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| {{#Wiki_filter:}} | | {{#Wiki_filter:September 8, 2003 To: Virginia Electric and Power Company FROM: Stephen Monarque, Project Manager /RA/ |
| | Project Directorate II, Section 1 Division of Licensing Project Management Office of Nuclear Reactor Regulation |
| | |
| | ==SUBJECT:== |
| | NORTH ANNA POWER STATION, UNITS 1 AND 2 - FACSIMILE TRANSMISSION OF QUESTIONS ON PROPOSED LICENSE AMENDMENT TO USE FRAMATOME ANP ADVANCED MARK-BW FUEL (TACS MB4714, AND MB4715) |
| | A facsimile of the attached questions on containment analysis was transmitted on September 8, 2003 to Mr. Tom Shaub of Virginia Electric and Power Company (VEPCO). |
| | These questions were transmitted to VEPCO in order to support a conference call on these questions. |
| | ADAMS ACCESSION NO. ML032731572 |
| | |
| | ==Enclosure:== |
| | Request for Additional Information |
| | |
| | REQUEST FOR ADDITIONAL INFORMATION NORTH ANNA POWER STATIONS, UNITS 1 AND 2 PROPOSED LICENSE AMENDMENT TO USE FRAMATOME ANP FUEL |
| | : 1. Reference 15 of Topical Report EMF-2103 Revision 0 is Supplement 1 to Revision 2 of ICECON. This has not been supplied to the NRC staff. What is its relevance to the review of the calculation of minimum containment pressure? |
| | : 2. Please confirm that the version of ICECON, documented in XN-CC-39 dated August 1975 and approved by the NRC staff in a June 30, 1978 SER, is identical with the version documented in EMF-CC-39(P) (dated November 1999). If this is not the case, please describe any differences and explain their effect on the calculated minimum containment pressure. |
| | : 3. The NRC SER approving ICECON (June 30, 1978) requires, as a condition for approval, that a user of ICECON will provide justification for the values of the area and heat capacities of the structural heat sinks used in the analysis of minimum containment pressure. Please provide justification for the values used. It is not necessary to provide the values themselves. |
| | : 4. An important consideration in calculating containment pressure is the distribution of the break flow as it enters the containment atmosphere. Please describe the assumption used. CONTEMPT contains a temperature flash model. If temperature flash was used for minimum containment pressure calculations please explain why this is acceptable since temperature flash tends to overestimate pressure. |
| | : 5. The calculation of peak cladding temperature conservatively assumes a worst single failure. However, it is not conservative to assume a single failure for the minimum containment pressure portion of the calculation. Please explain how the best estimate LOCA methods accommodate these considerations. |
| | : 6. What is the basis for assuming the distribution of volumes from minimum to maximum is uniform? (Table 7.2-3 of the May 6, 2003 letter) Why is no standard deviation specified?}} |
Latest revision as of 10:58, 25 March 2020
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MONTHYEARML0213503742002-05-13013 May 2002 Request for Withholding Information from Public Disclosure by Letter Dated 03/28/2002 Project stage: Withholding Request Acceptance ML0220500122002-07-23023 July 2002 Ltr, Proposed Technical Specification Changes and Exemption Request Regarding Use of Framatome and Advanced Mark-BW Fuel Project stage: Other ML0302701122003-01-24024 January 2003 Fax, Request for Additional Information Framatome Fuel Transition Project stage: RAI ML0308003902003-03-21021 March 2003 Request for Additional Information on Small-break LOCA Evaluation in Support of Proposed Technical Specifications Changes and Exemption Request to Use Framatome Anp Advanced Mark-BW Fuel Project stage: RAI ML0309104342003-03-31031 March 2003 Facsimile Transmission of Questions for Proposed Technical Specifications Changes and Exemption Request, Use of Framatome Anp Advanced Mark-BW Fuel Project stage: Other ML0316106732003-06-10010 June 2003 Withholding from Public Disclosure, Document Response to Request for Additional Information and Revised Pages for March 2002 Evaluation Report - Framatome Fuel Transition Program Technical Specification Change Project stage: RAI ML0316403882003-06-12012 June 2003 N. Anna, Units 1 and 2 - Framatome Anp Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML0323200022003-08-19019 August 2003 Facsimile Transmission of Questions for Proposed Technical Specifications Changes, Use of Framatome Anp Advanced Mark-BW Fuel Project stage: Other ML0323906432003-08-20020 August 2003 Request for Additional Information Regarding Realistic Large Break Loss of Coolant Accident Analysis Results for Proposed TS Changes & Exemption Request for Use of Framatome Anp Advanced Mark-BW Fuel Project stage: Request ML0326807202003-08-29029 August 2003 Submittal of Approved Topical Report VEP-FRD-42, Revision 2.0-A, Reload Nuclear Design Methodology for Application Project stage: Request ML0325411792003-09-0404 September 2003 Proposed Technical Specifications Changes and Exemption Request for Use of Framatome Anp Advanced Mark - Bw Fuel Small Break Loss of Coolant Accident (SBLOCA) Analysis Results Request for Additional Information Project stage: Request ML0325804552003-09-0505 September 2003 Proposed Technical Specifications Changes and Exemption Request for Use of Framatome Anp Advanced Mark-BW Fuel Supplemental Information for Realistic Large Break Loss of Coolant Accident (Rlbloca) Analysis Results Project stage: Supplement ML0327315722003-09-0808 September 2003 Facsimile Transmission of Questions on Proposed License Amendment to Use Framatome Anp Advanced Mark-BW Fuel Project stage: Other ML0325500032003-09-11011 September 2003 Facsimile Transmission of Questions on Proposed License Amendment to Use Framatome Anp Advanced Mark-BW Fuel Project stage: Other ML0327314452003-09-22022 September 2003 Supplemental Information for Realistic Large Break Loss of Coolant Accident (Rlbloca) Analysis Results Proposed Technical Specifications Changes and Exemption Request for Use of Framatome Anp Advanced Mark-BW Fuel Project stage: Supplement ML0327903962003-09-26026 September 2003 Proposed Technical Specifications Changes and Exemption Request for Use of Framatome Anp Advanced Mark-BW Fuel, Request for Additional Information Pertaining to the Icecon Modules in the Realistic Large Break LOCA (Rlbloca) Project stage: Request ML0327904052003-09-26026 September 2003 Proposed Technical Specifications Changes and Exemption Request for Use of Framatome Anp Advanced Mark-BW Fuel, Supplemental Information for Realistic Large Break Loss of Coolant Accident (Rlbloca) Analysis Results Project stage: Supplement ML0328205902003-10-0606 October 2003 Meeting Summary - Usnrc/Vepco & Anp - to Discuss Framatome Fuel Transition Program at North Anna, Units 1 and 2 Project stage: Meeting ML0332404512003-11-10010 November 2003 Proposed Technical Specifications Changes and Exemption Request for Use of Framatome Anp Advanced Mark-BW Fuel Supplement Information for Realistic Large Break Loss of Coolant Accident (Rlbloca) Analysis Results Project stage: Supplement ML0401405102004-01-0606 January 2004 Supplemental Information for Realistic Large Break Loss of Coolant Accident (Rlbloca) Containment Pressure Analysis Proposed Technical Specifications Change & Exemption Request for Use of Framatome Anp Advanced Mark-BW Fuel Project stage: Supplement ML0401405642004-01-13013 January 2004 Facsimile Transmission of Question for Proposed Technical Specifications Changes, Use of Framatome Anp Advanced Mark-BW Fuel (Tacs MB4714 and MB4715) Project stage: Other ML0402908102004-01-22022 January 2004 Proposed Technical Specifications Changes & Exemption Request for Use of Framatome Anp Advanced Mark-BW Fuel, Response to Request for Additional Information Regarding Assessment of Fuel Assembly Bow Concern Project stage: Response to RAI ML0405505522004-02-12012 February 2004 Proposed Technical Specifications Changes and Exemption Request for Use of Framatome Anp Advanced Mark-BW Fuel, Supplemental Information for Loss of Coolant Accident Mixed Core Effects Project stage: Supplement ML0406909252004-03-0101 March 2004 Supplemental Information for SBLOCA Slot Breaks, Per Proposed Technical Specifications Changes and Exemption Request for Use of Framatome Anp Advanced Mark-BW Fuel Project stage: Supplement ML0409703402004-04-0101 April 2004 Tech Spec Pages for Amendment No. 216 Use of Framatome Anp Advanced Mark-BW Fuel Project stage: Other ML0409600402004-04-0101 April 2004 Issuance of License Amendment Use of Framatome Fuel, TAC MB4715 Project stage: Approval ML0419502182004-07-0101 July 2004 Day Report of Emergency Core Cooling System (ECCS) Evaluation Model Changes Pursuant to the Requirements of 10 CFR 50.46 Project stage: Request ML0423305602004-08-20020 August 2004 Technical Specification Amendment No. 237, Pages 2.0-1, 4.0-1, 5.6-3, 5.6-4, 5.6-5 Project stage: Other ML0423306592004-08-20020 August 2004 8/20/04, North Anna, Unit 1, Issuance of Amendment Re. Conversion to Framatome Advanced Mark-BW Fuel Project stage: Approval 2003-09-11
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Category:Letter
MONTHYEARML24221A1892024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Nansemond Indian Nation ML24221A1932024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Upper Mattaponi Tribe ML24221A1862024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Eastern Band of Cherokee Indians ML24221A1842024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Delaware Nation, Oklahoma ML24221A1902024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Pamunkey Indian Tribe ML24163A3002024-08-0808 August 2024 Request for Relief Request N1-I5-NDE-007 Inservice Inspection Alternative ML24206A0052024-08-0808 August 2024 SLR Final EIS Letter to Achp ML24221A1872024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Eastern Shawnee Tribe of Oklahoma ML24221A1942024-08-0808 August 2024 Tribal Section 106 Letters-North Anna-United Keetoowah Band of Cherokee Indians in Oklahoma ML24206A0062024-08-0808 August 2024 Notice of Availability of the Final Environmental Impact Statement for the North Anna Nuclear Power Station Unit Numbers 1 and 2 Subsequent License Renewal (Docket Numbers: 50-338 and 50-339) ML24221A1812024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Catawba Indian Nation ML24221A1852024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Delaware Tribe of Indians ML24208A0142024-08-0808 August 2024 Tribal Section 106 Letters-North Anna-Absentee-Shawnee Tribe of Indians of Oklahoma ML24221A1922024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Tuscarora Nation of New York ML24221A1882024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Monacan Indian Nation ML24221A1832024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Chickahominy Indian Tribe-Eastern Division ML24221A1822024-08-0808 August 2024 Tribal Section 106 Letters - North Anna - Chickahominy Indian Tribe ML24221A1912024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Rappahannock Tribe, Inc IR 05000338/20240022024-08-0202 August 2024 Integrated Inspection Report 05000338/2024002 and 05000339/2024002 ML24206A0432024-07-26026 July 2024 Feis - Letter to the Applicant ML24206A0902024-07-24024 July 2024 Owners Activity Report ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24143A1622024-06-12012 June 2024 – Correction to Issuance of Amendment Nos. 297 and 280 and Surry Units 1 and 2, Correction to Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code IR 05000338/20240012024-05-10010 May 2024 Integrated Inspection Report 05000338/2024001 and 05000339/2024001 IR 05000338/20244032024-04-30030 April 2024 – Security Baseline Inspection Report 05000338-2024403 and 05000339-2024403 ML24054A0142024-04-22022 April 2024 Issuance of Amendment Nos. 297 and 280, and Surry Power Station Unit Nos. 1 and 2, Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times ML24110A1462024-04-18018 April 2024 Independent Spent Fuel Storage Installation (Sfsi) - Annual Radiological Environmental Operating Report ML24110A1392024-04-18018 April 2024 Annual Environmental Operating Report ML24110A1502024-04-18018 April 2024 Independent Spent Fuel Storage Installation (ISFSI) - Annual Radioactive Effluent Release Report ML24087A0572024-04-16016 April 2024 Correction to Issuance of Amendment Nos. 296 and 279 ML24088A2692024-03-27027 March 2024 Core Operating Limits Report Cycle 31 Pattern Sos Revision 0 ML24086A4292024-03-25025 March 2024 Response to Request for Additional Information Associated with Alternative Request N1-I5-NDE-007 Request to Deter Additional Required Reactor Coolant Pump Casing Inspection ML24082A2742024-03-22022 March 2024 Request for Approval of Alternative Request N1-I5-NDE-007 to Deter Additional Required Reactor Coolant Pump Casing Inspection ML24086A4682024-03-21021 March 2024 Summary of Facility Changes, Tests and Experiments ML24074A3012024-03-14014 March 2024 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000338-2024403 and 05000339-2024403) IR 05000338/20244012024-03-0808 March 2024 Security Baseline Inspection Report 05000338/2024401, 05000339/2024401 and 07200016/2024401 IR 05000338/20230062024-02-28028 February 2024 Annual Assessment Letter for North Anna Power Station, Units 1 and 2 - NRC Inspection Reports 05000338/2023006 and 05000339/2023006 IR 05000338/20240102024-02-22022 February 2024 Notification of an NRC Fire Protection Team Inspection - NRC Inspection Report 05000338/2024010- 05000339/2024010- RFI ML24057A0612024-02-19019 February 2024 and Virgil C. Summer Power Nuclear Stations - Nuclear Property Insurance Coverage ML24032A1112024-02-0101 February 2024 Owner'S Activity Report for North Anna, Unit 2, Refueling Outage N2R29 - First Period of the Fifth ISI Interval ML24032A4662024-01-16016 January 2024 Response to Comments on Draft Vpdes Permit No. VA0052451 ML24017A0802024-01-11011 January 2024 Notification of Licensed Operator Initial Examination 05000338/2024301 and 05000339/2024301 ML24003A8472024-01-0909 January 2024 Letter to Tom Jonathan, Chief, Tuscarora Nation, Notice of Availability of the Draft Site-Specific EIS for North Anna Power Station, Units 1 and 2, Subsequent License Renewal ML24003A8352024-01-0909 January 2024 Letter to Acee Watt, Thpo, United Keetoowah Band of Cherokee Indians in Oklahoma Re Notice of Availability of the Draft Site-Specific Environmental Impact Statement for North Anna Power Station Subsequent License Renewal ML24003A8492024-01-0909 January 2024 Letter to W. Frank Adams, Chief, Upper Mattaponi Tribe Re Re Notice of Availability of the Draft Site-Specific Environmental Impact Statement for North Anna Power Station Subsequent License Renewal ML24003A8432024-01-0909 January 2024 Letter to Robert Gray, Chief, Pamunkey Indian Tribe, Notice of Availability of the Draft Site-Specific EIS for North Anna Power Station, Units 1 and 2, Subsequent License Renewal ML24003A8362024-01-0909 January 2024 Notice of Availability of the Draft Site-Specific Environmental Impact Statement for the North Anna Power Station, Units 1 and 2, Subsequent License Renewal ML24003A8452024-01-0909 January 2024 Letter to Stephen Adkins, Chief, Chickahominy Indian Tribe, Notice of Availability of Draft Site-Specific Environmental Impact Statement for North Anna Power Station Units 1 and 2, Subsequent License Renewal 2024-08-08
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24087A0112024-03-23023 March 2024 NRR E-mail Capture - Draft RAIs for Reactor Coolant Pump (RCP) Relief Request (L-2024-LLR-0022) ML23318A1172023-11-13013 November 2023 NRR E-mail Capture - Formal Issuance of RAIs for North Anna Technical Support Center (TSC) License Amendment Request (LAR) (L-2023-LLA-0006) ML23257A2092023-09-14014 September 2023 NRR E-mail Capture - Formal Issuance of 2nd Round RAIs for Surry Units 1&2 and North Anna Units 1&2 Emergency Plans LAR ML23243A9862023-08-31031 August 2023 NRR E-mail Capture - Draft RAIs for EP Staff Augmentation Times LAR (L-2022-LLA-0166) ML23219A1602023-08-0707 August 2023 003 Radiation Safety Baseline Inspection Information Request ML23171B0522023-06-20020 June 2023 NRR E-mail Capture - RAI for Review of Appendix F to DOM-NAF-2-P (Redacted) ML23081A5282023-04-26026 April 2023 Request for Additional Information - North Anna Subsequent License Renewal Application Environmental Review ML23075A0232023-03-15015 March 2023 NRR E-mail Capture - RAI - License Amend Req (LAR) to Revise Tech Spec (Ts) 3.6.8 Limiting Condition for Operation to Remove Refueling Water Chemical Addition Tank and Replace the Containment Sump Buffer North Anna, 1 and 2 (L-2022-LLA-0162 ML23060A0932023-03-0101 March 2023 NRR E-mail Capture - Formal Issuance of RAIs for Surry/North Anna Emergency Plans LAR ML23059A2282023-02-28028 February 2023 NRR E-mail Capture - Draft RAIs for Containment Buffer Change to Natb (L-2022-LLA-0162) ML22251A1292022-09-0909 September 2022 Request for Additional Information Related to Response to Generic Letter 2004-04 ML22242A0452022-08-23023 August 2022 NRR E-mail Capture - Dominion GL 04-02 Response Draft RAIs (L-2017-LRC-0000) ML22083A2102022-03-24024 March 2022 NRR E-mail Capture - Draft RAI - Relief Request N2-14-LMT-003 Fourth Ten Year Inservice Inspection Interval ML21327A3652021-11-23023 November 2021 NRR E-mail Capture - Draft RAI for TSTF-577 LAR ML21322A0962021-11-18018 November 2021 Final Request for Additional Information Set 5 - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Email ML21322A0992021-11-18018 November 2021 Final Request for Additional Information Set 5 - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Enclosure ML21256A0672021-09-13013 September 2021 Final Request for Confirmation of Information Set 2 - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Email ML21256A0692021-09-13013 September 2021 Final Request for Confirmation of Information Set 2 - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Request for Confirmation of Information ML21238A0942021-08-25025 August 2021 Draft Request for Additional Information Set Z - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Email ML21238A0982021-08-25025 August 2021 Draft Request for Additional Information Set Z - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Enclosure ML21225A5022021-08-13013 August 2021 Request for Additional Information for North Anna Power Station, Units 1 and 2, Surry Power Station, Units 1 and 2, and Millstone Power Station, Units 2 and 3, Appendix E of Fleet Report Com-Naf-2 (EPID:L02021-LLT-0000) Public Version ML21195A2442021-07-13013 July 2021 NRR E-mail Capture - Draft RAI Appendix E to Topical Report DOM-NAF-2 Qualification of the Framatome BWU-I CHF Correlation in the Dominion Energy VIPRE-D Computer Code ML21188A1632021-07-0707 July 2021 Final Request for Additional Information Set 4 - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Email ML21188A1652021-07-0707 July 2021 Final Request for Additional Information Set 4 - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Enclosure ML21174A1952021-06-23023 June 2021 Safety RAIs - Set Y - Draft - Enclosure ML21166A3512021-06-15015 June 2021 Safety RAIs - Set 4 - Draft ML21123A2972021-05-0303 May 2021 Final Request for Additional Information Set 3 - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - E-mail ML21123A2982021-05-0303 May 2021 Final Request for Additional Information Set 3 - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Enclosure ML21091A0032021-04-0101 April 2021 Final Request for Additional Information Set 2 - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Enclosure 1 - RAIs ML21091A0042021-04-0101 April 2021 SLRA Safety Review - Withdrawn Requests for Information (EPID No. L-2020-SLR-0000) - Enclosure 2 ML21076A4622021-03-17017 March 2021 NRR E-mail Capture - Draft RAI for Versatile Internals and Component Program for Reactors Vipre Code Review (L-2021-LLT-0000) ML21075A0032021-03-12012 March 2021 Emergency Preparedness Exercise Inspection Request for Information for - Brunswick, Catawba, North Anna, Oconee, Vogtle 1 & 2 ML21063A5602021-03-0404 March 2021 Final Request for Additional Information Set 1 - North Anna SLRA Safety Review (EPID L-2020-SLR-0000) - Enclosure ML21049A0212021-02-17017 February 2021 Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000338/2021012 and 05000339/2021012) and Request for Information (RFI) ML21028A3902021-01-29029 January 2021 Request for Additional Information - North Anna Subsequent License Renewal Application Environmental Review (EPID Number: L-2020-SLE-0000) (Docket: 50-338 and 50-339) ML21028A4352021-01-28028 January 2021 Notification of Target Set Inspection and Request for Information (NRC Inspection Report No. 05000338/2021404 and 05000339/2021404) ML21012A3412021-01-22022 January 2021 Requests for Confirmation of Information for the Environmental Review of the North Anna Power Station, Units 1 and 2, Subsequent License Renewal Application (EPID Number: L-2020-SLE-0000) (Docket: 50-338 and 50-339) ML21019A4512021-01-19019 January 2021 Notification of Inspection and Request for Information ML20316A0422020-11-10010 November 2020 NRR E-mail Capture - FW: Draft RAI for North Anna Unit 2 Steam Generator Tube Inspection Report (ML19179A075) ML20223A3412020-08-10010 August 2020 003 Radiation Safety Baseline Inspection Information Request ML20218A4282020-08-0505 August 2020 Notification of Inspection and Request for Information ML20125A0762020-05-0101 May 2020 NRR E-mail Capture - Draft RAI Related to Revised Reactor Vessel Material Surveillance Capsule Withdrawal Schedule Dominion Energy Virginia North Anna Power Station Units 1 and 2 (L-2020-LLL-0038) ML20113A5792020-04-21021 April 2020 NRR E-mail Capture - Draft RAI North Anna Fifth 10-year Interval Relief Request (L-2020-LLR-0023) ML19354B6142019-12-20020 December 2019 NRR E-mail Capture - Draft RAI for North Anna Relief Request P-9 ML19317F1042019-11-0707 November 2019 NRR E-mail Capture - Draft RAIs for SB LOCA LAR (Non Prop) ML19191A2512019-07-10010 July 2019 NRR E-mail Capture - Request for Additional Information Open Phase Condition LAR ML19169A0962019-06-17017 June 2019 NRR E-mail Capture - Request for Additional Information Emergency Action Level Scheme Change for Millstone Power Station - Units 1, 2, and 3, North Anna Power Station - Units 1 and 2, and Surry Power Station - Units 1 and 2 ML19162A0052019-06-10010 June 2019 NRR E-mail Capture - Draft RAIs for Dominion EAL Scheme Change ML19108A1902019-04-18018 April 2019 Emergency Preparedness Program Inspection Request for Information ML19060A2432019-03-0101 March 2019 Related to License Amendment Request to Address Open Phase Conditions 2024-03-23
[Table view] |
Text
September 8, 2003 To: Virginia Electric and Power Company FROM: Stephen Monarque, Project Manager /RA/
Project Directorate II, Section 1 Division of Licensing Project Management Office of Nuclear Reactor Regulation
SUBJECT:
NORTH ANNA POWER STATION, UNITS 1 AND 2 - FACSIMILE TRANSMISSION OF QUESTIONS ON PROPOSED LICENSE AMENDMENT TO USE FRAMATOME ANP ADVANCED MARK-BW FUEL (TACS MB4714, AND MB4715)
A facsimile of the attached questions on containment analysis was transmitted on September 8, 2003 to Mr. Tom Shaub of Virginia Electric and Power Company (VEPCO).
These questions were transmitted to VEPCO in order to support a conference call on these questions.
ADAMS ACCESSION NO. ML032731572
Enclosure:
Request for Additional Information
REQUEST FOR ADDITIONAL INFORMATION NORTH ANNA POWER STATIONS, UNITS 1 AND 2 PROPOSED LICENSE AMENDMENT TO USE FRAMATOME ANP FUEL
- 1. Reference 15 of Topical Report EMF-2103 Revision 0 is Supplement 1 to Revision 2 of ICECON. This has not been supplied to the NRC staff. What is its relevance to the review of the calculation of minimum containment pressure?
- 2. Please confirm that the version of ICECON, documented in XN-CC-39 dated August 1975 and approved by the NRC staff in a June 30, 1978 SER, is identical with the version documented in EMF-CC-39(P) (dated November 1999). If this is not the case, please describe any differences and explain their effect on the calculated minimum containment pressure.
- 3. The NRC SER approving ICECON (June 30, 1978) requires, as a condition for approval, that a user of ICECON will provide justification for the values of the area and heat capacities of the structural heat sinks used in the analysis of minimum containment pressure. Please provide justification for the values used. It is not necessary to provide the values themselves.
- 4. An important consideration in calculating containment pressure is the distribution of the break flow as it enters the containment atmosphere. Please describe the assumption used. CONTEMPT contains a temperature flash model. If temperature flash was used for minimum containment pressure calculations please explain why this is acceptable since temperature flash tends to overestimate pressure.
- 5. The calculation of peak cladding temperature conservatively assumes a worst single failure. However, it is not conservative to assume a single failure for the minimum containment pressure portion of the calculation. Please explain how the best estimate LOCA methods accommodate these considerations.
- 6. What is the basis for assuming the distribution of volumes from minimum to maximum is uniform? (Table 7.2-3 of the May 6, 2003 letter) Why is no standard deviation specified?