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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:Technical Specification
MONTHYEARULNRC-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) ML23310A0512023-11-0606 November 2023 EIP-ZZ.OO1O1, Addendum 2, Revision 22, Emergency Action Level Technical Bases Document ML23227A1272023-08-15015 August 2023 Corrected Proposed Technical Specification 55.16 Changes (Markup) ML23227A1282023-08-15015 August 2023 Corrected Proposed Technical Specification 5.5.16 Changes (Clean Pages) ML23206A2252023-07-25025 July 2023 Corrected Proposed Technical Specification 5.5.16 Changes (Clean Pages) ML23206A2242023-07-25025 July 2023 Corrected Proposed Technical Specification 5.5.16 Changes (Markup) ML23093A0952023-05-10010 May 2023 Issuance of Amendment No. 232 Regarding Technical Specification Changes for Spent Fuel Storage ML23088A1222023-03-29029 March 2023 Attachment 2: Revised (Clean) Technical Specification Pages ML23088A1232023-03-29029 March 2023 Attachment 3: Marked-Up Technical Specification, Bases Pages ML23088A1212023-03-29029 March 2023 Attachment 1: Marked-Up Technical Specification Pages ML23088A2542023-03-23023 March 2023 EIP-ZZ-00101, Addendum 2, Revision 020, Emergency Action Level Technical Bases Document ML23052A0472023-02-21021 February 2023 Enclosure 5 - Revised Technical Specification Bases (for Information Only) ML23067A1832022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Table of Contents ML23067A1752022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Chapter 3.3, Instrumentation ML23067A1762022-12-29029 December 2022 Rev. 18 to Technical Specification Bases, Chapter 3.5, Emergency Core Cooling System S(Eccs) ML23067A1742022-12-29029 December 2022 Rev. 18 to Technical Specifications, Bases Change, Chapter 3.7, Plant Systems ML23067A1772022-12-29029 December 2022 Rev. 18 to Technical Specification Bases Change, Chapter B3, Safety Limits (Sls) ML23067A1782022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Chapter 3.6, Containment Systems ML23067A1852022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Chapter B 3.9, Refueling Operations ML23067A1842022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Chapter 3.4, Reactor Coolant System ML23067A1822022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Chapter 3.8, Electrical Power Systems ML23067A1792022-12-29029 December 2022 Rev. 18 to Technical Specification Bases, Implemented Change Notice Log ULNRC-06782, Rev. 18 to Technical Specification Bases, List of Effective Sections2022-12-29029 December 2022 Rev. 18 to Technical Specification Bases, List of Effective Sections ML23067A1802022-12-29029 December 2022 Rev. 18 to Technical Specification Bases, Chapter 3.1, Reactivity Control Systems ML23067A1812022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Chapter B2, Safety Limits (Sls) ML23067A1862022-12-29029 December 2022 Rev. 18 to Technical Specification, Bases Change, Chapter 3.2, Power Distribution Limits ML22335A5092022-12-0101 December 2022 Description and Assessment of the Proposed Change ML22335A5112022-12-0101 December 2022 Attachment 2 - Proposed TS Bases Changes (Markups) ML22307A3142022-11-0303 November 2022 Attachment 2: Proposed Technical Specification 5.5.16 Changes (Markup) ML22307A3152022-11-0303 November 2022 Attachment 3: Proposed Technical Specification 5.5.16 Changes (Clean Pages) ML22285A1202022-10-12012 October 2022 Attachment 3 to Enclosure 1: Marked-Up Technical Specifications Bases (for Information Only) ML22251A3452022-09-0808 September 2022 Attachment 2: Retyped TS Pages for TS 3.6.8 ML22242A1262022-08-29029 August 2022 Attachment 2 to Enclosure 1 - Revised Clean Technical Specifications ML22242A1272022-08-29029 August 2022 Attachment 3 to Enclosure 1 - Marked-Up Technical Specification Bases ML22242A1252022-08-29029 August 2022 Attachment 1 to Enclosure 1 - Marked-Up Existing Technical Specifications ML22216A2422022-08-0404 August 2022 Proposed Technical Specification Changes (Mark-Up) ML22181B1342022-06-30030 June 2022 Attachment 4 - Replacement for Attachment 4, Proposed Changes to Technical Specification Bases Changes (Mark-Up) Pages (for Information), of ULNRC-06688 ML22153A1792022-06-0202 June 2022 Attachment 3 - Marked-Up Technical Specifications Bases ULNRC-06686, Attachment 4: Proposed Technical Specifications Bases Changes (Mark-Up)2021-12-0909 December 2021 Attachment 4: Proposed Technical Specifications Bases Changes (Mark-Up) ML21335A4572021-12-0101 December 2021 Enclosure 5: Proposed Technical Specification Bases Changes (Mark-up - for Info Only) ML21294A4102021-10-21021 October 2021 Enclosure 10 - Program Implementation ML21294A4112021-10-21021 October 2021 Enclosure 11 - Monitoring Program ML21294A4092021-10-21021 October 2021 Enclosure 9 - Key Assumptions and Sources of Uncertainty ML21294A4122021-10-21021 October 2021 Enclosure 12 - Risk Management Action Examples ML21294A4072021-10-21021 October 2021 Enclosure 7 - PRA Model Update Process ML21294A4062021-10-21021 October 2021 Enclosure 6 - Justification of Application of At-Power PRA Models to Shutdown Modes ML21294A4052021-10-21021 October 2021 Enclosure 5 - Baseline Core Damage Frequency (CDF) and Large Early Release Frequency (LERF) ML21294A4042021-10-21021 October 2021 Enclosure 4 - Information Supporting Justification of Excluding Sources of Risk Not Addressed by the PRA Models ML21294A4032021-10-21021 October 2021 Enclosure 3 - Information Supporting Technical Adequacy of PRA Models Without PRA Standards Endorsed by Regulatory Guide 1.200, Revision 2 ML21294A4082021-10-21021 October 2021 Enclosure 8 - Attributes of the Real Time Risk Model 2023-08-15
[Table view] Category:Amendment
MONTHYEARML23206A2242023-07-25025 July 2023 Corrected Proposed Technical Specification 5.5.16 Changes (Markup) ML23206A2252023-07-25025 July 2023 Corrected Proposed Technical Specification 5.5.16 Changes (Clean Pages) ML23093A0952023-05-10010 May 2023 Issuance of Amendment No. 232 Regarding Technical Specification Changes for Spent Fuel Storage ML23088A1222023-03-29029 March 2023 Attachment 2: Revised (Clean) Technical Specification Pages ML23088A1212023-03-29029 March 2023 Attachment 1: Marked-Up Technical Specification Pages ML22251A3452022-09-0808 September 2022 Attachment 2: Retyped TS Pages for TS 3.6.8 ML22242A1262022-08-29029 August 2022 Attachment 2 to Enclosure 1 - Revised Clean Technical Specifications ML22242A1252022-08-29029 August 2022 Attachment 1 to Enclosure 1 - Marked-Up Existing Technical Specifications ML21294A3992021-10-21021 October 2021 Attachment 5 - Cross-Reference of TSTF-505 and Callaway Technical Specifications ML21294A4122021-10-21021 October 2021 Enclosure 12 - Risk Management Action Examples ML21294A4102021-10-21021 October 2021 Enclosure 10 - Program Implementation ML21294A4112021-10-21021 October 2021 Enclosure 11 - Monitoring Program ML21294A4092021-10-21021 October 2021 Enclosure 9 - Key Assumptions and Sources of Uncertainty ML21294A4082021-10-21021 October 2021 Enclosure 8 - Attributes of the Real Time Risk Model ML21294A4072021-10-21021 October 2021 Enclosure 7 - PRA Model Update Process ML21294A4062021-10-21021 October 2021 Enclosure 6 - Justification of Application of At-Power PRA Models to Shutdown Modes ML21294A4052021-10-21021 October 2021 Enclosure 5 - Baseline Core Damage Frequency (CDF) and Large Early Release Frequency (LERF) ML21294A4042021-10-21021 October 2021 Enclosure 4 - Information Supporting Justification of Excluding Sources of Risk Not Addressed by the PRA Models ML21294A4032021-10-21021 October 2021 Enclosure 3 - Information Supporting Technical Adequacy of PRA Models Without PRA Standards Endorsed by Regulatory Guide 1.200, Revision 2 ML21294A4022021-10-21021 October 2021 Enclosure 2 - Information Supporting Consistency with Regulatory Guide 1.200, Revision 2 ML21294A4012021-10-21021 October 2021 Enclosure 1 - List of Revised Required Actions to Corresponding PRA Functions ML21294A4002021-10-21021 October 2021 Attachment 6 - Description and Assessment Specific to TSTF-439 ML21294A3972021-10-21021 October 2021 Attachment 3 - Revised Technical Specification Pages ML21294A3962021-10-21021 October 2021 Attachment 2 - Proposed Technical Specification Changes (Mark-Up) ML21294A3952021-10-21021 October 2021 Attachment 1 - Description and Assessment ML20070R1212020-03-10010 March 2020 Technical Specification Page Markup ML20070R1142020-03-10010 March 2020 Description and Assessment of the Proposed Change ULNRC-06433, License Amendment Request for Emergency Action Level (EAL) Changes2018-09-0404 September 2018 License Amendment Request for Emergency Action Level (EAL) Changes ULNRC-06264, Revision of TS 2.1.1.1 and 5.6.5 to Remove Uncertainties from the DNBR Safety Limit and Adopt Approved WCAP-14565-P-A Methodology2015-11-0909 November 2015 Revision of TS 2.1.1.1 and 5.6.5 to Remove Uncertainties from the DNBR Safety Limit and Adopt Approved WCAP-14565-P-A Methodology ML15062A0522015-03-0606 March 2015 NRC-Callaway-TS-renewed License ULNRC-05832, Revision of Technical Specification 3.3.8, TAC No. ME51732011-12-13013 December 2011 Revision of Technical Specification 3.3.8, TAC No. ME5173 ML1130706942011-11-0303 November 2011 Attachment 5 - Control Building Room Locations and P&ID Excerpts ML1130706832011-11-0303 November 2011 Attachment 1 - Technical Specification Page Mark Up ML1130706812011-11-0303 November 2011 Enclosure Page 1 of 22, Evaluation of the Proposed Change ULNRC-05804, Facility Operating License NPF-30 - Proposed Revision to Technical Specification 3.6.6, Containment Spray and Cooling Systems, (License Amendment Request LDCN 09-0025)2011-06-30030 June 2011 Facility Operating License NPF-30 - Proposed Revision to Technical Specification 3.6.6, Containment Spray and Cooling Systems, (License Amendment Request LDCN 09-0025) ULNRC-05793, Application for Amendment to Facility Operating License NPF-30 (LDCN 10-0036) Revision of Technical Specification 3.3.8,2011-06-16016 June 2011 Application for Amendment to Facility Operating License NPF-30 (LDCN 10-0036) Revision of Technical Specification 3.3.8, ULNRC-05682, Application for Amendment, Revision of Technical Specification 3.3.92010-03-0404 March 2010 Application for Amendment, Revision of Technical Specification 3.3.9 ULNRC-05560, Revision of Technical Specifications 3.8.4 and 3.8.5, Application for Amendment to Facility Operating License NPF-30 (LDCN 08-002)2008-12-29029 December 2008 Revision of Technical Specifications 3.8.4 and 3.8.5, Application for Amendment to Facility Operating License NPF-30 (LDCN 08-002) ML0824602412008-11-24024 November 2008 Issuance of Amendment No. 187, Revise Technical Specification 5.5.8, Inservice Testing Program, Testing Frequencies ULNRC-05494, Application for Amendment to Facility Operating License NPF-30 OL1283 - Revision of Technical Specifications 3.3, 3.7, and 3.82008-06-0303 June 2008 Application for Amendment to Facility Operating License NPF-30 OL1283 - Revision of Technical Specifications 3.3, 3.7, and 3.8 ML0706803502007-03-21021 March 2007 License and Technical Specification Pages - Amendment No. 182 Revision to Technical Specifications for Use of Beacon Power Distribution Monitoring System ML0632801852006-11-17017 November 2006 Callaway - Proposed Revision to Technical Specification 3.9.2 Unborated Water Source Isolation Valves and Associated Revisions to Technical Specification 3.3.9 Boron Dilution Mitigation System (Bdms) (License Amendment Request OL 1238) ULNRC-05345, Proposed Revision to Technical Specification 3.9.2 Unborated Water Source Isolation Valves and Associated Revisions to Technical Specification 3.3.9 Boron Dilution Mitigation System (Bdms).2006-11-17017 November 2006 Proposed Revision to Technical Specification 3.9.2 Unborated Water Source Isolation Valves and Associated Revisions to Technical Specification 3.3.9 Boron Dilution Mitigation System (Bdms). ULNRC-05314, Exigent Request for Revision to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation.2006-07-19019 July 2006 Exigent Request for Revision to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation. ULNRC-05301, Proposed Revision to Technical Specification TSs 3.7.10, 3.7.11 and 3.7.132006-06-0707 June 2006 Proposed Revision to Technical Specification TSs 3.7.10, 3.7.11 and 3.7.13 ULNRC-05297, Proposed Revision to Technical Specifications for Use of Beacon Power Distribution Monitoring System2006-05-25025 May 2006 Proposed Revision to Technical Specifications for Use of Beacon Power Distribution Monitoring System ULNRC-05269, Proposed Revision to Technical Specification 3.9.2 Unborated Water Source Isolation Valves and Associated Revisions to Technical Specification 3.3.9 Boron Dilution Mitigation System (Bdms) (License Amendment Request OL 1238)2006-03-28028 March 2006 Proposed Revision to Technical Specification 3.9.2 Unborated Water Source Isolation Valves and Associated Revisions to Technical Specification 3.3.9 Boron Dilution Mitigation System (Bdms) (License Amendment Request OL 1238) ULNRC-05206, License Amendment Request OL 1258 Revision to Technical Specification 3.7.3, Main Feedwater Isolation Valves (Mfiv'S)2005-09-0909 September 2005 License Amendment Request OL 1258 Revision to Technical Specification 3.7.3, Main Feedwater Isolation Valves (Mfiv'S) ML0506903182005-03-0808 March 2005 Technical Specification Pages Re Elimination of Requirements to Provide Monthly Operating Reports & Annual Occupational Radiation Exposure Reports ULNRC-05117, Technical Specification Revisions Associated with the Steam Generator Replacement Project2005-02-11011 February 2005 Technical Specification Revisions Associated with the Steam Generator Replacement Project 2023-07-25
[Table view] |
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Callaway Plant MISSOURI November 09, 2015 ULNRC-06264 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-000 1 10 CFR 50.90 Ladies and Gentlemen:
DOCKET NUMBER 50-483 CALLA WAY PLANT UNIT 1 UNION ELECTRIC CO.RENEWED FACILITY OPERATING LICENSE NPF-30 REVISION OF TS 2.1.1.1 AND 5.6.5 TO REMOVE UNCERTAINTIES FROM THE DNBR SAFETY LIMIT AND ADOPT APPROVED WCAP-14565-P-A METHODOLOGY
Reference:
ULNRC-06215 Letter from S.A.Maglio (Ameren Missouri)to U.S.Nuclear Regulatory Commission,"Revision of TS 2.1.1.1 and 5.6.5 to Remove Uncertainties from the DNBR Safety Limit and Adopt Approved WCAP-14565-P-A Methodology,"
dated May 8, 2015[NRC ADAMS Accession Number ML15132A137j In the referenced document above, Ameren Missouri submitted an application for amendment to Renewed Facility License Number NPF-30 for the Callaway Plant.That amendment application proposed changes to Technical Specification (TS)requirements to adopt the NRC approved methodology described in WCAP-14565-P-A Addendum 2-P-A,"Extended Application of ABB-NV Correlation and Modified ABB-NV Correlation WLOP for PWR Low Pressure Applications,"
and revise TS 2.1.1.1 to provide a safety limit for the Departure from Nucleate Boiling Ratio (DNBR)that is aligned with the original intent of approved topical report WCAP-144$3,"Generic Methodology for Expanded Core Operating Limits Report."From the NRC staffs review, a request for additional information (RAI)was identified and issued electronically on October 13, 2015 with a response requested by November 12, 2015.Attachment 1 provides the requested information.
The information provided in Attachment 1 does not affect the licensing evaluations submitted in the referenced amendment application, nor does Attachment 1 alter the conclusions of those licensing evaluations.
Ameren Missouri continues to request approval of this license amendment request prior to reactor criticality during the restart from the upcoming Refuel 21 outage.Reactor criticality is currently scheduled for May 04, 2016.As noted in Ameren Missouri's May 08, 2015 letter, Ameren Missouri PD Box 620: Fulton, I'1O 65251: rnerenIVissouri.corn STARS Alliance ULNRC-06264 November 09, 2015 Page 2 requests that the license amendment be made effective upon NRC issuance, to be implemented within 90 days from the date of issuance.This submittal does not contain new commitments.
If there are any questions, please contact Mr.Tom Elwood at 314-225-1905.
I declare under penalty of perjury that the foregoing is true and correct.Sincerely, Executed on:/10 tf7 4 Scott A.Maglio Manager, Regulatory Affairs TAW Attachments:
1.Response to NRC Request for Additional Information Regarding LDCN 15-0005 ULNRC-06264 November 06, 2015 Page 3 cc: Mr.Marc L.Dapas Regional Administrator U.S.Nuclear Regulatory Commission Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 Senior Resident Inspector Callaway Resident Office U.S.Nuclear Regulatory Commission
$201 NRC Road$teedman, MO 65077 Mr.L.John Klos Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission Mail Stop O$H4 Washington, DC 20555-000 1 ULNRC-06264 November 06, 2015 Page 4 Index and send hardcopy to QA File A160.0761 Hardcopy: Certrec Corporation 6100 Western Place, Suite 1050 fort Worth, IX 76107 (Certrec receives ALL attachments as long as they are non-safeguards and may be publicly disclosed.)
Electronic distribution for the following can be made via Tech Spec ULNRC Distribution:
F.M.Diya D.W.Neterer L.H.Graessle T.E.Herrmann B.L.Cox L.H.Kanuckel S.A.Maglio I.B.Elwood Corporate Communications NSRB Secretary STARS Regulatory Affairs Mr.John O'Neill (Pillsbury Winthrop Shaw Pittman LLP)Missouri Public Service Commission Mr.Robert D.Stout (DNR)Ms.Leanne Tippett-Mosby (DNR)
Enclosure to ULNRC-06264 Attachment 1 Page 1 of 3 ATTACHMENT 1 RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION REGARDING LDCN 15-0005 Enclosure to ULNRC-06264 Attachment 1 Page 2 of 3 REQUEST FOR ADDITIONAL INFORMATION CALLA WAY PLANT, UNIT 1 UNION ELECTRIC CO.LICENSE AMENDMENT APPLICATION TO REVISE IS 2.1.1.1 AND 5.6.5 TO REMOVE UNCERTAINTIES FROM THE DNBR SAFETY LIMIT AND ADOPT APPROVED WCAP-14565-P-A METHODOLOGY The NRC staff requests additional information to complete its review of the license amendment request (LAR)to revise Technical Specification (IS)2.1.1.1 and 5.6.5 to remove uncertainties from the Departure from Nucleate Boiling Ratio (DNBR)safety limit and adopt approved WCAP-14565-P-A methodology.
By letter dated May 08, 2015 (NRC ADAMS Accession No.ML15132A137), Ameren Missouri (the licensee)requested the removal of analytical uncertainties from TS 2.1.1.1 consistent with the intent of WCAP-144$3-A.
From NRC staff review of the provided application, the NRC staff has the following question listed below.Question 1 10 CFR 50.36(c)requires licensees to include safety limits in the TS, defined as limits upon important process variables that are found to be necessary to reasonably protect the integrity of certain of the physical barriers that guard against the uncontrolled release of radioactivity.
The Departure from Nucleate Boiling Ration (DNBR)limit is one such safety limit, since it protects the integrity of the fuel cladding.The proposed change to IS 2.1.1.1 would only specify the 95/95 DNBR limit associated with the WRB-2 correlation.
However, the license amendment request is requesting approval of two additional alternative DNB correlations, each of which has its own unique DNBR limit.Please explain why the DNBR limits associated with the ABB-NV and Westinghouse Low Pressure Departure from Nucleate Boiling correlations are not being included in IS 2.1.1.1.RAI Response The proposed Technical Specification (TS)2.1.1.1 content provided in Reference 1 is consistent with the format in Volume 1 of NUREG-143 1, Revision 4 (Reference 2).The current format for TS 2.1.1.1 in Reference 2 is based on the approved topical report WCAP-14483-A,"Generic Methodology for Expanded Core Operating Limits Report,"(Reference 3).The Safety Evaluation Report (SER)for Reference 3 states that the safety limits, which were originally included in the Westinghouse TS as the Reactor Core Limits figure (Figure 2.1.1-1)to satisfy 1OCFR5O.36, are"intended to provide the relationship between the process variables that are available Enclosure to ULNRC-06264 Attachment 1 Page 3 of 3 to the operator (i.e., T-avg, pressurizer pressure, and thermal power)and the DNB design basis safety limit."With the approval of Reference 3, the Reactor Core Limits figure itself was moved from TS 2.1.1.1 to the COLR, and replaced with the true safety limits (DNBR and fuel melting limits)that are protected by staying within the bounds for the process variables defined by the Reactor Core Limits figure, thereby ensuring that the intent of 1OCFR5O.36 is satisfied.
Since the WRB-2 correlation is the only DNB correlation used to establish the COLR Reactor Core Limits figure for the Callaway plant, only the WRB-2 correlation and the associated 95/95 DNBR limit are specifically listed in TS 2.1.1.1.This is consistent with the format for 15 2.1.1.1 as specified in Reference 2.While the ABB-NV and Westinghouse Low Pressure (WLOP)DNB correlations will be used in the safety analyses for the Callaway plant, these correlations are neither applicable to nor will they be used for the establishment of the COLR Reactor Core Limits figure.It is not appropriate to list any DNB correlations and their associated limits in TS 2.1.1.1 that are not used in the establishment of the COLR Reactor Core Limits figure.
References:
1.Letter from S.A.Maglio (Ameren Missouri)to U.S.Nuclear Regulatory Commission,"Revision of TS 2.1.1.1 and 5.6.5 to Remove Uncertainties from the DNBR Safety Limit and Adopt Approved WCAP-14565-P-A Methodology' dated May 8, 2015[Nuclear Regulatory Commission ADAMS Accession Number ML 1513 2A 137].2.Standard Technical Specifications
-Westinghouse Plants: Volume 1, Specifications, NUREG 1431, Revision 4, April, 2012.3.D.S.Huegel, J.D.Andrachek, and C.E.Morgan,"Generic Methodology for Expanded Core Operating Limits Report,"WCAP-144$3-A, January, 1999.
Callaway Plant MISSOURI November 09, 2015 ULNRC-06264 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-000 1 10 CFR 50.90 Ladies and Gentlemen:
DOCKET NUMBER 50-483 CALLA WAY PLANT UNIT 1 UNION ELECTRIC CO.RENEWED FACILITY OPERATING LICENSE NPF-30 REVISION OF TS 2.1.1.1 AND 5.6.5 TO REMOVE UNCERTAINTIES FROM THE DNBR SAFETY LIMIT AND ADOPT APPROVED WCAP-14565-P-A METHODOLOGY
Reference:
ULNRC-06215 Letter from S.A.Maglio (Ameren Missouri)to U.S.Nuclear Regulatory Commission,"Revision of TS 2.1.1.1 and 5.6.5 to Remove Uncertainties from the DNBR Safety Limit and Adopt Approved WCAP-14565-P-A Methodology,"
dated May 8, 2015[NRC ADAMS Accession Number ML15132A137j In the referenced document above, Ameren Missouri submitted an application for amendment to Renewed Facility License Number NPF-30 for the Callaway Plant.That amendment application proposed changes to Technical Specification (TS)requirements to adopt the NRC approved methodology described in WCAP-14565-P-A Addendum 2-P-A,"Extended Application of ABB-NV Correlation and Modified ABB-NV Correlation WLOP for PWR Low Pressure Applications,"
and revise TS 2.1.1.1 to provide a safety limit for the Departure from Nucleate Boiling Ratio (DNBR)that is aligned with the original intent of approved topical report WCAP-144$3,"Generic Methodology for Expanded Core Operating Limits Report."From the NRC staffs review, a request for additional information (RAI)was identified and issued electronically on October 13, 2015 with a response requested by November 12, 2015.Attachment 1 provides the requested information.
The information provided in Attachment 1 does not affect the licensing evaluations submitted in the referenced amendment application, nor does Attachment 1 alter the conclusions of those licensing evaluations.
Ameren Missouri continues to request approval of this license amendment request prior to reactor criticality during the restart from the upcoming Refuel 21 outage.Reactor criticality is currently scheduled for May 04, 2016.As noted in Ameren Missouri's May 08, 2015 letter, Ameren Missouri PD Box 620: Fulton, I'1O 65251: rnerenIVissouri.corn STARS Alliance ULNRC-06264 November 09, 2015 Page 2 requests that the license amendment be made effective upon NRC issuance, to be implemented within 90 days from the date of issuance.This submittal does not contain new commitments.
If there are any questions, please contact Mr.Tom Elwood at 314-225-1905.
I declare under penalty of perjury that the foregoing is true and correct.Sincerely, Executed on:/10 tf7 4 Scott A.Maglio Manager, Regulatory Affairs TAW Attachments:
1.Response to NRC Request for Additional Information Regarding LDCN 15-0005 ULNRC-06264 November 06, 2015 Page 3 cc: Mr.Marc L.Dapas Regional Administrator U.S.Nuclear Regulatory Commission Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 Senior Resident Inspector Callaway Resident Office U.S.Nuclear Regulatory Commission
$201 NRC Road$teedman, MO 65077 Mr.L.John Klos Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission Mail Stop O$H4 Washington, DC 20555-000 1 ULNRC-06264 November 06, 2015 Page 4 Index and send hardcopy to QA File A160.0761 Hardcopy: Certrec Corporation 6100 Western Place, Suite 1050 fort Worth, IX 76107 (Certrec receives ALL attachments as long as they are non-safeguards and may be publicly disclosed.)
Electronic distribution for the following can be made via Tech Spec ULNRC Distribution:
F.M.Diya D.W.Neterer L.H.Graessle T.E.Herrmann B.L.Cox L.H.Kanuckel S.A.Maglio I.B.Elwood Corporate Communications NSRB Secretary STARS Regulatory Affairs Mr.John O'Neill (Pillsbury Winthrop Shaw Pittman LLP)Missouri Public Service Commission Mr.Robert D.Stout (DNR)Ms.Leanne Tippett-Mosby (DNR)
Enclosure to ULNRC-06264 Attachment 1 Page 1 of 3 ATTACHMENT 1 RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION REGARDING LDCN 15-0005 Enclosure to ULNRC-06264 Attachment 1 Page 2 of 3 REQUEST FOR ADDITIONAL INFORMATION CALLA WAY PLANT, UNIT 1 UNION ELECTRIC CO.LICENSE AMENDMENT APPLICATION TO REVISE IS 2.1.1.1 AND 5.6.5 TO REMOVE UNCERTAINTIES FROM THE DNBR SAFETY LIMIT AND ADOPT APPROVED WCAP-14565-P-A METHODOLOGY The NRC staff requests additional information to complete its review of the license amendment request (LAR)to revise Technical Specification (IS)2.1.1.1 and 5.6.5 to remove uncertainties from the Departure from Nucleate Boiling Ratio (DNBR)safety limit and adopt approved WCAP-14565-P-A methodology.
By letter dated May 08, 2015 (NRC ADAMS Accession No.ML15132A137), Ameren Missouri (the licensee)requested the removal of analytical uncertainties from TS 2.1.1.1 consistent with the intent of WCAP-144$3-A.
From NRC staff review of the provided application, the NRC staff has the following question listed below.Question 1 10 CFR 50.36(c)requires licensees to include safety limits in the TS, defined as limits upon important process variables that are found to be necessary to reasonably protect the integrity of certain of the physical barriers that guard against the uncontrolled release of radioactivity.
The Departure from Nucleate Boiling Ration (DNBR)limit is one such safety limit, since it protects the integrity of the fuel cladding.The proposed change to IS 2.1.1.1 would only specify the 95/95 DNBR limit associated with the WRB-2 correlation.
However, the license amendment request is requesting approval of two additional alternative DNB correlations, each of which has its own unique DNBR limit.Please explain why the DNBR limits associated with the ABB-NV and Westinghouse Low Pressure Departure from Nucleate Boiling correlations are not being included in IS 2.1.1.1.RAI Response The proposed Technical Specification (TS)2.1.1.1 content provided in Reference 1 is consistent with the format in Volume 1 of NUREG-143 1, Revision 4 (Reference 2).The current format for TS 2.1.1.1 in Reference 2 is based on the approved topical report WCAP-14483-A,"Generic Methodology for Expanded Core Operating Limits Report,"(Reference 3).The Safety Evaluation Report (SER)for Reference 3 states that the safety limits, which were originally included in the Westinghouse TS as the Reactor Core Limits figure (Figure 2.1.1-1)to satisfy 1OCFR5O.36, are"intended to provide the relationship between the process variables that are available Enclosure to ULNRC-06264 Attachment 1 Page 3 of 3 to the operator (i.e., T-avg, pressurizer pressure, and thermal power)and the DNB design basis safety limit."With the approval of Reference 3, the Reactor Core Limits figure itself was moved from TS 2.1.1.1 to the COLR, and replaced with the true safety limits (DNBR and fuel melting limits)that are protected by staying within the bounds for the process variables defined by the Reactor Core Limits figure, thereby ensuring that the intent of 1OCFR5O.36 is satisfied.
Since the WRB-2 correlation is the only DNB correlation used to establish the COLR Reactor Core Limits figure for the Callaway plant, only the WRB-2 correlation and the associated 95/95 DNBR limit are specifically listed in TS 2.1.1.1.This is consistent with the format for 15 2.1.1.1 as specified in Reference 2.While the ABB-NV and Westinghouse Low Pressure (WLOP)DNB correlations will be used in the safety analyses for the Callaway plant, these correlations are neither applicable to nor will they be used for the establishment of the COLR Reactor Core Limits figure.It is not appropriate to list any DNB correlations and their associated limits in TS 2.1.1.1 that are not used in the establishment of the COLR Reactor Core Limits figure.
References:
1.Letter from S.A.Maglio (Ameren Missouri)to U.S.Nuclear Regulatory Commission,"Revision of TS 2.1.1.1 and 5.6.5 to Remove Uncertainties from the DNBR Safety Limit and Adopt Approved WCAP-14565-P-A Methodology' dated May 8, 2015[Nuclear Regulatory Commission ADAMS Accession Number ML 1513 2A 137].2.Standard Technical Specifications
-Westinghouse Plants: Volume 1, Specifications, NUREG 1431, Revision 4, April, 2012.3.D.S.Huegel, J.D.Andrachek, and C.E.Morgan,"Generic Methodology for Expanded Core Operating Limits Report,"WCAP-144$3-A, January, 1999.