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Category:Graphics incl Charts and Tables
MONTHYEARML20142A3972020-05-0505 May 2020 Annual Radiological Environmental Operating Report, Figure 32, Wind Rose Annual Average 10M ML20142A3982020-05-0505 May 2020 Annual Radiological Environmental Operating Report, Figure 31, Wind Riose Annual Average 75M ML20142A3992020-05-0505 May 2020 Annual Radiological Environmental Operating Report, Figure 30, Wind Rose Annual Average 100M ML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports ML15239B2122015-09-0303 September 2015 Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation ML15238B8652015-09-0303 September 2015 FHRR MSFHI Tables 1 and 2 ML14307B7072014-12-10010 December 2014 Supplemental Information Related to Development of Seismic Risk Evaluations for Information Request Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-T L-13-257, Notification of Completion of a License Renewal Commitment Related to the Review of License Renewal Application TAC No. ME4640) and License Renewal Application Amendment No. 45)2013-07-23023 July 2013 Notification of Completion of a License Renewal Commitment Related to the Review of License Renewal Application TAC No. ME4640) and License Renewal Application Amendment No. 45) ML12167A2622012-05-29029 May 2012 Enclosure - Davis-Besse 17RFO License Condition 2.C(7) SG Circumferential Crack Report ML1214500142012-05-23023 May 2012 NFPA 805 LAR Status Matrix - May 2012 ML1015201172010-05-28028 May 2010 Nozzle 4 - 52M Deposit Depth ML1005396232010-02-22022 February 2010 Lessons Learned Task Force Action Plan Regarding Stress Corrosion Cracking Dec 2009 (Final Update) ML0824903002008-10-0202 October 2008 ITSB Draft R, to Davis-Besse Amendment Conversion Improved Technical Specifications with Beyond Scope Issues ML0824902752008-10-0202 October 2008 Draft a, Attachment to Davis Besse Amendment Conversion Improved Technical Specifications with Beyond Scope Issues ML0824902802008-10-0202 October 2008 ITSB Draft La, to Davis Besse Amendment Conversion Improved Technical Specifications with Beyond Scope Issues ML0824902952008-10-0202 October 2008 ITSB Draft M, to Davis-Besse Amendment Conversion Improved Technical Specifications with Beyond Scope Issues ML0824902892008-10-0202 October 2008 ITSB Draft L, to Davis-Besse Amendment Conversion Improved Technical Specifications with Beyond Scope Issues L-08-094, Response to Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate Amendment Application2008-03-12012 March 2008 Response to Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate Amendment Application ML0727405102008-02-11011 February 2008 Lltf Action Plan Feb 2008 Update - Public ML0803700812008-02-0101 February 2008 Lltf Status of Recommendations February 2008 ML0728203072007-10-11011 October 2007 Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists ML0708602822007-03-15015 March 2007 Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Appendix B, Crack Driving Force and Growth Rate Estimates ML0708602532007-03-15015 March 2007 Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 3. Background ML0708602612007-03-15015 March 2007 Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 5. Worldwide Industry Response to CRDM and Other Alloy 600 Nozzle Cracking ML0708602682007-03-15015 March 2007 Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 7. FENOC/Davis-Besse Response to CRDM Cracking and Boric Acid Corrosion Issues ML0708602812007-03-15015 March 2007 Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Appendix a, Finite Element Stress Analysis of Davis-Besse CRDM Nozzle 3 Penetration ML0708602712007-03-15015 March 2007 Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 8. Stress Analysis and Crack Growth Rates for Davis-Besse CRDM Nozzles 2 and 3 ML0708602642007-03-15015 March 2007 Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 6. Boric Acid Wastage of Carbon Steel Components in Us PWR Plants ML0702603952007-01-31031 January 2007 Summary of Conference Telephone Call Regarding the Spring 2006 Steam Generator Inspections - Handouts ML0618002582006-06-27027 June 2006 Closure of Davis-Besse Operational Improvement Plan ML0611401302006-03-16016 March 2006 Ltr Fm J. Gutierrez, Morgan Lewis to S. Brock Requesting to Withhold Materials from Public Disclosure Which Was Submitted by FENOC - Affidavits of Terry Young and Warren Bilanin ML0525707982005-09-12012 September 2005 Documentation of Completed Post-Restart Process Plan for Transition of Davis-Besse from the IMC 0350 Oversight Process to the Reactor Oversight Program (ROP) ML0523801412005-08-31031 August 2005 Status of Davis-Besse Lessons Learned Task Force Recommendations - Last Update: August 31, 2005 ML0411301992004-04-21021 April 2004 Oversight Panel Final Restart Checklist Public Release Memo ML0414503382004-02-13013 February 2004 Oversight Panel Open Action Item List ML0414503372004-02-13013 February 2004 IMC 0350 Panel Process Plan ML0414503262004-02-13013 February 2004 Restart Action Matrix - Open Items Only ML0308000432003-01-0101 January 2003 Firstenergy Nuclear Operating Company, NRC Allegations and Employee Concerns Program Contact Trends, January 2002 - January 2003 ML0224601492002-08-29029 August 2002 Undated Data Chart, CDF, LERF, Rem ML0224601482002-08-29029 August 2002 Heat 69 Crack Growth - Bounding Weibull with 1.5 Shape Facto with Handwritten Notes ML0224601422002-08-29029 August 2002 Chart, Long-Term Results for Integrated Model with Handwritten Notes ML0224003452002-08-27027 August 2002 Failure Frequency Curve for Davis-Besse Conditions ML0224003402002-08-27027 August 2002 Draft Graphs for Flaw Curves and Stress Intensity Factors ML0530703682002-03-13013 March 2002 Timeline of Key Events Related to Reactor Vessel Head Boric Acid Wastage Rev.3, 3-13-02 ML0530704022001-04-20020 April 2001 Normal Sump Pump Samples 2020-05-05
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RESTART ACTION MATRIX - OPEN ITEMS ONLY Page 1 of 5 02/13/04
- "1 RESTART ACTION MATRIX - OPEN ITEMS ONLY RAM# Source Date Issue No. Restart Issue Contact Plan CoReferenc C re
- - RfereneIDat btain NRC review and approval of the repair or modification and testing plans for emains open he existing RPV head, prior to pending successful mplementation of those activities. Prior to petin of restart of the reactor, obtain NRC review and completion of CAL-04 CAL 05/15/02 CAL.4 7.a pproval of any modification and testing Thomas/ control rod drive activity related to the reactor core or Jacobson Pedormance test reactivity control systems. If the reactor per CAL update of vessel head is replaced in lieu of repair or 12/24/02. (Irs 02-07 modification, the replacement must comply 1 (0 with appropriate Commission rules and _)
industry requirements.
Prior to the restart of the unit, meet with the NRC to obtain restart approval. During that eeting, we expect you will discuss your Pending Restart CAL-05 CAL 05/15/02 CAL.5 7.a root cause determination, extent of condition Passehl approval meeting valuations, and corrective actions with RA.
completed and planned to repair the damage and prevent recurrence.
Respond to Riccio's two questions 7/31/03 e-mail to concerning adequacy of design basis and E-37 Ricco 10:28 am Grobe N/A ack of adequate safety evaluations Lipa associated with modifications already installed.
X lER2002 X min-'?
.12/15 T.-~>alevitse--
' CorrectivhAction t, et "-'
- z. ma_, -
F-f iY008' . . emo .
?/~.iO S31/03N 6bi6sjiia 1L a.
LER:2003' -2' - Insufficient:Deslign1MarginilforAir:LOperatedl I-H6lMberg . Z 7 ER 2003- Potential Degradation of High Pressure Jacobson LER-1 1 00 05/05/03 5.b Injection Pumps Due to Debris in 002 Emergency Sump Fluid Post Accident Page 2 of 5 02/13/04
I..
RESTART ACTION MATRIX - OPEN ITEMS ONLY start closure Closure
!cklist Issue Contact Plan Refere Reernce Date
, rtATI? ; VuFalevitsd close toAURI ;-
PotehtiaUErrorstirPfAnalysiof:Block Pr*th Walls -Rutkowski -i h lmeg ting HE~iifrnir Pl'e .;s-l^-'4 A
.~~'a S~es ~.'.m,s,.I..,
li.vi o adeqatytiv U~astis~onr.hseltend t to SW-.
- Faleyits- s'C ATI ervice'watbrsters Gi-SA, pa)
- arAtidA pUmscsfo-ha aetptacs Gopi-,,.:- .' A 2-e3qumd 6 U
-rd.-'t-edj ,SW.-'-M. ...
Failure to Address All Significant Causal Thomas Factors Related to the Configuration Control spects Associated With the Installation of Unqualified Relays SFAS.
- .d Failure to Verify Adequacy of Short Circuit Falevits CATI Protection for Direct Current Circuits Lack of Calculations to Ensure Minimum Falevits CATI Voltage Availability at Device Terminals Corrective Actions
- Determine that uantitative or qualitative measures of IR 02-018, 03-12 &
I/A uccess have been developed for Wright IR02-015.
etermining the effectiveness of the orrective actions to prevent recurrence.
Review of Licensee Control Systems for Identifying, Assessing, and Correcting Performance Deficiencies: By reviewing IR02-11, IR02-18, elected aspects of the employee concerns Residents mention I/A rogram, ensure that employees are not Wright in a report, &
esitant to raise safety concerns and that Mngmt & Human afety significant concerns entered into the Performance 3 Insp mployee concern program receive an Appropriate level of attention.
Page 3 of 5 02/13/04
RESTART ACTION MATRIX - OPEN ITEMS ONLY ttri b"'te siArs's~ess't~heteffectiven"ess!
1vo v ngaengnies-. defi~c6n xfc-retv-atosfor ies~.:-
assessment of Performance in the Reactor
- afety Strategic Performance Area
- Key
,ttribute - Human Performance: Assess the ffectiveness of corrective actions for eficiencies involving human performance.
Page 4 of 5 02/13/04
.,r RESTART ACTION MATRIX - OPEN ITEMS ONLY RetatClosure Closure RAM# Source Date Issue No. Checklist Issue Contact Plan Reference Date Item _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
.URI-28R.02'144 02126/03' -01r.;
C , 5Qb( I a'd 'teUHS'ia~ itoy alysi@'..Z. fFaleitsC ATI V ' -
~5b No V~i'e~ie WaY~upNdticstv12Flit~A V,;7.9."
URI-29t .IR0O2 °, 02610 -sj . *,,-^We*cio*Mar n l <^- i> ~.
URI'32- .IR 02-14'-' 02/26/03 .- 02b,-* '5 5*b: Inadeq _at-SW:bst^mhflow .balancetlesting:
f.FaleditsW' f; CAT '; -.v -.. 'sp*'
,URI-34. ;IR02,14-, 02126/03 -03Wb i5 b%
- Rep etitivefailurestofSWrelief valves;' . '" Falevits CATI,7-R 0tionjregardingrthddfinitionof"a a 7 ; - ;~~ ~InaideqU~atb.1nfipl~rThetatioh.of-the:CorrectiVe rFalevits-z. C ATI ~~ --
UR-421 74ifl02-177- 1 2/09/02!,rFN-~0 3' 3 a-:&-4.b6 ~ -- ~----~ e.lsueegardinig0he
~ ~Poentialy-Reortb
. 0Potential Inability for HPI Pumps to Perform Jacobson URII44 IR03-15 07/30/03 04 Safety Related Function (see LER 03-02) .. . ,
OPEN ITEMS ASSIGNMENTS: TOTAL 38 ITEMS NOT SUBMITTED FOR PANEL AS OF 02/13/04: TOTAL 15 Falevits = 2 Jacobson = 3 Lipa = 1 NRR = 3 Passehl= 1 Thomas = 1 Wright = 4 Page 5 of 5 02/13/04