|
---|
Category:E-Mail
MONTHYEARML24107A9112024-04-15015 April 2024 NRC to Fws, Follow-up on Request for Concurrence for North Anna SLR ML24107A9122024-04-11011 April 2024 Fws to NRC, Follow-up on Request for Concurrence for North Anna SLR ML24087A0102024-03-26026 March 2024 NRR E-mail Capture - Verbal Relief for North Anna Unit 1 - (ASME Code), Section XI, Subsection IWB-2430 ML24087A0112024-03-23023 March 2024 NRR E-mail Capture - Draft RAIs for Reactor Coolant Pump (RCP) Relief Request (L-2024-LLR-0022) ML24107B1562024-02-20020 February 2024 Cherokee Nation E.Toombs Na Removal Request ML24044A2462024-02-0606 February 2024 001 Radiation Safety Baseline Inspection Information Request ML23320A1122024-01-18018 January 2024 NRC to Fws, Concurrence with Endangered Species Act Determinations for North Anna Power Station, Units 1 and 2, Subsequent License Renewal, Issuance of Draft Supplemental Environmental Impact Statement, and Opportunity for Public Comment ML23355A2722023-12-21021 December 2023 NRR E-mail Capture - Schedule Revision for Emergency Preparedness Staff Augmentation Times License Amendment Request 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) 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 ML23067A2162023-03-0707 March 2023 NRR E-mail Capture - RAI for North Anna, 1 & 2, Surry 1 & 2, Millstone, 2 & 3, Request for Approval of App. F Fleet Report DOM-NAF-2-P, Qual of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion VIPRE-D Computer Code 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) ML23039A1712023-02-0808 February 2023 NRR E-mail Capture - Acceptance Review for Technical Support Center (TSC) Relocation (L-2023-LLA-0006) ML23018A0352023-01-17017 January 2023 NRR E-mail Capture - Acceptance Review for Fleet Report Re Appendix F of DOM-NAF-2-P (L-2022-LLT-0003) ML22342B1472022-12-0808 December 2022 NRR E-mail Capture - Acceptance Review for LAR Re NAPS Post LOCA Buffer Change (L-2022-LLA-0162) ML22335A4842022-12-0101 December 2022 NRR E-mail Capture - Acceptance Review for LAR North Anna Power Station - Units 1 and 2 and Surry Power Station - Units 1 and 2 Emergency Plan Staff Augmentation Times (L-2022-LLA-0166) ML22242A0452022-08-23023 August 2022 NRR E-mail Capture - Dominion GL 04-02 Response Draft RAIs (L-2017-LRC-0000) ML22174A3552022-06-23023 June 2022 NRR E-mail Capture - Acceptance Review for Dominion Fleet LAR to Implement TSTF-554 (L-2022-LLA-0078) ML22104A0252022-04-14014 April 2022 NRR E-mail Capture - Dominion Presentation Slides for April 21, 2022 Public Meeting on Emergency Preparedness Submittal for the North Anna Power Station and the Surry Power Station ML22083A2102022-03-24024 March 2022 NRR E-mail Capture - Draft RAI - Relief Request N2-14-LMT-003 Fourth Ten Year Inservice Inspection Interval ML22032A0962022-02-0101 February 2022 002 Radiation Safety Baseline Inspection Information Request ML22018A0272022-01-18018 January 2022 2022 All RFI Responses - Exercise and Program Inspections - Revl ML22007A2672022-01-0707 January 2022 NRR E-mail Capture - North Anna, Unit 2, ASME Section XI Inservice Inspection Program Relief Request N2-14-LMT-003 Fourth Interval Third Period Limited Examinations (L-2021-LLR-0088) ML21335A0812021-12-0101 December 2021 NRR E-mail Capture - Acceptance Review for OMN-28 Request Alternative to ISTC-3700, Position Verification Testing (L-2021-LLR-0086) ML21334A1922021-11-30030 November 2021 NRR E-mail Capture - Audit Plan for Reactor Core Thermal-Hydraulics Using the VIPRE-D Appendix E Review ML21327A3652021-11-23023 November 2021 NRR E-mail Capture - Draft RAI for TSTF-577 LAR ML21326A1502021-11-22022 November 2021 NRR E-mail Capture - Acceptance Review for Relocation of Unit Staff Requirements to the QAPD LAR (L-2021-LLA-0195) ML21322A0962021-11-18018 November 2021 Final Request for Additional Information Set 5 - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Email ML21312A0082021-11-0404 November 2021 Enclosure 2 - NAPS Draft SER Table A.1-1 Markup ML21312A0012021-11-0404 November 2021 Comments on North Anna Draft SER ML21312A0112021-11-0404 November 2021 Enclosure 3 - NAPS Draft SER Section 3 Comments ML21306A3302021-11-0202 November 2021 NRR E-mail Capture - Acceptance Review for TSTF-569 LAR ML21286A7372021-10-13013 October 2021 Additional Element Included in the Implementation Plan for the Surry Fuel Melt Safety Limit (SL) LAR ML21274A0022021-09-30030 September 2021 NRR E-mail Capture - Acceptance Review for TSTF-577 LAR (L-2021-LLA-0158) ML21312A0072021-09-21021 September 2021 Enclosure 1 - E-mail - Enclosure B - NAPS SER App a - Dominion Comments 9-21-2021 ML21312A0032021-09-21021 September 2021 Enclosure 1 - E-mail - Enclosure a - Dominion Table A4.4-1 Clean Version ML21312A0022021-09-21021 September 2021 Enclosure 1 - E-mail - NAPS SLR SER Appendix a for Dominion Review 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 ML21152A1722021-09-0707 September 2021 NRC to Fws, NRC Issuance of Draft Environmental Impact Statement for North Anna Subsequent License Renewal, Opportunity for Public Comment, and Endangered Species Act Determinations ML21238A0942021-08-25025 August 2021 Draft Request for Additional Information Set Z - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Email ML21225A5512021-08-13013 August 2021 Discussion Point for Public Meeting Regarding Fire Protection Piping Cyclic Loading - Transmittal E-mail 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 ML21154A0152021-06-0101 June 2021 NRR E-mail Capture - Acceptance Review for Primary Grade Water LAR (L-2021-LLA-0082) ML21140A3682021-05-20020 May 2021 Response to North Anna Hardship (Temporary Staff Guidance Additional Guidance for FOF Inspections During the PHE) 2024-04-15
[Table view] |
Text
Bettle, Jerome From: Bettle, Jerome Sent: Tuesday, September 06, 2011 1:57 PM To: Dennig, Robert
Subject:
RE: North Anna Relevant reading - still looking for the more specific requirement, Sect III of 10CFR100 App A (c) The Safe Shutdown Earthquake' is that earthquake which is based upon an evaluation of the maximum earthquake potential considering the regional and local geology and seismology and specific characteristics of local subsurface material. It is that earthquake which produces the maximum vibratory ground motion for which certain structures, systems, and components are designed to remain functional, These structures, systems, and components are those necessary to assure:
(1) The integrity of the reactor coolant pressure boundary, (2) The capability to shut down the reactor and maintain it in a safe shutdown condition, or (3) The capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to the guideline exposures of this part.
(d) The OperatingBasis Earthquake is that earthquake which, considering the regional and local geology and seismology and specific characteristics of local subsurface material, could reasonably be expected to affect the plant site during the operating life of the plant; it is that earthquake which produces the vibratory ground motion for which those features of the nuclear power plant necessary for continued operation without undue risk to the health and safety of the public are designed to remain functional.
Sect V of 10CFR100 App A (2) Determinationof OperatingBasis Earthquake. The Operating Basis Earthquake shall be specified by the applicant after considering the seismology and geology of the region surrounding the site. If vibratory ground motion exceeding that of the Operating Basis Earthquake occurs, shutdown of the nuclear power plant will be required. Prior to resuming operations, the licensee will be required to demonstrate to the Commission that no functional damage has occurred to those features necessary for continued operation without undue risk to the health and safety of the public.
The maximum vibratory ground acceleration of the Operating Basis Earthquake shall be at least one-half the maximum vibratory ground acceleration of the Safe Shutdown Earthquake.
Sect VI of 10CFR100 App A The nuclear power plant shall be designed so that, if the Safe Shutdown Earthquake occurs, certain structures, systems, and components will remain functional. These structures, systems, and components are those necessary to assure (i) the integrity of the reactor coolant pressure boundary, (ii) the capability to shut down the reactor and maintain it in a safe condition, or (iii) the capability to prevent or mitigate
the consequences of accidents which could result in potential offsite exposures comparable to the guideline exposures of this part. In addition to seismic loads, including aftershocks, applicable concurrent functional and accident-induced loads shall be taken into account in the design of these safety-related structures, systems, and components. The design of the nuclear power plant shall also take into account the possible effects of the Safe Shutdown Earthquake on the facility foundations by ground disruption, such as fissuring, differential consolidation, cratering, liquefaction, and landsliding, as required in paragraph (d) of section V.
(2) OperatingBasis Earthquake. The Operating Basis Earthquake shall be defined by response spectra.
All structures, systems, and components of the nuclear power plant necessary for continued operation without undue risk to the health and safety of the public shall be designed to remain functional and within applicable stress and deformation limits when subjected to the effects of the vibratory motion of the Operating Basis Earthquake in combination with normal operating loads. The engineering method used to insure that these structures, systems, and components are capable of withstanding the effects of the Operating Basis Earthquake shall involve the use of either a suitable dynamic analysis or a suitable qualification test to demonstrate that the structures, systems and components can withstand the seismic and other concurrent loads, except where it can be demonstrated that the use of an equivalent static load method provides adequate conservatism. The analysis or test shall take into account soil-structure interaction effects and the expected duration of vibratory motion.
From: Dennig, Robert Sent: Tuesday, September 06, 2011 9:11 AM To: Bettle, Jerome; Lee, Brian
Subject:
North Anna Should we require any Appendix J testing to demonstrate containment integrity prior to restart?
2