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| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 March 17,2009 Mr. Keith J. Polson Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093 REQUEST FOR ADDITIONAL INFORMATION REGARDING NINE MILE POINT NUCLEAR STATION, UNIT NO.1, ALTERNATIVE FOR THE REPAIR AND INSERVICE INSPECTION OF CONTROL ROD DRIVE STUB TUBES FOR THE LICENSE RENEWAL PERIOD OF EXTENDED OPERATION (TAC NO. MD9604) | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 17,2009 Mr. Keith J. Polson Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093 |
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| | ==SUBJECT:== |
| | REQUEST FOR ADDITIONAL INFORMATION REGARDING NINE MILE POINT NUCLEAR STATION, UNIT NO.1, ALTERNATIVE FOR THE REPAIR AND INSERVICE INSPECTION OF CONTROL ROD DRIVE STUB TUBES FOR THE LICENSE RENEWAL PERIOD OF EXTENDED OPERATION (TAC NO. MD9604) |
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| ==Dear Mr. Polson:== | | ==Dear Mr. Polson:== |
| By letter dated August 29, 2008, Nine Mile Point Nuclear Station, LLC, submitted for Nuclear Regulatory Commission (NRC) staff review and approval, Relief Request 11SI-02 for Nine Mile Point Unit No.1 (NMP1). The relief request would allow the use of American Society of Mechanical Engineers, Boiler and Pressure Vessel Code (ASME Code), Section XI, Code Case N-730, "Roll-Expansion of Class 1 Control Rod Drive [CRD] Bottom Head Penetrations in BWRs," as an alternative permanent repair for CRD housing penetrations that may exhibit leakage during the license renewal period of extended operation (Le., from August 23, 2009 to August 22, 2029) or for the re-roll expansion of any previously roll expanded CRD housing that exhibits a repeat occurrence of leakage. The NRC staff is reviewing the submittal and has determined that additional information is needed to support its review. Enclosed is the NRC staff's request for additional information (RAI). The RAI was discussed with your staff on February 3 and 19, 2009, and it was agreed that your response would be provided within 60 days from the date of this letter. | | |
| Sincerely, Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-220 | | By letter dated August 29, 2008, Nine Mile Point Nuclear Station, LLC, submitted for Nuclear Regulatory Commission (NRC) staff review and approval, Relief Request 11SI-02 for Nine Mile Point Unit No.1 (NMP1). The relief request would allow the use of American Society of Mechanical Engineers, Boiler and Pressure Vessel Code (ASME Code), Section XI, Code Case N-730, "Roll-Expansion of Class 1 Control Rod Drive [CRD] Bottom Head Penetrations in BWRs," as an alternative permanent repair for CRD housing penetrations that may exhibit leakage during the license renewal period of extended operation (Le., from August 23, 2009 to August 22, 2029) or for the re-roll expansion of any previously roll expanded CRD housing that exhibits a repeat occurrence of leakage. |
| | The NRC staff is reviewing the submittal and has determined that additional information is needed to support its review. Enclosed is the NRC staff's request for additional information (RAI). The RAI was discussed with your staff on February 3 and 19, 2009, and it was agreed that your response would be provided within 60 days from the date of this letter. |
| | Sincerely, Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-220 |
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| ==Enclosure:== | | ==Enclosure:== |
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| RAI cc w/encl: | | RAI cc w/encl: Distribution via Listserv |
| Distribution via Listserv REQUEST FOR ADDITIONAL INFORMATION NINE MILE POINT NUCLEAR STATION, UNIT NO.1 REQUEST TO UTILIZE AN ALTERNATIVE FOR THE REPAIR AND INSERVICE INSPECTION OF CONTROL ROD DRIVE STUB TUBES FOR THE LICENSE RENEWAL PERIOD OF EXTENDED OPERATION DOCKET NO. 50-220 The Nuclear Regulatory Commission (NRC) staff is reviewing the Nine Mile Point Nuclear Station (NMPNS or the licensee) submittal for Nine Mile Point Unit NO.1 (NMP1) dated August 29, 2008. The NRC staff has determined that additional information requested below will be needed to support its review. In its proposed alternative for repair of control rod drive stub tubes, the licensee requested in Alternative 1A to apply the American Society of Mechanical Engineers, Boiler and Pressure Vessel Code (ASME Code), Section XI, Code Case N-730, "Roll-Expansion of Class 1 Control Rod Drive [CRD] Bottom Head Penetrations in BWRs." In Alternative 2A, the licensee requested to apply ASME Code, Section XI, Code Case N-730, but with the exception to perform the post-roll expansion VT-2 examination at approximately 900 pounds-per-square inch (psig) prior to returning NMP1 to full power operation. ASME Code Case N-730 requires a repair leakage test at the operating pressure. As the basis for the proposed alternatives (1A and 2A), the submittal references both Title 10 to Code of Federal Regulations (10 CFR), Section 50.55a(a)(3)(i) related to demonstrating an acceptable level of quality and safety as well as Section 50.55a(a)(3)(ii) related to demonstrating hardship. Please clarify which regulatory basis is being applied for each alternative when responding to the questions below. RAI-1. For proposed Alternative 1A, provide additional basis for using ASME Code Case N-730 instead of the ASME Code, Section XI, requirements by addressing the 4 considerations of the evaluation stated in Section 5 of the ASME Code Case N-730. If a generic evaluation is available, demonstrate that the generic evaluation is applicable to NMP1. RAI-2. For proposed Alternative 2A, provide the basis for using ASME Code Case N-730 with the exception of performing a leakage test at 900 psig, instead of the ASME Code, Section XI, requirements. If 10 CFR 50.55a(a)(3)(ii) is the applicable regulatory basis, as discussed during the teleconference between NRC and licensee staff on February 19, 2009, provide a more detailed justification to support your use of 10 CFR 50.55a(a)(3)(ii) and, in particular, the following referenced items in your original submittal: Basis for Relief (ii) states, "[i]nspections of CRD stub tubes for leakage durlnq a system leakage test at the nominal operating pressure | | |
| (-1030 psiq) associated with 100% rated reactor power cannot be performed during a normal plant startup, Enclosure | | REQUEST FOR ADDITIONAL INFORMATION NINE MILE POINT NUCLEAR STATION, UNIT NO.1 REQUEST TO UTILIZE AN ALTERNATIVE FOR THE REPAIR AND INSERVICE INSPECTION OF CONTROL ROD DRIVE STUB TUBES FOR THE LICENSE RENEWAL PERIOD OF EXTENDED OPERATION DOCKET NO. 50-220 The Nuclear Regulatory Commission (NRC) staff is reviewing the Nine Mile Point Nuclear Station (NMPNS or the licensee) submittal for Nine Mile Point Unit NO.1 (NMP1) dated August 29, 2008. The NRC staff has determined that additional information requested below will be needed to support its review. |
| -due to the excessive temperature and radiological exposure conditions to which the NDE [nondestructive examination] | | In its proposed alternative for repair of control rod drive stub tubes, the licensee requested in Alternative 1A to apply the American Society of Mechanical Engineers, Boiler and Pressure Vessel Code (ASME Code), Section XI, Code Case N-730, "Roll-Expansion of Class 1 Control Rod Drive [CRD] Bottom Head Penetrations in BWRs." In Alternative 2A, the licensee requested to apply ASME Code, Section XI, Code Case N-730, but with the exception to perform the post-roll expansion VT-2 examination at approximately 900 pounds-per-square inch (psig) prior to returning NMP1 to full power operation. ASME Code Case N-730 requires a post repair leakage test at the operating pressure. As the basis for the proposed alternatives (1A and 2A), the submittal references both Title 10 to Code of Federal Regulations (10 CFR), |
| examiners performing the visual VT-2 examinations would be exposed in the primary containment." Provide justification to support this statement as a hardship. Basis for Relief (iii) states, "[tlhls special test usually takes one full day of plant outage time, and the additional valve lineups and system reconfigurations necessary to support this special test impose an additional challenge to the affected systems." Provide justification to support this statement as a hardship. | | Section 50.55a(a)(3)(i) related to demonstrating an acceptable level of quality and safety as well as Section 50.55a(a)(3)(ii) related to demonstrating hardship. Please clarify which regulatory basis is being applied for each alternative when responding to the questions below. |
| March 17, 2009 Mr. Keith J. Polson Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093 REQUEST FOR ADDITIONAL INFORMATION REGARDING NINE MILE POINT NUCLEAR STATION, UNIT NO.1, ALTERNATIVE FOR THE REPAIR AND INSERVICE INSPECTION OF CONTROL ROD DRIVE STUB TUBES FOR THE LICENSE RENEWAL PERIOD OF EXTENDED OPERATION (TAC NO. MD9604) | | RAI-1. For proposed Alternative 1A, provide additional basis for using ASME Code Case N-730 instead of the ASME Code, Section XI, requirements by addressing the 4 considerations of the evaluation stated in Section 5 of the ASME Code Case N-730. If a generic evaluation is available, demonstrate that the generic evaluation is applicable to NMP1. |
| | RAI-2. For proposed Alternative 2A, provide the basis for using ASME Code Case N-730 with the exception of performing a leakage test at 900 psig, instead of the ASME Code, Section XI, requirements. If 10 CFR 50.55a(a)(3)(ii) is the applicable regulatory basis, as discussed during the teleconference between NRC and licensee staff on February 19, 2009, provide a more detailed justification to support your use of 10 CFR 50.55a(a)(3)(ii) and, in particular, the following referenced items in your original submittal: |
| | * Basis for Relief (ii) states, "[i]nspections of CRD stub tubes for leakage durlnq a system leakage test at the nominal operating pressure (-1030 psiq) associated with 100% rated reactor power cannot be performed during a normal plant startup, Enclosure |
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| | - 2 due to the excessive temperature and radiological exposure conditions to which the NDE [nondestructive examination] examiners performing the visual VT-2 examinations would be exposed in the primary containment." Provide justification to support this statement as a hardship. |
| | * Basis for Relief (iii) states, "[tlhls special test usually takes one full day of plant outage time, and the additional valve lineups and system reconfigurations necessary to support this special test impose an additional challenge to the affected systems." Provide justification to support this statement as a hardship. |
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| | March 17, 2009 Mr. Keith J. Polson Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093 |
| | |
| | ==SUBJECT:== |
| | REQUEST FOR ADDITIONAL INFORMATION REGARDING NINE MILE POINT NUCLEAR STATION, UNIT NO.1, ALTERNATIVE FOR THE REPAIR AND INSERVICE INSPECTION OF CONTROL ROD DRIVE STUB TUBES FOR THE LICENSE RENEWAL PERIOD OF EXTENDED OPERATION (TAC NO. MD9604) |
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| ==Dear Mr. Polson:== | | ==Dear Mr. Polson:== |
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| By letter dated August 29, 2008, Nine Mile Point Nuclear Station, LLC, submitted for Nuclear Regulatory Commission (NRC) staff review and approval, Relief Request 11SI-02 for Nine Mile Point Unit NO.1 (NMP1). The relief request would allow the use of American Society of Mechanical Engineers, Boiler and Pressure Vessel Code (ASME Code), Section XI, Code Case N-730, "Roll-Expansion of Class 1 Control Rod Drive [CRD] Bottom Head Penetrations in BWRs," as an alternative permanent repair for CRD housing penetrations that may exhibit leakage during the license renewal period of extended operation (Le., from August 23, 2009 to August 22, 2029) or for the re-roll expansion of any previously roll expanded CRD housing that exhibits a repeat occurrence of leakage. The NRC staff is reviewing the submittal and has determined that additional information is needed to support its review. | | By letter dated August 29, 2008, Nine Mile Point Nuclear Station, LLC, submitted for Nuclear Regulatory Commission (NRC) staff review and approval, Relief Request 11SI-02 for Nine Mile Point Unit NO.1 (NMP1). The relief request would allow the use of American Society of Mechanical Engineers, Boiler and Pressure Vessel Code (ASME Code), Section XI, Code Case N-730, "Roll-Expansion of Class 1 Control Rod Drive [CRD] Bottom Head Penetrations in BWRs," as an alternative permanent repair for CRD housing penetrations that may exhibit leakage during the license renewal period of extended operation (Le., from August 23, 2009 to August 22, 2029) or for the re-roll expansion of any previously roll expanded CRD housing that exhibits a repeat occurrence of leakage. |
| Enclosed is the NRC staff's request for additional information (RAI). The RAI was discussed with your staff on February 3 and 19, 2009, and it was agreed that your response would be provided within 60 days from the date of this letter. | | The NRC staff is reviewing the submittal and has determined that additional information is needed to support its review. Enclosed is the NRC staff's request for additional information (RAI). The RAI was discussed with your staff on February 3 and 19, 2009, and it was agreed that your response would be provided within 60 days from the date of this letter. |
| Sincerely, IRA! Richard V. | | Sincerely, IRA! |
| Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-220 | | Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-220 |
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| ==Enclosure:== | | ==Enclosure:== |
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| RAI cc w/encl: | | RAI cc w/encl: Distribution via Listserv DISTRIBUTION: |
| Distribution via Listserv DISTRIBUTION: | | PUBLIC RidsNrrPMRGuzman RidsNrrLASLittle RidsNrrDorlLpl1-1 Resource LPLI-1 R/F RidsRgn1 MailCenter RidsOGCRp RidsNrrAcrsAcnw&mMailCenter SSheng RidsNrrDciCvib Resource Accession No.: ML090710108 *RAI Wit. h concurrence provt'dedbiv e-man. . I chanqes rnade. NRR058 "I No su bst antia OFFICE LPLI-1/PM LPLI-1/LA CVIB/BC LPLI-1/BC NAME RGuzman MO'Brien for SLittle* MMitchell* MKowal DATE 3/12/09 3/12/09 3/12/09 3/17/09 OFFICIAL RECORD COpy}} |
| PUBLIC RidsNrrPMRGuzman RidsNrrLASLittle RidsNrrDorlLpl1-1 Resource LPLI-1 R/F RidsRgn1 MailCenter RidsOGCRp RidsNrrAcrsAcnw&mMailCenter SSheng RidsNrrDciCvib Resource RAI .h 'd db "I N bt .Ih d NRR058 Accession No.: ML090710108 | |
| * Wit concurrence provt e iv e-man. o su s antia c anqes rna e. LPLI-1/BC MKowal 3/17/09 OFFICE LPLI-1/PM LPLI-1/LA CVIB/BC NAME RGuzman MO'Brien for SLittle* | |
| MMitchell* | |
| DATE 3/12/09 3/12/09 3/12/09 OFFICIAL RECORD COpy}} | |
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Results
Other: ML043000333, ML043210580, ML051650086, ML053630052, ML060180205, ML060890579, ML060940577, ML060940622, ML060950413, ML061020154, ML061020166, ML061090064, ML062830307, ML062830317, ML082530250, ML091830049, ML091980454, ML110680289, ML110680291
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MONTHYEARML0414902132004-05-26026 May 2004 Transmittal of Nine Mile Point Units 1 & 2 Application for Renewed Operating Licenses, Including Environmental Report Project stage: Request ML0430003332004-10-26026 October 2004 to Audit and Review Plan for Plant Aging Management Reviews and Programs for the Nine Mile Point Nuclear Station, Units 1 and 2. Project stage: Other ML0432105802004-11-15015 November 2004 Audit and Review Plan for Plant Aging Management Reviews and Programs for the Nine Mile Point Nuclear Station, Units 1 and 2 (TAC Nos MC3272 and MC3273.) Project stage: Other ML0504601382005-02-14014 February 2005 Summary of a Conference Call Between the U.S. Nuclear Regulatory Commission and the Constellation Energy Group Inc. Concerning the Review of the Nine Mile Point Nuclear Station, Units 1 and 2 Project stage: Approval ML0516500862005-06-0909 June 2005 Presentation Slides, Nine Mile Point, Units 1 and 2, LRA Status Update Project stage: Other ML0516704462005-06-16016 June 2005 Summary of Meeting Held on June 9, 2005, Between the U.S. Nuclear Regulatory Commission (NRC) Staff and the Constellation Energy Group, Inc. Representatives to Discuss the Status of Their Recovery Effort, Nine Mile Point Nuclear Station, Un Project stage: Meeting ML0529702752005-10-20020 October 2005 E-mail from Ngoc Le of NRC to David Dellario Regarding the Audit and Review Plan for Plant Aging Management Programs and Reviews for Nine Mile Point Nuclear Station, Units 1 and 2 Project stage: Acceptance Review ML0536300522005-12-13013 December 2005 License Renewal Application (LRA) - Editorial Changes to Letter NMP1L 2005 and NMP1L 2007 Project stage: Other ML0601301972006-01-11011 January 2006 Amended License Renewal Application - Responses to NRC Requests for Additional Information - Sections 3.4 and 4.7 Project stage: Response to RAI ML0602200092006-01-18018 January 2006 Summary of Meeting with the Constellation Energy Group Inc. to Discuss Results of the Staff Audit of the Aging Management Programs and Reviews for Nine Mile Point, Units 1 and 2 Project stage: Meeting ML0601802052006-01-18018 January 2006 1/18/06 - Audit and Review Report for the Nine Mile Point Nuclear Station, Units 1 and 2, Amended License Renewal Application (TAC Nos. MC3272 and MC3273 Project stage: Other ML0605807562006-03-0303 March 2006 Transmittal Letter - Safety Evaluation Report for the Nine Mile Point Nuclear Station, Units 1 and 2, License Renewal Application Project stage: Approval ML0605807582006-03-0303 March 2006 Safety Evaluation Report for the Nine Mile Point Nuclear Station, Units 1 and 2, License Renewal Application Project stage: Approval ML0609504132006-03-23023 March 2006 SER Open Item 4.7B.1-1 and Closure of Amended License Renewal Application (Alra) Section A2.4, Commitment 39 - Biological Shield Wall Neutron Fluence Analysis Project stage: Other ML0609406222006-03-29029 March 2006 Email (3/29/06) from Peter Mazzaferro to Ngoc (Tommy) B. Le NMP2 Bioshield Fluence Calc Info Project stage: Other ML0608905792006-03-29029 March 2006 01/23/2006 Summary of a Telephone Conference Call Held Between the U.S. Nuclear Regulatory Commission and the Constellation Energy Group, Inc. Concerning the Review for the Nine Mile Point, Units 1 & 2, License Renewal Application Project stage: Other ML0610201662006-04-0303 April 2006 Safety Evaluation Report with Open Items Related to the License Renewal of Nine Mile Point, Dated March 2006 - NMPNS Comments (TAC Nos. MC3272 and MC3273) Project stage: Other ML0609405772006-04-0404 April 2006 Note to File - Docketing of Additional Information Pertaining to License Renewal Application of the Nine Mile Point Nuclear Station, Units 1 and 2 (TAC Nos. MC3272 and MC3273) Project stage: Other ML0610201542006-04-0404 April 2006 Safety Evaluation Report (Ser), with Open Items Related to the License Renewal Dated March 2006 - SER Open Item 3.0.3.2.17-1 Project stage: Other ML0610900642006-04-18018 April 2006 Note to File - Docketing of Additional Information Pertaining to License Renewal Application of the Nine Mile Point Nuclear Station, Units 1 and 2 (TAC No'S. MC3272 and MC3273) Project stage: Other ML0610901062006-04-19019 April 2006 Request for Additional Information, Review of Nine Mile Point Nuclear Station, Units 1 and 2, License Renewal Application (TAC Nos. MC3272 and MC3273) Project stage: RAI ML0612205952006-04-21021 April 2006 Amended License Renewal Application - NRC Request for Additional Information (RAI) 4.7.5. A-1 Project stage: Request ML0611802422006-06-0101 June 2006 Ltr to Timothy O' Connor - Final Safety Evaluation Report Related to the License Renewal of the Nine Mile Point Nuclear Station, Units 1 and 2 (TAC Nos. MC3272 and MC3273) Project stage: Approval ML0614603132006-06-0101 June 2006 Safety Evaluation Report Related to the License Renewal of the Nine Mile Point Nuclear Station, Units 1 and 2 (TAC Nos. MC3272 and MC3273) Project stage: Approval ML0619800502006-07-13013 July 2006 03/27/2006 Summary of Meeting Between U.S. Nuclear Regulatory Commission Staff & Constellation Energy Group Inc. Representatives to Discuss Status of Open Item 3.0.3.2.17-1 for Nine Mile Point Nuclear Station, Units 1 & 2, License Renewal A Project stage: Meeting ML0628303072006-10-31031 October 2006 LLC Docket No. 50-220 Nine Mile Point Nuclear Station, Unit 1 Renewed Facility Operating License Renewed License No. DPR-63 Project stage: Other ML0628303172006-10-31031 October 2006 LLC Docket No. 50-410 Nine Mile Point Nuclear Station, Unit 2 Renewed Facility Operating License Renewed License No. NPF-69 Project stage: Other ML0628304332006-10-31031 October 2006 Federal Register Notice for Nine Mile Point Nuclear, LLC Nine Mile Point Nuclear Station Units 1 and 2, Notice of Issuance of Renewed Facility Operating License Nos. DPR-63 and NPF-69 for an Additional 20-Year Period Project stage: Approval ML0628302732006-10-31031 October 2006 Issuance of Renewed Facility Operating License Nos. DPR-63 and NPF-69 for the Nine Mile Point Nuclear Station, Units 1 and 2 Project stage: Approval ML0825302502008-08-29029 August 2008 Request to Utilize an Alternative to the Requirements of 10 CFR 50.55a(g) for the Repair and Inservice Inspection of Control Rod Drive Stub Tubes for the License Renewal Period of Extended Operation Project stage: Other ML0907101082009-03-17017 March 2009 Request for Additional Information, Alternative for the Repair and Inservice Inspection of Control Rod Drive Stub Tubes for the License Renewal Period of Extended Operation Project stage: RAI ML0914104472009-05-14014 May 2009 Request to Utilize an Alternative to the Requirements of 10 CFR 50.55a(g) for the Repair and Inservice Inspection of Control Rod Drive Stub Tubes for the License Renewal Period of Extended Operation - Response to NRC Request for Additional Project stage: Request ML0918300492009-06-25025 June 2009 Request to Utilize an Alternative to the Requirements of 10 CFR 50.55a(g) for the Repair & Inservice Inspection of Control Rod Drive Stub Tubes for the License Renewal Period of Extended Operation - Response. Project stage: Other ML0919804542009-08-0303 August 2009 Request to Utilize Alternative of Applying ASME Code Case 730 for Repair and ISI of Control Rod Drive Bottom Head Penetrations for the License Renewal Period of Extended Operation Project stage: Other ML1106802892011-03-0404 March 2011 Areva Calculation No. 32-9138066-000, NMP-1 CRD Housing Idtb Weld Anomaly Analysis. (Non-Proprietary) Project stage: Other ML1106802912011-03-0404 March 2011 Request to Utilize an Alternative to the Requirements of 10CFR50.55a(g) for Repair of Control Rod Drive Housing Penetrations for the Remainder of License Renewal Period of Extended Operation Project stage: Other 2006-03-03
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Category:Letter
MONTHYEARML24268A3382024-10-16016 October 2024 Issuance of Amendment No. 253 Regarding the Modification of TS Surveillance Requirement 4.3.6.a Related to Adoption of TSTF-425, Revision 3 RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP2L2890, Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6)2024-10-0404 October 2024 Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6) ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing IR 05000220/20243022024-10-0303 October 2024 Initial Operator Licensing Examination Report 05000220/2024302 ML24190A0012024-09-26026 September 2024 Issuance of Amendment Nos. 252 and 197 Regarding the Revision to Technical Specification Design Features Section to Remove Nine Mile Point Unit 3 Project Designation NMP1L3608, Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-09-20020 September 2024 Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024 Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000220/20240052024-08-29029 August 2024 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2024005 and 05000410/2024005) IR 05000220/20240102024-08-22022 August 2024 Age-Related Degradation Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3603, Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan2024-08-20020 August 2024 Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000220/20240022024-08-0505 August 2024 Integrated Inspection Report 05000220/2024002 and 05000410/2024002 ML24215A3002024-08-0202 August 2024 Operator Licensing Examination Approval NMP1L3601, Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-07-31031 July 2024 Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation ML24213A1412024-07-31031 July 2024 Requalification Program Inspection NMP2L2883, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations2024-07-24024 July 2024 Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations ML24198A0852024-07-16016 July 2024 Senior Reactor and Reactor Operator Initial License Examinations RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3584, License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2024-06-13013 June 2024 License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling IR 05000220/20244012024-05-30030 May 2024 Security Baseline Inspection Report 05000220/2024401 and 05000410/2024401(Cover Letter Only) ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 NMP1L3591, Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request2024-05-18018 May 2024 Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request NMP1L3589, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-05-16016 May 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable NMP1L3582, 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 22024-05-15015 May 2024 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 2 ML24158A2052024-05-15015 May 2024 Annual Radioactive Environmental Operating Report IR 05000220/20240012024-05-10010 May 2024 Integrated Inspection Report 05000220/2024001 and 05000410/2024001 RS-24-049, Updated Notice of Intent to Pursue Subsequent License Renewal Applications2024-05-0909 May 2024 Updated Notice of Intent to Pursue Subsequent License Renewal Applications RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024 Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds NMP2L2880, Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum2024-05-0101 May 2024 Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP1L3581, Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report2024-04-30030 April 2024 Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report NMP2L2877, 2023 Annual Environmental Operating Report2024-04-19019 April 2024 2023 Annual Environmental Operating Report NMP2L2878, Core Operating Limits Report2024-04-16016 April 2024 Core Operating Limits Report ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition ML24092A3352024-04-0101 April 2024 NRC Office of Investigations Case No. 1-2023-002 RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24074A2812024-03-14014 March 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3577, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-03-13013 March 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable IR 05000220/20230062024-02-28028 February 2024 Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2, (Reports 05000220/2023006 and 05000410/2023006) NMP1L3570, 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 05000410/LER-2023-001, Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater2024-01-30030 January 2024 Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater 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 2024-09-04
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24197A0162024-07-12012 July 2024 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC - Fleet Request - License Amendment Request to Adopt TSTF-591 ML24074A2812024-03-14014 March 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000220/2024010 and 05000410/2024010 ML23264A7992023-09-21021 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) ML18067A1482018-03-0808 March 2018 Enclosurequest for Additional Information (Letter to P. R. Simpson Request for Additional Information Regarding Exelon Generating Company, Llc'S Decommissioning Funding Plan Update for Independent Spent Fuel Storage Installation) 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 2024-07-12
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 17,2009 Mr. Keith J. Polson Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING NINE MILE POINT NUCLEAR STATION, UNIT NO.1, ALTERNATIVE FOR THE REPAIR AND INSERVICE INSPECTION OF CONTROL ROD DRIVE STUB TUBES FOR THE LICENSE RENEWAL PERIOD OF EXTENDED OPERATION (TAC NO. MD9604)
Dear Mr. Polson:
By letter dated August 29, 2008, Nine Mile Point Nuclear Station, LLC, submitted for Nuclear Regulatory Commission (NRC) staff review and approval, Relief Request 11SI-02 for Nine Mile Point Unit No.1 (NMP1). The relief request would allow the use of American Society of Mechanical Engineers, Boiler and Pressure Vessel Code (ASME Code),Section XI, Code Case N-730, "Roll-Expansion of Class 1 Control Rod Drive [CRD] Bottom Head Penetrations in BWRs," as an alternative permanent repair for CRD housing penetrations that may exhibit leakage during the license renewal period of extended operation (Le., from August 23, 2009 to August 22, 2029) or for the re-roll expansion of any previously roll expanded CRD housing that exhibits a repeat occurrence of leakage.
The NRC staff is reviewing the submittal and has determined that additional information is needed to support its review. Enclosed is the NRC staff's request for additional information (RAI). The RAI was discussed with your staff on February 3 and 19, 2009, and it was agreed that your response would be provided within 60 days from the date of this letter.
Sincerely, Richard V. Guzman, Senior 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
REQUEST FOR ADDITIONAL INFORMATION NINE MILE POINT NUCLEAR STATION, UNIT NO.1 REQUEST TO UTILIZE AN ALTERNATIVE FOR THE REPAIR AND INSERVICE INSPECTION OF CONTROL ROD DRIVE STUB TUBES FOR THE LICENSE RENEWAL PERIOD OF EXTENDED OPERATION DOCKET NO. 50-220 The Nuclear Regulatory Commission (NRC) staff is reviewing the Nine Mile Point Nuclear Station (NMPNS or the licensee) submittal for Nine Mile Point Unit NO.1 (NMP1) dated August 29, 2008. The NRC staff has determined that additional information requested below will be needed to support its review.
In its proposed alternative for repair of control rod drive stub tubes, the licensee requested in Alternative 1A to apply the American Society of Mechanical Engineers, Boiler and Pressure Vessel Code (ASME Code),Section XI, Code Case N-730, "Roll-Expansion of Class 1 Control Rod Drive [CRD] Bottom Head Penetrations in BWRs." In Alternative 2A, the licensee requested to apply ASME Code,Section XI, Code Case N-730, but with the exception to perform the post-roll expansion VT-2 examination at approximately 900 pounds-per-square inch (psig) prior to returning NMP1 to full power operation. ASME Code Case N-730 requires a post repair leakage test at the operating pressure. As the basis for the proposed alternatives (1A and 2A), the submittal references both Title 10 to Code of Federal Regulations (10 CFR),
Section 50.55a(a)(3)(i) related to demonstrating an acceptable level of quality and safety as well as Section 50.55a(a)(3)(ii) related to demonstrating hardship. Please clarify which regulatory basis is being applied for each alternative when responding to the questions below.
RAI-1. For proposed Alternative 1A, provide additional basis for using ASME Code Case N-730 instead of the ASME Code,Section XI, requirements by addressing the 4 considerations of the evaluation stated in Section 5 of the ASME Code Case N-730. If a generic evaluation is available, demonstrate that the generic evaluation is applicable to NMP1.
RAI-2. For proposed Alternative 2A, provide the basis for using ASME Code Case N-730 with the exception of performing a leakage test at 900 psig, instead of the ASME Code,Section XI, requirements. If 10 CFR 50.55a(a)(3)(ii) is the applicable regulatory basis, as discussed during the teleconference between NRC and licensee staff on February 19, 2009, provide a more detailed justification to support your use of 10 CFR 50.55a(a)(3)(ii) and, in particular, the following referenced items in your original submittal:
- Basis for Relief (ii) states, "[i]nspections of CRD stub tubes for leakage durlnq a system leakage test at the nominal operating pressure (-1030 psiq) associated with 100% rated reactor power cannot be performed during a normal plant startup, Enclosure
- 2 due to the excessive temperature and radiological exposure conditions to which the NDE [nondestructive examination] examiners performing the visual VT-2 examinations would be exposed in the primary containment." Provide justification to support this statement as a hardship.
- Basis for Relief (iii) states, "[tlhls special test usually takes one full day of plant outage time, and the additional valve lineups and system reconfigurations necessary to support this special test impose an additional challenge to the affected systems." Provide justification to support this statement as a hardship.
March 17, 2009 Mr. Keith J. Polson Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING NINE MILE POINT NUCLEAR STATION, UNIT NO.1, ALTERNATIVE FOR THE REPAIR AND INSERVICE INSPECTION OF CONTROL ROD DRIVE STUB TUBES FOR THE LICENSE RENEWAL PERIOD OF EXTENDED OPERATION (TAC NO. MD9604)
Dear Mr. Polson:
By letter dated August 29, 2008, Nine Mile Point Nuclear Station, LLC, submitted for Nuclear Regulatory Commission (NRC) staff review and approval, Relief Request 11SI-02 for Nine Mile Point Unit NO.1 (NMP1). The relief request would allow the use of American Society of Mechanical Engineers, Boiler and Pressure Vessel Code (ASME Code),Section XI, Code Case N-730, "Roll-Expansion of Class 1 Control Rod Drive [CRD] Bottom Head Penetrations in BWRs," as an alternative permanent repair for CRD housing penetrations that may exhibit leakage during the license renewal period of extended operation (Le., from August 23, 2009 to August 22, 2029) or for the re-roll expansion of any previously roll expanded CRD housing that exhibits a repeat occurrence of leakage.
The NRC staff is reviewing the submittal and has determined that additional information is needed to support its review. Enclosed is the NRC staff's request for additional information (RAI). The RAI was discussed with your staff on February 3 and 19, 2009, and it was agreed that your response would be provided within 60 days from the date of this letter.
Sincerely, IRA!
Richard V. Guzman, Senior 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 RidsNrrPMRGuzman RidsNrrLASLittle RidsNrrDorlLpl1-1 Resource LPLI-1 R/F RidsRgn1 MailCenter RidsOGCRp RidsNrrAcrsAcnw&mMailCenter SSheng RidsNrrDciCvib Resource Accession No.: ML090710108 *RAI Wit. h concurrence provt'dedbiv e-man. . I chanqes rnade. NRR058 "I No su bst antia OFFICE LPLI-1/PM LPLI-1/LA CVIB/BC LPLI-1/BC NAME RGuzman MO'Brien for SLittle* MMitchell* MKowal DATE 3/12/09 3/12/09 3/12/09 3/17/09 OFFICIAL RECORD COpy