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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
MONTHYEARIR 05000338/20240032024-10-28028 October 2024 – Integrated Inspection Report 05000338-2024003 and 05000339-2024003 ML24283A0392024-10-0909 October 2024 Annual Submittal of Technical Specification Bases Changes Pursuant to Technical Specification 5.5.13.D ML24281A1372024-10-0707 October 2024 ISFSI - Submittal of Cask Registration for Spent Fuel Storage 05000338/LER-2024-001-01, Automatic Reactor Trip Due to Prni High Negative Rate2024-09-24024 September 2024 Automatic Reactor Trip Due to Prni High Negative Rate IR 05000338/20244202024-09-23023 September 2024 Security Baseline Inspection Report 05000338/2024420 and 05000339/2024420, Cover Letter ML24243A0872024-09-20020 September 2024 Response to EPA Comments Regarding the Final Site Specific Supplement to the Generic Eist for License Renewal North Anna Power Station, Units 1 and 2 IR 05000338/20244022024-09-17017 September 2024 Security Baseline Inspection Report 05000338/2024402 and 05000339/2024402 ML24215A2622024-08-28028 August 2024 Transmittal Letter for Subsequent Renewed License IR 05000338/20240052024-08-27027 August 2024 Updated Inspection Plan for North Anna Power Station, Units 1 and 2 (Report 05000338/2024005 and 05000339/2024005) 05000339/LER-2024-001-01, Loss of Generator Field for 2J Eog During 2-PT-82.282024-08-20020 August 2024 Loss of Generator Field for 2J Eog During 2-PT-82.28 ML24234A0742024-08-15015 August 2024 Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Letter OG-23-63, NEI 03-08 Needed Guidance: PWR Thermal Shield Flexure Inspection Requirements ML24221A1932024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Upper Mattaponi Tribe ML24206A0052024-08-0808 August 2024 SLR Final EIS Letter to Achp ML24221A1882024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Monacan Indian Nation ML24221A1842024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Delaware Nation, Oklahoma ML24221A1922024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Tuscarora Nation of New York ML24221A1912024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Rappahannock Tribe, Inc ML24221A1942024-08-0808 August 2024 Tribal Section 106 Letters-North Anna-United Keetoowah Band of Cherokee Indians in Oklahoma ML24221A1852024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Delaware Tribe of Indians ML24221A1832024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Chickahominy Indian Tribe-Eastern Division 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) ML24163A3002024-08-0808 August 2024 Request for Relief Request N1-I5-NDE-007 Inservice Inspection Alternative ML24208A0142024-08-0808 August 2024 Tribal Section 106 Letters-North Anna-Absentee-Shawnee Tribe of Indians of Oklahoma ML24221A1872024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Eastern Shawnee Tribe of Oklahoma ML24221A1862024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Eastern Band of Cherokee Indians ML24221A1902024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Pamunkey Indian Tribe ML24221A1812024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Catawba Indian Nation ML24221A1822024-08-0808 August 2024 Tribal Section 106 Letters - North Anna - Chickahominy Indian Tribe ML24221A1892024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Nansemond Indian Nation ML24241A0692024-08-0606 August 2024 ISFSI, Submittal of Cask Registration for Spent Fuel Storage 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 05000338/LER-2024-001, Automatic Reactor Trip Due to Prni High Negative Rate2024-07-25025 July 2024 Automatic Reactor Trip Due to Prni High Negative Rate 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 05000339/LER-2024-001, Loss of Generator Field for 2J EDG During 2-PT-82.282024-06-0505 June 2024 Loss of Generator Field for 2J EDG During 2-PT-82.28 ML24165A1462024-06-0505 June 2024 Loss of Generator Field for 2J EDG During 2-PT-82.28 IR 05000338/20240102024-05-24024 May 2024 NRC Fire Protection Team Inspection (FPTI) Report 05000338/2024010 and 05000339/2024010 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 ML24110A1502024-04-18018 April 2024 Independent Spent Fuel Storage Installation (ISFSI) - Annual Radioactive Effluent Release Report ML24110A1392024-04-18018 April 2024 Annual Environmental Operating 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 2024-09-24
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January 13, 2004 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 QUESTION FOR PROPOSED TECHNICAL SPECIFICATIONS CHANGES, USE OF FRAMATOME ANP ADVANCED MARK-BW FUEL (TACS MB4714, AND MB4715)
A facsimile of the attached question on Rod-to-Rod Radiation was transmitted on January 13, 2004 to Mr. Tom Shaub of Virginia Electric and Power Company (VEPCO). This question was transmitted in order to allow VEPCO to determine the response time needed to address this request for additional information.
JU4LOUD 101-6
NORTH ANNA POWER STATION, UNITS 1 AND 2 ROD-TO-ROD RADIATION QUESTION The NRC staff has developed an example of a thermal radiation problem that could be used to justify the use of the RELAP 5 radiation model presented in Topical Report 2103(P), Revision 0, "Realistic Large Break LOCA Methodology for Pressurized Water Reactors."
A. In this example, a 6x6 array of rods in the hot bundle are selected, with the following bounding conditions presented below.
- 1) The limiting rod is located in position # 16 roughly in the center of the array.
- 2) The limiting rod peak cladding temperature (PCT) is 2032 F.
- 3) All remaining rods in the array are at a temperature of 1975 F.
- 4) The fence is at a temperature of 1975 F.
- 5) No guide tubes were modeled in this array.
Using these bounding conditions in this example, the minimum equivalent heat transfer coefficient for rod no. 16 is calculated to be 2.6 Btu/hr-ft2-F. This value bounds the FLECHT test data equivalent heat transfer coefficients of 1.87, 2.22, and 1.90 Btu/hr-ft2 -F for FLECHT Tests 31504, 13609, and 13914, respectively. The temperature value of 1975 F for all of the rods surrounding the hot rod bounds the power distribution in the vicinity of the PCT rod.
Specifically, a pin census would show that the difference in peaking factors between the hot rod and the rods surrounding the hot rod (nearest neighbors) is bounded by the 1975 F temperature assumed for the neighboring rods. If the hot rod temperature is 2032 F and the average hot bundle temperature is 1838 F, then the use of the actual peaking factors for the hot rod and the rods surrounding the hot rod would result in rod temperatures lower than 1975 F.
This demonstrates that rod temperatures, in the intermediate range between the highest temperature rod and the average hot bundle temperature, can be obtained by interpolating both the peaking factors and the associated temperatures from the highest temperature rod and the average hot bundle temperature along with their associated peaking factors.
Note, in the above example, the highest temperature rod is rod # 16 with a temperature of 2032 F and peaking factor of Fhr. The temperature of the average bundle rod is 1838 F with a peaking factor of Fave. If the actual peaking factors for the rods surrounding the hot rods are used to generate their temperatures (something in the intermediate range between Fhr and Fave), this cause temperatures to be lower than the assumed neighboring temperatures of 1975 F. Thus, the chosen power distribution (or temperatures of neighboring rods) bounds the PDQ pin census distributions during the fuel cycle.
B. Regarding its proposed license amendment to implement Framatome Advanced Mark-BW Fuel at North Anna Power Station, Units 1 and 2, Virginia Electric and Power Company is requested to confirm that the separation in power between the highest temperature rod and the surrounding rods bounds the power distribution for potential peak temperature rod locations in the core (i.e all rods in the hot bundle within the physics uncertainty on peaking factor) during the entire fuel cycle.