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| {{#Wiki_filter:VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 February 16, 2012 U.S. Nuclear Regulatory Commission Attention: | | {{#Wiki_filter:VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 February 16, 2012 U.S. Nuclear Regulatory Commission Serial No.: 12-083 Attention: Document Control Desk NAPS/JHL: RO Washington, D.C. 20555 Docket No.: 50-339 License No.: NPF-7 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION) |
| Document Control Desk Washington, D.C. 20555 Serial No.: NAPS/JHL: Docket No.: License No.: 12-083 RO 50-339 NPF-7 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION) | | NORTH ANNA POWER STATION UNIT 2 OWNER'S ACTIVITY REPORT In accordance with the requirements of American Society of Mechanical Engineers (ASME) Code Case N-532-4, enclosed is the Owner's Activity Report (Form OAR-I), for refueling outage N2R21. This report is for the first refueling outage of the first period of the fourth inspection interval. |
| NORTH ANNA POWER STATION UNIT 2 OWNER'S ACTIVITY REPORT In accordance with the requirements of American Society of Mechanical Engineers (ASME) Code Case N-532-4, enclosed is the Owner's Activity Report (Form OAR-I), for refueling outage N2R21. This report is for the first refueling outage of the first period of the fourth inspection interval.Should you have any questions regarding this submittal, please contact Mr. Donald R.Taylor at (540) 894-2616.Very truly yours,:. -F. Mladen Director -Nuclear Station Safety and Licensing Commitments made in this letter: None Attachment ocl Q U P.cc: U.S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Avenue, NE, Suite 1200 Atlanta, Georgia 30303-1257 NRC Senior Resident Inspector North Anna Power Station Mr. J. E. Reasor, Jr.Old Dominion Electric Cooperative Innsbrook Corporate Center 4201 Dominion Blvd.Suite 300 Glen Allen, Virginia 23060 Dr. V. Sreenivas NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 0-8 G9A Rockville, MD 20852-2738 Ms. K. R. Cotton NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 0-8 G9A Rockville, MD 20852-2738 Mr. M. M. Grace Authorized Nuclear Inspector North Anna Power Station W Attachment Owner's Activity Reports for North Anna Unit 2 Refueling Outage N2R21 -First Period of the Fourth ISI Interval Virginia Electric and Power Company (Dominion) | | Should you have any questions regarding this submittal, please contact Mr. Donald R. |
| &OFDominion-Form OAR-I, Owner's Activity Report E-,A-S-0 ATAHET PaeIo Report Number: N2R21 (Unit 1, 4th Interval, 1 a Period)Plant: North Anna Power Station Unit No. 2f (if applicable)
| | Taylor at (540) 894-2616. |
| Commercial service date: 12/14/1980 Refueling outage no. N2R21 Current inspection interval: | | Very truly yours, |
| 4t" (December 14, 2010 -December 13, 2020)(16, 2no, 3 T, 4 t , other)Current inspection period: 1 " (December 14,.2010 -December 13, 2013)(19, 2no, 3rd, 4e1)Edition and Addenda of Section XA applicable to the inspection plans: 2004 Edition with No Addenda Date and revision of inspection plans: Revision 1. February 2011 Edition and Addenda of Section XA applicable to repair/replacement activities, if different than the inspection plans N/A Code Cases used: N-432-1. N-460, N-504-3. N-526, N-532-4. N-552, N-566-2. N-586-1, N-597-2. N-61 3-1.N-624, N-638-1, N-641, N-651, N-658, N-661, N-663, N-683, N-696, N-706-1, N-722, and N-729-1 (if applicable) | | :. - |
| CERTIFICATE OF CONFORMANCE I certify that (a) the statements made In this report are correct; (b) the examinations and tests meet the Inspection Plan as required by the ASME Code, Section Xi; and (c) the repair/replacement actUvities and evaluations supporting the completion of N2R21 conform to the requirements of Section XI.(refueling outage number)Signed Owner or Owner's Desine il Date 9 -/Z CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Virginla and employed by HSB CT of Hartford, CT have inspected the items described In this Owner's Activity Report, and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section Xl.By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal Injury or property damage or a loss of any kind arising from or connected with this inspection. | | F. Mladen Director - Nuclear Station Safety and Licensing Commitments made in this letter: None Attachment ocl Q U |
| _ _ Cm Commissions NB 9531-A-N-I-C I VA 424-R Inspector's'Signature National Board, State, Province and Endorsements Date /, 3' L'-'-/2, ZtZ , Form No. 729596 (Aug 2009) | | |
| WDominion-Form OAR-1, Owner's Activity Report ER-l AISI10 AT ... TA HM N I ae A2o Table I Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination Item Description Evaluation Description Category and Item Number H-603A Sway Strut for 2-SI-P- Eval per CR442495 for 1B improperly seated snap ring F-A / F1.40A does not impact the ability of the support to perform its design function in both normal or abnormal conditions.
| | P. |
| Summary # N2.F1.40.090 Snubber, 2-SI-HSS-809B 2 PSI found missing spacers, eval by CR442392 F-A / F1.20D verified that missing spacer does not impact ability of Summary# N2.F1.20.1 19 snubber to perform its function or provide support.Snubber 2-SI-HSS-421.02 CR442784, missing spacer on piston rod clevis pin, verified F-Al FI.IOD that missing spacer does not impact ability of snubber to#N2.11.10.095 perform its function or provide Summary# Nsupport.Snubber 2-RH-HSS-102 CR443946, loose bolt on pipe clamp, low fluid, tested SAT, F-A/ Fl.20D no slipping, evaluated as functional. | | cc: U.S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Avenue, NE, Suite 1200 Atlanta, Georgia 30303-1257 NRC Senior Resident Inspector North Anna Power Station Mr. J. E. Reasor, Jr. |
| Performed additional examinations | | Old Dominion Electric Cooperative Innsbrook Corporate Center 4201 Dominion Blvd. |
| -Summary # N2.F1 .20.371 ST SAT.Attachment Weld 12H *CR444219, Relevant indication found. CC N-586-1 B-KI B10.20 evaluation, construction flaw at surface. Ground out, Summary # N2.B10.20.001 teedST tested SAT.Snubber 2-RC-HSS-459.01 CR444443, snubber & pipe F-A /FI. 1OD clamp alignment/binding, Summary # N2.F1.10.222 tested SAT RPVH Pens #8, 15, and 23 CR443870, discoloration and B-E / B4.30 staining, cleaned and found no degradation.
| | Suite 300 Glen Allen, Virginia 23060 Dr. V. Sreenivas NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 0-8 G9A Rockville, MD 20852-2738 Ms. K. R. Cotton NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 0-8 G9A Rockville, MD 20852-2738 Mr. M. M. Grace Authorized Nuclear Inspector North Anna Power Station |
| Evaluated Summary # N2.B4.30.001 SAT.RPVH Pen #18 CR444072, canopy seal weld B-E / B4.30 leakage from above, boric Summary # N2.134.30.001 acid residue, no degradation RPVH Pen #41 CR444091, residue from B-E I B4.30 canopy seal identified at pen Form No. 729595 (Aug 2009) | | |
| Dftminion-Form OAR-I, Owner's Activity Report ERAA-S-0 ATTACMN I ae3o Summary# N2.B4.30.001
| | W Attachment Owner's Activity Reports for North Anna Unit 2 Refueling Outage N2R21 - First Period of the Fourth ISI Interval Virginia Electric and Power Company (Dominion) |
| #18, no degradation Spring Hanger SH-1 CR446060, owner elected F-A / FI. 1OC examination found loose nut, evaluated as able to perform Summary# N2.Fl.10.263 design function Restraint R-537 CR444413, PSI found F-A / F1.20B clearance issue, evaluation determined within the Summary # N2.F1.20.253 standard.CR448737, rub marks and no Reactor Vessel Pad Support-5 measurable gap on one side.No depth or displaced metal, F-A I F1.40B free to move, permits thermal growth and restrains in lateral Summary # N2.F1 .40.067 and vertical direction, meets function.Form No. 729595 (Aug 2009) | | |
| WDominion-Form OAR-I, Owner's Activity Report Table 2 Abstract of Repair/Replacement Activities Required for Continued Service Code Date Repair/Replacement Class Item Description Description of Work Completed Plan Number Snubber, 2-RC- 2nd preservice found 1 HSS-455.012preicfon 1 welded lug to anchor 2011-110 F-A / for paddle pin bent 11/6/2011 2011-120 F1.10D Summary# downward, N2.Fl.10.486 CR442774.2"-WS-485-164-Q3 Replace 2" piping due 11/17/2011 2011-172 D-B / D2.10 downstream of 2- to MIC leak at weld SW-212 Form No. 729595 (Aug 2009)}}
| | Form OAR-I, Owner's Activity Report |
| | &OFDominion- E-,A-S-0 ATAHET PaeIo Report Number: N2R21 (Unit 1, 4th Interval, 1 a Period) |
| | Plant: North Anna Power Station Unit No. 2f Commercial service date: 12/14/1980 Refueling outage no. N2R21 (if applicable) |
| | Current inspection interval: 4t" (December 14, 2010 - December 13, 2020) |
| | (16, 2no, 3T, 4 t , other) |
| | Current inspection period: 1" (December 14,.2010 - December 13, 2013) |
| | (19, 2no, 3rd, 4e1) |
| | Edition and Addenda of Section XA applicable to the inspection plans: 2004 Edition with No Addenda Date and revision of inspection plans: Revision 1. February 2011 Edition and Addenda of Section XA applicable to repair/replacement activities, if different than the inspection plans N/A Code Cases used: N-432-1. N-460, N-504-3. N-526, N-532-4. N-552, N-566-2. N-586-1, N-597-2. N-61 3-1. |
| | N-624, N-638-1, N-641, N-651, N-658, N-661, N-663, N-683, N-696, N-706-1, N-722, and N-729-1 (if applicable) |
| | CERTIFICATE OF CONFORMANCE I certify that (a) the statements made In this report are correct; (b) the examinations and tests meet the Inspection Plan as required by the ASME Code, Section Xi; and (c) the repair/replacement actUvities and evaluations supporting the completion of N2R21 conform to the requirements of Section XI. |
| | (refueling outage number) |
| | Signed Date 9-/Z Owner or Owner's Desine il CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Virginla and employed by HSB CT of Hartford, CT have inspected the items described In this Owner's Activity Report, and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section Xl. |
| | By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal Injury or property damage or a loss of any kind arising from or connected with this inspection. |
| | _ _ Cm Commissions NB 9531-A-N-I-C I VA 424-R Inspector's'Signature National Board, State, Province and Endorsements Date /, 3' L'-'-/2,ZtZ , |
| | Form No. 729596 (Aug 2009) |
| | |
| | Form OAR-1, Owner's Activity Report AT I ae WDominion- ER-l AISI10 ... |
| | TA HM N A2o Table I Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination Item Description Evaluation Description Category and Item Number H-603A Sway Strut for 2-SI-P- Eval per CR442495 for 1B improperly seated snap ring F-A / F1.40A does not impact the ability of the support to perform its design function in both normal Summary # N2.F1.40.090 or abnormal conditions. |
| | Snubber, 2-SI-HSS-809B 2 PSI found missing spacers, eval by CR442392 F-A / F1.20D verified that missing spacer does not impact ability of Summary# N2.F1.20.1 19 snubber to perform its function or provide support. |
| | Snubber 2-SI-HSS-421.02 CR442784, missing spacer on piston rod clevis pin, verified F-Al FI.IOD that missing spacer does not impact ability of snubber to |
| | #N2.11.10.095 perform its function or provide Summary# Nsupport. |
| | Snubber 2-RH-HSS-102 CR443946, loose bolt on pipe clamp, low fluid, tested SAT, F-A/ Fl.20D no slipping, evaluated as functional. Performed Summary # N2.F1 .20.371 additional examinations - |
| | ST SAT. |
| | Attachment Weld 12H *CR444219, Relevant indication found. CC N-586-1 B-KI B10.20 evaluation, construction flaw Summary # N2.B10.20.001 at surface. Ground out, teedST tested SAT. |
| | Snubber 2-RC-HSS-459.01 CR444443, snubber & pipe F-A /FI. 1OD clamp alignment/binding, Summary # N2.F1.10.222 tested SAT RPVH Pens #8, 15, and 23 CR443870, discoloration and B-E / B4.30 staining, cleaned and found no degradation. Evaluated Summary # N2.B4.30.001 SAT. |
| | RPVH Pen #18 CR444072, canopy seal weld B-E / B4.30 leakage from above, boric Summary # N2.134.30.001 acid residue, no degradation RPVH Pen #41 CR444091, residue from B-E I B4.30 canopy seal identified at pen Form No. 729595 (Aug 2009) |
| | |
| | Form OAR-I, Owner's Activity Report Dftminion- ERAA-S-0 ATTACMN I ae3o Summary# N2.B4.30.001 #18, no degradation Spring Hanger SH-1 CR446060, owner elected F-A / FI. 1OC examination found loose nut, evaluated as able to perform Summary# N2.Fl.10.263 design function Restraint R-537 CR444413, PSI found F-A / F1.20B clearance issue, evaluation determined within the Summary # N2.F1.20.253 standard. |
| | CR448737, rub marks and no Reactor Vessel Pad Support-5 measurable gap on one side. |
| | No depth or displaced metal, F-A I F1.40B free to move, permits thermal growth and restrains in lateral Summary # N2.F1 .40.067 and vertical direction, meets function. |
| | Form No. 729595 (Aug 2009) |
| | |
| | Form OAR-I, Owner's Activity Report WDominion-Table 2 Abstract of Repair/Replacement Activities Required for Continued Service Code Date Repair/Replacement Class Item Description Description of Work Completed Plan Number Snubber, 2-RC- 2nd preservice found 1 HSS-455.012preicfon 1 welded lug to anchor 2011-110 F-A / for paddle pin bent 11/6/2011 2011-120 F1.10D Summary# downward, N2.Fl.10.486 CR442774. |
| | 2"-WS-485-164-Q3 Replace 2" piping due 11/17/2011 2011-172 D-B / D2.10 downstream of 2- to MIC leak at weld SW-212 Form No. 729595 (Aug 2009)}} |
|
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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:Report
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 ML23214A1942023-09-0505 September 2023 Staff Assessment of Updated Seismic Hazards Following the NRC Process for the Ongoing Assessment of Natural Hazards Information - Report ML23103A2282023-04-12012 April 2023 Stations Units 1 and 2; Millstone Power Station Units 2 and 3, DOM-NAF-2-P/NP-A, Revision 0.4, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code ML22353A6202022-12-19019 December 2022 Request for Approval of Appendix F Fleet Report DOM-NAF-2-P, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code ML22255A0102022-06-28028 June 2022 Owner'S Activity Report ML22263A2852022-05-23023 May 2022 Alert and Notification System Evaluation Report_Ans Evaluation_Redacted Page 1-65 ML22119A1722022-04-13013 April 2022 Post-Accident Monitoring (PAM) Report ML21333A2842021-11-29029 November 2021 Requal Notification Letter ML21175A2472021-06-24024 June 2021 2020 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the....- ML21036A0772021-02-23023 February 2021 Review of Steam Generator Tube Inspection Report for the Cycle 26 Spring 2019 Refueling Outage ML21042B3212021-02-11011 February 2021 Stations, Units 1 & 2; Millstone Power Station, Units 2 & 3 - Request for Approval of Fleet Report DOM-NAF-2 Qualification of the Framatome BWU-I CHF Correlation in the Dominion Energy VIPRE-D Computer Code ML20254A3472020-09-0808 September 2020 Supplement to Operator License Examination Comments ML20247J6162020-09-0303 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 ML20246G7062020-08-24024 August 2020 Enclosure 4: Attachment 1 - PWROG-18005-NP, Revision 2, Determination of Unirradiated Rt and Upper-Shelf Values of the North Anna Units 1 and 2 Reactor Vessel Materials ML20203M1602020-07-20020 July 2020 VA Elec. & Power Co., Dominion Energy Nuclear Co. Inc., Dominion Energy Sc Inc., Millstone Power Station 2, N. Anna & Surry Power Stations 1 & 2, Virgil C. Summer Station 1, Updated Anchor Darling Double Disc Gate Valve Information & Status ML20149K6712020-05-31031 May 2020 PWROG-19047-NP, Revision 0, North Anna, Units 1 and 2, Reactor Vessels Low Upper-Shelf Fracture Toughness Equivalent Margin Analysis ML20140A2392020-05-18018 May 2020 ASME Section XI Inservicee Inspection Program Proposed Inservice Inspection Alternative N1-15-NDE-002 ML20246G7012020-03-31031 March 2020 Enclosure 4: Attachment 3 - WCAP-18364-NP, Rev. 1, North Anna Units 1 and 2 Time-Limited Aging Analysis on Reactor Vessel Integrity for Subsequent License Renewal (SLR) ML20090B3972020-03-26026 March 2020 Revised License Renewal Commitment Pressurizer Surge Line Weld Inspection Frequency ML20246G7072020-01-31031 January 2020 Enclosure 4: Attachment 4 - WCAP-11164-NP, Rev. 2, Technical Justification for Eliminating Large Primary Loop Pipe Rupture as the Structural Design Basis for North Anna Units 1 and 2 Nuclear Power Plants for the Subsequent License Renewal ML19347A4212019-11-26026 November 2019 Owner'S Activity Report ML19249B7742019-08-29029 August 2019 Enclosure 5 - Surry Power Station EAL Technical Bases Document Final (Updated) ML19249B7682019-08-29029 August 2019 Enclosure 3 - Millstone Power Station EAL Technical Bases Documents Final (Updated) ML19249B7782019-08-29029 August 2019 Enclosure 6 - Millstone Power Station, Unit 2, Comparison Matrix RCS Pot. Loss A.1 ML19249B7722019-08-29029 August 2019 Enclosure 4 - North Anna Power Station, EAL Technical Bases Document Final (Updated) ML19106A3562019-04-23023 April 2019 Review of Steam Generator Tube Inspection Report for the Cycle 26 Spring 2018 Refueling Outage ML19011A1722019-01-0404 January 2019 Enclosure 3, Attachments 2C-3C - MPS3 EAL Technical Bases Document (Marked-Up) ML19011A1732019-01-0404 January 2019 Enclosure 4 - North Anna Power Station Units 1 & 2, EAL Scheme Revisions-Supporting Documents ML19011A1742019-01-0404 January 2019 Enclosure 5 - Surry Power Station, EAL Scheme Revisions-Supporting Documents ML20246G7092018-10-31031 October 2018 Enclosure 4: Attachment 2 - WCAP-18353-NP, Rev. 0, Reactor Internals Fluence Evaluation for a Westinghouse 3-Loop Plant with Two Units - Subsequent License Renewal ML18198A1192018-05-31031 May 2018 Attachment 5 to 18-233, ANP-3467NP, Rev. 0, North Anna Fuel-Vendor Independent Small Break LOCA Analysis Licensing Report ML17186A0842017-06-29029 June 2017 Flooding Focused Evaluation Summary ML16187A3232016-06-24024 June 2016 Submittal of Owner'S Activity Report (Form OAR-1), for Refueling Outage N2R24 ML15253A4102016-03-11011 March 2016 Enclosure 2 Screening Analysis Report ML15238A8442015-09-25025 September 2015 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation ML15259A3422015-08-24024 August 2015 10 CFR 71.95 Report Evaluation Form; Submitted by Fenok, Erwin Resin Solutions, North Anna Power Stations, Et Al ML15232A8112015-08-24024 August 2015 Evaluation of Information Related to Commitments 6 and 8 from Confirmatory Action Letter No. NRR-2011-002 ML15238B5922015-08-17017 August 2015 Review of Commitment Action Completion Confirmation Action Letter Regarding Earthquake in 2011 ML15175A1902015-06-17017 June 2015 Owner'S Activity Report ML15057A2492015-04-20020 April 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations Relating to Recommendation 2.1 ML15058A0342015-02-23023 February 2015 Summary of Facility Changes, Tests and Experiments ML14133A0112014-05-0707 May 2014 March 12, 2012 Information Request Phase 2 Staffing Assessment Report ML14092A4162014-03-31031 March 2014 Response to March 12, 2012 Information Request Seismic Hazard and Screening Report (CEUS Sites)For Recommendation 2.1 ML14080A0022014-03-31031 March 2014 PNNL-22553, Final Assessment of Manual Ultrasonic Examinations Applied to Detect Flaws in Primary System Dissimilar Metal Welds at North Anna Power Station. ML14084A3272014-03-27027 March 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML14084A2122014-03-27027 March 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML14283A0462014-02-28028 February 2014 MRP-375, Technical Basis for Reexamination Interval Extension for Alloy 690 PWR Reactor Vessel Top Head Penetration Nozzles (EPRI 3002002441), Attachment 1 ML13338A4482014-01-29029 January 2014 Interim Staff Evaluation and Audit Report Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14006A1712014-01-23023 January 2014 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for North Anna Power Station, Units 1 and 2, TAC Nos.: MF0998 and MF0999 2024-02-01
[Table view] Category:Miscellaneous
MONTHYEARML24032A1112024-02-0101 February 2024 Owner'S Activity Report for North Anna, Unit 2, Refueling Outage N2R29 - First Period of the Fifth ISI Interval ML22353A6202022-12-19019 December 2022 Request for Approval of Appendix F Fleet Report DOM-NAF-2-P, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code ML22255A0102022-06-28028 June 2022 Owner'S Activity Report ML21333A2842021-11-29029 November 2021 Requal Notification Letter ML21036A0772021-02-23023 February 2021 Review of Steam Generator Tube Inspection Report for the Cycle 26 Spring 2019 Refueling Outage ML20254A3472020-09-0808 September 2020 Supplement to Operator License Examination Comments ML20247J6162020-09-0303 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 ML19347A4212019-11-26026 November 2019 Owner'S Activity Report ML17186A0842017-06-29029 June 2017 Flooding Focused Evaluation Summary ML16187A3232016-06-24024 June 2016 Submittal of Owner'S Activity Report (Form OAR-1), for Refueling Outage N2R24 ML15253A4102016-03-11011 March 2016 Enclosure 2 Screening Analysis Report ML15238A8442015-09-25025 September 2015 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation ML15259A3422015-08-24024 August 2015 10 CFR 71.95 Report Evaluation Form; Submitted by Fenok, Erwin Resin Solutions, North Anna Power Stations, Et Al ML15232A8112015-08-24024 August 2015 Evaluation of Information Related to Commitments 6 and 8 from Confirmatory Action Letter No. NRR-2011-002 ML15238B5922015-08-17017 August 2015 Review of Commitment Action Completion Confirmation Action Letter Regarding Earthquake in 2011 ML15175A1902015-06-17017 June 2015 Owner'S Activity Report ML15057A2492015-04-20020 April 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations Relating to Recommendation 2.1 ML15058A0342015-02-23023 February 2015 Summary of Facility Changes, Tests and Experiments ML14084A3272014-03-27027 March 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML14084A2122014-03-27027 March 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML14024A6022014-01-10010 January 2014 Post Accident Monitoring (PAM) Report ML14015A3142014-01-0808 January 2014 Submittal of Owner'S Activity Report Refueling Outage N1R23 (Form OAR-1) ML12160A2682012-06-11011 June 2012 Review of 60-Day Response to Request for Information Regarding Recommendation 9.3, of the Near-Term Task Force Related to the Fukushima Daiichi Nuclear Power Plant Accident ML12060A3492012-02-16016 February 2012 Owner'S Activity Report for Refueling Outage N2R21 ML12039A1602012-01-25025 January 2012 Steam Generator Tube Inspection Report ML12039A1612012-01-25025 January 2012 Steam Generator Tube Inspection Report ML12005A0112011-12-0909 December 2011 Independent Spent Fuel Storage Installation Response to Earthquake ML1103107402011-01-25025 January 2011 Owner'S Activity Report ML1019304172010-05-0606 May 2010 Tritium Database Report ML0921908942009-08-0404 August 2009 Units 1 & 2, Millstone, Units 2 and 3 and Kewaunee - Approved Topical Report DOM-NAF-2, Revision 0.1-A ML0913206392009-05-12012 May 2009 Reactor Coolant Pressure Boundary Visual Inspections Proposed Alternative - N1-I3-NDE-024 and N2-I3-NDE-025 ML0912504812009-05-0404 May 2009 30-Day Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML0901304802009-01-0505 January 2009 Owner'S Activity Report for Refueling Outage ML0812702032008-04-25025 April 2008 Summary of Facility Changes, Tests and Experiments ML0807903432008-03-18018 March 2008 Response to Request for Additional Information Steam Generator Tube Inspection Report ML0802800722008-01-0808 January 2008 Update on North Anna Zirlo Characterization and LOCA Embrittlement Testing ML0732002342007-11-15015 November 2007 Steam Generator Tube Inspection Report ML0728205762007-10-0909 October 2007 Steam Generator Tube Inspection Report ML0719704722007-07-13013 July 2007 Owner'S Activity Reports, for Refueling Outage (N2R18) ML0705903272007-02-27027 February 2007 Fitness-For-Duty Program Semi-Annual Performance Data Report ML0623300712006-08-16016 August 2006 Fitness-for-Duty Program Semi-Annual Performance Data Report ML0609404202006-03-27027 March 2006 Summary of Facility Changes, Tests and Experiments ML0634101622006-02-27027 February 2006 Fitness-For-Duty Program Semi-Annual Performance Data Report ML0602600412006-01-25025 January 2006 Virginia Electric and Power Company North Anna Power Station Unit 2 - Owner'S Activity Reports ML0523501142005-08-22022 August 2005 Fitness-For-Duty Program Semi-Annual Performance Data Report ML0514603252005-05-25025 May 2005 .2 & 3, North Anna Power Station Units 1 & 2, Surry Power Station Units 1 & 2 - Nuclear Liability Insurance Endorsement ML0505403042005-02-22022 February 2005 Fitness-for-Duty Program Semi-Annual Performance Data Report Correction of Information ML0505300392005-02-21021 February 2005 Fitness-for-duty Program Semi-Annual Performance Data Report ML0727008492005-01-31031 January 2005 Caldon Experience in Nuclear Feedwater Flow Measurement ML0427101862004-09-24024 September 2004 Emergency Response Data System (ERDS) Database Revisions 2024-02-01
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Text
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 February 16, 2012 U.S. Nuclear Regulatory Commission Serial No.: 12-083 Attention: Document Control Desk NAPS/JHL: RO Washington, D.C. 20555 Docket No.: 50-339 License No.: NPF-7 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
NORTH ANNA POWER STATION UNIT 2 OWNER'S ACTIVITY REPORT In accordance with the requirements of American Society of Mechanical Engineers (ASME) Code Case N-532-4, enclosed is the Owner's Activity Report (Form OAR-I), for refueling outage N2R21. This report is for the first refueling outage of the first period of the fourth inspection interval.
Should you have any questions regarding this submittal, please contact Mr. Donald R.
Taylor at (540) 894-2616.
Very truly yours,
- . -
F. Mladen Director - Nuclear Station Safety and Licensing Commitments made in this letter: None Attachment ocl Q U
P.
cc: U.S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Avenue, NE, Suite 1200 Atlanta, Georgia 30303-1257 NRC Senior Resident Inspector North Anna Power Station Mr. J. E. Reasor, Jr.
Old Dominion Electric Cooperative Innsbrook Corporate Center 4201 Dominion Blvd.
Suite 300 Glen Allen, Virginia 23060 Dr. V. Sreenivas NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 0-8 G9A Rockville, MD 20852-2738 Ms. K. R. Cotton NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 0-8 G9A Rockville, MD 20852-2738 Mr. M. M. Grace Authorized Nuclear Inspector North Anna Power Station
W Attachment Owner's Activity Reports for North Anna Unit 2 Refueling Outage N2R21 - First Period of the Fourth ISI Interval Virginia Electric and Power Company (Dominion)
Form OAR-I, Owner's Activity Report
&OFDominion- E-,A-S-0 ATAHET PaeIo Report Number: N2R21 (Unit 1, 4th Interval, 1 a Period)
Plant: North Anna Power Station Unit No. 2f Commercial service date: 12/14/1980 Refueling outage no. N2R21 (if applicable)
Current inspection interval: 4t" (December 14, 2010 - December 13, 2020)
(16, 2no, 3T, 4 t , other)
Current inspection period: 1" (December 14,.2010 - December 13, 2013)
(19, 2no, 3rd, 4e1)
Edition and Addenda of Section XA applicable to the inspection plans: 2004 Edition with No Addenda Date and revision of inspection plans: Revision 1. February 2011 Edition and Addenda of Section XA applicable to repair/replacement activities, if different than the inspection plans N/A Code Cases used: N-432-1. N-460, N-504-3. N-526, N-532-4. N-552, N-566-2. N-586-1, N-597-2. N-61 3-1.
N-624, N-638-1, N-641, N-651, N-658, N-661, N-663, N-683, N-696, N-706-1, N-722, and N-729-1 (if applicable)
CERTIFICATE OF CONFORMANCE I certify that (a) the statements made In this report are correct; (b) the examinations and tests meet the Inspection Plan as required by the ASME Code, Section Xi; and (c) the repair/replacement actUvities and evaluations supporting the completion of N2R21 conform to the requirements of Section XI.
(refueling outage number)
Signed Date 9-/Z Owner or Owner's Desine il CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Virginla and employed by HSB CT of Hartford, CT have inspected the items described In this Owner's Activity Report, and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section Xl.
By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal Injury or property damage or a loss of any kind arising from or connected with this inspection.
_ _ Cm Commissions NB 9531-A-N-I-C I VA 424-R Inspector's'Signature National Board, State, Province and Endorsements Date /, 3' L'-'-/2,ZtZ ,
Form No. 729596 (Aug 2009)
Form OAR-1, Owner's Activity Report AT I ae WDominion- ER-l AISI10 ...
TA HM N A2o Table I Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination Item Description Evaluation Description Category and Item Number H-603A Sway Strut for 2-SI-P- Eval per CR442495 for 1B improperly seated snap ring F-A / F1.40A does not impact the ability of the support to perform its design function in both normal Summary # N2.F1.40.090 or abnormal conditions.
Snubber, 2-SI-HSS-809B 2 PSI found missing spacers, eval by CR442392 F-A / F1.20D verified that missing spacer does not impact ability of Summary# N2.F1.20.1 19 snubber to perform its function or provide support.
Snubber 2-SI-HSS-421.02 CR442784, missing spacer on piston rod clevis pin, verified F-Al FI.IOD that missing spacer does not impact ability of snubber to
- N2.11.10.095 perform its function or provide Summary# Nsupport.
Snubber 2-RH-HSS-102 CR443946, loose bolt on pipe clamp, low fluid, tested SAT, F-A/ Fl.20D no slipping, evaluated as functional. Performed Summary # N2.F1 .20.371 additional examinations -
ST SAT.
Attachment Weld 12H *CR444219, Relevant indication found. CC N-586-1 B-KI B10.20 evaluation, construction flaw Summary # N2.B10.20.001 at surface. Ground out, teedST tested SAT.
Snubber 2-RC-HSS-459.01 CR444443, snubber & pipe F-A /FI. 1OD clamp alignment/binding, Summary # N2.F1.10.222 tested SAT RPVH Pens #8, 15, and 23 CR443870, discoloration and B-E / B4.30 staining, cleaned and found no degradation. Evaluated Summary # N2.B4.30.001 SAT.
RPVH Pen #18 CR444072, canopy seal weld B-E / B4.30 leakage from above, boric Summary # N2.134.30.001 acid residue, no degradation RPVH Pen #41 CR444091, residue from B-E I B4.30 canopy seal identified at pen Form No. 729595 (Aug 2009)
Form OAR-I, Owner's Activity Report Dftminion- ERAA-S-0 ATTACMN I ae3o Summary# N2.B4.30.001 #18, no degradation Spring Hanger SH-1 CR446060, owner elected F-A / FI. 1OC examination found loose nut, evaluated as able to perform Summary# N2.Fl.10.263 design function Restraint R-537 CR444413, PSI found F-A / F1.20B clearance issue, evaluation determined within the Summary # N2.F1.20.253 standard.
CR448737, rub marks and no Reactor Vessel Pad Support-5 measurable gap on one side.
No depth or displaced metal, F-A I F1.40B free to move, permits thermal growth and restrains in lateral Summary # N2.F1 .40.067 and vertical direction, meets function.
Form No. 729595 (Aug 2009)
Form OAR-I, Owner's Activity Report WDominion-Table 2 Abstract of Repair/Replacement Activities Required for Continued Service Code Date Repair/Replacement Class Item Description Description of Work Completed Plan Number Snubber, 2-RC- 2nd preservice found 1 HSS-455.012preicfon 1 welded lug to anchor 2011-110 F-A / for paddle pin bent 11/6/2011 2011-120 F1.10D Summary# downward, N2.Fl.10.486 CR442774.
2"-WS-485-164-Q3 Replace 2" piping due 11/17/2011 2011-172 D-B / D2.10 downstream of 2- to MIC leak at weld SW-212 Form No. 729595 (Aug 2009)