Letter Sequence Other |
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MONTHYEARULNRC-05521, Request for Extension of Corrective Actions Completion Date for NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.2008-06-24024 June 2008 Request for Extension of Corrective Actions Completion Date for NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. Project stage: Request ML0818503312008-06-27027 June 2008 Email Response from Scott Maglio to Mohan Thadani, Jack Donahew, Leon Whitney Generic Letter - 2004 - 02 Project stage: Other ML0818503552008-06-27027 June 2008 Attachment, Summary of Telephone Conference Regarding Request for Extension of Completion of Corrective Actions for NRC Generic Letter 2004-02 Project stage: Request ML0818406062008-07-0303 July 2008 Approval of Second Extension Request for Corrective Actions GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors. Project stage: Other ML0920101192008-12-18018 December 2008 Email Re Request for Additional Information, Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: RAI ML0920101222008-12-18018 December 2008 Request for Additional Information, Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: RAI ML0920306202009-07-31031 July 2009 Notice of Forthcoming Conference Call with Union Electric Company and Wolf Creek Nuclear Operating Company Re Draft Requests for Additional Information on Generic Letter 2004-02 for Callaway Plant and Wolf Creek Creek Generating Station Project stage: Draft RAI ML0922205722009-08-27027 August 2009 Request for Additional Information Related to Generic Letter 2004-02, Potential Impact of Debris Blockage of Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: RAI ML0924607142009-09-28028 September 2009 Summary of Meeting with Union Electric Co., and Wolf Creek, to Discuss Draft Requests for Additional Information on GL 2004-02 for Callaway, Unit 1, and Wolf Creek Project stage: Draft RAI ML0928003162009-10-16016 October 2009 Notice of Meeting with Union Electric Company and Wolf Creek Nuclear Operating Company to Discuss NRC Requests for Additional Information on Generic Letter 2004-02 Sent 7/31/0209 and 8/27/2009, Respectively Project stage: RAI ML0929300152009-10-20020 October 2009 Revised Notice of Meeting with Union Electric Company and Wolf Creek Nuclear Operating Company to Discuss NRC Requests for Additional Information on Generic Letter 2004-02 Project stage: RAI ML0933801482009-11-20020 November 2009 Licensee Handouts from November 20, 2009, Public Meeting with Union Electric Company and Wolf Creek Nuclear Operating Company to Discuss GL 2004-02 Response Rai'S Project stage: Request ULNRC-05668, Request for Extension of Response Date to NRC Request for Additional Information Re Responses to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at PWRs2009-11-24024 November 2009 Request for Extension of Response Date to NRC Request for Additional Information Re Responses to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at PWRs Project stage: Request ML0933805662009-12-17017 December 2009 Summary of Meeting with Union Electric Company and Wolf Creek Nuclear Operating Company to Discuss NRC Requests for Additional Information on Generic Letter 2004-02 Sent 7/31/2009 and 8/27/2009, Respectively Project stage: RAI ULNRC-05989, Path Forward for Resolution of GSI-1912013-05-16016 May 2013 Path Forward for Resolution of GSI-191 Project stage: Request ML13263A1682013-09-23023 September 2013 Request for Additional Information, Closure of Option 2 to Address In-Vessel Mitigative Measures for Potential In-Vessel Blockage; Related to Generic Safety Issue 191 Project stage: RAI ULNRC-06045, Response to Request for Additional Information Closure of Option 2 to Address In-Vessel Mitigative Measures for Potential In-Vessel Blockage2013-10-31031 October 2013 Response to Request for Additional Information Closure of Option 2 to Address In-Vessel Mitigative Measures for Potential In-Vessel Blockage Project stage: Response to RAI 2009-11-24
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Category:Code Relief or Alternative
MONTHYEARML20225A2922020-08-12012 August 2020 Request to Use a Portion of a Later Edition of the ASME B&PV Code, Section XI ML19079A1482019-04-0101 April 2019 Request for Alternative I4R-05 to Reactor Vessel Nozzle Weld Examination Frequency Requirements (EPID L-2018-LLR-0051 ML18313A0692018-11-26026 November 2018 Request for Relief I4R-01 Related to the Inservice Inspection Program for Class 3 Buried High Density Polyethylene Piping ULNRC-06420, Request 14R-05 for Relief from Requirements of ASME Code Case N-770-2 Regarding Inspection Intervals for Reactor Vessel Nozzle Dissimilar Metal Welds2018-04-0909 April 2018 Request 14R-05 for Relief from Requirements of ASME Code Case N-770-2 Regarding Inspection Intervals for Reactor Vessel Nozzle Dissimilar Metal Welds ML17262A7002017-10-0303 October 2017 Request for Alternative I4R-04 Applicable to the Fourth 10-Year Inspection Program Interval ML17254A1202017-09-25025 September 2017 Request for Alternative No. PR-07 from the Requirements of the ASME Code for the Fourth 10-Year Inservice Testing Interval ML17058A4432017-03-0606 March 2017 Request for Alternative I4R-03 Applicable to the Fourth 10-Year Inservice Inspection Program Interval ML16223A7122016-08-30030 August 2016 Relief Request No. 13R-08 from Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, for Piping Welds, Third 10-Year Inservice Inspection Interval ML16055A4642016-03-17017 March 2016 Relief Requests 13R-09 (Steam Generator Tubesheet Weld), 13R-11 (Pressurizer Welds) from Code Case N-460 and 13R-18 (SG Weld), from Appendix Viii Requirements, Third 10-Year Inservice Inspection Interval (CAC MF6735-MF6737) ML16027A1582016-01-29029 January 2016 Relief Request I4R-02 from Requirements of ASME Code Section XI, Table IWF-2500-1 for 100% Visual Examination of Class 1 Supports, Fourth 10-Year Inservice Inspection Interval ML15064A1252015-05-12012 May 2015 Request for Relief I4R-01 from ASME Code Requirements for Replacement of Class 3 Essential Service Water Buried Piping with High Density Polyethylene Piping, for the Fourth 10-year Inservice Testing Interval ML15035A1482015-02-10010 February 2015 Relief Request 13R-17, Proposed Alternative to ASME Code, Section XI Requirements, Which Extends Reactor Vessel Inservice Inspection Frequency from 10 to 20 Years, Third 10-Year Interval ML14239A0972014-09-0404 September 2014 Request for Relief I3R-15, ASME Code Class 1 Pressure-Retaining Piping/Components Leakage Testing at Full Pressure, Third 10-Year Inservice Inspection Interval ML14234A4512014-09-0404 September 2014 Relief Request I3R-16, Temporary Non-Code Repair of the Train a Component Cooling Water Heat Exchanger to Control ESW Leakage, Third 10-Year Inservice Inspection Interval ML14178A7692014-07-15015 July 2014 Requests for Relief PR-01, PR-02, PR-03, PR-04, and PR-06 (PR-05 Withdrawn), ASME OM Code Cases for Group a and B Pumps for Fourth 10-Year Inservice Testing Interval ML14027A0572014-01-29029 January 2014 Relief Request PR-07, Testing Frequency for Pumps and Valves, Third 10-year Inservice Testing Interval ML13246A3042013-08-30030 August 2013 Verbal Authorization Email, Relief Request PR-07, Testing Frequency for Pumps and Valves, Third 10-year Inservice Testing Interval ML13126A3202013-05-0707 May 2013 Summary of Telephone Conference, Verbal Authorization of Relief Request I3R-14. Proposed Alternative to ASME Code Requirements for Leakage Testing of RPV Head Flange Leakoff Lines, Third 10-Year ISI Interval. ML12258A0452012-09-18018 September 2012 Relief Request VR-01 from Requirements of ASME OM Code, Mandatory Appendix I, One-time Extension for 5-Year Replacement Interval, from 4/11/12 to 6/2013, Main Steam Isolation Valve Actuator Rupture Disks ML1211502472012-05-0303 May 2012 Memo to File, Verbal Authorization, Relief Request VR-01 from Requirements of ASME OM Code Mandatory Appendix I, One-time Extension Replacement of Main Steam Isolation Valve Actuator Rupture Disks ML1201907482012-02-16016 February 2012 Relief Request 13R-13, Alternative to ASME Code Section XI Requirements for Performance of Second Successive Exam of C Cold Leg Safe-End to Elbow Weld, Third 10-Year Inservice Inspection ML0831002882008-11-0707 November 2008 Relief Request 13R-10 Approved on October 31, 2008, for Third 10-Year Inservice Inspection Interval for Use of Polyethylene Pipe in Lieu of Carbon Steel Pipe in Buried Essential Service Water Piping System ML0818406062008-07-0303 July 2008 Approval of Second Extension Request for Corrective Actions GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors. ML0731114422007-12-10010 December 2007 Correction to Authorization of Relief Request ISI-39 for the Second 10-Year Inservice Inspection Interval ML0729803972007-10-30030 October 2007 Relief Request ISI-38, Reactor Pressure Vessel Inlet Safe-End to-Elbow Welds Proposed Alternative Examination for Second 10-Year Inservice Inspection Interval ML0724000922007-09-17017 September 2007 Issuance of Relief Requests (Rrs) ISI-36, ISI-37, and ISI-38 for Second Year Inservice Inspection (ISI) Interval ML0725504882007-08-30030 August 2007 10 CFR 50.55a Request: Proposed Alternative to ASME Section Xi Requirements for Replacement of Class 3 Buried Piping ML0715203292007-07-10010 July 2007 Request for Alternatives for Application of Structural Weld Overlays to Pressurizer Dissimilar Metal Nozzle Welds for Third 10-Year Inservice Inspection Program Interval ML0705803332007-03-15015 March 2007 Authorization of Relief Request No. ISI-33 for Second 10-Year and Third 10-Year ISI Interval ML0635203182007-01-18018 January 2007 Request for Relief No. ISI-35 for Second 10-year Inservice Inspection Interval ML0700303362007-01-18018 January 2007 Relief Request ISI-41 for the Second 10-year Inservice Inspection Interval ML0630604782006-12-0707 December 2006 Relief Request 13R-04 for the Third 10-Year Interval Inservice Inspection ML0629302822006-11-17017 November 2006 Relief Requests I3R-05 and I3R-06 for the Third Inservice Inspection Interval ULNRC-05183, Requests for Relief from ASME Section XI Code Inservice Examination Requirements2006-10-25025 October 2006 Requests for Relief from ASME Section XI Code Inservice Examination Requirements ML0614301312006-06-15015 June 2006 Relief, Third 10-Year Interval Inservice Inspection Program Relief Request I3R-02 ML0520802152005-08-18018 August 2005 Relief, Use a Subsequent Edition of ASME Code Examinations for the Third Inservice Inspection Interval ML0515302072005-06-22022 June 2005 6/22/05 Callaway, Unit 1 - Relief Requests ISI-24,ISI-25 and ISI-26 of the Second 10-Year Inservice Inspection (ISI) Interval (Tacs. MC4435 and MC4436) ML0507601292005-05-19019 May 2005 Relief, Request for Relief from Certain ASME Code Examinations for the Second Inservice Inspection Interval ULNRC-05092, Revision to Approve Request for Relief from ASME Section III Requirements Regarding Non-destructive Examination of Welds Performed Under Site Repair/Replacement Program2004-11-18018 November 2004 Revision to Approve Request for Relief from ASME Section III Requirements Regarding Non-destructive Examination of Welds Performed Under Site Repair/Replacement Program ULNRC-05049, Union Electric Company Callaway Plant Request for Relief from ASME Section XI Code Inservice Examination Requirements2004-09-0303 September 2004 Union Electric Company Callaway Plant Request for Relief from ASME Section XI Code Inservice Examination Requirements ML0414100712004-05-19019 May 2004 Relief, ASME Code Requirements on the Use of Weld Overlay Reinforcement to Restore Wall Thickness of ASME Class 2 Carbon Steel Main Feedwater Piping. ML0414100352004-05-19019 May 2004 Relief, Second Ten-Year Interval Inservice Inspection Program Relief Request to Use an Alternative Examination Method ULNRC-04993, Revision of Request for Relief from ASME Section XI Requirements in Order to Temporarily Restore Wall Thickness of ASME Class 2 Carbon Steel Main Feedwater Piping by Weld Overlay Reinforcement2004-05-0707 May 2004 Revision of Request for Relief from ASME Section XI Requirements in Order to Temporarily Restore Wall Thickness of ASME Class 2 Carbon Steel Main Feedwater Piping by Weld Overlay Reinforcement ML0409806642004-04-0707 April 2004 4/7/04 Callaway Plant - Request for Relief from ASME Code Requirements on the Use of Weld Overlay Reinforcement to Restore Wall Thickness of ASME Class 2 Carbon Steel Main Feedwater Piping ULNRC-04879, Requests for Relief Regarding Implementation of ASME Section XI Appendix VII Requirements2003-08-14014 August 2003 Requests for Relief Regarding Implementation of ASME Section XI Appendix VII Requirements ML0318305352003-07-0101 July 2003 Second Ten-Year Interval Inservice Inspection Program Relief Request to Use an Alternative Examination Method (Tac. MB6534) ML0134602652002-01-30030 January 2002 Relief, Application of Risk-Informed Inservice Inspection Program for the American Society of Mechanical Engineers Boilers and Pressure Vessel Code Class 1 and 2 TAC No MB1205) 2020-08-12
[Table view] 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
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July 3, 2008 Mr. Charles D. Naslund Senior Vice President and Chief Nuclear Officer Union Electric Company Post Office Box 620 Fulton, MO 65251
SUBJECT:
CALLAWAY PLANT, UNIT 1 - APPROVAL OF EXTENSION REQUEST FOR CORRECTIVE ACTIONS RE: GENERIC LETTER 2004-02, "POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY RECIRCULATION DURING DESIGN BASIS ACCIDENTS AT PRESSURIZED-WATER REACTORS," (TAC NO. MC4571)
Dear Mr. Naslund:
By letter dated June 24, 2008, Union Electric Company (UEC), the licensee for Callaway Plant, Unit 1 (Callaway), requested an extension to the Nuclear Regulatory Commission (NRC)
Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, corrective action due date for Callaway . The stated intent of this extension was to allow UEC additional time to review and act on delayed vendor documentation of emergency core coolant system (ECCS) sump strainer testing; to complete evaluation of upstream effects, downstream effects, debris generation, debris transport, and chemical effects; and to complete certain GL 2004-02 corrective actions.
Identified corrective actions are: (1) modifications to the new ECCS sump strainers to regain net positive suction head margin necessitated by a manufacturing error resulting from a vendor error in the clean-strainer head-loss calculation and (2) potential modifications (if indicated by the final downstream effects evaluations) to safety injection system components and containment spray system pump cyclone separators. UEC plans to implement these additional modifications, if required, during the fall 2008 refueling outage. Therefore, UEC requests an extension of the due date to December 15, 2008, for completion of the specified activities.
In accordance with its reviews for granting extensions to the due date for completion of GL 2004-02 corrective actions, the NRC staff has evaluated the licensees request, based on the criteria stated in SECY-06-0078.
Based on the licensee having satisfactorily addressed the NRC GL 2004-02 due date extension criteria, the NRC staff finds it acceptable to extend the Callaway completion date for GL 2004-02 corrective actions associated with strainer performance testing, final analysis, and related licensing activities from June 30, 2008, to December 15, 2008.
C. Naslund The NRC staffs evaluation of the extension request is enclosed. If you have any questions, please contact me at (301) 415-1476 or email mohan.thadani@nrc.gov.
Sincerely,
/RA/
Mohan C. Thadani, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-483
Enclosure:
As stated cc w/encl: See next page
ML081840606 *memo dated OFFICE NRR/LPL4/PM NRR/LPL4/LA DSS/SSIB/BC NRR/LPL4/BC NRR/LPL4/PM NAME MThadani JBurkhardt MScott (*) THiltz, MCT for MThadani DATE 07/03/08 7/3/08 6/27/08 07/03/08 07/03/08 Callaway Plant, Unit 1 (7/2/2008) cc:
John ONeill, Esq. Mr. Rick A. Muench, President and CEO Pillsbury Winthrop Shaw Pittman LLP Wolf Creek Nuclear Operating Corporation 2300 N. Street, NW P.O. Box 411 Washington, DC 20037 Burlington, KA 66839 Mr. Tom Elwood, Supervising Engineer Certrec Corporation Regulatory Affairs and Licensing 4200 S. Hulen, Suite 422 AmerenUE Fort Worth, TX 76109 P.O. Box 620 Fulton, MO 65251 Technical Services Branch Chief FEMA Region VII Mr. Les H. Kanuckel, Manager 2323 Grand Blvd., Suite 900 Quality Assurance Kansas City, MO 64108-2670 AmerenUE P.O. Box 620 Kathleen Logan Smith, Executive Director and Fulton, MO 65251 Kay Drey, Representative, Board of Directors Missouri Coalition for the Environment Mr. Luke Graessle, Manager 6267 Delmar Blvd., Suite 2E Regulatory Affairs St. Louis, City, MO 63130 AmerenUE P.O. Box 620 Mr. Lee Fritz, Presiding Commissioner Fulton, MO 65251 Callaway County Courthouse 10 E. Fifth Street Mr. Scott Maglio Fulton, MO 65251 Assistant Manager, Regulatory Affairs AmerenUE Mr. Keith G. Henke, Planner III P.O. Box 620 Division of Community and Public Health Fulton, MO 65251 Office of Emergency Coordination Missouri Department of Health and U.S. Nuclear Regulatory Commission Senior Services Resident Inspector Office 930 Wildwood Drive 8201 NRC Road P.O. Box 570 Steedman, MO 65077-1302 Jefferson City, MO 65102 Missouri Public Service Commission Mr. Scott Clardy, Director Governor Office Building Section for Environmental Public Health 200 Madison Street Missouri Department of Health and P.O. Box 360 Senior Services Jefferson City, MO 65102-0360 930 Wildwood Drive P.O. Box 570 Regional Administrator, Region IV Jefferson City, MO 65102 U.S. Nuclear Regulatory Commission 612 E. Lamar Blvd., Suite 400 Director, Missouri State Emergency Arlington, TX 76011-4125 Management Agency P.O. Box 116 Mr. H. Floyd Gilzow Jefferson City, MO 65102-0116 Deputy Director for Policy Department of Natural Resources P.O. Box 176 Jefferson City, MO 65102-0176
EVALUATION OF EXTENSION REQUEST RELATED TO GENERIC LETTER 2004-02 BY OFFICE OF NUCLEAR REACTOR REGULATION FACILITY OPERATING LICENSES NOS. NPF-76 AND NPF-80 CALLAWAY PLANT, UNIT 1 DOCKET NO. 50-483 By letter dated June 24, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML081840061), Union Electric Company (UEC), the licensee for Callaway Plant, Unit 1 (Callaway), requested an extension to the Nuclear Regulatory Commission (NRC) Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, corrective actions due date for Callaway. The stated intent of the requested extension was to allow UEC additional time to review and act on delayed vendor documentation of emergency core coolant system (ECCS) sump strainer testing; to complete evaluation of upstream effects, downstream effects, debris generation, debris transport, and chemical effects; and to complete certain GL 2004-02 corrective actions. Identified corrective actions are: (1) modifications to the new ECCS sump strainers to regain net positive suction head (NPSH) margin necessitated by a manufacturing error resulting from a vendor error in the clean-strainer head-loss calculation, and (2) potential modifications (if indicated by the final downstream effects evaluations) to safety injection system components and containment spray system (CSS) pump cyclone separators.
UEC plans to implement these additional modifications, if required, during the fall 2008 refueling outage. Therefore, UEC requested an extension from June 30, 2008, to December 15, 2008, for completion of the specified activities.
By letters dated December 10 and December 20, 2007, UEC submitted a request for extension of the Callaway sump clogging corrective actions due date of December 31, 2007, stated in GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized-Water Reactors. The licensee stated that additional time was needed to complete plant-specific testing and related activities, including completion of licensee verification of design inputs, calculations, and evaluations. The NRC staff reviewed the information provided by letter dated December 28, 2007 (ADAMS Accession No. ML073610243), and determined that it was acceptable to extend the due date for completion of corrective actions at Callaway for GL 2004-02 to June 30, 2008.
In its June 24, 2008, letter, UEC stated that it had successfully completed strainer performance testing that showed adequate NPSH margin would be maintained, that increase in head-loss due to chemical effects was minimal, and the new strainer design was resistant to blockage from transported debris. Strainer bypass testing was also performed. Therefore, UEC concluded that corrective actions are nearly complete.
ENCLOSURE
The licensee noted, however, that additional time is needed to perform the following:
- Receipt of the final strainer vendor test report by mid-August 2008.
- Assessment of impact of the test results on completed strainer calculations, debris bypass impacts on downstream effects evaluations, and potential impacts on other GL 2004-02 corrective actions, along with completion of activities needed to comply with 10 CFR 50 Appendix B, by December 15, 2008.
The NRC has based its reviews for granting extensions to the due date for completion of GL 2004-02 corrective actions on the criteria stated in SECY-06-0078. Specifically, an extension may be granted if:
- the licensee has a plant-specific technical/experimental plan with milestones and schedule to address outstanding technical issues with enough margin to account for uncertainties, and
- the licensee identifies mitigation measures to be put in place prior to December 31, 2007, and adequately describes how these mitigation measures will minimize the risk of degraded ECCS and CSS functions during the extension period.
SECY-06-0078 also states that for proposed extensions beyond several months, a licensees request will more likely be accepted if the proposed mitigation measures include temporary physical improvements to the ECCS sump or materials inside containment to better ensure a high level of ECCS sump performance.
With regard to the first extension criterion, UEC has provided a plant-specific technical/
experimental plan, with milestones and schedules, to complete the GL 2004-02 corrective actions, as discussed above.
With regard to the second extension criterion, the licensee stated in its letter dated June 24, 2008, that the following mitigating measures are in place:
- Plant hardware modifications, developed in response to issues identified in GL 2004-02, are installed in Callaway and are actively supporting compliance with the regulatory requirements for long-term cooling following a design basis loss-of-coolant accident. Hardware modifications include replacement of ECCS sump screens with new strainers with a surface area of 6623 square feet, and installation of debris barriers in two of the four loop entrances. These modifications are intended to maximize strainer capability while minimizing the debris load to the extent practical.
- Plant administrative procedures and processes, such as programmatic changes to controls for plant design changes and containment material controls have been implemented to support the hardware modifications.
With regard to the third extension criterion, the large new sump strainers satisfy this criterion.
In an e-mail dated June 27, 2008 (ADAMS Accession No. ML081850324), UEC stated that there is a significant NPSH margin at Callaway, as supported by successful chemical effects and debris by-pass testing conducted in January 2008. In its June 27, 2008, e-mail, UEC explained that the modification to be performed during the Callaway fall 2008 refueling outage will replace the existing strainer support with one strainer having the correct hole size in order to increase NPSH margin to desired levels. UEC also stated that the current configuration ensures ECCS operability with respect to the strainer issue addressed by GL 2004-02 notwithstanding the modification planned for the fall 1008 refueling outage.
In summary, the licensee has stated that it believes it has nearly completed corrective actions for GL 2004-02 and that it has demonstrated adequate NPSH through strainer testing. Given this information, and the mitigation measures and plant improvements already in place, the additional time requested in the June 24, 2008, letter to complete remaining evaluations, documentation, and modifications is considered to be of low safety concern.
Based on the licensee having satisfactorily addressed the NRC GL 2004-02 due date extension criteria, as discussed above, the NRC staff finds it acceptable to extend the Callaway completion date for GL 2004-02 corrective actions associated with strainer performance testing, final analysis and related licensing activities, as described in this enclosure, from June 30, 2008, to December 15, 2008.
Principal Contributors: J. Golla E. Geiger Date: July 3, 2008