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Category:E-Mail
MONTHYEARML23320A1122024-01-18018 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 ML21312A0112021-11-0404 November 2021 Enclosure 3 - NAPS Draft SER Section 3 Comments ML21312A0012021-11-0404 November 2021 Comments on North Anna Draft SER 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) ML21312A0022021-09-21021 September 2021 Enclosure 1 - E-mail - NAPS SLR SER Appendix a for Dominion Review 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 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) ML21140A3712021-05-19019 May 2021 FOF Discussion 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 ML21091A0022021-04-0101 April 2021 Final Request for Additional Information Set 2 - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Email 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 ML21069A3522021-03-10010 March 2021 NRR E-mail Capture - Acceptance Review for Topical Report DOM-NAF-2 VIPRE-D 2024-01-18
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Kulesa, Gloria From: Martin, Robert , ( .
Sent: Tuesday, September 13, 2011 3:27 PM To: McCoy, Gerald Cc: Hiland, Patrick; Khanna, Meena; Glitter, Joseph; Howe, Allen; Kulesa, Gloria; Boyle, Patrick; Jones, William; Franke, Mark; Kolcum, Gregory
Subject:
RE: Reactor Systems North Anna Questions I agree with your perspective. I think it represents an NRR-Region I coordinated approach that recognizes that both organizations are interested in many of the same-titled issues, but from somewhat different perspectives. And I think we will do our best to handle the coordination issue with constant continued C_
communication.
From: McCoy, Gerald %
Sent: Tuesday, September 6l, 2011 3:11 PM To: Martin, Robert; Kulesa, Gloria; ]ones, William Cc: Franke, Mark; Kolcum, Gregory
Subject:
RE: Reactor Systems North Anna Questions From my perspective, Dominion, NRR and Region 2 have different functions in this process. Dominion has the responsibility to provide sufficient information to provide adequate the plant is safe to operate. NRR. has the engineering expertise to determine if the plan is acceptable. Region 2's responsibility is to provide information on the adequacy of the licensee's inspections by inspecting a sample of the inspections, either through witnessing the inspection or reviewing completion data. If NRR has an issue with Dominion's proposed evaluation of a system, I think that they should address it directly to Dominion.
For the issues raised here:
- 1. How has the licensee evaluated, inspected, or analyzed the steam generators to ensure SG tube integrity?
What further work is planned in this area?
The licensee should describe the process they used to ensure the SG tube integrity. Region 2 has plans to witness some of the SG ISI inspections that the licensee has planned.
- 2. What assurances does the licensee have that system pressure relief capabilities are maintained?
Again, the licensee should describe the process. Once we hear about how they intend to test the reliefs, we will see if there is anything that can be inspected.
- 3. How will licensee ensure overall RCS pressure boundary integrity? What have the licensee's observations been so far?
Licensee should describe what testing (if any) they have planned. NRR decides if that Is acceptable, Region 2 will see what is available for review.
- 4. How has the licensee inspected, examined, and evaluated the ECCS? How does the licensee know it will still perform as intended? Can it continue to perform its ECCS functions under simultaneous design basis earthquake loading per the ECCS design basis seismic requirements?
Again, the process should be described in the licensee's submittal. NRR needs to judge whether the plan is acceptable. Region 2 currently plans to observe selected surveillance tests when we know about them,
- 5. Were there any complications in residual heat removal following the earthquake? Did all RHR equipment perform as intended?
Iniormatior in this record wns deel'ed in accordance with he Freedom of Information Act, exemptions 1,...
FOIA-
There have been no issues reported with the RHR system. The RHR system was not put into service until several days after the earthquake.
- 6. How has the licensee assessed the reactor trip system, including its actuation circuitry and its mechanical components? How will the licensee ensure the RCCAs and the guide tubes retain their required functionality?
The licensee needs to describe how they will assess the RPS (reactor protective system). NRR needs to determine whether the proposed plan is acceptable. Region 2 plans on observing selected tests.
We are planning to observe tests that we know about as they occur. Once we see Dominion's submittal, we will see what else we need to inspect.
Do you agree with my perspective on this process?
Gerald J. McCoy Chief, Reactor Projects Branch 5 Division of Reactor Projects, Region 2 United States Nuclear Regulatory Commission Offic- 404-97-4551 Cell :*()6) ) ~
From: Martin, Robert \\ "-
Sent: Tuesday, September 13, 2011 7:59 AM To: McCoy, Gerald; Kolcum, Gregory; Franke, Mark Cc: Kulesa, Gloria; Boyle, Patrick; Ulses, Anthony; Parks, Benjamin; Khanna, Meena
Subject:
Reactor Systems North Anna Questions We are preparing questions to send to Dominion. Which of the following Reactor Systems branch questions do you regard as being within Region Il"s scope - either as covered by the AIT or other Regional actions?
Even if within the Region's scope and NRR/Reactor Systems has the Q, how should we proceed with getting.
the answer? Region II to provide the answer or should we ask it of Dominion anyway?
From: Mendiola, Anthony Sent: Monday, September 12, 2011 3:18 PM To: Martin, Robert
Subject:
FW: North Anna Questions Fyi...
From: Parks, Benjamin X .
Sent: Monday, September 12, 2011 12:56 PM To: Mendiola, Anthony; Miranda, Samuel
Subject:
FW: North Anna Questions These were sent for Tony's-consideration. --bp
- 7. How has the licensee evaluated, inspected, or analyzed the steam generators to ensure SG tube integrity?
What further work is planned in this area?
- 8. What assurances does the licensee have that system pressure relief capabilities are maintained?
2
11.
- 9. How will licensee ensure overall RCS pressure boundary integrity? What have the licensee's observations been so far?
- 10. How has the licensee inspected, examined, and evaluated the ECCS? How does the licensee know it will still perform as intended? Can it continue to perform its ECCS functions under simultaneous design basis earthquake loading per the ECCS design basis seismic requirements?
- 11. Were there any complications in residual heat removal following the earthquake? Did all RHR equipment perform as intended?
- 12. How has the licensee assessed the reactor trip system, including its actuation circuitry and its mechanical components? How will the licensee ensure the RCCAs and the guide tubes retain their required functionality?
Benjamin T. Parks Reactor Systems Branch, NRR 01 O-D2 415-6472 3