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| | number = ML073381315 | | | number = ML073381315 |
| | issue date = 12/03/2007 | | | issue date = 12/03/2007 |
| | title = Monticello - Draft RAI for Relief Request No. 15 (TAC MD6854) | | | title = Monticello - Draft RAI for Relief Request No. 15 |
| | author name = Tam P S | | | author name = Tam P S |
| | author affiliation = NRC/NRR/ADRO/DORL/LPLIII-1 | | | author affiliation = NRC/NRR/ADRO/DORL/LPLIII-1 |
Revision as of 06:44, 10 February 2019
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Category:E-Mail
MONTHYEARML24022A0212024-01-20020 January 2024 NRR E-mail Capture - Monticello - Request for Additional Information ISI RR-002 Alternative to Use IWB-2500(f) ML23353A0742023-12-19019 December 2023 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Proposed Alternative VR-09, Modifications to OMN-17 ML23348A3462023-12-14014 December 2023 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of License Amendment Request to Revise TS 3.8.6, Battery Parameters, SR 3.8.6.6 ML23268A0292023-09-20020 September 2023 SLRA - Requests for Confirmation of Information - Set 2 - Email from Marieliz Johnson to Shawn Hafen ML23249A2092023-09-0606 September 2023 NRR E-mail Capture - Action: Opportunity to Review and Comment on a New NRC Information Collection, 10 CFR Part 50.55a, Codes and Standards (3150-XXXX) ML23248A3462023-09-0505 September 2023 NRR E-mail Capture - Request for Additional Information for Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant - Decommissioning Funding Status Reports ML23237A4822023-08-25025 August 2023 SLRA - Request for Additional Information - Set 3 - Email from Marieliz Johnson to Shawn Hafen ML23228A1212023-08-16016 August 2023 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Alternative Request VR-11 for MO-2397 ML23227A2182023-08-15015 August 2023 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Alternative Request RR-002 to Use IWB-2500(f) ML23219A1072023-08-0707 August 2023 SLRA - Requests for Additional Information - Set 2 - Email from Marieliz Johnson to Shawn Hafen ML23200A3502023-07-19019 July 2023 SLRA - Requests for Additional Information - Set 1 - Email from Marieliz Johnson to Christopher Domingos ML23172A1122023-06-21021 June 2023 SLRA - Requests for Confirmation of Information - Set 1 - Email from Marieliz Johnson to Christopher Domingos ML23054A3322023-02-23023 February 2023 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Relief Request to Use Later Edition of ASME BPV Code, Section XI, for ISI Program Code of Record ML23053A1362023-02-13013 February 2023 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Relief Request to Use Later Edition of ASME BPV Code, Section XI, for Cisi Program ML23017A2222023-01-13013 January 2023 Verbal Authorization of Proposed Alternative PR-08 Regarding Inservice Testing Requirements of Certain High Pressure Coolant Injection System Components (EPID L-2022-LLR-0088) (Email) ML23004A1982023-01-0404 January 2023 NRR E-mail Capture - Draft Request for Additional Information Monticello Nuclear Generating Plant Request Pr 08, HPCI Pump Quarterly Testing ML23012A2102022-07-26026 July 2022 Letter Submitting Monticello Outline Package ML22181A1962022-06-24024 June 2022 NRR E-mail Capture - Draft RAI Monticello Alternative VR-08 ML22175A1602022-06-24024 June 2022 NRR E-mail Capture - RAI Monticello Fuel Oil Storage Tank Inspection ML22131A2652022-05-11011 May 2022 NRR E-mail Capture - Request for Additional Information Xcel Energy Amendment Request to Create a Common Eplan and EOF for Monticello and Prairie Island ML22123A2822022-05-0303 May 2022 NRR E-mail Capture - Request for Additional Information Monticello Alternative VR-10, EFCV Testing Frequency ML22101A0712022-04-11011 April 2022 NRR E-mail Capture - Monticello - Acceptance of Requested Licensing Action License Amendment Request to Revise TS 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray Header and Nozzle Surveillance Frequency ML22089A1302022-03-30030 March 2022 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Alternative Related Excess Flow Check Valve Testing Frequency ML22082A1812022-03-23023 March 2022 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of VR-08 Alternative to Adopt ASME OM Code Case OMN-28 ML22075A2612022-03-16016 March 2022 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of VR-07 Alternative Related to MOV Testing Per ASME OM Code Case OMN-26 ML22067A2032022-03-0808 March 2022 Audit Plan to Support Review of an Amendment to Transition to Atrium 11 Fuel (Redacted) ML22011A0642022-01-11011 January 2022 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Licensing Action License Amendment Request to Support Diesel Generator Fuel Oil Storage Tank Inspection ML22005A3612022-01-0505 January 2022 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Pump Vibration Testing Per ASME OM Code Case OMN-22 ML21347A0082021-12-10010 December 2021 NRR E-mail Capture - Monticello and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested License Amendment Standard Emergency Plan and Consolidated Emergency Operations Facility ML21330A0382021-11-18018 November 2021 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related RHR and RHRSW Pump Testing ML21286A7882021-10-0606 October 2021 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Residual Heat Removal Heat Exchanger Flow Control Valve Stroke Timing ML21256A1892021-09-13013 September 2021 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Testing the Control Rod Drive Scram Discharge Header Check Valves ML21256A1862021-09-13013 September 2021 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to HPCI and RCIC Pump Testing ML21256A1882021-09-13013 September 2021 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Vibration Testing Range for the Sblc Pumps ML21253A2002021-09-10010 September 2021 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Pressure Isolation Valve Testing ML21252A0132021-08-31031 August 2021 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Licensing Action License Amendment Request to Adopt Advanced Framatome Methodologies ML21130A3022021-05-0707 May 2021 Initial and Final Written 10 CFR 21 Notification for GE Hitachi Numac Prnm System ML21110A7042021-04-20020 April 2021 Response: Monticello Nuclear Plant Outage - Covid Risk to On-Site Employees ML21084A2522021-03-24024 March 2021 NRR E-mail Capture - Revised Review Schedule for Monticello TSTF-505 (EPID L-20200LLA-0062) ML21068A2772021-03-0909 March 2021 NRR E-mail Capture - Monticello TSTF-505, Request for Additional Information ML20343A1292020-12-0808 December 2020 NRR E-mail Capture - Request for Additional Information ML20342A1782020-12-0707 December 2020 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Licensing Action License Amendment Request to Adopt TSTF-564 Safety Limit MCPR ML20302A1972020-10-26026 October 2020 NRR E-mail Capture - Monticello Request for Additional Information TSTF-505 License Amendment Request ML20289A1072020-10-0606 October 2020 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Licensing Action License Amendment Request to Adopt TSTF-582 Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements (EPID L-2020-LLA-0209 ML20191A0252020-07-0101 July 2020 NRR E-mail Capture - Draft Request for Additional Information Monticello Alternative Request RR-016 Related to H8, H9, and H 10 Weld Examinations ML20120A0272020-04-28028 April 2020 NRR E-mail Capture - Request for Additional Information Monticello Long Term Steam Dryer Inspection Plan ML20099F1292020-04-0606 April 2020 E-mail to Licensee for Monticello Lr Phase 4 RFI ML20077L4632020-03-17017 March 2020 NRR E-mail Capture - Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant, Units 1 and 2 -Acceptance of Requested Licensing Action Request to Adopt TSTF-529 ML20064C5352020-03-0404 March 2020 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Revise the Previously Authorized Alternative in RR-008 for the H8 and H9 Welds 2024-01-20
[Table view] |
Text
From: Peter Tam To: Arias, Jesus; Loeffler, Rick; tmblake@nmcco.com Date: 12/3/2007 1:31:07 PM
Subject:
Monticello - Draft RAI for Relief Request No.15 (TAC MD6854)
Rick, Jay:
By letter dated September 26, 2007, Nuclear Management Company requested relief from certain examination coverage requirements of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, for the Monticello Nuclear Generating Plant. Our reviewer, John Tsao, has written the following draft RAI questions. We would like to discuss these with you in a conference call in the near future. However, with or without the conference call, I plan to formally issue the questions in a formal RAI in early January 2008. .
- 1. Discuss the applicable edition or addenda of the ASME Code,Section XI, Appendix VIII, for the ultrasonic examination of the subject welds during the 2007 refueling outage and for the remaining fourth 10-year inservice inspection (ISI) interval.
- 2. Discuss the future inspection frequency of the subject welds in the fourth ISI interval.
- 3. On page 4 of Request No. 15, the licensee discussed the UT inspection of the subject welds during the 2007 outage without providing the previous history of the ultrasonic examinations. Discuss the history of volumetric examinations of the subject welds, including specific year and during which ISI interval, inspection results, and examination coverage.
Discuss whether relief was requested for the examination coverage of the subject welds in the previous 10-year ISI intervals. If not, discuss why the 100% examination coverage was achieved in the previous examination(s) but not in the 2007 refueling outage.
- 4. On page 5 of Request No.15, the licensee stated that the materials for subject components are A508 Class II nozzle forgings welded to A533, Class I vessel shell plate.
However, the material specifications of the welds and associated piping were not provided.
Discuss material specifications for the following components: welds, pipes, safe ends, and butter (if applicable).
- 5. On page 5 of Request No. 15, the licensee stated that a review of operating experience within the nuclear industry did not reveal any instance of cracking in this [the nozzle] location and the type of weldment. The staff notes that feedwater nozzles to the reactor vessel have experienced cracking as discussed in the NRC report, NUREG-0619, ABWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking,@ November 1980. Discuss whether the feedwater nozzles in Monticello have experienced cracking and whether feedwater nozzle inspection frequency follows NUREG-0619.
- 6. In Enclosure 2, Table A, of the September 26, 2007, submittal, the licensee calculated various percentages of examination coverage obtained for each of the five welds. The staff calculated the percentages of examination coverage of the subject welds using the diagrams in of the submittal. However, the staff was not able to verify the percentages of coverage as shown in Table A. Provide detailed calculations of the percentages of coverage.
It is not clear from the diagrams in Enclosure 3 of the September 26, 2007, submittal whether the unexamined volume is in the reactor vessel nozzles, the welds, butter, or safe ends. Please provide the axial dimensions for the weld, piping, and safe end. Also identify the interface line among the weld, nozzle, safe end, and pipe.
This e-mail aims solely to prepare you and others for the proposed conference call. It does not convey a formal NRC staff position, and does not formally request for information.
Peter S. Tam, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
e-mail: pst@nrc.gov Tel.: 301-415-1451
CC: Chawla, Mahesh; Terence Chan; Tsao, John
Mail Envelope Properties (47544B6B.C28 : 12 : 35330)
Subject:
Monticello - Draft RAI for Relief Request No.15 (TAC MD6854)
Creation Date 12/3/2007 1:31:07 PM From: Peter Tam Created By: PST@nrc.gov Recipients Action Date & Time nmcco.com Transferred 12/3/2007 1:31:33 PM Jesus.Arias (Jesus Arias)
Richard.Loeffler (Rick Loeffler) tmblake (tmblake@nmcco.com)
nrc.gov OWGWPO03.HQGWDO01 Delivered 12/3/2007 1:31:15 PM MLC CC (Mahesh Chawla) Opened 12/3/2007 2:03:18 PM TLC CC (Terence Chan)
nrc.gov TWGWPO02.HQGWDO01 Delivered 12/3/2007 1:31:07 PM JCT CC (John Tsao) Opened 12/3/2007 1:56:15 PM Post Office Delivered Route nmcco.com OWGWPO03.HQGWDO01 12/3/2007 1:31:15 PM nrc.gov TWGWPO02.HQGWDO01 12/3/2007 1:31:07 PM nrc.gov Files Size Date & Time MESSAGE 5088 12/3/2007 1:31:07 PM Options Auto Delete: No Expiration Date: None Notify Recipients: Yes Priority: Standard ReplyRequested: No Return Notification: None Concealed
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No Security: Standard To Be Delivered: Immediate Status Tracking: Delivered & Opened