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| {{#Wiki_filter:From: Peter TamTo:Loeffler, Rick; Salamon, GaborDate: 06/29/2006 8:36:47 AM | | {{#Wiki_filter:From: Peter Tam To: Loeffler, Rick; Salamon, Gabor Date: 06/29/2006 8:36:47 AM |
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| ==Subject:== | | ==Subject:== |
| Monticello: Draft RAI (Radiological) re. Full-Scope Application of AlternativeSource TermGabe, Rick: | | Monticello: Draft RAI (Radiological) re. Full-Scope Application of Alternative Source Term Gabe, Rick: |
| Our radiological consequences reviewer, Michelle Hart, has written the following draft questionsfor discussion with you in a telephone conference. We will decide how to disposition these draftquestions in the conference: | | Our radiological consequences reviewer, Michelle Hart, has written the following draft questions for discussion with you in a telephone conference. We will decide how to disposition these draft questions in the conference: |
| | | : 1. What is the basis for the assumed reduction in leakage through the main steam isolation valves (MSIVs) at 24 hours and 72 hours in the loss of coolant accident (LOCA) dose analysis? |
| 1.What is the basis for the assumed reduction in leakage through the main steam isolation valves (MSIVs) at 24 hours and 72 hours in the loss of coolant accident (LOCA) dose analysis? | | The submittal indicates that the reduction in leakage into the main steam lines is consistent with the reduction in primary containment leakage based on reduction of primary containment pressure. How does the reduction in primary containment pressure lead to a reduction in MSIV leakage? |
| The submittal indicates that the reduction in leakage into the main steam lines is consistent with the reduction in primary containment leakage based on reduction of primary containment pressure. How does the reduction in primary containment pressure lead to a reduction in MSIV leakage?2.Does the LOCA analysis modeling of iodine aerosol deposition in the MSIV leakagepathway account for the preceding removal of aerosols in the primary containment by naturaldeposition? 3.Was potential iodine revolatilization accounted for in the modeling of iodine removal forthe LOCA MSIV leakage pathway? Does the piping temperature profile used to determine theaerosol deposition efficiency include heating from aerosols deposited in the piping? 4.Please provide the control room shine dose calculations, including any diagrams thatindicate the location of the source(s) and receptor(s).Please call me to set up the telephone conference for the near future, but we will avoid FridayJuly 7. The sole purpose of this e-mail is to prepare you and others for the requested telephoneconference. It does not formally request for information, and it does not state a formal NRC staff position. Peter S. Tam, Senior Project ManagerPlant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulatione-mail: pst@nrc.gov Tel.: 301-415-1451 CC:Arias, Jesus; Hart, MichelleMail Envelope Properties(44A3C95F.4AD : 12 : 35330) | | : 2. Does the LOCA analysis modeling of iodine aerosol deposition in the MSIV leakage pathway account for the preceding removal of aerosols in the primary containment by natural deposition? |
| | : 3. Was potential iodine revolatilization accounted for in the modeling of iodine removal for the LOCA MSIV leakage pathway? Does the piping temperature profile used to determine the aerosol deposition efficiency include heating from aerosols deposited in the piping? |
| | : 4. Please provide the control room shine dose calculations, including any diagrams that indicate the location of the source(s) and receptor(s). |
| | Please call me to set up the telephone conference for the near future, but we will avoid Friday July 7. |
| | The sole purpose of this e-mail is to prepare you and others for the requested telephone conference. It does not formally request for information, and it does not state a formal NRC staff position. |
| | 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: Arias, Jesus; Hart, Michelle Mail Envelope Properties (44A3C95F.4AD : 12 : 35330) |
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| ==Subject:== | | ==Subject:== |
| Monticello: Draft RAI (Radiological) re. Full-Scope Application ofAlternative Source Term Creation Date 06/29/2006 8:36:47 AMFrom: Peter TamCreated By:PST@nrc.gov RecipientsActionDate & Timenmcco.comTransferred06/29/2006 8:37:36 | | Monticello: Draft RAI (Radiological) re. Full-Scope Application of Alternative Source Term Creation Date 06/29/2006 8:36:47 AM From: Peter Tam Created By: PST@nrc.gov |
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| AM Gabor.Salamon (Gabor Salamon) | | Recipients Action Date & Time nmcco.com Transferred 06/29/2006 8:37:36 AM Gabor.Salamon (Gabor Salamon) |
| Jesus.Arias CC (Jesus Arias) | | Jesus.Arias CC (Jesus Arias) |
| Richard.Loeffler (Rick Loeffler)nrc.gov OWGWPO04.HQGWDO01Delivered06/29/2006 8:36:52 | | Richard.Loeffler (Rick Loeffler) nrc.gov OWGWPO04.HQGWDO01 Delivered 06/29/2006 8:36:52 AM MLH3 CC (Michelle Hart) Opened 06/29/2006 8:38:06 AM Post Office Delivered Route nmcco.com OWGWPO04.HQGWDO01 06/29/2006 8:36:52 AM nrc.gov Files Size Date & Time MESSAGE 2960 06/29/2006 8:36:47 AM Options Auto Delete: No Expiration Date: None Notify Recipients: Yes Priority: Standard ReplyRequested: No Return Notification: None Concealed |
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| AM MLH3 CC (Michelle Hart)Opened06/29/2006 8:38:06 | |
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| AMPost Office DeliveredRoutenmcco.com OWGWPO04.HQGWDO0106/29/2006 8:36:52 AMnrc.govFilesSizeDate & Time MESSAGE296006/29/2006 8:36:47 AMOptions Auto Delete:
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| No Expiration Date:None Notify Recipients:Yes Priority:Standard ReplyRequested: | |
| No Return Notification:None Concealed | |
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| ==Subject:== | | ==Subject:== |
| | | No Security: Standard To Be Delivered: Immediate Status Tracking: Delivered & Opened}} |
| No Security:Standard To Be Delivered:Immediate Status Tracking:Delivered & Opened}} | |
Letter Sequence Draft RAI |
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TAC:MC8971, Revise Containment Requirements During Handling Irradiated Fuel and Core Alterations (Approved, Closed) TAC:MD2395, (Approved, Closed) |
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MONTHYEARML0534003682005-12-12012 December 2005
Request for Withholding Information from Public Disclosure
Project stage: Withholding Request Acceptance
ML0604502112006-02-17017 February 2006
Notice of Meeting with Nuclear Management Company, LLC, Monticello Nuclear Generating Plant, Regarding Full-Scope Application of Alternative Source Term Methodology
Project stage: Meeting
ML0613104452006-04-13013 April 2006
Monticello - Full Scope Alternate Source Term - Supplemental Information, Description of Meteorological Data
Project stage: Request
ML0611103102006-05-11011 May 2006
Withholding from Public Disclosure, Compact Disk 2 of 2, Alternative Source Term Supplemental Information, Submitted by Letter Dated 04/13/2006 in Support of Application for Amendments to Use Alternative Source Term Methodology
Project stage: Other
ML0618604632006-06-29029 June 2006
Draft RAI (Radiological) Re. Full-Scope Application of Alternative Source Term
Project stage: Draft RAI
ML0623500462006-08-21021 August 2006
Supplemental Submittal Regarding Full Scope Application of an Alternative Source Term (AST)
Project stage: Supplement
L-MT-06-054, Supplemental Submittal Regarding Full Scope Application of an Alternative Source Term (AST)2006-08-21021 August 2006
Supplemental Submittal Regarding Full Scope Application of an Alternative Source Term (AST)
Project stage: Supplement
L-MT-06-059, Response to Request for Additional Information to License Amendment Request for Full Scope Alternative Source Term2006-08-22022 August 2006
Response to Request for Additional Information to License Amendment Request for Full Scope Alternative Source Term
Project stage: Response to RAI
ML0628606312006-10-0606 October 2006
Draft SE for Alternative Source Term Amendment, Monticello Nuclear Generating Plant
Project stage: Draft Approval
ML0624105152006-11-29029 November 2006
Environment Assessment for Proposed Exemption from Appendix J of 10 CFR 50
Project stage: Approval
ML0627900152006-12-0707 December 2006
License Amendment 148 Regarding Full-Scope Implementation of the Alternative Source Term Methodology
Project stage: Approval
ML0624105072006-12-0707 December 2006
Exemption from Certain Requirements of 10 CFR 50, Appendix J
Project stage: Approval
ML0634205172006-12-0707 December 2006
Tech Spec Pages for Amendment 148 Regarding Full-Scope Implementation of the Alternative Source Term Methodology
Project stage: Acceptance Review
ML0709900892007-04-17017 April 2007
Correction of Errors in Safety Evaluation Associated with Amendment No. 148 Regarding Alternative Source Term
Project stage: Approval
ML0906100352009-03-0909 March 2009
Correction of Inadvertent Errors on Two TS Pages in Amendment No. 148
Project stage: Other
2006-04-13
[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
From: Peter Tam To: Loeffler, Rick; Salamon, Gabor Date: 06/29/2006 8:36:47 AM
Subject:
Monticello: Draft RAI (Radiological) re. Full-Scope Application of Alternative Source Term Gabe, Rick:
Our radiological consequences reviewer, Michelle Hart, has written the following draft questions for discussion with you in a telephone conference. We will decide how to disposition these draft questions in the conference:
- 1. What is the basis for the assumed reduction in leakage through the main steam isolation valves (MSIVs) at 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in the loss of coolant accident (LOCA) dose analysis?
The submittal indicates that the reduction in leakage into the main steam lines is consistent with the reduction in primary containment leakage based on reduction of primary containment pressure. How does the reduction in primary containment pressure lead to a reduction in MSIV leakage?
- 2. Does the LOCA analysis modeling of iodine aerosol deposition in the MSIV leakage pathway account for the preceding removal of aerosols in the primary containment by natural deposition?
- 3. Was potential iodine revolatilization accounted for in the modeling of iodine removal for the LOCA MSIV leakage pathway? Does the piping temperature profile used to determine the aerosol deposition efficiency include heating from aerosols deposited in the piping?
- 4. Please provide the control room shine dose calculations, including any diagrams that indicate the location of the source(s) and receptor(s).
Please call me to set up the telephone conference for the near future, but we will avoid Friday July 7.
The sole purpose of this e-mail is to prepare you and others for the requested telephone conference. It does not formally request for information, and it does not state a formal NRC staff position.
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: Arias, Jesus; Hart, Michelle Mail Envelope Properties (44A3C95F.4AD : 12 : 35330)
Subject:
Monticello: Draft RAI (Radiological) re. Full-Scope Application of Alternative Source Term Creation Date 06/29/2006 8:36:47 AM From: Peter Tam Created By: PST@nrc.gov
Recipients Action Date & Time nmcco.com Transferred 06/29/2006 8:37:36 AM Gabor.Salamon (Gabor Salamon)
Jesus.Arias CC (Jesus Arias)
Richard.Loeffler (Rick Loeffler) nrc.gov OWGWPO04.HQGWDO01 Delivered 06/29/2006 8:36:52 AM MLH3 CC (Michelle Hart) Opened 06/29/2006 8:38:06 AM Post Office Delivered Route nmcco.com OWGWPO04.HQGWDO01 06/29/2006 8:36:52 AM nrc.gov Files Size Date & Time MESSAGE 2960 06/29/2006 8:36:47 AM 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
