdrawal of rod gang)
- 9. Address all NUREG-0800 accidents involving rod movement in No Significant Hazards Consideration 9
Draft LAR Outline :xe l ,.
Nuclear General LAR Outline; Detailed Outline Provided as Attachment Description SIntent of LAR (Item 1)
Proposed Change SRevision of Licensing Basis (Item 1)
Technical Evaluation SDescription and Design Basis (Items 2, 3, 4, 5, 6, and 7)
> Failure Analysis (Items 8a, 8b, and 8c)
Regulatory Analysis SNo Significant Hazards Consideration (item 9)
Appendices SNetwork Diagram (Item 4)
SRCMS Failure Modes and Effects Analysis (Item 8a) 10
ProposedRegulatory Finding Exel(n+/-f Nuclear "The requirements of General Design Criteria (GDC) 10, 17, 20, 24, and 25 had been met for ganged rod drive capabilityat LaSalle County Station as part of the Rod Control Management System, since the system design contains a Rod Worth Minimizer.
This system has been reviewed and found acceptable because single failures in the reactorcontrol system, which could result in uncontrolled withdrawal of control rods under low-power conditions, have been precluded.
The scope of this review has included the design features which act to prevent such withdrawals."
11
CurrentProject Status Exelon.
Nuclear SDesign Specifications Complete SHardware Build Complete
~ Software Code Written; Code tested SIntegration Testing in progress SV&V and Factory Acceptance Testing will be completed in July SParallel unit on-site for Exelon evaluation SInfrastructure installation in-progress 12
Attachment Exelor,'
Nuclear LaSalle County Station Draft License Amendment Request Ganged Rod Withdrawal Detailed Outline.
13
Exeln' fln Nuclear LaSalle County Station Ultimate Heat Sink Regulatory Resolution and Optimum Approach for Submittal of License Amendment Request
Introduction Exelri5 .
Nucdea.r Obiective of Meeting
> Review the 2006 License Amendment Request (LAR) for Ultimate Heat Sink (UHS) at LaSalle County Station
> Review of the NRC Safety Evaluation
> Discussion of the NRC approved LaSalle County Station UHS Licensing Basis and Plant Design
> Exelon's Perspective of the License Amendment Denial
> Regulatory Resolution Pathways 15
Introduction Exelorts Nuclear Topics and Presenters
>Review of the original LAR Alison Mackellar, Corporate Licensing Engineer SDiscussion of Licensing Basis and Design Terry Simpkin, Regulatory Assurance. Manager LaSalle
> Review of Denial SE Alison Mackellar, Corporate Licensing Engineer
> Exelon's Perspective on the Denial Darin Benyak, Corporate Licensing Manager
> Regulatory Resolution Pathways Darin Benyak, Corporate Licensing Manager 16
Original LAR Exelen .
Nuclear UHS License Amendment Request The original LAR proposed a change to increase the Technical Specification (TS) indicated temperature limit of UHS from < 100°F to < 101.5 0F The increase was to be achieved by reducing the measurement uncertainty by replacing existing thermocouples with higher precision temperature measuring equipment (i.e., RTDs)
The Circulating Water (CW) temperature instrumentation indication loop(s) are of an equivalent design The method and procedures used to determine UHS are unchanged 17
LAR Original LAR Exelkn,.
Original Nucdea.r CW Inlet Temperature Trend Data from Plant Process Computer UNIT 1 I MoDEo,i fir1I 2 Trend . 1/24/2007 I I ACTIVE A n Ii 2 trendJ 13:45:05 I1
"~~ - tr n I . .. ... I, ,
Start Time: MM Mt 1 Archive Sample Rate:
End Time:
- M* *M*a*M Real-Time Sample Rate:
51.99 DnGF X T63~0 52.80 52.80 52.12 DEGF [
52.60 52.60 62.40 . 24.20..
. 13:20:001.24.20..13:30.001/.4/200... . 13:400....
52.40 52.20 52.20 52.00 52.00 51.80 51.80 51.60 51.60 51.40 51.40 51.20 51.20 u,1[pI U"
1/24/2007 13:20:00 1/24/200713:30:00 1/24/2007 13:40:00
OriginalLAR Exelon,.
Simplified Circulating Water (CW) System Nuclear 19
Original LAR Exelek n Nuclear UHS LAR Technical Basis The UHS post-accident temperature maximum allowable cooling water inlet value = 1041F Existing Analysis
> 1041F = 100°F (TS max) + 20 F (transient) +/- 1.80 F (calculated thermocouple uncertainty) + .20 F (margin added)
Analysis Results Remains Unchanged
> 104'F = 101.5 0 F (new TS max) + 20 F (transient) +/- 0.31°F (calculated RTD uncertainty) + 0.19 0 F (margin added) 20
UHS Design Exelk ns.
Nuclear UHS Licensing Basis and Plant Design SR 3.7.3.1 was added to LaSalle TS during ITS in 2001 The CW temperature instrumentation indication loop(s) originally designed as non-safety-related The replacement instrumentation used to measure the UHS temperature is non-safety-related NES-EIC-20.04 - methodology reviewed during ITS Calculation performed in accordance with NEC-EIC-20.04 and was appropriate -for instrument uncertainty for non-safety related indicating loops The method and procedures used to determine UHS are unchanged 21
NRC SE Review Exelon.
Nuclear Review of the NRC Safety Evaluation (SE)
"the degree of measurement accuracy that would be required to support the requested modification is not adequately demonstrated in Exelon's analysis" "the TS modification itself does not adequately address single-unit operation (if only one unit is operating the lack of flow to the other unit could cause the temperature measurements associated with that unit to become non-representative of the UHS temperature.)"
22
NRC SE Review ExelNule.
Nucea-r Review of the NRC Safety Evaluation.(SE)
"the degree of measurement accuracy that would be required to support the requested modification is not adequately demonstrated in Exelon's analysis"
> RG 1.105 -graded approach
> HICB-12 SISA-$67.04
> NES-EIC-20.04 - reviewed with ITS SHICB issued TIA on UHS instrument accuracy for Millstone 2 SWaterford Unit 3 23
NRC SE Review Exekn~.
Nuclear Review of the NRC Safety Evaluation (SE)
> TS modification itself does not adequately address single-unit "the operation (if only one unit is operating the lack of flow to the other unit could cause the temperature measurements associated with that unit to become non-representative of the UHS temperature)"
> The Circulating Water (CW) temperature instrumentation indication loop(s) are of an equivalent design
> The replacement instrumentation used to measure the UHS temperature is non-safety-related, installed and fully functional SThe method and procedures used to determine UHS are unchanged
> The CW temperature of the installed RTDs on either unit is representative of the UHS temperature with a CW pump running
> Ifthe unit does not have a CW pump in operation, the surveillance procedure directs the CW temperature to be recorded from a unit that does have a CW pump in operation 24
Discussion ExelN flear Nudea.r Exelon Perspective of Denial Change in NRC position on measurement uncertainty methodology for non-safety related systems
> Challenging current design and licensing basis for LaSalle CW system 25
Discussion Exeulear~
Nuclear SRe-gulatory Resolution Pathways Identify additional issues with Exelon approach
> Resolve Issues
> Resubmittal 26