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Category:Meeting Summary
MONTHYEARML23257A2412023-09-19019 September 2023
Summary of August 15, 2023, Pre-submittal Teleconference with Entergy Operations, Inc. to Discuss Proposed License Amendment Request Concerning Pressurizer Heaters for Arkansas Nuclear One, Unit 1
ML23047A3822023-03-21021 March 2023
Summary of December 15, 2022 Periodic Advanced Reactor Stakeholder Public Meeting
ML22215A1912022-08-0909 August 2022
Summary of July 13, 2022, Teleconference Meeting with Entergy Operations, Inc. to Discuss Planned License Amendment Requests to Adopt Technical Specifications Task Force (TSTF) Traveler 505, Risk-Informed Extended Completion Times
ML22147A0932022-06-0606 June 2022
2021 Annual Assessment Public Meeting Summary
ML22151A1302022-06-0202 June 2022
May 10, 2022, Summary of Teleconference Meeting W/Entergy Operations, Inc. to Discuss a Planned Alternative for a One-Time Schedule Extension for the In-Service Examination of Control Rod Drive Mechanism Penetration No. 1 in the Reactor Ves
ML22125A2452022-05-0909 May 2022
May 3, 2022, Summary of Teleconference Meeting with Entergy Operations, Inc. to Discuss Proposed License Amendment Request for ANO, Units 1 & 2 Regarding Proposed Revision to Emergency Plan and On-Shift Staff Analysis
ML22003A0562022-01-10010 January 2022
Summary of December 16, 2021, Presubmittal Teleconference with Entergy Operations, Inc. to Discuss Proposed Amendment Request Concerning TS 3.4.4, RCS Loops, Modes 1 and 2, for Arkansas Nuclear One, Unit 1
ML21323A0472021-12-0606 December 2021
Summary of Public Meeting on November 5, 2021, with the National Organization of Test, Research, and Training Reactors on Operator Licensing for Research and Test Reactors
ML21288A0392021-10-18018 October 2021
September 14, 2021, Summary of Public Workshop on Scale/Melcor Source Term Demonstration Project - Pebble-Bed Molten-Salt-Cooled Reactor
ML21181A3352021-07-0101 July 2021
June 23, 2021, Summary of Public Meeting to Discuss Technology Inclusive Content of Application Project
ML21158A2232021-06-0808 June 2021
Meeting Summary for Ticap Workshop 3
ML21140A3892021-05-24024 May 2021
Riv Column 1 EOC 2020 Public Meeting Summary
ML21132A2952021-05-14014 May 2021
Summary of Public Meeting to Discuss Technology Inclusive Content of Application Project
ML21117A0262021-05-0505 May 2021
Summary of Teleconference with Entergy Operations, Inc. to Discuss Forthcoming LAR Concerning Reactor Coolant System Primary Activity and Primary-to-Secondary Leak Rate
ML20337A1572020-12-0808 December 2020
Summary of Teleconference Meeting with Entergy Operations, Inc. to Discuss the Forthcoming Supplemental Response Concerning Generic Letter 2004-02 for Arkansas Nuclear One, Units 1 and 2
ML20287A4012020-10-26026 October 2020
Summary of September 17, 2020, Meeting with Entergy to Discuss Proposed License Amendment Request for Arkansas Nuclear One, Units 1 and 2 Request to the Extend Allowable Outage Time for the Emergency Cooling Pond
ML20260G9992020-09-16016 September 2020
Summary of August 4, 2020, Teleconference Meeting with Entergy Operations, Inc. to Discuss Proposed License Amendment Request for Arkansas Nuclear One, Units 1 and 2 Regarding Adoption of 10 CFR 50.69
ML20189A2832020-07-0707 July 2020
Summary of Region IV Annual Assessment Public Meeting
ML20153A2252020-06-0404 June 2020
April 29, 2020, Summary of Meeting with Entergy Operations, Inc. to Discuss a Proposed Relief Request Use of Carbon Fiber Reinforced Polymer Piping for Underground Service Water Piping at Arkansas Nuclear One, Units 1 and 2
ML19182A0332019-07-10010 July 2019
Summary of Teleconference with Entergy Operations, Inc. Regarding Proposed License Amendment Request Revised Fuel Handling Analysis and Adoption of Various TSTF Travelers for Arkansas Nuclear One, Unit 2
ML18176A1312018-06-21021 June 2018
Summary of Annual Assessment Meeting with Entergy Operations, Inc., Regarding 2017 Performance of Arkansas Nuclear One
ML18107A4972018-04-27027 April 2018
April 10, 2017, Summary of Public Meeting with Entergy Nuclear Operations, Inc. Regarding Upcoming License Amendment Request to Add Setpoint Verification Requirement to Technical Specification Surveillance Requirements
ML18099A0712018-04-16016 April 2018
March 20, 2018, Summary of Meeting with the Nuclear Energy Institute and Other Industry Representatives Regarding the Surveillance Frequency Control Program
ML17353A1542017-12-22022 December 2017
Summary of Public Meeting with Entergy Operations, Inc., on Proposed Changes to Emergency Plans to Revise Emergency Action Levels for Arkansas; Grand Gulf; River Bend; and Waterford (EPID-L-2017-LRM-0060)
ML16109A3642016-04-18018 April 2016
Summary of Meeting to Discuss Supplemental Inspection Results and Annual Assessment Meeting with Entergy Operations Inc. Regarding 2015 Performance of Arkansas Nuclear One
ML15348A1882016-01-0606 January 2016
Summary of October 28, 2015, Closed Meeting Between Representatives of the U.S. Army Corps of Engineers, U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc. to Discuss Flood Analysis Associated with Arkansas Nuclear One,
ML15267A4182015-09-24024 September 2015
Summary of Meeting to Discuss Arkansas Nuclear One Performance Improvement
ML15225A2542015-08-14014 August 2015
Summary of 4/20-23/2015 Audit in Support of Request to Adopt National Fire Protection Association NFPA 805, Performance-Based Standard for Fire Protection for LWR Generating Plants (2001 Edition)
ML15132A1752015-05-21021 May 2015
Summary of Annual Assessment Meeting with Entergy Operations Inc., Regarding ANO 2014 Performance
ML15089A1642015-04-27027 April 2015
Summary of February 25, 2015, Partially Closed Meeting with Industry Stakeholders Regarding the Babcock and Wilcox Loss of Coolant Accident Evaluation Model Analysis
ML15007A4782015-01-15015 January 2015
Summary of July 15-18, 2013, Arkansas Nuclear One, Unit 2, Audit Associated with License Amendment Request to Transition to National Fire Protection Association Standard 805
ML14356A1722014-12-22022 December 2014
Summary of Site Audit to Support the Review of a License Amendment Request for Arkansas Nuclear One, Unit 2 to Transition to the National Fire Protection Association (NFPA) Standard 805 Fire Protection Licensing Basis
ML14197A5832014-09-18018 September 2014
Summary of the June 19, 2014, Category 1 Public Meeting with Entergy to Discuss Seismic Hazard Reevaluations Associated with Implementation of Japan Lessons-Learned Near-Tear Task Force Recommendation 2.1
ML14259A5972014-09-16016 September 2014
Summary of Annual Performance Assessment Meeting for Arkansas Nuclear One Performance
ML14213A4272014-09-12012 September 2014
Summary of July 16, 2014, Closed Meeting Between Representatives of the U.S. Army Corps of Engineers Nuclear Regulatory Commission, and Entergy Operations Inc. to Discuss Flooding Analysis Associated with Arkansas Nuclear One, Units 1 and 2
ML14162A3712014-06-26026 June 2014
5/22/2014 Summary of Meeting with Entergy Operations, Inc. to Discuss Flooding Hazard Reevaluation Extension Request for Arkansas Nuclear One, Units 1 and 2; Near-Term Task Force Recommendation 2.1
ML14170A0602014-06-23023 June 2014
Summary of 5/27/2014 Conference Call Regarding Refueling Outage Steam Generator Inspection
ML14163A0502014-06-13013 June 2014
Summary of Conference Call with Arkansas Nuclear One, Unit 2, Regarding the Spring Steam Generator Inspections
ML14128A5122014-05-0909 May 2014
Summary of Regulatory Conference to Discuss Safety Significance of Arkansas Nuclear One Unit 1 Dropped Stator
ML13172A0292013-07-0909 July 2013
Summary of 5/10/2013 Conference Call with Entergy Operations, Inc., 2013 Steam Generator Tube Inspections at Arkansas Nuclear One, Unit 1
ML13142A2272013-05-22022 May 2013
Summary of Public Meeting to Discuss Results of Augmented Inspection at Arkansas Nuclear One
ML13043A6112013-02-26026 February 2013
Summary of 1/25/2013 Conference Call Regarding the Upcoming 2013 Steam Generator Tube Inspections
ML12276A3012012-10-12012 October 2012
Summary of October 25, November 8, and November 10, 2011, Conference Calls Related to Fall 2011 Refueling Outage Steam Generator Tube Inspections
ML12275A5492012-10-0101 October 2012
Summary of Meeting with Entergy Operations, Inc., to Discuss the Performance of the Subject Facilities, Recent Organizational Changes, and Current Regulatory Issues
ML12240A4162012-08-27027 August 2012
Public Meeting with Entergy Operations, Inc to Discuss the Performance of the Subject Facilities and Current Regulatory Issues
ML12222A0312012-08-0808 August 2012
Arkansas Monitoring Call Summary
ML12171A3662012-07-16016 July 2012
6/12-13/2012 Summary of Meeting at the Plant Site in Russellville, AR, to Discuss Entergy Operations, Inc.'S License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805 at Arkansas Nuclear One, Unit 2
ML1202704162012-02-13013 February 2012
1/26/2012 - Summary of Meeting with Entergy and Exelon to Discuss Recent Once-Through Steam Generator Inservice Inspection Results
ML1127903812011-11-0101 November 2011
Summary of Meeting with Entergy Operations, Inc. to Discuss Amendment Request to Revise Arkansas Nuclear One, Unit 2's Fuel Handling Accident (FHA) Analysis and Several TSTFs 51, 272, 286, and 471 That Support FHA
ML1117906392011-06-28028 June 2011
Summary of Meeting with Entergy Operations Inc
2023-09-19
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SUMMARY
OF MEETING WITH ANO I L !, I., % -, ,If
- t. *'Relied on defih's from RG 1.189 associated circuits Lk F I
-i .. emergency control station I.I free of fre dan a e v Lcx r 1
V-1ul 21982 Mattson iif < shuto081 c" cc-i--
allowable rpii~ civ aesud ~ Il' i/July, 1, 1982 Appendix R compliance reviewx-.,V%' x (U' I '
.~~~f ~ ~Fa_ ctions to comply with IIGI . C-Ct '
N143 fire zones I LA 1~~I00 comply with Appendix R
~i4 of the 100 rlied on manual actions to meet IIIGI alternate shutdown zones (111G3) were identified in Appendices A & B C L,/A ecting ~~on alternate safe shiutdown c.\m. .--
,qustinedthe14 zones -that relied on manual actions
~,'eetig summyissued Septdmbcf 1982.
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/ saffaskd fr wvritten discussion of the mebodology being employed
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/ methodology discussion provided -c-> cev;-(P j~C Y\:L
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,/treated safe shutdown for IIIGI and altermae II1G3 compliance -
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the component to be operated is not in affected fire zone.-
sufficient time to performn the required action is available - .
personnel beyond fire brigade are available '-I L
examples of the various fire zones wer8 provided one that required an exemption (43) one that met Appendix R (100) one that relied on manual actions (110)
Nuclear Utility Fire Protection Group Meeting March 16, 1983 summary dated March 28, 1983 mm J .. Taylor's answers on the inspection process
~Leon Whtnej~' vas also i attendance accepted the ASB position on mianual actions for associated circuits -
I&E Manual 25 15/62, Rev I Inspection bf SSD equirements section HIG looked at both alternative and redundant safe tdw ars.. _
- SECY 83-269 dated July5,l1983-PnA t ~kk -L allowable repairs to achieve safe suldowvn referenced Mattson memo
( allowed manuial actions to comply with IIIGI
- discussion of fire zones and fire areas pursuant to GL 83-33
- regional workshops held in spring of 1984
- CEB guidance (free of fire damage) for llIGI compliance
- AprIl 27, 1984 meeting with ANO sunimary dated June 5, 18 ~~~
methodology appeared to be consistent wvith staff position
- reaqalyis agaiist IG, J, &OCi's(Y( I credit taken for manual operation of valves not invicinitoffr
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Total CDF 1. -UH (a)Severity Factors. S. ,f,r.e,seyeqityfactor is a fractional value (between 0 and 1)that is used to adjust fire frequency estimates to reflect some specific mitigating pattern of.Y behaviorof the fire event. ..The severity factor is applied to reflect a split in large versus small fires. " neAge.ic ,of.plant-specific information,.theseverityfactors forjlei,_v,.
'7 electrical cabinets, ventilation syster~p and fire ,proitioq panels were b ased. or;heag.E Fjg6.e,?PAmplementatiQn Guide (FP P e),oDecember.1 995 (Section D.3). .The FP.RAIG.,
spyprItyJactors ranged from.8OM taland engine ing ju*Jgrent. wasused tQdetermine. ai In the case of the electrical cabinets attery c gers in fire zone 98-J, the EPRI FPRAIG did not Drovide specific erity facto alues for electrical cabinets and battery t
d~pi chargersAnite li'a,# building t ofg ; v-o.a.sth t~~~~yi __an~l~si_ pa a , i Probability of automatic suppression system being unavailable, P1 - As discussed in Section 3(b), the probability of pre-action sprinkler system in fire zone 98-J being unavailable is assumed to be 0.05 for the normal operating state based on the EPRI database (EPRI FIVE report, page 10.3-7). This unavailability value include the consideration for failure of the system to operate on demand and the system being out of service at the time of a fire (due to shut control valve, etc.). Infire zone 99-M, no automatic fire suppression system is provided. Therefore, the P1 value was assumed to be 1.0.
(c)Manual Suppression by Fire Brigade, P2 - Recent fire drills performed on fire zone 100-N,which is adjacent to fire zone 99-M, indicated that the response times of the entire fire brigade arriving at the fire zone averaged less than 10 minutes. wlhere are two access ala ypoints-to.the fire zones -which are easily-accessible by-the fire-brigade respons.ej.geams" Based on these considerations, it was assumed that any fire scenario requiring greater
- than 20 minutes to sustain cable damage may be suppressed by the fire brigade.
Hawever,..the SPLB fire modeling analyses indicate that severe, fires with. HRR greaterp than 400 kW in fire.zones.90-Jand.9 M could cause.damage to the overhead cables in;I
-approximately 19 minutes and 10 minutes, respectively. -Thvrefore, the failure prob&bilit of manual suppression by the fire brigade associated with severe fires was estimated to be b.5in this risk analysis.
(d)Conditional Core Damage Probability, P3 - For the fire scenarios in fire zone 98-J involving ignition of the electrical cabinets, battery chargers, ventilation systems, and fire protection panels, it is assumed that one equipment train would be available to perform mitigating functions because a one-hour rated barrier surrounds the Red train AC instrumentation power supply cables. Although other Red train power cables in fire zone 98-J are unprotected, the estimated time of 19 minutes to cable damage allows the arrival of the fire brigade in 10 minutes to control the fire. It is not likely that a fire from these sources would damage both equipment trains at the same time. Therefore, the CCDP
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associated circuits defined consistent with GL 81-12 clarification -
- inspection 87-14 report dated Sep 30, 1987 (D. Kubicki, et. al.)
found manual component operation for fire induced maloperation acceptable manual operation of redundant components evaluated to be satisfactor J
-- references made to SOC for IIIJ and inspectionguidance_
- FPFI report dated T 98orusqueanna q u e-protection for fire-iduced spurious failures found acceptabl.e recognized the use of symptom-based procedures for post-fire safe shutdown URI identified regarding adequacy of symptom-based procedures
- Susquehanna response dated July 20, 1998 pre-fire plans describe symptoms that lead to required manual actions
- NRC Special Inspection Report dated September 4, 1998 closed FPFI URI based on procedural clarifications and improvements J
- ANO interprets the usqueln inspection resiltis`si-6ffri~nliiTlheir use of symptom-based procedures for post-fire safe shutdown
- ANO recommends that symptom-based procedures be used to guide manual actions in any future rulemak-ing by NRC
- ANO firmly believes that their use of manual actions for IIIG2 redundant safe shutdown areas is consistent with NRC regulations and guidance
- ANO believes that the b/f panel finding was flaved because we did not adequately consider the licensing basis for their facility
- they attempted to lay out their understandingfjtheir licensing basis at this information exchange meeting
- they asserted that their survey ofother re-74jan Idicated they wre.not outliers; there are at leas thefacilities who have similar manual action methodology without prior NRC approval
- the meeting was adjourned - NRC will consider the licensee's perspective as we determine how to process the finding in the ROP John Hannon October 3, 2002
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