|
|---|
Category:Letter
MONTHYEARIR 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
ML23317A1192023-11-10010 November 2023
Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums
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
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
ML23081A0382023-04-25025 April 2023
County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration
ML23110A3202023-04-21021 April 2023
Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection
ML23107A1822023-04-18018 April 2023
Operator Licensing Examination Approval Lasalle County Station, May 2023
RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023
Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations
ML23073A2182023-03-22022 March 2023
Issuance of Amendment No. 258 to Renewed Facility Operating Licenses Exigent Amendment to Revise Design Basis Related to Seismic Requirements
RS-23-048, Exigent Amendment Request to Revise Design Basis Related to Seismic Requirements2023-03-0707 March 2023
Exigent Amendment Request to Revise Design Basis Related to Seismic Requirements
ML23061A1632023-03-0303 March 2023
Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch 3
IR 05000373/20220062023-03-0101 March 2023
Annual Assessment Letter for LaSalle County Station, Units 1 and 2 (Report 05000373/2022006 and 05000374/2022006)
RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023
Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203
RS-23-037, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station2023-02-22022 February 2023
Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station
ML23024A1372023-02-0303 February 2023
Request for Withholding Information from Public Disclosure for LaSalle County Station, Unit Nos. 1 and 2
ML23031A1972023-01-31031 January 2023
Notification of NRC Fire Protection Team Inspection Request for Information, Inspection Report Nos. 05000373/2023011 and 05000374/2023011
IR 05000373/20220042023-01-31031 January 2023
County Station - Integrated Inspection Report 05000373/2022004 and 05000374/2022004
RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023
Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10
2024-01-05
[Table view] |
Text
January 16, 2003 Mr. Mike Mulligan P.O. Box 161 Hinsdale, NH 03451
Dear Mr. Mulligan:
I am responding to your e-mails dated December 13 and 19, 2002. In your e-mails, directed to Geoffrey Grant in Region III, you expressed concerns about the Nuclear Regulatory Commissions (NRC's) ongoing evaluation of a suppression pool cooling (SPC) issue at LaSalle County Station and about the adequacy of the wording in the plant's Technical Specifications (TS) and Updated Final Safety Analysis Report (UFSAR).
As discussed in NRC Inspection Report 50-373/01-10(DRP);50-374/01-10(DRP), LaSalle personnel operated the Residual Heat Removal (RHR) system in the SPC mode of operation continuously for an extended period of time. As you know, this inspection report is publicly available in ADAMS under accession number ML012610129. Due to a concern regarding the operability of the RHR system following an anticipated waterhammer as a direct consequence of a loss-of-offsite-power (LOOP) followed by a loss-of-coolant-accident (LOCA), Unresolved Item (URI) 50-373/2001010-02 was opened. Based on the low initiating event frequency of a simultaneous LOOP and LOCA, this URI has a low risk significance and remains open while Region III considers enforcement-related action.
Based on the low risk significance, the time required to perform thorough evaluations, and the iterative nature of the risk-informed enforcement process between the NRC and the licensee, this issue has taken considerable time to evaluate and resolve. Pre-decisional information is not normally released to the public. However, all relevant information related to this URI was previously disclosed to you publicly in our November 29, 2001, response (ML013020117) to your 10 CFR 2.206 petition dated September 27, 2001. Additionally, a Task Interface Agreement response to Region III (TIA 2001-14, ML021220399) that you reference was recently made publicly available to allow the licensee and the industry's Boiling Water Reactor Owner's Group to formally respond to the NRC technical staff's evaluation prior to Region III taking enforcement-related action. As we previously told you in our response to your petition, these ongoing discussions primarily involve regulatory interpretations and do not involve any new technical issues which have not already been the subject of NRC staff review and evaluation. Neither your previous petition request nor your latest e-mails present any significant new information which is relevant to these discussions.
Regarding your concern about the adequacy of TS and UFSAR wording at LaSalle and other plants, the staff recognizes that some minor discrepancies may exist and we endeavor to correct these differences where practical through the licensing and enforcement processes.
However, the staff is confident that current operating licenses are adequately documented and meet regulatory requirements to maintain safety. Where nuclear reactor safety is concerned, risk-significant operating requirements specified in a plant's TS and UFSAR are conservative, thoroughly analyzed, and unambiguously defined. Your assertion at one point that the TS and UFSAR wordings have been "politically arranged by the utilities" and that "the industry is
M. Mulligan making the regulatory control wording more ambiguous" is unsupported. One of the NRCs performance goals is to reduce unnecessary regulatory burden, and the staff actively works with all stakeholders to focus attention on those areas of highest safety priority and make more realistic decisions using risk-informed and performance-based approaches. This is a public process conducted in full compliance with NRC regulations and subject to independent oversight by the Advisory Committee on Reactor Safeguards (ACRS) and the Atomic Safety and Licensing Board (ASLB).
The NRCs primary obligation is to ensure adequate protection of the public health and safety.
Only if this goal is satisfied is there consideration of other goals, such as the goal to avoid regulatory burden.
Thank you for your interest in this matter.
Sincerely,
/RA by L. Raghavan for/
Anthony J. Mendiola, Chief, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-373, 50-374
M. Mulligan making the regulatory control wording more ambiguous" is unsupported. One of the NRCs performance goals is to reduce unnecessary regulatory burden, and the staff actively works with all stakeholders to focus attention on those areas of highest safety priority and make more realistic decisions using risk-informed and performance-based approaches. This is a public process conducted in full compliance with NRC regulations and subject to independent oversight by the Advisory Committee on Reactor Safeguards (ACRS) and the Atomic Safety and Licensing Board (ASLB).
The NRCs primary obligation is to ensure adequate protection of the public health and safety.
Only if this goal is satisfied is there consideration of other goals, such as the goal to avoid regulatory burden.
Thank you for your interest in this matter.
Sincerely,
/RA by L. Raghavan for/
Anthony J. Mendiola, Chief, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-373, 50-374 DISTRIBUTION:
PUBLIC PD3-2 Reading S. Collins/W. Borchardt (RidsNrrOd)
J. Zwolinski/L. Marsh (RidsNrrDlpm)
B. Sheron (RidsNrrAdpt)
L. Raghavan (RidsNrrDlpmLpdiii1)
A. Mendiola (RidsNrrDlpmLpdiii2)
W. Macon (RidsNrrPMWMacon)
C. Rosenberg (RidsNrrLACRosenberg)
L. Cox LCC B. Burgess, RIII (RidsRgn3MailCenter)
NRR Mailroom (YT020020292 & 93) (RidsNrrWpc)
ADAMS Accession Number: ML030090023 *Concurred by e-mail dated 1/13/03 Incoming #1: ML030160644 Incoming #2: ML030160638 Package # : ML030160854 OFFICE PM:LPD3-2 LA:LPD3-2 SC:RIII/DRP SC:LPD3-2 NAME WMacon, Jr. CRosenberg BBurgess* AMendiola DATE 1/15/03 1/15/03 1/13/03 1/16/03 OFFICIAL RECORD COPY
