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| | {{#Wiki_filter: Accession No. ML12178A557 From: Tam, Peter Sent: Tuesday, June 26, 2012 1:58 PM To: Loeffler, Richard A.; 'Rippy, L. Randal'; 'Kissinger, Peter W.' Cc: Wallace, Jay; Sydnor, Christopher; Alley, David Subject: Monticello - Draft RAI on Relief Request RR-005 (TAC ME8071) Rick, Randy: By letter dated February 28, 2012, Northern States Power Company - Minnesota submitted request for alternative RR-005, "Alternative Requirements for BWR Class 1 System Leakage Test Pressure Following Repair/Replacement Activities, Section XI, Division 1," (Accession No. ML12059A403). The licensee proposed to use the provisions of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) Case N-795, with conditions, to perform the system leakage test and associated VT-2 examination following repair/replacement activities. Our technical review branch has developed the following information in order to complete its review: 1. The NRC staff notes that alternative pressure requirements for leak testing of bolted joints has been authorized for specific cases (e.g., see Accession No. ML12025A010), but is unaware of generic authorization for alternate leak testing pressure requirements for welded repairs. The NRC staff acknowledges that authorization of the proposed alternative for welded repairs could be supported on a case-by-case basis, but can envision cases, such as when the segment being tested is isolable and can be independently pressurized, where determination of hardship to support the relief may not be possible. In addition, the NRC staff questions whether pressurization of welded repairs to pressures less than that corresponding to 100 percent of normal operating pressure provides reasonable assurance of the structural integrity of the welded repair. Please provide justification for the generic use of the proposed alternative pressure requirement for leak testing of welded repairs and demonstrate that the structural integrity of welded repairs is ensured. 2. Please describe the methods for attaining 100% of normal operating pressure required by IWB-5221(a) in order to perform the Code-compliant system leakage test and describe the hardship or unusual difficulty associated with each. 3. Please describe the method for attaining 90% of normal operating pressure in order to perform the proposed alternative leakage test. 4. The Basis for Use of the proposed alternative states that the core decay heat during a maintenance outage is much higher than that after a refueling outage, and that the heat load is difficult to control once shutdown cooling is removed from service. a. What are the temperature and pressure limits for use of shutdown cooling? b. Given these limits, please explain why pressurization to 90 percent normal operating pressure, with a hold for up to 8 hours, is possible but pressurizing to 100 percent normal operating pressure is unusually difficult. |
| | You may choose to accept this e-mail as transmitting a formal RAI, and formally respond to the above questions within 45 days of receipt of this e-mail. Alternatively, you may request to hold a conference call with our review staff, during which we discuss the disposition of the above draft questions and a date for formal response. Peter S. Tam Senior Project Manager (for D. C. Cook and Monticello) Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Tel. 301-415-1451 |
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Revision as of 13:25, 28 March 2018
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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
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24290A0452024-10-0707 October 2024 Attachment - Monticello SLRA - 3rd Round Request for Additional Information 3rd Round RAI ML24254A4542024-08-26026 August 2024 RAI-holding Ponds ML24218A2282024-08-0505 August 2024 Request for Confirmation of Information for Relief Request RR-017, Inservice Inspection Impracticality During the Fifth Ten-Year Interval ML24198A2372024-07-18018 July 2024 Information Request to Support Upcoming Biennial Problem Identification and Resolution (Pi&R) Inspection at Monticello Nuclear Generating Plant ML24141A1782024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML24131A0802024-05-10010 May 2024 Final RAI for LAR to Revise TS 3.8.6, Battery Parameters, SR 3.8.6.6 ML24107A1462024-04-15015 April 2024 Final Request for Additional Information Re VR-09 ML24040A0482024-02-12012 February 2024 – Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000263/2024010 ML24022A0212024-01-20020 January 2024 NRR E-mail Capture - Monticello - Request for Additional Information ISI RR-002 Alternative to Use IWB-2500(f) ML23268A0252023-09-25025 September 2023 SLRA - Requests for Confirmation of Information - Set 2 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 ML23237A4832023-08-25025 August 2023 SLRA - Request for Additional Information - Set 3 ML23219A1072023-08-0707 August 2023 SLRA - Requests for Additional Information - Set 2 - Email from Marieliz Johnson to Shawn Hafen ML23219A1082023-08-0707 August 2023 SLRA - Requests for Additional Information - Set 2 ML23201A0352023-07-24024 July 2023 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23200A3502023-07-19019 July 2023 SLRA - Requests for Additional Information - Set 1 - Email from Marieliz Johnson to Christopher Domingos ML23200A3512023-07-19019 July 2023 SLRA - Request for Additional Information - Set 1 ML23059A3522023-03-0101 March 2023 Request for Information for NRC Commercial Grade Dedication Inspection: Inspection Report 05000263/2023010 ML23058A1522023-02-27027 February 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000263/2023002 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 ML22206A1662022-07-25025 July 2022 Information Request to Support Upcoming Problem Identification and Resolution Inspection at Monticello Nuclear Generating Plant 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 ML21322A2362021-11-18018 November 2021 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000263/2022401 ML21085A8582021-03-26026 March 2021 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team): Inspection Report 05000263/2021010 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 ML20302A1972020-10-26026 October 2020 NRR E-mail Capture - Monticello Request for Additional Information TSTF-505 License Amendment Request 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 ML20133K0532020-05-14014 May 2020 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML20134H9282020-05-12012 May 2020 Notification of NRC Design Bases Assurance Inspection (Programs) and Initial Request for Information: Inspection Report 05000263/2020013 ML20120A0272020-04-28028 April 2020 NRR E-mail Capture - Request for Additional Information Monticello Long Term Steam Dryer Inspection Plan ML20099F3622020-04-0606 April 2020 Lr Phase 4 Request for Information ML20055F3672020-02-24024 February 2020 Information Request to Support Upcoming Temporary Instruction 2515/193 Inspection at Monticello Nuclear Generating Plant ML20035F1552020-02-0404 February 2020 NRR E-mail Capture - Request for Additional Information Monticello and Prairie Island Alternative Requests to Adopt Code Cases N-786-3 and N-789-3 (Epids: L-2019-LLR-0078 and L-2019-LLR-0079) ML19270E8652019-09-27027 September 2019 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information (Rbaker) ML19080A2182019-03-21021 March 2019 NRR E-mail Capture - Request for Additional Information Monticello License Amendment Request to Remove Note TS LCO 3.5.1 ML19070A1302019-03-0808 March 2019 Ltr. 03/08/19 Monticello Nuclear Generating Plant - Notification of an NRC Triennial Heat Sink Performance Inspection and Request for Information; Inspection Report 05000263/2019003 (DRS-V.Petrella) ML19031A9132019-01-31031 January 2019 NRR E-mail Capture - Request for Additional Information Monticello License Amendment Request to Adopt 10 CFR 50.69 ML18269A3572018-09-26026 September 2018 NRR E-mail Capture - Request for Additional Information Monticello License Amendment Request to Adopt TSTF-425 ML18173A0512018-06-22022 June 2018 NRR E-mail Capture - Request for Additional Information Monticello Request for Exemption from Appendix R Requirements (L-2018-LLE-0001) ML18130A7472018-05-0909 May 2018 NRR E-mail Capture - Request for Information Monticello TSTF-542 License Amendment Request ML18121A2542018-05-0101 May 2018 Enclosurequest for Additional Information (05/01/2018, E-Mail from C. Jacobs/Dsfm to S. Jurek Monticello Exemption: NRC Clarification Questions on RAI#1 Responses) ML18065A5482018-03-0606 March 2018 EnclosuRAI-1 (non-proprietary) (Letter to T. J. O'Connor First Request for Additional Information for Review of Exemption Request for Five Nonconforming Dry Shielded Canisters 11 Through 15) ML17293A0912017-10-18018 October 2017 NRR E-mail Capture - Request for Additional Information Monticello Request for Exemption from Appendix R Requirements (CAC No. MF9586; EPID L-2017-LLE-00012) ML17235B0012017-08-23023 August 2017 NRR E-mail Capture - Request for Additional Information Monticello EAL Scheme Change Amendment Request ML17221A3882017-08-0909 August 2017 NRR E-mail Capture - Request for Additional Information for Monticello Nuclear Generating Plant License Amendment Request Dated March 24, 2017 Emergency Response Organization ML17219A0752017-08-0707 August 2017 NRR E-mail Capture - Request for Additional Information for Monticello Nuclear Generating Plant License Amendment Request Dated March 24, 2017 Emergency Response Organization 2024-08-05
[Table view] |
Text
Accession No. ML12178A557 From: Tam, Peter Sent: Tuesday, June 26, 2012 1:58 PM To: Loeffler, Richard A.; 'Rippy, L. Randal'; 'Kissinger, Peter W.' Cc: Wallace, Jay; Sydnor, Christopher; Alley, David Subject: Monticello - Draft RAI on Relief Request RR-005 (TAC ME8071) Rick, Randy: By letter dated February 28, 2012, Northern States Power Company - Minnesota submitted request for alternative RR-005, "Alternative Requirements for BWR Class 1 System Leakage Test Pressure Following Repair/Replacement Activities,Section XI, Division 1," (Accession No. ML12059A403). The licensee proposed to use the provisions of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) Case N-795, with conditions, to perform the system leakage test and associated VT-2 examination following repair/replacement activities. Our technical review branch has developed the following information in order to complete its review: 1. The NRC staff notes that alternative pressure requirements for leak testing of bolted joints has been authorized for specific cases (e.g., see Accession No. ML12025A010), but is unaware of generic authorization for alternate leak testing pressure requirements for welded repairs. The NRC staff acknowledges that authorization of the proposed alternative for welded repairs could be supported on a case-by-case basis, but can envision cases, such as when the segment being tested is isolable and can be independently pressurized, where determination of hardship to support the relief may not be possible. In addition, the NRC staff questions whether pressurization of welded repairs to pressures less than that corresponding to 100 percent of normal operating pressure provides reasonable assurance of the structural integrity of the welded repair. Please provide justification for the generic use of the proposed alternative pressure requirement for leak testing of welded repairs and demonstrate that the structural integrity of welded repairs is ensured. 2. Please describe the methods for attaining 100% of normal operating pressure required by IWB-5221(a) in order to perform the Code-compliant system leakage test and describe the hardship or unusual difficulty associated with each. 3. Please describe the method for attaining 90% of normal operating pressure in order to perform the proposed alternative leakage test. 4. The Basis for Use of the proposed alternative states that the core decay heat during a maintenance outage is much higher than that after a refueling outage, and that the heat load is difficult to control once shutdown cooling is removed from service. a. What are the temperature and pressure limits for use of shutdown cooling? b. Given these limits, please explain why pressurization to 90 percent normal operating pressure, with a hold for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, is possible but pressurizing to 100 percent normal operating pressure is unusually difficult.
You may choose to accept this e-mail as transmitting a formal RAI, and formally respond to the above questions within 45 days of receipt of this e-mail. Alternatively, you may request to hold a conference call with our review staff, during which we discuss the disposition of the above draft questions and a date for formal response. Peter S. Tam Senior Project Manager (for D. C. Cook and Monticello) Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Tel. 301-415-1451