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| ==SUBJECT:== | | ==SUBJECT:== |
| SUMMARY OF PUBLIC MEETING TO DISCUSS AN APPARENT VIOLATION IDENTIFIED AT WOLF CREEK GENERATING STATION | | |
| | ==SUMMARY== |
| | OF PUBLIC MEETING TO DISCUSS AN APPARENT VIOLATION IDENTIFIED AT WOLF CREEK GENERATING STATION |
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| ==Dear Mr. Heflin,== | | ==Dear Mr. Heflin,== |
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| : 1. List of Attendees 2. WCNOC Presentation Slides | | : 1. List of Attendees 2. WCNOC Presentation Slides |
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| SUNSI Review MSH By: Non-Sensitive Sensitive Publicly Available MSH Non-Publicly Available Keyword: OFFICE DRS/PSB1 DRP/PBB DRP/PBB DRS/PSB1 ACES DRP/CPBB DRS/CPSB1 NAME P. Elkmann C. Peabody D. Proulx G. Guerra R. Browder MHaire/VGaddy SIGNATURE | | SUNSI Review MSH By: Non-Sensitive Sensitive Publicly Available MSH Non-Publicly Available Keyword: OFFICE DRS/PSB1 DRP/PBB DRP/PBB DRS/PSB1 ACES DRP/CPBB DRS/CPSB1 NAME P. Elkmann C. Peabody D. Proulx G. Guerra R. Browder MHaire/VGaddy SIGNATURE /RA/ /RA/ /RA/ /RA/ /RA/ /RA/ /RA/ DATE 5/6/14 5/8/14 5/6/14 5/8/14 5/7/14 5/7/14 5/9/14 Enclosure 1 List of Attendees NRC Mr. S. Reynolds, Deputy Regional Administrator Ms. K. Fuller, Regional Counsel Mr. J. Clark, Acting Division Director, Division of Reactor Safety Mr. T. Pruett, Deputy Division Director, Division of Reactor Projects Mr. M. Haire, Branch Chief, Plant Support Branch 1, Division of Reactor Safety Mr. N. O Ms. V. Campbell, Branch Chief, Allegation and Enforcement Branch Mr. R. Kahler, Branch Chief, DPR, Office of Nuclear Security and Incident Response Mr. P. Elkmann, Senior Inspector, Plant Support Branch 1, Division of Reactor Safety Mr. C. Peabody, Senior Resident Inspector, Branch B, Division of Reactor Projects Mr. S. LaVie, Senior Specialist, DPR, Office of Nuclear Security and Incident Response Mr. D. Proulx, Senior Project Engineer, Branch B, Division of Reactor Projects Mr. J. Wray, Senior Enforcement Specialist, Office of Enforcement Mr. G. Guerra, Inspector, Plant Support Branch 1, Division of Reactor Safety Ms. R. Browder, Senior Enforcement Specialist, Allegation and Enforcement Branch Wolf Creek Nuclear Operating Corporation Mr. R. Smith, Chief Nuclear Officer Mr. M. Westman, Manager, Regulatory Affairs Mr. T. East, Superintendent, Emergency Planning Mr. W. Ketchum, Supervisor, Engineering Mr. W. Muilenburg, Supervisor, Licensing M. D. Michel, Instructor, Chemistry W o l f C reek Nu c lear O p e r atin g C o rp o r a ti on |
| /RA/ /RA/ /RA/ /RA/ /RA/ /RA/ /RA/ DATE 5/6/14 5/8/14 5/6/14 5/8/14 5/7/14 5/7/14 5/9/14 Enclosure 1 List of Attendees NRC Mr. S. Reynolds, Deputy Regional Administrator Ms. K. Fuller, Regional Counsel Mr. J. Clark, Acting Division Director, Division of Reactor Safety Mr. T. Pruett, Deputy Division Director, Division of Reactor Projects Mr. M. Haire, Branch Chief, Plant Support Branch 1, Division of Reactor Safety Mr. N. O Ms. V. Campbell, Branch Chief, Allegation and Enforcement Branch Mr. R. Kahler, Branch Chief, DPR, Office of Nuclear Security and Incident Response Mr. P. Elkmann, Senior Inspector, Plant Support Branch 1, Division of Reactor Safety Mr. C. Peabody, Senior Resident Inspector, Branch B, Division of Reactor Projects Mr. S. LaVie, Senior Specialist, DPR, Office of Nuclear Security and Incident Response Mr. D. Proulx, Senior Project Engineer, Branch B, Division of Reactor Projects Mr. J. Wray, Senior Enforcement Specialist, Office of Enforcement Mr. G. Guerra, Inspector, Plant Support Branch 1, Division of Reactor Safety Ms. R. Browder, Senior Enforcement Specialist, Allegation and Enforcement Branch Wolf Creek Nuclear Operating Corporation Mr. R. Smith, Chief Nuclear Officer Mr. M. Westman, Manager, Regulatory Affairs Mr. T. East, Superintendent, Emergency Planning Mr. W. Ketchum, Supervisor, Engineering Mr. W. Muilenburg, Supervisor, Licensing M. D. Michel, Instructor, Chemistry Wolf Creek Nuclear Operating Corporation
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| Regulatory Conference Inspection Report 05000482/201 3-502 Preliminary White Finding Enclosure 2 Wolf Creek Representatives
| | R egu l a t o r y C on f e rence Inspec t i on R epo r t 05000482/201 3-5 0 2 P reli mina r y W h i t e F i nd i ng Enclosure 2 W ol f C r ee k Rep r e s en t a t i v es |
| * Russell Smith - Site Vice President | | * R usse l l Sm it h - S it e V i c e P r es i dent |
| * Mike Westman - Manager Regulatory Affairs | | * M i k e W es t ma n - Manage r R egu l a t o r y A f f a ir s |
| * Timothy East - Superintendent EP | | * T i mo t h y East - Supe ri n tenden t E P |
| * Bill Muilenburg - Supervisor Licensing | | * B il l Mu ilenbu r g - Supe r v i so r L i cens i ng |
| * Bill Ketchum - Supervisor Engineer | | * B il l Ke tchu m - Supe r v i so r Eng i neer |
| * Dan Michel - Instructor II Enclosure 2 | | * D a n M iche l - I nstr uc t o r I I Enclosure 2 |
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| NRC's Preliminary finding | | NRC's Preli m i nary f i nding |
| * An apparent violation of 10 CFR 50.54(q)(2) was identified involving the failure to maintain adequate methods for assessing the actual or potential consequences of a radiological emergency between September 2012 and November 2013, in accordance with the requirements of 10 CFR 50.47(b)(9). | | * An appa r ent viola tion of 10 CFR 50.54 (q)(2) w as iden t i fied in v ol ving t he f a i lu r e t o ma i n t a in adequa t e me thods f or a ss e ssing t he a c t ual or po t en tial c on sequen c es of a r ad i o l ogi c al eme r gen c y be t ween S ep tember 2012 and N o vember 2013, in a cc o rdan c e w i t h t he r equi remen t s of 10 CFR 50.47 (b)(9). |
| * The inaccurate calculation was corrected on February 25, 2014. | | * The ina cc u r a t e c al cula tion w as c o rr e c t ed on Feb r ua r y 25, 2014. |
| * The inspectors determined the failure to maintain a Dose Assessment Process capable of providing a technically adequate estimate of offsite dose. This issue has been entered into the licensee's corrective action system as Condition Report 2013-0076247. Enclosure 2 Root Cause Evaluation Findings | | * The in s pe c t o r s de t e rmined t he failu r e t o ma i n tain a D o s e A ss e ss me nt P r o c e s s capab l e of p r o vid i ng a t e c hn i cally adequa t e e s tima t e of o f f s i t e do s e. This i ss ue has been en t e r ed in t o t he li c en s ee's c o rr e ct i v e a c tion s y s t em as Condition Repo r t 2013-0076 2 47. Enclosure 2 Roo t Cau se Ev alua t io n Findings |
| * ROOT CAUSE - Information Systems (IS) procedures and guidance did not require comprehensive verification and validation for risk significant software. | | * R OO T CAUS E - I n f o rm a t i on S ys t e m s (I S) p rocedu res and gu idance d i d not r equ i r e co m p r ehens i ve ve r i f i ca t i on and va li da t i on f or r i sk s i gn i f icant so ft w a r e. |
| * CONTRIBUTING CAUSE 1 - Less than adequate EP oversight of risk significant drill-identified issues. | | * C O N T R I BU T I N G CAUS E 1 - Less t han adequa t e E P ove r s i ght of r i sk s i gn i f icant d r ill-i den t i f i ed issues. |
| * Also determined the EDCP Containment Spray Filtration Toggle was not functional. | | * Also de t e rm i ned t he EDC P C on t a i n ment S p r ay F il tr a t i on T ogg l e was not f unc t i ona l. |
| * Determined the EDCP deficiencies were introduced with Version 3.6 issued in February 2003. Enclosure 2 Key Corrective Actions | | * D e t e rm ined t he EDC P de f i c i enc i es w e r e i n troduced wi t h V e r s i on 3.6 issued i n Feb r ua ry 2003. Enclosure 2 K e y Co rrect i v e Act io ns |
| * Improve Emergency Planning ownership of risk significant issues. | | * I m prov e E mergenc y P l ann i n g o wnersh ip o f r isk s i gn i f i can t i ssues. |
| * Improve Computer Software verification and validation (V&V). | | * I m prov e C o m pu t e r Soft w ar e ver i f i cat i o n and va li da ti o n (V&V). |
| * EDCP was corrected and issued February 25, 2014 including both filter factor and containment spray toggles. Enclosure 2 EDCP Field Team Data 11Other Event Trees Calculated Value SGTR Rad Mon Unit Vent & RWVent Rad Mon DBA Meteorology EAL | | * EDC P w a s correc t e d an d i ssue d Februar y 25, 201 4 i nc l ud i n g bo th f il te r facto r an d con t a i n ment spra y togg l es. Enclosure 2 EDCP Field Team Data 1 1Other Event Trees Calculated Value SGTR Rad Mon Unit Vent & RWVent Rad Mon DBA Meteorology EAL |
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| Enclosure 2 Vent Rad Monitor Detail (normal mode) Enclosure 2 | | Enclosure 2 V en t R a d Monito r Detai l (no r ma l mode) Enclosure 2 |
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| Vent Rad Monitor Detail (accident mode)
| | V en t R a d Monito r Detai l (a cciden t mode) |
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| Enclosure 2 Affect of the Deficiencies | | Enclosure 2 A f f e ct o f t h e De f i cien c ies |
| * Iodine concentration can be overestimated by a factor of ten | | * Iodine c on c en t r a tion c an be o v e r e s tima t ed by a f a c t or of t en |
| * However, concentration is not the only input to calculating dose | | * H o w e v e r , c on c en t r a tion is not t he only input t o c al cula ting do s e |
| * The EDCP deficiencies affect the dose | | * The EDC P de f i cien cies a f f e c t t he do s e |
| * Containment Spray operation > 30 minutes | | * C on tainment S p r ay ope r a tion > 30 minu t es |
| * Unit Vent is in accident mode with operable HEPA | | * Unit V ent is in a ccident mode w i th ope rable H E P A |
| * In these cases, the Iodine concentration is determined using an Iodine to Noble Gas ratio | | * I n t he s e c a s e s , t he I od i ne c on c en t r a tion is de t e rmined u sing an Iodine t o Noble Gas r a tio |
| * So, the result is dependent upon the Noble Gas concentration rather than the iodine concentration Enclosure 2 Affect of the Deficiencies (cont.) | | * S o, t he r e s u l t is dependent upon t he N ob l e Gas c on c en t r a tio n r a ther than t he iodine c on c en t r a tion Enclosure 2 A f f e ct o f t h e De f i cien c ie s (c on t.) |
| * The ten Design Basis Accidents in EDCP were reviewed to determine the significance of the deficiencies. o LOCA and Fuel Handling Accident o No credible scenarios for combining deficiencies Containment Spray TEDE Factor CDE Factor LOCA 1.5 1.5 Unit Vent Filtration TEDE Factor CDE Factor Fuel Handling Acc. 1.0 1.1 LOCA 3.0 3.8 Enclosure 2 Summary | | * T h e ten D e si gn Ba si s Acc i d e nts i n ED CP w e r e r e viewed t o d e t ermi n e the si gn i f i c a nce of t h e d e f i c i e nc i e s. o L O CA a n d Fu el Ha nd li n g Acc i d e n t o N o c r e d i b le s c e n ari os f or c o m b i n i n g d e f i c i e nc i es C o n t a i n m e n t S p ra y T E D E F a c t o r C D E F a c t or L O CA 1.5 1.5 U n it V e n t Filt r a ti o n T E D E F a c t o r C D E F a c t or Fu e l H andli n g Acc. 1.0 1.1 L O CA 3.0 3.8 Enclosure 2 S ummary |
| * EAL decision making was unaffected by these deficiencies o In order to have a dose assessment large enough to cause an EAL declaration, plant conditions will drive declarations o EDCP calculations lag plant conditions | | * EA L de c i sion ma king w as una f f e c t ed by t he s e de f i cien cies o I n o r de r t o ha ve a dose a ss e ssm en t la r g e enoug h t o c au se an EAL de c la r a tion , plan t c ondi tion s w il l d r i ve de c la r a tions o E DC P c al cula tion s la g plan t c ondi tions |
| * PAR decision making was unaffected by these deficiencies o Initial PARs are plant condition based o Dose assessment is used for follow-up PARs or to prove initial PARs | | * P AR de c i sion ma king w as una f f e c t ed by t he s e de f i cien cies o I ni t ia l P A R s are plan t c ondi t io n ba s ed o Do se a ss e ssm en t i s u s e d f o r follo w-u p P A R s o r t o p r o ve ini tial P A R s |
| * One of five EDCP calculation methods was affected with the largest impact involving a LOCA o Had this event actually occurred, a GE would have been declared based on plant conditions and a corresponding plant condition PAR evacuating 0-2 miles around and 10 miles downwind would be made o The EDCP deficiencies would not have any impact because they would not have been used to develop these PARs Enclosure 2 Wolf Creek Closing Remarks Russell Smith - Site Vice President & CNOO | | * One of f i v e EDC P c al cula tion me thods w as a f f e c t ed w i t h t he la r ge s t impa c t in v ol ving a LO C A o Ha d t hi s e v en t a c tuall y o cc u rr ed , a G E woul d ha ve bee n de c la r ed ba s e d o n plan t c ondi tion s and a c o rr e spondin g plan t c ondi tion P AR e v a c ua t in g 0-2 m ile s a r oun d an d 1 0 m ile s do w n w in d w oul d b e m ade o T h e E DC P de f i cien c ie s woul d no t ha ve an y i m pa ct be c au se they woul d no t ha ve bee n u s e d t o de velo p t he se P A R s Enclosure 2 Wolf C r eek Cl os i ng R e m a r ks Ru ss el l S m i t h - Si t e V ice P r e siden t & CN O O |
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| Enclosure 2 | | Enclosure 2 |
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| Acronym list
| | A c ro n y m li s t |
| * EP - Emergency Planning | | * EP - E mergen c y P l ann i ng |
| * EDCP - Emergency Dose Calculation Program | | * EDCP - E mergen c y D o s e C a lc u l at i on Program |
| * HEPA - High Efficiency Particulate Air | | * H E P A - H i gh E f fici en c y Part ic u l ate A i r |
| * LOCA - Loss of Coolant Accident | | * L OC A - Lo s s of C oo l ant A cci dent |
| * TEDE - Total Effective Dose Equivalent | | * T E D E - Total E f fe c t i v e D o s e Equ i v a l ent |
| * CDE - Committed Dose Equivalent | | * CDE - C o mm i tted D o s e Equ i v a l ent |
| * EAL - Emergency Action Level | | * EAL - E mergen c y A c t i on Le v el |
| * PAR - Protective Action Recommendation | | * P AR - Prote c t i v e A c t i on R e c o mmendat i on |
| * GE - General Emergency | | * G E - General E mergen c y |
| * CNOO - Chief Nuclear Operating Officer Enclosure 2}} | | * CNO O - C h i ef N u cl ear Operat i ng O f f ic er Enclosure 2}} |
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Category:Letter
MONTHYEARIR 05000482/20244202024-10-31031 October 2024
Security Baseline Inspection Report 05000482/2024420
05000482/LER-2024-001-01, Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing2024-10-22022 October 2024
Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing
ML24296B1902024-10-22022 October 2024
10 CFR 50.55a Requests for the Fifth Ten-Year Interval Inservice Testing Program
05000482/LER-2024-002, Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve2024-10-21021 October 2024
Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve
ML24284A2842024-10-10010 October 2024
(Wcgs), Revision of One Form That Implements the Radiological Emergency Response Plan (RERP)
ML24283A0752024-10-0909 October 2024
Notification of Commercial Grade Dedication Inspection (05000482/2025012) and Request for Information
ML24199A1712024-09-17017 September 2024
Issuance of Amendment No. 241 Revise Ventilation Filter Testing Program Criteria and Administrative Correction of Absorber in Technical Specification 5.5.11
ML24260A0712024-09-12012 September 2024
License Amendment Request for a Risk-Informed Resolution to GSI-191
IR 05000482/20240102024-09-10010 September 2024
Biennial Problem Identification and Resolution Inspection Report 05000482/2024010 (Public)
ML24255A8642024-09-0606 September 2024
Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification
ML24248A2492024-09-0404 September 2024
Inservice Inspection Program Fourth Interval, Third Period, Refueling Outage 26 Owner’S Activity Report
ML24248A0762024-09-0404 September 2024
Containment Inservice Inspection Program Third Interval, Second Period, Refueling Outage 26 Owner’S Activity Report
ML24241A2212024-08-29029 August 2024
Notice of Enforcement Discretion for Wolf Creek Generating Station
ML24240A2642024-08-27027 August 2024
Corporation - Request for Notice of Enforcement Discretion Regarding Technical Specification 3.7.5, Auxiliary Feedwater (AFW) System
ML24239A3972024-08-23023 August 2024
Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243
IR 05000482/20240052024-08-14014 August 2024
Updated Inspection Plan for Wolf Creek Generating Station (Report 05000482/2024005)
ML24227A5562024-08-14014 August 2024
Application to Revise Technical Specifications to Adopt TSTF-569-A, Revision 2, Revision of Response Time Testing Definitions
ML24213A3352024-07-31031 July 2024
License Amendment Request to Revise Technical Specification 3.2.1, Heat Flux Hot Channel Factor (Fq(Z)) (Fq Methodology), to Implement the Methodology from WCAP-17661-P-A, Revision 1.
ML24206A1252024-07-24024 July 2024
Revision of Three Procedures and Two Forms That Implement the Radiological Emergency Response Plan (RERP)
IR 05000482/20240022024-07-18018 July 2024
Integrated Inspection Report 05000482/2024002
05000482/LER-2024-001, Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing2024-07-0202 July 2024
Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing
IR 05000482/20244012024-07-0202 July 2024
Security Baseline Inspection Report 05000482/2024401
ML24178A4142024-06-26026 June 2024
Revision of One Procedure and One Form That Implement the Radiological Emergency Response Plan (RERP)
ML24178A3672024-06-26026 June 2024
Correction to 2023 Annual Radioactive Effluent Release Report – Report 47
ML24162A1632024-06-11011 June 2024
Operating Corporation – Notification of Biennial Problem Identification and Resolution Inspection and Request for Information (05000482/2024010)
ML24150A0562024-05-29029 May 2024
Foreign Ownership, Control or Influence (FOCI) Information – Change to Lists of Owners, Officers, Directors and Executive Personnel - Form 405F Amendment
ML23345A1602024-05-0909 May 2024
Revision of Safety Evaluation for Amendment No. 237 Request for Deviation from Fire Protection Requirements
ML24089A2622024-04-29029 April 2024
Financial Protection Levels
ML24118A0032024-04-27027 April 2024
2023 Annual Radioactive Effluent Release Report - Report 47
ML24118A0022024-04-27027 April 2024
Wolf Generating Nuclear Station - 2023 Annual Radiological Environmental Operating Report
ML24113A1882024-04-19019 April 2024
Foreign Ownership, Control or Influence Information - Change to Lists of Owners, Officers, Directors and Executive Personnel - Form 405F Amendment
ML24109A1212024-04-18018 April 2024
(WCGS) Form 5 Exposure Report for Calendar Year 2023
ML24109A1842024-04-18018 April 2024
Cycle 27 Core Operating Limits Report
IR 05000482/20240012024-04-17017 April 2024
Integrated Inspection Report 05000482/2024001
ML24114A1442024-04-15015 April 2024
Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37
ML24106A1482024-04-15015 April 2024
Notification of Inspection (NRC Inspection Report 05000482/2024003) and Request for Information
ML24098A0052024-04-0707 April 2024
2023 Annual Environmental Operating Report
ML24089A1352024-03-29029 March 2024
10 CFR 50.46 Annual Report of Emergency Core Cooling System (ECCS) Evaluation Model Changes
ML24089A0972024-03-29029 March 2024
Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations
ML24074A3312024-03-14014 March 2024
Missed Quarterly Inspection Per 40 CFR 266 Subpart N
ML24080A3452024-03-11011 March 2024
7 of the Wolf Creek Generating Station Updated Safety Analysis Report
IR 05000482/20240122024-03-11011 March 2024
Fire Protection Team Inspection Report 05000482/2024012
ML24016A0702024-03-0808 March 2024
Issuance of Amendment No. 240 Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications
ML24068A1992024-03-0707 March 2024
Changes to Technical Specification Bases - Revisions 93 and 94
ML24066A0672024-03-0505 March 2024
4-2022-024 Letter - OI Closure to Licensee
ML24061A2642024-03-0101 March 2024
Revision of Two Procedures That Implement the Radiological Emergency Response Plan (RERP) for Wolf Creek Generating Station (WCGS) Commissioners
ML24059A1702024-02-28028 February 2024
Annual Fitness for Duty Program Performance Report, and Annual Fatigue Report for 2023
IR 05000482/20230062024-02-28028 February 2024
Annual Assessment Letter for Wolf Creek Generating Station Report 05000482/2023006
ML24026A0212024-02-27027 February 2024
Issuance of Amendment No. 239 Modified Implementation Date of License Amendment No. 238
ML24050A0012024-02-19019 February 2024
(Wcgs), Revision of One Form That Implements the Radiological Emergency Response Plan (RERP)
2024-09-06
[Table view]
Category:Meeting Briefing Package/Handouts
MONTHYEARML24311A1572024-11-0606 November 2024
Slides for Pre-submittal Public Teleconference Meeting for License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
ML24180A0092024-06-28028 June 2024
July 23, 2024, Portable Lighting Amendment 237 Meeting Slides
ML24071A2102024-03-25025 March 2024
March 25, 2024, Portable Lighting Revised SE Meeting Slides
ML24085A2732024-03-21021 March 2024
Comments for March 25, 2024 Meeting on Portable Lighting Revised SE
ML23275A1712023-10-16016 October 2023
October 16, 2023, Licensee Pre-submittal Meeting Slides - License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2 for Wolf Creek Generating Station
ML21333A1512021-11-29029 November 2021
Pre-Submittal Meeting Slides License Amendment Request Addressing Portable Lighting for Operator Manual Actions
ML21179A0892021-07-13013 July 2021
Background Information July 13, 2021, Pre-Submittal Public Teleconference
ML20308A7332020-11-18018 November 2020
Slides for GSI-191 Pre-Submittal Public Teleconference November 18, 2020
ML18299A0492018-10-30030 October 2018
Accident Analyses Methodology Transition LAR Public Meeting
IR 05000482/20174072017-12-22022 December 2017
Summary of Closed Regulatory Conference to Discuss Wolf Creek, Unit 1, Security Inspection Report 05000482/2017407
ML16271A4822016-09-27027 September 2016
Summary of Regulatory Conference to Discuss Safety Significance of Wolf Creek Generating Station Emergency Generator Excitation Diode Apparent Violation
ML16236A0952016-08-25025 August 2016
and Wolf Creek Generating Station - August 25, 2016, Class 1E Electrical Equipment Air Conditioning System Pre-Application Meeting
ML16095A0782016-04-12012 April 2016
Slides for the WCGS Meeting Discussion 4/12/16
ML16095A0852016-04-12012 April 2016
Large Scale Head Loss Test Specification 4/12/16
ML16095A0802016-04-12012 April 2016
Large Scale Penetration Test Specification 4/12/16
ML16095A0922016-03-31031 March 2016
Large Scale Penetration and Head Loss Test Plan 4/12/16
ML14188C4812014-07-0707 July 2014
Summary of Annual Assessment Meeting with Wolf Creek Generating Station
ML14134A1842014-05-14014 May 2014
Summary of Public Meeting to Discuss an Apparent Violation Identified at Wolf Creek Generating Station
ML14038A3852014-02-0606 February 2014
1/22/2014 - Summary of Public Meeting to Discuss Corrective Actions Implemented to Address the Chilling Effect Letter
ML13218A0212013-08-0707 August 2013
Licensee Slides, 08/07/13 Preapplication Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Long-Term Corrective Actions for Water Hammer Events in the Essential Service Water System at Wolf Creek
ML13205A2142013-07-30030 July 2013
Operating Corporation - Slides for Pre-application Meeting on 7/30/13 - Core Design and Safety Analysis Methodology Transition License Amendment Request for Wolf Creek Generating Station
ML12263A3622012-09-20020 September 2012
Pre-application Meeting Slide Core Design and Safety Analysis Methodology Transition License Amendment Request TAC No. ME9495)
ML12191A1742012-07-0909 July 2012
6/25/2012 Summary of Public Meeting with Wolf Creek Nuclear Operating Corporation
ML1110104292011-04-11011 April 2011
Summary of Annual Performance Assessment Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Wolf Creek Generating Station Performance for the NRC Inspection Period Ending December 31, 2010
ML1016901162010-06-16016 June 2010
6/16/2010 Construction Reactor Oversight Process Category 2 Public Meeting Handout: Meeting Slides (Enforcement Cases)
ML1016204902010-06-16016 June 2010
Notice of Construction Reactor Oversight Process Category 2 Public Meeting Handout: Wolf Creek 2, Notice of Violation and Proposed Imposition of Civil Penalty, Dated 11/21/1984
ML1013404892010-05-14014 May 2010
Summary of Annual Performance Assessment Meeting with Wolf Creek Nuclear Operating Corporation to Discuss the Wolf Creek Generating Station Performance for the NRC Inspection Period from January 1 Through December 31, 2009
ML0933702032009-12-0303 December 2009
Summary of Public Meeting for Wolf Creek Generating Station
ML0933801482009-11-20020 November 2009
Licensee Handouts from November 20, 2009, Public Meeting with Union Electric Company and Wolf Creek Nuclear Operating Company to Discuss GL 2004-02 Response Rai'S
ML0913300232009-05-13013 May 2009
Meeting Slides, Successful Licensing of the Als Fpga Based Safety Related I&C Platform
ML0912600692009-05-0606 May 2009
Lessons Learned Using Digital I&C Interim Staff Guidance Workshop
ML0902102422009-01-15015 January 2009
Licensee Slides, January 15, 2009, Category 1 Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Changes to Post Fire Shutdown Unresolved Items Analysis Methods Pre-Application for Wolf Creek Generating Station
ML0834700222008-12-11011 December 2008
Slides, Category 2 Public Meeting Digital Instrumentation and Control Steering Committee
M080717, M080717-Commission Briefing Slides/Exhibits Briefing on Fire Protection2008-07-17017 July 2008
M080717-Commission Briefing Slides/Exhibits Briefing on Fire Protection
ML0817706682008-06-25025 June 2008
Summary of Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Several Initiatives That Were Being Implemented to Improve Plant Performance at Wolf Creek
ML0803706102008-01-11011 January 2008
Westinghouse Electric Company LLC, LTR-CDME-08-2, Rev. 1 NP-Attachment, Meeting Handouts from the December 13, 2007 Meeting with Wolf Creek and NRR on H*/B*.
ML0729204682007-10-29029 October 2007
09/25/2007, Summary of Meeting Between the U.S. Nuclear Regulatory Commission Staff and Strategic Teaming and Resource Sharing Representatives to Discuss License Renewal Activities
ML0721501532007-08-0202 August 2007
NRC Staff Handout for August 2, 2007, Meeting with Wolf Creek Nuclear Operating Corporation
ML0721102382007-07-24024 July 2007
Performanc Contracting, Inc.'S Powerpoint Slide, Proposed Wolf Creek/Callaway Test Configuration
ML0719303772007-07-11011 July 2007
Handouts (NRC and Licensee) for Meeting with Representatives of Wolf Creek Nuclear Operating Corporation
ML0718606902007-06-19019 June 2007
06/19-20/2007 Slides,Fabrication Records Review, from Category 2 Public Meeting Between the NRC Staff and the Expert Panel for the Wolf Creek Advanced Finite Element Analyses (Fea)
ML0716203882007-06-0101 June 2007
06/01/07 - Presentation Material, Advanced Fea Crack Growth Calculations for Evaluation of PWR Pressurizer Nozzle Dissimilar Metal Weld Circumferential Pwscc.
ML0733409182007-05-31031 May 2007
05/31/2007 Presentation by J. Cudsworth NRC Treatment of Issues Other than Category 2 Issues for License Renewal
ML0713703642007-05-17017 May 2007
Handout for Meeting with Wolf Creek Nuclear Operating Corporation on the Licensee'S Application for the Main Steam and Feedwater Isolation System (Msfis) Modification
ML0713506532007-05-0808 May 2007
Slides, Recommendations for Critical Flaw Size Calculations (in Wolf Creek Advanced Fea Project).
ML0713506462007-05-0808 May 2007
Industry Slides, Advanced Fea Crack Growth Calculations for Evaluation of PWR Pressurizer Nozzle Dissimilar Metal Weld Circumferential PWSCC, from Status Meeting on Implications of Wolf Creek Dissimilar Metal Weld Inspections
ML0713506512007-05-0808 May 2007
Slides, Category 2 Public Meeting with NEI on the Implications of the Wolf Creek Dissimilar Metal Weld Inspections.
ML0713603732007-05-0101 May 2007
Enclosure-1 05/01/2007 Dominion Engineering Presentation Advanced Fea Crack Growth Calculations for Evaluation of PWR Pressurizer Nozzle Dissimilar Metal Weld Circumferential Pwscc.
ML0713603962007-05-0101 May 2007
Enclosure 2-05/01/2007 Engineering Mechanics Corporation of Columbus Presentation, NRC Welding Residual Stress Solutions as Generated by Battelle and Emc2.
ML0701704732007-01-19019 January 2007
12/19/2006 Summary of Public Meetings Related to the Review of the Wolf Creek Generating Station License Renewal Application
2024-06-28
[Table view]
Category:Meeting Summary
MONTHYEARML24268A0722024-09-24024 September 2024
Summary of August 28, 2024, Public Meeting to Discuss Cyber Security Regulatory Issues Regarding Wolf Creeks Implementation of Advanced Remote Monitoring Using Wireless
ML24212A0372024-08-0707 August 2024
Summary of July 23, 2024, Teleconference with Wolf Creek Nuclear Operating Corporation Regarding Wolf Creek Generating Station, Unit 1, Amendment No. 237, Allowing the Use of Portable Lighting
ML24088A3122024-04-0101 April 2024
Summary of March 25, 2024, Teleconference with Wolf Creek Nuclear Operating Corporation Regarding Revised Safety Evaluation for Wolf Creek Generating Station Unit 1, Amendment No. 237, Allowing the Use of Portable Lighting
ML23303A2182023-11-0606 November 2023
Summary of October 16, 2023, Pre-Submittal Teleconference with Wolf Creek Nuclear Operating Corporation Regarding a License Amendment Request to Adopt TSTF-505 for Wolf Creek Generating Station, Unit 1
ML22147A0932022-06-0606 June 2022
2021 Annual Assessment Public Meeting Summary
ML22011A0862022-01-11011 January 2022
Summary of January 10, 2022, Pre-Submittal Teleconference with Wolf Creek Nuclear Operating Corporation Regarding a License Amendment Request to Use Portable Lighting for Wolf Creek Generating Station, Unit 1
ML21333A1312021-12-0707 December 2021
Summary of Meeting with Wolf Creek Nuclear Operating Corporation Diesel Generator Completion Time License Amendment Request for Wolf Creek Generating Station
ML21200A1102021-07-21021 July 2021
Summary of July 13, 2021, Pre-Submittal Teleconference with Wolf Creek Nuclear Operating Corporation Regarding a Temporary Emergency Preparedness Exercise Exemption Request
ML21140A3892021-05-24024 May 2021
Riv Column 1 EOC 2020 Public Meeting Summary
ML21127A1322021-05-11011 May 2021
Summary of April 16, 2021, Conference Call with Representatives of Wolf Creek Generating Station Regarding the Spring 2021 Steam Generator Tube Inspections
ML20332A0422020-12-0101 December 2020
Summary of November 19, 2020, Pre-Submittal Teleconference with Wolf Creek Nuclear Operating Corporation an Emergency Response Organization Staffing License Amendment Request
ML20332A0462020-11-30030 November 2020
Summary of November 18, 2020, Pre-Submittal Teleconference with Wolf Creek Nuclear Operating Corporation a Risk-Informed Generic Safety Issue (GSI)-191 License Amendment Request
ML20189A2832020-07-0707 July 2020
Summary of Region IV Annual Assessment Public Meeting
ML19143A4182019-05-21021 May 2019
Summary of Public Meeting with Wolf Creek Nuclear Operation Corporation
ML19140A4742019-05-20020 May 2019
Closed Meeting with Wolf Creek Nuclear Operating Corporation to Conduct a Mediation Session Regarding Falsification of Documentation Associated with Licensee Maintenance Activities
ML18313A2542018-11-16016 November 2018
Summary of Public Meeting with Wolf Creek Nuclear Operating Corporation Regarding License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses for Wolf Creek Generating Station
ML17276B4892017-10-23023 October 2017
9/25/17 Summary of Public Meeting with Wolf Creek Nuclear Operating Corporation Regarding the Proposed LAR for Change in Emergency Plan Staff Augmentation Response Times for Wolf Creek Generating Station (CAC No. MG0174; EPID L-2017-LRM-001
ML16271A4822016-09-27027 September 2016
Summary of Regulatory Conference to Discuss Safety Significance of Wolf Creek Generating Station Emergency Generator Excitation Diode Apparent Violation
ML16250A1652016-09-0909 September 2016
8/25/16 Summary of Preapplication Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Amendment Request to Transition to Westinghouse Analyses Methodologies and Alternate Source Term at Wolf Creek Generating Station
ML16243A5132016-09-0101 September 2016
Summary of August 25, 2016, Public Meeting with Wolf Creek Nuclear Operating Corporation and Amerenue Regarding a Proposed Application for a New Technical Specification for the Class 1E Electrical Equipment Air Conditioning System (MF8118 a
ML16106A1742016-04-22022 April 2016
Summary of Meeting with Wolf Creek Nuclear Operating Company to Discuss the Generic Safety Issue (GSI)-191 Testing Plan/Fiber Penetration and Head Loss Testing Approach for Wolf Creek Generating Station
ML15182A0952015-06-30030 June 2015
Summary of Annual Assessment Meeting with Wolf Creek Nuclear Operating Corporation (WCNOC) Regarding Wolf Creek Generating Station 2014 Performance
ML14188C4812014-07-0707 July 2014
Summary of Annual Assessment Meeting with Wolf Creek Generating Station
ML14134A1842014-05-14014 May 2014
Summary of Public Meeting to Discuss an Apparent Violation Identified at Wolf Creek Generating Station
ML14038A3852014-02-0606 February 2014
1/22/2014 - Summary of Public Meeting to Discuss Corrective Actions Implemented to Address the Chilling Effect Letter
ML13221A2132013-08-12012 August 2013
8/7/2013 - Summary of Preapplication Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Long-Term Corrective Actions for Water Hammer Events in the Essential Service Water System at Wolf Creek
ML13221A2152013-08-12012 August 2013
7/30/2013 - Summary of Preapplication Meeting with Wolf Creek Nuclear Operating Company to Discuss Proposed Transition to Westinghouse Methodologies for Core Design and Non-LOCA Safety Analyses at Wolf Creek Generating Station
ML13121A4892013-05-0101 May 2013
End of Cycle Meeting Summary 4-18-13
ML13077A0732013-04-0101 April 2013
Summary of 2/28/13 and 3/11/13 Conference Calls with Licensee and Its Contractors Ongoing Steam Generator Tube Inspection Activities During Refueling Outage 19
ML12355A6922012-12-20020 December 2012
Summary of Public Meeting with Wolf Creek Nuclear Operating Corp Re Improved Station Performance
ML12276A2652012-11-0101 November 2012
Meeting Summary with Wolf Creek Nuclear Operating Corporation to Discuss Transition from Current to NRC-Approved Westinghouse Methodologies for Performing the Core Design and Non-LOCA Safety Analysis at Wolf Creek
ML12191A1742012-07-0909 July 2012
6/25/2012 Summary of Public Meeting with Wolf Creek Nuclear Operating Corporation
ML12191A1462012-07-0606 July 2012
6/26/2012 - Summary of Public Meeting to Discuss Performance of Wolf Creek Nuclear Operating Corporation
ML13246A3802012-05-0808 May 2012
Email from M. King, NRR on Ioeb Clearinghouse Screening Summary for Tuesday, May 8, 2012
ML1207601012012-03-16016 March 2012
Summary of Public Meeting with Wolf Creek Nuclear Operating Corporation
ML13246A3782012-02-16016 February 2012
Email from M. King, NRR on Ioeb Clearinghouse Screening Summary for Thursday, February 16, 2012
ML13246A3772012-01-31031 January 2012
Email from M. King, NRR on Ioeb Clearinghouse Screening Summary for Tuesday, January 31, 2012
ML13246A3762012-01-23023 January 2012
Email from M. King, NRR on Ioeb Clearinghouse Screening Summary for Monday, January 23, 2012
ML12011A1012012-01-19019 January 2012
Summary of Meeting with NEI and to Address Di&C Issues
ML13246A3742012-01-17017 January 2012
Email from M. King, NRR on Ioeb Clearinghouse Screening Summary for Tuesday, January 17, 2012
ML1110104292011-04-11011 April 2011
Summary of Annual Performance Assessment Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Wolf Creek Generating Station Performance for the NRC Inspection Period Ending December 31, 2010
ML1024506282010-09-0202 September 2010
Summary of Public Meeting with Wolf Creek Nuclear Operating Corporation
ML1013404892010-05-14014 May 2010
Summary of Annual Performance Assessment Meeting with Wolf Creek Nuclear Operating Corporation to Discuss the Wolf Creek Generating Station Performance for the NRC Inspection Period from January 1 Through December 31, 2009
ML0933805662009-12-17017 December 2009
Summary of Meeting with Union Electric Company and Wolf Creek Nuclear Operating Company to Discuss NRC Requests for Additional Information on Generic Letter 2004-02 Sent 7/31/2009 and 8/27/2009, Respectively
ML0933702032009-12-0303 December 2009
Summary of Public Meeting for Wolf Creek Generating Station
ML0924607142009-09-28028 September 2009
Summary of Meeting with Union Electric Co., and Wolf Creek, to Discuss Draft Requests for Additional Information on GL 2004-02 for Callaway, Unit 1, and Wolf Creek
ML0911205282009-04-21021 April 2009
Summary of Annual Performance Assessment Meeting for Wolf Creek Generating Station
ML0902102062009-01-23023 January 2009
Summary of Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Changes to Post Fire Shutdown Unresolved Items Analysis Methods Pre-Application for Wolf Creek Generating Station
ML0829607972008-10-22022 October 2008
Summary of Meeting with Wolf Creek, Discussing Several Initiatives Being Implemented to Improve Plant Performance
ML0817706682008-06-25025 June 2008
Summary of Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Several Initiatives That Were Being Implemented to Improve Plant Performance at Wolf Creek
2024-09-24
[Table view]
Category:Slides and Viewgraphs
MONTHYEARML24311A1572024-11-0606 November 2024
Slides for Pre-submittal Public Teleconference Meeting for License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
ML24180A0092024-06-28028 June 2024
July 23, 2024, Portable Lighting Amendment 237 Meeting Slides
ML24071A2102024-03-25025 March 2024
March 25, 2024, Portable Lighting Revised SE Meeting Slides
ML23275A1712023-10-16016 October 2023
October 16, 2023, Licensee Pre-submittal Meeting Slides - License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2 for Wolf Creek Generating Station
ML21333A1512021-11-29029 November 2021
Pre-Submittal Meeting Slides License Amendment Request Addressing Portable Lighting for Operator Manual Actions
ML20310A2232020-11-19019 November 2020
Slides for ERO Staffing pre-submittal Public Teleconference November 19, 2020 (L-2020-LRM-0104)
IR 05000482/20174072017-12-22022 December 2017
Summary of Closed Regulatory Conference to Discuss Wolf Creek, Unit 1, Security Inspection Report 05000482/2017407
ML16236A0952016-08-25025 August 2016
and Wolf Creek Generating Station - August 25, 2016, Class 1E Electrical Equipment Air Conditioning System Pre-Application Meeting
ML16236A0972016-08-25025 August 2016
Operating Corporation - August 25, 2016, Core Design and Safety System Analysis Methodology Transition License Amendment Request Revised
ML16095A0782016-04-12012 April 2016
Slides for the WCGS Meeting Discussion 4/12/16
ML14188C4812014-07-0707 July 2014
Summary of Annual Assessment Meeting with Wolf Creek Generating Station
ML14134A1842014-05-14014 May 2014
Summary of Public Meeting to Discuss an Apparent Violation Identified at Wolf Creek Generating Station
ML14038A3852014-02-0606 February 2014
1/22/2014 - Summary of Public Meeting to Discuss Corrective Actions Implemented to Address the Chilling Effect Letter
ML13218A0212013-08-0707 August 2013
Licensee Slides, 08/07/13 Preapplication Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Long-Term Corrective Actions for Water Hammer Events in the Essential Service Water System at Wolf Creek
ML13219A1932013-08-0707 August 2013
Licensee Slides (Final), 08/07/13 Preapplication Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Long-Term Corrective Actions for Water Hammer Events in the Essential Service Water System at Wolf Creek
ML13205A2142013-07-30030 July 2013
Operating Corporation - Slides for Pre-application Meeting on 7/30/13 - Core Design and Safety Analysis Methodology Transition License Amendment Request for Wolf Creek Generating Station
ML13121A4892013-05-0101 May 2013
End of Cycle Meeting Summary 4-18-13
ML12263A3622012-09-20020 September 2012
Pre-application Meeting Slide Core Design and Safety Analysis Methodology Transition License Amendment Request TAC No. ME9495)
ML12191A1742012-07-0909 July 2012
6/25/2012 Summary of Public Meeting with Wolf Creek Nuclear Operating Corporation
ML1110104292011-04-11011 April 2011
Summary of Annual Performance Assessment Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Wolf Creek Generating Station Performance for the NRC Inspection Period Ending December 31, 2010
ML1016901162010-06-16016 June 2010
6/16/2010 Construction Reactor Oversight Process Category 2 Public Meeting Handout: Meeting Slides (Enforcement Cases)
ML1013404892010-05-14014 May 2010
Summary of Annual Performance Assessment Meeting with Wolf Creek Nuclear Operating Corporation to Discuss the Wolf Creek Generating Station Performance for the NRC Inspection Period from January 1 Through December 31, 2009
ML0933702032009-12-0303 December 2009
Summary of Public Meeting for Wolf Creek Generating Station
ML0933801482009-11-20020 November 2009
Licensee Handouts from November 20, 2009, Public Meeting with Union Electric Company and Wolf Creek Nuclear Operating Company to Discuss GL 2004-02 Response Rai'S
ML0913300232009-05-13013 May 2009
Meeting Slides, Successful Licensing of the Als Fpga Based Safety Related I&C Platform
ML0912600762009-05-0606 May 2009
Lessons Learned Using Digital I&C Interim Staff Guidance Workshop Application of ISG-4 During Wolf Creek and Oconee Reviews
ML0912600692009-05-0606 May 2009
Lessons Learned Using Digital I&C Interim Staff Guidance Workshop
ML0902102422009-01-15015 January 2009
Licensee Slides, January 15, 2009, Category 1 Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Changes to Post Fire Shutdown Unresolved Items Analysis Methods Pre-Application for Wolf Creek Generating Station
ML0834700222008-12-11011 December 2008
Slides, Category 2 Public Meeting Digital Instrumentation and Control Steering Committee
M080717, M080717-Commission Briefing Slides/Exhibits Briefing on Fire Protection2008-07-17017 July 2008
M080717-Commission Briefing Slides/Exhibits Briefing on Fire Protection
ML0817706682008-06-25025 June 2008
Summary of Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Several Initiatives That Were Being Implemented to Improve Plant Performance at Wolf Creek
ML0813606472008-06-10010 June 2008
05/01/2008-Summary of Public Meeting on Safety Evaluation Report with Open Items Regarding the Wolf Creek Generating Station License Renewal Review
ML0721102382007-07-24024 July 2007
Performanc Contracting, Inc.'S Powerpoint Slide, Proposed Wolf Creek/Callaway Test Configuration
ML0720601382007-07-17017 July 2007
Slides from Meeting Between NRC Staff and Wolf Creek Panel Enclosures 2 to 3, Advanced Fea Crack Growth Calculations for Evaluation of PWR Pressurizer Nozzle Dissimilar Metal Weld Circumferential Pwscc.
ML0719303772007-07-11011 July 2007
Handouts (NRC and Licensee) for Meeting with Representatives of Wolf Creek Nuclear Operating Corporation
ML0718606902007-06-19019 June 2007
06/19-20/2007 Slides,Fabrication Records Review, from Category 2 Public Meeting Between the NRC Staff and the Expert Panel for the Wolf Creek Advanced Finite Element Analyses (Fea)
ML0716203882007-06-0101 June 2007
06/01/07 - Presentation Material, Advanced Fea Crack Growth Calculations for Evaluation of PWR Pressurizer Nozzle Dissimilar Metal Weld Circumferential Pwscc.
ML0733409182007-05-31031 May 2007
05/31/2007 Presentation by J. Cudsworth NRC Treatment of Issues Other than Category 2 Issues for License Renewal
ML0713703642007-05-17017 May 2007
Handout for Meeting with Wolf Creek Nuclear Operating Corporation on the Licensee'S Application for the Main Steam and Feedwater Isolation System (Msfis) Modification
ML0713506512007-05-0808 May 2007
Slides, Category 2 Public Meeting with NEI on the Implications of the Wolf Creek Dissimilar Metal Weld Inspections.
ML0713506532007-05-0808 May 2007
Slides, Recommendations for Critical Flaw Size Calculations (in Wolf Creek Advanced Fea Project).
ML0713603962007-05-0101 May 2007
Enclosure 2-05/01/2007 Engineering Mechanics Corporation of Columbus Presentation, NRC Welding Residual Stress Solutions as Generated by Battelle and Emc2.
ML0713603732007-05-0101 May 2007
Enclosure-1 05/01/2007 Dominion Engineering Presentation Advanced Fea Crack Growth Calculations for Evaluation of PWR Pressurizer Nozzle Dissimilar Metal Weld Circumferential Pwscc.
ML0701601892006-12-19019 December 2006
12/19/2006, Viewgraphs from Meeting with Wolf Creek Generating Station to Discuss License Renewal Process and Environmental Scoping
ML0635603582006-11-30030 November 2006
Industry Presentation Slides: MRP-139 Analysis Basis
ML0635603462006-11-30030 November 2006
November 30, 2006 NRC Presentation Slides: Wolf Creek Flaw Evaluation
ML0632100772006-11-16016 November 2006
NRC Presentation: NRC Perspective on Wolf Creek Inspection Results
ML0632100802006-11-16016 November 2006
Industry Presentations: Nov. 16, 2006 Public Meeting
ML0622804372006-08-16016 August 2006
Handouts from Wolf Creek Nuclear Operating Corporation and from Union Electric Company for Meeting with NRC on the Main Steam Isolation Valve (MSIV) Operability Determination
ML0618000292006-06-28028 June 2006
Handout for June 28, 2006, Meeting with Representatives of Wolf Creek Nuclear Operating Corporation for Wolf Creek Generating Station on the Main Steam and Feedwater Isolation System (Msfis) Controls Replacement Project
2024-06-28
[Table view] |
Text
May 14, 2014 Mr. Adam C. Heflin, President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839
SUBJECT:
SUMMARY
OF PUBLIC MEETING TO DISCUSS AN APPARENT VIOLATION IDENTIFIED AT WOLF CREEK GENERATING STATION
Dear Mr. Heflin,
On April 30, 2014, members of the U.S. Nuclear Regulatory Commission (NRC) staff met with representatives of Wolf Creek Nuclear Operating Corporation at the Region IV office in Arlington, Texas, to discuss an apparent violation identified at Wolf Creek Generating Station. The apparent violation concerned the accuracy of the licand was discussed in NRC Inspection Report 05000482/2013502 (ADAMS ML14092A618). The licensee presented its perspective on the circumstances of the violation and the safety significance. The list of attendees and enclosed. made available electronically for public inspection in the NRC Public Document Room or from the NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. To receive a summary of future meetings and other plant-specific e-mail distributions, you must subscribe to the Operating Reactor Correspondence electronic distribution for this plant via http://www.nrc.gov/public-involve/listserver/plants-by-region.html. Once subscribed, if you wish to discontinue receiving electronic distribution, you may unsubscribe at any time by visiting the same web address above. Sincerely, /RA/ V.Gaddy for Mark S. Haire, Chief Plant Support Branch 1 Division of Reactor Safety Docket No. 50-482 License No. NPF-42
Enclosures:
- 1. List of Attendees 2. WCNOC Presentation Slides
SUNSI Review MSH By: Non-Sensitive Sensitive Publicly Available MSH Non-Publicly Available Keyword: OFFICE DRS/PSB1 DRP/PBB DRP/PBB DRS/PSB1 ACES DRP/CPBB DRS/CPSB1 NAME P. Elkmann C. Peabody D. Proulx G. Guerra R. Browder MHaire/VGaddy SIGNATURE /RA/ /RA/ /RA/ /RA/ /RA/ /RA/ /RA/ DATE 5/6/14 5/8/14 5/6/14 5/8/14 5/7/14 5/7/14 5/9/14 Enclosure 1 List of Attendees NRC Mr. S. Reynolds, Deputy Regional Administrator Ms. K. Fuller, Regional Counsel Mr. J. Clark, Acting Division Director, Division of Reactor Safety Mr. T. Pruett, Deputy Division Director, Division of Reactor Projects Mr. M. Haire, Branch Chief, Plant Support Branch 1, Division of Reactor Safety Mr. N. O Ms. V. Campbell, Branch Chief, Allegation and Enforcement Branch Mr. R. Kahler, Branch Chief, DPR, Office of Nuclear Security and Incident Response Mr. P. Elkmann, Senior Inspector, Plant Support Branch 1, Division of Reactor Safety Mr. C. Peabody, Senior Resident Inspector, Branch B, Division of Reactor Projects Mr. S. LaVie, Senior Specialist, DPR, Office of Nuclear Security and Incident Response Mr. D. Proulx, Senior Project Engineer, Branch B, Division of Reactor Projects Mr. J. Wray, Senior Enforcement Specialist, Office of Enforcement Mr. G. Guerra, Inspector, Plant Support Branch 1, Division of Reactor Safety Ms. R. Browder, Senior Enforcement Specialist, Allegation and Enforcement Branch Wolf Creek Nuclear Operating Corporation Mr. R. Smith, Chief Nuclear Officer Mr. M. Westman, Manager, Regulatory Affairs Mr. T. East, Superintendent, Emergency Planning Mr. W. Ketchum, Supervisor, Engineering Mr. W. Muilenburg, Supervisor, Licensing M. D. Michel, Instructor, Chemistry W o l f C reek Nu c lear O p e r atin g C o rp o r a ti on
R egu l a t o r y C on f e rence Inspec t i on R epo r t 05000482/201 3-5 0 2 P reli mina r y W h i t e F i nd i ng Enclosure 2 W ol f C r ee k Rep r e s en t a t i v es
- R usse l l Sm it h - S it e V i c e P r es i dent
- M i k e W es t ma n - Manage r R egu l a t o r y A f f a ir s
- T i mo t h y East - Supe ri n tenden t E P
- B il l Mu ilenbu r g - Supe r v i so r L i cens i ng
- B il l Ke tchu m - Supe r v i so r Eng i neer
- D a n M iche l - I nstr uc t o r I I Enclosure 2
NRC's Preli m i nary f i nding
- An appa r ent viola tion of 10 CFR 50.54 (q)(2) w as iden t i fied in v ol ving t he f a i lu r e t o ma i n t a in adequa t e me thods f or a ss e ssing t he a c t ual or po t en tial c on sequen c es of a r ad i o l ogi c al eme r gen c y be t ween S ep tember 2012 and N o vember 2013, in a cc o rdan c e w i t h t he r equi remen t s of 10 CFR 50.47 (b)(9).
- The ina cc u r a t e c al cula tion w as c o rr e c t ed on Feb r ua r y 25, 2014.
- The in s pe c t o r s de t e rmined t he failu r e t o ma i n tain a D o s e A ss e ss me nt P r o c e s s capab l e of p r o vid i ng a t e c hn i cally adequa t e e s tima t e of o f f s i t e do s e. This i ss ue has been en t e r ed in t o t he li c en s ee's c o rr e ct i v e a c tion s y s t em as Condition Repo r t 2013-0076 2 47. Enclosure 2 Roo t Cau se Ev alua t io n Findings
- R OO T CAUS E - I n f o rm a t i on S ys t e m s (I S) p rocedu res and gu idance d i d not r equ i r e co m p r ehens i ve ve r i f i ca t i on and va li da t i on f or r i sk s i gn i f icant so ft w a r e.
- C O N T R I BU T I N G CAUS E 1 - Less t han adequa t e E P ove r s i ght of r i sk s i gn i f icant d r ill-i den t i f i ed issues.
- Also de t e rm i ned t he EDC P C on t a i n ment S p r ay F il tr a t i on T ogg l e was not f unc t i ona l.
- D e t e rm ined t he EDC P de f i c i enc i es w e r e i n troduced wi t h V e r s i on 3.6 issued i n Feb r ua ry 2003. Enclosure 2 K e y Co rrect i v e Act io ns
- I m prov e E mergenc y P l ann i n g o wnersh ip o f r isk s i gn i f i can t i ssues.
- I m prov e C o m pu t e r Soft w ar e ver i f i cat i o n and va li da ti o n (V&V).
- EDC P w a s correc t e d an d i ssue d Februar y 25, 201 4 i nc l ud i n g bo th f il te r facto r an d con t a i n ment spra y togg l es. Enclosure 2 EDCP Field Team Data 1 1Other Event Trees Calculated Value SGTR Rad Mon Unit Vent & RWVent Rad Mon DBA Meteorology EAL
Enclosure 2 V en t R a d Monito r Detai l (no r ma l mode) Enclosure 2
V en t R a d Monito r Detai l (a cciden t mode)
Enclosure 2 A f f e ct o f t h e De f i cien c ies
- Iodine c on c en t r a tion c an be o v e r e s tima t ed by a f a c t or of t en
- H o w e v e r , c on c en t r a tion is not t he only input t o c al cula ting do s e
- The EDC P de f i cien cies a f f e c t t he do s e
- C on tainment S p r ay ope r a tion > 30 minu t es
- Unit V ent is in a ccident mode w i th ope rable H E P A
- I n t he s e c a s e s , t he I od i ne c on c en t r a tion is de t e rmined u sing an Iodine t o Noble Gas r a tio
- S o, t he r e s u l t is dependent upon t he N ob l e Gas c on c en t r a tio n r a ther than t he iodine c on c en t r a tion Enclosure 2 A f f e ct o f t h e De f i cien c ie s (c on t.)
- T h e ten D e si gn Ba si s Acc i d e nts i n ED CP w e r e r e viewed t o d e t ermi n e the si gn i f i c a nce of t h e d e f i c i e nc i e s. o L O CA a n d Fu el Ha nd li n g Acc i d e n t o N o c r e d i b le s c e n ari os f or c o m b i n i n g d e f i c i e nc i es C o n t a i n m e n t S p ra y T E D E F a c t o r C D E F a c t or L O CA 1.5 1.5 U n it V e n t Filt r a ti o n T E D E F a c t o r C D E F a c t or Fu e l H andli n g Acc. 1.0 1.1 L O CA 3.0 3.8 Enclosure 2 S ummary
- EA L de c i sion ma king w as una f f e c t ed by t he s e de f i cien cies o I n o r de r t o ha ve a dose a ss e ssm en t la r g e enoug h t o c au se an EAL de c la r a tion , plan t c ondi tion s w il l d r i ve de c la r a tions o E DC P c al cula tion s la g plan t c ondi tions
- P AR de c i sion ma king w as una f f e c t ed by t he s e de f i cien cies o I ni t ia l P A R s are plan t c ondi t io n ba s ed o Do se a ss e ssm en t i s u s e d f o r follo w-u p P A R s o r t o p r o ve ini tial P A R s
- One of f i v e EDC P c al cula tion me thods w as a f f e c t ed w i t h t he la r ge s t impa c t in v ol ving a LO C A o Ha d t hi s e v en t a c tuall y o cc u rr ed , a G E woul d ha ve bee n de c la r ed ba s e d o n plan t c ondi tion s and a c o rr e spondin g plan t c ondi tion P AR e v a c ua t in g 0-2 m ile s a r oun d an d 1 0 m ile s do w n w in d w oul d b e m ade o T h e E DC P de f i cien c ie s woul d no t ha ve an y i m pa ct be c au se they woul d no t ha ve bee n u s e d t o de velo p t he se P A R s Enclosure 2 Wolf C r eek Cl os i ng R e m a r ks Ru ss el l S m i t h - Si t e V ice P r e siden t & CN O O
Enclosure 2
A c ro n y m li s t
- EP - E mergen c y P l ann i ng
- EDCP - E mergen c y D o s e C a lc u l at i on Program
- H E P A - H i gh E f fici en c y Part ic u l ate A i r
- L OC A - Lo s s of C oo l ant A cci dent
- T E D E - Total E f fe c t i v e D o s e Equ i v a l ent
- CDE - C o mm i tted D o s e Equ i v a l ent
- EAL - E mergen c y A c t i on Le v el
- P AR - Prote c t i v e A c t i on R e c o mmendat i on
- G E - General E mergen c y
- CNO O - C h i ef N u cl ear Operat i ng O f f ic er Enclosure 2
