|
---|
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 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 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 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 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 Staffs 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 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 2024-07-31
[Table view] |
Text
1 NRR-PMDAPEm Resource From: Thadani, Mohan Sent: Monday, September 08, 2014 2:10 PM To: Wanda D Craft (Generation - 6) (wanda.d.craft@dom.com)
Cc: Dennig, Robert; Sallman, Ahsan
Subject:
Millstone 3-Request for Additional Informati on: Proposed Change to TS 3.5.4 ,Refueling Water Storage Tank," and Surveillance Requirement SR 4.6.2.1a.
Wanda: The NRC staff has reviewed the Dominion Nuclear Connecticut Inc. (the licensee's) request in support of establishing additional margin for controlling the Refueling Water Storage TANK temperature. The NRC staff has determined that additional information is needed to facilitate timely completion of NRC's review of the licensee's request.
Please provide your response to the request for additional information, pasted below, within 30 days from the date of this request for additional information, so that the NRC staff can respond to the licensee's request.
Best regards,'
Mohan C Thadani Senior Project Manager Millstone, Ginna, and Constellation Fleet Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation (301) 415-1476 Mohan.Thadani@nrc.gov
_______________________________________________________________________________________
___________________________________________________________
REQUEST FOR ADDITIONAL INFORMATION By CONTAINMENT AND VENTILATION BRANCH TECHNICAL SPECIFICATION CHANGES FOR THE REFUELING WATER STORAGE TANK TEMPERATURE MILLSTONE POWER STATION UNIT 3 DOCKET NO. 50-423 By letter dated November 6, 2013 (Reference 1), pursuant to Section 50.90 of the Title 10 of the Code of Federal Regulations, Dominion Nuclear Connecticut, Inc. requested an amendment to Operating License Numbers NPF-49 in the form of changes to the Technical Specifications (TSs) for Millstone Power Station Unit 3 (MPS3).
The proposed change would revise TS 3.5.4, "Refueling Water Storage Tank," and Surveillance Requirement (SR) 4.6.2.1a).2 for providing additional operational margin for controlling the Refueling Water Storage Tank (RWST) temperature.
The Containment and Ventilation Branch (SCVB) staff has reviewed licensee's information supporting the proposed amendment and is requesting responses to the following items to complete its review:
2 SCVB-RAI-1
Reference 1, Section 3.2, last sentence of last paragraph:
"While not using 100 oF, subsequent analyses have been performed which continue to bound the RWST maximum temperature of 73 oF proposed herein."
Please provide responses to the following: a. Does the "subsequent analyses" replace the licensing basis containment analysis for the Stretch Power Uprate (SPU) in Reference 3? Is the subsequent analysis the current Analysis of Record (AOR) in the current Final Safety Analysis Report (FSAR)? Provide reasons for performing this analysis.
- b. Provide the values of other input parameters and assumptions that have been revised from the SPU Mass and Energy (M&E) release and containment response analyses to the AOR in the current FSAR which is the proposed basis for changes in the RWST temperatures. Justify the differences between the input parameters and assumptions.
SCVB-RAI-2
The LOCA containment M&E release analysis documented in the SPU application (References 2 and 3) was not based on the presently corrected versions of the computer codes in WCAP-10325-P-A (Reference 4) methodology. Westinghouse has issued Nuclear Safety Advisory Letters (NSALs)-06-6, 5, and 2 reporting errors in the WCAP-10325-P-A methodology and requires containment analyses should be corrected. These specific NSAL s have been addressed by other licensees in recent LARs. Describe changes in the following containment analyses results using the corrected Reference 4 methodology that incorporates corrections listed in the above NSALs, together with the revised RWST temperatures: (a) containment peak pressure, (b) containment peak gas temperature for Environment Equipment Qualification (EEQ), (c) containment peak wall temperature, (d) containment sump peak water temperature, (e) pump Net Positive Suction Head Available (NPSHA) for the pumps that draw water from the containment sump during recirculation mode of safety injection and containment cooling, and (f) containment minimum pressure analysis for Emergency Core Cooling System (ECCS) performance capability. REFERENCES
- 1. Letter from Dominion to NRC dated November 6, 2013, "Dominion Nuclear Connecticut, Inc. Millstone Power Station Unit 3, Licensee Amendment Request, Proposed Technical Specification Changes of the Refueling Water Storage Tank Allowable Temperatures", (ADAMS Accession Number ML13322A415)
- 2. Letter from Dominion to NRC, "Dominion Nuclear Connecticut, Inc., Millstone Power Station Unit 3, License Amendment Request, Stretch Power Uprate," dated July 13, 2007, (ADAMS Accession Number ML072000386)
- 3. NRC letter to Dominion dated August 12, 2008, "Millstone Power Station, Unit No. 3, Issuance of Amendment RE: Stretch Power Uprate (TAC No. MD6070)," (ADAMS Accession Number
ML081610585)
- 4. WCAP-10325-P-A, May 1983 (Proprietary) and WCAP-10326-A (Nonproprietary), "Westinghouse LOCA Mass and Energy Release Model for Containment Design, March 1979."
Mohan C Thadani 3Senior Project Manager Millstone, Ginna, and Constellation Fleet Plants Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation (301) 415-1476 Mohan.Thadani@nrc.gov
Hearing Identifier: NRR_PMDA Email Number: 1554 Mail Envelope Properties (Mohan.Thadani@nrc.gov20140908140900)
Subject:
Millstone 3-Request for Additional Information: Proposed Change to TS 3.5.4 ,Refueling Water Storage Tank," and Surveillance Requirement SR 4.6.2.1a. Sent Date: 9/8/2014 2:09:55 PM Received Date: 9/8/2014 2:09:00 PM From: Thadani, Mohan Created By: Mohan.Thadani@nrc.gov Recipients: "Dennig, Robert" <Robert.Dennig@nrc.gov> Tracking Status: None "Sallman, Ahsan" <Ahsan.Sallman@nrc.gov> Tracking Status: None "Wanda D Craft (Generation - 6) (wanda.d.craft@dom.com)" <wanda.d.craft@dom.com> Tracking Status: None Post Office: Files Size Date & Time MESSAGE 5437 9/8/2014 2:09:00 PM
Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received: