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MONTHYEARML11258A0212011-09-14014 September 2011 Request for Additional Information Regarding the Earthquake of August 23, 2011 (TAC Nos. ME7050 and ME7051) Project stage: RAI ML11262A2602011-09-14014 September 2011 Communication Plan for North Anna Nuclear Power Plant Earthquake Response Project stage: Other ML11269A0922011-09-26026 September 2011 Request for Information Regarding the Earthquake of August 23, 2011 Project stage: RAI ML11270A3172011-09-28028 September 2011 Request for Information Regarding the Earthquake of August 23, 2011 Project stage: RAI ML11272A1712011-09-30030 September 2011 Request for Information Regarding the Earthquake on August 23, 2011 Project stage: RAI ML11278A1322011-10-0606 October 2011 Request for Information Regarding August 23, 2011 Earthquake Project stage: RAI 2011-09-26
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Category:Letter
MONTHYEARIR 05000338/20244202024-09-23023 September 2024 Security Baseline Inspection Report 05000338/2024420 and 05000339/2024420, Cover Letter IR 05000338/20244022024-09-17017 September 2024 Security Baseline Inspection Report 05000338/2024402 and 05000339/2024402 ML24215A2622024-08-28028 August 2024 Transmittal Letter for Subsequent Renewed License IR 05000338/20240052024-08-27027 August 2024 Updated Inspection Plan for North Anna Power Station, Units 1 and 2 (Report 05000338/2024005 and 05000339/2024005) 05000339/LER-2024-001, Loss of Generator Field for 2J Eog During 2-PT-82.282024-08-20020 August 2024 Loss of Generator Field for 2J Eog During 2-PT-82.28 ML24234A0742024-08-15015 August 2024 Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Letter OG-23-63, NEI 03-08 Needed Guidance: PWR Thermal Shield Flexure Inspection Requirements 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 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) ML24221A1832024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Chickahominy Indian Tribe-Eastern Division ML24221A1852024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Delaware Tribe of Indians ML24221A1942024-08-0808 August 2024 Tribal Section 106 Letters-North Anna-United Keetoowah Band of Cherokee Indians in Oklahoma ML24221A1912024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Rappahannock Tribe, Inc ML24221A1882024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Monacan Indian Nation ML24221A1932024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Upper Mattaponi Tribe ML24206A0052024-08-0808 August 2024 SLR Final EIS Letter to Achp ML24221A1842024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Delaware Nation, Oklahoma ML24221A1922024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Tuscarora Nation of New York ML24221A1872024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Eastern Shawnee Tribe of Oklahoma ML24221A1862024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Eastern Band of Cherokee Indians ML24221A1812024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Catawba Indian Nation ML24208A0142024-08-0808 August 2024 Tribal Section 106 Letters-North Anna-Absentee-Shawnee Tribe of Indians of Oklahoma ML24221A1822024-08-0808 August 2024 Tribal Section 106 Letters - North Anna - Chickahominy Indian Tribe ML24221A1892024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Nansemond Indian Nation ML24241A0692024-08-0606 August 2024 ISFSI, Submittal of Cask Registration for Spent Fuel Storage IR 05000338/20240022024-08-0202 August 2024 Integrated Inspection Report 05000338/2024002 and 05000339/2024002 ML24206A0432024-07-26026 July 2024 Feis - Letter to the Applicant 05000338/LER-2024-001, Automatic Reactor Trip Due to Prni High Negative Rate2024-07-25025 July 2024 Automatic Reactor Trip Due to Prni High Negative Rate ML24206A0902024-07-24024 July 2024 Owners Activity Report ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24143A1622024-06-12012 June 2024 – Correction to Issuance of Amendment Nos. 297 and 280 and Surry Units 1 and 2, Correction to Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code ML24165A1462024-06-0505 June 2024 Loss of Generator Field for 2J EDG During 2-PT-82.28 IR 05000338/20240102024-05-24024 May 2024 NRC Fire Protection Team Inspection (FPTI) Report 05000338/2024010 and 05000339/2024010 IR 05000338/20240012024-05-10010 May 2024 Integrated Inspection Report 05000338/2024001 and 05000339/2024001 IR 05000338/20244032024-04-30030 April 2024 – Security Baseline Inspection Report 05000338-2024403 and 05000339-2024403 ML24054A0142024-04-22022 April 2024 Issuance of Amendment Nos. 297 and 280, and Surry Power Station Unit Nos. 1 and 2, Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times ML24110A1462024-04-18018 April 2024 Independent Spent Fuel Storage Installation (Sfsi) - Annual Radiological Environmental Operating Report ML24110A1502024-04-18018 April 2024 Independent Spent Fuel Storage Installation (ISFSI) - Annual Radioactive Effluent Release Report ML24110A1392024-04-18018 April 2024 Annual Environmental Operating Report ML24087A0572024-04-16016 April 2024 Correction to Issuance of Amendment Nos. 296 and 279 ML24088A2692024-03-27027 March 2024 Core Operating Limits Report Cycle 31 Pattern Sos Revision 0 ML24086A4292024-03-25025 March 2024 Response to Request for Additional Information Associated with Alternative Request N1-I5-NDE-007 Request to Deter Additional Required Reactor Coolant Pump Casing Inspection ML24082A2742024-03-22022 March 2024 Request for Approval of Alternative Request N1-I5-NDE-007 to Deter Additional Required Reactor Coolant Pump Casing Inspection ML24086A4682024-03-21021 March 2024 Summary of Facility Changes, Tests and Experiments ML24005A0042024-03-18018 March 2024 Issuance of Amendment Nos. 296 and 279, Regarding Revised Emergency Plan for Relocation of the Technical Support Center ML24074A3012024-03-14014 March 2024 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000338-2024403 and 05000339-2024403) IR 05000338/20244012024-03-0808 March 2024 Security Baseline Inspection Report 05000338/2024401, 05000339/2024401 and 07200016/2024401 IR 05000338/20230062024-02-28028 February 2024 Annual Assessment Letter for North Anna Power Station, Units 1 and 2 - NRC Inspection Reports 05000338/2023006 and 05000339/2023006 2024-09-23
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24087A0112024-03-23023 March 2024 NRR E-mail Capture - Draft RAIs for Reactor Coolant Pump (RCP) Relief Request (L-2024-LLR-0022) ML23318A1172023-11-13013 November 2023 NRR E-mail Capture - Formal Issuance of RAIs for North Anna Technical Support Center (TSC) License Amendment Request (LAR) (L-2023-LLA-0006) ML23257A2092023-09-14014 September 2023 NRR E-mail Capture - Formal Issuance of 2nd Round RAIs for Surry Units 1&2 and North Anna Units 1&2 Emergency Plans LAR ML23243A9862023-08-31031 August 2023 NRR E-mail Capture - Draft RAIs for EP Staff Augmentation Times LAR (L-2022-LLA-0166) ML23219A1602023-08-0707 August 2023 003 Radiation Safety Baseline Inspection Information Request ML23171B0522023-06-20020 June 2023 NRR E-mail Capture - RAI for Review of Appendix F to DOM-NAF-2-P (Redacted) ML23081A5282023-04-26026 April 2023 Request for Additional Information - North Anna Subsequent License Renewal Application Environmental Review ML23075A0232023-03-15015 March 2023 NRR E-mail Capture - RAI - License Amend Req (LAR) to Revise Tech Spec (Ts) 3.6.8 Limiting Condition for Operation to Remove Refueling Water Chemical Addition Tank and Replace the Containment Sump Buffer North Anna, 1 and 2 (L-2022-LLA-0162 ML23060A0932023-03-0101 March 2023 NRR E-mail Capture - Formal Issuance of RAIs for Surry/North Anna Emergency Plans LAR ML23059A2282023-02-28028 February 2023 NRR E-mail Capture - Draft RAIs for Containment Buffer Change to Natb (L-2022-LLA-0162) ML22251A1292022-09-0909 September 2022 Request for Additional Information Related to Response to Generic Letter 2004-04 ML22242A0452022-08-23023 August 2022 NRR E-mail Capture - Dominion GL 04-02 Response Draft RAIs (L-2017-LRC-0000) ML22083A2102022-03-24024 March 2022 NRR E-mail Capture - Draft RAI - Relief Request N2-14-LMT-003 Fourth Ten Year Inservice Inspection Interval ML21327A3652021-11-23023 November 2021 NRR E-mail Capture - Draft RAI for TSTF-577 LAR ML21322A0962021-11-18018 November 2021 Final Request for Additional Information Set 5 - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Email ML21322A0992021-11-18018 November 2021 Final Request for Additional Information Set 5 - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Enclosure ML21256A0672021-09-13013 September 2021 Final Request for Confirmation of Information Set 2 - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Email ML21256A0692021-09-13013 September 2021 Final Request for Confirmation of Information Set 2 - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Request for Confirmation of Information ML21238A0942021-08-25025 August 2021 Draft Request for Additional Information Set Z - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Email ML21238A0982021-08-25025 August 2021 Draft Request for Additional Information Set Z - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Enclosure ML21225A5022021-08-13013 August 2021 Request for Additional Information for North Anna Power Station, Units 1 and 2, Surry Power Station, Units 1 and 2, and Millstone Power Station, Units 2 and 3, Appendix E of Fleet Report Com-Naf-2 (EPID:L02021-LLT-0000) Public Version ML21195A2442021-07-13013 July 2021 NRR E-mail Capture - Draft RAI Appendix E to Topical Report DOM-NAF-2 Qualification of the Framatome BWU-I CHF Correlation in the Dominion Energy VIPRE-D Computer Code ML21188A1632021-07-0707 July 2021 Final Request for Additional Information Set 4 - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Email ML21188A1652021-07-0707 July 2021 Final Request for Additional Information Set 4 - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Enclosure ML21174A1952021-06-23023 June 2021 Safety RAIs - Set Y - Draft - Enclosure ML21166A3512021-06-15015 June 2021 Safety RAIs - Set 4 - Draft ML21123A2972021-05-0303 May 2021 Final Request for Additional Information Set 3 - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - E-mail ML21123A2982021-05-0303 May 2021 Final Request for Additional Information Set 3 - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Enclosure ML21091A0032021-04-0101 April 2021 Final Request for Additional Information Set 2 - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Enclosure 1 - RAIs ML21091A0042021-04-0101 April 2021 SLRA Safety Review - Withdrawn Requests for Information (EPID No. L-2020-SLR-0000) - Enclosure 2 ML21076A4622021-03-17017 March 2021 NRR E-mail Capture - Draft RAI for Versatile Internals and Component Program for Reactors Vipre Code Review (L-2021-LLT-0000) ML21075A0032021-03-12012 March 2021 Emergency Preparedness Exercise Inspection Request for Information for - Brunswick, Catawba, North Anna, Oconee, Vogtle 1 & 2 ML21063A5602021-03-0404 March 2021 Final Request for Additional Information Set 1 - North Anna SLRA Safety Review (EPID L-2020-SLR-0000) - Enclosure ML21049A0212021-02-17017 February 2021 Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000338/2021012 and 05000339/2021012) and Request for Information (RFI) ML21028A3902021-01-29029 January 2021 Request for Additional Information - North Anna Subsequent License Renewal Application Environmental Review (EPID Number: L-2020-SLE-0000) (Docket: 50-338 and 50-339) ML21028A4352021-01-28028 January 2021 Notification of Target Set Inspection and Request for Information (NRC Inspection Report No. 05000338/2021404 and 05000339/2021404) ML21012A3412021-01-22022 January 2021 Requests for Confirmation of Information for the Environmental Review of the North Anna Power Station, Units 1 and 2, Subsequent License Renewal Application (EPID Number: L-2020-SLE-0000) (Docket: 50-338 and 50-339) ML21019A4512021-01-19019 January 2021 Notification of Inspection and Request for Information ML20316A0422020-11-10010 November 2020 NRR E-mail Capture - FW: Draft RAI for North Anna Unit 2 Steam Generator Tube Inspection Report (ML19179A075) ML20223A3412020-08-10010 August 2020 003 Radiation Safety Baseline Inspection Information Request ML20218A4282020-08-0505 August 2020 Notification of Inspection and Request for Information ML20125A0762020-05-0101 May 2020 NRR E-mail Capture - Draft RAI Related to Revised Reactor Vessel Material Surveillance Capsule Withdrawal Schedule Dominion Energy Virginia North Anna Power Station Units 1 and 2 (L-2020-LLL-0038) ML20113A5792020-04-21021 April 2020 NRR E-mail Capture - Draft RAI North Anna Fifth 10-year Interval Relief Request (L-2020-LLR-0023) ML19354B6142019-12-20020 December 2019 NRR E-mail Capture - Draft RAI for North Anna Relief Request P-9 ML19317F1042019-11-0707 November 2019 NRR E-mail Capture - Draft RAIs for SB LOCA LAR (Non Prop) ML19191A2512019-07-10010 July 2019 NRR E-mail Capture - Request for Additional Information Open Phase Condition LAR ML19169A0962019-06-17017 June 2019 NRR E-mail Capture - Request for Additional Information Emergency Action Level Scheme Change for Millstone Power Station - Units 1, 2, and 3, North Anna Power Station - Units 1 and 2, and Surry Power Station - Units 1 and 2 ML19162A0052019-06-10010 June 2019 NRR E-mail Capture - Draft RAIs for Dominion EAL Scheme Change ML19108A1902019-04-18018 April 2019 Emergency Preparedness Program Inspection Request for Information ML19060A2432019-03-0101 March 2019 Related to License Amendment Request to Address Open Phase Conditions 2024-03-23
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UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 September 26, 2011 Mr. David A. Heacock President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711 NORTH ANNA POWER STATION, UNIT NOS. 1 AND 2, REQUEST FOR INFORMATION REGARDING THE EARTHQUAKE OF AUGUST 23,2011 (TAC NOS. ME7050 AND ME7051)
Dear Mr. Heacock:
A public meeting was held between the Virginia Electric and Power Company and the Nuclear Regulatory Commission (NRC) staff on September 8, 2011, to discuss the earthquake that occurred near the North Anna Power Station (NAPS) on August 23, 2011, and an NRC request for information was issued on September 14, 2011, on that topic. On September 17, 2011, you submitted the report, "Virginia Electric and Power Company (Dominion)
North Anna Power Station, Units 1 and 2, North Anna Independent Spent Fuel Storage Installation Summary Report of August 23, 2011, Earthquake Response and Restart Readiness Determination Plan" (Agencywide Documents Access and Management System Accession No. ML 11262A 151). This letter forwards the staff's request for information on additional topics. Your most expeditious response is requested to enable the staff to continue its review of your proposed plans for restarting the NAPS. Sincerely, Meena Khanna Lead of North Anna Restart Team Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-338 and Request for cc w/encl: Distribution via REQUEST FOR INFORMATION VIRGINIA ELECTRIC AND POWER COMPANY (VEPCO) NORTH ANNA POWER STATION. UNIT NOS. 1 AND 2 (NAPS) DOCKET NOS. 50-338 AND 50-339 The following requests for information are related to the earthquake of August 23, 2011, that occurred in the vicinity of the North Anna Power Station, Unit Nos. 1 and 2 (NAPS), as discussed in the public meeting held by the Nuclear Regulatory Commission (NRC) staff on September 8, 2011 and communicated to the NRC in a letter dated September 17, 2011, (ADAMS Accession No. ML 11262A151).
Heating. Ventilation and Air Conditioning Provide the basis for concluding that the bypass leakage of the safety-related charcoal filters meets technical specifications. Provide the basis for concluding that the control room in-leakage remains less than assumed in the control room habitability dose analysis.
Containment Explain how VEPCO has re-established operability of the containment. Explain whether VEPCO has performed analyses of the stresses, specifically of the containment structures. What were the results? If analyses were not performed, discuss why such analyses are not needed prior to restart. Confirm whether VEPCO performed inservice testing on containment isolation valves during the shutdown.
List the valves tested and provide the results. Confirm whether VEPCO performed a general visual inspection of the containment consistent with Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Appendix J and industry guidance in Nuclear Energy Institute document NEI 94-01, "Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J," and American National Standards Institute/American Nuclear Society document ANSIIANS 56.8, "Containment System Leakage Testing Requirements" as referenced in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program"?
If performed, provide the results. If not performed, list the containment inspections performed and provide the results. Enclosure Electrical Explain how VEPCa has determined that all electrical equipment, including electrical equipment that was commercially dedicated by the licensee, as well as the safety-related batteries, required to function during and following a seismic event (operating basis earthquake and safe shutdown earthquake (aBE/SSE>>, remains qualified to perform their required safety-functions during all design basis events. Explain how VEPCa has determined that electrical connections (Le., electrical bus bars (power and control cable and wiring connections at all voltage levels), battery, contactors, etc.) maintained their electrical connection integrity to perform their required safety-functions under both normal and accident conditions and also during and following another seismic event (aBE or SSE). Explain how VEPCa has determined that support features associated with bus bars, battery racks, switchgear, cable raceways, containment electrical penetration assemblies, etc., are adequate to enable electrical equipment to perform their required safety-functions under both normal and accident conditions and also during and following another seismic event (aBE or SSE). Explain how VEPCa has evaluated the emergency diesel generator and the support systems (cooling water, starting air and fuel oil) to ensure maintenance of their required safety-functions during all design-basis events. Explain how electrical systems were declared operable including any integrated tests performed.
Was any maintenance or operator action required following the seismic event to restore the integrity of any equipment required for plant safe shutdown? Explain how VEPCa has determined that the neutron flux instrumentation functioned in accordance with the design requirement and that the trip was valid. Regarding the NAPS dual-unit trips, how did VEPCa determine that the offsite power system has adequate capacity and capability to mitigate all design-basis events and that the degraded voltage setpoints are adequate.
Instrumentation and Controls (I&C) The staff understands that VEPCa has been examining all unusual spurious states of I&C and electrical equipment that impacted the sequence-of-events recorders and other post-trip review logs from the August 23, 2011, event, and that the NRC staff Augmented Inspection Team members are evaluating the licensee's actions in thoroughly investigating the root causes of unexpected equipment performance in this area. Describe how these unexpected instrumentation issues were resolved. The licensee's presentation to the NRC staff on September 8, 2011, identified that "comprehensive surveillance testing to validate SSC [structures, systems, and components1 operability/performance" (448 surveillance tests) will be performed.
The staff would like to understand the basis for selection of the particular I&C-related surveillance tests that are scheduled to be performed (or were performed) and whether the licensee has identified any
-additional acceptance criteria for such testing that may require additional field confirmations or additional test steps to be performed during such surveillance testing. For example, some reactor trip system and engineered safety feature periodic functional testing is performed without including the local transmitter in the loop, and some locally mounted instrumentation devices have flexible conduit connections.
Should these connections be subjected to seismic acceleration in key natural frequencies of the flexible section that are in excess of design-basis conditions, the additional stress put on the instrument terminals could weaken the electrical connections at the terminal strips of the devices, which could result in momentary disruption of the signal, but not permanent disruption that would manifest itself under the static conditions normally present during a periodic surveillance test. Describe how potentially loose electrical and/or mechanical connections were addressed.
- b. Describe how the verification of the safety related instrumentation (especially mechanical instrumentation) calibration remained within the speci'fication limits was performed.
- c. Describe how verification that safety related instrumentation channel response times remained within the specification limits was performed (especially the settings of mechanically-based instrumentation devices and relays, e.g., Agastat time delay relays, resulting in a total channel response time that could exceed analyzed event response time requirements) The staff requests the licensee to confirm that the plans for start-up testing of each unit include confirmation of proper operation of non-safety, but important to safety control systems, such as would be performed as elements of the pre-operational and power ascension testing described within Appendix A to Revision 3 of 1.68, "Initial Test Programs for Water-Cooled Nuclear Power Plants," to verify proper operability of the normal (nonsafety related) plant control systems (e.g., feedwater control, rod control, pressurizer level and pressure controls, secondary system steam pressure control system, main turbine and feedwater pump turbine control systems, in-core instrumentation, plant annunciator and process computer systems, seismic instrumentation system, plant instrumentation grounding system, etc.). Confirm which nonsafety but important-to-safety plant systems were identified by the licensee as critical to the safe operation of the plant. Confirm what pre-operational testing has been selected to confirm proper operability of these systems prior to startup. Identify the sequence of testing and administrative controls that will be utilized during the planned power ascension during restart to ensure that such systems are properly operating before increasing to the next power level.
-4 Fire Protection Describe how VEPCO has verified or confirmed the functionality following the earthquake of the fire protection SSCs, both passive and active, that are credited in the NAPS approved fire protection program or are relied upon to ensure safe shutdown in the event of a fire. Describe plant staff activities that have been conducted (testing, etc.) subsequent to the earthquake.
Identify any discrepancies found as a result of these activities that may have affected functionality or indicated a need for repairs. Include plant staff activities related to assuring functionality of automatic and manual fire protection systems and fire-fighting equipment. Also indicate if there were fire protection system actuations, detection system signals or other fire protection related indications due to the earthquake.
Probabilistic Risk Assessment Was the functionality of any nonsafety related equipment, credited in a risk-informed license amendment for NAPS, considered as part of the restart plan? If not, what is VEPCO's approach to ensure the continued adequacy of such risk-informed license amendments?
Steam Generators Describe the evaluations, inspections, and analyses (if any) of the steam generators (SGs) to ensure the SG supports, tubes, and other internals (tube support structures, steam separation equipment, j-nozzles, wrapper and wrapper supports, blowdown piping, etc.) will function as designed.
If a sample inspection were performed, please provide justification for limiting the scope of the inspections.
Please discuss the results of the inspections highlighting any differences observed since the last inspections.
September 26, 2011 Mr. David A. Heacock President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711 NORTH ANNA POWER STATION, UNIT NOS. 1 AND 2, REQUEST FOR INFORMATION REGARDING THE EARTHQUAKE OF AUGUST 23,2011 (TAC NOS. ME7050 AND ME7051)
Dear Mr. Heacock:
A public meeting was held between the Virginia Electric and Power Company and the Nuclear Regulatory Commission (NRC) staff on September 8, 2011, to discuss the earthquake that occurred near the North Anna Power Station (NAPS) on August 23, 2011, and an NRC request for information was issued on September 14, 2011, on that topic. On September 17, 2011, you submitted the report, "Virginia Electric and Power Company (Dominion)
North Anna Power Station, Units 1 and 2, North Anna Independent Spent Fuel Storage Installation Summary Report of August 23, 2011, Earthquake Response and Restart Readiness Determination Plan" (Agencywide Documents Access and Management System Accession No. IVIL 11262A 151). This letter forwards the staff's request for information on additional topics. Your most expeditious response is requested to enable the staff to continue its review of your proposed plans for restarting the NAPS. Sincerely, IRA! Meena Khanna Lead of North Anna Restart Team Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-338 and Request for cc w/encl: Distribution via DISTRIBUTION:
Public RidsNrrLACSola Resource LPL2-1 R/F RidsOgcRp Resouce RidsNrrLpl2-1 Resource RidsRgn2MailCenter Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDorlDpr Resource RidsNrrPMNorthAnna Resource PClifford, NRR RidsNrrPMNorthAnna Resource PBoyle, NRR DRoth,OGC MKhanna, NRR PHiland, NRR GMcCoy, Rgn2 RidsNrrDorl KKarwoski, NRR ADAMS Accession No. ML 11269A092 OFFICE NRRlLPL2-1/PM NAME DATE 09/26/11