Letter Sequence Draft RAI |
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TAC:MD9990, Clarify Application of Setpoint Methodology for LSSS Functions (Approved, Closed) |
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Administration
- Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance
- Meeting, Meeting, Meeting, Meeting, Meeting, Meeting
Results
Other: L-MT-08-091, Calculation 0801040.301, Steam Dryer Outer Hood Submodel Analysis., L-MT-09-002, Response to NRC Probabilistic Risk Assessment (PRA) Branch Requests for Additional Information (Rais) Dated December 5, 2008, L-MT-09-003, Response to NRC Environmental Branch Requests for Additional Information (Rais) Dated December 18, 2008, L-MT-09-004, Enclosure 1 (Continued) to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 2, Copy of MNGP Appr T0406 Data Transmittal Pages 1 of 538 Through Pages 538 of 538, L-MT-09-026, Calculation 0000-0081-6958 MNGP-PRNMS-APRM Calc-2008-NP, Rev. 1, Average Power Range Monitor Selected Prnm Licensing Setpoints - EPU Operation (Numac), L-MT-09-027, Extended Power Uprate: Response to Instrumentation and Controls Branch RAI No. 3 Dated April 6, 2009, L-MT-09-044, Extended Power Uprate: Response to NRC Mechanical and Civil Engineering Review Branch (Emcb) Requests for Additional Information (Rais) Dated March 28, 2009, L-MT-09-049, Drawing C.5-2007, Revision 15, Failure to Scram, L-MT-09-073, Extended Power Uprate: Response to NRC Containment and Ventilation Review Branch (Scvb) Requests for Additional Information (Rais) Dated July 2, 2009 and July 14, 2009, L-MT-09-083, Extended Power Uprate: Limit Curves Requested by the Mechanical and Civil Review Branch (Emcb) Associated with Requests for Additional Information (Rais) Dated March 20, 2009, L-MT-09-088, Extended Power Uprate: Revision to Clarify Text in Enclosures 5 and 7 of L-MT-08-052, L-MT-09-097, Extended Power Uprate: Acknowledgement of NRC Review Delay, L-MT-10-025, Extended Power Uprate (Epu): Response to NRC-NSPM February 25, 2010 Conference Call, L-MT-10-072, Extended Power Uprate: Updates to Docketed Information, L-MT-11-044, Uprate (Epu): Update on EPU Commitments, L-MT-12-056, WCAP-17549-NP, Rev. 0, Monticello Replacement Steam Dryer Structural Evaluation for High-Cycle Acoustic Loads Using ACE, L-MT-12-090, Westinghouse, LTR-A&SA-12-8, Rev. 1, Attachment B, Recommendations for Inspections of the Monticello Replacement Steam Dryer., L-MT-12-114, Drawing C.5-2007, Rev. 17, Failure to Scram, L-MT-13-020, Enclosure 1 - Responses to the Gap Analysis, L-MT-13-029, Enclosure 14 to L-MT-13-029 - WCAP-17716-NP, Revision 0, Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project., L-MT-13-091, WCAP-17716-NP, Revision 1 - Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project, Enclosure 14, L-MT-13-092, Extended Power Uprate (Epu): Completion of EPU Commitments, Proposed License Conditions and Revised Power Ascension Test Plan, L-MT-13-096, GE-MNGP-AEP-3304R1, Enclosure 4, NEDC-33435 Corrected Pages, L-MT-13-126, Enclosure 3, GE-MNGP-AEP-3306, Enclosure 2 GEH Response to Mella+ Eicb RAI and Affidavit, L-MT-14-023, Maximum Extended Load Line Limit Analysis Plus: Technical Specification Clarifications, L-MT-15-074, Enclosure 7, WCAP-18604-NP, Revision 0, Monticello EPU Main Steam Line Strain Data Evaluation Report., L-MT-16-017, Revised Commitment to Reconcile Analysis of Bypass Voiding for Transition to Areva Analysis Methodology, L-MT-16-071, Submittal of 2016 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46, ML083230111, ML083400402, ML083500575, ML083570610, ML083590127, ML090710680, ML090710683, ML090710684, ML091120578, ML091140470, ML091410121, ML091410122, ML091410123, ML091410124, ML091760769, ML092290250, ML092810554, ML093160816, ML093220925, ML093220964, ML093620024, ML100280558... further results
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MONTHYEARML0907106832008-02-17017 February 2008 Enclosure 1 (Continued) to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 2, Attachment 1-1g Through End of Encl. 1 Project stage: Other ML13064A4352008-03-20020 March 2008 CA-95-075, Main Steam Line High Flow Setpoint, Attachment 4 Project stage: Other ML0914101242008-08-11011 August 2008 Monticello - Calculation CA-08-050, Rev. 0, Instrument Setpoint Calculation - Average Power Range Monitor (APRM) Non-Flow Eiased Prnm Setpoints for Cl Tp and EPU Project stage: Other L-MT-08-091, Calculation 0801040.301, Steam Dryer Outer Hood Submodel Analysis.2008-10-31031 October 2008 Calculation 0801040.301, Steam Dryer Outer Hood Submodel Analysis. Project stage: Other ML0832301122008-10-31031 October 2008 NEDC-33322-NP, Revision 3, Monticello Nuclear Generating Plant, Safety Analysis Report, Constant Pressure Power Uprate. Project stage: Request ML0832301112008-11-0505 November 2008 Monticello Nuclear Generating Plant, License Amendment Request: Extended Power Uprate Project stage: Other ML0832301142008-11-0505 November 2008 Monticello Nuclear Generating Plant, Steam Dryer Dynamic Stress Evaluation. Project stage: Request ML0834003662008-12-0202 December 2008 Extended Power Uprate Acceptance Review Questions on Probabilistic Risk Assessment Issues Project stage: Acceptance Review ML0834004022008-12-0505 December 2008 Extended Power Uprate - Monticello - Request to Supplement the Application in the Probabilistic Risk Assessment Area Project stage: Other ML0835000992008-12-11011 December 2008 Monticello Extended Power Uprate (Usnrc TAC MD9990): Acceptance Review Supplement Regarding Steam Dryer Outer Hood Submodel Analysis Project stage: Supplement ML0835303022008-12-16016 December 2008 Draft Request for Additional Information, Environmental Issues of EPU Application Project stage: Draft RAI ML0936200242008-12-18018 December 2008 Report 0800760.401, Rev. 1, Flaw Evaluation and Vibration Assessment of Existing Monticello Steam Dryer Flaws for Extended Power Uprate. Project stage: Other ML0835005752008-12-18018 December 2008 Letter Finding 11/5/08 Application for Amendment Acceptable for Review Project stage: Other ML0835309982008-12-18018 December 2008 EPU Application - Additional RAI Question Regarding an Environmental Issue Project stage: RAI ML0835310022008-12-18018 December 2008 Proposed Eou Amendment - Revised RAI Re. Containment Analysis Project stage: RAI ML0914101222008-12-18018 December 2008 Monticello - Calculation CA-95-075, Revision 1, Main Steam Line High Flow Setpoint Project stage: Other ML0914101212008-12-19019 December 2008 Monticello - Calculation CA-95-073, Revision 4, Reactor Low Water Level SCRAM Setpoint Project stage: Other ML0835901272009-01-14014 January 2009 Letter Conveying Determination That Enclosure 5 of 11/5/08 Application for EPU Amendment Contains Proprietary Information and Withheld from Public Disclosure Project stage: Other ML0835706102009-01-26026 January 2009 Letter Conveying Determination That Enclosure 11 of 11/5/08 Application for EPU Amendment Contains Proprietary Information and Is Withheld from Public Disclosure Project stage: Other L-MT-09-003, Response to NRC Environmental Branch Requests for Additional Information (Rais) Dated December 18, 20082009-01-29029 January 2009 Response to NRC Environmental Branch Requests for Additional Information (Rais) Dated December 18, 2008 Project stage: Other L-MT-09-005, Revision to Attachment 1 of Enclosure 17 of MNGP License Amendment Request for Extended Power Uprate2009-02-0404 February 2009 Revision to Attachment 1 of Enclosure 17 of MNGP License Amendment Request for Extended Power Uprate Project stage: Request L-MT-09-002, Response to NRC Probabilistic Risk Assessment (PRA) Branch Requests for Additional Information (Rais) Dated December 5, 20082009-02-0404 February 2009 Response to NRC Probabilistic Risk Assessment (PRA) Branch Requests for Additional Information (Rais) Dated December 5, 2008 Project stage: Other ML0904204852009-02-11011 February 2009 Draft RAI from Materials Engineering Re. Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0907106792009-02-17017 February 2009 Monticello, Response to NRC Containment & Ventilation Branch Request for Additional Information (Rals) Dated December 18, 2008 Project stage: Request ML0907106802009-02-17017 February 2009 Monticello, Enclosure 1 to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 1 Dated December 18, 2008, Cover Through Copy of MNGP Appr T0406 Data Transmittal Page 424 of 424 Project stage: Other L-MT-09-004, Enclosure 1 (Continued) to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 2, Copy of MNGP Appr T0406 Data Transmittal Pages 1 of 538 Through Pages 538 of 5382009-02-17017 February 2009 Enclosure 1 (Continued) to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 2, Copy of MNGP Appr T0406 Data Transmittal Pages 1 of 538 Through Pages 538 of 538 Project stage: Other ML0907106842009-02-17017 February 2009 Enclosures 2 - 4: NSPM Response to Containment & Ventilation Branch RAI Numbers 2, 3 and 4 Dated December 18, 2008 Project stage: Other L-MT-09-018, Response to NRC Steam Generator Tube Integrity & Chemical Engineering Branch Request for Additional Information (RAI) Dated February 11, 20092009-02-24024 February 2009 Response to NRC Steam Generator Tube Integrity & Chemical Engineering Branch Request for Additional Information (RAI) Dated February 11, 2009 Project stage: Request ML0907100912009-03-11011 March 2009 Conveying Draft RAI Questions from the Instrumentation and Controls Branch Regarding the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0907200572009-03-12012 March 2009 Conveys Draft RAI Regarding Fire Protection for the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0907800062009-03-18018 March 2009 Draft RAI from Probabilistic Risk Assessment Licensing Branch on the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0907800042009-03-18018 March 2009 Conveys Draft RAI by the PRA Licensing Branch on the Proposed EPU Amendment Project stage: Draft RAI ML0907809032009-03-19019 March 2009 Conveys Draft RAI Provided by the Containment and Ventilation Branch on the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0907809092009-03-19019 March 2009 RAI from the Containment and Ventilation Branch the Proposed Extended Power Uprate Amendment Project stage: RAI L-MT-09-017, Extended Power Uprate: Response to NRC Reactor Systems Branch & Nuclear Performance & Code Review Branch Request for Additional Information (RAI) Dated January 16, 20092009-03-19019 March 2009 Extended Power Uprate: Response to NRC Reactor Systems Branch & Nuclear Performance & Code Review Branch Request for Additional Information (RAI) Dated January 16, 2009 Project stage: Request ML0908200312009-03-20020 March 2009 Draft RAI Re. Health Physics Issues for the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0908200992009-03-23023 March 2009 Draft RAI from the Balance of Plant Branch Re the Proposed Amendment on Extended Power Uprate Project stage: Draft RAI ML0908800022009-03-28028 March 2009 Second Portion of Draft RAI from the Mechanical and Civil Engineering Branch Regarding the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0908800032009-03-28028 March 2009 Draft RAI from the Electrical Engineering Branch Re. the Proposed Extended Power Uprate Amendment for Monticello Project stage: Draft RAI ML0908800012009-03-29029 March 2009 Additional Draft RAI Questions from the Containment and Ventilation Branch Proposed EPU Amendment for Monticello Project stage: Draft RAI ML0910300212009-04-0606 April 2009 Draft RAI Question from Instrumentation and Controls Branch Re. Proposed EPU Amendment Project stage: Draft RAI ML0910300172009-04-0606 April 2009 Conveys an Additional EPU Draft RAI Question from Instrumentation and Controls Branch Project stage: Draft RAI L-MT-09-025, Extended Power Uprate: Response to NRC Reactor Systems Branch and Nuclear Performance & Code Review Branch Request for Additional Information (RAI) Dated February 23, 20092009-04-22022 April 2009 Extended Power Uprate: Response to NRC Reactor Systems Branch and Nuclear Performance & Code Review Branch Request for Additional Information (RAI) Dated February 23, 2009 Project stage: Request ML0911205782009-04-22022 April 2009 Request for Audit of Implementation of Long-Term Stability Solution Project stage: Other ML0911902092009-04-29029 April 2009 Transmit Revised Draft RAI from the Probabilistic Risk Assessment Licensing Branch on the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0914101232009-05-0606 May 2009 Monticello - Calculation 96-054, Rev 5, Turbine Stop Valve Closure/Generator Load Reject Scram Bypass Project stage: Other ML0911404702009-05-0707 May 2009 Determination That Submitted Information Can Be Withheld from Public Disclosure Project stage: Other ML0914101202009-05-13013 May 2009 Monticello - Extended Power Uprate: Response to NRC Instrumentation & Controls Branch Request for Additional Information Dated March 11, 2009, and April 6, 2009, and Fire Protection Branch RAIs Dated March 12, 2009 Project stage: Request L-MT-09-045, Extended Power Uprate: Response to NRC Electrical Engineering Review Branch (Eeeb) Request for Additional Information (RAI) Dated March 28, 20092009-05-26026 May 2009 Extended Power Uprate: Response to NRC Electrical Engineering Review Branch (Eeeb) Request for Additional Information (RAI) Dated March 28, 2009 Project stage: Request L-MT-09-029, Extended Power Uprate: Response to NRC Probabilistic Risk Assessment (PRA) Licensing Branch Request for Additional Information (RAI) Dated April 29, 20092009-05-29029 May 2009 Extended Power Uprate: Response to NRC Probabilistic Risk Assessment (PRA) Licensing Branch Request for Additional Information (RAI) Dated April 29, 2009 Project stage: Request 2009-02-24
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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] Category:Request for Additional Information (RAI)
MONTHYEARML24022A0212024-01-20020 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 ML17086A0602017-03-27027 March 2017 NRR E-mail Capture - Request for Additional Information Monticello Nuclear Generating Plant Integrated Leak Rate Test Interval Extension Request ML16323A2422016-11-18018 November 2016 NRR E-mail Capture - Monticello ILRT Extension Amendment Request for Additional Information ML13336A7072013-12-0404 December 2013 Request for Additional Information Changes to Security Plan Revision 18 ML13304B4182013-11-0101 November 2013 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns ML13275A1872013-10-28028 October 2013 Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051 ML13154A4702013-06-0404 June 2013 Rai'S Following Ifib Analysis 2013 Decommissioning Funding Status Report for Prairie Island 1 and 2 and Monticello ML12279A2952012-10-12012 October 2012 Request for Additional Information 10 CFR 50.54(p)(2) Changes to Security Plan ML12221A3362012-08-0808 August 2012 Draft RAI on Revision to Security Plan 2024-01-20
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Accession No. ML090880002 From: Peter Tam Sent: Saturday, March 28, 2009 5:04 PM To: 'Pointer, Kenneth'; 'Salamon, Gabor' Cc: Karl Feintuch; Alexander Tsirigotis; Kerby Scales
Subject:
Monticello - Second portion, draft RAI from Mechanical & Civil Engineering Branch re. proposed EPU amendment (TAC MD9990)
Ken:
Our review of your 11/5/09 application for an extended power uprate (EPU) amendment is ongoing. Our Mechanical & Civil Engineering Branch (EMCB) has previously provided draft RAI questions on the steam dryer, which I e-mailed to you on 3/20/09; following please find the balance of the draft RAI, not concerning the steam dryer, from EMCB. Please contact me to set up a conference call to discuss these questions. If you desire to hold the conference call during 3/24 - 4/10 when I am on leave, please contact my backup Karl Feintuch to make arrangements (301-415-3079).
- Enclosure 5 of the 11/5/09 application contains the Power Uprate Safety Analysis Report (PUSAR) NEDC-33333P, Rev 3. This draft RAI (below) is referring to the PUSAR, unless otherwise noted.
- The CLTR is Reference 1 of the PUSAR
- The ELTR1 is Reference 2 of the PUSAR
- The ELTR2 is Reference 3 of the PUSAR
RAI 1
Provide a table which contains information on plant operating parameters similar to Table 1-2 and include a column for OLTP. Include design and maximum temperatures for reactor recirculation system (RRS) vessel outlet and inlet nozzles and feedwater (FW) nozzles.
RAI 2
Confirm whether the current licensing basis criteria for high energy line break (HELB) are the criteria contained in the Giambusso/Schwencer letters (1972-73).
RAI 3
PUSAR Section 2.2.1 states that corrective actions are underway to perform HELB analysis upgrades at Monticello due to changes in pipe break methodology.
a) Explain why corrective actions are in place to upgrade the Monticello pipe break methodology.
b) Verify whether the Monticello pipe break methodology upgrade is based on SRP Section 3.6.2, MEB 3-1 criteria. If not, provide supporting justification.
RAI 4
ELTR 1 and ELTR 2 both recommend that HELB evaluations for High Pressure Core Spray (HPCS) and Building Heating Line be performed on plant-specific power uprate submittals. Please indicate where in the proposed LAR submittal these evaluations have been performed or provide the HELB plant-specific evaluations for these systems at EPU conditions.
RAI 5
Page 3-23 states that:
During the 6.3 percent rerate in 1996, only one new case was reanalyzed at CLTP for the RWCU system - a break in the system suction piping at the outboard isolation valve. For this reason a detailed comparison of CLTP and EPU results for HELBs in the RWCU system is not possible.
The statement that, For this reason a detailed comparison of CLTP and EPU results for HELBs in the RWCU system is not possible is not clear. Please provide clarification.
RAI 6
The same paragraph on page 3-23, as above, in reference to the reactor water cleanup (RWCU),
continues as follows:
For the break location that was analyzed during rerate, new mass and energy release calculations considered additional blowdown sources that had not been considered in the previous 1996 analysis. This resulted in an increase in integrated mass release of about 90% and an increase in integrated energy release of 63 percent.
a) Confirm that the 90% and 63% increases are referring to the proposed EPU.
b) Please explain how the effects of the increased mass and energy release have been evaluated, include evaluations of pipe whip restraints and jet targets.
RAI 7
Page 2-37 states that: The combination of stresses was evaluated to meet the requirements of the pipe break criteria. Based on these criteria, no new postulated pipe break locations were identified. For systems affected by the EPU, specifically steam (all EPU affected steam lines) and FW lines (including condensate), provide a pipe break analysis summary table (that includes the main steam increased turbine stop valve (TSV) closure transient loads in the analysis) which compares values at EPU and CLTP conditions and shows code equation stresses and CUFs compared to break limit for stresses and CUFs.
Include pipe break locations and types selected for CLTP and EPU. Include lines inside and outside containment.
RAI 8 , PUSAR Section 2.2.1.2, Liquid Line Breaks, on page 2-23 states that:
The mass and energy releases for HELBs in the RWCU, FW, Condensate, CRD, Standby Liquid Control, and Zinc Injection System (GEZIP) systems and instrument and sample lines may be affected by EPU and were re-evaluated at EPU conditions. ((Plant specific))
evaluations of liquid line breaks have been performed at EPU conditions.
Provide similar summaries as in RAI 7 for the RWCU line breaks at EPU conditions.
RAI 9
Indicate whether the FW lines have been structurally analyzed for any flow instabilities and loads due to water hammer or other flow transients and whether reanalysis has considered the EPU higher flows for these transients in evaluating pipe stresses, pipe breaks and pipe supports.
RAI 10
Are there any new liquid or steam line pipe break locations that need to be postulated due to EPU conditions?
RAI 11
a) For main steam (MS) and FW piping, state the design basis (DB) code for Class I and Class II piping and pipe supports.
b) Verify that all structural evaluations of SSCs, required for EPU, were performed in accordance with the DB codes of record for piping and pipe supports. If a different code than the DB code of record was used, provide a justification.
RAI 12
Page 2-36 of the PUSAR states that, The effects of the EPU conditions have been evaluated for the following piping [BOP] systems: A list of piping systems follows this statement. On page 2-37 of the PUSAR, it is stated that, These piping systems have been evaluated using the process defined in Appendix K of ELTR1 and found to meet the appropriate code criteria for the EPU conditions, when in fact evaluations of many of these systems, including RHR and MS, has not been completed, as shown by the submitted EPU LAR, see PUSAR Table 2.2-2d. In addition, Enclosure 8, Table 8-2 states that EPU planned modifications include, Revise documentation to incorporate revised pressure and temperature ratings for specific piping systems affected by EPU. Modify supports as required by the analyses.
a) The above PUSAR statements are not consistent. Please clarify the apparent inconsistency.
b) The proposed EPU LAR indicates that some EPU evaluations have not been completed for the staff to review. The acceptability of the proposed EPU LAR will be determined based upon the results of the LAR evaluation reviews that are performed by the staff in accordance with the policies and procedures set forth in LIC-101, License Amendment Review Procedures. Please provide a schedule of completion of these analyses and submittal of your evaluation results which shows that piping and pipe supports meet code allowables. Also, submit a schedule of completion for EPU required piping and pipe support modifications.
RAI 13
a) Provide a list of systems (inside and outside containment) for which temperature, pressure, flow and mechanical loads have been increased due to EPU. Please include OLTP and EPU values.
b) Provide a brief summary that shows the EPU maximum code equation stresses compared to CLTP for the affected systems. For MS, FW and condensate see RAI 14, below. Include fatigue evaluation CUFs, where applicable. It is noted, that although the tables in Section 2.2 of the PUSAR include, for some BOP systems, the percentage increases for pipe stresses and pipe support loads, varying from 9 to 72 percent increases, due to temperature or pressure increases, these percentages are not
indications that piping and pipe supports meet code equation allowable values, without providing maximum resulted values compared to code allowables.
RAI 14
Verify whether the increased flow rate due to EPU affects the structural analysis (pipe stress and support loads) of only the MS and FW piping.
RAI 15
The reactor coolant pressure boundary (RCPB) piping systems structural evaluation is contained in Section 2.2.2 of the PUSAR. Please provide structural evaluations for the residual heat removal (RHR) low pressure coolant injection (LPCI) and core spray systems and whether their piping and supports are structurally adequate for the EPU conditions.
RAI 16
The PUSAR indicates that the MS piping pressures and temperatures are not affected by EPU. Please confirm that the main steam piping has no temperature and pressure increases due to the EPU and whether that includes main steam branch piping inside and outside containment including the main steam turbine bypass piping.
RAI 17
Steam flow and feedwater flow will increase as a result of the CPPU implementation. The load due to the TSV fast closure transient is used in the design of the MS piping system. Page 2-31 states that Due to the magnitude of the TSVC transient load increase [at EPU], the transient event was reanalyzed. The main steam piping was then reanalyzed using this revised load definition.
a) Provide a quantitative summary of the MS and associated piping system evaluation (inside and outside containment), including pipe supports, that contains the increased loading associated with the TSV closure transient at EPU conditions, along with a comparison to the code allowable limits.
For piping, include maximum stresses and data at critical locations (i.e. nozzles, penetrations, etc),
including fatigue evaluation CUFs, where applicable. For pipe supports, state the method of evaluation for EPU conditions and confirm that the supports on affected piping systems have been evaluated and shown to remain structurally adequate to perform their intended design functions.
For non-conforming piping and pipe supports, provide a summary of the modifications required to ensure that piping and pipe supports are structurally adequate to perform their intended design functions and the schedule for completion of these modifications.
b) For FW and condensate, please respond as in part (a) of this RAI.
RAI 18
In accordance with Section 2.2.2 of the PUSAR, the main steam and associated piping system structural evaluation was performed to justify the operation of these systems at EPU conditions. This evaluation showed that one small bore branch line did not meet the displacement criteria. PUSAR further states that, Additional detailed analysis will be performed to qualify this line or the piping modified prior to operation at EPU conditions.
a) Provide identification of the small bore branch line (size, system, location, function).
b) Describe the required displacement limits and their bases.
c) Since this piping analysis, with potential piping and or support modifications, is required for EPU, please discuss the reasoning for not including this information in your application. Also, indicate when necessary modifications, as needed, will be completed.
RAI 19
Page 2-31 of the PUSAR states that, SRV discharge loads are not affected by EPU.
Please clearly present your evaluation of the effects of the safety relief valve (SRV) discharge line and containment loads at EPU conditions, which demonstrates that the current design basis for containment dynamic load definitions for the SRVs are still valid and bound the EPU conditions.
RAI 20
Page 2-33 states that:
FW piping from the MOVs [downstream from the high pressure heaters] to the condensate pumps will be modified as a result of the replacement of the feedwater and condensate pumps, and will be qualified for full EPU operation as part of the modification. The current piping and associated components are adequate for operation within the capability of the existing feedwater and condensate pumps.
Page 2-61 indicates that:
BOP FW from the condensate pumps to the first isolation valves (IV) (outside containment) will be analyzed and qualified with the FW and Condensate pump modifications prior to operation at EPU conditions.
a) In addition to the minimum flow line modifications for EPU FW and condensate pumps (identified in Enclosure 8, Planned Modifications), what other piping modifications are anticipated?
b) Indicate whether piping (including supports) analysis at the EPU conditions of the above mentioned FW and condensate piping modifications (including minimum flow lines) has been completed and discuss the analysis results.
c) Provide an explanation whether any transients are applicable in the sections of piping mentioned above (including pump min flow lines) and evaluate their affects with regard to structural integrity of the proposed modifications of piping, pipe components and pipe supports.
RAI 21
PUSAR, on page 2-33, to makes the following statement with regard to FW pipe stress evaluation:
A review of the small increases in pressure, temperature and flow associated with EPU indicates that the EPU temperature, pressure and flow conditions are bounded by the existing analyses. The original design analyses have sufficient design margin between calculated stresses and ANSI-B31.1-1977, including Winter 1978 Addenda Code allowable limits to justify operation at EPU conditions.
Explain the small increases in FW flow between OLTP and EPU and between CLTP and EPU that are bounded by the existing analyses, and whether the existing analyses contain flow induced loads at the OLTP or CLTP.
RAI 22
PUSAR, on page 2-33, makes the following statement with regards to the FW pipe support evaluation:
The FW system was evaluated for the effects of seismic, deadweight and thermal expansion displacements on the piping snubbers, hangers, and struts. A review of the increases in temperature and FW flow associated with EPU indicates that the EPU conditions are bounded by the existing analyses.
Provide a discussion which shows that the FW flow induced loads on pipe supports in the existing analysis bound the EPU flow induced loads.
RAI 23
a) Discuss whether there is any piping analysis, in the current design basis of the plant, that contains stratification or discuss whether there is any CLTP stratification monitoring currently in place.
b) If a stratification phenomenon currently exists, explain how these stratification locations have been evaluated at EPU conditions and provide a summary of their evaluation results.
RAI 24
Consider the two statements below:
LAR Enclosure 10, on page 3 of 16, states the following:
If the vibration level in the main piping in these systems [(FW and MS)] is greater than 50% of the acceptance criteria, then an engineering evaluation of the small bore piping will be performed to ensure that the steady state stresses are within the endurance limit.
In response to NRC staff RAI, CLTR for the EPU generic evaluation states that:
[T]ypically the measured piping vibration levels of the MS and FW piping are only a few percent of [the acceptance] criteria. Hence, the vibration levels of the large bore piping are small and therefore the vibration levels of components and branch piping attached to the large bore piping are not of concern. However, if during testing, the vibration levels of the large bore MS and FW piping are found to be significant, ((say 50% or higher of their acceptance criteria,{3})) then the attached components and branch piping connections will have a higher probability of fatigue failure relative to operation at the original power level. Hence when the measured MSL or FW large bore piping vibration levels reach ((50% of{3})) their acceptance criteria, the attached branch piping connections will be further evaluated.
a) Please revise the statement of Enclosure 10 of the LAR to be in accordance with the generic CLTR evaluation, in that if the vibration levels of the main piping reach 50% or higher, an engineering evaluation of all attached branch piping, not just for the small bore, will be performed to ensure that the steady state stresses are within the endurance limits. As this was the intention of the CLTR statement.
b) It appears that the 50% was based on the CLTR statement that, measured piping vibration levels of the MS and FW piping are only a few percent of [the acceptance] criteria. However, in the
Monticello case, from readings taken at 100% CLTP, vibration resulted in levels well above just a few percent of the acceptance criteria. At CLTP, 10 locations came in at above 20% of the acceptance criteria for FW and MS. Inside containment, the maximums were 14% and 32% of the acceptance criteria for FW and MS, respectively. Outside containment, the maximums were 43% and 34% of the acceptance criteria for FW and MS, respectively. Using the EPU expected vibration increase of 32%,
the CLTP values of 14, 20, 32, 34 and 43 percent of the acceptance criteria are projected for the EPU to be 18, 26, 42, 45 and 57 percent of the acceptance criteria, respectively.
- 1. Using the 50% or higher criterion, one location has been predicted to be 57% of the acceptance criterion. Please discuss whether evaluations have been performed for branch lines in the vicinity of this location? Provide a discussion of the evaluation results.
- 2. Provide a basis for justification that the 50% criterion, which the CLTR recommends for cases where piping vibration levels are only a few percent of the acceptance criteria, is applicable for Monticello, where the vibration levels even at CLTP have reached well above a few percent of the acceptance criteria, as shown above.
RAI 25
With regard to the reactor pressure vessel (RPV) evaluation for EPU, Page 2-45 of the PUSAR states that:
The Top Head and Cylindrical Shell and the Stabilizer Bracket were not evaluated for fatigue at the time that the OLTP evaluation was performed, and have not been evaluated for EPU.
Monticello USAR Rev 24, Section 4.2.1 states that:
[T]he reactor vessel was also designed for the transients which could occur during the design [ ]
life. The reactor vessel was analyzed for the cycles listed in Table 4.2-1.
Provide an evaluation which shows that the RPV top head and cylindrical shell and the RPV supports will be structurally adequate at EPU conditions for the renewed plant life.
RAI 26
Table 2.2-4 of the PUSAR shows that the fatigue CUFs for the recirculation (RRS) inlet nozzle (Ri) and FW Nozzle significantly increased for EPU by 146% for Ri and 47% for FW nozzle, placing the FW nozzle within approx 8.6% of its limit. Provide an explanation for these significant EPU CUFs increases, confirm that these CUFs are to the end of renewal life and assure that all required transients at EPU conditions have been properly included for these fatigue evaluations.
RAI 27
In Table 2.2-9 of the PUSAR, some of the locations are shown with --. Please explain what is meant by this designation.
RAI 28
In Section 2.2.2 of the PUSAR, it is stated that, The effects of FIV induced stresses at EPU conditions on safety-related thermowells in the MS and FW system and the sample probe in the FW system were evaluated and indicates that they remain acceptable under EPU conditions (see page 2-28 of the PUSAR). However, Enclosure 8, page 5 of 9 states, Replace or remove the thermowells in main steam piping to insure appropriate margin for flow induced vibration. Provide a quantitative summary of the
evaluation that supports the acceptability of the thermowells and sample probes in the MS, FW and related piping systems. Identify nonconforming component(s) and provide description of their modification(s).
RAI 29
Page 2-59 of the PUSAR states that:
The temperatures, accident radiation level, and the normal radiation level increase due to EPU.
These effects are not considered to have an adverse effect on the functional capability of nonmetallic components in the mechanical equipment both inside and outside containment.
Please provide a justification that the radiation due to the EPU is not higher than the radiation damage threshold of the non-metallic parts of the resilient seated check valves, hydraulic snubbers and flex joint bellows affected by the EPU.
RAI 30
Page 2-59 of the PUSAR states that:
The Monticello design and licensing bases do not require a formal mechanical EQ program like the EQ program applied to electrical equipment.
What program used at Monticello establishes the capability of active safety-related mechanical equipment and their components to perform their required safety function for the life of the plant during postulated normal and accident conditions?
This e-mail aims solely to prepare you and others for the requested conference call. This e-mail does not convey a formal NRC staff position, and does not formally request for additional information.
Peter S. Tam, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Tel. 301-415-1451 E-mail Properties Mail Envelope Properties (C56E360E9D804F4B95BC673F886381E71DBF72EB97)
Subject:
Monticello - Second portion, draft RAI from Mechanical & Civil Engineering Branch re. proposed EPU amendment (TAC MD9990)
Sent Date: 3/28/2009 5:04:22 PM Received Date: 3/28/2009 5:04:00 PM From: Peter Tam Created By: Peter.Tam@nrc.gov
Recipients:
Kenneth.Pointer@xenuclear.com ('Pointer, Kenneth')
Tracking Status: None Gabor.Salamon@xenuclear.com ('Salamon, Gabor')
Tracking Status: None Karl.Feintuch@nrc.gov (Karl Feintuch)
Tracking Status: None Alexander.Tsirigotis@nrc.gov (Alexander Tsirigotis)
Tracking Status: None Kerby.Scales@nrc.gov (Kerby Scales)
Tracking Status: None Post Office:
HQCLSTR02.nrc.gov Files Size Date & Time MESSAGE 46669 3/28/2009 Options Expiration Date:
Priority: olImportanceNormal ReplyRequested: False Return Notification: False Sensitivity: olNormal Recipients received: