Letter Sequence Response to RAI |
---|
|
|
|
|
---|
Category:Letter
MONTHYEARML24025A9362024-01-31031 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0055 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000263/20230042024-01-31031 January 2024 Integrated Inspection Report 05000263/2023004 ML24024A0722024-01-24024 January 2024 Independent Spent Fuel Storage Installation, Onticello, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000263/20244012024-01-22022 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000263/2024401 L-MT-23-054, Subsequent License Renewal Application Supplement 82024-01-11011 January 2024 Subsequent License Renewal Application Supplement 8 L-MT-23-047, License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data2023-12-29029 December 2023 License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data L-MT-23-056, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 22023-12-18018 December 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 2 ML23349A0572023-12-15015 December 2023 and Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota IR 05000263/20234022023-12-13013 December 2023 Security Baseline Inspection Report 05000263/2023402 L-MT-23-042, 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462023-12-11011 December 2023 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 L-MT-23-052, Subsequent License Renewal Application Supplement 72023-11-30030 November 2023 Subsequent License Renewal Application Supplement 7 L-MT-23-051, Update to the Technical Specification Bases2023-11-28028 November 2023 Update to the Technical Specification Bases L-MT-23-049, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 12023-11-21021 November 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 ML23319A3182023-11-15015 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000263/20230032023-11-13013 November 2023 Integrated Inspection Report 05000263/2023003 and 07200058/2023001 L-MT-23-043, 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-092023-11-13013 November 2023 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-09 L-MT-23-038, License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.62023-11-10010 November 2023 License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 L-MT-23-046, Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 12023-11-0909 November 2023 Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 1 ML23291A1102023-10-23023 October 2023 Environmental Audit Summary and RCIs and RAIs ML23285A3062023-10-12012 October 2023 Implementation of the Fleet Standard Emergency Plan for the Monticello Nuclear Generating Plant and the Prairie Island Nuclear Generating Plant L-MT-23-041, Subsequent License Renewal Application Response to Request for Confirmation of Information Set 22023-10-0303 October 2023 Subsequent License Renewal Application Response to Request for Confirmation of Information Set 2 L-MT-23-037, Subsequent License Renewal Application Response to Request for Additional Information Set 32023-09-22022 September 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 3 ML23262B0372023-09-19019 September 2023 Response to NRC Request for Additional Information Regarding the 2023 Monticello and Prairie Island Plant Decommissioning Funding Status Reports ML23248A2092023-09-18018 September 2023 Proposed Alternative VR-11 to the Requirements of the ASME OM Code Associated with Periodic Verification Testing of MO-2397, Reactor Water Cleanup Inboard Isolation Valve ML23256A1682023-09-13013 September 2023 Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Voluntary Security Clearance Program 2023 Insider Threat Program Self-Inspection IR 05000263/20230102023-09-0707 September 2023 Commercial Grade Dedication Inspection Report 05000263/2023010 L-MT-23-036, Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 62023-09-0505 September 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 6 ML23214A2412023-08-31031 August 2023 Letter: Aging Management Audit - Monticello Unit 1 - Subsequent License Renewal Application IR 05000263/20230052023-08-30030 August 2023 Updated Inspection Plan for Monticello Nuclear Generating Plant (Report 05000263/2023005) L-MT-23-035, Subsequent License Renewal Application Supplement 52023-08-28028 August 2023 Subsequent License Renewal Application Supplement 5 ML23241A9732023-08-21021 August 2023 Request for Scoping Comments Concerning the Environmental Review of Monticello Nuclear Generating Plant, Unit 1, Subsequent License Renewal Application (Docket No. 50-263) L-MT-23-034, Subsequent License Renewal Application Response to Request for Additional Information Set 12023-08-15015 August 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 1 ML23222A0122023-08-10010 August 2023 Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Changes in Foreign Ownership, Control or Influence ML23215A1312023-08-0909 August 2023 License Renewal Regulatory Audit Regarding the Environmental Review of the Subsequent License Renewal Application IR 05000263/20230022023-08-0707 August 2023 Plantintegrated Inspection Report 05000263/2023002 L-MT-23-028, 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report2023-07-31031 July 2023 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report L-MT-23-032, 10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-112023-07-31031 July 2023 10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-11 ML23198A0412023-07-28028 July 2023 LRA Availability Letter ML23206A2342023-07-25025 July 2023 Independent Spent Fuel Storage Installation, and Monticello Nuclear Generating Plant, Changes in Foreign Ownership, Control or Influence ML23201A0352023-07-24024 July 2023 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23202A0032023-07-21021 July 2023 Independent Spent Fuel and Independent Spent Fuel Storage Installation, Monticello Nuclear Generating Plant, Submittal of Quality Assurance Topical Report (NSPM-1) L-MT-23-031, Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 12023-07-18018 July 2023 Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 1 ML23195A1732023-07-14014 July 2023 Revision of Standard Practice Procedures Plan IR 05000263/20235012023-07-13013 July 2023 Emergency Preparedness Inspection Report 05000263/2023501 2024-01-31
[Table view] Category:Inservice/Preservice Inspection and Test Report
MONTHYEARL-MT-23-028, 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report2023-07-31031 July 2023 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report L-MT-23-024, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Inspection (ISI) Interval, RR-002 (L-MT-23-024)2023-07-11011 July 2023 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Inspection (ISI) Interval, RR-002 (L-MT-23-024) L-MT-22-030, Sixth Interval Inservice Testing (1ST) Plan2022-09-0606 September 2022 Sixth Interval Inservice Testing (1ST) Plan ML22067A0842022-03-0707 March 2022 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-28 (LMT-22-007) L-MT-22-006, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-26 (L-MT-22-006)2022-02-18018 February 2022 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-26 (L-MT-22-006) L-MT-21-051, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-22 (L-MT-21-051)2021-12-23023 December 2021 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-22 (L-MT-21-051) ML21305A0672021-11-0101 November 2021 Clone of 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing (IST) Ten-Year Interval PR-02 (L-MT-21-054) ML21278A1852021-10-0505 October 2021 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval VR-02 (LMT-21-049) L-MT-21-041, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval VR-05 (L-MT-21-041)2021-08-31031 August 2021 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval VR-05 (L-MT-21-041) L-MT-21-038, 2021 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report2021-08-17017 August 2021 2021 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report L-MT-20-004, 10 CFR 50.55a Request: Request RR-016 Associated with the Fifth Ten-Year Inservice Inspection (ISI) Interval2020-02-14014 February 2020 10 CFR 50.55a Request: Request RR-016 Associated with the Fifth Ten-Year Inservice Inspection (ISI) Interval L-MT-20-001, 10 CFR 50.55a(z)(1) Request Vr 05: Request for Approval of an Alternative for Pressure Isolation Valve Testing2020-01-16016 January 2020 10 CFR 50.55a(z)(1) Request Vr 05: Request for Approval of an Alternative for Pressure Isolation Valve Testing L-MT-19-028, 2019 Refueling Outage 90-Day Lnservice Inspection (ISI) Summary Report; Second Steam Dryer Inspection Summary2019-08-0909 August 2019 2019 Refueling Outage 90-Day Lnservice Inspection (ISI) Summary Report; Second Steam Dryer Inspection Summary L-MT-17-059, 2017 Refueling Outage 90-Day Lnservice Inspection (ISI) Summary Report2017-08-0909 August 2017 2017 Refueling Outage 90-Day Lnservice Inspection (ISI) Summary Report L-MT-15-064, Cycle 27 Inservice Inspection Summary Report2015-08-26026 August 2015 Cycle 27 Inservice Inspection Summary Report ML14212A0712014-07-30030 July 2014 10 CFR 50.55a Request No. Vr 05: Proposed Alternative to Lnservice Testing Requirements Pursuant to 10 CFR 50.55a(a)(3)(ii) L-MT-14-037, CFR 50.55a Request No. 009: Relief from Impractical Examination Coverage Requirements Pursuant to 10 CFR 50.55a(g)(5)(iii) for the Fifth Ten-Year Lnservice Inspection Interval2014-06-0606 June 2014 CFR 50.55a Request No. 009: Relief from Impractical Examination Coverage Requirements Pursuant to 10 CFR 50.55a(g)(5)(iii) for the Fifth Ten-Year Lnservice Inspection Interval L-MT-14-021, Proposed Alternative in Accordance with 10 CFR 50.55a Request RR-008 Associated with the Fifth Ten-Year Inservice Inspection (ISI) Interval2014-02-28028 February 2014 Proposed Alternative in Accordance with 10 CFR 50.55a Request RR-008 Associated with the Fifth Ten-Year Inservice Inspection (ISI) Interval ML13308B2192013-10-11011 October 2013 Enclosure 3 - MNGP Evaluation EC-22537 - 2013 H8-H9 Shroud Support Structure Indications Update ML13308B2182013-10-0808 October 2013 Enclosure 2- BWRVIP Inspection Summary Report ML13308B2172013-10-0808 October 2013 Enclosure 1 - Cycle No. 26 and 1R26 2013 Refueling Outage Inservice Inspection: Interval 4, Period 3 and Interval 5, Period 1, Owner'S Activity Report (OAR-1) L-MT-13-060, Response to Request for Additional Information Regarding Fifth 10-Year Inservice Inspection Program Plan Review2013-07-17017 July 2013 Response to Request for Additional Information Regarding Fifth 10-Year Inservice Inspection Program Plan Review L-MT-12-094, In-service Testing (IST) Program Plan for Safety Related Seismic Restraints (Snubbers) for the Fifth 10-Year Interval2012-11-30030 November 2012 In-service Testing (IST) Program Plan for Safety Related Seismic Restraints (Snubbers) for the Fifth 10-Year Interval L-MT-12-019, CFR 50.55a Requests Associated with the Fifth Ten-Year Inservice Testing Interval2012-02-28028 February 2012 CFR 50.55a Requests Associated with the Fifth Ten-Year Inservice Testing Interval L-MT-12-017, CFR 50.55a Requests Associated with the Fifth Ten-Year Inservice Inspection Interval2012-02-28028 February 2012 CFR 50.55a Requests Associated with the Fifth Ten-Year Inservice Inspection Interval L-MT-12-020, Fifth Ten-Year Lnservice Testing Plan2012-02-28028 February 2012 Fifth Ten-Year Lnservice Testing Plan L-MT-12-018, Fifth Ten-Year Lnservice Inspection Plan2012-02-28028 February 2012 Fifth Ten-Year Lnservice Inspection Plan L-MT-12-011, Supplement to 10CFR50.55a Requests Associated with the Fourth and Fifth Lnservice Lnspection Ten-Year Intervals2012-02-15015 February 2012 Supplement to 10CFR50.55a Requests Associated with the Fourth and Fifth Lnservice Lnspection Ten-Year Intervals L-MT-11-046, Cycle 25 Inservice Inspection Summary Report2011-08-23023 August 2011 Cycle 25 Inservice Inspection Summary Report L-MT-09-078, Submittal of Cycle No. 24 Inservice Inspection Summary Report for Inservice Inspection and ASME Section Xl Repairs and Replacements2009-08-0707 August 2009 Submittal of Cycle No. 24 Inservice Inspection Summary Report for Inservice Inspection and ASME Section Xl Repairs and Replacements L-MT-07-058, Cycle No. 23 Lnservice Inspection Summary Report for Lnservice Inspection and ASME Section XI Repairs and Replacements2007-07-27027 July 2007 Cycle No. 23 Lnservice Inspection Summary Report for Lnservice Inspection and ASME Section XI Repairs and Replacements L-MT-05-088, 10 CFR 50.55a Request No. 13: Relief from Impractical Examination Coverage Requirements Pursuant to 10 CFR 50.55a(g)(5)(iii) for the Fourth Ten-Year Inservice Inspection Interval2005-09-27027 September 2005 10 CFR 50.55a Request No. 13: Relief from Impractical Examination Coverage Requirements Pursuant to 10 CFR 50.55a(g)(5)(iii) for the Fourth Ten-Year Inservice Inspection Interval L-MT-05-078, Summary Report for Inservice Inspections and ASME Section XI Repairs and Replacements2005-07-12012 July 2005 Summary Report for Inservice Inspections and ASME Section XI Repairs and Replacements L-MT-05-039, Fourth Interval Inservice Inspection Examination Plan. Revision 32005-04-26026 April 2005 Fourth Interval Inservice Inspection Examination Plan. Revision 3 L-MT-04-050, Fourth Interval Inservice Inspection Examination Plan, Revision 22004-09-16016 September 2004 Fourth Interval Inservice Inspection Examination Plan, Revision 2 L-MT-03-056, Summary Report for Inservice Inspections and ASME Section XI Repairs and Replacements2003-08-25025 August 2003 Summary Report for Inservice Inspections and ASME Section XI Repairs and Replacements L-MT-03-023, Response to Request for Additional Information Regarding Fourth 10-Year Interval Inservice Testing Program Relief Request Number No.VR-012003-04-29029 April 2003 Response to Request for Additional Information Regarding Fourth 10-Year Interval Inservice Testing Program Relief Request Number No.VR-01 ML0235205912002-12-0606 December 2002 to Engineering Work Instruction EWI-09.04.01, Inservice Testing Program. ML0233806832002-11-22022 November 2002 Part 2 of 2, Monticello, Request for Review and Approval of Relief Request Associated with Fourth 10-Year Interval Inservice Testing Program Plan Submittal ML0233701072002-11-22022 November 2002 Part 1 of 2, Monticello, Request for Review and Approval of Relief Request Associated with Fourth 10-Year Interval Inservice Testing Program Plan Submittal ML0217102272002-06-0606 June 2002 Inservice Testing Program for Engineering Work Instruction, Revision 8 ML0211905312002-04-0101 April 2002 Revision 7 to EWI-09.04.01, Inservice Testing Program. ML0208603482002-03-12012 March 2002 Part 1 of 4, Monticello Nuclear Generating Plant, Summary Report for Inservice Inspections & ASME Section XI Repairs & Replacements ML0208605512002-03-12012 March 2002 Part 2 of 4, Monticello Nuclear Generating Plant, Summary Report for Inservice Inspections & ASME Section XI Repairs & Replacements, Owner'S Report for Repairs or Replacements - Form NIS-2, Revision 4 to 3613 ML0208606762002-03-12012 March 2002 Part 3 of 4, Monticello Nuclear Generating Plant, Summary Report for Inservice Inspections & ASME Section XI Repairs & Replacements, Owner'S Report for Repairs or Replacements - Form NIS-2, Revision 4 to 3613 ML0208606932002-03-12012 March 2002 Part 4 of 4, Monticello Nuclear Generating Plant, Summary Report for Inservice Inspections & ASME Section XI Repairs & Replacements, Owner'S Report for Repairs or Replacements - Form NIS-2, Revision 4 to 3613 ML0203203662002-01-11011 January 2002 Inservice Inspection Plan Submittal of Relief Request Number 14 for the Third Ten Year Interval 2023-07-31
[Table view] |
Text
Xcel Energy@ July 17, 2013 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket 50-263 Renewed Facility Operating License No. DPR-22 Monticello Nuclear Generating Plant 2807 W County Road 75 Monticello, MN 55362 L-MT -13-060 10 CFR 50.55a(g) Response to Request for Additional Information Regarding Fifth 10-Year Inservice Inspection Program Plan Review (TAC ME8186) References: 1) Letter from Northern States Power Company, a Minnesota corporation (NSPM), d/b/a Xcel Energy to Document Control Desk, "Fifth Ten-Year Inservice Inspection Plan", dated February 28,2012 (ADAMS Accession No. ML 12060A298). 2) NRC Draft Request for Additional Information Regarding Review of the Fifth 1 O-Year Inservice Inspection Program Plan (TAC ME8186), dated April 9, 2013 (ADAMS Accession No. ML 13099A275). 3) NRC Request for Additional Information Regarding Review of the Fifth1 0-Year Inservice Inspection Program Plan (TAC ME8186), dated May 16, 2013 (ADAMS Accession No. ML 13171A278). Pursuant to 10 CFR 50.55a(g)(5)(i), Northern States Power Company, a Minnesota corporation, d/b/a Xcel Energy, the licensee for the Monticello Nuclear Generating Plant, submitted its fifth ten-year intervallnservice Inspection (lSI) Program Plan (Reference 1). Subsequently, the U. S. Nuclear Regulatory Commission (NRC) issued a Draft Request for Additional Information (RAI) Regarding Review of the Fifth10-Year Inservice Inspection Program Plan (Reference 2). At the conclusion of a May 9, 2013 teleconference among NSPM, the NRC and its contractors, it was determined that draft RAI Question 1 was no longer required and RAI Question 4 (a comment) was understood and removed. Draft RAI Questions 2 and 3 were formally issued (Reference 3). The NSPM response to the NRC RAI is provided in the Enclosure.
Document Control Desk L-MT-13-060 Page 2 of 2 Summary of Commitments This letter makes no new commitments and no revisions to existing commitments. Should you have questions regarding this letter, please contact Mr. Randy Rippy at (612) 330-6911. Mark A. Schimmel Site Vice President, Monticello Nuclear Generating Plant Northern States Power Company -Minnesota Enclosure cc: Administrator, Region III, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC ENCLOSURE RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION FIFTH TEN-YEAR INSERVICE INSPECTION PLAN DATED MAY 16, 2013 RAI-1: Exempt Components RAI-1: In Section 3.0 and Appendix D of the submittal, the licensee stated that examinations of Class 1, 2, 3 components, including welded attachments and supports, are based on the requirements as defined in ASME Code,Section XI, Sections IWB-, IWC-, IWD-, and IWF-2000. The Bottom Head Drain Nozzle listed under ASME Code Category B-D is exempt per ASME Code,Section XI, Paragraph IWB-1220(c). Please verify there are not any other components being examined that fall under the provisions of ASME Code,Section XI, Paragraphs IWB-, IWC-, and IWD-1220, "Components Exempt from Examination, " and IWF-1230, "Supports Exempt from Examination. " Response to RAI-1: As noted, the Bottom Head Drain Nozzle is identified as exempt, and is therefore not subject to examination under IWB-1220(c) and has no scheduled exams. It was included in Appendix D as an anecdotal notation and, as seen by the Category Total of 58, it was not included in the total number of components subject to examination. Review has determined that there are no components being examined under ASME Section XI provisions that are exempted by paragraphs IWB-, IWC-, IWD-1220 or IWF-1230. Page 1 of 7 RAI-2: Appendix 0, Inspection Plan and Schedule Tables RAI-2.1: Category B-A, Item B1.11, Reactor Vessel circumferential shell welds -ASME Code Table IWB-2500-1, Category B-A, Item B1.11, states that all welds should be inspected. Request for Alternative, RR-001, requires that all welds be examined at a reduced percentage of 2 to 3 percent associated with the intersection with longitudinal welds. The licensee has listed only one out of four circumferential shell welds that are to be inspected for the fifth ten-year inservice inspection program plan. Please explain the basis for examining only one of the four circumferential-to-axial intersecting areas for all RPV shell welds at MNGP. Response to RAI-2.1 : NSPM would like to clarify that all four circumferential welds will be examined.1 Per footnote 1 of Appendix 0, Category B-A, Item B1.11, approximately 2 to 3 percent of each circumferential weld shall be examined. The footnote goes on to say that welds VCBA-2, VCBB-3, and VCBB-4 will be examined with the longitudinal welds at the intersection point. VCBB-1 will be examined through the Nozzle Window N1A. As described in the alternative 1, weld VCBB-1 necessitates examination independent of the longitudinal seam. To ensure compliance with the alternative, this independently scheduled weld is the 1 of 4 (25%) depicted in Appendix 0, Category B-A, Item B 1.11. The remaining 3 of 4 (75%) circumferential welds, VCBA-2, VCBB-3, and VCBB-4, do not require independent scheduling as they will be examined during examinations of the associated longitudinal seam welds to comply with the approved alternative. Longitudinal welds (B1.12) are scheduled as shown in Appendix 0, (8 of 8, 100%) and are scheduled at the end of the 10-year Interval, which, as noted above, includes the applicable circumferential weld intersection. Scheduling and performing exams as described in Appendix ° will ensure compliance with the approved alternative for Category B-A Item B 1.11. NRC letter to NSPM, "Monticello Nuclear Generation Plant (MNGP) -Request For Relief No. 17 Regarding Examination of Reactor Pressure Vessel Shell Circumferential Welds" (T AC No. ME3526), ADAMS Accession Number ML 110200700. Page 2 of 7 RAI-2.2: Category B-K, Item B10.10, Pressure Vessel Welded Attachments -According to ASME Code Table IWB-2500-1, it is not permissible to defer examinations to the end of the interval. The examination of a larger component, such as the reactor vessel support skirt, should be performed in segments throughout the entire interval. The table lists the inspection taking place during the last period which is not permitted by IWB-2500. Please verify and explain the schedule for examination of the reactor vessel support skirt. Response to RAI-2.2: Details of Category B-K and Reactor Vessel welded attachments are provided in the Plan on page 8. NSPM has selected and scheduled the B-K, B1 0.1 0 components in accordance with the requirements of Table IWB-2500-1, with specific details provided in its Note 4. MNGP has five welded attachments for Item Number B1 0.1 O. For a single vessel, only one welded attachment shall be selected for examination. Further, the one examined shall be an attachment under continuous load during normal operation. The reactor vessel support skirt attachment weld is the only one of the five that meets this requirement. There is no requirement to perform a larger, single component in segments. Note 3 of Table IWB-2500-1 Category B-K states that "selected samples of welded attachments shall be examined each inspection intervaL" Because the skirt weld is a population of one required exam, the sample size is one each interval. The reactor vessel support skirt has not been deferred to the end of the Interval. The skirt attachment weld is the single welded attachment selected for examination in accordance with Category B-K Note 4, and it is being performed in the 3rd Period of the Interval, which is approximately 1 O-years from its previous examination in 2011, thereby meeting the requirements of IWB-2411 (a) and IWB-2420(a). NSPM finds it efficient, in alignment with ALARA principles, and in accordance with the Code to perform this single, welded attachment in one outage. Appendix D will implement Category B-K, Item B10.10 correctly, as written. Page 3 of 7 RAI-2.3: Category B-K, Items B10.20 and B10.30, and Category C-C, Items C3.20 and C3.30, Piping and Pump Welded Attachment Welds -Notes 2 and 3, respectively, state that for piping and pump welded attachments, a sample of 10 percent of the welded attachments associated with the component supports selected for examination under IWF-2510 shall be examined. For Category B-K, there are a combined 50 piping and pump welded attachments and only three (3) are listed to be inspected. Additionally, for Category C-C; there are a combined 84 piping and pump welded attachments and only 3 are listed to be inspected. These do not total to 10 percent of the welded attachments. Please explain why 10 percent of the piping and pump welded attachments for each category is not being met. Response to RAI-2.3: Details of Category B-K piping, and pump welded attachments are provided in the Plan on page 8, with Category C-C details provided in the Plan on pages 13 and 14. It should be noted that the Code requirement is not a direct 10 percent of the welded attachments. As stated in Note 5 of Table IWB-2500-1, Category B-K, and Note 5 of Table IWC-2500-1, Category C-C, it is 10 percent of the welded attachments associated with the component supports selected for examination under IWF-251 0, which results in examination of less than 10 percent of the total population of welded attachments as described below: For Category B-K, Item B10.20: There are a total of 144 piping supports; 39 of those supports have been selected for examination under IWF-2510. Of those supports selected for examination, only 12 have welded attachments; 10 percent of 12, or 1.2 rounded up to 2, would require examination. For Category B-K, Item B10.30: There are 2 reactor recirculation pumps which have 3 welded support attachments each. Per Category F-A, Item F1.40, Note 3, all the supports on one of the multiple pumps are selected for examination under IWF-2510, which includes the supports connected to the pump's 3 welded support attachments; 10 percent of 3, or 0.3 rounded up to 1, welded attachment is required to be examined. For Category C-C, Item C3.20: There are a total of 268 piping supports of which 42 piping supports (15%) have been selected for examination under IWF-2510. Of those 42 piping supports selected for examination under IWF-251 0, 14 have welded attachments; therefore 10 percent of 14, or 1.4 rounded up to 2, welded attachments on piping supports require examination. Page 4 of 7 For Category C-C, Item C3.30: There are a total of six pumps that have welded attachments (4 RHR and 2 Core Spray pumps); Per Category F-A, Item F1.40, Note 3, two of the associated pump's supports will be selected for examination under IWF-251 0, one RHR pump and one Core Spray pump. Both of the selected pump supports have welded attachments, therefore 10% of 2, or 0.2 rounded up to 1, pump welded attachment requires examination. Appendix 0 will ensure NSPM will implement Category B-K and C-C correctly at MNGP for the noted Items. Page 5 of 7 RAI-2.4: There appears to be inconsistencies in the "Examination Percentage Required" column shown in the inspection plan and schedule tables of Appendix D. For some categories (e.g. Category B-O), the licensee put the percentage of what would actually be inspected (12.5 percent) in lieu of what is actually required by ASME Code (10 percent). For other categories (e.g. Category B-P), the licensee stated the percentage required by ASME Code (100 percent). Please explain the differences between Appendix 0, the Inspection Plan and Schedule Tables, and, specifically, items in the "Examination Percentage Required" column with those required by IWB-, IWC-, IWD-, and IWF-2000 in the ASME Code. Response to RAI-2.4: NSPM would like to clarify that the tables provided in Appendix 0 of the MNGP Plan are used for scheduling the lSI components by Code Category and Item, or augmented and Owner-elected plans for implementation over the 10-year interval. It is based on the actual number of components for each category I item specific to MNGP. They are not intended to be a direct repeat-back of the IWx-2500-1 tables within ASME Section XI, but rather they are prepared such that the number of components and scheduling sequence of examinations meet the requirements of the Table IWx-2500-1, 10CFR50.55a, 10CFR50.55a alternatives, or augmented and Owner-elected plans. The lSI Plan Sections 3.0 through 7.0 provide descriptions and details of each Category and the applicable requirements. The examination percentages are met by use of the lSI Plan, including Appendix D. Appendix 0 provides each applicable Code Category or alternative Category. The table for each category consistently lists the number of applicable components, the number that require examination, and the associated percentage of those components. For each Item, the frequency is described, and the number of required exams is listed on a per-period basis. Multiple notes are provided to explain the numbers and percentages, as needed. For the example 8-0 mentioned above, Code Table IW8-2500-1, Category 8-0 requires weld exams on 10% of the peripheral CRD housings. Appendix 0, Note 1 explains that 10% of the 24 peripheral drives is 3 (rounded up). Note 2 explains that there are two welds per peripheral drive (48 welds total). Using the actual weld count that requires examination, 6 welds of 48 is 12.5% of the total count that requires examination during the 5th Interval. Therefore, examination of 12.5% of the welds equates to meeting weld exam requirements on 10% of the peripheral CRD housings for Code Table IW8-2500-1, Category 8-0. Similar examples were described above in responses to RAI 2.1,2.2, and 2.3. It can be seen that the numbers and percentages that NSPM has included in Page 6 of 7 Appendix D, including all applicable notes, are customized to provide an Interval long implementing schedule of examinations at MNGP for each Category and Item Number, or applied alternative. The lSI Plan, including Appendix D, provides the details necessary for NSPM to implement the MNGP 5th Interval lSI Program to meet the required inspection percentages for each Category and Item. Page 7 of 7