Letter Sequence Other |
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MONTHYEARML0606705972006-03-24024 March 2006
Notice of Consideration of Proposed Amendment Regarding Contingent Installation of a Temporary Spent Fuel Storage Rack, Proposed No Significant Hazards Consideration Determination, and Opportunity for Hearing/Hybrid Hearing
Project stage: Other
ML0610900252006-04-17017 April 2006
Draft RAI, Proposed Amendment Re. Spent Fuel Storage
Project stage: Draft RAI
ML0617401212006-07-0606 July 2006
Request for Withholding Information from Public Disclosure
Project stage: Withholding Request Acceptance
L-MT-06-058, Response to Request for Additional Information for License Amendment Request for Contingent Installation of Temporary Fuel Storage Rack in Spent Fuel Pool2006-09-0707 September 2006
Response to Request for Additional Information for License Amendment Request for Contingent Installation of Temporary Fuel Storage Rack in Spent Fuel Pool
Project stage: Response to RAI
ML0633900212006-12-0404 December 2006
Draft RAI Re Proposed Amendment on Contingent Installation of Temporary Spent Fuel Rack
Project stage: Draft RAI
ML0700500712007-01-0404 January 2007
Request for Conference Call Re. Structural Issues Concerning Temporary Installation of Spent Fuel Rack
Project stage: Other
ML0706604562007-02-28028 February 2007
Draft SE for Monticello Temporary Spent Fuel Rack Amendment
Project stage: Draft Approval
ML0707103752007-03-0909 March 2007
Technical Specification Amendment, Revised Section 4.3, Fuel Storage, to Allow Contingent Installation of a Temporary Spent Fuel Storage Rack
Project stage: Other
ML0705405222007-03-0909 March 2007
License Amendment, Revised Section 4.3, Fuel Storage, of the Technical Specifications to Allow for Contingent Installation of a Temporary Spent Fuel Storage Rack
Project stage: Acceptance Review
2006-07-06
[Table View] |
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Category:E-Mail
MONTHYEARML24022A0212024-01-20020 January 2024
NRR E-mail Capture - Monticello - Request for Additional Information ISI RR-002 Alternative to Use IWB-2500(f)
ML23353A0742023-12-19019 December 2023
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Proposed Alternative VR-09, Modifications to OMN-17
ML23348A3462023-12-14014 December 2023
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of License Amendment Request to Revise TS 3.8.6, Battery Parameters, SR 3.8.6.6
ML23268A0292023-09-20020 September 2023
SLRA - Requests for Confirmation of Information - Set 2 - Email from Marieliz Johnson to Shawn Hafen
ML23249A2092023-09-0606 September 2023
NRR E-mail Capture - Action: Opportunity to Review and Comment on a New NRC Information Collection, 10 CFR Part 50.55a, Codes and Standards (3150-XXXX)
ML23248A3462023-09-0505 September 2023
NRR E-mail Capture - Request for Additional Information for Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant - Decommissioning Funding Status Reports
ML23237A4822023-08-25025 August 2023
SLRA - Request for Additional Information - Set 3 - Email from Marieliz Johnson to Shawn Hafen
ML23228A1212023-08-16016 August 2023
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Alternative Request VR-11 for MO-2397
ML23227A2182023-08-15015 August 2023
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Alternative Request RR-002 to Use IWB-2500(f)
ML23219A1072023-08-0707 August 2023
SLRA - Requests for Additional Information - Set 2 - Email from Marieliz Johnson to Shawn Hafen
ML23200A3502023-07-19019 July 2023
SLRA - Requests for Additional Information - Set 1 - Email from Marieliz Johnson to Christopher Domingos
ML23172A1122023-06-21021 June 2023
SLRA - Requests for Confirmation of Information - Set 1 - Email from Marieliz Johnson to Christopher Domingos
ML23054A3322023-02-23023 February 2023
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Relief Request to Use Later Edition of ASME BPV Code, Section XI, for ISI Program Code of Record
ML23053A1362023-02-13013 February 2023
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Relief Request to Use Later Edition of ASME BPV Code, Section XI, for Cisi Program
ML23017A2222023-01-13013 January 2023
Verbal Authorization of Proposed Alternative PR-08 Regarding Inservice Testing Requirements of Certain High Pressure Coolant Injection System Components (EPID L-2022-LLR-0088) (Email)
ML23004A1982023-01-0404 January 2023
NRR E-mail Capture - Draft Request for Additional Information Monticello Nuclear Generating Plant Request Pr 08, HPCI Pump Quarterly Testing
ML23012A2102022-07-26026 July 2022
Letter Submitting Monticello Outline Package
ML22181A1962022-06-24024 June 2022
NRR E-mail Capture - Draft RAI Monticello Alternative VR-08
ML22175A1602022-06-24024 June 2022
NRR E-mail Capture - RAI Monticello Fuel Oil Storage Tank Inspection
ML22131A2652022-05-11011 May 2022
NRR E-mail Capture - Request for Additional Information Xcel Energy Amendment Request to Create a Common Eplan and EOF for Monticello and Prairie Island
ML22123A2822022-05-0303 May 2022
NRR E-mail Capture - Request for Additional Information Monticello Alternative VR-10, EFCV Testing Frequency
ML22101A0712022-04-11011 April 2022
NRR E-mail Capture - Monticello - Acceptance of Requested Licensing Action License Amendment Request to Revise TS 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray Header and Nozzle Surveillance Frequency
ML22089A1302022-03-30030 March 2022
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Alternative Related Excess Flow Check Valve Testing Frequency
ML22082A1812022-03-23023 March 2022
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of VR-08 Alternative to Adopt ASME OM Code Case OMN-28
ML22075A2612022-03-16016 March 2022
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of VR-07 Alternative Related to MOV Testing Per ASME OM Code Case OMN-26
ML22067A2032022-03-0808 March 2022
Audit Plan to Support Review of an Amendment to Transition to Atrium 11 Fuel (Redacted)
ML22011A0642022-01-11011 January 2022
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Licensing Action License Amendment Request to Support Diesel Generator Fuel Oil Storage Tank Inspection
ML22005A3612022-01-0505 January 2022
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Pump Vibration Testing Per ASME OM Code Case OMN-22
ML21347A0082021-12-10010 December 2021
NRR E-mail Capture - Monticello and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested License Amendment Standard Emergency Plan and Consolidated Emergency Operations Facility
ML21330A0382021-11-18018 November 2021
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related RHR and RHRSW Pump Testing
ML21286A7882021-10-0606 October 2021
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Residual Heat Removal Heat Exchanger Flow Control Valve Stroke Timing
ML21256A1892021-09-13013 September 2021
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Testing the Control Rod Drive Scram Discharge Header Check Valves
ML21256A1862021-09-13013 September 2021
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to HPCI and RCIC Pump Testing
ML21256A1882021-09-13013 September 2021
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Vibration Testing Range for the Sblc Pumps
ML21253A2002021-09-10010 September 2021
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Pressure Isolation Valve Testing
ML21252A0132021-08-31031 August 2021
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Licensing Action License Amendment Request to Adopt Advanced Framatome Methodologies
ML21130A3022021-05-0707 May 2021
Initial and Final Written 10 CFR 21 Notification for GE Hitachi Numac Prnm System
ML21110A7042021-04-20020 April 2021
Response: Monticello Nuclear Plant Outage - Covid Risk to On-Site Employees
ML21084A2522021-03-24024 March 2021
NRR E-mail Capture - Revised Review Schedule for Monticello TSTF-505 (EPID L-20200LLA-0062)
ML21068A2772021-03-0909 March 2021
NRR E-mail Capture - Monticello TSTF-505, Request for Additional Information
ML20343A1292020-12-0808 December 2020
NRR E-mail Capture - Request for Additional Information
ML20342A1782020-12-0707 December 2020
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Licensing Action License Amendment Request to Adopt TSTF-564 Safety Limit MCPR
ML20302A1972020-10-26026 October 2020
NRR E-mail Capture - Monticello Request for Additional Information TSTF-505 License Amendment Request
ML20289A1072020-10-0606 October 2020
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Licensing Action License Amendment Request to Adopt TSTF-582 Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements (EPID L-2020-LLA-0209
ML20191A0252020-07-0101 July 2020
NRR E-mail Capture - Draft Request for Additional Information Monticello Alternative Request RR-016 Related to H8, H9, and H 10 Weld Examinations
ML20120A0272020-04-28028 April 2020
NRR E-mail Capture - Request for Additional Information Monticello Long Term Steam Dryer Inspection Plan
ML20099F1292020-04-0606 April 2020
E-mail to Licensee for Monticello Lr Phase 4 RFI
ML20077L4632020-03-17017 March 2020
NRR E-mail Capture - Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant, Units 1 and 2 -Acceptance of Requested Licensing Action Request to Adopt TSTF-529
ML20064C5352020-03-0404 March 2020
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Revise the Previously Authorized Alternative in RR-008 for the H8 and H9 Welds
2024-01-20
[Table view] |
Text
Accession No. ML070050071 From: Peter Tam To: Loeffler, Rick; Salamon, Gabor Date: 01/04/2007 3:25:01 PM
Subject:
Request for Conference Call re. Structural Issues for Temporary Spent Fuel Rack (TAC MD0302)
Rick; The NRC staff's main structural safety concerns regarding the installation of an 8x8 fuel storage rack, were:
(1) The response spectrum used in the 1977 seismic analysis did not envelope the proposed Monticello Nuclear Generating Plant (MNGP) site floor response spectrum; and (2) There was no information on natural frequencies of the PaR 8x8 fuel storage rack to show that the seismic response of the 8x8 rack will be bounded by the responses of other racks being analyzed.
Based on the new information submitted in your 1/02/07 letter, the NRC staff agrees that if the artificial time history response spectrum from the fundamental frequencies of the PaR 8x8 fuel storage rack to zero period bounds the MNGP response spectrum by a wide margin, the seismic loading used in the 1977 PaR Systems Report will bound loads from a seismic evaluation using the MNGP response spectrum. The remaining issue is the determination of fundamental frequencies of the 8x8 rack.
In Enclosure 2 to response, you presented calculation results for the 8x11 rack using SAP 2000 based on A simplified ANSYS model (see Fig. 2 of [I]), consisting of a cantilever beam extending the height of the racks, attached to a horizontal beam at the base bottom casting elevation with leg beams connecting the ends of this member to the floor (sheet 5 of 12). The calculated 1st and 2nd horizontal natural frequencies are given at 8.2 Hz and 33.7 Hz, respectively. The "Casting Bottom" vertical mode is approximately 17.2 Hz (sheet 7 of 12).
Notice that PaR report Section 5.3 Model Description, Formulation and Assumptions for the Seismic Analysis of BWR Spent Fuel Racks (July 1977), page 5.3-4, stated: Dynamic analysis of a detailed SAP IV model have determined the first two natural frequencies to be orthogonal and simple cantilever modes at 8 Hz; and subsequent horizontal frequencies are greater than 28 Hz. A vertical diaphragming frequency of the bottom casting exists at 14 Hz.
Our reviewer Weijun Wang has some remaining questions that he would like to discuss with you in a conference call:
- 1. The PaR report indicated that the natural frequencies of the rack was determined by a detailed SAP IV model as illustrated in Figure 1 of the PaR report (page 5.3-13), while the new calculation used a simplified ANSYS model.
- 2. It is not clear which rack configuration was used in the SPA IV model analysis. Although the new calculation presented similar 1st mode frequency, the 2nd horizontal frequency is 28 Hz, the casting bottom (vertical) is 14 Hz in PaRs report; the new calculation yielded 33.7 Hz and 17.2 Hz, respectively (for the 8x11 rack).
- 3. Since it is not convincing that using a simplified model by SAP 2000 can obtain similar results as that using a detailed SAP IV model for the 8x11 rack, the same method used to determine the natural frequencies for the 8x8 rack may be questionable.
- 4. The conclusion that 8 Hz is the lower bound natural frequency of the rack configurations cannot be drawn until we are certain that the natural frequency of the 8x8 rack is higher than 8
Hz.
The sole purpose of this e-mail is to prepare you and others for the requested conference call.
It does not convey a formal NRC staff position, and it 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 e-mail: pst@nrc.gov Tel.: 301-415-1451 CC: Weijun Wang Mail Envelope Properties (459D629D.F35 : 12 : 35330)
Subject:
Request for Conference Call re. Structural Issues for Temporary Spent Fuel Rack (TAC MD0302)
Creation Date 01/04/2007 3:25:01 PM From: Peter Tam Created By: PST@nrc.gov Recipients Action Date & Time nmcco.com Transferred 01/04/2007 3:25:09 PM Gabor.Salamon (Gabor Salamon)
Richard.Loeffler (Rick Loeffler) nrc.gov TWGWPO04.HQGWDO01 Delivered 01/04/2007 3:25:06 PM WXW2 CC (Weijun Wang) Opened 01/04/2007 3:30:23 PM Post Office Delivered Route nmcco.com TWGWPO04.HQGWDO01 01/04/2007 3:25:06 PM nrc.gov Files Size Date & Time MESSAGE 5104 01/04/2007 3:25:01 PM Options Auto Delete: No Expiration Date: None Notify Recipients: Yes Priority: Standard ReplyRequested: No Return Notification: None Concealed
Subject:
No
Security: Standard To Be Delivered: Immediate Status Tracking: Delivered & Opened
