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| | number = ML13050A019 | | | number = ML13050A019 |
| | issue date = 02/15/2013 | | | issue date = 02/15/2013 |
| | title = 2013/02/15 NRR E-mail Capture - Monticello Nuclear Generating Plant - Request for Additional Information License Amendment Request to Support Fuel Storage Changes (TAC No. ME9893) | | | title = Monticello Nuclear Generating Plant - Request for Additional Information License Amendment Request to Support Fuel Storage Changes |
| | author name = Beltz T A | | | author name = Beltz T A |
| | author affiliation = NRC/NRR/DORL/LPLIII-1 | | | author affiliation = NRC/NRR/DORL/LPLIII-1 |
Revision as of 06:12, 8 February 2019
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Category:E-Mail
MONTHYEARML24284A2822024-10-0707 October 2024 Cover Email Re Monticello SLRA-3rd Round Request for Additional Information ML24254A3932024-08-26026 August 2024 SLRA - 2nd Round Request for Additional Information ML24218A2282024-08-0505 August 2024 Request for Confirmation of Information for Relief Request RR-017, Inservice Inspection Impracticality During the Fifth Ten-Year Interval ML24131A0802024-05-10010 May 2024 Final RAI for LAR to Revise TS 3.8.6, Battery Parameters, SR 3.8.6.6 ML24036A2462024-04-24024 April 2024 NRC to Fws, NRC Issuance of Draft Environmental Impact Statement for Monticello Subsequent License Renewal, Opportunity for Public Comment, and Endangered Species Act Determinations ML24092A2152024-03-27027 March 2024 Email: Requests for Information to Support Deis ML24068A0612024-03-0707 March 2024 Extension of Audit for License Amendment Request to Revise TS 3.8.6, Battery Parameters, SR 3.8.6.6 ML24064A1802024-03-0404 March 2024 Acceptance of Relief Request RR-017, Inservice Inspection (ISI) Impracticality During the Fifth Ten-Year Interval ML24036A0932024-02-0202 February 2024 Acceptance of License Amendment Request to Revise TS 5.6.5 and Update PTLR Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data ML24022A0212024-01-20020 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 ML22175A1602022-06-24024 June 2022 NRR E-mail Capture - RAI Monticello Fuel Oil Storage Tank Inspection ML22181A1962022-06-24024 June 2022 NRR E-mail Capture - Draft RAI Monticello Alternative VR-08 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 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 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 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 2024-08-05
[Table view] |
Text
1 NRR-PMDAPEm Resource From: Beltz, Terry Sent: Friday, February 15, 2013 8:07 AM To: 'Adams, Glenn D.'
Cc: 'Eckholt, Gene F.'; Hunt, Christopher; Yoder, Matthew; Wong, Emma
Subject:
Monticello Nuclear Generating Plant - Reques t for Additional Information re: License Amendment Request to Support Fuel Storage Changes (TAC No. ME9893)
Attachments:
Monticello - Fuel Storage Change LAR - Request for Additional Information (TAC No.
ME9893).docx
Dear Mr. Adams:
By letter dated October 30, 2012 (Agencywide Documents Access and Management System Accession No. ML12307A433), Northern States Power Company - Minnesota, doing business as Xcel Energy, Inc., submitted a license amendment request to revise the Monticello Nuclear Generating Plant Technical Specifications to support fuel storage system changes and a revised criticality safety analysis that addresses legacy fuel types and new fuel designs.
The U.S. Nuclear Regulatory Commission (NRC) staff in the Steam Generator Tube Integrity and Chemical Engineering Branch (ESGB) of the Office of Nuclear Reactor Regulation is currently reviewing your submittal. The ESGB 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 March 28, 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
Hearing Identifier: NRR_PMDA Email Number: 612 Mail Envelope Properties (87B1F1BDFE5A554CA9D C5EAA75EB6D0DC63D87391B)
Subject:
Monticello Nuclear Generating Plant - Request for Additional Information re: License Amendment Request to Support Fuel Storage Changes (TAC No. ME9893) Sent Date: 2/15/2013 8:07:08 AM Received Date: 2/15/2013 8:07:00 AM From: Beltz, Terry Created By: Terry.Beltz@nrc.gov Recipients: "'Eckholt, Gene F.'" <Eugene.Eckholt@xenuclear.com> Tracking Status: None "Hunt, Christopher" <Christopher.Hunt@nrc.gov> Tracking Status: None "Yoder, Matthew" <Matthew.Yoder@nrc.gov>
Tracking Status: None "Wong, Emma" <Emma.Wong@nrc.gov> Tracking Status: None
"'Adams, Glenn D.'" <Glenn.Adams@xenuclear.com> Tracking Status: None
Post Office: HQCLSTR01.nrc.gov Files Size Date & Time MESSAGE 1441 2/15/2013 8:07:00 AM Monticello - Fuel Storage Change LAR - Request for Additional Information (TAC No. ME9893).docx 23140 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received:
REQUEST FOR ADDITIONAL INFORMATION REGARDING MONTICELLO NUCLEAR GENERATING PLANT LICENSE AMENDMENT REQUEST SUPPORTING SPENT FUEL STORAGE CHANGES SPENT FUEL POOL NEUTRON ABSORBING MATERIAL NORTHERN STATES POWER COMPANY - MINNESOTA MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263 By letter dated October 30, 2012 (Agencywide Documents Access and Management System Accession No. ML12307A433), Northern States Power Company - Minnesota, doing business as Xcel Energy, Inc., submitted a license amendment request to revise the Monticello Nuclear Generating Plant (MNGP) Technical Specifications to support fuel storage system changes and a revised criticality safety analysis that addresses legacy fuel types and new fuel designs. The U.S. Nuclear Regulatory Commission staff in the Steam Generator Tube Integrity and Chemical Engineering Branch of the Office of Nuclear Reactor Regulation has determined that additional information is required to complete its review. The NRC staff requests the following information:
- 1. When was the last time a neutron attenuation test was performed (in-situ or coupon) for the Boral in the MNGP spent fuel pool?
- 2. When is the next planned neutron attenuation test at MNGP?
- 3. Your application states that Boral integrity is managed using the Water Chemistry Aging Management Program and One-time Inspection Program as described in NUREG-1865. While the use of Industry and historical plant operating experience is useful for informing a neutron absorbing material aging management program, it is not an adequate replacement for physical testing. Additionally, your Water Chemistry Aging Management Program does not include neutron attenuation testing. The concern is how MNGP will continue to monitor and mitigate any degradation or deformation of your Boral so that it will not reduce the neutron attenuation capability of the material in the future.
- a. Discuss whether you plan on performing in-situ neutron attenuation testing on the Boral panels installed in the spent fuel pool? If so, provide the frequency, acceptance criteria, and proposed corrective actions should the acceptance criteria not be met after a given test. b. Alternatively, if in-situ testing will not be performed, describe the method you will use to detect any degradation, deformation, or reduction in neutron attenuation capability of your Boral, and what actions will be taken to monitor and mitigate future degradation, deformation, or reduction in neutron attenuation capability.