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Category:Letter
MONTHYEARIR 05000263/20240022024-08-14014 August 2024 Integrated Inspection Report 05000263/2024002 ML24218A2282024-08-0505 August 2024 Request for Confirmation of Information for Relief Request RR-017, Inservice Inspection Impracticality During the Fifth Ten-Year Interval ML24208A1502024-07-26026 July 2024 Independent Spent Fuel Storage Installation - Submittal of Quality Assurance Topical Report (NSPM-1) ML24215A2992024-07-23023 July 2024 Minnesota State Historic Preservation Office Comments on Monticello SLR Draft EIS ML24198A2372024-07-18018 July 2024 Information Request to Support Upcoming Biennial Problem Identification and Resolution (Pi&R) Inspection at Monticello Nuclear Generating Plant L-MT-24-022, – Preparation and Scheduling of Operator Licensing Examinations2024-07-0909 July 2024 – Preparation and Scheduling of Operator Licensing Examinations ML24164A2402024-06-10010 June 2024 Minnesota State Historic Preservation Office- Comments on Draft Monticello SLR Draft EIS L-MT-24-019, Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii)2024-06-10010 June 2024 Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii) L-MT-24-017, Response to Request for Additional Information Regarding License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 (EPID-L-2023-LLA-01602024-06-0404 June 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 (EPID-L-2023-LLA-0160 ML24137A2792024-06-0303 June 2024 Audit Summary for License Amendment Request to Revise Technical Specification 3.8.6, Battery Parameters, Surveillance Requirement 3.8.6.6 IR 05000263/20244012024-05-30030 May 2024 Public - Monticello Nuclear Generating Plant - Cyber Security Inspection Report 05000263/2024401 ML24141A1292024-05-22022 May 2024 Northern States Power Company - Use of Encryption Software for Electronic Transmission of Safeguards Information ML24141A1782024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection L-MT-24-015, Response to Request for Additional Information - Alternative Request VR-09 for OMN-172024-05-16016 May 2024 Response to Request for Additional Information - Alternative Request VR-09 for OMN-17 ML24135A1902024-05-14014 May 2024 Submittal of 2023 Annual Radioactive Effluent Release Report L-MT-24-013, 2023 Annual Radiological Environmental Operating Report2024-05-14014 May 2024 2023 Annual Radiological Environmental Operating Report IR 05000263/20240102024-05-13013 May 2024 Age-Related Degrading Inspection Report 05000263/2024010 ML24128A0042024-05-0909 May 2024 Letter to Minnesota State Historic Preservation Office- Section 106 Consultation Regarding the Monticello Nuclear Generating Plant Subsequent License Renewal Application ML24127A1472024-05-0909 May 2024 Letter to Mille Lacs Band- Section 106 Consultation Regarding the Monticello Nuclear Generating Plant Subsequent License Renew. Application L-MT-24-016, 2023 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)2024-05-0808 May 2024 2023 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP) IR 05000263/20240012024-04-29029 April 2024 Plan - Integrated Inspection Report 05000263/2024001 ML24115A2952024-04-25025 April 2024 Sec106 Tribal, Kakkak, Gena-Menominee Indian Tribe of Wisconsin ML24115A3022024-04-25025 April 2024 Sec106 Tribal, Stiffarm, Jeffrey-Fort Belknap Indian Community ML24115A2992024-04-25025 April 2024 Sec106 Tribal, Renville, J. Garret-Sisseton Wahpeton Oyate of the Lake Travers Reservation ML24115A3032024-04-25025 April 2024 Sec106 Tribal, Taylor, Louis-Lac Courte Oreilles Band of Lake Superior Chippewa Indians ML24115A2962024-04-25025 April 2024 Sec106 Tribal, Larsen, Robert-Lower Sioux Indian Community ML24115A3002024-04-25025 April 2024 Sec106 Tribal, Rhodd, Timothy-Iowa Tribe of Kansas and Nebraska ML24115A2892024-04-25025 April 2024 Sec106 Tribal, Fowler, Thomas-St. Croix Chippewa of Wisconsin ML24115A2922024-04-25025 April 2024 Sec106 Tribal, Jensvold, Kevin-Upper Sioux Community ML24115A2902024-04-25025 April 2024 Sec106 Tribal, Jackson-Street, Lonna-Spirit Lake Nation ML24115A2882024-04-25025 April 2024 Sec106 Tribal, Fairbanks, Michael-White Earth Nation.Docx ML24115A2972024-04-25025 April 2024 Sec106 Tribal, Miller, Cole-Shakopee Mdewakanton Sioux Community ML24115A2982024-04-25025 April 2024 Sec106 Tribal, Reider, Anthony-Flandreau Santee Sioux Tribe ML24115A2932024-04-25025 April 2024 Sec106 Tribal, Johnson, Grant-Prairie Island Indian Community ML24115A2912024-04-25025 April 2024 Sec106 Tribal, Jacskon, Sr., Faron-Leech Lake Band of Ojibwe ML24115A3072024-04-25025 April 2024 Sec106 Tribal, Williams, Jr., James-Lac Vieux Desert Band of Lake Superior Chippewa Indians ML24115A3052024-04-25025 April 2024 Sec106 Tribal, Vanzile, Jr., Robert-Sokaogon Chippewa Community ML24115A2872024-04-25025 April 2024 Sec106 Tribal, Dupuis, Kevin-Fond Du Lac Band of Lake Superior Chippewa ML24115A3062024-04-25025 April 2024 Sec106 Tribal, Wassana, Reggie-Cheyenne and Arapaho Tribes ML24115A3012024-04-25025 April 2024 Sec106 Tribal, Seki, Darrell-Red Lake Nation ML24115A2942024-04-25025 April 2024 Sec106 Tribal, Johnson, John-Lac Du Flambeau Band of Lake Superior Chippewa Indians ML24115A2792024-04-24024 April 2024 Sec106 Tribal, Blaker, Doreen-Keweenaw Bay Indian Community ML24115A2862024-04-24024 April 2024 Sec106 Tribal, Deschampe, Robert-Grand Portage Band of Lake Superior Chippewa ML24115A2812024-04-24024 April 2024 Sec106 Tribal, Boyd, NIcole-Red Cliff Band of Lake Superior Chippewa ML24115A2782024-04-24024 April 2024 Sec106 Tribal, Azure, Jamie-Turtle Mountain Band of Chippewa Indians ML24115A2842024-04-24024 April 2024 Sec106 Tribal, Chavers, Catherine-Boise Forte Band of Chippewa ML24115A2822024-04-24024 April 2024 Sec106 Tribal, Chavers, Catherine J-Minnesota Chippewa Tribe ML24115A2852024-04-24024 April 2024 Sec106 Tribal, Denney, Alonzo-Santee Sioux Nation ML24115A2802024-04-24024 April 2024 Sec106 Tribal, Blanchard, Robert-Bad River Band of Lake Superior L-MT-24-004, Submittal of 10 CFR 72.48 Report for Monticello Nuclear Generating Plant (MNGP)2024-04-17017 April 2024 Submittal of 10 CFR 72.48 Report for Monticello Nuclear Generating Plant (MNGP) 2024-08-05
[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] |
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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 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 3 rd 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 5 th 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 5 th Interval lSI Program to meet the required inspection percentages for each Category and Item. Page 7 of 7