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Category:E-Mail
MONTHYEARML24304B0562024-10-30030 October 2024 Acceptance of LAR to Revise TS to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements ML24284A2822024-10-0707 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 ML24239A3722024-08-26026 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 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) 2024-08-05
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Text
NRR-PMDAPEm Resource From: Beltz, Terry Sent: Tuesday, May 27, 2014 10:00 AM To: Loeffler, Richard A.
Cc: Eckholt, Gene F. (Eugene.Eckholt@xenuclear.com); Carlson, Robert; Razzaque, Muhammad; Panicker, Mathew
Subject:
Monticello Nuclear Generating Plant - Draft Requests for Additional Information re:
Amendment to Reduce Reactor Steam Dome Pressure Safety Limit (TAC No. MF1054)
Dear Mr. Loeffler:
By letter dated March 11, 2013 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML13074A811), Northern States Power Company - Minnesota (NSPM) submitted a license amendment request for the Monticello Nuclear Generating Plant. The proposed amendment would reduce the reactor steam dome pressure specified within Technical Specification 2.1.1, Reactor Core SLs [Safety Limits]. This proposed change to the specified steam dome pressure is a plant-specific resolution to a 10 CFR Part 21 issue.
The U.S. Nuclear Regulatory Commission (NRC) staff in the Reactor Systems Branch of the Office of Nuclear Reactor Regulation has determined that additional information is needed to complete its review. The draft requests for additional information (RAIs) are provided below.
You may accept this as a formal request for additional information and respond to the questions by June 27, 2014. Alternatively, you may request to discuss the content of the RAIs with the NRC staff in a conference call, including any change to the proposed response date.
Please contact me if you have any additional questions or concerns.
Sincerely, TERRY A. BELTZ, SENIOR PROJECT MANAGER Office of Nuclear Reactor Regulation Division of Operating Reactor Licensing Plant Licensing Branch III-1 (301) 415-3049 O-8E8 Terry.Beltz@nrc.gov OFFICE OF NUCLEAR REACTOR REGULATION REACTOR SYSTEMS BRANCH (SRXB)
REQUEST FOR ADDITIONAL INFORMATION (RAI)
REGARDING LICENSE AMENDMENT REQUEST TO REDUCE THE REACTOR STEAM DOME PRESSURE VALUE 1
AS SPECIFIED IN THE REACTOR CORE SAFETY LIMITS MONTICELLO NUCLEAR GENERATING PLANT (MNGP)
DOCKET NO. 50-263 (TAC NO. MF1054)
SRXB RAI # 1 Since the proposed approach for MNGP is a plant-specific resolution of the 10 CFR Part 21 issue as discussed in your submittal (Reference 1), please provide the following additional information:
- 1. Discuss how Northern States Power Company - Minnesota (NSPM) plans to address the Part 21 issue when the MNGP core may be a mixed-core design consisting of more than one fuel design whose critical power ratio (CPR) correlations have different lower bound pressures.
- 2. Describe the current MNGP core design, including the fuel types in use.
When the MNGP core transitions to a fuel design whose lower bound pressure for the CPR correlation is higher (or lower) than that of the current CPR correlation, discuss how NSPM intends to address the change. The discussion should include whether it will require a Technical Specification (TS) license amendment to address the change.
SRXB RAI # 2 In Reference 1, page 2 of 15, it was stated, While this condition had been determined by GE to not involve an actual safety hazard, the potential for violation of a Reactor Core Safety Limit had been identified and restoration to comply with the safety limit is required.
The U.S. Nuclear Regulatory Commission (NRC) staff understands that although this issue may not be an actual safety hazard, by lowering the dome pressure in TS 2.1.1 from the current value of 785 psig to the proposed value of 686 psig may prevent unnecessary reactor shutdowns as required by TS 2.2.2 if dome pressure goes below 785 psig during a transient.
Please discuss if there are any other operational and/or safety benefits of lowering dome pressure from the current value of 785 psig to 686 psig.
REFERENCE
- 1. Letter from John C. Grubb (NSPM) to the NRC Document Control Desk re: License Amendment Request: Reduce the Reactor Steam Dome Pressure Specified in the Reactor Core Safety Limits, dated March 11, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13074A811).
2
Hearing Identifier: NRR_PMDA Email Number: 1392 Mail Envelope Properties (Terry.Beltz@nrc.gov20140527095900)
Subject:
Monticello Nuclear Generating Plant - Draft Requests for Additional Information re: Amendment to Reduce Reactor Steam Dome Pressure Safety Limit (TAC No. MF1054)
Sent Date: 5/27/2014 9:59:34 AM Received Date: 5/27/2014 9:59:00 AM From: Beltz, Terry Created By: Terry.Beltz@nrc.gov Recipients:
"Eckholt, Gene F. (Eugene.Eckholt@xenuclear.com)" <Eugene.Eckholt@xenuclear.com>
Tracking Status: None "Carlson, Robert" <Robert.Carlson@nrc.gov>
Tracking Status: None "Razzaque, Muhammad" <Muhammad.Razzaque@nrc.gov>
Tracking Status: None "Panicker, Mathew" <Mathew.Panicker@nrc.gov>
Tracking Status: None "Loeffler, Richard A." <Richard.Loeffler@xenuclear.com>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 3954 5/27/2014 9:59:00 AM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received: ZZZ