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MONTHYEARML24296A0652024-10-22022 October 2024 NRR E-mail Capture - Arkansas Nuclear One, Unit 2 - Verbal Authorization of Relief Request for the Proposed Alternative ANO2-RR-24-001 ML24227A0072024-08-13013 August 2024 NRR E-mail Capture - LIC-109 Acceptance - ANO 2 - Proposed Alternative for Implementation of Extended Reactor Vessel In-Service Inspection Interval (ANO2-ISI-24-02) - EPID L-2024-LLR-0048 ML24218A0652024-08-0202 August 2024 NRR E-mail Capture - LIC-109 Acceptance Review - Arkansas Nuclear One, Unit 1 - License Amendment Request - Request for Review and Approval Changes to SAR and to a Confirmatory Order - Pzr Htr Emergency Power Supply - EPID L-2024-LLA-0092 ML24180A0022024-06-26026 June 2024 NRR E-mail Capture - LIC-109 Acceptance - ANO 1 and 2 - Proposed Alternatives for Examinations of SG Pressure Retaining Welds and Full Penetrations Nozzles - EPID L-2024-LLR-0038 ML24149A3672024-05-28028 May 2024 August 2024 Emergency Preparedness Exercise Inspection - Request for Information ML24117A0262024-04-26026 April 2024 NRR E-mail Capture - 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[Table view] Category:Graphics incl Charts and Tables
MONTHYEARML24190A1452024-07-0808 July 2024 Public Meeting Slides for Arkansas Nuclear One 2023 Annual Assessment, Pope County Quorum Court 2CAN012401, U.S. Additional Protocol2024-01-17017 January 2024 U.S. Additional Protocol ML22259A1222022-09-0808 September 2022 ANO Service Water KM Version ML21354A7552021-12-20020 December 2021 Recertification of Foreign Ownership Control or Influence and Request for FOCI Redetermination - Part 10 of 18 CNRO-2018-00011, Submittal of Joint Plant Access Shared Information Table2018-03-19019 March 2018 Submittal of Joint Plant Access Shared Information Table ML17150A2562017-06-0505 June 2017 Entergy Fleet - 2017 Onsite Insurance Submittal Review for Entergy Operations, Inc., and Entergy Nuclear Operations, Inc. (CAC No. TM3058) ML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports 2CAN011502, Response to Request for Additional Information Concerning the Spring 2014 Steam Generator Inspections2015-01-12012 January 2015 Response to Request for Additional Information Concerning the Spring 2014 Steam Generator Inspections ML13133A1382013-05-10010 May 2013 One, Unit 1, ANO1 Steam Generator Tube Inspection Discussion Points, Preventative Tube Plugging and Proximity Calls ML13133A1362013-05-10010 May 2013 One, Unit 1, ANO1 Steam Generator Tube Inspection Discussion Points, Preventative Tube to Plug and Proximity Calls ML12241A2962012-08-28028 August 2012 RAI for the Request to Use of Alternate ASME Code Case N-770-1 Baseline Examination, Request for Alternative ANO2-ISI-007 ML1019004182010-06-28028 June 2010 Quick View Chart 0CAN061001, Annual 10 CFR 50.46 Report for Calendar Year 2009 Emergency Core Cooling System Evaluation Changes2010-06-0303 June 2010 Annual 10 CFR 50.46 Report for Calendar Year 2009 Emergency Core Cooling System Evaluation Changes 2CAN070807, Transmittal of Request for Alternative ANO2-PT-001 Visual Examination of Extended Reactor Coolant Pressure Boundary Piping During System Leakage Tests2008-07-31031 July 2008 Transmittal of Request for Alternative ANO2-PT-001 Visual Examination of Extended Reactor Coolant Pressure Boundary Piping During System Leakage Tests 1CAN070801, Transmittal of Analysis of Proposed Technical Specification Change Sodium Hydroxide Tank Concentration2008-07-30030 July 2008 Transmittal of Analysis of Proposed Technical Specification Change Sodium Hydroxide Tank Concentration ML0728203072007-10-11011 October 2007 Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists ML0710002572007-03-26026 March 2007 Attachment 5 - HI-2063601, Holtec Licensing Report for ANO Unit 2 Partial Rerack, (non-propriety) ML0519603252005-07-15015 July 2005 Attachment 3 - Recommendation and Action Item Cross Reference Table 2005-025 ML0427205342004-09-28028 September 2004 Tables to ANO-2 Amendment on Administrative Controls (Amendment No. 255) ML0426101132004-09-13013 September 2004 Plant Engineering Branch Open Items Interim Safety Basis (URI 2002003-01) ML0414101322004-04-27027 April 2004 E-mail Dated 04/27/04 ANO 1 Slides for NRC Conference Call on 04/27/04 ML0406407512004-02-20020 February 2004 Attachment 3: List of Components in Fire Zones 98J and 99M ML0406407502004-02-20020 February 2004 Equip/Cable/Reel#/Cable Type/Po#/Insulation/Material/Type ML0230501762002-09-17017 September 2002 Attachment 13, ANO-1, Units 1 and 2, Table B-1, Minimum Staffing Requirements ML0230501692002-09-16016 September 2002 Attachment 12, ANO-1, Units 1 and 2, Table B-1, Minimum Staffing Requirements 2024-07-08
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24264A1592024-09-30030 September 2024 Adtf Exemption Request Pre-submittal Meeting Presentation ML24190A1452024-07-0808 July 2024 Public Meeting Slides for Arkansas Nuclear One 2023 Annual Assessment, Pope County Quorum Court ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology – Slides and Affidavit for Pre-Submittal Meeting ML23296A1002023-10-24024 October 2023 Entergy Presentation Slides for Pre-Submittal Meeting on 10/24/23, Mtc LAR ML23223A2032023-08-11011 August 2023 (ANO) Unit 1 Licensees Slide Presentation for 8/15/23 Public Meeting Pressurizer Heaters ML22193A0262022-07-12012 July 2022 (ANO) RICT License Amendment Request TSTF-505 NRC Pre-Submittal Meeting Presentation - July 13, 2022 ML22164A8012022-06-13013 June 2022 Entergy Fleet (GGNS, RBS, and WF-3) - Code Case N-752 RR 6-14-22 Pre-Submittal Public Meeting Presentation Slides ML22124A0692022-05-10010 May 2022 RVCH Penetration No. 1 Relief Request Public Meeting May 10, 2022 (EPID L-2022-LRM-0036) (Slides) ML21351A0282021-12-16016 December 2021 Preliminary Information of ANO-1 1R17 (2002) Findings on CRDM Nozzle 56, and Presentation Slides for PT Exam of Nozzle 56 ML21348A1262021-12-14014 December 2021 RCP TS LAR Pre-Submittal Meeting Slides, December 16, 2021 ML21319A2452021-11-15015 November 2021 Natrium Energy Island Decoupling Strategy - 11-17-2021 ML21309A0622021-11-0909 November 2021 NRC Slides for November 9, 2021, Technology Inclusive Content of Application Project Public Meeting ML21306A3162021-11-0909 November 2021 Digital IC Presentation 11/09/2021 ML21312A0342021-11-0909 November 2021 Combined Slides for November 9, 2021, Technology Inclusive Content of Application Project Public Meeting ML21200A1792021-07-31031 July 2021 Scale/Melcor Non-LWR Source Term Demonstration Project - High Temperature Gas-Cooled Reactor 0CAN062101, Presentation Information for Pre-Submittal Meeting Regarding the Response to Request for Additional Information - Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency Cooling2021-06-15015 June 2021 Presentation Information for Pre-Submittal Meeting Regarding the Response to Request for Additional Information - Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency Cooling ML21095A2122021-04-0808 April 2021 Pre-Submittal Meeting - ANO-1 LAR Related to RCS Primary Activity and Primary-to-Secondary Leak Rate ML20344A0572020-12-10010 December 2020 Combined Industry and NRC Slides for the December 10, 2020, Public Meeting on Technology Inclusive Content of Application Project, Advanced Reactor Content of Application Project and Applicability of Regulations to Non-Light Water Reactors ML20315A1582020-11-17017 November 2020 Presentation Meeting Slides for the 11/17/20 Teleconference ML20269A3452020-09-28028 September 2020 Pre-submittal Meeting for Request for One-Time Exemption from 10 CFR Part 50, Appendix E, Biennial EP Exercise (Offsite) Due to COVID-19- Entergy Presentation Slides ML20255A0242020-09-11011 September 2020 (Ano), Pre-Submittal Meeting with NRC - Request to Extend Allowable Outage Time (AOT) for the Emergency Cooling Pond (ECP) ML20211L7052020-08-0404 August 2020 (ANO) Units 1 & 2, Pre-Submittal Slide Presentation for August 4, 2020 Public Meeting ML20114E2752020-04-29029 April 2020 (ANO) Carbon Fiber Reinforced Polymer (Cfrp) Relief Request Pre-Submittal Meeting with NRC - April 29, 2020 ML18107A3342018-04-10010 April 2018 Tech Spec 3.3.5.2a Change Pre-Submittal Meeting Presentation Slides ML18075A1232018-03-20020 March 2018 Entergy Nuclear Operations - March 20, 2018, Presentation Slides for Surveillance Frequency Control Program, UFSAR Change Considerations ML18081A1922018-03-20020 March 2018 Presentation at the PRA Workshop ML17328A3652017-11-30030 November 2017 Workshop on Sharing Operating Experience from Rigging, Lifting and Load Handling Events - Temporary Overhead Crane Failure at Arkansas Nuclear One Presented to IAEA ML15132A1752015-05-21021 May 2015 Summary of Annual Assessment Meeting with Entergy Operations Inc., Regarding ANO 2014 Performance ML15014A0842015-01-14014 January 2015 NRC ANO Unit 1 Stator Drop SDP Evaluation ML14329B2092014-11-25025 November 2014 Summary of Regulatory Conference to Discuss Safety Significance of Arkansas Nuclear One Flood Protection Deficiencies ML14259A5972014-09-16016 September 2014 Summary of Annual Performance Assessment Meeting for Arkansas Nuclear One Performance ML14169A0722014-06-19019 June 2014 Entergy Public Meeting Presentation Slides ML13142A2272013-05-22022 May 2013 Summary of Public Meeting to Discuss Results of Augmented Inspection at Arkansas Nuclear One ML12332A1792012-11-26026 November 2012 Power Point Presentation by Entergy at the November 26, 2012 Meeting (TAC No. ME9706.) 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 ML1218003062012-06-28028 June 2012 Handouts at the June 29, 2012 NFPA 805 Meeting at the Hq - Power Point Slides ML1202501112012-01-25025 January 2012 Licensee Slides Arkansas Nuclear One, Unit 1 - Steam Generators Tube to Tube Wear ML1126502692011-09-22022 September 2011 Licensee Handouts for 10/05/2011 Presubmittal Meeting ML11221A3212011-08-0101 August 2011 521- R326C B&W Tech Cross Training - Chapter 17 ANO-1 Seal Failure ML1110401532011-04-13013 April 2011 Licensee Slides from 4/13/11 Meeting with Entergy Operations, Inc., to Discuss Proposed National Fire Protection Programs Standards 805 License Amendment Submittal for Arkansas Nuclear One, Units 1 & 2 ML1107504262011-03-15015 March 2011 Licensee Slides from 3/15/11 Pre-Sumittal Meeting SWS Room Cooling Required Action ML1107504162011-03-15015 March 2011 Licensee Slides from 3/15/11 Meeting with Entergy Operations on Technical Specification Change - Testing of Idle RCS Cooling Loop ML1016705012010-06-17017 June 2010 Discussion of Screening Criteria - Arkansas Nuclear One (ANO) ML0935201272009-12-18018 December 2009 Nrc/Entergy Operations, Inc., Management Meeting ML0913104172009-05-11011 May 2009 Summary of Meeting with Entergy to Discuss Arkansas Nuclear One 2008 Performance ML0831102062008-11-0606 November 2008 Summary of Meeting with Entergy to Discuss an Open Substantive Crosscutting Issue at Arkansas Nuclear One ML0828000612008-10-0101 October 2008 Enclosure 3-Technical Papers 2 - Plant Application of Weld Onlay for Butt Weld Mitigation ML0828300322008-08-31031 August 2008 NRC Presentation Arkansas Nuclear One - Unit One ML0814306742008-05-22022 May 2008 Summary of Annual Performance Assessment Meeting for Arkansas Nuclear One ML0718004262007-06-29029 June 2007 Summary of Arkansas Nuclear One End-Of-Cycle Public Meeting 2024-09-30
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Jhomas Alexion - FW: Slides for NRC Conference Call on April 27, 2004 Page_1 Pa 11 Thoms W: Side fo.NR Cofrec Ca on Ap1 27, 200 Aexin- I From: 'DAVANT, GUY H"<GDAVANT@ entergy.com>
To: "'twa~nrc.gov"' <twa~nrc.gov>
Date: 4/27/04 12:06PM
Subject:
FW: Slides for NRC Conference Call on April 27, 2004 Tom, Attached are notes we will be discussing during the 1:00 call today. You may docket these.
Thanks!
Guy
> <<<SIA EPFM NRC CONF 4-27-04.pdf>>
I CA\WIND0WS\TEMP\GW)00001.TMP
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FW: Slides for NRC Conference Call on April 27, 2004 Creation Date: 4/27/04 11:59AM From: "DAVANT, GUY H" <GDAVANT@entergy.com>
Created By: GDAVANT@entergy.com Recipients nrc.gov owf4_po.0WFNDO TWA (Thomas Alexion)
Post Office Route owf4_po.0WFNDO nrc.gov Files Size Date & Time MESSAGE 159 04/27/04 11:59AM Part.001 861 SIA EPFM NRC CONF 4-27-04.pdf 710470 Mime.822 975129 Options Expiration Date: None Priority: Standard Reply Requested: No Return Notification: None Concealed
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No Security: Standard
Response to NRC Questions
- 1. Upper shelf Charpy V-notch energy (USE) estimates for the ANO-1 head material were developed as shown in Figure 4, This Figure indicates three Charpy energy data points derived from measurements on the ANO-1 head material at +100 F. The actual measurements were higher, but they were measured in the Longitudinal direction, so they were reduced for the Transverse direction in accordance with USNRC SRP/NUREG-75/087 MTEB 5-2 Position 1.1 B-3a. These are obviously not on the upper shelf, so they have been plotted on a complete Charpy Energy plot for a comparable material (GGNS beltline plate, comparable thickness, Transverse direction). The three ANO points fall well within the range of the GGNS data at +100F, and therefore, the GGNS data, which exhibit USEs ranging from 94 to 120 ft-lbs, are considered representative of the ANO-1 head material USE. The lower bound value of 94 ft-lbs was used, in conjunction with J-T versus Charpy USE correlations in NUREG-0744 (Figures 2 and 3), to estimate a conservative J-T curve for the analysis.
- 2. The screening criteria of Appendix H were developed using the "Fracture Analysis Diagram" (FAD) approach.
Although Appendix H itself is strictly applicable only to ferritic piping, the FAD approach upon which it is based is more generally applicable. A second criterion for the applicability of J-T stability analysis to ferritic materials is that the temperature be at least 500F greater than the onset of upper shelf. From Figure 4, it is seen that onset of upper shelf occurs at about 210 0F. Since the ANO-1 evaluation is at operating temperature of -5501F, it clearly meets the latter criterion as well.
Response to NRC Questions (continued)
- 3. The Appendix K approximation for J-integral requires that the plastic zone size be small (i.e. contained plasticity).
The plastic zone size with the recommended safety factors (SF=3 on primary loads, 1.5 on secondary) is 0.319",
which is considered small in comparison to the original crack size of -1.5" and the nominal head thickness of 6.6".
The plastic zone sizes become significantly greater for the higher safety factor cases (0.5" to 2"), but these are just informational cases to demonstrate margin, and not the focal point of the analysis. Also, since the dominant loading in these analyses is residual stress (amplified by safety factors), which is strain controlled and highly localized, the approximation of using LEFM K-values to estimate EPFM J-values remains valid for much larger plastic zone sizes than might be interpreted from Appendix K.
- 4. The analysis demonstrates large margins between applied J-integral and the crack instability point (i.e. the point where the applied J-T line intersects the appropriate J-T material curve) in all cases. In Figure 6, it is seen that the applied J-T point for the recommended safety factors of 3 on primary loads and 1.5 on secondary (residual) loads is below even the 40 ft-lb J-T material curve, which was measured at +10 for the ANO-1 head material, and is an extreme lower bound of USE for this material. Considering a more reasonable estimate of J-T material for the ANO-head material on the upper shelf (the 94 ft-lb curve - still a lower bound) shows ample margin to instability, and even supports application of the full safety factor of 3 on both primary and secondary (residual) loads.
8 58 189 158 289 T mat Figure 1: J-T Diagram for Several Reactor Vessel Steels and Welds Showing Rough Correlation with Charpy V-notch Upper Shelf Energy [5J. Power Law Correlations used for ANO-1 Head (40 and 94 ft-lbs) also Shown
(
15 10 *a150/_
170 C o 200 o3 20 5
SS 00 0.0, 0.4 0.8 1.2 1.6 2.0 CVN/100t+ l6>
Figure 2: Correlation of Coefficient C of Power Law J R-curve Representation with Charpy V-notch Upper Shelf Energy [51
0.7.
0.6 0
04 0.5 o05* Y o
EQ-so---O-
.0.4 o 00 m
043 1. 1.61T-CT 0.2z 0.1
- 0 2. 4 6 8 ic 12 14 16 X=C+1.5( O.'
Figure 3: Correlation of Exponent m of Power Law J R-curve Representation with Coefficient C and Flow Stress cs 151
130 120 USE Mean 106 ft-ibs
/
110 1-In 100 _..e 7~ 7 7 i , _ . . . .. .. ..
.0 4-- 90 ., ' ,' , . '-' -/- ' 7."-"' - -' -, /-' _ _- .. -
cm il- 80 Lowest USE 94 ft-lbs ar w 70 USE LC L98 Ft-lbs ..
'a
-D
-0 60 o
Vn
.0 50 0.
40 co C-,
D
. ' ' .i .- I , AND-I ,RVH
,", I1.',',,' .,,,--Charpy'-, Data' Cmparison.,
tI..,..I ...... , I .; s2^.............. ' w.;-
30 -wit GGNS BatinPlate Data to estals S (Fourth Order polynomnial fit With 99% confidence bounds) h-GG 20 10 NS RV Beitline Plates (transverse CVN) 4-plates
- ANO-1 RVH (CVN at +10F) using MTEB 5-2; B-1.1-3a 0
-110 -90 -70 -50 -30 -10 10 30 50 70 90 1110 130 150 170 190 210 230 Test Temperature {Deg. F)
Figure 4. GGNS RV Plate (beltline) data (Lukens Steel A533 Gr. B Cl. 1) from transverse Charpy V-notch test. ANO-1 data from FSAR Table 4-16, @ +10 F Longitudinal. Converted to Transverse using USNRC SRP/NUREG-75/087 MTEB 5-2 Position 1.1 B-3a.
J J I INSTABILITY MATERIAL haSLOPE dA 7--
I APPLIED Aa T= -()
93220rO Figure 5- Schematic of EPFM Stability Analysis from ASME XI, Appendix K 141
12 10 a..
a -A 2;.._.'.'.........
0 0 20 40 60 80 100 120 140 Tearing Modulus Figure 6- Results of EPFM Stability Analysis for ANO-1 Top Head Remnant Cracking Concern
Table 1: J-T Computations for ANO-1 Top Head Remnant Crack (postulated) using ASME Section XI Appendix K Approximate Method
-:Safety I KID !,-"a 1-Ktot K- . rD I I 'K'totat: 0 'l(a a),
Factor _-.__ ksi in ,,- inches. -____ __lkin:
SF=1 3.7 90.7 94.4 0.131 1.631 1.043 98.4 SF=3,1.5 11.1 136.1 147.2 0.319 1.819 1.101 162.0 SF=2 7.4 181.4 188.8 0.525 2.025 1.162 219.4 SF=3 11.1 272.1 283.2 1.182 2.682 1.337 378.7 SF=3.5 13.0 317.5 330.4 1.609 3.109 1.440 475.6 SF=4 14.8 362.8 377.6 2.101 3.601 1.549 585.1 I ksi i . ; .- n-kips/in ; __-' - : In-kips/i .
SF=1 3.7 90.7 94.4 98.4 0.294 0.916 0.046 SF-3, 1.5 11.1 136.1 147.2 162.0 0.797 2.483 0.124 SF=2 7.4 181.4 188.8 219.4 1.460 4.551 0.228 SF=3 11.1 272.1 283.2 378.7 4.350 13.559 0.678 SF=3.5 13.0 317.5 330.4 475.6 6.863 21.392 1.070 SF=4 14.8 362.8 377.6 585.1 10.383 32.367 1.618