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MONTHYEARML1109503072011-03-25025 March 2011 Request to Utilize an Alternative to the Requirements of 10 CFR 50.55a(g) for the Repair of Control Rod Drive Housing Penetrations for the Remainder of the License Renewal Period of Extended Operation Project stage: Other ML1109502922011-04-0505 April 2011 Acceptance Review Determination Relief Request for Repair of CRD Housing Penetrations Project stage: Acceptance Review ML1116400612011-06-22022 June 2011 Request for Withholding Information from Public Disclosure - Nine Mile Point, Unit No. 1 Request to Utilize Alternative for Repair of Control Rod Drive Housing Penetrations Dated March 4 and 25, 2011 - Areva Proprietary Documents Project stage: Withholding Request Acceptance ML1122200932011-08-11011 August 2011 Request for Additional Information Request for Alternative Relief Request No. 1ISI-004 Project stage: RAI ML11279A0372011-09-29029 September 2011 Request to Utilize an Alternative to the Requirements of 10 CFR 50.55a(g) for the Repair of Control Rod Drive Housing Penetrations - Response to NRC Request for Additional Information Project stage: Response to RAI ML12048A8362012-02-23023 February 2012 Request for Additional Information Relief Request No. 1ISI-004 Project stage: RAI ML12102A1122012-04-0909 April 2012 Request to Utilize an Alternative to the Requirements of 10 CFR 50.55a(g) for the Repair of Control Rod Drive Housing Penetrations - Response to NRC Follow-up Request for Additional Information Project stage: Request ML12152A1732012-05-22022 May 2012 Request to Utilize an Alternative to the Requirements of 10 CFR 50.55a(g) for the Repair of Control Rod Drive Housing Penetrations - Revised Affidavits Justifying Withholding Proprietary Information Project stage: Other ML12160A3492012-06-0707 June 2012 Request to Utilize an Alternative to the Requirements of 10 CFR 50.55a(g) for the Repair of Control Rod Drive Housing Penetrations - Withdrawal of the Portion of the Request Regarding Rotary Peening Project stage: Withdrawal ML12124A2322012-06-12012 June 2012 ME5789-Proprietary Information Determination Letter, Submissions Dated March 4, 25, 2011, and April 9, 2012 Project stage: Other ML12250A8062012-09-13013 September 2012 Request for Additional Information (RAI) Request No. 1lSl-004, Request to Utilize an Alternative for the Repair of Control Rod Drive Housing Penetrations Project stage: RAI ML12312A2552012-10-31031 October 2012 Request to Utilize an Alternative to the Requirements of 10 CFR 50.55a(g) for the Repair of Control Rod Drive Housing Penetrations - Response to NRC Request for Additional Information Project stage: Response to RAI ML12312A2562012-10-31031 October 2012 Calculation 32-9157438-000, NMP-1 LAS Scc/Sicc Evaluation. Project stage: Other ML12313A0912012-11-15015 November 2012 Request for Withholding Information from Public Disclosure License Response Dated October 31, 2012 Project stage: Withholding Request Acceptance ML13058A0762013-03-0404 March 2013 Draft Safety Evaluation for Nine Mile Point Nuclear Station, Unit No. 1 Relief from the Requirements of the ASME Code, Section XI, Request No. 1ISI-004, Revision 1, Repair of Control Rod Drive Housing Penetrations Project stage: Draft Approval ML13084A2442013-03-14014 March 2013 Response to Request for Review of Draft NRC Safety Evaluation, Relief from Requirements of ASME Code, Section XI, Request No. 1ISI-004, Revision 1, Repair of Control Rod Drive Housing Penetrations Project stage: Draft Request ML13052A3732013-03-15015 March 2013 ME5789-Authorization of Relief Request 1ISI-004, Revision 1 (NMP1 Relief Request) Project stage: Acceptance Review 2012-02-23
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Category:Letter
MONTHYEARNMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024 Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations ML23354A0012024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023 Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 NMP1L3564, Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements ML23291A4642023-12-0707 December 2023 Issuance of Amendment No. 251 Regarding the Adoption of Title 10 the Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of SSC for Nuclear Power Plants ML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b NMP1L3563, Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-12-0404 December 2023 Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) IR 05000220/20234022023-11-28028 November 2023 Security Baseline Inspection Report 05000220/2023402 and 05000410/2023402 NMP1L3557, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000220/20234202023-11-0101 November 2023 Security Baseline Inspection Report 05000220/2023420 and 05000410/2023420 ML23305A0052023-11-0101 November 2023 Operator Licensing Examination Approval IR 05000220/20230032023-10-25025 October 2023 Integrated Inspection Report 05000220/2023003 and 05000410/2023003 IR 05000220/20235012023-10-17017 October 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000220/2023501 and 05000410/2023501 IR 05000220/20230112023-10-16016 October 2023 Comprehensive Engineering Team Inspection Report 05000220/2023011 and 05000410/2023011 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans NMP1L3554, Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases2023-10-0606 October 2023 Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases C IR 05000220/20233032023-09-20020 September 2023 Retake Operator Licensing Examination Report 05000220/2023303 ML23250A0822023-09-19019 September 2023 Regulatory Audit Summary Regarding LARs to Adopt TSTF-505, Rev. 2, and 10 CFR 50.69 ML23257A1732023-09-14014 September 2023 Requalification Program Inspection IR 05000220/20230052023-08-31031 August 2023 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2023005 and 05000410/2023005) RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs NMP2L2851, Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations2023-08-25025 August 2023 Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration NMP1L3534, License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2023-08-18018 August 2023 License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation ML23220A0262023-08-0808 August 2023 Licensed Operator Positive Fitness-for-Duty Test IR 05000220/20234012023-08-0808 August 2023 Cyber Security Inspection Report 05000220/2023401 and 05000410/2023401 (Cover Letter Only) NMP1L3545, Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .2023-08-0404 August 2023 Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems . RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor IR 05000220/20230022023-08-0101 August 2023 Integrated Inspection Report 05000220/2023002 and 05000410/2023002 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 NMP1L3544, Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations2023-07-14014 July 2023 Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations ML23186A1642023-07-0606 July 2023 Operator Licensing Retake Examination Approval NMP2L2846, Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications2023-07-0505 July 2023 Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications ML23192A0622023-06-30030 June 2023 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance, Report No. 10CFR21-0136, Rev. 0 IR 05000220/20230102023-06-29029 June 2023 Biennial Problem Identification and Resolution Inspection Report 05000220/2023010 and 05000410/2023010 ML23131A4242023-06-23023 June 2023 Issuance of Amendment No. 249 Regarding the Revision to Technical Specification 3.3.1 to Adopt Technical Specifications Task Force Traveler TSTF-568 RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3539, Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-06-0909 June 2023 Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling IR 05000410/20233022023-05-15015 May 2023 Initial Operator Licensing Examination Report 05000410/2023302 2024-02-01
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23264A7992023-09-21021 September 2023 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC Fleet Request License Amendment Request to Adopt TSTF-580, Revision 1 ML23205A2432023-07-19019 July 2023 NRC Staff Follow-up Question on Audit Question 18 TSTF-505 and 50.69 Regulatory Audit (E-mail Dated 7/19/2023) (EPIDs L-2022-LLA-0185 and L-2022-LLA-0186) ML23087A2912023-03-28028 March 2023 Request for Additional Information (3/28/2023 E-mail) - Proposed Emergent I5R-11 Alternative Associated with a Weld Overlay on RPV Recirculation Nozzle N2E DM Weld ML23061A0522023-03-0202 March 2023 Request for Additional Information (3/2/2023 E-mail) - Proposed Alternative Associated with a Weld Overlay Repair to the Torus ML23012A2002023-01-13013 January 2023 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000220/2023401 and 05000410/2023401 ML22207A2162022-07-26026 July 2022 Information Request to Support Triennial Baseline Design-Basis Capability of Power-Operated Valves Inspection; Inspection Report 05000220/2022010 and 05000410/2022010 ML22194A9412022-07-13013 July 2022 Request for Additional Information Relief Request CS-PR-02 (7/13/2022 e-mail) ML22041B5362022-02-10010 February 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541 ML22020A0642022-01-13013 January 2022 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles ML21320A3472021-11-16016 November 2021 Request for Additional Information LAR to Revise TSs to Adopt TSTF-582, Revision 0 ML21306A3312021-11-0202 November 2021 Request for Additional Information Alternative Request GV-RR-10 (11/2/2021 e-mail) ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21144A2132021-05-24024 May 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21117A0342021-05-0505 May 2021 Request for Additional Information Regarding Proposed Alternative to Use ASME Code Case N-893 ML21125A1282021-05-0404 May 2021 OPC Document Request - Feb 2021 ML21110A5112021-04-20020 April 2021 Request for Additional Information Review of License Amendment Request to Revise Technical Specifications to Adopt TSTF-582 ML21088A2682021-03-30030 March 2021 Notification of Conduct of a Fire Protection Team Inspection ML21062A0652021-03-0101 March 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting ML21049A2572021-02-18018 February 2021 Request for Additional Information Byron/Dresden Proposed Changes to Site Emergency Plans to Support Post-Shutdown and Permanently Defueled Conditions (EPID-2020-LLA-0240 & EPID-2020-LLA-0237) ML20365A0092020-12-30030 December 2020 Request for Additional Information Concerning Review of License Amendment Request and Relief Request to Change Excess Flow Check Valve Testing Frequency (EPIDs L-2020-LLA-0188 and L-2020-LLR-0114) ML20358A2602020-12-28028 December 2020 Changes to Draft Request for Additional Information Regarding License Amendment Request and Relief Request to Change Excess Flow Check Valve Testing Frequency ML20272A2802020-09-28028 September 2020 Withdrawal and Replacement of Request for Additional Information to Support Review of License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times ML20248H5192020-09-28028 September 2020 Changes to Draft Request for Additional Information Regarding Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times ML20246G6362020-09-0202 September 2020 Request for Additonal Information to Support Review of License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times NMP2L2739, Request for Additional Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 22020-08-28028 August 2020 Request for Additional Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 ML20239A7982020-08-25025 August 2020 NRR E-mail Capture - Exelon Generation Company, LLC - Fleet License Amendment Request to Adopt TSTF-568, Revision 2 ML20212L8702020-07-30030 July 2020 Request for Additonal Information Review of License Amendment Requests Regarding Riskinformed Categorization and Treatment of Structures, Systems and Components (L-2019-LLA-0290) ML20213A9352020-07-30030 July 2020 Request for Additional Information Review of License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times ML20153A7042020-06-0101 June 2020 NRR E-mail Capture - Preliminary RAI for Fleet Request to Use Alternative OMN-26 ML20135H1972020-05-14014 May 2020 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Request to Extend Safety Relief Valve Test Interval ML20045E3582020-02-14014 February 2020 Draft Request for Additional Information Regarding License Amendment Request to Increase Allowable MSIV Leakage Rates ML19296A1862019-10-23023 October 2019 Request for Additional Information Regarding License Amendment Request to Increase Allowable MSIV Leakage Rates (L-2019-LLA-0115) ML19275H1362019-10-0202 October 2019 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Request to Use ASME Code Case N-879 ML19179A0612019-07-19019 July 2019 Three Mile Point 1 - Supplemental Information Needed to Proposed Alternative to Use ASME Code Case N-879 ML19151A8132019-05-31031 May 2019 Licensed Operator Positive Fitness-For-Duty Test ML19025A1572019-01-25025 January 2019 Request for Additional Information Regarding Primary Containment Oxygen Concentration License Amendment Request ML19025A1202019-01-24024 January 2019 NRR E-mail Capture - Calvert Cliffs, Fitzpatrick, and Nine Mile Point - Request for Additional Information Regarding License Amendment Request to Revise Emergency Response Organization Staffing ML18341A2212018-12-0707 December 2018 Request for Additional Information Regarding Emergency Tech Spec Change Re HPCS Completion Time (EPID -L-2018-LLA-0491) ML18228A6932018-08-15015 August 2018 Request for Additional Information Regarding Reactor Pressure Vessel Water Inventory Control License Amendment Request (L-2017-LLA-0426) ML18205A3922018-07-24024 July 2018 Request for Additional Information Regarding Reactor Pressure Vessel Water Inventory Control License Amendment Request (L-2017-LLA-0426) ML18184A2882018-07-0303 July 2018 Request for Additional Information Regarding Removal of Boraflex Credit from Spent Fuel Pool License Amendment Request(L-2018-LLA-0039) ML18102A2372018-04-12012 April 2018 NRR E-mail Capture - Calvert Cliffs, Ginna, and Nine Mile Point - Request for Additional Information Regarding License Amendment Request to Revise Emergency Action Level Schemes (EPID-L-2017-LLA-0237) ML17331B1342017-12-12012 December 2017 2, and R.E. Ginna Nuclear Power Plant - Request for Additional Information - Regarding ML17285B1962017-10-27027 October 2017 Request for Additional Information Regarding Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools. ML17272A0112017-10-10010 October 2017 Request for Additional Information Regarding License Amendment Concerning Reactor Pressure Vessel Water Inventory Control ML17234A3592017-08-30030 August 2017 Request for Additional Information Regarding Relief Request NMP-RR-001 to Utilize Code Case N-702 ML17241A2752017-08-29029 August 2017 Request for Additional Information Response MSA (MF7946,7) and FE (MG0087,8) E-mail Attachment ML17240A3102017-08-15015 August 2017 NRR E-mail Capture - Nine Mile Point MSA and FE RAI ML17172A0842017-06-27027 June 2017 Request for Additional Information Regarding Relief Request to Utilize ASME Code Case N-702 ML17065A1622017-03-14014 March 2017 Request for Additional Information Regarding Proposed Alternative to Perform Pressure Isolation Valve Leakage Testing at Frequencies Consistent with 10 CFR Part 50, Appendix J 2023-09-21
[Table view] |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 September 13, 2012 Mr. Ken Langdon Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNIT NO.1, REQUEST FOR ADDITIONAL INFORMATION (RAI) RE: REQUEST NO. 1ISI-004, REQUEST TO UTILIZE AN ALTERNATIVE FOR THE REPAIR OF CONTROL ROD DRIVE HOUSING PENETRATIONS (TAC NO. ME5789)
Dear Mr. Langdon:
By letter dated March 4, 2011 (Agencywide Documents Access and Management System (ADAMS) Package Accession No. ML110680293), Nine Mile Point Nuclear Station, LLC submitted the "Request to Utilize an Alternative to the Requirements of 10 CFR 50.55a(g) for the Repair of Control Rod Drive Housing Penetrations for the Remainder of the License Renewal Period of Extended Operation." Additionally, the licensee has responded to the Nuclear Regulatory Commission (NRC) staff's request for additional information (RAI) by letters dated March 25, 2011, (ADAMS Package Accession No. ML110950302), September 29, 2011, (ADAMS Accession No. ML11279A037), April 9, (ADAMS Package Accession No. ML121020213), and June 7,2012, (ADAMS Accession No. ML12160A349).
The NRC staff has reviewed the information provided in the letters from the licensee and has determined that additional information is needed to complete its review. Enclosed is the NRC staff's RAI.
The RAI was discussed with your staff on September 6, 2012, to clarify the draft RAls sent to the licensee earlier and the licensee committed to provide the responses to these RAls by COB October 31,2012.
Please contact me at (301) 415-3308, if you have any questions.
Sincerely,
~~~~'""r
~~
Bhalchandra Vaidya, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-220
Enclosure:
As stated cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION NMPNS RELIEF REQUEST 11SI-004 REVISION 1 INSERVICE INSPECTION PROGRAM REQUEST FOR ALTERNATIVE FOR NINE MILE POINT NUCLEAR STATION UNIT 1 DOCKET NUMBER 50-220 (TAC NO. ME5789)
RAJA Table 1 to Attachment 2 of the submittal dated March 25, 2011 (Ref. 1) notes that abrasive waterjet machining is specified for the severing, weld prep forming and final machining, under the repair methodology approved in [Boiling Water Reactor Vessel and Internals Project Topical Report] BWRVIP-58-A: BWR Vessel and Internals Project, [Control Rod Drive] CRD Internal Access Weld Repair (Ref. 2). A variation to allow conventional machining, followed by rotary peening, was requested for the Nine Mile Point, Unit 1 (NMP1) specific repair methodology. By letter dated June 7, 2012, (Ref. 3), the request to perform rotary peening was withdrawn. The variation to use conventional machining versus abrasive waterjet machining was linked to the use of peening. Therefore, the staff requests the licensee to clarify which machining technique is planned. If conventional machining is planned, provide a revised justification for the variation considering that peening will no longer be performed.
RAIB For Proposed Alternative 2, 48-hour hold, the Basis for Relief in Section 2B of 11SI-004 (Ref. 4) states, "EPRI [Electric Power Research Institute] Report 1013558, Repair and Replacement Applications Center: Temperbead Welding Applications 48-Hour Hold Requirements for Ambient Temperature Temperbead Welding, provides justification for starting the 48-hour hold after completion of the third temperbead weld layer rather than waiting for the weld overlay to cool to ambient temperature." The EPRI report provides information to address issues associated with allowance of a 48-hour hold following completion of the third temperbead weld layer as applied to low alloy steel SA-508, Class 2 reactor vessel (RV) nozzle materials as an alternative to the provisions in Code Case N-638 and N-740. The reactor vessel bottom head and CRD housing penetration materials are not SA-508, Class 2. Provide a technical basis for the applicability of this report to the materials listed in Table 1 of the March 25, 2011 submittal (Ref. 1). In addition, whereas the EPRI report discusses American Society of Mechanical Engineers Boiler & Pressure Vessel Code (ASME Code) Code Case N-638 and N-740, the applicable ASME Code requirement for the CRD bottom head penetrations is Code Case N-606-1. Provide a technical basis for the applicability of this report to Code Case N-606-1.
RAIC Section 1A of 11SI-004 (Ref. 4) states that "the nondestructive examination (NDE) volumes and areas will be similar to those described in BWRVIP-58-A, as discussed in Attachment 2," and references Figure 2 [of 1ISI-004] which depicts the areas for PT and UT examinations of the modified CRD penetration. BWRVIP-58-A, consistent with Figure IWB-2500-18 of the ASME Code,Section XI, requires the surface examination area to extend /'2 inch beyond the upper and lower weld toe. However, Section 1A and the figure do not provide any dimensions for the examination area/volume for the PT or UT examinations.
Enclosure
- 2 As such, the staff requests the following information:
- 1. Clarify the ASME Code required exam volumes/surfaces for ultrasonic testing (UT) and penetrant testing (PT) that apply for the CRD housing penetration welds at NMP1 by providing a description of the examination volumes and areas that includes dimensions.
The description should indicate the dimension from the weld toe to the end of the examination area/volume.
- 2. Revise Figure 2 accordingly with the dimensions of these areas/surfaces clearly marked and to ensure that the figure depicts both the required exam and the coverage that is achievable.
- 3. In addition, please clarify the weld extent as shown by Figure 2; it appears that there is a thin layer of weld material that extends down from the primary weld area.
RAID The basis for relief in Section 1B of 11SI-004 (Ref. 4) states that the UT exam is "qualified to detect flaws in the new weld and base metal interface beneath the new weld." The basis for relief for Proposed Alternatives 1 and 3 in Section 1A and 3A of 11SI-004 (Ref. 3), describe the nondestructive examination (NDE) volumes and areas, and the NDE technique, for the proposed UT technique for the NMP1 repair, as similar to those specified in BWRVIP-58-A.
However, the staff notes that the UT technique described in BWRVIP-58-A was only demonstrated on two stub tube mock-ups with implanted flaws. and of the four fatigue cracks in these mock-ups, three were documented as "not detected" by the UT technique. It is therefore not clear how the results presented in Table 4-3 on page 4.12 of BWRVIP-58-A show that "satisfactory performance for detection of the flaws was accomplished."
Therefore, the staff requests the licensee to clarify and provide details on how the UT technique described in 11SI-004 has been qualified.
RAIE Request No. 11SI-004 (Ref. 4) states that UT exam acceptance criteria are in accordance with f\lB-5331 as modified by BWRVIP-58-A. Please explicitly explain how the acceptance criteria are modified by BWRVIP-58-A. Provide justification for any modifications to the acceptance criteria.
RAJ F Provide details of how it was determined that the UT is able to detect and size the triple point anomaly such that, should a rejectable anomaly be present (>0.1 "), the UT would be able to detect and size it appropriately.
-3 RAIG ASME Code,Section III acceptance criteria require discrimination of flaw type such that cracks, lack of fusion (LOF), and incomplete penetration (ICP) > 20% distance amplitude curve (DAC) are rejected. How is flaw type determined by the UT procedure such that this criterion may be applied? .
RAIH At least two vendors in the United States have performance demonstration initiative (POI) qualified UT techniques for inspecting upper head control rod drive mechanism (CRDM) nozzles in pressurized water reactors (PWRs). As noted in Table 1 on page 7 of 13 of Attachment 2 to the March 25, 2011 submittal (Ref. 1), "The CRDM nozzle penetration repair configuration is very similar to the dissociated configuration for NMP1; therefore the same beam angles will be used." In addition to using the same beam angles, will the personnel, procedures, and equipment used for the qualified PWR upper head exams be used for NMP1 CRD housings repairs?
RAil As noted in Table 1 on page 8 of 13 of Attachment 2 to the March 25, 2011 submittal (Ref. 1),
UT examination at the end of the defined inservice inspection (lSI) interval will confirm acceptance for the subsequent interval. However, lSI NDE qualifications were not addressed in this relief request or BWRVIP-58A. Please provide a detailed description of the UT that will be used for lSI.
RAIJ In Item 4 of Table 1 of Attachment 2 to the March 25, 2011 submittal (Ref. 1), as part of the justification for the reduced UT coverage of the modified weld configuration. an evaluation of a postulated flaw in the area of reduced UT coverage is referenced (Reference 18 to Attachment 2 of the March 25, 2011 submittal). Provide Reference 18 to Attachment 2 to the March 25, 2011 submittal (Ref. 1) for staff review.
The following questions are related to AREVA Document No. 32-9138065-002, "NMP1 CRD Housing IDTB Weld Anomaly Analysis" (Proprietary), (ADAMS Accession No. ML110950319),
hereafter referred to as "the flaw evaluation." References to the ASME Code,Section XI, are to the 2004 Edition, No Addenda.
RAIK Table 4-2 of the flaw evaluation lists the load combinations and cycles used to calculate fatigue crack growth for the postulated flaws. Tables 5-2, 5-5, and 5-7 through 5-10 show the contributions of these transients to fatigue crack growth various postulated flaw types and propagation paths. However, for the end-of-life stability evaluations of the three flaw types postulated (continuous external circumferential flaw and external axial flaw in the repair weld.
cylindrical flaw in repair weld or low-alloy steel), it is not clear which of these loads were
- 4 considered and which loads were considered limiting. Two AREVA internal documents, References 5 and 7 to the flaw evaluation are referenced as the source of the transients considered. It is not clear how these transients were derived from the NMP1 design basis.
For the evaluations of the circumferential and axial flaws in the weld metal summarized in Table 5-3 and 5-6, only the safety factor for Service Level A (normal operating) conditions is given, implying that only Service Level A conditions were considered, or were determined to be limiting.
For the cylindrical flaws, the margins for normal, upset, faulted and emergency conditions were calculated in accordance with the ASME Code,Section XI, IWB-3612. However, it is not clear which transient conditions and loadings were used to determine the applied stress intensity factors (K,) for these evaluations.
The staff therefore requests the following information:
- 1. Explain which transients and load combinations were used for the end-of-life evaluation for each type of flaw, and how these transients and load combinations were determined to be limiting.,
- 2. Identify which Service Levels the limiting loads provided in the response to item 1 represent. If the end-of-life flaw stability evaluation did not consider each Service Level (A, B, C, and D), justify why only certain service level conditions were considered.
- 3. Identify the source in the NMP1 design basis for the transients and loading combinations used to determine fatigue crack growth and to evaluate end-of-life flaw stability.
Describe how the tranSients listed were derived from the plant design basis.
RAI L For the normal startup and shutdown tranSients, the number of occurrences listed in Table 4-2 differs from the number of occurrences of these transients listed in Table V-2 of the Nine Mile Point, Unit 1 (NMP1) Updated Final Safety Analysis Report (UFSAR). Explain this discrepancy.
RAIM Clarify whether the end-of-life evaluations for the continuous external circumferential flaw and external axial flaw, summarized in Tables 5-3 and 5-6 and described as "limit load" analyses, should be characterized as "Elastic-Plastic Fracture Mechanics (EPFM)" evaluations since the procedures of Article C-6000 of the ASME Code,Section XI were used for these evaluations.
RAI N Figure C-4210 of the ASME Code,Section XI, Appendix C, "Flowchart for Selecting Analysis Method for Austenitic Piping," indicates for a weld metal flaw in a nonflux weld, the procedures of C-5000 should be used. Therefore, the staff requests that the licensee explain why the
- 5 procedures of C-6000 were used for the evaluations of the continuous external circumferential flaw and external axial flaw in the repair weld, since the gas-tungsten arc welding (GTAW) process used for the repair weld does not involve flux.
References
- 1. Nine Mile Point, Unit 1 - Request to Utilize an Alternative to the Requirements of 10 CFR 50.55a(g) for the Repair of Control Rod Drive Housing Penetrations for the Remainder of the License Renewal Period of Extended Operation, March 25, 2011 (ADAMS Accession No ML110950307)
- 2. BWRVIP-58-A: BWR Vessel and Internals Project, CRD Internal Access Weld Repair, EPRI, Palo Alto, CA: 2005,1012618
- 3. Nine Mile Point, Unit 1, Request to Utilize an Alternative to the Requirements of 10 CFR 50.55a(g) for the Repair of Control Rod Drive Housing Penetrations - Withdrawal of the Portion of the Request Regarding Rotary Peening (TAC No. ME5789) June 7,2012 (ADAMS Accession No. NIL 12160A349)
- 4. Nine Mile Point Nuclear Station, Unit1, 10CFR50.55a Request Number 1ISI-004, Revision 1, Attachment 2 to Nine Mile Point, Unit 1 - Request to Utilize an Alternative to the Requirements of 10 CFR 50.55a(g) for the Repair of Control Rod Drive Housing Penetrations - Response to NRC Follow-up Request for Additional Information, April 9, 2012 (ADAMS Accession No. ML12102A112)
September 13, 2012 Mr. Ken Langdon Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNIT NO.1, REQUEST FOR ADDITIONAL INFORMATION (RAI) RE: REQUEST NO. 1ISI-004, REQUEST TO UTILIZE AN ALTERNATIVE FOR THE REPAIR OF CONTROL ROD DRIVE HOUSING PENETRATIONS (TAC NO. ME5789)
Dear Mr. Langdon:
By letter dated March 4, 2011 (Agencywide Documents Access and Management System (ADAMS) Package Accession No. ML110680293), Nine Mile Point Nuclear Station, LLC submitted the "Request to Utilize an Alternative to the Requirements of 10 CFR 50.55a(g) for the Repair of Control Rod Drive Housing Penetrations for the Remainder of the License Renewal Period of Extended Operation." Additionally, the licensee has responded to the Nuclear Regulatory Commission (NRC) staffs request for additional information (RAI) by letters dated March 25,2011, (ADAMS Package Accession No. ML110950302), September 29,2011, (ADAMS Accession No. ML11279A037), April 9, (ADAMS Package Accession No. ML121020213), and June 7,2012, (ADAMS Accession No. ML12160A349).
The NRC staff has reviewed the information provided in the letters from the licensee and has determined that additional information is needed to complete its review. Enclosed is the NRC staff's RAI.
The RAI was discussed with your staff on September 6,2012, to clarify the draft RAls sent to the licensee earlier and the licensee committed to provide the responses to these RAls by COB October 31, 2012.
Please contact me at (301) 415-3308, if you have any questions.
Sincerely, Ira/
Bhalchandra Vaidya, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor licenSing Office of Nuclear Reactor Regulation Docket No. 50-220
Enclosure:
RAI cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsNrrPMNineMilePoint RidsNrrDeEvib RidsAcrsAcnw_MailCTR RidsNrrLAKGoldstein RidsOGCRp RidsRgn1 MailCenter JPoehler, NRR/EVIB CFairbanks, NRR/EVIB CNove, RES LPL1-1 R/F ADAMS Accession Number' ML12250A806 OFFICE LPL 1-1/PM LPL 1-1/LA NRR/DE/EVIB/BC LPLI-1/BC ILPLI-1/PM INAME BVaidya KGoldstein SRosenberg GWilson BVaid~a DATE 9/12/12 9/12/12 9/12/12 9/13/12 9/13/12 OFFICIAL RECORD COpy