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Category:Meeting Briefing Package/Handouts
MONTHYEARML23348A3572023-12-14014 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 ML22193A0262022-07-12012 July 2022 (ANO) RICT License Amendment Request TSTF-505 NRC Pre-Submittal Meeting Presentation - July 13, 2022 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 ML21309A0622021-11-0909 November 2021 NRC Slides for November 9, 2021, Technology Inclusive Content of Application Project Public Meeting ML21312A0342021-11-0909 November 2021 Combined Slides for November 9, 2021, Technology Inclusive Content of Application Project Public Meeting ML21242A2792021-08-30030 August 2021 ANO Slides Presentation for 9-1-21 Public Meeting ML21200A1792021-07-31031 July 2021 Scale/Melcor Non-LWR Source Term Demonstration Project - High Temperature Gas-Cooled Reactor 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 ML19136A2512019-06-13013 June 2019 Handout for the June 13, 2019 Pre-submittal Public Meeting for Planned License Amendment Request Regarding Fuel Handling Accident Analysis ML18176A1312018-06-21021 June 2018 Summary of Annual Assessment Meeting with Entergy Operations, Inc., Regarding 2017 Performance of Arkansas Nuclear One ML18107A3342018-04-10010 April 2018 Tech Spec 3.3.5.2a Change Pre-Submittal Meeting Presentation Slides 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 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 ML16015A0622016-01-20020 January 2016 Briefing Notes for 95003 Inspection at Arkansas Nuclear One ML15132A1752015-05-21021 May 2015 Summary of Annual Assessment Meeting with Entergy Operations Inc., Regarding ANO 2014 Performance ML14356A1852014-12-22022 December 2014 ANO2 Exit 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 ML12332A1792012-11-26026 November 2012 Power Point Presentation by Entergy at the November 26, 2012 Meeting (TAC No. ME9706.) ML12306A2912012-11-0101 November 2012 Transmittal Email and WCAP-17128-NP, Revision 1, Flaw Evaluation of CE Design RCP Suction and Discharge Nozzle Dissimilar Metal Welds, Phase III Study, May 2010 ML12278A2552012-10-0909 October 2012 Licensee Slide Presentation, ANO-2 NFPA 805 Application, at the October 9, 2012, pre-submittal Meeting to Discuss the NFPA 805 Application ML12278A2532012-10-0909 October 2012 Licensee Handout, Design Input for Fire Risk Evaluation, at the 10/9/2012 Pre-submittal Meeting to Discuss the NFPA 805 Application 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 ML1218003412012-06-28028 June 2012 Handouts at the June 29, 2012 NFPA 805 Meeting at the Hq - Item #4 ML1218003192012-06-28028 June 2012 Handouts at the June 29, 2012 NFPA 805 Meeting at the Hq - Item #3 ML1218003122012-06-28028 June 2012 Handouts at the June 29, 2012 NFPA 805 Meeting at the Hq - Item #2, Table W-2 ANO-2 Fire Area Risk Summary ML1218003102012-06-28028 June 2012 Handouts at the June 29, 2012 NFPA 805 Meeting at the Hq - Item #1, Plant Modifications and Items to Be Completed ML1218003062012-06-28028 June 2012 Handouts at the June 29, 2012 NFPA 805 Meeting at the Hq - Power Point Slides ML12166A5602012-06-12012 June 2012 Licensee Presentation on June 12 & 13, 2012, Meeting License Amendment Request on NFPA 805 Adoption 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 ML1117906392011-06-28028 June 2011 Summary of Meeting with Entergy Operations Inc 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 ML0935005652009-12-15015 December 2009 NRC Handouts Current Status of Arkansas Nuclear One Unit Steam Generators, December 2009 ML0913104172009-05-11011 May 2009 Summary of Meeting with Entergy to Discuss Arkansas Nuclear One 2008 Performance 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 2023-12-14
[Table view] Category:Slides and Viewgraphs
MONTHYEARML23348A3572023-12-14014 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 Licensee'S 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 ML21312A0342021-11-0909 November 2021 Combined Slides for November 9, 2021, Technology Inclusive Content of Application Project Public Meeting ML21306A3162021-11-0909 November 2021 Digital IC Presentation 11/09/2021 ML21309A0622021-11-0909 November 2021 NRC 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 ML0627703242006-10-19019 October 2006 Draft Slide Presentation for Nrc/Entergy/Westinghouse Pre-Submittal Meeting (Non-Proprietary) ML0619203612006-06-30030 June 2006 Storage Project and Spent Fuel Pool - Meeting Slides Meeting - June 2006 2023-08-11
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ARKANSAS NUCLEAR ONE APPENDIXR
- REGULATORY CONFERENCE I.
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OPENING REMARKS
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Craig Anderson
. Vice President, ANO I!
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' im Risk Assessment Overview' i
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- NRC's preliminary SDP evaluation concluded unacceptable (greater than green) increase in core damage frequency I .
- Key assumptions in.NRC evaluations vs ANO's
-pr.eli"minary assessment ' . *r 1
- Heat release rate
- Human error probability 10 -
S Subsequent site-specific in-depth assessment...
- Results incorporated into Unit 1 PSA model 'to derive ACDF I
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e, CD-Unit 1 4KV Switchgear Room (fire zone 991 EC204 EC204 EC204 EC205 ;
EB203 EB202 EB202 E8202 E8203 EC236 EC236 , . v (enters)I J-.
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- eD f'ire (Characterization
- Electrical cabinet fires .I The-heat release rate data profile is' HRR Profile based on the best available fire test i-data 120 Sandia National Lab (NUREG/CR-45 27, 100 87/88) and VTT (Valtion Teknillinen Tutkimuskeskus, .94/96) in Finland 80
- Same test used in the NRC SDP analysis 60
- The ANO.. HRR is based on the highest 40 j
peak of.ST5 (unqualified, ope'n 110 20 KBTU loading) and all qualified, vertical cabinets (excluding PCT6 and test 23 0.
with 1.5 MBTU loading) 5 10;
- The NRC. HRR is based on test 23 (qualified, open 1.47 MBTU loading) and Time [min]'
test 24 (Unqualified, open, .1.44 MBTU)
- Time-to-peak is based on the -average I :
- Tests are based on control'panels (I I I
- The switchgear, MCC's and load centers are enclosed with sealed penef rations I I I I.,
- . Used for-scenarios Ia, 2 - 5 C, rC
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Results (cont.) 32 Comparison of NRC -and ANO Results lDamage threshold;
., Damage thResh:d 0
.Upper Layer Timperature in,99M-
-NRC: 425 F
- ANO: 7000F 800 Heat release rate 600
- NRC: 500KW _500 fire peaking in 105 sec. '-' 400 _ _-
- ANO: 1OOKW peaking -300 in 12 min (Scenario la) + cable 200 fires and high energy fault in A4l10 10 switchgear and cable fires (Scenario Ib) 0 250 500 - 750 1000 High energy arcing fault Time sec in the 4KV\ switchgearAN0-ULTenpScenario la Open Door
- NRC: Not analyzed . NRC-ULTerrp ANO: Limiting scenario, in terms UL Terrp Scenario>bOpenDoor.
of its consequence,.i.e., affected circuits and timing' %
Neither analysis reaches 700 0 F I
I, Res-u Its: 34 Frequency of Fire Scenarios in Fire Zone,99M ANO SDP Analysis Results -
0 1 ~~~~~~~~~WF WIS lorRatio of HE Pnsb 2 ~~~~~~~~~~~~~~~~Generic (location igton area ratio Severity eetfra pat Psb IS <"Source Frequency weighting source (transient Factor severe e hie Results U) ~~~~~~~~~~~~~~~~weighting switchgear or fire brigade factor) factor) fires) fire wtch la Fire In the A4 swtchgear.
bNomnalvalue, I j0KWAr fire 11.50E-02 2.50E-01 5 88E-0 1.00E+00 1.20E-01 2.50E-01 1 O00 1.0OE.00 6.62E-05 lb High energy arcing fault in any of the A4 switchgear breaker cubicles
_______________ _ 1.1.50E42 2.50E4 1 588E-01 1.OOE+00 1.20E-01 7.50E-041 .000 1,E0 2 Fire in the B55 MCC. Nominai__
100KW fire. Fires in Inverler Y28 .
are bounded by this scenario.
11.50E-02? 2.50E-01 5 88E-02 1.OOE400 1.20E-01 10.ooE00 11.008+00 1.OOE800 2.65E405 3 Fire In the B56 MCC. Nominal
________ _0OKW fire 1.50E-02 2.50E-01 5.88E-02 1OOE+00 1.20E-01 1.OOE+00 . 1.00E+00 11.00rE400 _2.65E-05 4 Fire In the Y22 Inverter. Base .
case.rtOO KW fire. Fires in Y24 . .
and Y 25 are bounded by this scenario. 1.50E-02 2.50E-01 5 88E02 1OOE+00 1,20E.01 l.0Ed, 1.OOE*00 5.OOE-4
- 1.32E-05 5 Fire in the Load Center 86.
1WK om -n"Ln RR 1 50E-02 2.50E-01 _ 5 88E- 10 0 1E-01 1.00E00 1O.OEE0 2.00E41 5.29E-06 6a Transient fire in areas of the room. . . _
where cable trays are exposed to a floor-based fire. Nominal Value ,.
of 150KW. 3 60E-02 2 OOE*00 11.80E-02 11.00E-01 1.00E+00 100+.00 5.00E-01 11.00E+00 6.i8E-05 6b Cable fire caused by welding and ..
cutting in areas of the room where I cable trays are exposed to a foor-based fire. Nominal Value of O1iKW. 1.30E-03 2OOE+00 2OOE-02 1 OOE-01 OOE800 1.00800 5.002-0 1.008+00 2.608-07 II
. I NRC SDP Analysis Results (May 15, 2003 Supplemental Letter Page 25)
? I Source . ' Frequency Electrical cabinets 2.3E-04
.1 Transformers .1.6E05 II Ventilation Subsystems. . 4.4E-06
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Key Systems Affected in the Risk- I 39 Significance Determination (FireZone 99M) I
., I The following systems/trains are directly failed due to' fire induced power losses of A4 and B6 .
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- One train and the swing pump of service water'
- One train and the swing pump of HPI (makeup)
- The A4 associated diesel is no longer usa I ..
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II Human Error Probability I~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
. C Comparison 57
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- NRC approach assumes zone wide damage at time zero .
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- NRC approach included loss of offsite power
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Operat& Actiton I
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Establish EFW I
(A3 local start) I 'l Establish, EFW (Control. EFW,)
4.
I Establish Feed N.
& Bleed Establish Feed ' 0.75 0.55 0.11 ,. ' . 0.098 '
& Bleed, (A3 Local Start)
Secure Diesel 0.75 . 0.55 Not needed due'to no loss of offsite with no Service power Water" I
.! I
SCiENCE SAIC APPLICATIONS INTERNATIONAL CORP.
EMPLOYMENT HISTORY:
Mr. Najafi is the Manager of the'Fire Protection Program at SAIC responsible for overseeing a business area that includes domestic iad international nuclear utilities, DOEfacilities and commercial/industrial facilities..
He is one of the principal investigators for Electric Power Res~earch Institute (EPRI)'fire risk analysis and fire protection projects. These projects included development of EPRI's Fire PRA Implementation'Guide and Fire-Induced Vulnerability Evaluation (FIVE) methodology and application of these technologies to US
- nuclear power plant support Over the past decade Mr. Najafi has been instrumental in development of the fire research program -at EPRI to support 'nuclear power industry move, towards a Risk-Informed/Performance-Based (RI/PB) fire protection rule.', Under this program data and methods are being developed a;nore'engineering-based (as opposed to prescriptive-based) approach to fire protection. Several methods where also developed to demonstrate use of the technology, such'as "Methods for Evaluating Cable Wrap Fire Barrier Performance."
As part'of this .process of continuous enhancerment of technology, Mr. Najafi is currently the princpl technical anager of a oint roect between EPRI and USNRC office of Research for development of the next generaion of Fire Risk Analysis Ileiho shia G p e protection imdustry in RI/PB rule.
This is a ground braking exercise in cooperative research between EPRI and NRC and key to improving the environment-for risk-informed rule in fire protection. Mr. Najafi is the key in providing goals and directions to this program that includes the development of the first documented methodology for assessment of fire risk during low power and shutdown modes of operation.
Between 1991'and 1997, Mr. Najafi managed Fire PSA projects at over eighteen (18) U.S. nuclear plants in response to NRC's Individual Plant Examination for External Events (IPEEE) as well as Dodewaard Plant in the Netherlands. The experience was part of the process to improve the Fie PSA data and methods developed 1y EPRI (with Mr. Najafi as the Project Manager).
Between 1988 and 1993, Mr. Najafi served as SAIC Project'Manager for GE's ABWR/SBKrR Level 1 PRA, Comanche Peak Level I/II PRA support, Project Engineer (Technical Project Manager) for the Turkey Point Nuclear Power Plant (PWR-YZ) Units 3 and 4 Level 2 PRA xith external events (excluding seismic), and Systems Analysis Task Leader for the River Bend Station (BWR) Level 1 PRA. He also-served as an instructor in a course on Seismic PRA and Unresolved Safety Issue (USI) A46, "Seismic Qualification of Equipment in Operating Plants," for the Omaha Public Power District staff.
During 1987-1988, he was the manager of a project to update the PRA for the Indian Point Unit 3 plant and perform a SAIC/Utility-conducted Level 1 PRA for a BWR-4 plant (confidential client). Mr. Najafi was involved in- the N-Reactor Safety and Reliability Evaluation program as the task leader responsible for analyzing the Confinement, Reactor Trip, HVAC, and Emnergency Core Cooling Systems.
Mr. Najafi was one of the principal authors of the Reliability-Centered Maintenance studies for the Diesel Generator Systems at the Catawba (PWR-I and Palo Verde (PWR-CE) Nuclear Power Plants, and the River Water Makeup System for the Susquehanna Steam Electric Station (BWR).
During 1985, Mr. Najafi was one of the principal authors of a PRA study for the Peach Bottom plant (BWR) as part of the NUREG-1150 program for Sandia National Laboratories. He was primarily responsible for the" modeling of the plant Safety Support Systems including Electric Power and Service Water Systems.
During 1985_ and 1986, Mr. Najafi directed an NRC-sponsored work to develop a methodology for assessment of uncertainties in the phenomenological events (back-end). This effort involved development of