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Category:Letter
MONTHYEARULNRC-06853, Submittal of 2023 Fitness for Duty Performance Data Per Per 10 CFR 26.7172024-01-29029 January 2024 Submittal of 2023 Fitness for Duty Performance Data Per Per 10 CFR 26.717 IR 05000483/20230042024-01-19019 January 2024 Integrated Inspection Report 05000483/2023004 ML24008A0552024-01-19019 January 2024 Acceptance of Requested Licensing Action - Proposed Alternative to the Requirements of the ASME Code (EPID L-2023-LLR- 0061) ML23353A1712024-01-18018 January 2024 Issuance of Amendment No. 237 to Clarify Support System Requirements for the Residual Heat Removal System and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 ML23317A0012024-01-12012 January 2024 Audit Summary Regarding LAR to Clarify Support System Requirements for the Residual Heat Removal and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 ML23347A1212024-01-11011 January 2024 Issuance of Amendment No. 236 to Adopt TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Volume Values to Licensee Control EPID L-2023-LLA-0046) ML24011A1492024-01-11011 January 2024 Notification of Post-Approval Site Inspection for License Renewal and Request for Information (05000483/2024011) ULNRC-06847, Supplement to Relief Request from Requirements of ASME BPV Code, Section XI, Subsection Iwl Regarding Examination and Testing of the Unbonded Post-Tensioning System (Relief Request C3R-01)2023-12-21021 December 2023 Supplement to Relief Request from Requirements of ASME BPV Code, Section XI, Subsection Iwl Regarding Examination and Testing of the Unbonded Post-Tensioning System (Relief Request C3R-01) ULNRC-06849, License Renewal Resolution for Commitments 34 and 35 Perform Evaluation of Crack Initiation and Propagation in Steam Generator Divider Plate and Tube-To-Tubesheet Welds2023-12-20020 December 2023 License Renewal Resolution for Commitments 34 and 35 Perform Evaluation of Crack Initiation and Propagation in Steam Generator Divider Plate and Tube-To-Tubesheet Welds ML23346A0392023-12-14014 December 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action Request for Relief from Requirements of ASME Code, Section Xl, Examination and Testing Unbonded Post-Tensioning System ULNRC-06844, Request for Exemption from Specific Requirements in 2023 Security Rule, Enhanced Weapons, Firearms Background Checks, and Security Event Notification2023-12-0707 December 2023 Request for Exemption from Specific Requirements in 2023 Security Rule, Enhanced Weapons, Firearms Background Checks, and Security Event Notification 05000483/LER-2023-001, Submittal of LER 2023-001-00 for Callaway, Unit 1, Inoperable Instrument Tunnel Sump Level Indication Resulted in Condition Prohibited by Technical Specifications2023-11-29029 November 2023 Submittal of LER 2023-001-00 for Callaway, Unit 1, Inoperable Instrument Tunnel Sump Level Indication Resulted in Condition Prohibited by Technical Specifications ULNRC-06827, Supplement to License Amendment Request Regarding Support System Requirements for Residual Heat Removal and Control Room Air Conditioning Systems Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029)2023-11-20020 November 2023 Supplement to License Amendment Request Regarding Support System Requirements for Residual Heat Removal and Control Room Air Conditioning Systems Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029) IR 05000483/20230102023-11-15015 November 2023 NRC License Renewal Phase 1 Inspection Report 05000483 2023010 IR 05000483/20233012023-11-0909 November 2023 NRC Examination Report 05000483-2023301 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23297A2502023-11-0606 November 2023 Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed No Significant Hazards Consideration Determination and Opportunity for a Hearing (EPID L-2022-LLA-0176) - Letter IR 05000483/20240122023-10-24024 October 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection (05000483/2024012) ML23293A2652023-10-24024 October 2023 3rd Quarter 2023 Integrated Inspection Report ML23240A3692023-10-0505 October 2023 Issuance of Amendment No. 235 to Revise Technical Specifications to Use of Framatome Gaia Fuel (EPID L-2022-LLA-0150) (Non-Proprietary) ML23234A1522023-10-0505 October 2023 Exemption from the Requirements of 10 CFR Part 50, Section 50.46, and Appendix K Regarding Use of M5 Cladding Material (EPID L-2022-LLE-0030) (Letter) ML23305A0942023-10-0202 October 2023 10-CW-2023-09 Post-Exam Submittal ML23270B9662023-09-27027 September 2023 10 CFR 50.55a(z)(I) Request for Relief from ASME OM Code Pump and Valve Testing Requirements for Fifth 120-Month Inservice Testing Interval ML23228A0252023-09-25025 September 2023 Issuance of Amendment No. 234 to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML23261C3852023-09-25025 September 2023 Safety Evaluation for Operating Quality Assurance Manual Revision 36A ML23166B0882023-09-20020 September 2023 Issuance of Amendment No. 233 for Adoption of Alternative Source Term and Revision of Technical Specifications ML23206A1992023-09-15015 September 2023 Regulatory Audit Summary Regarding License Amendment and Regulatory Exemptions Request for Fuel Transition to Framatome Gaia Fuel (Epids L-2022-LLA-0150 and L-2022-LLE-0030) IR 05000483/20234012023-09-13013 September 2023 NRC Security Baseline Inspection Report 05000483/2023401 ML23240A7572023-08-31031 August 2023 NRC Initial Operator Licensing Examination Approval 05000483/2023301 IR 05000483/20230052023-08-23023 August 2023 Updated Inspection Plan for Callaway Nuclear Power Plant, Unit 1 (Report 05000483/2023005) - Mid Cycle Letter 2023 ULNRC-06824, Response to Request for Additional Information Regarding Operating Quality Assurance Manual (Oqam) Revision 36A2023-08-17017 August 2023 Response to Request for Additional Information Regarding Operating Quality Assurance Manual (Oqam) Revision 36A ML23219A1392023-08-15015 August 2023 Request for Withholding Information from Public Disclosure ULNRC-06830, Transmittal of Updated Technical Specification Markup and Clean Pages for License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak2023-08-15015 August 2023 Transmittal of Updated Technical Specification Markup and Clean Pages for License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak ML23215A1972023-08-0303 August 2023 Supplement to License Amendment and Exemption Request Regarding Use of Framatome Gaia Fuel (LDCN 22-0002) ULNRC-06223, Minor Correction to License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies (LDCN 2020-0004)2023-07-25025 July 2023 Minor Correction to License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies (LDCN 2020-0004) ULNRC-06799, Submittal of Licensee Event Report 2022-003-01, Class 1E Electrical Air Conditioning System Thermal Expansion Valve Failure Resulted in Condition Prohibited by Technical Specifications2023-07-13013 July 2023 Submittal of Licensee Event Report 2022-003-01, Class 1E Electrical Air Conditioning System Thermal Expansion Valve Failure Resulted in Condition Prohibited by Technical Specifications IR 05000483/20230022023-07-10010 July 2023 Integrated Inspection Report 05000483/2023002 ML23174A1272023-06-23023 June 2023 Cw FFD Document Request List 2023 ML23171A9942023-06-22022 June 2023 Acceptance of Request for Approval of Operating Quality Assurance Manual Revision 36a ULNRC-06821, Post-Audit Follow-Up Information in Support of Callaway'S License Amendment Request and Proposed Exemption to Allow Use of Framatome Gaia Fuel (LDCN 22-0002) (EPID L-2022-LLA-0150 and EPID L-2022-LLE-00301)2023-06-21021 June 2023 Post-Audit Follow-Up Information in Support of Callaway'S License Amendment Request and Proposed Exemption to Allow Use of Framatome Gaia Fuel (LDCN 22-0002) (EPID L-2022-LLA-0150 and EPID L-2022-LLE-00301) IR 05000483/20230112023-06-15015 June 2023 Comprehensive Engineering Team Inspection (CETI) Inspection Report 05000483/2023011 ULNRC-06822, Additional Information Regarding Request for NRC Approval of Operating Quality Assurance Manual (Oqam) Revision 36a2023-06-14014 June 2023 Additional Information Regarding Request for NRC Approval of Operating Quality Assurance Manual (Oqam) Revision 36a ML23158A1462023-06-13013 June 2023 Notification of Post-Approval Site Inspection for License Renewal and Request for Information Inspection (05000483/2023010) ULNRC-06815, Request for NRC Approval of Operating Quality Assurance Manual, Revision 36a2023-06-0505 June 2023 Request for NRC Approval of Operating Quality Assurance Manual, Revision 36a ULNRC-06818, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate .2023-06-0505 June 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate . ML23093A0952023-05-10010 May 2023 Issuance of Amendment No. 232 Regarding Technical Specification Changes for Spent Fuel Storage ULNRC-06816, Withdrawal of Previously Submitted Enclosures Regarding License Amendment Request for Adoption of Alternative Source Term and Revision of Technical Specifications (LDCN 21-0015)2023-05-0909 May 2023 Withdrawal of Previously Submitted Enclosures Regarding License Amendment Request for Adoption of Alternative Source Term and Revision of Technical Specifications (LDCN 21-0015) ML23129A7942023-05-0909 May 2023 Post-Audit Supplement to License Amendment Request and Exemption to Allow Use of Framatome Gaia Fuel (LDCN 22-0002) (Iepid L-2022-LLA-0150 and EPID L-2022-LLE-0030) ML23122A3172023-05-0808 May 2023 Review of the Spring 2022 Steam Generator Tube Inservice Inspections ML23118A3492023-05-0808 May 2023 Request for Withholding Information from Public Disclosure 2024-01-29
[Table view] Category:Report
MONTHYEARML23354A2462023-12-20020 December 2023 Cracking Assessment for Framatome RSG Channel Head Assembly ML23215A1992023-08-31031 August 2023 ANP-4012NP, Callaway, Unit 1, Rod Ejection Accident Analysis Revision 2, August 2023 ML23299A1982023-06-16016 June 2023 Enclosure 2: Callaway RR Tech Report Containment Post-Tensioning System Inservice Inspection Technical Report Basis for Proposed Extension of Examination Interval, Revision 0 ML23156A6712023-06-0505 June 2023 Description and Justification for Changes ML23150A1832023-05-30030 May 2023 EIP-ZZ-00240 Addendum E, Revision 027, Health Physics Coordinator (Hpc) Checklist Administrative Correction ML23150A1842023-05-18018 May 2023 EIP-ZZ-00240 Addendum E, Revision 027, Health Physics Coordinator (Hpc) Checklist ML23150A1892023-05-18018 May 2023 EIP-ZZ-00245 Addendum H, Revision 004, Security Coordinator Checklist for the Alternate Tsc/Osa Assembly Area ML23131A3882023-04-26026 April 2023 EIP-ZZ-PRO2O Minor Revision 54, Activation and Operation of the Joint Information Center - Procedure Review Form and 50.54(q) Screening Form ML23110A0712023-04-0606 April 2023 Procedure Review Form (PRF) for EIP-ZZ-A0066, Revision 28, RERP Training Program ML23068A0992023-03-0909 March 2023 Special Report 2023-01 PAM Report ML23052A0492023-02-14014 February 2023 Enclosure 7 - Holtec International Report HI-2230125, Revision 0, Supplemental Criticality Safety Analysis of SFP for Callaway Nuclear Generating Station, Revision 0, Dated February 14, 2023 ML22349A6272022-12-15015 December 2022 Enclosure 3 - 2022 Proxy Statement of Ameren Corporation ML22349A6322022-12-15015 December 2022 Enclosure 8 - 10-K Filed 02/23/2022 ML22349A6342022-12-15015 December 2022 Enclosure 9 - 10-Q Filed 03/31/2022 ML22349A6352022-12-15015 December 2022 Enclosure 10 - 10-Q Filed 06/30/2022 ML22349A6362022-12-15015 December 2022 Enclosure 11 - 10-Q Filed 09/30/2022 ML22349A6402022-12-15015 December 2022 Enclosure 14 - Schedule 14C Information for Union Electric Company March 2022 ML22327A2242022-11-23023 November 2022 Enclosure 1: Callaway Plant - Report Period: 10 CFR 50.59 and 10 CFR 72.48 Summary Report June 16, 2021 to November 23, 2022 ML22335A5012022-11-16016 November 2022 Enclosure 3: ANP-4012NP, Revision 1, Callaway Rod Ejection Accident Analysis ML22318A1902022-11-14014 November 2022 Enclosure 2 - Pressurized Water Reactor Owners Group Letter, OG-22-187, Subject: PWR Owners Group Mode 4 LOCA Analysis for Westinghouse NSSS Plants ML22299A2352022-10-21021 October 2022 HI-2220020, Revision 2, Non Proprietary Version of Criticality Safety Analysis of SFP for Callaway Nuclear Generating Station ML22285A1252022-10-12012 October 2022 Attachment 8 to Enclosure 1: ANP-3969NP, Callaway Non-LOCA Summary Report, Revision 2, Dated October 2022 ML22285A1222022-10-12012 October 2022 Attachment 5 to Enclosure 1: ANP-3947NP, Callaway Unit 1 License Amendment Request Inputs for Use of Framatome Fuel, Revision 3, Dated October 2022 ML22285A1232022-10-12012 October 2022 Attachment 6 to Enclosure 1: ANP-3944NP, Callaway Realistic Large Break LOCA Analysis with Gaia Fuel Design, Revision 1, Dated October 2022 ML22285A1242022-10-12012 October 2022 Attachment 7 to Enclosure 1: ANP-3943NP, Callaway Small Break LOCA Analysis with Gaia Fuel Design, Revision 1, Dated October 2022 ML22181B1362022-06-30030 June 2022 Attachment 6 - Replacement for Attachment 6, Description and Assessment Specific to TSTF-439, of ULNRC-06688 ML22181B1402022-06-30030 June 2022 Enclosure 1 - Replacement for Enclosure 1, List of Revised Required Actions to Corresponding PRA Functions, of ULNRC-06688 ML22181B1412022-06-30030 June 2022 Enclosure 4 - Replacement for Enclosure 4, Information Supporting Justification of Excluding Sources of Risk Not Addressed by the PRA Models, of ULNRC-06688 ML22153A1822022-06-0202 June 2022 Attachment 6 - Non-Proprietary Version of Rlbloca Summary Report ML22153A1832022-06-0202 June 2022 Attachment 7 - Non-Proprietary Version of SBLOCA Summary Report ML22153A1852022-06-0202 June 2022 Attachment 8 - Non-Proprietary Version of Non-LOCA Summary Report ULNRC-06715, Enclosure 3: Attachment a to the NPDES Permit Modification Application2022-03-0101 March 2022 Enclosure 3: Attachment a to the NPDES Permit Modification Application ML22027A8092022-01-27027 January 2022 Enclosure 4: Callaway, Unit 1, Acronyms and Definitions ML22027A8082022-01-27027 January 2022 Enclosure 3: Callaway, Unit 1, Methodology for a Risk-Informed Approach to Address Generic Letter 2004-02 ML22027A8062022-01-27027 January 2022 Enclosure 1: Request for Exemptions for Risk-Informed Approach to Resolution for Generic Letter 2004-02 ML21356B5072021-12-22022 December 2021 Enclosure 1: Mark-up of Operating License (OL) ML21356B5082021-12-22022 December 2021 Enclosure 2: Clean Copy of Affected OL Pages (Reflecting Proposed Change) ML21343A0952021-12-0909 December 2021 Attachment 1: Description and Assessment ML21335A1602021-12-0101 December 2021 Special Report 2021-02: Accident Monitoring Instrumentation Non-Functional for Greater than 7 Days ML21280A3802021-10-0707 October 2021 Cumulative Summary of Changes to Enclosure 2, License Amendment Request, and Enclosure 3, Callaway Methodology for a Risk-Informed Approach to Address Generic Letter 2004-02, of ULNRC-06526 ML21280A3812021-10-0707 October 2021 License Amendment Request for Risk-Informed Approach to Resolution of Generic Letter 2004-02 ML21272A1702021-09-28028 September 2021 Enclosure 2 - Full Scope Implementation of Alternative Source Term Evaluation of Proposed Changes (Redacted) ML21237A1372021-08-23023 August 2021 Enclosure 1: Callaway, Unit 1, Amendment Request Regarding Risk-Informed Approach to Closure of Generic Safety Issue 191 - Baseline Weld Input ML21237A1382021-08-23023 August 2021 Enclosure 2: Callaway, Unit 1, Amendment Request Regarding Risk-Informed Approach to Closure of Generic Safety Issue 191 - CAL Roverd Results Baseline (Critical Breaks) ULNRC-06683, Enclosure 3: Callaway, Unit 1, Amendment Request Regarding Risk-Informed Approach to Closure of Generic Safety Issue 191 - CAL Roverd Results Baseline (Non-Isolable Breaks)2021-08-23023 August 2021 Enclosure 3: Callaway, Unit 1, Amendment Request Regarding Risk-Informed Approach to Closure of Generic Safety Issue 191 - CAL Roverd Results Baseline (Non-Isolable Breaks) ULNRC-06526, Methodology for a Risk-Informed Approach to Address Generic Letter 2004-022021-07-22022 July 2021 Methodology for a Risk-Informed Approach to Address Generic Letter 2004-02 ULNRC-06660, Cycle 24 Commitment Change Summary Report2021-06-22022 June 2021 Cycle 24 Commitment Change Summary Report ML21173A3412021-06-22022 June 2021 CFR 50.59 and 10 CFR 72.48 Summary Report - May 16, 2019 to June 15, 2021 ML21090A2502021-03-31031 March 2021 Attachment 1 - Changes to the Westinghouse ECCS Evaluation Model and PCT Penalty Assessments ML21090A1882021-03-31031 March 2021 Enclosure 3 - Callaway Methodology for a Risk-Informed Approach to Address Generic Letter 2004-02 2023-08-31
[Table view] Category:Miscellaneous
MONTHYEARML23156A6712023-06-0505 June 2023 Description and Justification for Changes ML23131A3882023-04-26026 April 2023 EIP-ZZ-PRO2O Minor Revision 54, Activation and Operation of the Joint Information Center - Procedure Review Form and 50.54(q) Screening Form ML23068A0992023-03-0909 March 2023 Special Report 2023-01 PAM Report ULNRC-06715, Enclosure 3: Attachment a to the NPDES Permit Modification Application2022-03-0101 March 2022 Enclosure 3: Attachment a to the NPDES Permit Modification Application ML22027A8062022-01-27027 January 2022 Enclosure 1: Request for Exemptions for Risk-Informed Approach to Resolution for Generic Letter 2004-02 ML22027A8092022-01-27027 January 2022 Enclosure 4: Callaway, Unit 1, Acronyms and Definitions ML21356B5072021-12-22022 December 2021 Enclosure 1: Mark-up of Operating License (OL) ML21356B5082021-12-22022 December 2021 Enclosure 2: Clean Copy of Affected OL Pages (Reflecting Proposed Change) ML21343A0952021-12-0909 December 2021 Attachment 1: Description and Assessment ML21335A1602021-12-0101 December 2021 Special Report 2021-02: Accident Monitoring Instrumentation Non-Functional for Greater than 7 Days ML21280A3802021-10-0707 October 2021 Cumulative Summary of Changes to Enclosure 2, License Amendment Request, and Enclosure 3, Callaway Methodology for a Risk-Informed Approach to Address Generic Letter 2004-02, of ULNRC-06526 ML21280A3812021-10-0707 October 2021 License Amendment Request for Risk-Informed Approach to Resolution of Generic Letter 2004-02 ML21173A3412021-06-22022 June 2021 CFR 50.59 and 10 CFR 72.48 Summary Report - May 16, 2019 to June 15, 2021 ULNRC-06437, Cycle 22 Commitment Change Summary Report2018-06-0707 June 2018 Cycle 22 Commitment Change Summary Report ULNRC-06349, Callaway, Unit 1 - Enclosure 2 to ULNRC-06349 - Minimum Decommissioning Cost - Per 10 CFR 50.75 Formula Process2017-03-30030 March 2017 Callaway, Unit 1 - Enclosure 2 to ULNRC-06349 - Minimum Decommissioning Cost - Per 10 CFR 50.75 Formula Process ML17097A5582017-03-30030 March 2017 Enclosure 2 to ULNRC-06349 - Minimum Decommissioning Cost - Per 10 CFR 50.75 Formula Process ML16160A0952016-06-0808 June 2016 ASP ANALYSIS-REJECT- Callaway Unit 1 Auxiliary Feedwater Control Valves in Motor Driven Pump Train Inoperable due to Faulty Electric positioner Cards (LER 483-2015-003 and 483-2015-004) ULNRC-06292, Transmittal of 10 CFR50.46 Annual Report ECCS Evaluation Model Revisions2016-03-30030 March 2016 Transmittal of 10 CFR50.46 Annual Report ECCS Evaluation Model Revisions ULNRC-06199, Nuclear Property Insurance Reporting2015-03-18018 March 2015 Nuclear Property Insurance Reporting ULNRC-06173, Submits Owner'S Activity Reports (OAR-1 Forms) for Cycle 20 and Refuel 202015-02-19019 February 2015 Submits Owner'S Activity Reports (OAR-1 Forms) for Cycle 20 and Refuel 20 ML14310A8362015-02-0909 February 2015 NRC Staff Evaluation of Final Rule for Continued Storage of Spent Nuclear Fuel for the License Renewal Environmental Review for Callaway, Unit 1 ULNRC-06168, Enclosure 10 - Articles of Incorporation Ameren Corporation Restated 10/17/19952014-12-18018 December 2014 Enclosure 10 - Articles of Incorporation Ameren Corporation Restated 10/17/1995 ULNRC-06168, Enclosure 7 - 10-Q Filed Period 6/30/2014 Ameren2014-12-18018 December 2014 Enclosure 7 - 10-Q Filed Period 6/30/2014 Ameren ULNRC-06168, Enclosure 16 - Articles of Incorporation - Union Electric Company Restated 04/12/19942014-12-18018 December 2014 Enclosure 16 - Articles of Incorporation - Union Electric Company Restated 04/12/1994 ULNRC-06168, Enclosure 5 - 10-K Filed Period 12/31/2013 - Ameren2014-12-18018 December 2014 Enclosure 5 - 10-K Filed Period 12/31/2013 - Ameren ULNRC-06168, Enclosure 8 - 10-Q Filed Period 9/30/2014 Ameren2014-12-18018 December 2014 Enclosure 8 - 10-Q Filed Period 9/30/2014 Ameren ULNRC-06168, Enclosure 9 - Articles of Incorporation Ameren Corporation Dated 08/07/19952014-12-18018 December 2014 Enclosure 9 - Articles of Incorporation Ameren Corporation Dated 08/07/1995 ULNRC-06168, Enclosure 14 - Defc 14c Filed Period 3/11/2014 - Union Electric2014-12-18018 December 2014 Enclosure 14 - Defc 14c Filed Period 3/11/2014 - Union Electric ULNRC-06168, Enclosure 6 - 10-Q Filed Period 3/31/2014 - Ameren2014-12-18018 December 2014 Enclosure 6 - 10-Q Filed Period 3/31/2014 - Ameren ULNRC-06168, Enclosure 11 - Ameren Corporation By-Laws Effective 12/14/20122014-12-18018 December 2014 Enclosure 11 - Ameren Corporation By-Laws Effective 12/14/2012 ULNRC-06168, Enclosure 15 - Articles of Incorporation - Missouri Electric Light and Power Company Dated 11/20/19222014-12-18018 December 2014 Enclosure 15 - Articles of Incorporation - Missouri Electric Light and Power Company Dated 11/20/1922 ULNRC-06168, Enclosure 4 - 2013 Annual Report (Includes 2013 Form 10-K) - Ameren2014-12-18018 December 2014 Enclosure 4 - 2013 Annual Report (Includes 2013 Form 10-K) - Ameren ULNRC-06168, Enclosure 17 - By-Laws of Union Electric Company as Amended to 12/10/20102014-12-18018 December 2014 Enclosure 17 - By-Laws of Union Electric Company as Amended to 12/10/2010 ML14352A4292014-12-18018 December 2014 Enclosure 15 - Articles of Incorporation - Missouri Electric Light and Power Company Dated 11/20/1922 ML14352A4302014-12-18018 December 2014 Enclosure 17 - By-Laws of Union Electric Company as Amended to 12/10/2010 ML14352A4472014-12-18018 December 2014 Enclosure 3 - 2014 Proxy Statement of Ameren Corporation - Ameren ML14352A4322014-12-18018 December 2014 Enclosure 16 - Articles of Incorporation - Union Electric Company Restated 04/12/1994 ML14352A4332014-12-18018 December 2014 Enclosure 4 - 2013 Annual Report (Includes 2013 Form 10-K) - Ameren ML14352A4342014-12-18018 December 2014 Enclosure 11 - Ameren Corporation By-Laws Effective 12/14/2012 ML14352A4352014-12-18018 December 2014 Enclosure 6 - 10-Q Filed Period 3/31/2014 - Ameren ML14352A4362014-12-18018 December 2014 Enclosure 14 - Defc 14c Filed Period 3/11/2014 - Union Electric ML14352A4382014-12-18018 December 2014 Enclosure 9 - Articles of Incorporation Ameren Corporation Dated 08/07/1995 ML14352A4392014-12-18018 December 2014 Enclosure 8 - 10-Q Filed Period 9/30/2014 Ameren ML14352A4402014-12-18018 December 2014 Enclosure 5 - 10-K Filed Period 12/31/2013 - Ameren ML14352A4412014-12-18018 December 2014 Enclosure 7 - 10-Q Filed Period 6/30/2014 Ameren ML14352A4432014-12-18018 December 2014 Enclosure 10 - Articles of Incorporation Ameren Corporation Restated 10/17/1995 ULNRC-06157, Special Report 2014-04: Inoperability of a Seismic Instrument for Greater than 30 Days2014-11-14014 November 2014 Special Report 2014-04: Inoperability of a Seismic Instrument for Greater than 30 Days ML14290A5322014-10-29029 October 2014 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood -Causing Mechanism Reevaluation ULNRC-06139, Special Report 2014-01 - PAM Report Inoperability of a Post Accident Monitoring (PAM) Instrument2014-09-0202 September 2014 Special Report 2014-01 - PAM Report Inoperability of a Post Accident Monitoring (PAM) Instrument RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 2023-06-05
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Enclosure to ULNRC-05960 Westinghouse Non-Proprietary Class 3 Page 1 of 11 To: Paula Pawlak Date: February 18, 2013 cc: Debbie Kelly From: Post-Fukushima Products & Services Your Ref: LTR-PFPS-13-3 Tel: 412-374-2304 Revision 0
Subject:
Ameren Missouri Spent Fuel Pool Instrumentation Integrated Plan
Reference:
- 1. EA-12-051, Issuance of Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation, March 12, 2012.
Westinghouse has been contracted by Ameren Missouri to draft the Spent Fuel Pool (SFP) instrumentation integrated plan in response to the Nuclear Regulatory Commission (NRC) Order EA-12-051 (Reference 1).
Attachment 1 contains the SFP instrumentation integrated plan for Ameren Missouri to support their submittal to the NRC by February 28, 2013.
The integrated plan was prepared utilizing industry feedback and lessons learned from the Nuclear Energy Institute (NEI) meeting attended by Westinghouse on January 15, 2013, STARS feedback from the February 6, 2013 benchmark meeting, and feedback provided by Ameren Missouri.
Any questions can be directed to Mike Drudy at drudymp@westinghouse.com or 412-374-2304.
Author: Mike Drudy* Author: Monzer Allam*
Post-Fukushima Products & Services Plant Engineering, US Verifier: Dennis Skeers* Verifier: Jason Beasley*
Process Instrumentation Electrical and I&C Verifier: Jim Smith*
Plant Licensing Manager: Stephanie Harsche*
Post-Fukushima Products & Services Attachments:
Attachment 1 - Callaway Unit 1 Integrated Plan for Reliable Spent Fuel Pool Instrumentation
© 2013 Westinghouse Electric Company LLC All Rights Reserved
- Electronically approved records are authenticated in the Electronic Document Management System.
Enclosure to ULNRC-05960 Page 2 of 11 Westinghouse NonProprietary Class 3 Callaway Unit 1 Integrated Plan for Reliable Spent Fuel Pool Instrumentation I. Introduction The Nuclear Regulatory Commission (NRC) issued Order EA12051, Issuance of Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation, (Reference 1) dated March 12, 2012. The Order requires licenses to have a reliable indication of the water level in associated spent fuel storage pools capable of supporting identification of the following pool water level conditions by trained personnel: (1) level that is adequate to support operation of the normal fuel pool cooling system, (2) level that is adequate to provide substantial radiation shielding for a person standing on the spent fuel pool operating deck, and (3) level where fuel remains covered and actions to implement makeup water addition should no longer be deferred. The Order also requires submission of an overall integrated plan that provides a description of how the requirements of the Order will be achieved.
Nuclear Energy Institute (NEI) 1202, Industry Guidance for Compliance with NRC Order EA12051, To Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation, (Reference 2) provides an approach for complying with order EA12051. NRC Interim Staff Guidance (ISG) JLDISG201203, Compliance with Order EA12051, Reliable Spent Fuel Pool Instrumentation, (Reference 3) considers that the methodologies and guidance in conformance with the guidelines provided in Reference 2, subject to the clarifications and exceptions specific to Reference 2, Section 3.4, Qualification, are an acceptable means of meeting the requirements of Reference 1.
This integrated plan applies to Callaway Energy Center Unit 1 (hereafter referred to as Callaway) and provides the approach for complying with Reference 1 using the methods described in Reference 3. Consistent with the requirements of Reference 1 and the guidance in Reference 2, sixmonth reports will delineate progress made, any proposed changes in compliance methods, updates to the schedule, and if needed, requests for relief and basis.
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Enclosure to ULNRC-05960 Page 3 of 11 Westinghouse NonProprietary Class 3 II. Schedule Installation of reliable spent fuel pool (SFP) level instrumentation will be completed prior to startup from the second refueling outage, after submittal of this plan, or December 31, 2016, whichever occurs first, consistent with Callaway Plant Unit 1 Initial Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Reference 4).
The following milestone schedule is provided. The dates are planning dates and are subject to change as design and implementation details are developed. Any changes to the following milestones will be reflected in the subsequent sixmonth status reports.
The current milestones are:
Commence Engineering and Design 1Q2013 Complete Design 4Q2013 Receipt of SFP Instruments 2Q2014 Complete SFP Instrumentation Procedures & Training 3Q2014 SFP Instruments Operational 4Q2014 III. Identification of Spent Fuel Pool Water Levels Key spent fuel pool water levels:
- 1. Level adequate to support operation of the normal fuel pool cooling system -
Indicated level on either the primary or backup instrument channel of 24 feet 10.75 inches above the top of the fuel storage racks plus the accuracy of the SFP level instrument channel, which is to be determined. This aligns with the normal SFP level as shown in Callaway Final Safety Analysis Report (FSAR) Figure 1.221 (Reference 5) and provides adequate margin to maintain fuel pool cooling pump suction.
- 2. Level adequate to provide substantial radiation shielding for a person standing on the spent fuel pool operating deck - Indicated level on either the primary or backup instrument channel of greater than 10 feet (+/ 1 foot) above the top of the fuel storage racks based on Reference 2 and Reference 3. This monitoring level ensures there is an adequate water level to provide substantial radiation shielding for a person standing on the spent fuel pool operating deck.
- 3. Level where fuel remains covered Indicated level on either the primary or backup instrument channel of greater than 1 foot above the top of the fuel storage racks plus the accuracy of the SFP level instrument channel, which is to be determined. This LTRPFPS133 Attachment 1 Page 2 of 10 Revision 0
Enclosure to ULNRC-05960 Page 4 of 11 Westinghouse NonProprietary Class 3 monitoring level assures that there is adequate water level above the stored fuel seated in the rack.
IV. Instruments The design of the instruments will be consistent with the guidelines of Reference 2 and Reference 3 as discussed below.
Primary and Backup Instrument Channels:
The Callaway SFP Instrumentation System (SFPIS) will utilize fixed primary and backup guided wave radar (GWR) sensors. The GWR technology meets the requirements of Reference 1 and Reference 3 by providing the capability to reliably monitor the SFP water level under adverse environmental conditions.
GWR technology uses the principle of time domain reflectometry to detect the SFP water level.
A microwave signal is sent down the cable probe sensor, and when it reaches the water, it is reflected back to the sensor electronics. This is due to the difference between the dielectric constants of air and water. Using the total signal travel time, the sensor electronics embedded firmware computes the level of the water in the SFP. The probe, which is located in the SFP, is separated from the sensor electronics, and connected by an interconnecting cable that is routed into an adjacent building. By placing the sensor electronics outside of the SFP area it is not subject to the harsh environment resulting from the boiling or loss of water in the pool during a postulated loss of inventory event that creates high humidity, steam and/or radiation.
The primary and backup instrument channels will provide continuous level indication over a range of 23 feet 10.75 inches, from 12 inches above the top of the fuel storage racks (plant elevation 2,022 feet 1.25 inches) to the normal pool level elevation (plant elevation 2,046 feet) as shown in the Callaway FSAR Figure 1.221 (Reference 5).
V. Reliability Reliability of the primary and backup instrument channels will be assured by conformance with the guidelines of Reference 3 and Reference 2, Section 3.4, Qualification, and Section 4.3, Testing and Calibration.
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Enclosure to ULNRC-05960 Page 5 of 11 Westinghouse NonProprietary Class 3 VI. Instrument Channel Design Criteria:
Instrument channel design criteria will meet the guidelines of Reference 2 and Reference 3.
The primary and backup measurement systems will consist of a flexible stainlesssteel sensor cable probe, suspended in the SFP from a bracket attached to the operating deck or to a raised curb at the side of the pool. The cable probe will extend from slightly above the normal pool level elevation to less than 1 foot above the top of the fuel storage racks. The sensor electronics will be mounted in an adjacent building, to prevent instrument exposure to radiation and high temperatures which could result from a postulated loss of water inventory in the pool. There are also two mounted panels, providing sensor and display interfaces and wireless transmission and reception capabilities.
The 420 milliamp (mA) signal from the sensor electronics module is connected to a mounted, seismically qualified power supply and transmitter panel. The panel contains a 24 volt (V) direct current (dc) (Vdc) uninterruptible power supply (UPS), a wireless transmitter for the sensor signal, and batteries for continued system operation during a loss of alternating current (ac) power for a minimum of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, in which time an alternate external source of power can be supplied. A bulkhead connector and transfer switch is externally accessible for the connection of an alternate power source. The panel is located with or near the sensor electronics housing, outside of the spent fuel pool area. The interface between the sensor electronics and the mounted panel is a twisted, shielded pair cable.
The transmitter panel will send a signal to the wireless receiver panel. The mounted seismically qualified wireless receiver panel contains a 24Vdc UPS, doormounted digital display of SFP level, and batteries for continued system operation during a loss of ac power until an alternate external source of power can be supplied. A bulkhead connector and transfer switch is externally accessible for the connection of an alternate power source. The mounted receiver panel is located in one of the accessible locations in the vicinity of the control room.
VII. Arrangement The primary and backup instrument sensing components will be separated consistent with the guidelines of Reference 2 and Reference 3. Design of the mounting bracket will allow the fuel handling machine to pass over it without interference.
A SFP walkdown identified preliminary locations for the primary and backup level sensing components. The preliminary locations of the primary and backup instrument sensing components are at the plant northeast and northwest corners of the SFP. The design for LTRPFPS133 Attachment 1 Page 4 of 10 Revision 0
Enclosure to ULNRC-05960 Page 6 of 11 Westinghouse NonProprietary Class 3 installation will include physical separation of the two sensors, separate extension cables from the electronics to the sensors, routing all cables in separate conduit / trays, separate UPS power supplied from different ac sources, and seismically qualified mounting with physical separation of both the level sensing electronics and indications.
The final location of the primary and backup system mounting brackets will be determined during the design phase with consideration of power availability and separation requirements to protect against missiles.
The level sensing electronics for both primary and backup systems will be located in the auxiliary building, compliant with Reference 2 and Reference 3 for separation and accessibility.
The primary system indicator will be located in the vicinity of the control room. The backup system indicator will be located in an accessible location. The locations will allow for reading of the indicators following an event.
VIII. Mounting The mounting of both the primary and backup system will be installed to maintain its integrity during and following a design basis seismic event. All locations will be reviewed for twooverone seismic interference.
IX. Qualification Reliability of both instrument channels will be demonstrated via an appropriate combination of design, analyses, operating experience, and/or testing of channel components for the following sets of parameters:
(1) conditions in the area of instrument channel component used for all instrument components, (2) effects of shock and vibration on instrument channel components used during and following any applicable event for installed components, and (3) seismic effects on instrument channel components used during and following a potential seismic event for only installed components.
The normal operational, event, and postevent conditions for temperature, humidity, and radiation, will be addressed for no fewer than seven days postevent or until offsite resources can be deployed by the mitigating strategies resulting from the NRC issued Order EA12049, Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for LTRPFPS133 Attachment 1 Page 5 of 10 Revision 0
Enclosure to ULNRC-05960 Page 7 of 11 Westinghouse NonProprietary Class 3 BeyondDesignBasis External Events, dated March 12, 2012 (Reference 6). Examples of postevent (beyonddesignbasis) conditions to be considered are:
(1) radiological conditions for a normal refueling quantity of freshly discharged (100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />) fuel with the SFP water level 3 (Section III, Item 3) as described in Reference 1, (2) temperatures of 212°F and 100 percent relative humidity environment, (3) boiling water and/or steam environment, (4) a concentrated borated water environment, (5) impact of FLEX mitigating strategies.
The instrument channel reliability will be demonstrated via an appropriate combination of design, analyses, operating experience, and/or testing of channel components for the effects of shock and vibration. Demonstration of shock and vibration adequacy will be consistent with the guidelines in Reference 2 and Reference 3.
Demonstration of seismic adequacy will be achieved using one or more of the following methods:
(1) demonstration of seismic motion consistent with that of existing design basis loads at the installed location; (2) substantial history of operational reliability in environments with significant vibration, such as for portable handheld devices or transportation applications. Such a vibration design envelope shall be inclusive of the effects of seismic motion imparted to the components proposed at the location of the proposed installation; (3) adequacy of seismic design and installation is demonstrated based on the guidance in Sections 7, 8, 9, and 10 of IEEE Standard 3442004, IEEE Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations, (Reference 7) or a substantially similar industrial standard; (4) demonstration that proposed devices are substantially similar in design to models that have been previously tested for seismic effects in excess of the plant design basis at the location where the instrument is to be installed (glevels and frequency ranges); or (5) seismic qualification using seismic motion consistent with that of existing design basis loading at the installation location.
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Enclosure to ULNRC-05960 Page 8 of 11 Westinghouse NonProprietary Class 3 X. Independence The backup instrument system will be redundant to and independent of the primary instrument system.
Independence of the two systems includes: location, mounting, power sources, power and signal wiring, and indications, to prevent any failure of one system from affecting the other system.
XI. Power Supplies An ac source will be selected for each systems 24Vdc UPS, with power cables routed separately through existing or new tray / conduit and penetrations.
Both channels will be powered by independent batteries following a lossofac power. The minimum battery life will be 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> battery life is a sufficient amount of time for an alternate source of power to be provided by the plantspecific procedures to address Reference 6. Each channel will include an externally accessible bulkhead connector and transfer switch for connection of an alternate power source.
XII. Accuracy Instrument channels will be designed such that they will maintain their specified accuracy without recalibration following a power interruption or change in power source.
The accuracy will be within the resolution requirements of Reference 2, Figure 1.
The instrument accuracy will be sufficient to allow personnel using plant procedures to determine when the water level reaches levels 1, 2, and 3 without conflicting or ambiguous indication.
XIII. Testing Instrument channel design will provide for routine testing and calibration consistent with Reference 2 and Reference 3.
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Enclosure to ULNRC-05960 Page 9 of 11 Westinghouse NonProprietary Class 3 XIV. Display The primary system indicator will be located in the vicinity of the control room. The backup system indicator will be located in an accessible location. The locations will allow for reading of the indicators following an event. The display will provide continuous indication of the SFP water level and will be consistent with the guidelines of Reference 2 and Reference 3.
XV. Instrument Channel Program Criteria Instrument channel program criteria will be consistent with the guidelines of Reference 2 and Reference 3.
A. Training The Systematic Approach to Training (SAT) will be used to identify the population to be trained and to determine both the initial and continuing elements of the required training. Training will be completed prior to placing the instrumentation in service.
B. Procedures Procedures will be developed using guidelines and vendor instructions to address the maintenance, operation, and abnormal response issues associated with the new SFP instrumentation.
FLEX Support Guidelines will address a strategy to ensure the SFP water makeup is initiated at an appropriate time consistent with implementation of NEI 1206, Diverse and Flexible Coping Strategies (FLEX) Implementation Guide, (Reference 8).
C. Testing and Calibration Processes will be established and maintained for scheduling and implementing necessary testing and calibration of the primary and backup spent fuel pool level instrument channels to maintain the instrument channels at the design accuracy.
Testing and calibration of the instrumentation will be consistent with vendor recommendations and any other documented basis.
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Enclosure to ULNRC-05960 Page 10 of 11 Westinghouse NonProprietary Class 3 XVI. Need for Relief and Basis Ameren Missouri is not requesting relief from the requirements of Reference 1 or the guidance in Reference 3 at this time.
Consistent with the requirements of Reference 1 and the guidance in Reference 2, the six month reports will delineate progress made, any proposed changes in the compliance methods, updates to the schedule, and if needed, requests for relief and their bases.
XVII. References
- 1) EA12051, Issuance of Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation, March 12, 2012.
- 2) NEI 1202, Industry Guidance for Compliance with NRC Order EA12051, To Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation, Revision 1, August 2012.
- 3) NRC JLDISG201203, Compliance with Order EA12051, Reliable Spent Fuel Pool Instrumentation, Revision 0, August 29, 2012.
- 4) Ameren Missouri Letter ULNRC05925, Docket Number 50483, Callaway Plant Unit 1, Union Electric Co., Facility Operating License NPF30, Initial Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA12051), October 29, 2012.
- 5) Callaway Final Safety Analysis Report, Revision OL19a, July 2012.
- 6) EA12049, Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for BeyondDesignBasis External Events, March 12, 2012.
- 7) IEEE Standard 3442004, IEEE Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations.
- 8) NEI 1206, Diverse and Flexible Coping Strategies (FLEX) Implementation Guide, Revision 0, August 2012.
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Enclosure to ULNRC-05960 Page 11 of 11 Westinghouse NonProprietary Class 3 XVIII. Sketches Plant North Sketch 1 Preliminary Probe Locations for Callaway Unit 1 XIX. Open Items There are no open items.
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