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MONTHYEARML0610800322006-04-18018 April 2006 Rescheduled, Notice of Meeting with Nebraska Public Power District to Discuss an Unresolved Item Identified During an NRC Inspection on 7/2/05 Project stage: Request ML0610801052006-04-20020 April 2006 Memorandum to Docket File, Reason for Postponing Public Meeting Discussing Tornado Design Concerns Project stage: Meeting ML0612904602006-05-0505 May 2006 May 5, 2006 Meeting Slides Project stage: Meeting ML0613001122006-05-12012 May 2006 Cooper Nuclear Station, Meeting Summary of NPPD Meeting Tornado Concerns Project stage: Meeting ML0616501662006-06-27027 June 2006 Final Response to Task Interface Agreement - TIA 2005-08, Evaluation of Protection Against Tornadoes at Cooper Nuclear Station Project stage: Other 2006-05-12
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Category:Meeting Briefing Package/Handouts
MONTHYEARML23317A2032023-12-13013 December 2023 Pre-Submittal Meeting: Tech Spec Amendment Request for HPCI Flow Switch Setpoint Change ML23150A1382023-06-0101 June 2023 Pre Submittal Meeting: Containment Inservice Inspection (Cisi) Relief Request, June 1, 2023 ML23150A1372023-06-0101 June 2023 Pre-Submittal Meeting: Diesel Generator Fuel Oil Storage Tank Cleaning/Inspection, June 1, 2023 ML21125A0372021-05-0606 May 2021 May 6, 2021 Public Meeting (Observation) Slides for RAP Back Program Presentation to Industry(003) ML20080M1582020-02-21021 February 2020 PFHA-2020-3B-3-Vossmar_Stafford-2019_CNS_FCS_Flooding ADAMS Version ML18255A0102018-09-12012 September 2018 NRC Slides for Target Rock Public Meeting ML18255A0142018-09-12012 September 2018 BWROG Presentation Slides for Public Meeting Sept 12 2018 ML14149A0742014-05-30030 May 2014 5/22/14 Meeting Handouts - Meeting with OPPD and NPPD to Discuss Flooding Hazard Reevaluation Extension Requests for Fort Calhoun Station and Cooper Nuclear Station - Response to Question 1 Part 2 ML14149A0902014-05-22022 May 2014 5/22/14 Meeting Handouts - Meeting with OPPD and NPPD to Discuss Flooding Hazard Reevaluation Extension Requests for Fort Calhoun Station and Cooper Nuclear Station - Detailed Schedule June 2012 Through February 2015 Gantt Chart ML14149A0882014-05-22022 May 2014 5/22/14 Meeting Handouts - Meeting with OPPD and NPPD to Discuss Flooding Hazard Reevaluation Extension Requests for Fort Calhoun Station and Cooper Nuclear Station - Detailed Schedule May 2014 Through February 2015 Gantt Chart ML14149A0852014-05-22022 May 2014 5/22/14 Meeting Handouts - Meeting with OPPD and NPPD to Discuss Flooding Hazard Reevaluation Extension Requests for Fort Calhoun Station and Cooper Nuclear Station - Hi-Level Overview Schedule for Flooding Hazard Reevaluation Report ML14129A1492014-05-0909 May 2014 Station/Cooper Nuclear Station - Meeting Slide for Flood Hazard Reevaluation Report Schedule Extension Review ML13178A1592013-06-26026 June 2013 Summary of Meeting for Public Meeting with Nebraska Public Power District Regarding Cooper Nuclear Station ML12311A0492012-09-18018 September 2012 Part 26 Public Meeting NEI Presentation Slides ML1129715762011-10-24024 October 2011 Licensee Slides from 10/24/11 Meeting with Nebraska Public Power District to Discuss Cooper Nuclear Station ML1121401792011-07-11011 July 2011 Licensee Slides from Conference Call with Nebraska Public Power District IR 05000298/20110092011-06-10010 June 2011 EA-11-204, Cooper Nuclear Station, Final Significance Determination of White Finding and Notice of Violation, NRC Inspection Report 05000298/2011009 ML1112606772011-05-0606 May 2011 Summary of Meeting with Nebraska Public District, Cooper Discussed the Significance, Cause and Corrective Action Associated with an Apparent Violation with Low-to-Moderate Safety Significance ML1029202962010-10-19019 October 2010 Meeting Handouts for October 19, 2010 with Nebraska Public Power District Regarding Cooper Nuclear Station ML1016001102010-06-0909 June 2010 Summary of Annual Performance Assessment Meeting for Cooper Nuclear Station ML1011904802010-04-29029 April 2010 Summary of Meeting with Nebraska Public Power District to Discuss Issues Associated with the Independent Spent Fuel Storage Installation (ISFSI) ML1011103782010-04-20020 April 2010 Public Meeting Summary from 4/7/2010 ML1010503762010-04-0707 April 2010 Preliminary Site-Specific Results of the License Renewal Environmental Review for Cooper Nuclear Station ML0909700972009-04-0707 April 2009 Summary of Annual Performance Assessment Meeting with Nebraska Public Power District to Discuss Safety Performance at Cooper Nuclear Station Between January 1 & December 31, 2008 ML0907506862009-02-25025 February 2009 Scoping and Process Public Meeting Sides of February 25, 2009 ML0816201532008-06-10010 June 2008 End-of-Cycle Meeting Summary 6/2/08 ML0815501022008-05-28028 May 2008 Meeting Summary for Regulatory Conference with Nebraska Public Power District to Discuss the Significance of an Inspection Finding Associated with Two Procedures That Were Not Adequate ML0712005272007-04-30030 April 2007 Nrc/Entergy Operations, Inc. Management Meeting to Discuss the Performance of Arkansas Nuclear One, Cooper, Grand Gulf, River Bend and Waterford, Unit 3 ML0721104822006-10-31031 October 2006 Significance Determination Process Refresher Training ML0612904602006-05-0505 May 2006 May 5, 2006 Meeting Slides ML0524300942005-10-0303 October 2005 Slides from August 29, 2005 Meeting with NPPD ML0503405322005-02-0303 February 2005 Summary of Meeting with Nebraska Public Power District Regarding Cooper Nuclear Station ML0413802292004-05-17017 May 2004 Summary of Confirmatory Action Letter 5th Quarterly Inspection Exit Meeting with Nebraska Public Power District Regarding Cooper Nuclear Station ML0410503302004-04-14014 April 2004 Meeting Summary for End-of-Cycle Performance Assessment for Cooper Nuclear Station ML0402800142004-01-27027 January 2004 Summary of CAL 4th Quarterly Inspection Exit Meeting with Nebraska Public Power District Cooper Nuclear Station ML0331402912003-11-0707 November 2003 Summary of Meeting with Nebraska Public Power District Regarding Cooper Nuclear Station ML0302905232002-12-13013 December 2002 Briefing Slides for Presentation Status of the CNS BWRVIP Program from 12/13/2002 Meeting with Nebraska Public Power District ML0208107562002-03-19019 March 2002 Operator Licensing Workshop Meeting Summary ML0205703522002-02-26026 February 2002 02-07-02 Cooper/Nebraska Public Power District Meeting Summary ML17252A1571977-09-14014 September 1977 Summary of Meeting Held with Representatives of the Mark I Owner'S Group to Discuss the Structural Acceptance Criteria for the Mark I Containment Long Term Program 2023-06-01
[Table view] Category:Slides and Viewgraphs
MONTHYEARML23150A1372023-06-0101 June 2023 Pre-Submittal Meeting: Diesel Generator Fuel Oil Storage Tank Cleaning/Inspection, June 1, 2023 ML23150A1382023-06-0101 June 2023 Pre Submittal Meeting: Containment Inservice Inspection (Cisi) Relief Request, June 1, 2023 ML21125A0372021-05-0606 May 2021 May 6, 2021 Public Meeting (Observation) Slides for RAP Back Program Presentation to Industry(003) ML20080M1582020-02-21021 February 2020 PFHA-2020-3B-3-Vossmar_Stafford-2019_CNS_FCS_Flooding ADAMS Version ML19196A3452019-07-18018 July 2019 July 18, 2019 Public Teleconference Slides Appendix J Exemption Request Presubmittal Teleconference ML18255A0142018-09-12012 September 2018 BWROG Presentation Slides for Public Meeting Sept 12 2018 ML14149A0742014-05-30030 May 2014 5/22/14 Meeting Handouts - Meeting with OPPD and NPPD to Discuss Flooding Hazard Reevaluation Extension Requests for Fort Calhoun Station and Cooper Nuclear Station - Response to Question 1 Part 2 ML14129A1492014-05-0909 May 2014 Station/Cooper Nuclear Station - Meeting Slide for Flood Hazard Reevaluation Report Schedule Extension Review ML13178A1592013-06-26026 June 2013 Summary of Meeting for Public Meeting with Nebraska Public Power District Regarding Cooper Nuclear Station ML12311A0492012-09-18018 September 2012 Part 26 Public Meeting NEI Presentation Slides ML1129715762011-10-24024 October 2011 Licensee Slides from 10/24/11 Meeting with Nebraska Public Power District to Discuss Cooper Nuclear Station ML1121401792011-07-11011 July 2011 Licensee Slides from Conference Call with Nebraska Public Power District ML1113805552011-05-16016 May 2011 Summary of Annual Performance Assessment Meeting for Cooper Nuclear Station ML1112606772011-05-0606 May 2011 Summary of Meeting with Nebraska Public District, Cooper Discussed the Significance, Cause and Corrective Action Associated with an Apparent Violation with Low-to-Moderate Safety Significance ML1029202962010-10-19019 October 2010 Meeting Handouts for October 19, 2010 with Nebraska Public Power District Regarding Cooper Nuclear Station ML1016001102010-06-0909 June 2010 Summary of Annual Performance Assessment Meeting for Cooper Nuclear Station ML1011904802010-04-29029 April 2010 Summary of Meeting with Nebraska Public Power District to Discuss Issues Associated with the Independent Spent Fuel Storage Installation (ISFSI) ML1011103782010-04-20020 April 2010 Public Meeting Summary from 4/7/2010 ML1010503762010-04-0707 April 2010 Preliminary Site-Specific Results of the License Renewal Environmental Review for Cooper Nuclear Station ML0909700972009-04-0707 April 2009 Summary of Annual Performance Assessment Meeting with Nebraska Public Power District to Discuss Safety Performance at Cooper Nuclear Station Between January 1 & December 31, 2008 ML0907506862009-02-25025 February 2009 Scoping and Process Public Meeting Sides of February 25, 2009 ML0831101972008-11-0505 November 2008 Summary of Meeting with Nebraska Public Power District to Discuss Inspection Procedure 95002 Supplemental Inspection Preparations and Diesel Generator Performance Improvement Plan ML0823503312008-08-22022 August 2008 Summary of Public Meeting with Nebraska Public Power District Presentation of Preparations for Inspection and Plans to Improve Performance of Emergency Diesel Generators at Cooper Nuclear Station ML0815501022008-05-28028 May 2008 Meeting Summary for Regulatory Conference with Nebraska Public Power District to Discuss the Significance of an Inspection Finding Associated with Two Procedures That Were Not Adequate ML0720002802007-07-18018 July 2007 Meeting Summary for Regulatory and Predecisional Enforcement Conference; Cooper Nuclear Station ML0623601232006-08-22022 August 2006 Danger Will Robinson: If You Change Cell Locations You May Break the VB Code! ML0615700432006-06-0202 June 2006 Summary of 05/30/2006 Annual Performance Assessment Meeting with Nebraska Public Power District Cooper Nuclear Station ML0612904602006-05-0505 May 2006 May 5, 2006 Meeting Slides ML0617905182006-03-0909 March 2006 RIC 2006 Presentation - Th5E - Jerry Roberts - ROP Inspection Program Update ML0617802712006-03-0707 March 2006 RIC 2006 Presentation - T2E - Vincent Coulehan - Use of Operating Experience (Regulator/Operator/Licensee) ML0532206852005-11-17017 November 2005 Nrc/Entergy Operations, Inc. Management Meeting 11/10/05 ML0531904622005-11-15015 November 2005 Summary of Meeting with Nebraska Public Power District Regarding Cooper Nuclear Station ML0524300942005-10-0303 October 2005 Slides from August 29, 2005 Meeting with NPPD ML0511000652005-04-19019 April 2005 Summary of Meeting with Nebraska Public Power District Regarding Cooper Nuclear Station end-of-cycle ML0506802362005-03-0909 March 2005 Summary of Public Meeting with Nebraska Public Power District Regarding Cooper Nuclear Station'S Simulator Fidelity Issues ML0503405322005-02-0303 February 2005 Summary of Meeting with Nebraska Public Power District Regarding Cooper Nuclear Station ML0422602762004-08-12012 August 2004 Meeting Summary of the August 8, 2004 Public Workshop - Region IV Operator Licensing Feedback ML0413802292004-05-17017 May 2004 Summary of Confirmatory Action Letter 5th Quarterly Inspection Exit Meeting with Nebraska Public Power District Regarding Cooper Nuclear Station ML0409701292004-03-12012 March 2004 Summary of Meeting with Cooper Nuclear Station to Discuss Progress in Implementing Strategic Improvement Plan ML0409804682004-03-11011 March 2004 RIC 2004 Presentation - T4 - Jerry Roberts - Operating Experience ML0402800142004-01-27027 January 2004 Summary of CAL 4th Quarterly Inspection Exit Meeting with Nebraska Public Power District Cooper Nuclear Station ML0331402912003-11-0707 November 2003 Summary of Meeting with Nebraska Public Power District Regarding Cooper Nuclear Station ML0323407332003-08-21021 August 2003 Cooper Nuclear Station, Presentation Slides Re. Main Steam Isolation Valve Leakage Pathway, License Condition 2.C.(6) ML0319101132003-07-0909 July 2003 Summary of Confirmatory Action Letter Quarterly Inspection Exit Meeting with Nebraska Public Power District Regarding Cooper Nuclear Station ML0311207402003-04-22022 April 2003 Meeting Summary for End-of-Cycle Performance Assessment for Cooper Nuclear Station ML0309201462003-04-0101 April 2003 Summary of Confirmatory Action Letter Quarterly Inspection Exit Meeting with Cooper Nuclear Station ML0302905232002-12-13013 December 2002 Briefing Slides for Presentation Status of the CNS BWRVIP Program from 12/13/2002 Meeting with Nebraska Public Power District ML0224904012002-09-0303 September 2002 Cooper Supplemental Inspections, Presentation to Nebraska Public Power District Board of Directors ML0224001612002-08-26026 August 2002 8/22/02 - Summary of Meeting with Cooper Nuclear Station 2023-06-01
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CNS DIESEL GENERATOR (DG) -ORNADO COPING ANALYSIS May 5, 2006 2-1 PRESENTATION BACKGROUND
- SSD&PC Inspection Question Regarding Tomado Design of DG
- CNS Re-verified and Validated the Tornado Design of the DG
- DG ROOM HIIAC AND VIRTUAL Rooms.
TOUR - The DG Structures per USAR are Designed for:
Class I (seismic)
- TORNADO SEQUENCE Tomado p
and Wind Generated MissileProtection 3 si Differential Pressure Load from Atmospheric Pressure Change.
- TIA ISSUES - By Design, the DG Structures are Vented
- The DG Ccmponents Located Within hose Structures are Vented
- CNS CALCULATION and per the SRP,
- "AdequatelyProtectedandMayb.ErqectedtoPedonn
- CONCLUSIO1S NecessarySafety-ReatedFunclons.1
- Tomado Event isRecove ableCondiion in that Actions Can be
- QUESTIONS/DIALOGUE Taken to Mantain or Restore DG's 4
BACKGROUND, cont. BACKGROUND, cont.
- DG Components Cutside Structure VAII Not Prevent Engine - CNS Provided Calculation NEDC 05-021, Rev. 1 to Start and Load Atetr Tomado Demonstrate DG Ventilation Ductwork Integrity Is Maintained ExtaustMufflerAistys Bypassed During Tomado Induced Atmospheric Pressure Changes in Separate Alr Intakesfor EngineandBuikding ventiltion June of 2005.
- Based on Field Ins 3ection of Venting, OE and Engineering CNS Calculatbn of 2005 Not Performed for Desin.
Analysis, Other Ro 3m Components are not Affected by
- Calculationwas Performed for Showing Reasonable Atmospheric Pressure Changes. Expectationof Duct Inegrity.
- Electrical, Mecthanimat.Instnrumentation
- Calculation Utlized Venting of Rooms for Diftirential Pressure
- Question Still Existed Regarding Failure of DG Room on Duct Comporents.
Ventilation Ductwok that Could Potentially Result In Room Sound Engineering PracticesUsed in Calculathg Duct Overheating. Component Stresses.
- CNSDGSructnure; Not HamrhEnvirtnment, EO Is NotApplicable.
- Recognized thatSome Deformation May Occur Due to Faufted ElevatedRoomTenperatures CouldAffectElectricalcomponents. Condition.
- Calculation Cmtsistent wth Industry Practice(OE) 0 1
HVAC Schematic DG in Standby BACKGROUND, cont. Normal Spring/Summer Operation
- Familiarity with CNS Specific Design is Necessary to Understand the Calculations.
- Calculation was Revised Utilizing More Recent Methodology.
- Venting of Rooms Still Utilized
- 1984 Rectangular Ductwork Analysis (ASCE Paper)
- DG Ventilation Components with Highest Vulnerability tc Tornado Damage:
- Supply Plenuri Ducts Dunng Depressurization Phase
- Exhaust Backiraft Dampers During Re-pressurization Phase
-
HVAC Schematic DG Running Spring/Summer Operation VIRTUAL TOUR
- SITE LAY OUT AND OVERVIEW
- DG PENTHOUSE 9 IC SITE LAY OUT I 4fE:0 X
...0E 0' nd X i 2
DEPRESSURIZATION SEQUENCE DEPRESSURIZATION SEQUENCE WUE DURINGTUNADO
_ MUFR RYPA5S AMWJEWF.IIMP..
ENSSR ASNA7E5 F, I~~EquASTTL 13 14 DEPRESSIJRIZATION SEQUENCE DEPRESSURIZATION
SUMMARY
- MAXIMUM PRESSURE DIFFERENTIAL IS 0.83 PSID
- MOST LIMITED PRESSURE CAPABILITY OF DUCT IS 1.25 PSID
- Duct Work Flow Path Remains Intact
- LOCATION IS IN VESTIBULE SECTION OF SUPPLY PLENUM
- Having the normal Fi/AC suppl tan in operation during the depressurization phase Is inconsequenel since I provides litle additionrl resistance to the venting airflav pat) based on the resistance contribution of the other co onents nithe path. The fan capacty isinsufficisntto overcomehe presasre d erenti otfa tornado. The compressible ngture of air predudes damage b fan itself. The fan motor could trip on overload. Theefore the Calculation modeled the fan as'OFF-I1 1s RE-PRESSIJRIZATION SEQUENCE RE-PRESSURIZATION SEQUENCE DURINGT(RNADO MWTlEBYPASS AM4EBIIPI1 7ip.
PRESSWEEA5Burro NDlTrPA*5 F 17 1e 3
RE-PRESSURIZATION
SUMMARY
. MAXIMUM PRESSURE DIFFERENTIAL IS 2.50 PSI
- DUCT WORK REMAINS INTACT with POSITIVE INTERNAL PRESSURE
- CAPABIUTY OF DAMPER IS1.60 PSID
- SELF-RELIEVING (Actual dP will be much less than 2.5 psi)
- WILL NOT CAUSE ANY SIGNIFICANT FLOW BLOCKAGE
- MAY NOT IMPACT EXHAUST FAN, HOWEVER..
- EXHAUST FAN NOT NEEDEDWITH SUPPLY FAN RUNNING TO MAINTAIN ROOM COOUNG AND REDUCED DG LOAD.
- CNS REVIEWING REMOVAL OF DAMPERS TO PROVIDE ADDITIONAL DESIGN MARGIN FOR PRESSURE VALUES AND EXHAUST FAN PROTECTION.
TIA COMMENTS PIPING CODE USE
- ASME Code Allowable Stress (3 SM) Invoked for 'Faulted' Condition Based on Similarity of
- Allowable Stress of 3 SM from ASME Not Order of Magnitude for Tomadoes and DBA Appropriate LOCA as Low Probability Events.
- PRESSURE D)IFFERENTIAL UTILIZED
- Plate Bending Formulae are 'Textbook' Tools
- Should have used 3 psi Design Pressure for Analysis of Stressed Members.
(Non-vented vs. Vented Structure)
- Industry Code Expert (Reedy Engineering)
Confirms Acceptability of Use of ASME (3 SM)
- CNS Methodology Provides Similar, but
- Source of Material Yield Strengths Not Conservative Results to ASCE Alternative Identified Methodology.
21 22 TORNADO DATA CNS Desbtn Bsis Tomato of 300 MPH Rotational Wind Speed, BCMPH Translational Wind S meed and 3.0 PSID is Low Pflbability Event ALTERNATIVE METHODOLOGY A Revised Analytical Method
-ASCE Paper 1984
.15-0. '04.06 t00tlen aeQUIoP eaO
- Methodology Based on Testing (ANO) 0045 10661605.1 Sli ~ ~ tt O.CnN 6-tlaee-4 - Specific for Nuclear Rectangular Ducts
- Yield Line Theory utilized (plastic behavior)
- Similar 'Textbook' Plate Formulae Provided
- Negative Internal Pressure of Duct is Most Limiting Scenario
- Room Vent Paths Utilized p4 612 *04E4 4.6004
-E 05Z t.1 F4 naS *41N IIII44 t s2 - Actual Material Properties Used for Duct 24 4
PRESSURE DIFFERENTIALS MATERIAL PROPERTIES
- Structure Design Conservatively Assumes
- Worst-Case Material Properties Assumed Non-vented - ASTM-A-36 36 ksi yield
- Structure is Snot intentionally sealed"
- Components ir Structure are Vented - 42.5 ksi minimum yield (by test)
+ Depressurization of Room Calculated Based
- Stiffener Angle Properties Not Clearly on USAR 3.0 psi at 1.0 psi/second rate. Identified
- Re-pressurization of Room Calculated Based
- Duct Thickness of 0.1875" Used (Error)
- Best Estimate 'K" Factors Used for Entrance
- Actual Duct Thickness is 0.0747" Losses. - Calculation Continues to Demonstrate
- DG Fans Modeled in Standbys to Maximize Acceptability.
Pressure Differantials.
25 CONCLUSIONS QUESTIONS/DIALOGUE
- ORIGINAL CALC BASED ON SOUND ENGINEERING PRINCIPLES.
- MATERIAL PROPERTIES KNOWN.
- ALTERNATIVE METHODOLOGY FOR DUCTS, NUCLEAR SPECIFIC, STRAIGHTFORWARD AND SHOWS MORE MARC IN.
- DUCT INTEGRITY MAINTAINED.
27 28 5