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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance
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MONTHYEARLR-N20-0010, License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology2020-04-24024 April 2020 License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology Project stage: Request ML20296A6232020-10-22022 October 2020 Request for NRC Approval to Apply Leak-Before-Break Methodology to Reactor Coolant System Branch Piping Project stage: Request ML20302A2012020-10-22022 October 2020 NRR E-mail Capture - Surry Power Station, Units 1 and 2 - Acceptance Review (L-2020-LLA-0219) Project stage: Acceptance Review ML20338A5422020-12-0303 December 2020 Proposed License Amendment Request, Update of the Loss of Coolant Accident Alternate Source Term Dose Analysis Project stage: Request ML20346A1032020-12-11011 December 2020 NRR E-mail Capture - Surry Power Station, Units 1 and 2 LBB LAR - Acceptance Review (L-2020-LLA-0255) Project stage: Acceptance Review ML20364A0172020-12-28028 December 2020 NRR E-mail Capture - Surry Power Station, Units 1 and 2 AST LAR - Acceptance Review (L-2020-LLA-0258) Project stage: Acceptance Review ML21084A2732021-03-24024 March 2021 License Amendment Request - Application of Leak-Before-Break Methodology to Reactor Coolant System Branch Piping - Response to Request for Additional Information and Clarification Project stage: Response to RAI ML21127A1362021-05-13013 May 2021 May 13, 2021 NRC Pre-Submittal Meeting - Surry Power Station New Fuel Storage and Spent Fuel Pool Criticality Analysis Proposed License Amendment Request Project stage: Meeting ML21133A4212021-05-13013 May 2021 Response to NRC Request for Additional Information Regarding Proposed License Amendment Request Update of LOCA Alternative Source Term Dose Analysis Project stage: Response to RAI ML21270A0232021-07-0707 July 2021 State of Virginia Notification of Pending Amendment Issuance Ref: Surry Power Station, Units 1 and 2 - Request to Revise Technical Specifications 2.1.A.1.b Project stage: Other ML21175A1852021-08-20020 August 2021 Issuance of Amendment Nos. 304 and 304 Leak-Before-Break for Pressurizer Surge, Residual Heat Removal, Safety Injection Accumulator, Reactor Coolant System Bypass and Safety Injection Lines Project stage: Approval ML21272A0622021-09-28028 September 2021 NRR E-mail Capture - (External_Sender) Surry Fuel Melt Safety Limit (SL) LAR Question Project stage: Other ML21277A0652021-09-30030 September 2021 Proposed License Amendment Request Removal of Refueling Water Chemical Addition Tank and Replacement of Containment Sump Buffer Project stage: Request ML21286A7372021-10-13013 October 2021 Additional Element Included in the Implementation Plan for the Surry Fuel Melt Safety Limit (SL) LAR Project stage: Request ML21292A3022021-10-19019 October 2021 Response to Question on License Amendment Request to Revise Reactor Core Safety Limit Project stage: Request ML21294A3382021-10-21021 October 2021 Proposed Amendment to Relocate Unit Staff Qualification Requirements from Technical Specifications to Nuclear Facility Quality . Project stage: Request ML21188A1742021-10-26026 October 2021 Issuance of Amendment Nos. 305 and 305 Revised Reactor Core Safety Limit to Reflect Topical Report WCAP-177642-P-A, Revision 1 Project stage: Approval ML21307A4302021-11-0909 November 2021 Supplemental Information Needed for Acceptance of Requested Licensing Action Surry Post LOCA Buffer Change Project stage: Acceptance Review ML21253A0632021-11-19019 November 2021 Issuance of Amendment Nos. 306 and 306 to Update of the Loss of Coolant Accident Alternate Source Term Dose Analysis Project stage: Approval 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) Project stage: Acceptance Review ML21334A1692021-11-29029 November 2021 Proposed License Amendment Request Removal of Refueling Water Chemical Additional Tank and Replacement of Containment Buffer Supplemental Information Project stage: Supplement ML21340A1642021-12-0606 December 2021 Acceptance of Requested Licensing Action Amendment Project stage: Acceptance Review ML22004A2872022-01-14014 January 2022 Technical Specification Section 3.4.A.4 Change of Post Loss-of-Coolant Accident Chemical Buffer Audit Plan Project stage: Other ML22077A0542022-03-18018 March 2022 Change in Engineering Hours Estimate Surry Ph Buffer LAR Acceptance Project stage: Approval ML22089A0092022-04-13013 April 2022 Regulatory Audit Summary Related to the License Amendment Request to Change Loss-Of-Coolant Accident Chemical Buffer Project stage: Other ML22153A1352022-06-0202 June 2022 Proposed License Amendment Request (LAR) - Removal of Refueling Water Chemical Addition Tank and Replacement of Containment Sump Buffer - Response to Request for Additional Information Project stage: Response to RAI ML22164A9252022-06-13013 June 2022 Page Substitutions to ADAMS Accession Number ML21294A338 Project stage: Request ML22164A8532022-06-13013 June 2022 Proposed License Amendment Request Removal of Refueling Water Chemical Addition Tank and Replacement of Containment Sump Buffer - Response to Request for Confirmation Project stage: Request ML22095A1072022-07-11011 July 2022 Issuance of Amendment Nos. 120, 344, & 284, 293 & 276, & 307 & 307 to Relocate Requirements to the QAPD Project stage: Approval ML22193A2952022-08-26026 August 2022 Issuance of Amendment Nos. 308 and 308 License Amendment Request for Removal of the Refueling Water Chemical Addition Tank and Containment Sump, Ph Buffer Change and Safety Evaluation Project stage: Approval ML22250A6672022-10-12012 October 2022 Correction to Issuance of Amendment Nos. 304 (EPID L-2020-LLA-0255), 305 (EPID L-2020-LLA-0219) 306 (EPID L-2020-LLA-0258), 307 (EPID L-2021-LLA-0195) and 308 Project stage: Approval 2021-12-06
[Table View] |
Similar Documents at Surry |
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Category:Audit Plan
MONTHYEARML23152A0432023-06-22022 June 2023 Audit Plan License Amendment Requests to Change Emergency Plan Staff Augmentation Times ML23117A0952023-05-10010 May 2023 Audit Plan License Amendment Request to Support Relocation of the Technical Support Center ML22255A1862022-10-0303 October 2022 Tornado Classification of the Fuel Handling Trolley Support Structure License Amendment Request Audit Plan ML22250A4672022-09-15015 September 2022 Turbine Building Wind Loading Basis Change Audit Plan ML22004A2872022-01-14014 January 2022 Technical Specification Section 3.4.A.4 Change of Post Loss-of-Coolant Accident Chemical Buffer Audit Plan ML20099F8732020-04-17017 April 2020 Audit Proposed License Amendment Request for the Addition of Westinghouse Topical Report WCAP-16996-P-A, Revision 1 (EPID L-2019-LLA-0243 and EPID L-2019-LLA-0236 ML19338C6902019-12-10010 December 2019 Audit Plan License Amendment Request for Small Break Loss of Coolant Accident Methodology (Epids L-2018-LLA-0195 and L-2018-LLA-0215) ML19220A5552019-08-13013 August 2019 Audit Proposed License Amendment Request for the Addition of 24-Hour Associated with the Technical Specification Completion Time for an Inoperable Reactor Trip (EPID-L-2019-LLA-0110) ML19098A8102019-04-17017 April 2019 On-Site Regulatory Audit Regarding the Subsequent License Renewal Application Review (EPID Nos. L-2018-RNW-0023 and L-2018-RNW-0024) ML19044A5562019-03-0404 March 2019 License Renewal Environmental Site Audit Plan Regarding the Surry Power Station, Units 1 and 2, Subsequent License Renewal Application ML19044A6592019-03-0404 March 2019 License Renewal Severe Accident Mitigation Alternatives Audit Plan Regarding the Surry Power Station, Unit Nos. 1 and 2, Subsequent License Renewal Application ML19015A2432019-01-22022 January 2019 Plan for the In-Office Regulatory Audit Regarding the Subsequent License Renewal Application Review (EPID Nos. L-2018-RNW-0023 and L-2018-RNW-0024) ML18319A1842018-11-26026 November 2018 Plan for the Operating Experience Audit Regarding the Subsequent License Renewal Application Review (EPID Nos. L-2018-RWN-0023 and L-2018-RNW-0024 ML16259A1892016-12-0505 December 2016 Nuclear Regulatory Commission Plan for the Audit of Mitigation Strategies Assessment Submittals Related to Order EA-12-049, Order to Modify Licenses With Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events ML15153A1602015-06-15015 June 2015 Nuclear Regulatory Commission Plan for the Audit of Virginia Electric and Power Company'S Flood Hazard Reevaluation Report Submittal Relating to the Near-Term Task Force Recommendation 2.1 - Flooding for Surry Power Station, Units 1 and 2 ML14343A1412014-12-11011 December 2014 Plan for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Instrumentation Related to Orders EA-12-049 and EA-12-051 ML14189A3202014-07-0808 July 2014 Plan to Audit the Regional Response Center Proof of Concept Demonstration with Surry Power Station Regarding Implementation of Phase 3 Related to Order EA-12-049 (Mitigating Strategies) 2023-06-22
[Table view] Category:Letter
MONTHYEARIR 05000280/20244012024-02-0606 February 2024 Security Baseline Inspection Report 05000280/2024401, 05000281/2024401 and 07200002/2024401 IR 05000280/20230102024-01-18018 January 2024 Age Related Degradation Inspection Report 05000280-2023010 and 05000281-2023010 ML23312A1922024-01-18018 January 2024 Issuance of Amendment Nos. 316 & 316 Regarding a Risk Informed Approach for Tornado Classification of the Fuel Handling Trolley Support Structure ML24003A9022024-01-0303 January 2024 Stations, Units 1 and 2, Emergency Plan Revision - Relocation of the Technical Support Center (TSC) - Editorial Correction IR 05000280/20233012023-12-28028 December 2023 NRC Operator License Examination Report 05000280/2023301 and 05000281/2023301 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) ML23352A3692023-12-18018 December 2023 Associated Independent Spent Fuel Storage Installation, Revision to Emergency Plan Report of Change ML23334A2342023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23242A2292023-11-0707 November 2023 Issuance of Amendment Nos. 315 and 315, Regarding Emergency Procedure Relocation of the Technical Support Center ML23200A2622023-11-0202 November 2023 Issuance of Amendment Nos. 314 and 314, Regarding Technical Specification and Spent Fuel Pool Criticality Change IR 05000280/20230032023-10-25025 October 2023 Integrated Inspection Report 05000280/2023003 and 05000281/2023003 ML23286A0372023-10-13013 October 2023 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J ML23285A0922023-10-12012 October 2023 Inservice Testing Program for Pumps and Valves Sixth Interval Update and Associated Relief and Alternative Requests ML23277A1172023-10-0303 October 2023 Operator Licensing Examination Approval 05000280/2023301 and 05000281/2023301 ML23230A0502023-10-0202 October 2023 5 of the Quality Assurance Topical Report - Review of Program Changes ML23256A2672023-09-21021 September 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report ML23244A2352023-09-18018 September 2023 Request to Use a Subsequent Edition of the ASME Code, Section XI ML23230A0012023-09-15015 September 2023 Request to Use a Provision of a Previous Edition of the ASME Boiler and Pressure Vessel Code, Section XI, for Non-Destructive Examinations IR 05000280/20220042023-09-0101 September 2023 Reissue - Surry Power Station - Integrated Inspection Report 05000280/2022004 and 05000281/2022004 ML23244A0142023-08-30030 August 2023 Inservice Inspection Owner'S Activity Report IR 05000280/20230052023-08-23023 August 2023 Updated Inspection Plan for Surry Power Station, Units 1 and 2 (Report 05000280/2023005 and 05000281/2023005) ML23226A1862023-08-10010 August 2023 Proposed License Amendment Request - Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection Flow Instrumentation ML23220A1492023-08-0707 August 2023 Independent Spent Fuel Storage Installation - 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Relocation of the Technical Support Center (TSC) Supplemental Information - LOCA Dose Calculation Summary ML23117A0952023-05-10010 May 2023 Audit Plan License Amendment Request to Support Relocation of the Technical Support Center ML23130A3742023-05-10010 May 2023 Request to Delay NRC Intial Licensing Examination 2024-02-06
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Text
January 14, 2022 Mr. Daniel G. Stoddard Senior Vice President and Chief Nuclear Officer Dominion Nuclear Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
SURRY POWER STATION, UNITS 1 AND 2 - SURRY TECHNICAL SPECIFICATION SECTION 3.4.A.4 CHANGE OF POST LOSS-OF-COOLANT ACCIDENT CHEMICAL BUFFER AUDIT PLAN (EPID L-2021-LLA-0179)
Dear Mr. Stoddard:
By letters dated September 30, 2021, and November 29, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML21277A065 and ML21334A169, respectively), Virginia Electric and Power Company, the licensee (Dominion Energy Virginia) submitted a license amendment request (LAR) for the Surry Power Station, Units 1 and 2 (Surry). In its LAR, Dominion Energy Virginia proposed to revise the Surry technical specification to eliminate the Refueling Water Chemical Addition Tank and allow the use of sodium tetraborate decahydrate to replace sodium hydroxide as a chemical additive for containment sump pH control following a loss-of-coolant accident at Surry.
Subsequent to the LARs acceptance, the U.S. Nuclear Regulatory Commission (NRC) staff identified several items that require further clarification and detailed explanations. Therefore, the NRC staff will conduct a regulatory audit to support the LARs review in accordance with the enclosed audit plan. A regulatory audit is a planned activity that includes the examination and evaluation of primarily non-docketed information. The audit will be conducted to increase the NRC staffs understanding of the LAR and identify any information that may require docketing to support the NRC staffs regulatory finding.
The audit will be conducted using video conferencing on February 24, 2022 and an eDocs web portal (also known as an online portal, electronic portal, ePortal, electronic reading room) from February 1 to March 15, 2022. The outline for the logistics, schedule, and scope of this audit were initially discussed with your staff in December 2021. The audit plan is enclosed.
D. Stoddard If you have any questions, please contact me at (301) 415-5136, or via email at John.Klos@nrc.gov.
Sincerely,
/RA/
John Klos, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-280 and 50-281
Enclosure:
Audit Plan cc: Listserv
AUDIT PLAN FOR SURRY TECHNICAL SPECIFICATION SECTION 3.4.A.4 CHANGE OF POST LOSS-OF-COOLANT ACCIDENT CHEMICAL BUFFER VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-280 AND 50-281
1.0 BACKGROUND
By letters dated September 30, 2021, and November 29, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML21277A065, and ML21334A169, respectively), Virginia Electric and Power Company, the licensee (Dominion Energy Virginia) submitted a license amendment request (LAR) for the Surry Power Station, Units 1 and 2 (Surry). In its LAR, Dominion Energy Virginia proposed to revise the Surry Technical Specification to eliminate the Refueling Water Chemical Addition Tank and allow the use of sodium tetraborate decahydrate to replace sodium hydroxide as a chemical additive (buffer) for containment sump pH control following a loss-of-coolant accident at Surry.
2.0 REGULATORY AUDIT BASES A regulatory audit is a planned license or regulation-related activity that includes the examination and evaluation of primarily non-docketed information. The audit is conducted with the intent to gain understanding, to verify information, and to identify information that may require docketing to support the basis of a licensing or regulatory decision. Performing a regulatory audit is expected to assist the U.S. Nuclear Regulatory Commission (NRC) staff in efficiently conducting its review and gaining insights to the licensees processes, procedures, engineering documentation and calculations related to the LAR. Information that the NRC staff relies upon to make the safety determination must be submitted on the docket.
During the initial plant licensing of Surry, it was demonstrated that the Safety Injection, Containment Spray, and Recirculation Spray systems met the regulatory requirements in place at that time. The General Design Criteria (GDC) included in Appendix A to Title 10 of the Code of Federal Regulations (10 CFR) 50 did not become effective until May 21, 1971. The Construction Permits for Surry were issued prior to May 21, 1971; consequently, Surry was not subject to current GDC requirements (SECY-92-223, dated September 18, 1992). Section 1.4 of the Surry Updated Final Safety Analysis Report (UFSAR) discusses compliance with the GDC published in 1967 (Draft GDC), and the UFSAR discussion demonstrates that Surry meets the intent of these criteria.
This regulatory audit is based on the following regulatory requirements and guidance:
The regulations in 10 CFR 50.67, Accident Source Term and Regulatory Guide (RG) 1.183, Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Enclosure
Reactors, ADAMS Accession no. ML003716792, provides criteria for evaluating the consequences of applicable design basis accidents. RG 1.183 indicates that analyses should consider iodine re-evolution if the sump liquid pH is not maintained at 7 or greater.
Appendix A to Part 50, General Design Criterion (GDC) 2Design bases for protection against natural phenomena states that Structures, systems, and components important to safety shall be designed to withstand the effects of natural phenomena such as earthquakes, tornadoes, hurricanes, floods, tsunami, and seiches without loss of capability to perform their safety functions. The design bases for these structures, systems, and components shall reflect appropriate combinations of the effects of normal and accident conditions with the effects of the natural phenomena.
3.0 SCOPE The audit team will view the documentation and calculations that provide the technical support for the LAR. The scope of the NRC staffs audit will focus on the following subjects:
- 1. Alternate buffer pH calculations, including description of the key assumptions, methodology, and inputs.
- 2. The calculations that document and support the licensees statement in its November 29, 2021 letter which, in response to NRC request no. 11, stated that the basket members and connections are analyzed to meet Dominion Energy Nuclear Engineering Standard (DNES) DNES-STD-CE-0046, American Institute of Steel Construction 9th Edition, "Manual of Steel Construction." The documents and calculations provided by the licensee to support this audit item should fully describe, justify and document the licensees statement in response to NRC request above that also stated When considering the 1/3 increase for earthquake loading, the maximum member interaction for members, connections, welds, wheels, bolts, and anchor bolts is less than the required 1.0.
In addition, the audit team may request to discuss these topics with the licensees subject matter experts. The NRC staff will conduct this audit under the guidance provided in Office of Nuclear Reactor Regulation Office Instruction LIC-111, Regulatory Audits, Revision 1 (ADAMS Accession No. ML19226A274).
4.0 INFORMATION AND OTHER MATERIAL NECESSARY FOR THE REGULATORY AUDIT The NRC staff requests that the documents, data, and calculations regarding the scope above be made available to the NRC staff via the licensees electronic reading room.
The NRC staff acknowledges and will observe appropriate handling and protection of proprietary information made available for the audit. The NRC staff will not remove non-docketed information from the audit site or eDocs web portal.
5.0 AUDIT TEAM The following are the NRC audit team members:
Greg Makar, Materials Engineer, Team Leader, Gregory.Makar@nrc.gov
John Ma, Senior Civil Engineer (Structural), John.Ma@nrc.gov John Klos, Surry Licensing Project Manager, John.Klos@nrc.gov 6.0 LOGISTICS The audit will be conducted using video conferencing and an eDocs web portal (also known as an online portal, electronic portal, ePortal, or electronic reading room) from February 1 to March 15, 2022. During the audit, information may be shared using video conference and telephone conference. The licensees representatives are requested to be available for video or audio conferences on the audits scheduled discussion days as they are determined by the NRC licensing project manager and the Surry licensing team. The NRC project manager will coordinate any changes to the audit schedule and locations with the licensee and the NRC staff.
The NRC staff would like remote access to the available and related documents listed in Sections 3.0 and 4.0 by February 1, 2022. If this schedule needs to be adjusted please contact John Klos of the NRC at (301) 415-5136, or via email at John.Klos@nrc.gov.
Audit Schedule Date Time Subject February 1, 2022 12:00 pm Audit start date February 24, 2022 TBD Scheduled discussion of portal items, and any review items of concern March 15, 2022 12:00 pm Audit completion date 7.0 SPECIAL REQUESTS The following conditions associated with the eDocs web portal must be maintained throughout the duration that the NRC staff have access to the eDocs web portal:
The eDocs web will be password-protected, and separate passwords will be assigned to the NRC staff who are participating in the audit.
The eDocs web will be sufficiently secure to prevent the NRC staff from printing, saving, downloading, or collecting any information on the online portal.
Conditions of use of the eDocs web will be displayed on the login screen and will require acknowledgment by each user.
Username and password information should be provided directly to the NRC staff. The NRC project manager will provide Exelon the names and contact information of the NRC staff who will be participating in the audit. All other communications should be coordinated with the NRC project manager. NRC staff access to the eDocs web portal needs to be terminated 30 days after the end of the regulatory audit.
8.0 DELIVERABLES Upon completion of the audit, the regulatory audit summary report will be placed into ADAMS within 90 days of the completion of the audit or before the regulatory action that the audit supports is completed, whichever is shorter. If the NRC staff identifies information during the audit that is needed to support its regulatory decision, the NRC staff will issue requests for additional information to the licensee as soon as possible after the end date of the audit.
ML22004A287
- by email OFFICE DORL/LPL2-1/PM DORL/LPL2-1/LA* NRR/DNRL/NCSG/BC*
NAME JKlos KEntz SBloom DATE 01/03/2022 1/7/2022 1/12/2022 OFFICE NRR/DEX/ESEB/BC* DORL/LPL2-1/A(BC)* DORL/LPL2-1/PM NAME JColaccino MMarkley (SWilliams for) JKlos DATE 1/13/2022 1/14/2022 1/14/2022