Letter Sequence Other |
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TAC:MB6108, Increase the Completion Time When the Core Reactivity Balance is Not within Limit, Consolidate Specification 3.1.5 Actions to Restore Misaligned Ceas, TSTF-67 (Approved, Closed) |
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MONTHYEARML0302801242003-01-28028 January 2003
RAI, Reactivity Control Systems, Power Distribution Limits, & Special Test Exceptions
Project stage: RAI
ML0310501532003-04-15015 April 2003
Facsimile Transmission, Issues to Be Discussed in an Upcoming Conference Call
Project stage: Other
ML0317100302003-06-20020 June 2003
Facsimile Transmission, Issued to Be Discussed in an Upcoming Conference Call
Project stage: Other
ML0326913862003-09-17017 September 2003
Amended TS Pages Reactivity Control Systems, Power Distribution Limits, and Special Test Exceptions
Project stage: Other
ML0321300142003-09-25025 September 2003
License Amendment, Issuance of Amendment, Reactivity Control Systems, Power Distribution Limits, and Special Test Exceptions
Project stage: Approval
ML0331100272003-11-24024 November 2003
Correction to Safety Evaluation Related to Amendment 280: Reactivity Control Systems, Power Distribution Limits, and Special Test Exceptions
Project stage: Approval
2003-04-15
[Table View] |
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Category:Memoranda
MONTHYEARML22130A1702022-05-20020 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
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ML0710201942007-04-24024 April 2007
Draft Open Items from Staff Audit of Corrective Actions to Address Generic Letter 2004-02
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Facsimile Transmission, Draft Request for Additional Information Regarding Steam Generator Tube Integrity
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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
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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
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ML0619500092006-07-14014 July 2006
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ML0617805592006-07-10010 July 2006
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ML0617701952006-06-26026 June 2006
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ML0606702532006-03-24024 March 2006
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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
ML0528500672005-10-25025 October 2005
Facsimile Transmission RAI to Be Discussed in an Upcoming Conference Call
2022-05-20
[Table view] |
Text
April 15, 2003 MEMORANDUM TO: James W. Clifford, Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Senior Project Manager, Section 2 /RA/
Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation
SUBJECT:
MILLSTONE POWER STATION, UNIT NO. 2, FACSIMILE TRANSMISSION, ISSUES TO BE DISCUSSED IN AN UPCOMING CONFERENCE CALL (TAC NO. MB6108)
The attached information was transmitted by facsimile on April 15, 2003, 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 amendment request dated August 14, 2002, as supplemented on March 11, 2003. The proposed amendment would revise the Technical Specifications related to reactivity control systems, power distribution limits, and special test exceptions.
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
April 15, 2003 MEMORANDUM TO: James W. Clifford, Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Senior Project Manager, Section 2 /RA/
Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation
SUBJECT:
MILLSTONE POWER STATION, UNIT NO. 2, FACSIMILE TRANSMISSION, ISSUES TO BE DISCUSSED IN AN UPCOMING CONFERENCE CALL (TAC NO. MB6108)
The attached information was transmitted by facsimile on April 15, 2003, 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 amendment request dated August 14, 2002, as supplemented on March 11, 2003. The proposed amendment would revise the Technical Specifications related to reactivity control systems, power distribution limits, and special test exceptions.
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 JClifford SPeters PDI-2 Reading REnnis KKavanagh ACCESSION NO.: ML031050153 OFFICE PDI-2/PM NAME REnnis DATE 4/15/03 OFFICIAL RECORD COPY
ISSUES FOR DISCUSSION IN UPCOMING TELEPHONE CONFERENCE REGARDING PROPOSED AMENDMENT TO TECHNICAL SPECIFICATIONS REACTIVITY CONTROL SYSTEMS, POWER DISTRIBUTION LIMITS, AND SPECIAL TEST EXCEPTIONS MILLSTONE POWER STATION, UNIT NO. 2 DOCKET NO. 50-336 By letter dated August 14, 2002, as supplemented on March 11, 2003, Dominion Nuclear Connecticut, Inc. (DNC or the licensee), submitted a proposed amendment to the Technical Specifications (TSs) for Millstone Power Station, Unit No. 2 (MP2). The proposed amendment would revise the MP2 TSs related to reactivity control systems, power distribution limits, and special test exceptions.
By letter dated January 28, 2003, the Nuclear Regulatory Commission (NRC) staff provided a Request for Additional Information (RAI) to DNC with respect to the submittal dated August 14, 2002. The licensee provided a response to the RAI by letter dated March 11, 2003. The NRC staff has reviewed the information the licensee provided that supports the proposed TS changes and would like to discuss the following issues to clarify the submittals.
- 1. Your RAI response dated March 11, 2003, does not fully answer question 2. Specifically, your current TSs (CTS), Limiting Condition for Operation (LCO) 3.1.3.1 and Surveillance Requirement (SR) 4.1.1.1.1.a contain action statements for control element assemblies (CEAs) that are immovable but trippable. Your proposed LCO 3.1.3.1 states that all CEAs shall be OPERABLE. TS 1.6 indicates that the CEAs would be inoperable when they or any support system were incapable of performing their specified functions. In automatic control, a function of the CEAs would be to move in order to regulate core reactivity. An immovable CEA would, therefore, be considered inoperable. However, your proposed LCO 3.1.3.1 no longer contains action statements for rods that are immovable but trippable. Therefore, following your TS logic, an immovable but trippable CEA would require your plant to enter LCO 3.0.3 for shutdown. Your CTS, on the other hand, allow for operation of up to 7 days in this condition. Do you intend to force your plant into TS 3.0.3 for an immovable but trippable CEA? If not, provide a justification for removal of the operation limits for immovable but trippable CEAs.
- 2. Your RAI response dated March 11, 2003, does not fully answer question 3. Why is it necessary to increase your initial SR 4.1.1.1.2 requirement of 31 effective full power days (EFPDs) to 60 EFPDs? What is the safety significance of this change? Provide a safety justification.
ATTACHMENT
- 3. Your RAI response dated March 11, 2003, to question 4 indicates that the verification of shutdown margin (SDM) in SR 4.1.1.1.1.c is not necessary because the core reload design process calculates the SDM when the rods are at their insertion limits. By this logic, SR 4.1.1.1.1.c was never necessary in the life of the plant. If not, what is the purpose of SR 4.1.1.1.1.c? If you delete SR 4.1.1.1.c, how will this purpose be satisfied? What is the safety significance of the deletion?
- 4. Your RAI response dated March 11, 2003, to question 5 indicates that the wording difference between the proposed and current LCO 3.1.3.1 does not change its requirements. However, in the original LCO 3.1.3.1, the maximum separation of any CEA with respect to any other CEA would be 10 steps. In the proposed LCO, on the other hand, this difference could be up to 20 steps (i.e., one CEA 10 steps below group position and one CEA 10 steps above group position). With this condition, you would still be in compliance with the TS but would be less conservative. Provide a justification for this change.
- 5. Your RAI response dated March 11, 2003, to question 8 appears inaccurate in that you state the plant could operate for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> at 100% power with FTr outside its limit when in LCO 3.2.4.b. However, LCO 3.2.4.b states that you can only operate for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> with FTr inside its limit while Tq > 0.10 (with FTr outside its limits, you would have to enter TS 3.0.3).
After the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> period, you must reduce power to less than or equal to 20% of maximum allowable thermal power. Clarify your safety justification given the above information and given that the Standard TSs only allow 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to verify FTr. Furthermore, with Tq > 0.10, your current TS 3.2.4.b, only allows continuous operation at 20% power or below. However, your proposed TS 3.2.4.b.3 would allow continuous operation at 50% power or below with Tq > 0.10. Provide a safety justification for this change.
