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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
[Table view] Category:Safety Evaluation
MONTHYEARML24163A3002024-08-0808 August 2024 Request for Relief Request N1-I5-NDE-007 Inservice Inspection Alternative 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) 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 ML19092A4172019-04-15015 April 2019 Unit Nos.1 and 2 Inservice Inspection Alternative Requests N1-I5-NDE-001 and N2 I5 NDE 001 ML19093B2742019-04-15015 April 2019 Inservice Inspection Alternative Requests N1-I5-SPT-001 and N2 I5 Spt 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 2024-08-08
[Table view] |
Text
May 14, 2002 Mr. David A. Christian Senior Vice President - Nuclear Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Blvd.
Glen Allen, Virginia 23060
SUBJECT:
NORTH ANNA POWER STATION UNIT 2 RE: ASME SECTION XI INSERVICE INSPECTION (ISI) PROGRAM RELIEF REQUEST PARTIAL-1 (TAC NO.
MB4084)
Dear Mr. Christian:
This letter grants the relief you requested for Partial-1 for the North Anna Power Station, Unit 2.
By letter dated February 19, 2002, Virginia Electric and Power Company requested relief from certain ISI requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI. The protrusion of the reactor vessel nozzles from the reactor vessel head had prevented the complete examination of the three nozzle-to-vessel welds.
Our evaluation and conclusion are contained in the enclosed Safety Evaluation. The staff has concluded that the requirements of Section XI of the ASME Code are impractical for the subject welds and reasonable assurance of structural integrity is provided by the completed examinations. The relief you requested is authorized pursuant to Title 10 of the Code of Federal Regulations Section 50.55a(g)(6)(i) for the second 10-year ISI interval.
The staff has completed its evaluation of this request; therefore, we are closing TAC No.
MB4084.
Sincerely,
/RA/
John A. Nakoski, Chief, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-339
Enclosure:
As stated cc w/encl: See next page
May 14, 2002 Mr. David A. Christian Senior Vice President - Nuclear Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Blvd.
Glen Allen, Virginia 23060
SUBJECT:
NORTH ANNA POWER STATION UNIT 2 RE: ASME SECTION XI INSERVICE INSPECTION (ISI) PROGRAM RELIEF REQUEST PARTIAL-1 (TAC NO.
MB4084)
Dear Mr. Christian:
This letter grants the relief you requested for Partial-1 for the North Anna Power Station, Unit 2.
By letter dated February 19, 2002, Virginia Electric and Power Company requested relief from certain ISI requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI. The protrusion of the reactor vessel nozzles from the reactor vessel head had prevented the complete examination of the three nozzle-to-vessel welds.
Our evaluation and conclusion are contained in the enclosed Safety Evaluation. The staff has concluded that the requirements of Section XI of the ASME Code are impractical for the subject welds and reasonable assurance of structural integrity is provided by the completed examinations. The relief you requested is authorized pursuant to Title 10 of the Code of Federal Regulations Section 50.55a(g)(6)(i) for the second 10-year ISI interval.
The staff has completed its evaluation of this request; therefore, we are closing TAC No.
MB4084.
Sincerely,
/RA/
John A. Nakoski, Chief, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-339
Enclosure:
As stated cc w/encl: See next page Distribution PPatnaik RidsNrrPMSMonarque PUBLIC RidsNrrDlpmLpdii RidsNrrLAEDunnington PDII-1 R/F RidsOgcRp RidsAcrsAcnwMailCenter G. Hill (2)
RidsRgn2MailCenter Accession Number: ML021340006 OFFICE PDII-1/PM PDII-1/LA OGC PDII-1/SC NAME SMonarque EDunnington RHoefling JNakoski DATE 05/02/02 05/01/02 05/09/02 05/10/02 OFFICIAL RECORD COPY
Mr. David A. Christian North Anna Power Station Virginia Electric and Power Company Units 1 and 2 cc:
Mr. C. Lee Lintecum Mr. David A. Heacock County Administrator Site Vice President Louisa County North Anna Power Station P.O. Box 160 P.O. Box 402 Louisa, Virginia 23093 Mineral, Virginia 23117-0402 Ms. Lillian M. Cuoco, Esq.
Senior Nuclear Counsel Mr. Richard H. Blount, II Dominion Nuclear Connecticut, Inc. Site Vice President Millstone Power Station Surry Power Station Building 475, 5th Floor Virginia Electric and Power Company Rope Ferry Road 5570 Hog Island Road Rt. 156 Surry, Virginia 23883-0315 Waterford, Connecticut 06385 Dr. W. T. Lough Robert B. Strobe, M.D., M.P.H.
Virginia State Corporation State Health Commissioner Commission Office of the Commissioner Division of Energy Regulation Virginia Department of Health P.O. Box 1197 P. O. Box 2448 Richmond, Virginia 23209 Richmond, Virginia 23218 Old Dominion Electric Cooperative Mr. William R. Matthews 4201 Dominion Blvd. Vice President - Nuclear Operations Glen Allen, Virginia 23060 Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Mr. Stephen P. Sarver, Director Glen Allen, Virginia 23060-6711 Nuclear Licensing & Operations Support Virginia Electric and Power Company 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
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR RELIEF PARTIAL-1 SECOND 10-YEAR INSERVICE INSPECTION INTERVAL NORTH ANNA POWER STATION, UNIT 2 VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-339
1.0 INTRODUCTION
By letter dated February 19, 2002, Virginia Electric and Power Company (the licensee) requested relief from certain inservice examination requirements of the 1986 Edition of the American Society of Mechanical Engineers (ASME) Code,Section XI, in regard to volumetric examinations conducted on three reactor vessel outlet nozzle-to-shell welds identified as nos.
10, 12, and 14 during the second 10-year inservice inspection (ISI) interval of North Anna, Unit 2. The licensee stated that the welds were examined to the extent practical. Due to weld joint geometry, the reduction in coverage was greater than 10%. The protrusion of the nozzle beyond the shell physically restricted access for 100% coverage of the clockwise and counter-clockwise scans from the vessel shell.
2.0 BACKGROUND
The ISI of the ASME Code Class 1, 2, and 3 components is to be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code (Code) and applicable addenda as required by Title 10 of the Code of Federal Regulations (10 CFR) Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(i).
Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, and 3 components (including supports) shall meet the requirements, except the design and access provisions and the preservice examination requirements, set forth in the ASME Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," to the extent practical within the limitations of design, geometry, and materials of construction of the components. The regulations require that inservice examination of components and system pressure tests conducted during the first 10-year interval and subsequent intervals comply with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(b) 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. The applicable ISI Code of Record for the second 10-year ISI interval for the North Anna Power Station, Unit 2, is the 1986 Edition of ASME Section XI.
Enclosure
2.1 Request for Relief Pursuant to 10 CFR 50.55a(g)(5), if the licensee has determined that conformance with certain Code requirements is impractical for its facility, the licensee shall notify the Commission and submit, as specified in 10 CFR 50.4, information to support the determination. 10 CFR 50.55a(g)(6)(i) states that the Commission will evaluate determinations under 10 CFR 50.55a(g)(5) that Code requirements are impractical. The Commission may grant such relief and may impose such alternative requirements as it determines is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.
3.0 DISCUSSION (RELIEF REQUEST PARTIAL-1) 3.1 Identification of Components Mark/Weld# Line# Drawing# Class 10 2-RC-R-1 12050-WMKS-RC-R-1.1 1 12 2-RC-R-1 12050-WMKS-RC-R-1.1 1 14 2-RC-R-1 12050-WMKS-RC-R-1.1 1 3.2 Code Requirements The 1986 Edition of ASME Section XI, Table IWB-2500-1, Examination Category B-D, Item Number B3.90, does not allow any limitations to the required volumetric examinations. However, Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, which has been approved for use by NRC in Regulatory Guide (RG) 1.147, Inservice Inspection Code Case Acceptability-ASME Section XI, Division 1, allows a reduction in coverage if it is less than 10%.
3.3 Code Requirements from which Relief Is Requested Pursuant to 10 CFR 50.55a(g)(5), relief is requested from the volumetric examination coverage requirements of the 1986 Edition of ASME Code,Section XI, Table IWB-2500-1, Examination Category B-D, Item Number B3.90 for the identified reactor vessel outlet nozzle-to-shell welds.
3.4 Licensees Basis for Relief Reactor vessel outlet nozzle-to-shell welds 10, 12, and 14 have been examined to the extent practical as required by the Code. Due to weld joint geometry, the reduction in coverage for the listed components was greater than 10%. The protrusion of the nozzle beyond the shell physically restricted access for 100% coverage of the clockwise and counter-clockwise scans from the vessel shell. One hundred percent of the weld volume was covered from the nozzle bore. Table Partial-1 is provided to detail the limitations experienced during the March 2001 examination. Sketch Partial 1 has also been provided to show the limitations of examining the reactor vessel outlet nozzle-to-shell welds. Although less than the Code-required coverage was obtained, this examination provided an acceptable level of quality and safety.
3.5 Licensees Alternate Provisions The licensee proposed that the examinations already completed at the reduced coverage during the March 2001 refueling outage be accepted as meeting the Code requirements.
4.0 EVALUATION The ASME Code,Section XI, 1986 Edition, requires volumetric examination coverage of 100%
of the reactor vessel outlet nozzle-to-shell weld. However, a reduction in examination coverage of less than 10% due to interferences is acceptable as provided by Code Case N-460 that was approved by the NRC in RG 1.147. During the second 10-year inspection interval, the reactor vessel outlet nozzle-to-shell welds identified in the February 19, 2002, submittal as nos. 10, 12, and 14 were examined in the transverse direction with an average of 60.5% volumetric coverage and in the axial direction from the nozzle bore for 100% volumetric coverage. This resulted in an average volumetric coverage of 80.25% in lieu of the Code-required coverage in excess of 90%.
The limitation in examination coverage was attributed to the protrusion of the nozzle into the vessel interior, which restricted scanning from one side of each weld from the interior surface of the reactor vessel. The licensee has examined the subject welds to the maximum extent practical by ultrasonic examination. The staff has determined that it is impractical to perform the Code-required examination of the subject nozzle-to-shell welds due to the interference of the nozzle protrusion. In order to comply with the Code requirement, a design modification of the reactor vessel will be required that would impose a significant burden upon the licensee.
However, the staff finds that the volumetric examination conducted for each weld provides reasonable assurance of structural integrity of the weld since any significant pattern of degradation in the weld would have been detected with a high degree of confidence during examination of the accessible 80.25% of weld volume. Furthermore, in the highly unlikely event that a service-induced flaw in the unexamined region of the weld propagates to the inside surface of the weld, the staff determined that it would most likely be detected during the Code-required VT-3 visual examination of the reactor vessel interior surface, also conducted during the inspection interval.
5.0 CONCLUSION
The staff has reviewed the licensees submittal and concludes that compliance with the Code requirements are impractical for the reactor vessel outlet nozzle-to-shell weld nos. 10, 12, and 14 due to interference caused by the nozzle protrusions into the interior surface of the reactor vessel. The staff has further determined that if the Code requirements were to be imposed on the licensee, then the nozzles would have to be redesigned, imposing a significant burden upon the licensee. In addition, the staff finds that the completed examination coverages provide reasonable assurance of structural integrity for the subject welds. Therefore, relief is granted from the Code requirement pursuant to 10 CFR 50.55a(g)(6)(i) for the second 10-year ISI interval for North Anna, Unit 2.
The relief granted is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.
Principal Contributor: P. Patnaik Date: May 14, 2002