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MONTHYEARML0526602942005-10-0303 October 2005 RAI, Revised Reactor Vessel Material Surveillance Capsule Withdrawal Schedule (Tac MC6412, MC6413) Project stage: RAI ML0607304482006-03-15015 March 2006 Letter MC6412, Proposed Reactor Vessel Material Surveillance Capsule Withdrawal Schedule Project stage: Other 2005-10-03
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Category:Letter
MONTHYEARML24032A1112024-02-0101 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 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 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 ML24003A8502024-01-0909 January 2024 Letter to Wenonah Haire, Thpo, Catawba Indian Nation, Notice of Availability of the Draft Site-Specific EIS for North Anna Power Station, Units 1 and 2, Subsequent License Renewal 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 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 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 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 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 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 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 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 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 ML24003A8442024-01-0909 January 2024 Letter to Russell Townsend, Thpo, Eastern Band of Cherokee Indians 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 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 ML23332A1852024-01-0404 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 ML23332A0872024-01-0404 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 ML23360A6352024-01-0404 January 2024 Letter to Dominion Availability for North Anna Units 1 and 2 Draft Site Specific Environmental Impact Statement ML23332A1472023-12-21021 December 2023 Issuance of Environmental Scoping Summary Report Associated with the Staff'S Review of the North Anna Power Station, Units 1 and 2, Subsequent License Renewal Application ML23283A3052023-12-20020 December 2023 Review of Appendix F to DOM-NAF2, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code (EPID L-2022-LLT-0003) (Nonproprietary) ML23346A0972023-12-11011 December 2023 License Amendment Request to Revise the Emergency Plan Relocation of the Technical Support Center - Response to NRC Request for Additional Information ML23346A1022023-12-11011 December 2023 2024 North Anna Power Station Brq Inspection Notification Letter ML24012A0942023-12-0707 December 2023 GL Report from Dominion Virginia Power Regarding Transfer of Devices ML24012A0892023-12-0707 December 2023 GL Registration from Dominion Virginia Power ML23334A2432023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23362A0602023-11-29029 November 2023 ISFSI, Submittal of Cask Registration for Spent Fuel Storage IR 05000339/20234022023-11-27027 November 2023 Security Baseline Inspection Report 05000338 and 05000339/2023402 IR 05000338/20230032023-11-13013 November 2023 Integrated Inspection Report 05000338/2023003 and 05000339/2023003 ML23311A2042023-10-0909 October 2023 Annual Submittal of Technical Specification Bases Changes Pursuant to Technical Specification 5.5.13.d IR 05000338/20234032023-10-0505 October 2023 Reissue - North Anna Power Station - Cyber Security Inspection Report 05000338/2023403 and 05000339/2023403 (Cover Letter) ML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23230A0502023-10-0202 October 2023 5 of the Quality Assurance Topical Report - Review of Program Changes ML23275A0992023-09-28028 September 2023 Subsequent License Renewal Application Third 10 CFR 54.21(b) Annual Amendment IR 05000338/20230112023-09-26026 September 2023 Quadrennial Focused Engineering Inspection Commercial Grade Dedication Report 05000338/2023011 and 05000339/2023011 ML23242A3482023-09-11011 September 2023 Cyber Security Inspection Report 05000338/2023403 and 05000339/2023403 - Cover ML23254A0242023-09-0606 September 2023 Paragon Energy Solutions LLC, Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23249A2592023-09-0606 September 2023 Core Operating Limits Report Cycle 30, Pattern Ukr, Revision 0 ML23214A2022023-09-0505 September 2023 Staff Assessment of Updated Seismic Hazards Following the NRC Process for the Ongoing Assessment of Natural Hazards Information 2024-02-01
[Table view] Category:Safety Evaluation
MONTHYEARML23283A3052023-12-20020 December 2023 Review of Appendix F to DOM-NAF2, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code (EPID L-2022-LLT-0003) (Nonproprietary) ML23230A0502023-10-0202 October 2023 5 of the Quality Assurance Topical Report - Review of Program Changes ML23181A1352023-08-22022 August 2023 Issuance of Amendment Nos. 295 and 278 License Amendment Request to Remove the Refueling Water Chemical Addition Tank and Change the Containment Sump Ph Buffer ML23072A0892023-05-0101 May 2023 (Amendments 346 & 286), North Anna 1 & 2 (Amnds 294 & 277), Surry 1 & 2 (Amnds 311 & 311), and Summer 1 (Amd 225) - Issuance of Amendments to Revise TSs to Adopt TSTF-554 Revise Reactor Coolant Leakage Requirements ML21320A0072022-09-0707 September 2022 Review of Appendix E to DOM-NAF-2, Qualification of the Framatome BWU-I CHF Correlation in the Dominion Energy VIPRE-D Computer Code (EPID L-2021-LLT-0000) (Non-Proprietary) ML22196A1972022-07-28028 July 2022 Request for Relief Request N2-I4-LMT-004 Inservice Inspection Limitations ML22095A1072022-07-11011 July 2022 Issuance of Amendment Nos. 120, 344, & 284, 293 & 276, & 307 & 307 to Relocate Requirements to the QAPD ML22068A0712022-03-22022 March 2022 Issuance of Amendment Nos. 292 and 275 to Revise Technical Specifications to Adopt TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML22019A0022022-03-0808 March 2022 Regarding Request to Utilize Code Case OMN-28 ML22041A0102022-03-0101 March 2022 V.C. Summer 1, Issuance of Amendment Nos. 283 (Millstone), 291 and 274 (North Anna), and 221 (Summer) to Revise TSs to Adopt TSTF-569 Revision of Response Time Testing Definition ML21323A1742021-12-22022 December 2021 Issuance of Amendment Nos. 289 and 272 to Revise Reactor Core Safety Limit to Reflect WCAP-17642-P-A ML21232A2172021-10-19019 October 2021 Issuance of Amendment Nos. 288 and 271 to Revise Technical Specifications Battery Surveillance Testing ML21264A0112021-10-18018 October 2021 Safety Evaluation Report Related to the Subsequent License Renewal of North Anna Power Station, Units 1 and 2 ML21075A0452021-03-26026 March 2021 Request to Utilize Code Case N-885 ML20325A0952021-03-19019 March 2021 Issuance of Amendment to Revise Technical Specifications to Allow Usage of a Small Break Loss of Coolant Accident Methodology (Non-Proprietary) ML20364A0402021-01-15015 January 2021 Request for Relief Request N1-I4-LMT-003 Inservice Inspection Limitations ML20350B8062020-12-28028 December 2020 Request for Relief Request N1-I5-NDE-002 Inservice Inspection Alternative ML20302A1792020-10-29029 October 2020 Non-Proprietary, Issuance of Amendment Nos. 286 and 269 to Revise Technical Specifications to Allow Usage of a Full Spectrum Loss of Coolant Accident Methodology ML20253A3292020-09-30030 September 2020 Revised License Renewal Commitment Pressurizer Surge Line Weld Inspection Frequency ML20252A0042020-09-23023 September 2020 Request for Relief Request Fifth 10-Year Interval ML20252A0072020-09-15015 September 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI ML20031E7842020-02-19019 February 2020 Request for Relief Request P-9 to Defer Performance of Comprehensive Pump Test ML19319A5832020-01-17017 January 2020 Issuance of Amendment Nos. 285 and 268 to Revise Technical Specifications Regarding Emergency Diesel Generator Maximum Voltage Limits ML19305D2482019-12-31031 December 2019 Issuance of Amendments Adoption of Emergency Action Level Schemes Per NEI 99-01, Rev. 6 ML19274C9982019-11-13013 November 2019 Issuance of Amendments Regarding Installation of Water Headers in Flood Protection Dike ML19238A1272019-09-12012 September 2019 Issuance of Amendment Nos. 282 and 265 to Revise Technical Specifications Regarding Open Phase Protection ML19143A3422019-05-29029 May 2019 Inservice Inspection Alternative Request N2-I4-LMT-003 ML19140A2882019-05-28028 May 2019 Inservice Inspection Alternative Requests N1-I5-CMP-001 and N2-I5-CMP-001 ML19135A3242019-05-21021 May 2019 Inservice Inspection Alternative Request N1-I4-CS-002 ML19093B2742019-04-15015 April 2019 Inservice Inspection Alternative Requests N1-I5-SPT-001 and N2 I5 Spt 001 ML19092A4172019-04-15015 April 2019 Unit Nos.1 and 2 Inservice Inspection Alternative Requests N1-I5-NDE-001 and N2 I5 NDE 001 ML19031B2272019-02-27027 February 2019 Issuance of Amendment Nos. 281, 264, 294, and 294 to Consolidate Emergency Operations Facilities and Associated Emergency Plan Changes ML19039A2362019-02-14014 February 2019 Inservice Inspection Alternative N2-I4-NDE-007 ML18290A8522018-11-27027 November 2018 Issuance of Amendments 280, 263 to Revise Technical Specifications Regarding Ventilation System Surveillance Requirements in Accordance with TSTF-522 ML18225A0202018-08-29029 August 2018 ISFSI; North Anna 1 & 2 Isfsls, and Unit 3; Surry Power 1 & 2, and Isfsls); Dominion Energy Kewaunee, Inc. (Kewaunee Power Station and Isfsi): Request for Threshold Determination Under 10 CFR 50.80 ML18180A1972018-07-27027 July 2018 Issuance of Amendments to Revise Technical Specifications Regarding New and Spent Fuel Storage (CAC Nos. MF9712 and MF9713, EPID L-2017-LLA-0240) ML18031A2222018-02-0606 February 2018 Letter to D. G. Stoddard Issuance of Renewed Materials License No. SNM-2507 for the North Anna Power Station Independent Spent Fuel Storage Installation (Cac/Epid Nos. 001028/L-2017-RNW-0010 and 000993/L-2017-LNE-0008) ML18029A1842018-02-0202 February 2018 Proposed Inservice Inspection Alternatives N1-I4-NDE-010 and N2-I4-NDE-005 (CAC Nos. MF9534 and MF9535; EPID L-2017-LLR-0029) ML18019A1952018-01-24024 January 2018 Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination (CAC Nos. MF9923, MF9924, MF9925, MF9926, MF9927, and MF9928; EPID L-2017-LLR-0060) ML18005A1092018-01-10010 January 2018 Relief Request (RR) N1-I4-LMT-002, Limited Coverage Examinations for the Fourth Ten-Year Inspection Interval (CAC No. MF9689; EPID L-2017-LLR-0024) ML17332A0782017-12-12012 December 2017 ISFSI; Millstone and ISFSI; North Anna and ISFSI; Surry and ISFSI - Request for Approval of Revision 24 of the Nuclear Facility Quality Assurance Program Description Topical Report, DOM-QA-1 (CAC Nos. MF9732-MF9739; EPID L-2017-LLQ-0001) ML17332A6632017-12-0606 December 2017 Proposed Inservice Inspection Alternatives N1-I4-NDE-009 and N2-I4-NDE-004 (CAC Nos. MF9298 and MF9299; EPID L-2016-LLR-0018) ML17221A2522017-08-17017 August 2017 Proposed Alternative to Implement Code Case N-839 ML17053A2432017-07-21021 July 2017 Relief Request (RR) N1-I4-NDE-008, and N2-I4-NDE-003 Inservice Inspection Program ML17046A3162017-04-0606 April 2017 Connecticut, Virginia, Millstone, North Anna, Surry, Submission of Revision 21 of the Quality Assurance Topical Report for NRC Approval and Submission Revision 22 for Information Only (CAC Nos. MF8128 - MF8234) ML16252A4782016-10-17017 October 2016 Issuance of Amendments Revising Technical Specifications to Address the Issue Identified in Westinghouse NSAL-09-5, Revision 1, and NSAL-15-1, Revision 0 ML16209A4132016-07-27027 July 2016 Safety Evaluation For North Anna Power Station, Units 1 And 2, Proposed License Amendment To Revise The Technical Specifications To Address The Issue Identified In Westinghouse Documents NSAL-09-5. Rev. 1 and NSAL-15-I (TAC No. MF7186 and MF7187) ML16028A4342016-03-0101 March 2016 Relief Request (RR) N1-I4-SPT-006, Inservice Inspection Program ML16013A4442016-02-22022 February 2016 (NAPS) - Issuance of Amendment for Changes to Technical Specification (TS) 3.8.1 - AC Sources, Operating Revised Surveillance Requirement ML15307A3002016-02-0202 February 2016 (NAPS) - Issuance of Amendments for Changes to the Emergency Action Level Revisions - Correction of Equipment Mark Number 2023-08-22
[Table view] |
Text
March 15, 2006 Mr. David A. Christian Senior Vice President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
NORTH ANNA POWER STATION, UNIT NOS. 1 AND 2 (NORTH ANNA 1 AND 2) - APPROVAL OF PROPOSED REACTOR VESSEL MATERIAL SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULE (TAC NOS. MC6412 AND MC6413)
Dear Mr. Christian:
By letter dated March 15, 2005, as supplemented by letter dated December 9, 2005, Virginia Electric and Power Company submitted proposed reactor vessel material surveillance capsule withdrawal schedules for the Nuclear Regulatory Commission (NRC) staffs review and approval. The proposed schedules were developed to accommodate the 60-year licensing period for North Anna 1 and 2 using the guidance of the American Society for Testing and Materials (ASTM), E-185-82, Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, and NUREG-1801, Generic Aging Lessons Learned (GALL) Report.
Our review is contained in the enclosed safety evaluation. The NRC staff has concluded that the proposed surveillance capsule withdrawal schedules for North Anna 1 and 2 are in accordance with Title 10 of the Code of Federal Regulations, Part 50, Appendix H and the recommendations of ASTM E-185-82.
Sincerely,
/RA/
Evangelos C. Marinos, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-338 and 50-339
Enclosure:
Safety Evaluation cc w/encl: See next page
ML060730448 *SE Dated OFFICE NRR/LPL2-1/PM NRR/LPD2-1/LA NRR/CVIB/BC NRR/LPL2-1/BC NAME SMonarque MOBrien MMitchell* EMarinos DATE 2/17/06 2/17/06 02/17/06 3/15/06 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULE VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-338 AND 50-339
1.0 INTRODUCTION
By letter dated March 15, 2005, as supplemented by letter dated December 9, 2005, Virginia Electric and Power Company (VEPCO) submitted proposed reactor pressure vessel (RPV) material surveillance capsule withdrawal schedules for the Nuclear Regulatory Commission (NRC) staffs review and approval in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Appendix H,Section III.B.3. The proposed schedules were developed to accommodate the 60-year licensing period at North Anna Power Station, Unit Nos. 1 and 2 (North Anna 1 and 2) using the guidance of the American Society for Testing and Materials (ASTM), E-185-82, Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, and NUREG-1801, Generic Aging Lessons Learned (GALL) Report.
2.0 REGULATORY EVALUATION
The surveillance program requirements in Appendix H to 10 CFR Part 50, Reactor Vessel Material Surveillance Program Requirements, were established to monitor the radiation-induced changes in the mechanical and impact properties of the RPV materials. Appendix H to 10 CFR Part 50 requires licensees to monitor changes in the fracture toughness properties of ferritic materials in the RPV beltline region of light-water nuclear power reactors. Appendix H to 10 CFR Part 50 states that the design of the surveillance program and the withdrawal schedule must meet the requirements of the edition of ASTM E-185 that is current on the issue date of the American Society of Mechanical Engineers, Boiler and Pressure Vessel Code (ASME Code), to which the RPV was purchased. Later editions of ASTM E-185-82 may be used including those editions through 1982. NUREG-1801 provides additional guidance for the surveillance program for the 60-year extended period of operation.
3.0 TECHNICAL EVALUATION
3.1 Evaluation Criteria of ASTM E-185-82 For North Anna 1 and 2, VEPCO is using the requirements of ASTM E-185-82 as its basis for meeting the RPV surveillance capsule withdrawal requirements of 10 CFR Part 50, Appendix H.
Table 1 of ASTM E-185-82 requires that either a minimum of three, four, or five Enclosure
surveillance capsules be removed from each of the vessels, as based on the limiting amount of reference nil-ductility temperature shift (RTNDT) that is projected to occur at the clad-vessel interface location of the RPV at the end-of-licensed plant life (EOL). ASTM E-185-82 establishes the following criteria for determining the minimum number of capsules that are to be removed in accordance with a withdrawal schedule and the number of capsules that are to be tested:
- 1. For plants with projected RTNDT less than 100 EF (56 EC), three capsules are required to be removed from the RPV and the first two capsules are required to be tested (for dosimetry, tensile-ductility, Charpy-V impact toughness, and alloying chemistry).
- 2. For plants with projected RTNDT between 100 EF (56 EC) and 200 EF (111 EC), four surveillance capsules are to be removed from the RPV and the first three capsules are required to be tested.
- 3. For plants with projected RTNDT above 200 EF (111 EC), five surveillance capsules are required to be removed from the RPV and the first four capsules are required to be tested.
For the 60-year extended periods of operation, the North Anna 1 and 2 RPVs have limiting RTNDT values between 100 EF and 200 EF (i.e., an RTNDT value of 123.3 EF for North Anna 1 and an RTNDT value of 137.7 EF for North Anna 2). The licensee is therefore required, as a minimum, to remove four capsules from each reactor during the 60-year extended periods of operation. The licensee has already withdrawn three out of the four capsules from each reactor and has proposed an appropriate withdrawal schedule for the fourth capsule in each reactor.
The NRC staff notes that there can be up to four standby surveillance capsules for North Anna 1 and 2 that have the potential of being removed for storage. However, there currently is no detailed guidance regarding the treatment of standby capsules that are removed but not tested.
Therefore, the NRC staff requested the licensee to provide information on how they intend to ensure that any surveillance capsules removed from the North Anna 1 and 2 RPVs, without the intent to test them, are maintained in a condition that would permit their future use, if necessary.
This information concerning the storage of these standby capsules should be included in the North Anna 1 and 2 ?Updated Final Safety Analysis Report (UFSAR). In its letter dated December 9, 2005, VEPCO stated that the following would be included in the applicable section of the North Anna 1 and 2 UFSAR:
All surveillance capsules placed in storage will be maintained for possible future insertion. If one or more capsules will not be maintained in such a way as to permit future insertion, then the NRC staff will be notified of this change.
The NRC staff concludes that the inclusion of these requirements in the applicable North Anna 1 and 2 UFSAR sections provides the necessary guidance to ensure that any surveillance capsules removed from the North Anna 1 and 2 RPVs, without the intent to test them, are maintained in a condition that would permit their future use, if necessary.
3.2 Changes Proposed to the Withdrawal Schedule for North Anna 1 The licensees letters of March 15 and December 9, 2005, provide the updated RPV
surveillance capsule withdrawal schedule for North Anna 1. The letters indicate that Capsules V, U, and W were removed from North Anna Unit 1 at 1.1 effective full power years (EFPY),
5.9 EFPY, and 14.8 EFPY, and that the neutron fluences reported for Capsules V, U, and W at the time of withdrawal were 0.263 x 1019 n/cm2 (E > 1.0 MeV), 0.872 x 1019 n/cm2 (E > 1.0 MeV),
and 2.052 x 1019 n/cm2 (E > 1.0 MeV), respectively. The proposed withdrawal schedule has the fourth-capsule, Capsule Z, being withdrawn for testing at 44.5 EFPY with an estimated neutron fluence value of 6.49 x 1019 n/cm2 (E > 1.0 MeV). The letters also reported updated lead factors for surveillance Capsules V, U, W, and Z.
The NRC staff compared updated withdrawal data for surveillance Capsules V, U, W, and Z with the criteria of ASTM E-185-82 for a required four-capsule withdrawal schedule. The NRC staff confirmed that the withdrawals were consistent with the criteria in ASTM E-185-82 for the four-capsule withdrawal schedule. It should be noted that the proposed surveillance withdrawal schedule in the licensees letter dated March 15, 2005, provides an option that Capsule X may be withdrawn at 44.5 EFPY with an estimated neutron fluence value of 8.45 x 1019 n/cm2 (E >1.0 MeV) in lieu of Capsule Z to satisfy the ASTM E-185-82 fourth-capsule requirement for the extended period of operation. The limiting neutron fluence projected for the North Anna 1 RPV is approximately 5.9 x 1019 n/cm2 (E > 1.0 MeV) at its EOL (60-year operating period).
Since either Capsule Z or X has a neutron fluence value greater than this, but not greater than twice the EOL fluence value, the NRC staff has determined that the removal of either of these capsules is consistent with the criterion in ASTM E-185-82 for the final required capsule to be withdrawn and tested.
3.3 Changes Proposed to the Withdrawal Schedule for North Anna 2 The licensees letters of March 15 and December 9, 2005, provide the updated RPV surveillance capsule withdrawal schedule for North Anna 2. The letters indicate that Capsules V, U, and W were removed from North Anna Unit 2 at 1.0 EFPY, 6.3 EFPY, and 15.3 EFPY, and that the neutron fluences reported for Capsules V, U, and W at the time of withdrawal were 0.246 x 1019 n/cm2 (E > 1.0 MeV), 0.980 x 1019 n/cm2 (E > 1.0 MeV), and 2.092 x 1019 n/cm2 (E > 1.0 MeV), respectively. The proposed withdrawal schedule has the fourth-capsule, Capsule Z, being withdrawn for testing at 42.8 EFPY with an estimated neutron fluence value of 6.50 x 1019 n/cm2 (E > 1.0 MeV). The letters also reported updated lead factors for surveillance Capsules V, U, W, and Z.
The NRC staff compared updated withdrawal data for North Anna 2 surveillance Capsules V, U, W, and Z with the criteria of ASTM E-185-82 for a required four-capsule withdrawal schedule.
The NRC staff confirmed that the withdrawals were consistent with the criteria in ASTM E-185-82 for the four-capsule withdrawal schedule. It should be noted that the proposed surveillance capsule withdrawal schedule in the licensees letter dated March 15, 2005, provides an option that Capsule X may be withdrawn at 42.8 EFPY with an estimated neutron fluence value of 8.39 x 1019 n/cm2 (E > 1.0 MeV) in lieu of Capsule Z to satisfy the ASTM E-185-82 fourth-capsule requirement for the extended period of operation. The limiting neutron fluence projected for the North Anna 2 RPV is approximately 5.91 x 1019 n/cm2 (E > 1.0 MeV) at its EOL (60-year operating period). Since either Capsule Z or X has a neutron fluence value greater than this, but not greater than twice the EOL fluence value, the NRC staff has determined that the removal of either of these capsules is consistent with the criterion in ASTM E-185-82 for the final required capsule to be withdrawn and tested.
4.0 CONCLUSION
Based on the NRCs staffs review of VEPCOs submittal, the NRC staff has found that the revised surveillance capsule withdrawal schedules for the North Anna 1 and 2 RPVs satisfy the requirements of ASTM E-185-82. Therefore, the NRC staff concludes that the licensees modified surveillance capsule withdrawal schedules for North Anna 1 and 2, as provided in the March 15, 2005, letter and as supplemented by the December 9, 2005, letter, are acceptable for implementation and satisfy the requirements of Appendix H to 10 CFR Part 50 for the 60-year extended license period.
Principal Contributor: J. Honcharik Date: March 15, 2006
North Anna Power Station, Units 1 & 2 cc:
Mr. C. Lee Lintecum Mr. Jack M. Davis County Administrator Site Vice President Louisa County North Anna Power Station Post Office Box 160 Virginia Electric and Power Company Louisa, Virginia 23093 Post Office Box 402 Mineral, Virginia 23117-0402 Ms. Lillian M. Cuoco, Esq.
Senior Counsel Dr. Robert B. Stroube, MD, MPH Dominion Resources Services, Inc. State Health Commissioner Building 475, 5 th floor Office of the Commissioner Rope Ferry Road Virginia Department of Health Waterford, Connecticut 06385 Post Office Box 2448 Richmond, Virginia 23218 Dr. W. T. Lough Virginia State Corporation Commission Division of Energy Regulation Post Office Box 1197 Richmond, Virginia 23218 Old Dominion Electric Cooperative 4201 Dominion Blvd.
Glen Allen, Virginia 23060 Mr. Chris L. Funderburk, Director Nuclear Licensing & Operations Support Dominion Resources Services, Inc.
Innsbrook Technical Center 5000 Dominion Blvd.
Glen Allen, Virginia 23060-6711 Office of the Attorney General Commonwealth of Virginia 900 East Main Street Richmond, Virginia 23219 Senior Resident Inspector North Anna Power Station U. S. Nuclear Regulatory Commission 1024 Haley Drive Mineral, Virginia 23117