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MONTHYEARML0207100122002-03-0707 March 2002 Memo to File Facsimile Transmission, Draft Request for Additional Information (RAI) to Be Discussed in an Upcoming Conference Call (Tac No. MA3125) Project stage: Draft RAI ML0216101662002-06-0707 June 2002 Request for Additional Information, Facsimile Transmission, Draft Request for RAI to Be Discussed in an Upcoming Conference Call Project stage: Draft RAI 2002-03-07
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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 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 ML0528500672005-10-25025 October 2005 Facsimile Transmission RAI to Be Discussed in an Upcoming Conference Call 2022-05-20
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23318A0952023-11-14014 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 ML15349A8312016-01-0808 January 2016 Request for Additional Information License Amendment Request to Adopt Dominion Core Design and Safety Analysis Methods ML15337A1512015-12-0303 December 2015 NRR Email Capture - Millstone Unit 2 Request for Additional Information ML15279A1092015-10-0606 October 2015 NRR e-mail Capture - Millstone Power Station, Unit 3, NRC Staff Request for Additional Information - Relief Request Nos. IR-3-19,3-20,3-21 ML15275A1432015-10-0202 October 2015 2015/10/02 E-mail from R.Guzman to W.Craft - Follow-up Request for Additional Information TSTF-523, Revision 2, GL 2008-01, Managing Gas Accumulation 2023-07-18
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Text
March 7, 2002 MEMORANDUM TO: James W. Clifford, Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM: Victor Nerses, Sr. Project Manager /RA/
Project Directorate I, Section 2 Division of Licensing Project Management Office of Nuclear Reactor Regulation
SUBJECT:
MILLSTONE NUCLEAR POWER STATION, UNIT 3, FACSIMILE TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION (RAI) TO BE DISCUSSED IN AN UPCOMING CONFERENCE CALL (TAC NO. MA3125)
The attached draft RAI was transmitted by facsimile on March 7, 2002, to Mr. Ravi Joshi of Dominion Nuclear Connecticut, Inc. (DNC). This draft RAI was transmitted to facilitate an upcoming conference call in order to clarify the licensees application dated October 1, 2001, regarding emergency diesel generator allowed outage time. Review of the RAI would allow DNC to determine and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not convey a formal request for information or represent an NRC staff position.
Docket No. 50-423
Enclosure:
Draft Request for Additional Information
March 7, 2002 MEMORANDUM TO: James W. Clifford, Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM: Victor Nerses, Sr. Project Manager /RA/
Project Directorate I, Section 2 Division of Licensing Project Management Office of Nuclear Reactor Regulation
SUBJECT:
MILLSTONE NUCLEAR POWER STATION, UNIT 3, FACSIMILE TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION (RAI) TO BE DISCUSSED IN AN UPCOMING CONFERENCE CALL (TAC NO. MA3125)
The attached draft RAI was transmitted by facsimile on March 7, 2002, to Mr. Ravi Joshi of Dominion Nuclear Connecticut, Inc. (DNC). This draft RAI was transmitted to facilitate an upcoming conference call in order to clarify the licensees application dated October 1, 2001, regarding reactor coolant system heat-up and cool down curves. Review of the RAI would allow DNC to determine and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not convey a formal request for information or represent an NRC staff position.
Docket No. 50-423
Enclosure:
Draft Request for Additional Information DISTRIBUTION:
PDI-2 Rdg PUBLIC JSchiffgens, SPSB VNerses Accession No.: ML020710012 OFFICE PDI-2/PM SC/SPSB NAME VNerses FMReinhart DATE 3/7/02 3/7/02 OFFICIAL RECORD COPY
DRAFT REQUEST ADDITIONAL INFORMATION Concerning the Millstone Unit 3 License Amendment Request (LAR) for a Permanent Technical Specifications (TS) Modification to Extend Allowed Outage Times (AOTs) of the Limiting Condition for Operation (LCO) 3.8.1 This RAI is concerned only with the risk-informed aspect of the LAR and consists of two parts; introductory comments and specific requests. The former is to aid in preparing the response to the latter.
Comments:
- 1. In evaluating the risk associated with changes to an LCO AOT the NRC staff considers both the average risk of normal operation after the change compared to that before, and the risk of operation during the new allowed outage compared to average risk of normal operation. In the former, the impact of the change in AOT is incorporated into the quantitative risk estimate through the change in the maintenance unavailability of affected equipment. In the latter, which is more important to the evaluation, the impact is incorporated into the estimate by considering the plant risk configuration during the specific AOT. The risk of operation during the AOT is estimated by setting the unavailabilities of all equipment out of service (EOOS) to one. In addition to consideration of internal events, the impact of a proposed change on risks from fire and external events needs to be evaluated. The staff is also interested in, and considers when available, the risk of shutting down the plant to complete maintenance compared to the normal risk of shutting down the plant.
- 2. Maintenance associated with LCO allowed outages falls essentially into two categories, preventative or planned maintenance and corrective or unplanned maintenance. AOTs (or completion times, CTs) for LCOs were initially set to reasonably accommodate corrective maintenance of inoperable equipment important to plant safety, and entering LCOs for preventative maintenance at power was discouraged. The development of comprehensive risk assessment techniques have changed matters somewhat by allowing licensees to identify specific conditions under which preventative maintenance would be done, analyze the risk associated with these conditions before hand and, if the risk is small for the planned outage time, to voluntarily enter an LCO with reasonable confidence of safe operation. However, corrective maintenance on the same equipment, which by definition is unplanned, is another matter. Assuming preventative is planned for - and performed with - the plant in the minimum risk configuration, the corrective maintenance will have a risk equal to or greater than that for preventative maintenance; how much greater depends on the unavailability of other risk significant equipment when the LCO is entered. A licensee cannot specify the risk configuration of a plant for corrective maintenance before hand since there is no way to anticipate when specific equipment will become inoperable, consequently, no way to predict the risk for an associated AOT. Hence, the difficulty with using risk assessment, quantitative or
qualitative, to justify or extend allowed outage times of LCOs ahead of time. The problem is compounded by the proliferation and extension of preventative maintenance activities at power. As the frequency and length of AOTs for risk significant equipment increase, the probability of overlap (inadvertent and planned) increases, with an associated magnification of risk. The staff is concerned with increases in risk associated with equipment outage overlap, in particular in connection with AOT extensions.
Requests:
- 1. The interface of Units 2 and 3 electrical systems described in Attachment 1 appears to provide considerable redundancy, but also seems complex. Provide clarification concerning the following: (a) Does Unit 2 provide a backup source of emergency power for Unit 3? (b) Since Unit 3 provides an alternate source of AC power (via NSST, RSST, or EDGs) for Unit 2, what would be the impact of the proposed AOT change on incremental conditional risk estimates for Unit 2? (c) What is the impact on Unit 3 risks when a Unit 2 EDG is declared inoperable? (d) Can the Station Blackout Diesel Generator (SBO DG) completely substitute for EDG A or EDG B (or Unit 2 EDGs)? If not, what equipment is powered by the SBO DG? (e) Is the availability of the SBO DG comparable to EDGs A and B? (f) The attachment states that prior to application of the extended EDG AOT the availability of the SBO DG will be verified by test; why not verify the availability of the other EDG by test instead (or also)? (g) In the changes to Required Action statements, isnt it somewhat confusing to refer to the verifications as verify ... operable when it appears to be only a verification of not in maintenance and assumption of operability?
- 2. With regard to incremental conditional risk estimates (Tier 1):
(a) It is noted that Table 2 in Attachment 5 lists the contribution to the average core damage frequency for internal events, including internal flooding and fire, as well as seismic events. However, contributions form internal flooding, fire, and seismic events do not appear to have been included in the incremental conditional risk estimates for operation during allowed outage. Discuss the impact of the proposed change in AOT on these risks and the estimated total ICCDP and ICLERP.
(b) If the estimated risks (ICCDP or ICLERP) exceed the staffs definition of what constitutes a small increase, discuss the factors responsible for the estimated values and what could be done to reduce the risk (beyond those contingencies already proposed for the TS, as appropriate).
(c) With regard to the compensatory measure of staging a spare charging pump for emergency use in RCP seal cooling, the attachment states that the PRA model was altered to take the action into account in calculating the ICCDP and ICLERP; describe briefly what was done to the model and what would have been the risks without the compensatory measure.
- 3. With regard to Avoidance of Risk Significant Plant Configurations (Tier 2), Attachment 5 states that Millstone identifies potential high risk configurations that could exist if equipment in addition to that associated with the change were taken out of service simultaneously. To help the NRC staff appreciate the risks involved:
(a) For the most risk significant EDG out of service for maintenance, prepare a table showing the estimated the risk importances (e.g., RAWs) of remaining risk significant equipment (include in the list the associated allowed outage times);
(b) From the list of equipment that could cause the change in risk associated with the change in AOT to significantly exceed what the staff considers small for a single TS AOT change, select the most important (from those permitted to be inoperable by LCO AOT for, say, more than a day) which plant experience (e.g., as observed in the plant log) shows to have some out of service frequency (attempt to make the choice realistic, reflecting plant practices), and with it and the EDG out of service, re-estimate the risk for the AOT; and (c) Provide assurances that the risks associated with the LCO AOT for corrective maintenance will be kept comparable with that which the staff considers small for a single TS AOT for preventative maintenance.
- 4. Attachment 5 makes reference to a Configuration Risk Management Program (CRMP) in connection with the controlling and limiting risk during AOTs (Tier 3).
(a) Since significant increases in LCO AOTs, such as those proposed, significantly increase the window during which other risk significant equipment can become inoperable (inadvertently or planned), discuss the potential risk from overlapping equipment outages based on the Millstone 3 plant log and current AOTs and planned or proposed AOT extensions (e.g, discuss of the risk profile for the past cycle, showing maximum, minimum and mean risks that would result from having the EDG out of service at specific times for the proposed AOT);
(b) Provide copies of the administrative procedure and/or operational support procedure used to implement CRMP; (c) If not dealt with in the procedures, discuss the controls that limit at power preventative maintenance outage times and frequencies; (d) If not dealt with in the procedures, discuss application of the programs, or similar procedures, to corrective maintenance and emergent EOOS (unless already discuss in response to 2.c) - it is noted that the reassuring contingency measures discussed in the attachment and the proposed TS Bases, and limitations on voluntary entry, are not applicable to corrective maintenance; (e) If the procedures do not contain quantitative criteria used by Millstone 3 in making decisions on when a risk is small, and what level of risk (not color codes) triggers specific operational actions (not managerial levels of approval) together with the action associated with each level (e.g., discuss the point at which Millstone 3 would voluntarily reduce the maintenance time to less than the LCO AOT or shut down the plant), provide the information, and include discussion of qualitative considerations used by Millstone 3; and
- 5. Attachment 5 contains comments on the Millstone 3 PSA Peer Review.
(a) Provide a copy of the summary and conclusions sections (or their equivalent, say a recommendations section) of the review report; and (b) If not provided in the report, provide a discussion of the scope and purpose of the review.