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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
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Text
July 30, 2002 MEMORANDUM TO: Jacob I. Zimmerman, Acting Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Sr. Project Manager, Section 2 /RA/
Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation
SUBJECT:
MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2, FACSIMILE TRANSMISSION, ISSUES TO BE DISCUSSED IN AN UPCOMING CONFERENCE CALL (TAC NO. MB3386)
The attached information was transmitted by facsimile on July 25, 2002, to Mr. Ravi Joshi of Dominion Nuclear Connecticut, Inc. (the licensee). This information was transmitted to facilitate a upcoming conference call in order to clarify the licensees submittal dated November 6, 2001, as supplemented December 27, 2001, and July 15, 2002. In the submittal, the licensee requested a revision to the Millstone Nuclear Power Station, Unit No. 2 Technical Specifications associated with the spent fuel pool. This memorandum and the attachment do not convey a formal request for information or represent an NRC staff position.
Docket No. 50-336
Attachment:
Issues for Discussion in Upcoming Telephone Conference
July 30, 2002 MEMORANDUM TO: Jacob I. Zimmerman, Acting Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Sr. Project Manager, Section 2 /RA/
Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation
SUBJECT:
MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2, FACSIMILE TRANSMISSION, ISSUES TO BE DISCUSSED IN AN UPCOMING CONFERENCE CALL (TAC NO. MB3386)
The attached information was transmitted by facsimile on July 25, 2002, to Mr. Ravi Joshi of Dominion Nuclear Connecticut, Inc. (the licensee). This information was transmitted to facilitate a upcoming conference call in order to clarify the licensees submittal dated November 6, 2001, as supplemented December 27, 2001, and July 15, 2002. In the submittal, the licensee requested a revision to the Millstone Nuclear Power Station, Unit No. 2 Technical Specifications associated with the spent fuel pool. This memorandum and the attachment do not convey a formal request for information or represent an NRC staff position.
Docket No. 50-336
Attachment:
Issues for Discussion in Upcoming Telephone Conference DISTRIBUTION PUBLIC CLauron RGiardina PDI-2 Reading ASmith TAttard JZimmerman REnnis YDiaz ACCESSION NO.: ML022100043 OFFICE PDI-2/PM NAME REnnis DATE 7/29/02 OFFICIAL RECORD COPY
ISSUES FOR DISCUSSION IN UPCOMING TELEPHONE CONFERENCE REGARDING PROPOSED AMENDMENT TO TECHNICAL SPECIFICATIONS SPENT FUEL POOL REQUIREMENTS MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 DOCKET NO 50-336 By application dated November 6, 2001, as supplemented December 27, 2001, and July 15, 2002, Dominion Nuclear Connecticut, Inc. (the licensee) submitted a proposed amendment to the Technical Specifications (TSs) associated with the spent fuel pool (SFP) for Millstone Nuclear Power Station, Unit No. 2 (MP2). Specifically, the licensee has proposed changes that would increase the nominal average fuel assembly enrichment for all regions of the SFP, the new fuel storage racks (dry), and the reactor core; allow fuel to be stored in previously blocked fuel cells; credit SFP soluble boron for reactivity control during normal conditions, and reduce the boraflex reactivity credit in Regions A and B of the SFP. The Nuclear Regulatory Commission (NRC) staff has reviewed your submittals and would like to discuss the following issues:
- 1. How long have RACKLIFE and destructive examinations of poison panels been conducted? At what frequency are each completed?
- 2. What were the initial assumptions (including the escape coefficient) in RACKLIFE used to support the selection for the first poison panel subjected to destructive examination?
- 3. What assumptions in RACKLIFE have been modified to ensure that the predictions reflect the changes in the SFP parameters (e.g., chemistry) and actual Boraflex degradation?
- 4. The SFP racks in Regions A and B contain Boraflex in a flux trap design. However, Region B has 40 storage locations which are empty and blocked for reactivity control.
How are the differences in these two regions modeled in the RACKLIFE code?
- 5. Are RODLETS used only in Region C of the SFP and not in Regions A and B?
- 6. RACKLIFE is used to predict the remaining B-10 in the panels. In addition, the Boraflex panel with the highest predicted gamma dose and predicted Boraflex degradation value is destructively tested to determine the amount of B-10 remaining in the panel.
- a. How do the results of the destructive tests compare with the RACKLIFE predictions? How are these results tracked?
- b. How are the results of the destructive tests factored into future RACKLIFE projections?
- 7. After determining the Boraflex panel to be removed and destructively tested, the licensee does not discuss its replacement.
- a. Is the destructively tested Boraflex panel that is removed replaced? If so, with what material?
- b. How is the removal of the Boraflex panel destructively tested factored into RACKLIFE?
- c. How does the removal of this Boraflex panel affect the future placement of fuel in this storage rack?
- 8. With respect to your submittal dated July 15, 2002, the response to question 1d states that 4 sections of near full Boraflex width were removed for B-10 density measurements.
In addition, the submittal states: 4 sections were chosen to avoid the top and bottom 2 feet of the boraflex... Also sections of Boraflex were chosen if they showed thinned areas... testing was performed by selecting 32 random locations, and 1 specific location for a section that showed some minor thinning.
- a. What were the constraints that formed the basis for the 32 random locations tested on the 4 Boraflex panels?
- b. What was the tested area length for each of the 33 locations tested?
- 9. With respect to your submittal dated July 15, 2002, the response to question 2 states:
Cell blockers serve no function other than to provide a visible cue to the fuel handler that the fuel should not be inserted in that location.
- a. What is the purpose of the cell blocker if fuel will be stored beneath it?
- b. Will all fuel storage cells be blocked if fuel is stored beneath them?
- 10. Placing spent fuel underneath the cell blockers is something that hasn't been done before at MP2. The cell blockers weight about 20 pounds and are made of stainless steel. Has the licensee evaluated the possibility and subsequent consequences of cell blockers falling on the spent fuel?
- 11. The staff would also like to discuss the following:
a) criticality analysis for the new fuel storage vault and transfer machine as described on pages 11 and 12 of Attachment 1 in your submittal dated November 6, 2001; and b) responses to questions 6 and 8 in your submittal dated July 15, 2002.
