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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 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 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 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 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 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 2003-08-19
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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 05000338/20240102024-05-24024 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 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 ML24110A1462024-04-18018 April 2024 Independent Spent Fuel Storage Installation (Sfsi) - Annual Radiological Environmental Operating Report 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 ML23332A7272024-01-0909 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 ML24003A8422024-01-0909 January 2024 Letter to Paul Barton, Thpo, Eastern Shawnee Tribe of Oklahoma, Notice of Availability of Draft Site-Specific Environmental Impact Statement for North Anna Power Station Units 1 and 2, 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 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 ML24003A8372024-01-0909 January 2024 Letter to Elizabeth Toombs, Thpo, Cherokee Nation, Notice of Availability of the Draft Site-Specific EIS for North Anna Power Station, Units 1 and 2, Subsequent License Renewal ML24003A8402024-01-0909 January 2024 Letter to Katelyn Lucas, Thpo, Delaware Nation, Oklahoma, Notice of Availability of Draft Site-Specific Environmental Impact Statement for North Anna Power Station Units 1 and 2, Subsequent License Renewal ML24003A8412024-01-0909 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 ML24003A8392024-01-0909 January 2024 Letter to Gerald Stewart, Chief, Chickahominy Indian Tribe, Eastern Division Re Re Notice of Availability of the Draft Site-Specific Environmental Impact Statement for North Anna Power Station Subsequent License Renewal 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 ML24003A8382024-01-0909 January 2024 Letter to G. Anne Richardson, Chief, Rappahannock Tribe, Inc., Notice of Availability of Draft Site-Specific Environmental Impact Statement for North Anna Power Station Units 1 and 2, Subsequent License Renewal ML24003A8462024-01-0909 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 ML24003A8482024-01-0909 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 ML24003A8442024-01-0909 January 2024 Letter to Russell Townsend, Thpo, Eastern Band of Cherokee Indians 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 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 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 2024-08-08
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 September 22, 2003 U. S. Nuclear Regulatory Commission Serial No. 03-313D Attention: Document Control Desk NLOS/ETS Washington, D.C. 20555 Docket Nos. 50-338/339 License Nos. NPF-4/7 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
NORTH ANNA POWER STATION UNITS I AND 2 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 In a May 6, 2003 letter (Serial No.03-313), Dominion submitted the Realistic Large Break LOCA (RLBLOCA) results for Advanced Mark-BW fuel in North Anna Unit 2 to support the NRC's review of a proposed amendment and exemptions that will permit North Anna Units 1 and 2 to use Framatome ANP Advanced Mark-BW fuel. On August 20, 2003 (Serial No. 03-313A) Dominion provided a response to an August 6, 2003 NRC request for additional information regarding the RLBLOCA results. In an August 28, 2003 meeting to discuss the RLBLOCA analysis results, the NRC staff requested further clarification of Dominion's August 20, 2003 responses. Supplemental information for Questions 1, 5, 9, and 10b was provided on September 5, 2003 (Serial No. 03-313C). The attachment to this letter provides the requested clarification for Questions 6, 11 a and additional questions provided in an August 29, 2003 facsimile.
This information is applicable to both North Anna Units 1 and 2 even though the RAls received were specific to Unit 2.
To support the use of Framatome Advanced Mark-BW fuel in North Anna Unit 2, Cycle 17, we respectfully request the NRC to complete their review and approval of the license amendment and associated exemptions by September 30, 2003. We appreciate your consideration of our technical and schedular requests. If you have any questions or require additional information, please contact us.
Very truly yours, Leslie N. Hartz Vice President - Nuclear Engineering Commitments made in this letter: None Attachment A0-ool
cc: U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW Suite 23T85 Atlanta, Georgia 30303 Mr. J. E. Reasor, Jr.
Old Dominion Electric Cooperative Innsbrook Corporate Center 4201 Dominion Blvd.
Suite 300 Glen Allen, Virginia 23060 Commissioner Bureau of Radiological Health 1500 East Main Street Suite 240 Richmond, VA 23218 Mr. S. R. Monarque NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 8-H112 Rockville, MD 20852 Mr. M. J. Morgan NRC Senior Resident Inspector North Anna Power Station
SN: 03-313D Docket Nos.: 50-338/339
Subject:
Supplemental Information - Proposed TS Change RLBLOCA Analysis Results - Use of Framatome ANP Advanced Mark-BW Fuel COMMONWEALTH OF VIRGINIA )
)
COUNTY OF HENRICO )
The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by Leslie N. Hartz, who is Vice President - Nuclear Engineering, of Virginia Electric and Power Company. She has affirmed before me that she is duly authorized to execute and file the foregoing document in behalf of that Company, and that the statements in the document are true to the best of her knowledge and belief.
Acknowledged before me this 22nd day of September, 2003.
My Commission Expires: March 31, 2004.
/
Notar Public
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Dominion Supplemental Responses to NRC Request for Additional Information Questions 6 and 11 a from Dominion's August 20,2003 letter (Serial No. 03-313A) and questions posed In an August 29,2003 NRC facsimile In an August 28, 2003 meeting, the NRC staff requested additional information to supplement the responses provided in Dominion's August 20, 2003 letter (Reference 1).
The original questions and supplemental responses requested by NRC staff are provided below. It is our understanding that Dominion's responses to Questions 7, 8, 10a, 11 b, and 12 required no further clarification. Supplemental information for Questions 1, 5, 9, and 10b was provided in a September 5, 2003 letter (Serial No. 03-313A). The responses provided below are applicable to both North Anna Units 1 and 2, even though the RAls received were specific to Unit 2.
A. APPLICABILITY OF ANALYTICAL MODELS Many of the analytical models in the NAPS-2 best estimate LBLOCA methodology are supported by empirical data taken at temperatures less than 17000 F and by sensitivity studies performed at temperatures less than 1700 0F.
The RLBLOCA peak cladding temperature spectrum calculated for NAPS-2 using this methodology extends above 20000F. At temperatures above 1700OF many of the principal phenomena which influence peak cladding temperature (PCT) change or increase in their influence (e.g., cladding oxidation rate) such that the data and sensitivity studies identified for cladding temperatures lower than 1700OF may not apply.
Q6. The NAPS-2 LBLOCA calculations were ranged down to 0.1 ft2 which is below the minimum range in the current NAPS-2 LBLOCA. This size for NAPS-2 falls in the current SBLOCA range. The supporting demonstration plant analyses for the Framatome ANP RLBLOCA were accepted to this small size because for the demonstration plant the phenomena that were predicted to occur were indicative of a LBLOCA rather than a SBLOCA. NAPS-2 must justify that the ranging of break size for application of the Framatome ANP RLBLOCA methodology does not result in phenomena occurring that are typical of a SBLOCA.
Supplemental Response:
A set of 59 calculations was performed for NAPS Unit 2 using the RLBLOCA methodology to support the operation of the plant with FANP Advanced Mark-BW fuel. The smallest break size in this set was 0.44 fte (with the total break area defined as the sum from both break junctions). From a review of the case results, it was found that during blowdown the core region completely voided, which is a large break characteristic. The liquid level in the core region began to increase after the initiation of accumulator injection that occurred at about 130 seconds. This result for the smallest break analyzed provides confirmation that SBLOCA phenomena did not occur in any of the 59 cases that were run using the RLBLOCA methodology.
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Q1 1. Downcomer Boiling - The containment pressure in Figure 7.2-33 indicates that the containment pressure is at about 30 psia and continues to decline at 200 seconds into the limiting LBLOCA. Figures 7.2-23, 7.2-30, and 7.2-32 seem to indicate that downcomer boiling occurs at about 375 seconds into the transient.
The containment plot ends at 200 seconds and it appears from Figures 7.2-23 and 7.2-32 that the calculation was terminated at -460 seconds. At -460 seconds, the PCT drops to -450 0F. At this time, the (extrapolated) containment pressure is 30 psia or less. The saturation temperature at 30 psia is -250 0 F or less, but the drop in PCT stops at -450 0F. 10 CFR 50.46 requires that analyses to be run until the core is quenched.
- a. Extend the analysis results tables and graphs, particularly Table 7.2-11 and Figure 7.2-33, to beyond the time that stable and sustained quench is established.
Supplemental Response:
The calculation of the limiting North Anna Unit 2 realistic large break LOCA transient was extended to 640 seconds. The elevation independent peak cladding temperature is shown in Figure 11-1. It can be seen from this figure that stable and sustained quench is established after about 450 seconds. The minor temperature spikes seen in the figure after 450 seconds are due to intermittent liquid carryover to the reactor vessel side of the break. Figure 11-2 shows that the reactor vessel liquid inventory remains reasonably constant, exhibiting a rising trend.
Figure 11-1 PCTIndependent of Elevation 240.00 18boom .to ~
El E
1200w.0 .I E
S!
0.00IIII 0.0 100.0 2M0.0 W0OO OWN. OW00 7eo.0 Time (s) 2 of 4
Figure 11-2 Reactor Vessel Mass 160M000C _ _ _ _ _ _
120M00000 80M000C I____
I.
Ban0.0 100.0 2D0.0 300.0 4X0.0 600.0 600.0 700.0 600.0 lime (8)
Questions from August 29, 2003 facsimile:
Additionally VEPCO is requested to provide the following information:
If the built-in S-RELAP5 pump performance curves were used, then verify that they apply to the North Anna plant's pump curves for conditions during the LBLOCA.
Response
The North Anna realistic large break LOCA analyses used the S-RELAP5 built-in Westinghouse pump performance curves. The S-RELAP5 pump performance curves were validated for North Anna use by comparison with pump performance curve data provided by Dominion for North Anna (i.e., pump data used in the existing LBLOCA analysis). The comparison showed agreement with the data with the exception of differences in the neighborhood of the zero flow/zero speed point (the locked rotor point). These points are of little consequence since RLBLOCA analyses do not make use of the locked rotor assumption as do deterministic calculations. Framatome ANP concluded that the S-RELAP5 pump was appropriate for North Anna use.
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Verify that hot leg to downcomer nozzle gaps were not modeled in the LBLOCA Analysis.
Response
In compliance with the Safety Evaluation use conditions on FANP's RLBLOCA evaluation model (topical report EMF-2103) hot leg nozzle gaps were not modeled in the North Anna large break LOCA analyses.
REFERENCES
- 1. Letter, Leslie N. Hartz (Dominion) to USNRC, "Virginia Electric and Power Company, North Anna Power Station Units 1 and 2, Request For Additional Information Regarding Realistic Large Break Loss Of Coolant Accident (RLBLOCA) Analysis Results For The Proposed Technical Specifications Changes And Exemption Request For Use Of Framatome Anp Advanced Mark-Bw Fuel," Serial No. 03-313A, August 20, 2003.
- 2. Letter, Leslie N. Hartz (Dominion) to USNRC, "Virginia Electric and Power Company, North Anna Power Station Units 1 and 2, Realistic Large Break Loss of Coolant Accident (RLBLOCA) Analysis Results for the Proposed Technical Specifications Changes and Exemption Request for Use of Framatome ANP Advanced Mark-BW Fuel," Serial No.03-313, May 6, 2003.
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