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| {{#Wiki_filter:December 12, 2006MEMORANDUM TO: Harold K. Chernoff, ChiefPlant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationFROM:Victor Nerses, Senior Project Manager /RA/ Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation | | {{#Wiki_filter:December 12, 2006 MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Victor Nerses, Senior Project Manager /RA/ |
| | Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation |
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| ==SUBJECT:== | | ==SUBJECT:== |
| MILLSTONE POWER STATION, UNIT NO. 2 - FACSIMILETRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING TECHNICAL SPECIFICATION CHANGES BASED ON USING AN ALTERNATE SOURCE TERM (TAC NO. MC2346)The attached draft request for additional information (RAI) was transmitted by facsimile on December 12, 2006, to Mr. Paul Willoughby, at Dominion Nuclear Connecticut, Inc. (DNC orthe licensee). This draft RAI was transmitted to facilitate the technical review being conductedby the Nuclear Regulatory Commission (NRC) staff and to support a conference call with DNC in order to clarify certain items in the licensee's submittal. The draft RAI is related to DNC's submittal dated June 13, 2006, regarding Technical Specification changes based on using an alternate source term. Review of the draft RAI would allow DNC to determine and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not represent an NRC staff position. | | MILLSTONE POWER STATION, UNIT NO. 2 - FACSIMILE TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING TECHNICAL SPECIFICATION CHANGES BASED ON USING AN ALTERNATE SOURCE TERM (TAC NO. MC2346) |
| | The attached draft request for additional information (RAI) was transmitted by facsimile on December 12, 2006, to Mr. Paul Willoughby, at Dominion Nuclear Connecticut, Inc. (DNC or the licensee). This draft RAI was transmitted to facilitate the technical review being conducted by the Nuclear Regulatory Commission (NRC) staff and to support a conference call with DNC in order to clarify certain items in the licensees submittal. The draft RAI is related to DNCs submittal dated June 13, 2006, regarding Technical Specification changes based on using an alternate source term. Review of the draft RAI would allow DNC to determine and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not represent an NRC staff position. |
| Docket No. 50-336 | | Docket No. 50-336 |
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| ==Enclosure:== | | ==Enclosure:== |
| As stated December 12, 2006MEMORANDUM TO: Harold K. Chernoff, ChiefPlant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationFROM:Victor Nerses, Senior Project Manager /RA/ Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation | | |
| | As stated |
| | |
| | December 12, 2006 MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Victor Nerses, Senior Project Manager /RA/ |
| | Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation |
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| |
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| ==SUBJECT:== | | ==SUBJECT:== |
| MILLSTONE POWER STATION, UNIT NO. 2 - FACSIMILETRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING TECHNICAL SPECIFICATION CHANGES BASED ON USING AN ALTERNATE SOURCE TERM (TAC NO. MC2346)The attached draft request for additional information (RAI) was transmitted by facsimile on December 12, 2006, to Mr. Paul Willoughby, at Dominion Nuclear Connecticut, Inc. (DNC orthe licensee). This draft RAI was transmitted to facilitate the technical review being conductedby the Nuclear Regulatory Commission (NRC) staff and to support a conference call with DNC in order to clarify certain items in the licensee's submittal. The draft RAI is related to DNC's submittal dated June 13, 2006, regarding Technical Specification changes based on using an alternate source term. Review of the draft RAI would allow DNC to determine and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not represent an NRC staff position. | | MILLSTONE POWER STATION, UNIT NO. 2 - FACSIMILE TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING TECHNICAL SPECIFICATION CHANGES BASED ON USING AN ALTERNATE SOURCE TERM (TAC NO. MC2346) |
| | The attached draft request for additional information (RAI) was transmitted by facsimile on December 12, 2006, to Mr. Paul Willoughby, at Dominion Nuclear Connecticut, Inc. (DNC or the licensee). This draft RAI was transmitted to facilitate the technical review being conducted by the Nuclear Regulatory Commission (NRC) staff and to support a conference call with DNC in order to clarify certain items in the licensees submittal. The draft RAI is related to DNCs submittal dated June 13, 2006, regarding Technical Specification changes based on using an alternate source term. Review of the draft RAI would allow DNC to determine and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not represent an NRC staff position. |
| Docket No. 50-336 | | Docket No. 50-336 |
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| ==Enclosure:== | | ==Enclosure:== |
| As statedDISTRIBUTION | | |
| :Public LBrown CLauronRidsNrrDraAadb LPL1-2RidsNrrPMVNerses RidsNrrLACRaynorAccession No.: ML063070147OFFICELPL1-2/PMLPL1-2/LAAADD/BCCSGB/BCLPL1-2/BCNAMEVNerses: CRaynorMKotzalasAHiserHChernoff DATE12/06/0611/14/0611/16/068/25/0612/12/06OFFICIAL RECORD COPY DRAFT REQUEST FOR ADDITIONAL INFORMATIONMILLSTONE POWER STATION, UNIT NO. 2(TAC NO. MC2346
| | As stated DISTRIBUTION: |
| )By letter dated June 13, 2006, Dominion Nuclear Connecticut, Inc. (DNC) submitted a licenseamendment request (LAR) for changes to the Technical Specifications to Facility Operating License Number DPR-65 for Millstone Power Station, Unit No. 2 (MPS2). The proposed changes are being requested based on the radiological dose analysis margins obtained by using an alternate source term consistent with Title 10 of the Code of Federal RegulationsSection 50.67, "Accident Source Term." The Nuclear Regulatory Commission (NRC) staff requests the following additional information to complete its review.1. Attachment 1 to the LAR indicates that the proposal is a full-scope implementation ofRegulatory Guide (RG) 1.183, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors." Table 3.1.4, "Basic Data Assumptions for LOCA [loss-of-coolent accident]," of Section 3.1.5, "LOCA Analysis Assumptions & Key Parameter Values," to the attachment lists the assumptions supporting the LOCA reanalysis. The containment sump is assumed to be maintained at a pH greater than 7; however, details regarding this assumption are not provided.Consistent with Appendix A to RG 1.183, the NRC staff requests that the analysissupporting this assumption be provided for review. This analysis should include, at a minimum, the time-dependent changes to the pH as a result of the formation of acids and the introduction of bases to the containment during the LOCA.2.Provide figures which support the selection of the inputs and assumptions used tocalculate all of the /Q values. Include a figure of the general arrangement of plantstructures, drawn approximately to scale and showing true north, sufficient to enable the NRC staff to make confirmatory estimates of the selected inputs and assumptions and resultant /Q values. For each accident, highlight the postulated release and receptorlocations including control room locations that may experience unfiltered inleakage.3.Were distance inputs into the ARCON96 calculations directly estimated as horizontalstraight line distances or was another methodology (e.g., a "taut string" methodology) used to estimate the distances? If the distances were not estimated directly as the straight line horizontal distance, how were they determined? Did the procedure used to estimate the distances properly factor in differences in heights between source and receptor?4.Although implied in the text by discussion of some specific cases, please confirm thatthe accident scenarios and generated /Q values model the limiting doses consideringmultiple release scenarios (e.g., including those due to loss-of-offsite power or other single failure). Which /Q values are used to model unfiltered inleakage to the controlroom?
| | Public LBrown CLauron RidsNrrDraAadb LPL1-2 RidsNrrPMVNerses RidsNrrLACRaynor Accession No.: ML063070147 OFFICE LPL1-2/PM LPL1-2/LA AADD/BC CSGB/BC LPL1-2/BC NAME VNerses: CRaynor MKotzalas AHiser HChernoff DATE 12/06/06 11/14/06 11/16/06 8/25/06 12/12/06 OFFICIAL RECORD COPY |
| 5.The footnote to Table 1.3-4 of Attachment 1, page 10, notes that the MPS2 stackcontrol room atmospheric dispersion factors (/Q values) were approved as part ofMPS2 Amendment No. 228. The NRC staff agrees that these values were found acceptable for the first 24 hours of the postulated release. The /Q values in Table 1.3-4 for the 24-96 hour and 96-720 hour time periods are larger than the values approved as part of Amendment No. 228. Were these values calculated using the 1997-2001 (more recent) meteorological data and, since they are more limiting, are they being proposed to replace the Amendment No. 228 /Q values for the 24-96 hour and96-720 hour time periods?6.Technical Specification sections 4.3.4.2 and 3.4.3.4, related to the containment purgevalve isolation signal, are proposed for deletion. Both contain the same two X/Q values. Please confirm that reference to these values are in these two sections only, that is, deletion of the X/Q values would not impact other parts of the Technical Specifications, plant procedures, etc.7.DNC is seeking credit for an operator action. In particular, for a main steamline breakoutside containment (in the enclosure building or turbine building), operator action will be prompted to isolate the control room within 4 hours from the start of the event. The following information is required.a.What specific switch manipulations will be required to isolate the control room?Are the switches and the components they operate safety-grade and with safety-grade support systems (e.g., DC control power, AC motive power, air motive power)?b.Where will the switch manipulations occur? | | |
| c.Who will perform the manipulations required to isolate the control room? | | DRAFT REQUEST FOR ADDITIONAL INFORMATION MILLSTONE POWER STATION, UNIT NO. 2 (TAC NO. MC2346) |
| d.What alarms/indications will be used in response to a main steamline breakoutside containment to prompt the action to isolate the control room? Where are these alarms and indicators located? Are these alarms and indications safety-grade and powered from safety-grade electrical power supplies?e.What alarms/indications will be used to verify success in isolating the controlroom? For example, damper position indicating lights, flow indicators, alarms occurring or clearing, etc. Where are these alarms and indications located? Are these alarms and indications safety-grade and powered from safety-grade electrical power supplies?f.How will the operator action to isolate the control room in response to a mainsteamline break outside containment be incorporated into plant procedures?g.How will this new operator action to isolate the control room in response to amain steamline break outside containment be incorporated into your training programs?}} | | By letter dated June 13, 2006, Dominion Nuclear Connecticut, Inc. (DNC) submitted a license amendment request (LAR) for changes to the Technical Specifications to Facility Operating License Number DPR-65 for Millstone Power Station, Unit No. 2 (MPS2). The proposed changes are being requested based on the radiological dose analysis margins obtained by using an alternate source term consistent with Title 10 of the Code of Federal Regulations Section 50.67, Accident Source Term. The Nuclear Regulatory Commission (NRC) staff requests the following additional information to complete its review. |
| | : 1. Attachment 1 to the LAR indicates that the proposal is a full-scope implementation of Regulatory Guide (RG) 1.183, Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors. Table 3.1.4, Basic Data Assumptions for LOCA [loss-of-coolent accident], of Section 3.1.5, LOCA Analysis Assumptions & Key Parameter Values, to the attachment lists the assumptions supporting the LOCA reanalysis. The containment sump is assumed to be maintained at a pH greater than 7; however, details regarding this assumption are not provided. |
| | Consistent with Appendix A to RG 1.183, the NRC staff requests that the analysis supporting this assumption be provided for review. This analysis should include, at a minimum, the time-dependent changes to the pH as a result of the formation of acids and the introduction of bases to the containment during the LOCA. |
| | : 2. Provide figures which support the selection of the inputs and assumptions used to calculate all of the /Q values. Include a figure of the general arrangement of plant structures, drawn approximately to scale and showing true north, sufficient to enable the NRC staff to make confirmatory estimates of the selected inputs and assumptions and resultant /Q values. For each accident, highlight the postulated release and receptor locations including control room locations that may experience unfiltered inleakage. |
| | : 3. Were distance inputs into the ARCON96 calculations directly estimated as horizontal straight line distances or was another methodology (e.g., a taut string methodology) used to estimate the distances? If the distances were not estimated directly as the straight line horizontal distance, how were they determined? Did the procedure used to estimate the distances properly factor in differences in heights between source and receptor? |
| | : 4. Although implied in the text by discussion of some specific cases, please confirm that the accident scenarios and generated /Q values model the limiting doses considering multiple release scenarios (e.g., including those due to loss-of-offsite power or other single failure). Which /Q values are used to model unfiltered inleakage to the control room? |
| | : 5. The footnote to Table 1.3-4 of Attachment 1, page 10, notes that the MPS2 stack control room atmospheric dispersion factors (/Q values) were approved as part of MPS2 Amendment No. 228. The NRC staff agrees that these values were found acceptable for the first 24 hours of the postulated release. The /Q values in Table 1.3-4 for the 24-96 hour and 96-720 hour time periods are larger than the values approved as part of Amendment No. 228. Were these values calculated using the 1997-2001 (more recent) meteorological data and, since they are more limiting, are they being proposed to replace the Amendment No. 228 /Q values for the 24-96 hour and 96-720 hour time periods? |
| | : 6. Technical Specification sections 4.3.4.2 and 3.4.3.4, related to the containment purge valve isolation signal, are proposed for deletion. Both contain the same two X/Q values. |
| | Please confirm that reference to these values are in these two sections only, that is, deletion of the X/Q values would not impact other parts of the Technical Specifications, plant procedures, etc. |
| | : 7. DNC is seeking credit for an operator action. In particular, for a main steamline break outside containment (in the enclosure building or turbine building), operator action will be prompted to isolate the control room within 4 hours from the start of the event. The following information is required. |
| | : a. What specific switch manipulations will be required to isolate the control room? |
| | Are the switches and the components they operate safety-grade and with safety-grade support systems (e.g., DC control power, AC motive power, air motive power)? |
| | : b. Where will the switch manipulations occur? |
| | : c. Who will perform the manipulations required to isolate the control room? |
| | : d. What alarms/indications will be used in response to a main steamline break outside containment to prompt the action to isolate the control room? Where are these alarms and indicators located? Are these alarms and indications safety-grade and powered from safety-grade electrical power supplies? |
| | : e. What alarms/indications will be used to verify success in isolating the control room? For example, damper position indicating lights, flow indicators, alarms occurring or clearing, etc. Where are these alarms and indications located? Are these alarms and indications safety-grade and powered from safety-grade electrical power supplies? |
| | : f. How will the operator action to isolate the control room in response to a main steamline break outside containment be incorporated into plant procedures? |
| | : g. How will this new operator action to isolate the control room in response to a main steamline break outside containment be incorporated into your training programs?}} |
Letter Sequence Draft RAI |
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Category:Memoranda
MONTHYEARML24222A6992024-08-16016 August 2024
August 6, 2024, Summary of Regarding Potential License Amendment Request Change to Surveillance Requirements for Moderator Temperature Coefficient for Millstone, Unit No. 3, North Anna, Unit Nos. 1 and 2, and Summer, Unit No. 1 -
ML22130A1702022-05-20020 May 2022
Summary of April 21, 2022, Public Meeting to Discuss Potential Emergency Preparedness License Amendment Request
ML22028A3502022-01-21021 January 2022
Green Mountain Power, 2021 Annual Summary of Special Nuclear Committee
ML21027A0232021-01-28028 January 2021
Summary of January 26, 2021 Closed Meeting with Dominion Energy Regarding Performance of Force on Force Exercises in a Pandemic Environment
ML19165A1192019-06-14014 June 2019
Memoranda to File Environmental Assessment and Finding of No Significant Impact for the Virginia Electric and Power Company, Dominion Energy Kewaunee, Inc., and Dominion Nuclear Connecticut, Inc.'S Decommissioning Funding Plans Submitted
ML17271A0532017-09-29029 September 2017
2017 Summary of Annual Decommissioning Funding Status Reports for Reactors in Decommissioning
ML16088A2042016-03-28028 March 2016
Memo T Bowers from s Ruffin, Technical Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations W/ Encl 2 (Template)
ML16088A2052016-03-28028 March 2016
Enclosure 1 - (72.30 DFP Reviews to Be Completed 2015) - Memo T Bowers from s Ruffin, Technial Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations
ML15075A1922015-03-26026 March 2015
Reactor Coolant System Alloy 600 Inspection Program for License Renewal Commitment No. 14. (Tac No. MF3433)
ML13031A1832013-02-0505 February 2013
Closed Meeting Announcement Millstone Drop-In
ML13032A0572013-01-30030 January 2013
2012 Annual Summary of the Green Mountain Power Special Nuclear Committee
ML12178A6132012-06-27027 June 2012
Notice of Forthcoming Pre-Application Meeting with Dominion Nuclear Connecticut, Inc. to Discuss a Proposed Millstone Power Station, Unit 2, License Amendment Request Concerning Spent Fuel Pool Criticality Re-Analysis
ML13196A2202012-06-0606 June 2012
Memo from B. Balsam, NRR and D. Logan, NRR to J. Susco, NRR on Summary of Section 7 Consultation Activities Related to the National Marine Fisheries Service'S Final Rule to List the Atlantic Sturgeon
ML11271A1782011-10-0303 October 2011
Review of Topical Report, Revision 11 for Kewaunee Power Station and ISFSI, Millstone Power Station, Units 1, 2, & 3 and ISFSI, North Anna Power Station, Units 1 & 2 and ISFSI, Surry Power Station, Units 1 & 2 and ISFSI (Tac ME6649, ME6650,
ML11250A1712011-09-14014 September 2011
Notice of Forthcoming Meeting with Petitioner Requesting Action Under 10 CFR 2.206 Regarding Immediate Suspension of the Operating Licenses of General Electric (GE) Mark 1 Boiling Water Reactors (Bwrs)
ML1116804602011-06-30030 June 2011
Review of Commitment Change Report for 2009
ML1103106822011-02-0101 February 2011
Revised Notice of Forthcoming Public Meeting with Dominion Nuclear Connecticut, Inc., to Discuss Millstone Power Station Licensing Activities
ML1100701752011-01-11011 January 2011
Request for Technical Assistance on Request for Exemption Form Certain Requirements of 10 CFR 73.55 for Millstone Power Station, Unit 1
ML1035103202010-12-20020 December 2010
30-Day Report of Emergency Core Cooling System Model Change
ML1033305502010-12-15015 December 2010
Potential Notice of Enforcement Discretion for the Turbine Driven Auxiliary Feedwater Pump
ML1031202422010-11-0808 November 2010
Notice of Teleconference with Dominion Nuclear Connecticut, Inc. to Discuss Millstone Power Station, Unit No. 3 Generic Letter 2004-02 Supplemental Response
ML1030100732010-10-28028 October 2010
Meeting Notice Milestone Power Station Revised 10 CFR 73.55
ML1019502842010-07-14014 July 2010
Notice of Forthcoming Public Teleconference with Dominion Nuclear Connecticut, Inc. to Discuss Millstone Power Station, Unit No. 3 Generic Letter 2004-02 Supplemental Response
ML1008204222010-03-26026 March 2010
Notice of Conference Call with Dominion Nuclear Connecticut, Inc. to Discuss Millstone Power Station, Unit Nos 2 and 3 Generic Letter 2004-02 Supplemental Responses
ML1003314992010-03-0101 March 2010
Notice of Conference Call with Dominion Nuclear Connecticut, Inc., to Discuss Millstone Power Station, Unit Nos. 2 and 3 Generic Letter 2004-02 Supplemental Responses
ML0931406252009-11-17017 November 2009
Summary of Teleconference Verbal Authorization for Relief Request RR-89-67
ML0913401332009-05-15015 May 2009
Notice of Forthcoming Meeting with Dominion Nuclear Connecticut, Inc. to Discuss the Submittal of a License Amendment Request Regarding the Removal of Charging Pumps from the Technical Specifications for Millstone Power Station, Unit No. 2
ML0906205722009-03-0303 March 2009
Meeting Minutes of the Power Uprates Subcommittee, July 8, 2008
ML0811500912008-04-23023 April 2008
Proposed Stretch Power Uprate to Millstone Power Station, Unit 3
ML0807400842008-03-14014 March 2008
Draft Regulatory Guide for Comment
ML0734708412007-12-11011 December 2007
Drop-In Visit from Dominion (Millstone)
ML0730304052007-10-31031 October 2007
E. Marinos Memo Technical Assistance Request-Dominion Resources, Inc.'S December 6, 2006, Request for Exemption from 10 CFR 74.13(a) Requirements Regarding Material Status Report Submittal Time Frame
ML0715100542007-05-31031 May 2007
Closeout of TAC Numbers for Licensing Activities That Do Not Require Staff Review
ML0710201942007-04-24024 April 2007
Draft Open Items from Staff Audit of Corrective Actions to Address Generic Letter 2004-02
ML0707902492007-03-20020 March 2007
Facsimile Transmission, Draft Request for Additional Information Regarding Steam Generator Tube Integrity
ML0634902692007-01-11011 January 2007
Memo: K. Mcconnell to M. Lesar - Notice of Environmental Assessment and Finding of No Significant Impact Related to Partial Exemption from 10 CFR Part 50, Recordkeeping Requirements - Millstone Power Station, Unit 1
ML0633901162006-12-19019 December 2006
Fax - Draft Request for Additional Information Regarding Post-Maintenance/Modification Surveillance Requirements
ML0630701472006-12-12012 December 2006
Facsimile Transmission, Draft Request for Additional Information
ML0631101502006-11-13013 November 2006
Request for Additional Information Regarding Human Factors - Millstone, Unit 2, Alternate Source Term License Amendment Request
ML0626800242006-10-0202 October 2006
Transfer of Project Management Responsibilities
ML0625100662006-09-29029 September 2006
Facsimile Transmission, Draft Request for Additional Information Regarding Extension of Integrated Leakage Rate Test Interval
ML0619500042006-07-14014 July 2006
Facsimile Transmission, Draft Request for Additional Information Regarding Post Maintenance/Modification Surveillance Requirements
ML0619500092006-07-14014 July 2006
Facsimile Transmission, Draft Request for Additional Information Regarding Relaxation Request IR-2-46, Reactor Pressure Vessel Head Inspections
ML0617805592006-07-10010 July 2006
Revised Closeout Letter for Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors.
ML0617701952006-06-26026 June 2006
Closeout of Tac Number for Licensing Activities Incorrectly Identified for Staff Review
ML0606702532006-03-24024 March 2006
Facsimile Transmission, Draft Request for Additional Information to Be Discussed in an Upcoming Conference Call
ML0608601632006-03-21021 March 2006
Handouts to Applicants (Folder 3)
ML0604005082006-03-0202 March 2006
Facsimile Transmission, Draft Request for Additional Information to Be Discussed in an Upcoming Conference Call
ML0602700882006-01-31031 January 2006
Facsimile Transmission Draft Request for Additional Information to Be Discussed in an Upcoming Conference Call (Tac No. MC8327)
ML0602502612006-01-26026 January 2006
Facsimile Transmission, Draft Request for Additional Information to Be Discussed in an Upcoming Conference Call
2024-08-16
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24213A2602024-07-31031 July 2024
Request for Additional Information LAR to Support Implementation of Framatome Gaia Fuel
IR 05000336/20244032024-07-22022 July 2024
Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000336/2024403 and 05000423/2024403
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
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
ML23318A0952023-11-14014 November 2023
Request for Additional Information (E-mail Dated 11/14/2023) LAR to Revise TSs Related to Framatome Gaia Fuel
ML23199A2832023-07-18018 July 2023
Request for Additional Information (E-mail Dated 7/18/2023) LAR to Revise the Pressure-Temperature Limits
ML23171B0522023-06-20020 June 2023
NRR E-mail Capture - RAI for Review of Appendix F to DOM-NAF-2-P (Redacted)
ML23089A1882023-03-29029 March 2023
Request for Additional Information (E-mail Dated 3/29/2023) Spring 2022 Steam Generator Tube Inspection Report
ML23073A1802023-03-14014 March 2023
Notification of Commercial Grade Dedication Inspection (05000336/2023010 and 05000423/2023010) and Request for Information
ML22251A1292022-09-0909 September 2022
Request for Additional Information Related to Response to Generic Letter 2004-04
ML22242A0452022-08-23023 August 2022
NRR E-mail Capture - Dominion GL 04-02 Response Draft RAIs (L-2017-LRC-0000)
ML21225A5022021-08-13013 August 2021
Request for Additional Information for North Anna Power Station, Units 1 and 2, Surry Power Station, Units 1 and 2, and Millstone Power Station, Units 2 and 3, Appendix E of Fleet Report Com-Naf-2 (EPID:L02021-LLT-0000) Public Version
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
ML21182A2902021-07-0101 July 2021
7/1/2021 E-mail - Request for Additional Information Alternative Frequency to Supplemental Valve Position Verification Testing Requirements
ML21112A3082021-04-22022 April 2021
Request for Additional Information (E-mail Dated 4/22/2021) License Amendment Request for Measurement Uncertainty Recapture Power Uprate
ML21105A1152021-04-15015 April 2021
Request for Additional Information (e-mail Dated 4/15/2021) Proposed LAR for Addition of Analytical Methodology to the Core Operating Limits Report for a LBLOCA
ML21078A0332021-03-18018 March 2021
NRR E-mail Capture - Millstone Power Station, Unit 2 - Request for Additional Information - Proposed LAR to Revise TSs for Steam Generator Inspection Frequency
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)
ML21077A1652021-02-26026 February 2021
(02/26/2021 E-mail) Draft Request for Additional Information LAR to Revise Technical Specifications for Steam Generator Inspection Frequency
ML21034A5762021-02-0303 February 2021
Request for Additional Information (e-mail Dated 1/3/2021) Alternative Request RR-05-06 Inservice Inspection Interval Extension for Steam Generator Weld Inspections
ML20246G5612020-09-0202 September 2020
Request for Additional Information (E-mail Dated 9/2/2020) License Amendment Request for a One-Time Deferral of the Steam Generator Inspections
ML20244A2902020-08-31031 August 2020
Request for Additional Information (E-mail Dated 8/31/2020) License Amendment Request to Revise Battery Surveillance Requirements
ML20231A7172020-08-18018 August 2020
Request for Additional Information (e-mail Dated 8/18/2020) License Amendment Request to Revise TS Table 3.3-11 Accident Monitoring Instrumentation
ML20184A0052020-07-0202 July 2020
Request for Additional Information (E-mail Dated 7/2/2020) Relief Request IR-3-33 for Limited Coverage Examiniations
ML20075A0322020-03-15015 March 2020
Request for Additional Information (E-mail Dated 3/15/2020) Alternative Request IR-4-03 for Use of an Alternative Non-Code Methodology to Demonstrate Structural Integrity
ML20050F9212020-02-19019 February 2020
Request for Additional Information (E-mail Dated 2/19/2020) Proposed LAR to Revise TS 3.8.1.1, AC Sources Operating
ML20023D0372020-01-23023 January 2020
Request for Additional Information (E-mail Dated 1/23/2020) Proposed LAR to Revise TS 3.8.1.1, AC Sources Operating
ML19361A0382019-12-23023 December 2019
12/23/19 E-mail from R.Guzman to S. Sinha - Draft Request for Additional Information Planned Audit of LAR to Revise TS 3.8.1.1
ML19277B9082019-10-0707 October 2019
Supplemental Information Needed for Acceptance of Requested Licensing Action Extension of Technical Specification 3.8.1.1, A.C. Sources - Operating, Allowed Outage Time
ML19248D7552019-09-0505 September 2019
Request for Additional Information Via E-mail from R.Guzman to S. Sinha Proposed License Amendment Request to Adopt 10 CFR 50.69
ML19169A0962019-06-17017 June 2019
NRR E-mail Capture - Request for Additional Information Emergency Action Level Scheme Change for Millstone Power Station - Units 1, 2, and 3, North Anna Power Station - Units 1 and 2, and Surry Power Station - Units 1 and 2
ML19162A0052019-06-10010 June 2019
NRR E-mail Capture - Draft RAIs for Dominion EAL Scheme Change
ML19042A1822019-02-11011 February 2019
Request for Additional Information LAR for TS Changes to Spent Fuel Storage and New Fuel Storage, 02/11/2019 E-mail from R. Guzman to S. Sinha
ML18291B3262018-10-18018 October 2018
Request for Additional Information LAR Regarding Proposed Technical Specification Changes for Spent Fuel Pool Storage and New Fuel Storage, E-mail from R.Guzman to S.Sinha
ML18277A1762018-10-0404 October 2018
Request for Additional Information LAR to Revise TS Action Statement for Loss of Control Building Inlet Ventilation Rad Monitor Instrumentation Channels (e-mail from R.Guzman to M.Whitlock, EPID: L-2018-LLA-0099)
ML18213A1152018-08-0101 August 2018
Request for Additional Information Alternative Request P-06 'C' Charging Pump (08/01/2018 E-mail from R. Guzman to M. Whitlock)
ML18171A1532018-06-20020 June 2018
Request for Additional Information Via E-mail from R.Guzman to W.Craft Alternative Requests for Inservice Testing Program (E-mail from R.Guzman to W.Craft) (EPID: L-2018-LLR-0012-LLR-0022)
ML18137A3132018-05-17017 May 2018
Request for Additional Information Via E-mail from R.Guzman to W.Craft Proposed License Amendment Request to Revise ILRT Type a and Type C Test Intervals
ML17297A8472017-10-27027 October 2017
Request for Supplemental Information Regarding Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools (CAC No. MF9430; EPID L-2016-LRC-0001)
ML17033B6142017-02-0202 February 2017
Request for Additional Information, 2017/02/02 E-mail from R.Guzman to W.Craft Proposed Alternative RR-04-24 and IR-3-30 for the Elimination of Reactor Pressure Vessel Threads in Flange Examination (CAC Nos. MF8468/MF8469)
ML17005A3282017-01-0505 January 2017
MPS2 EOC-23 and MPS3 EOC-17 Steam Generator Tube Inspection Reports - Requests for Additional Information
ML16260A0062016-09-16016 September 2016
2016/09/16 E-mail from R. Guzman to W. Craft Request for Additional Information - License Amendment Request Realistic Large Break Loss of Coolant Accident Analysis (MF7761)
ML16267A0022016-09-12012 September 2016
2016/09/12 E-mail from R.Guzman to W.Craft Request for Additional Information - LAR to Revise ECCS TS and FSAR Ch. 14 to Remove Charging (MF7297)
ML16133A3562016-05-12012 May 2016
E-mail from R. Guzman to C. Sly Request for Additional Information Supporting License Amendment Request to Remove Charging Credit
ML16068A4142016-03-0808 March 2016
Request for Additional Information - Relief Request RR-04-19 Examination Cat R-A, Risk-Informed Piping Examinations (MF6569)
ML16055A5302016-02-24024 February 2016
2016/02/24 E-mail from R.Guzman to W.Craft Request for Additional Information - LAR to Adopt Dominion Core Design and Safety Analysis Methods (MF6251)
ML16047A1712016-02-16016 February 2016
2016/02/16 E-mail from R.Guzman to M. Whitlock Request for Additional Information - Small Break Loss of Coolant Accident Re-Analysis (MF6700)
ML16043A5232016-02-12012 February 2016
Request for Additional Information 2016/02/12 E-mail from R. Guzman to M.Whitlock Relief Requests IR-3-22 and IR-3-23 (CAC Nos. MF6573 and MF6574)
ML16013A4772016-01-13013 January 2016
NRR E-mail Capture - Millstone Power Station, Units 2 and 3 - Request for Additional Information License Amendment Request for Removal of Severe Line Outage Detection (Slod) from the Offsite Power System - (MF6430, MF6431)
ML16011A5172016-01-11011 January 2016
NRR E-mail Capture - Millstone Power Station, Unit 3, Reactor Vessel Surveillance Capsule Withdrawal Schedule - Request for Additional Information
2024-07-31
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Text
December 12, 2006 MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Victor Nerses, Senior Project Manager /RA/
Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
MILLSTONE POWER STATION, UNIT NO. 2 - FACSIMILE TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING TECHNICAL SPECIFICATION CHANGES BASED ON USING AN ALTERNATE SOURCE TERM (TAC NO. MC2346)
The attached draft request for additional information (RAI) was transmitted by facsimile on December 12, 2006, to Mr. Paul Willoughby, at Dominion Nuclear Connecticut, Inc. (DNC or the licensee). This draft RAI was transmitted to facilitate the technical review being conducted by the Nuclear Regulatory Commission (NRC) staff and to support a conference call with DNC in order to clarify certain items in the licensees submittal. The draft RAI is related to DNCs submittal dated June 13, 2006, regarding Technical Specification changes based on using an alternate source term. Review of the draft RAI would allow DNC to determine and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not represent an NRC staff position.
Docket No. 50-336
Enclosure:
As stated
December 12, 2006 MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Victor Nerses, Senior Project Manager /RA/
Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
MILLSTONE POWER STATION, UNIT NO. 2 - FACSIMILE TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING TECHNICAL SPECIFICATION CHANGES BASED ON USING AN ALTERNATE SOURCE TERM (TAC NO. MC2346)
The attached draft request for additional information (RAI) was transmitted by facsimile on December 12, 2006, to Mr. Paul Willoughby, at Dominion Nuclear Connecticut, Inc. (DNC or the licensee). This draft RAI was transmitted to facilitate the technical review being conducted by the Nuclear Regulatory Commission (NRC) staff and to support a conference call with DNC in order to clarify certain items in the licensees submittal. The draft RAI is related to DNCs submittal dated June 13, 2006, regarding Technical Specification changes based on using an alternate source term. Review of the draft RAI would allow DNC to determine and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not represent an NRC staff position.
Docket No. 50-336
Enclosure:
As stated DISTRIBUTION:
Public LBrown CLauron RidsNrrDraAadb LPL1-2 RidsNrrPMVNerses RidsNrrLACRaynor Accession No.: ML063070147 OFFICE LPL1-2/PM LPL1-2/LA AADD/BC CSGB/BC LPL1-2/BC NAME VNerses: CRaynor MKotzalas AHiser HChernoff DATE 12/06/06 11/14/06 11/16/06 8/25/06 12/12/06 OFFICIAL RECORD COPY
DRAFT REQUEST FOR ADDITIONAL INFORMATION MILLSTONE POWER STATION, UNIT NO. 2 (TAC NO. MC2346)
By letter dated June 13, 2006, Dominion Nuclear Connecticut, Inc. (DNC) submitted a license amendment request (LAR) for changes to the Technical Specifications to Facility Operating License Number DPR-65 for Millstone Power Station, Unit No. 2 (MPS2). The proposed changes are being requested based on the radiological dose analysis margins obtained by using an alternate source term consistent with Title 10 of the Code of Federal Regulations Section 50.67, Accident Source Term. The Nuclear Regulatory Commission (NRC) staff requests the following additional information to complete its review.
- 1. Attachment 1 to the LAR indicates that the proposal is a full-scope implementation of Regulatory Guide (RG) 1.183, Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors. Table 3.1.4, Basic Data Assumptions for LOCA [loss-of-coolent accident], of Section 3.1.5, LOCA Analysis Assumptions & Key Parameter Values, to the attachment lists the assumptions supporting the LOCA reanalysis. The containment sump is assumed to be maintained at a pH greater than 7; however, details regarding this assumption are not provided.
Consistent with Appendix A to RG 1.183, the NRC staff requests that the analysis supporting this assumption be provided for review. This analysis should include, at a minimum, the time-dependent changes to the pH as a result of the formation of acids and the introduction of bases to the containment during the LOCA.
- 2. Provide figures which support the selection of the inputs and assumptions used to calculate all of the /Q values. Include a figure of the general arrangement of plant structures, drawn approximately to scale and showing true north, sufficient to enable the NRC staff to make confirmatory estimates of the selected inputs and assumptions and resultant /Q values. For each accident, highlight the postulated release and receptor locations including control room locations that may experience unfiltered inleakage.
- 3. Were distance inputs into the ARCON96 calculations directly estimated as horizontal straight line distances or was another methodology (e.g., a taut string methodology) used to estimate the distances? If the distances were not estimated directly as the straight line horizontal distance, how were they determined? Did the procedure used to estimate the distances properly factor in differences in heights between source and receptor?
- 4. Although implied in the text by discussion of some specific cases, please confirm that the accident scenarios and generated /Q values model the limiting doses considering multiple release scenarios (e.g., including those due to loss-of-offsite power or other single failure). Which /Q values are used to model unfiltered inleakage to the control room?
- 5. The footnote to Table 1.3-4 of Attachment 1, page 10, notes that the MPS2 stack control room atmospheric dispersion factors (/Q values) were approved as part of MPS2 Amendment No. 228. The NRC staff agrees that these values were found acceptable for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the postulated release. The /Q values in Table 1.3-4 for the 24-96 hour and 96-720 hour time periods are larger than the values approved as part of Amendment No. 228. Were these values calculated using the 1997-2001 (more recent) meteorological data and, since they are more limiting, are they being proposed to replace the Amendment No. 228 /Q values for the 24-96 hour and 96-720 hour time periods?
- 6. Technical Specification sections 4.3.4.2 and 3.4.3.4, related to the containment purge valve isolation signal, are proposed for deletion. Both contain the same two X/Q values.
Please confirm that reference to these values are in these two sections only, that is, deletion of the X/Q values would not impact other parts of the Technical Specifications, plant procedures, etc.
- 7. DNC is seeking credit for an operator action. In particular, for a main steamline break outside containment (in the enclosure building or turbine building), operator action will be prompted to isolate the control room within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> from the start of the event. The following information is required.
- a. What specific switch manipulations will be required to isolate the control room?
Are the switches and the components they operate safety-grade and with safety-grade support systems (e.g., DC control power, AC motive power, air motive power)?
- b. Where will the switch manipulations occur?
- c. Who will perform the manipulations required to isolate the control room?
- d. What alarms/indications will be used in response to a main steamline break outside containment to prompt the action to isolate the control room? Where are these alarms and indicators located? Are these alarms and indications safety-grade and powered from safety-grade electrical power supplies?
- e. What alarms/indications will be used to verify success in isolating the control room? For example, damper position indicating lights, flow indicators, alarms occurring or clearing, etc. Where are these alarms and indications located? Are these alarms and indications safety-grade and powered from safety-grade electrical power supplies?
- f. How will the operator action to isolate the control room in response to a main steamline break outside containment be incorporated into plant procedures?
- g. How will this new operator action to isolate the control room in response to a main steamline break outside containment be incorporated into your training programs?
