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Category:E-Mail
MONTHYEARML24213A2602024-07-31031 July 2024 Request for Additional Information LAR to Support Implementation of Framatome Gaia Fuel ML24116A0112024-04-25025 April 2024 Acceptance Review Determination for Proposed Alternative Request IR-4-13 Regarding Steam Generator Channel Head Drain Modification ML24115A2622024-04-24024 April 2024 Acceptance Review Determination for Proposed Alternative Request IR-4-14 Regarding Pressurizer and Steam Generator Pressure-Retaining Welds and Full-Penetration Welded Nozzles ML24114A3192024-04-23023 April 2024 Acceptance Review Determination LAR to Extend Inspection Interval for Reactor Coolant Pump Flywheels (TSTF-421) Using the CLIIP ML24113A2502024-04-22022 April 2024 Request for Additional Information (e-mail 4/22/2024) License Renewal Commitment for Aging Management Program of Alloy 600 Components ML24096B7762024-04-0505 April 2024 Email - Fyi/Review: Draft Environmental Assessment for Haddam ML24092A1082024-04-0101 April 2024 3R22 RFO ISI Owners Activity Report Extension - NRC Staff Acknowledgement Email (4/1/2024) ML24065A3112024-03-0505 March 2024 Request for Additional Information (Redacted) (03/05/2025 E-mail from R. Guzman to S. Sinha) Framatome Gaia Fuel LOCA LAR ML24058A2322024-02-27027 February 2024 2/27/2024 E-mail from S. Sinha to R. Guzman P-8 Instrument Uncertainty in Support of LAR Framatome Gaia Fuel ML24032A4702024-02-0101 February 2024 Change in Estimated Review Schedule Revision to TS Design Features Section to Remove the Nine Mile Point Unit 3 Nuclear Project, LLC ML24024A0202024-01-24024 January 2024 Correction to Safety Evaluation Associated Wit Amendment No. 288 - Revision to Applicability Term for RCS Heat-Up and Cooldown Pressure-Temperature Limitations Figures ML24024A2452024-01-24024 January 2024 1/24/2024 E-mail from R.Guzman to S.Sinha - Acknowledgement of Error in SE for Amendment No. 288 - Revision to Applicability Term for RCS Heatup and Cooldown Pressure-Temperature Limitations Figures ML23326A0132023-11-22022 November 2023 Acceptance Review Determination LAR to Support Implementation of Framatome Gaia Fuel ML23318A0952023-11-14014 November 2023 Request for Additional Information (E-mail Dated 11/14/2023) LAR to Revise TSs Related to Framatome Gaia Fuel ML23317A0732023-11-13013 November 2023 Acceptance Review Determination - License Amendment Request Modification of TS SR 4.3.6.a ML23297A2312023-10-24024 October 2023 E-mail to File - Summary of September 13, 2023, Meeting with Dominion to Discuss Proposed LAR to Support Cycle Reloads Using Framatome Gaia Fuel ML23265A2302023-09-22022 September 2023 Acceptance Review Determination - License Amendment Request Revision to TS Design Features Section to Remove the Nine Mile Point Unit 3 Nuclear Project, LLC ML23258A0552023-08-31031 August 2023 Setup of Online Reference Portal and Audit Plan for the NRC Staff'S Review of LAR to Use Framatome Small Break and Realistic Large Break LOCA Methodologies (08/31/2023 e-mail) ML23199A2832023-07-18018 July 2023 Request for Additional Information (E-mail Dated 7/18/2023) LAR to Revise the Pressure-Temperature Limits ML23172A0752023-06-21021 June 2023 Acceptance Review Determination LAR to Revise TSs for Reactor Core Safety Limits, Fuel Assemblies, and COLR Related to Framatome Gaia Fuel ML23171B0522023-06-20020 June 2023 NRR E-mail Capture - RAI for Review of Appendix F to DOM-NAF-2-P (Redacted) ML23145A0052023-05-25025 May 2023 Acceptance Review Determination Exemption to Use Framatome Gaia Fuel Assemblies Containing Fuel Rods Fabricated with M5 Fuel Rod Cladding ML23145A0042023-05-25025 May 2023 Acceptance Review Determination LAR to Use Framatome Small Break and Realistic Large Break LOCA Methodologies ML23115A3022023-04-24024 April 2023 4/24/2023 E-mail from R.Guzman to S.Sinha - Acknowledgement of Error in Issuance of Amendments Adoption of TSTF-359, Increase Flexibility in Mode Restraints ML23089A1882023-03-29029 March 2023 Request for Additional Information (E-mail Dated 3/29/2023) Spring 2022 Steam Generator Tube Inspection Report 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 ML23038A0152023-02-0707 February 2023 Acceptance Review Determination LAR to Revise the Applicability Term for RCS Heatup and Cooldown Pressure-Temperature Limitations Figures ML23024A1522023-01-24024 January 2023 Acceptance Review Determination LAR to Supplement Burnup Credit of Criticality Safety Analysis 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) ML22320A5752022-11-16016 November 2022 E-mail to File - Summary of October 18, 2022, Meeting with Dominion to Discuss Requested Actions for Implementing Framatome Gaia Fuel ML22298A2052022-10-25025 October 2022 Acceptance Review Determination for Alternative Request for Extension of Examination Interval for Reactor Pressure Vessel Head Penetration Nozzles ML22292A3212022-10-19019 October 2022 Acceptance Review Determination for Alternative Request for Containment RSS Pump Periodic Verification Testing Program ML22297A1802022-10-0707 October 2022 Email Acknowledgement to Dominion Energy Nuclear Decommissioning Trust Fund Disbursement 30 Day Notification for Millstone Power Station Unit 1: Docket No 50-245 ML22278A0932022-10-0505 October 2022 E-mail to File - Summary of September 7, 2022, Meeting with Dominion to Discuss Proposed Supplement to the Spent Fuel Pool Criticality Safety Analysis (EPID L-2022-LRM-0059 ML22272A0332022-09-29029 September 2022 Memo E-mail to File - Summary of August 29, 2022, Meeting with Dominion to Discuss Proposed Alternative Request Post-peening follow-up Volumetric Exam of RPV Head Penetration Nozzle ML22252A1772022-09-0909 September 2022 Memo E-mail to File - Summary of August 9, 2022, Meeting with Dominion to Discuss Proposed Alternative Reqeust Recirculation Spray Pump Flow Testing (EPID L:2022-LRM-0057) 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) ML22123A0812022-05-0303 May 2022 Acceptance Review Determination for Proposed LAR for TS Change Applicable to TSTF-359, Increase Flexibility in Mode Restraints ML22069A7192022-03-10010 March 2022 E-mail from R. Guzman to S. Sinha - Millstone Unit 3 Steam Generator Outage Conference Call ML22020A4122022-01-11011 January 2022 1/11/2022 State Consultation E-mail, R. Guzman to J. Semancik Millstone Power Station, Unit 3 Planned Issuance of Amendment to Clarify Shutdown Bank TS and Add Alternate Control Rod Position Monitoring Requirements ML21348A7392021-12-14014 December 2021 E-mail - Acceptance Review Determination Alternative Request IR-4-09 for Use Alternative Brazed Joint Assessment Methodology for Class 3 Moderate Energy Piping ML21347A9412021-12-13013 December 2021 E-mail from R.Guzman to S.Sinha - Acknowledgement of Error in Safety Evaluation for Amendment No. 280 Measurement Uncertainy Recapture Power Uprate ML21334A1922021-11-30030 November 2021 NRR E-mail Capture - Audit Plan for Reactor Core Thermal-Hydraulics Using the VIPRE-D Appendix E Review 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) ML21306A3302021-11-0202 November 2021 NRR E-mail Capture - Acceptance Review for TSTF-569 LAR ML21297A0072021-10-19019 October 2021 E-mail from R. Guzman to S. Sinha - Acknowledgemnt of Error in SE for Millstone Power Station, Unit 3, Amendment No. 279 Addition of Analytical Methodology to the COLR for LBLOCA ML21286A7372021-10-13013 October 2021 Additional Element Included in the Implementation Plan for the Surry Fuel Melt Safety Limit (SL) LAR ML21223A3042021-08-11011 August 2021 Request for Withholding Information from Public Disclosure Proposed LAR to Add an Analytical Methodology to the COLR for a Large Break LOCA ML21200A2562021-07-19019 July 2021 7/19/2021 E-mail Pressurizer Steam Space Line Classification 2024-07-31
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From: Jeff Semancik, CT Nuclear Energy Advisory Council To: NEIMA108 Resource
Subject:
Response from "NEIMA Local Community Advisory Board Questionnaire" Date: Tuesday, October 29, 2019 1:25:23 PM Below is the result of your feedback form. It was submitted by Jeff Semancik, CT Nuclear Energy Advisory Council (jeffrey.semancik@ct.gov) on Tuesday, October 29, 2019 at 13:33:09 through the IP 148.184.182.44 using the form at https://www.nrc.gov/waste/decommissioning/neima-local-comm-advisory-board-questionnaire.html and resulted in this email to neima108.resource@nrc.gov
related-site: Millstone and Haddam Neck (CT) cab-question1: The Nuclear Energy Council (NEAC) was established in 1996 to provide the public with a forum to comment on the recovery efforts of the Millstone Nuclear Power Plants, then operated by Northeast Utilities. The legislation provided NEAC with the authority to liaison with the NRC and the Utility Management as well as hear from citizens regarding their concerns about Nuclear Power and plant operations.
Initially NEAC had a member that had unfettered access to the site and monitored the two plants, reporting to NEAC with a copy to Plant Management. This monitoring ceased after Dominion managers showed that they were able to provide safe operation of the plants.
A subcommittee of NEAC was formed to monitor the shutdown and SAFSTORE of Millstone One. This committee was disbanded when those operations were complete.
cab-question2: NEAC was established by an Act of the State Legislature, signed by the Governor in June 1996. The "charter for NEAC" is Connecticut General Statutes CGS 16a-11a.
cab-question3: Initially NEAC met monthly to cover the recovery efforts of Millstone One and Two by Northeast Utilities. After the recovery was completed and the facility sold to Dominion, NEAC settled on meeting quarterly. It continues to meet quarterly and provides an annual report to the Governor and the Legislature. All meetings are open to the public and subject to the State Freedom of Information Act.
cab-question4: Historically, NEAC was composed of cross section of professional experience. Generally two to three members are retired Submarine Officers with experience operating and supervising a nuclear power plant. At least one member was an elected State Legislator. One member represented the Licensee. Initially this was a Plant Vice President but now it is someone who is a former high level Plant Manager. Other members were from Academia and interested citizens.
The Committee tries to maintain this level of experience today.
cab-question5: Members are appointed by the Governor and leaders of the State House and Senate and CEOs of municipalities hosting the power plants according to the State Statue.
This has not changed.
cab-question6: There are no specific terms for members. One member has been on NEAC since it was established.
cab-question7: NEAC follows Robert's Rules of Order and the State Freedom of Information Act.
cab-question8: There are no specific logistics supporting NEAC meetings. One of the members takes minutes that are then posted on the DEEP web site and included in the annual report to the Governor and the Legislature.
cab-question9: Initially, NEAC received a small dollar amount from the State budget that were used for travel by some members to Washington or other locations for conferences. Today, NEAC gets no funds from the State and any expenditures are borne by the individual members.
cab-question10: NEAC holds an annual joint meeting with the NRC, has a brief by the Licensee and additional meetings with subject matter experts on storage and transporting of high and low level radioactive material.
Annual reports accessible from https://www.ct.gov/deep/cwp/view.asp?a=2713&q=457004&deepNav_GID=1639 provide topics covered by NEAC.
cab-question11: NEAC is unique in that it monitors two operating plants and one SAFSTORE plant. There is generally a lively dialog between NEAC and the Licensee during its annual briefing. The Licensee generally responds to NEAC when a question is not answered at the meeting.
the Annual Report is intended to inform the Governor and the legislature to allow them to take any necessary action.
cab-question12: NEAC has an annual joint meeting with the NRC. The NRC conducts its annual performance public meeting for the Millstone site in conjunction with the NEAC meeting.
cab-question13: The public has the opportunity to attend all NEAC meetings and the ability to comment during the meeting. All minutes are included in the annual reports available to public on the DEEP website at https://www.ct.gov/deep/cwp/view.asp?a=2713&q=457004&deepNav_GID=1639 cab-question14: NEAC provides a platform for the public and for the licensee to interact in a neutral arena. It provides the NRC with a platform to reach the public when it gives the annual update. NEAC serves as a year round civilian monitoring of plant activities. NEAC is able to calm citizen concerns through public meetings and factual presentations. Improves public confidence by having local experts review and listen to utility and NRC actions affecting safety.
cab-question15: None.
cab-question16: Public meetings Citizen participation in monitoring practices at the local plant In the beginning there is great public interest but as the licensee gets a handle on a problem and is able to explain in a neutral arena public concern is satisfied and attendance drops off.
NEAC's power is a bully pulpit that keeps the licensee "honest" and helps stop the spread of misinformation about the plant.
When tension's are high, giving a knowledgeable NEAC member access to the site for monitoring plant practices assisted both the licensee and the public nocab-question1:
nocab-question2:
nocab-question3:
nocab-question4:
nocab-question5: