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MONTHYEARML21288A4302021-10-18018 October 2021
Enclosure - Crystal River Unit 3 Nuclear Generating Plant - Correction to Safety Evaluation Related to the Issuance of Amendment No. 259 Approving the Independent Spent Fuel Storage Installation Only Emergency Plan
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Enclosure 6 - List of Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status
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Enclosure 1, Attachment 2 - Duke Energy Corporation and Progress Energy, Inc. Organization Charts Post Merger
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Public Meeting - Crystal River Nuclear Plant - Attendees
3F0311-07, Attachment B, Response to Request for Additional Information Required for the Development of the Confirmatory LOCA and Non-LOCA Models2011-03-15015 March 2011
Attachment B, Response to Request for Additional Information Required for the Development of the Confirmatory LOCA and Non-LOCA Models
ML1027201382010-10-29029 October 2010
Williams Q&A - Request #3 Info-Pugh-PART 6
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Williams Q&A- Request #3 Info-Pugh-PART 5
ML1029200682010-09-20020 September 2010
Ncr Number 358724, Assignment Number 23, Crystal River, Unit 3 Containment
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Petrographic Studies of Concrete for Construction Engineering Consultants
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Adverse Condition Investigation Form, CAP-NGGC-0200-3-18
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P11 Company Background
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Nuclear Generating Plant - Preliminary Review of Progress Energy'S 10 CFR 50.59 Evaluation
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Nuclear Generating Plant - Preliminary Review of Progress Energy'S 10 CFR 50.59 Evaluation
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Pef Letter to FDEP NPDES Permit Renewal App CR 4 & 5 January 25, 2010
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Onsite Ground/Surface Water Monitoring Questionnaire for Crystal River
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Crystal River Public Meeting Attendees Sheet
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Talking Points
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6.1 Uneven Force Along Tendon
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Sgr Action Plan for Concrete Cracks
ML1028709882010-01-11011 January 2010
5.4 Concrete Form Release
ML1028710452010-01-0404 January 2010
6.2 Inadequate Tendon
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5.5 Exhibit 1 Permeability V w2c from Mehta
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5.5 Exhibit 2 Mix Design from Dome Repair
ML1029202952009-11-27027 November 2009
Item 176 1992 Bs Event RB Temperature (4 Pages)
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Calculation S07-0033, Revision 0, NRC SIT Member Questions to Licensee (Request 43 Response Information, Attachment 2, Part 2 of 3
ML1027206552009-10-30030 October 2009
Williams Q&A - Request #24 - Q18 RFO14-IWE Exam
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Williams Q&A- Request #24 - Q18 RFO15-IWE Exam Liner UT
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Williams Q&A - Request #24 - Q18RFO15-IWE Exam Liner Containment Inspection
ML1027300762009-10-30030 October 2009
WR 341602 6th-Surv.pdf
ML1027201932009-10-29029 October 2009
Williams Q&A - Request #22 - Q16 Response
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Williams Q&A - Request #3 Info-Pugh-PART 7
ML1027201702009-10-29029 October 2009
Williams Q&A - Request #3 Info-Pugh-PART 8
ML1027302522009-10-29029 October 2009
Williams Q&A - Request #3 Info-Pugh-PART 4
ML1027201982009-10-28028 October 2009
Williams Q&A - Request #30 - Question 24
ML1029107252009-10-28028 October 2009
Interview Cliff Peters Gary Goetsch
ML1029107542009-10-24024 October 2009
Interview Gary Goetsch
ML1029107562009-10-23023 October 2009
Iwl of 10-25-09
ML1027202052009-10-22022 October 2009
NRC SIT Member Questions to Licensee (Request 42 Q36 Response Information)
ML1007504152009-10-14014 October 2009
Update for 10/14/09 from Plant Issue Tracking Application
ML1007502742009-10-0707 October 2009
Plant Issue Tracking, Crystal River Information for 10/7/09
ML1007504232009-10-0505 October 2009
Action Request: CR3 Sgr Hydrodemolition Exposed Cracks
ML1013903992009-05-11011 May 2009
Attachment to E-mail from Paul Roberts, May 11, 2009, Questions on the Use of Carborundum Neutron Absorbing Material in the Spent Fuel Pool
ML0914607852009-04-16016 April 2009
Utility Element and Generalized Future Land Use Map Received for Gary W. Maidhof, Dept Director, Dept of Development Services, Citrus County, Gov'T at April 16, 2009, Scoping Meeting in Crystal River, Fl
ML1027103312009-02-0101 February 2009
Document CR-N1002-504, Revision 1, Final Report for the 30th Year Containment Iwl Inspection, Fm 6.5 Exhibit 6
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Enclosure 5: Case Study 1: Structure of TS for Ultrasonic Flow Meters - Meeting Summary of the January 27 & 28 Meeting with Nrc/Tstf
3F0608-05, Response to Request for Additional Information Regarding Relief Requests 07-001-SS, Revision 0, Alternate Criteria for the Reactor Vessel Support Skirt to Perform Limited VT-3 Visual Examination on 3 Areas 120 Degrees Apart .2008-06-0505 June 2008
Response to Request for Additional Information Regarding Relief Requests #07-001-SS, Revision 0, Alternate Criteria for the Reactor Vessel Support Skirt to Perform Limited VT-3 Visual Examination on 3 Areas 120 Degrees Apart .
ML0732400242007-10-25025 October 2007
Examples of Max Thermal Power License Conditions
ML0634705992006-12-14014 December 2006
Plant Service List
ML0527000442005-09-21021 September 2005
Attachment 10, FAQ Log 9/21/05
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Order EA-03-009 Service List
2021-10-18
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ý I I-4017-ý'SGR Action Pan for Concr ee Cracks Team-P o s i t i o n : : ...D a y s h ift ... N i g h t s h i ft .: i ; : .: ' : Issue Manager .Magdy Bishar-SGRSOM Glenn Campbell[Bradd Fasel : AT. Morrow Bechtel Task Mgr Jon Bucliett Shane Adams rlect Issue Lead ..George.Smith,,......
-Dhiren Pandya Engiineering Lead Dan Jopling S. $ot Swenson...Licensing Rep Sid Powell KaraStacy.Operations-Rep Dave Jones.! .L. Leon Gagne..Engineering Rep- Jn Holliday ...Ja..y Jackson Cracks in Reg ReactrWIBuiidinp waliactions.
Ativit Ownr.Nee.Date -e t Restraints
- 1) Mobilize Bechtel resource with post-tensindl containment experienci, 2) Mobilize MPR personnel 3) Establish pressre taining capability in mode 6 S a;.
L gg Judgm.ent b..Develop rigorous assessmentNON, d., :REW.4) Establish restrictionsr on inPstallation 0ofth6e;HTS.
- 5) C:h~aracterize.Crackinig....
a., Establish'plan of action b,. Evaluate meth6ds for crack evauatioin' Bishara Bishara Jopling S&L Jopling Powell ,Jopling Jopling Joplidng ,Hbllidafy 10/7109 10/4/09, 1015/09: 10/2/09'10/25/09: 1 0/6/09.1015109, 10/4/09 10/6/09.Open'Complete.Open Open Open Open Open Open'Complete..Open Mode 6
,6) Establish an understanding of OE 7)' Develop necessary analysis for HIS OTSG loads on cracked wall, a.PNSC: review of HIS loading evaluation
- 8) evelop alterna te:HIS Rigging Plan 9) Ve'rify analysi'sl for Core reload and LODH scenario 10) Develop analysis for contain~ment design basis I11),Root Cause investigation Powell S&L..Jopling Hienshawg 10/5/09, 10/??/09 1 0/??/09 I 0/??/09 1 0/??/09 11/26/09 11/2/09*Open Open Open Open'Open,'Open OQpen.Installing HTS Mode:'5 Mode 4 Mode 4.~t eVerified,)
