ML13099A275
| ML13099A275 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 04/09/2013 |
| From: | Beltz T Plant Licensing Branch III |
| To: | Loeffler R Northern States Power Co |
| References | |
| TAC ME8186 | |
| Download: ML13099A275 (6) | |
Text
NRR-PMDAPEm Resource From: Beltz, Terry Sent: Tuesday, April 09, 2013 7:52 AM To: Loeffler, Richard A.
Cc: gene.eckholt@xenuclear.com; Rippy, L. Randal; Carlson, Robert; McLellan, Thomas; Cheruvenki, Ganesh; Hoffman, Keith
Subject:
Monticello Nuclear Generating Plant - Request for Additional Information re: Fifth 10-Year Inservice Inspection Program Plan Review (TAC No. ME8186)
Attachments: Monticello - Requests for Additional Information (TAC No. ME8186).docx
Dear Mr. Loeffler:
By letter dated February 28, 2012 (Agencywide Documents Access and Management System Accession No. ML12060A298), Northern States Power Company - Minnesota, doing business as Xcel Energy, Inc., submitted its fifth 10-year Inservice Inspection (ISI) Program Plan in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 50.55a, for the Monticello Nuclear Generating Plant.
The U.S. Nuclear Regulatory Commission (NRC) staff in the Vessels & Internals Integrity Branch and the Piping and NDE Branch of the Office of Nuclear Reactor Regulation is currently reviewing your submittal. The NRC staff has determined that additional information is required to complete its review. The draft request for additional information (RAI) is attached.
You may accept this draft RAI as a formal Request for Additional Information and respond to the questions by May 10, 2013. Alternatively, you may request to discuss the contents of this RAI with the NRC staff in a conference call, including any change to the proposed response date.
Please let me know if you have any questions or concerns.
Sincerely, Terry A. Beltz, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation (301) 415-3049 Terry.Beltz@nrc.gov 1
Hearing Identifier: NRR_PMDA Email Number: 660 Mail Envelope Properties (Terry.Beltz@nrc.gov20130409075200)
Subject:
Monticello Nuclear Generating Plant - Request for Additional Information re:
Fifth 10-Year Inservice Inspection Program Plan Review (TAC No. ME8186)
Sent Date: 4/9/2013 7:52:21 AM Received Date: 4/9/2013 7:52:00 AM From: Beltz, Terry Created By: Terry.Beltz@nrc.gov Recipients:
"gene.eckholt@xenuclear.com" <gene.eckholt@xenuclear.com>
Tracking Status: None "Rippy, L. Randal" <Randal.Rippy@xenuclear.com>
Tracking Status: None "Carlson, Robert" <Robert.Carlson@nrc.gov>
Tracking Status: None "McLellan, Thomas" <Thomas.McLellan@nrc.gov>
Tracking Status: None "Cheruvenki, Ganesh" <Ganesh.Cheruvenki@nrc.gov>
Tracking Status: None "Hoffman, Keith" <Keith.Hoffman@nrc.gov>
Tracking Status: None "Loeffler, Richard A." <Richard.Loeffler@xenuclear.com>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 1418 4/9/2013 7:52:00 AM image001.gif 3939 Monticello - Requests for Additional Information (TAC No. ME8186).docx 36640 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
Page 1 of 1 file://c:\EMailCapture\NRR_PMDA\660\attch1.gif 4/9/2013
REQUEST FOR ADDITIONAL INFORMATION FROM THE OFFICE OF NUCLEAR REACTOR REGULATION REGARDING REVIEW OF THE FIFTH 10-YEAR INSERVICE INSPECTION PROGRAM PLAN NORTHERN STATES POWER COMPANY - MINNESOTA MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263 TAC NO. ME8186 INTRODUCTION By letter to the U.S. Nuclear Regulatory Commission (NRC) dated February 28, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12060A298), Northern States Power Company - Minnesota, doing business as Xcel Energy, Inc. (the licensee), submitted its fifth 10-year Inservice Inspection (ISI) Program Plan in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 50.55a, for the Monticello Nuclear Generating Plant (MNGP). The licensee requested that the NRC staff review its proposed fifth 10-year ISI Program Plan for MNGP to the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code),Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, inspection requirements. The applicable ASME Code,Section XI code of record for the MNGP Fifth 10-Year ISI Program Plan is the 2007 Edition through the 2008 Addenda.
The licensees risk-informed ISI program plan will be submitted at a later date and will be reviewed by the NRC staff in a separate report.
The NRC staff has reviewed the information submitted by the licensee and, based on this review, determined that the following information is required to complete the evaluation.
REQUEST FOR ADDITIONAL INFORMATION
- 1. In the licensees submittal, Appendix A lists the ASME Code B&PV Code Cases adopted for inservice inspection and related NDE activities for the fifth 10-year inservice inspection interval. ASME Code Cases that the NRC has approved for use are listed in RG 1.147, Revision 16 Inservice Inspection Code Case Acceptability, Division 1, with any additional conditions the NRC may have imposed. When used, these ASME Code Cases must be implemented in their entirety. Published ASME Code Cases awaiting approval and subsequent listing in RG 1.147 may be adopted only if the applicant requests, and the NRC authorizes, an alternative in accordance with 10 CFR 50.55a(a)(3)
Enclosure
The licensee listed 25 ASME Code Cases in the fourth 10-year inservice inspection program plan. Only five of these code cases are currently in the fifth 10-year inservice inspection program plan. Please discuss and explain why other ASME Code Cases are not being used in the fifth 10-year inservice inspection interval. For example, ASME Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, is one of the code cases that is listed in the forth 10-year inservice inspection interval, but not in the fifth 10-year inservice inspection interval.
Please confirm that all ASME Code Cases to be used in the fifth 10-tear inservice inspection interval have been listed in Appendix A, Tables A.1-1, A.1-2, or A.1-3.
- 2. In Section 3.0 and Appendix D of the submittal, the licensee stated that examinations of ASME Code 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.
- 3. Appendix D, Inspection Plan and Schedule Tables 3.1 ASME Code,Section XI, 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 allows for all welds to 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 10-year inservice inspection program plan.
Please explain where the licensee obtained the requirement for examining only 25 percent of the four circumferential shell welds listed.
3.2 ASME Code,Section XI, Category B-K, Item B10.10, Pressure Vessels 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 done in segments throughout the entire interval. The table lists the inspection taking place during the last period which is not permitted.
Please verify and explain the schedule for examination of the reactor vessel support skirt.
3.3 ASME, Code,Section XI, 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 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.
3.4 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, for example ASME Code,Section XI, 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, for example Category B-P, the licensee stated the percentage required by ASME Code (100 percent).
Please resubmit Appendix D, Inspection Plan and Schedule Tables, with the Examination Percentage Required column consistent or explain why it is not consistent with what is required by ASME Code. Also, ensure and state that the required inspection percentages are being completed.
- 4. Editorial comment: Item 12 at the top of page 4 in the Introduction section of the licensees submittal should be 10 CFR 50.55a(b)(2)(xxix). The (2) is missing from the submittal.