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| {{#Wiki_filter:April 20, 2006MEMORANDUM TO:Docket FileFROM:Brian Benney, Project Manager/RA/Plant Licensing Branch IVDivision of Operating Reactor Licensing Office of Nuclear Reactor Regulation | | {{#Wiki_filter:April 20, 2006 MEMORANDUM TO: Docket File FROM: Brian Benney, Project Manager /RA/ |
| | Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation |
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| ==SUBJECT:== | | ==SUBJECT:== |
| COOPER NUCLEAR STATION RE: REASON FOR POSTPONINGPUBLIC MEETING DISCUSSING TORNADO DESIGN CONCERNS (TAC NO. MC8236)The NRC planned a public meeting for April 21, 2006, at the Nuclear Regulatory Commission's(NRC's) offices in Rockville, Maryland between the Nebraska Public Power District (the licenseefor the Cooper Nuclear Station (CNS)) and the NRC staff from Region IV and the Office ofNuclear Reactor Regulation. The purpose of the meeting was, in part, to discuss the NRC staff's concerns with the adequacy of an informal calculation performed by the licensee that was intended to demonstrate the structural integrity of the safety-related heating, ventilation,and air conditioning (HVAC) ductwork in the diesel generator building at CNS under certain tornado loadings. The NRC staff's review of the calculation found that the high stressescalculated for the ductwork did not demonstrate that the structural integrity of the HVACductwork would be maintained. The NRC also believes that the stresses would likely causefailure of the ductwork, and could lead to a condition where the diesel generators may become inoperable. The NRC staff proposed to hold the meeting as soon as possible to establish if thehigh stresses in the HVAC ductwork represented an immediate safety concern to the CNS facility.The licensee was aware of the NRC staff's concerns prior to the April 21, 2006, meeting, and,subsequently, performed a new calculation using a different methodology than previously used. The new calculation is based on an American Society of Civil Engineers (ASCE) paper entitled, "Evaluation of the Ultimate Pressure Capacity of Rectangular HVAC Ducts for Nuclear Power Plants," by Bendt W. Wedellsborg, published in the conference proceedings, "Structural Engineering in Nuclear Facilities," Volume 2, September 10-12, 1984. The licensee's newcalculation is intended to demonstrate that the HVAC ductwork will not fail when subjected tothe tornado depressurization and repressurization loadings using the design method described in the ASCE paper. The analytical design method in the ASCE paper is correlated with data obtained from testing of HVAC ductwork for another nuclear power plant. Consequently, the NRC staff decided to postpone the meeting until the first week in May 2006,which would allow the staff sufficient time to review the ASCE paper and the new calculation performed by the licensee. Because the licensee is no longer relying on its initial calculation to ensure the structural integrity of the HVAC ductwork, and instead, is relying on the newly found methodology based on the ASCE paper, the previous calculation is no longer valid and could not justify that there is an immediate safety concern with the CNS HVAC ductwork. Therefore, postponing the meeting for approximately two weeks was deemed appropriate.Docket No. 50-298 | | COOPER NUCLEAR STATION RE: REASON FOR POSTPONING PUBLIC MEETING DISCUSSING TORNADO DESIGN CONCERNS (TAC NO. MC8236) |
| | The NRC planned a public meeting for April 21, 2006, at the Nuclear Regulatory Commission's (NRCs) offices in Rockville, Maryland between the Nebraska Public Power District (the licensee for the Cooper Nuclear Station (CNS)) and the NRC staff from Region IV and the Office of Nuclear Reactor Regulation. The purpose of the meeting was, in part, to discuss the NRC staffs concerns with the adequacy of an informal calculation performed by the licensee that was intended to demonstrate the structural integrity of the safety-related heating, ventilation, and air conditioning (HVAC) ductwork in the diesel generator building at CNS under certain tornado loadings. The NRC staffs review of the calculation found that the high stresses calculated for the ductwork did not demonstrate that the structural integrity of the HVAC ductwork would be maintained. The NRC also believes that the stresses would likely cause failure of the ductwork, and could lead to a condition where the diesel generators may become inoperable. The NRC staff proposed to hold the meeting as soon as possible to establish if the high stresses in the HVAC ductwork represented an immediate safety concern to the CNS facility. |
| | The licensee was aware of the NRC staffs concerns prior to the April 21, 2006, meeting, and, subsequently, performed a new calculation using a different methodology than previously used. |
| | The new calculation is based on an American Society of Civil Engineers (ASCE) paper entitled, Evaluation of the Ultimate Pressure Capacity of Rectangular HVAC Ducts for Nuclear Power Plants, by Bendt W. Wedellsborg, published in the conference proceedings, Structural Engineering in Nuclear Facilities, Volume 2, September 10-12, 1984. The licensees new calculation is intended to demonstrate that the HVAC ductwork will not fail when subjected to the tornado depressurization and repressurization loadings using the design method described in the ASCE paper. The analytical design method in the ASCE paper is correlated with data obtained from testing of HVAC ductwork for another nuclear power plant. |
| | Consequently, the NRC staff decided to postpone the meeting until the first week in May 2006, which would allow the staff sufficient time to review the ASCE paper and the new calculation performed by the licensee. Because the licensee is no longer relying on its initial calculation to ensure the structural integrity of the HVAC ductwork, and instead, is relying on the newly found methodology based on the ASCE paper, the previous calculation is no longer valid and could not justify that there is an immediate safety concern with the CNS HVAC ductwork. Therefore, postponing the meeting for approximately two weeks was deemed appropriate. |
| | Docket No. 50-298 |
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| OFFICELPL4/PMLPL4/LALPL4/BCNAMEBBenney;mxr4LFeizollahiDTerao DATE4/19/064/16/064/20/06}}
| | OFFICE LPL4/PM LPL4/LA LPL4/BC NAME BBenney;mxr4 LFeizollahi DTerao DATE 4/19/06 4/16/06 4/20/06}} |
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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:Memoranda
MONTHYEARML22147A0932022-06-0606 June 2022 2021 Annual Assessment Public Meeting Summary ML21202A3632021-07-20020 July 2021 Memorandum Disposition of Documents Discovered at Jensen Hughes ML21140A3892021-05-24024 May 2021 Riv Column 1 EOC 2020 Public Meeting Summary ML21055A4022021-05-14014 May 2021 Memorandum: Final Environmental Assessment and Finding of No Significant Impact of Initial and Updated Decommissioning Funding Plans for the Cooper, Fort Calhoun and Virgil C. Summer Independent Spent Fuel Storage Installations ML18173A0082018-06-20020 June 2018 Cancelling Numerous Inspection Report Numbers ML16253A3212016-09-13013 September 2016 Notice of Webinar Meeting with Nebraska Public Power District to Discuss Dam Failure Analysis Developed for the Integrated Assessment for Cooper Nuclear Station ML16088A2042016-03-28028 March 2016 Memo T Bowers from s Ruffin, Technical Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations W/ Encl 2 (Template) ML16088A2052016-03-28028 March 2016 Enclosure 1 - (72.30 DFP Reviews to Be Completed 2015) - Memo T Bowers from s Ruffin, Technial Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations ML14129A4452014-05-12012 May 2014 5/13/2014 Notice of Forthcoming Closed Meeting to Discuss Dam Failure Analysis for Cooper Nuclear Station and Fort Calhoun Station, Unit 1 ML13346A0822013-12-12012 December 2013 Notice of Forthcoming Closed Meeting to Discuss Dam Failure Analysis for Cooper Nuclear Station and Fort Calhoun Station, Unit 1 ML13309A0802013-12-11011 December 2013 Memorandum to File: Transcript for 10 CFR 2.206 Petition from Beyond Nuclear (Et Al) Regarding General Electric Mark I and Mark II Boiling-Water Reactors ML13165A1972013-06-13013 June 2013 06/26//2013 Notice of Public Meeting with Nebraska Public Power District to Discuss Progress and Status Plans for Addressing Substantive Cross-Culting Issues in the Areas of Human Performance and Problem Identification and Resolution ML12340A2682012-11-27027 November 2012 CNS Memo DED12-0003 Response to 10 CFR 50.54(f) Section 2.3 Seismic, Enclosing Engineering Evaluation 12-E18, Revision 0 ML11250A1712011-09-14014 September 2011 Notice of Forthcoming Meeting with Petitioner Requesting Action Under 10 CFR 2.206 Regarding Immediate Suspension of the Operating Licenses of General Electric (GE) Mark 1 Boiling Water Reactors (Bwrs) ML1118100852011-06-30030 June 2011 Notice of Meeting with Nebraska Public Power District to Discuss Cooper'S Request to Revise TS 3.4.3, Safety/Relief Valves (Srvs) and Safety Valves (Svs), to Reduce Number of Required SRVs for Overpressure Protection ML11126A0962011-05-12012 May 2011 Notice of Meeting with Petitioner Requesting Action Under 10CFR2.206 Regarding Immediate Suspension of Operating Licenses of General Electric Mark 1 Boiling Water Reactors ML1028000022010-10-0707 October 2010 Notice of Forthcoming Meeting with Nebraska Public Power District to Discuss Future License Amendment Request for Cooper Nuclear Station Related to TSTF-493, Revision 4, Clarify Application of Setpoint Methodology for LSSS Functions ML1028505172010-10-0707 October 2010 S. Wastler Memo Technical Assistance Request - Review of Proposed Amendment to the Cooper Power Station Physical Security Plan (TAC L24478) ML1014801032010-09-0707 September 2010 ACRS Review of the Cooper Nuclear Station, License Renewal Application Safety Evaluation Report ML1020702582010-08-30030 August 2010 the Nuclear Regulatory Commission Staff Spot-Checks Review of Cooper Nuclear Station June 30, 2010 - Finding of No Potential Issues in Bank Statements ML1020305332010-07-22022 July 2010 Minutes of the Plant License Renewal Subcommittee Regarding Cooper Nuclear Station on May 5, 2010, in Rockville, Maryland ML1015303172010-07-13013 July 2010 Summary of Telephone Conference Call Held on May 26, 2010 Between the U.S. NRC Staff and Nebraska Public Power District, Related to a Clarification for Certain Responses to Requests for Additional Information, for Cooper Nuclear Station Lic ML1015204892010-06-16016 June 2010 Summary of Telephone Conference Call Held on May 18, 2010, Between the U.S. NRC Staff and Nebraska Public Power District, Related to a Clarification for Certain Responses to Requests for Additional Information for Cooper Nuclear Station Lic ML1010408722010-04-26026 April 2010 Summary of Teleconf Call Held on 4/7/10, Btw the USNRC and Nebraska Public Power District, Related to a Clarification for Certain Responses to Request for Additional Information for Cooper Nuclear Station License Renewal ML1007106452010-04-20020 April 2010 Summary of Telephone Conference Call Held Between NRC & NPPD, Related to a Clarification for Certain Responses to RAI for Cooper Nuclear Station Lr ML1009700562010-04-0707 April 2010 Federal Register Notice Regarding the ACRS Subcommittee Meeting on Plant License Renewal, May 5, 2010 ML1006903852010-04-0606 April 2010 Advisory Committee on Reactor Safeguards Review of the Cooper Nuclear Station License Renewal Application - Safety Evaluation Report with Open Items ML1007700292010-03-24024 March 2010 04/07/2010 Notice of Forthcoming Meeting to Discuss the Draft Supplemental Environmental Impact Statement for the License Renewal of Cooper Nuclear Station ML1007603032010-03-17017 March 2010 Ltr to William Maier, State Liaison Officer from State of Missouri, Department of Natural Resources, Dated 12/23/2009 ML1006010322010-03-0101 March 2010 Cy 2009 Baseline Inspection Completion ML1001900422010-02-0303 February 2010 Summary of Telephone Conference Call Held on 1/8/2010, Between the U.S. NRC and Nebraska Public Power District Related to a Clarification for Certain Responses to Requests for Additional Information for Cooper Nuclear Station ML1000900472010-01-21021 January 2010 November 9, 2009, Summary of Telephone Conference Call Held on Between NRC Staff and Nebraska Public Power District, Related to a Clarification for Certain Responses to Requests for Additional Information for Cooper License Renewal ML0930004402009-11-18018 November 2009 09/21/2009-Summary of Telephone Conference, Between USNRC Staff and Nebraska Public Power District, Related to a Clarification for Certain Responses to RAI, for Cooper Nuclear Station License Renewal ML0929904002009-11-0909 November 2009 Summary of Telephone Conference Call Held on August 6, 2009, and September 2, 2009, Between the NRC Staff and Nebraska Public Power District, Related to a Clarification for Responses to Certain Rais, for CNS License Renewal ML0928706932009-10-29029 October 2009 Summary of Telephone Conference Call Held on October 5, 2009, Between the NRC Staff and Nebraska Public Power District, Related to a Clarification for Certain Responses to Requests for Additional Information, for CNS LRA ML0929200262009-10-28028 October 2009 Summary of Telephone Conference Call Held on 09/14/09, Between the U.S. NRC Staff and NPPD, Related to a Request for Additional Information (RAI) and Clarification for Certain Responses to Rais, for Cooper Nuclear Station License Renewal ML0929405242009-10-28028 October 2009 Summary of Telephone Conference Call Held on 9/17/09, Between the NRC and Nebraska Public Power District, Related to a Clarification for Certain Responses to Requests for Additional Information, for Cooper Nuclear Station License Renewal ML0926805692009-10-0808 October 2009 09/02/09 Summary of Telephone Conference Call Between NRC Staff and NPPD, Related to a Clarification for Certain Responses to Requests for Additional Information, for Cooper Nuclear Station License Renewal ML0923804342009-09-17017 September 2009 07/07/2009 Meeting Summary, Telephone Conference Call Between the U.S. NRC Staff and Nebraska Public Power District, Related to a Clarification for Certain Requests for Additional Information, for Cooper Nuclear Station License Renewal ML0923101202009-09-17017 September 2009 Summary of Tele Conf Call with Nebraska Public Power Districts to Discuss Clarifications for the Severe Accident Mitigation Alternative Documented in the NRC Request for Additional Information Letter Dated May 1, 2009 ML0920103992009-08-25025 August 2009 Summary of Telephone Conference Call Held on June 16, 2009, Between the NRC Staff and Nebraska Public Power District, Related to a Clarification for Certain Requests for Additional Information, for Cooper Nuclear Station License Renewal ML0920303052009-07-29029 July 2009 Summary of Telephone Conference Call Held on 7/9/2009, Between the U.S. NRC Staff and Nebraska Public Power District, Related to a Clarification for Certain Requests for Additional Information, for Cooper Nuclear Station License Renewal ML0915900222009-06-11011 June 2009 Summary of Teleconference Held on 5/27/09, Between the U.S. NRC Staff and Nebraska Public Power District, Related to a Clarification on Certain RAIs (RAI 3.3.2.2.3.3-1, RAI 3.3.2.2.7.3-1, and RAI 3.3.2.2.7.3-2), for Cooper License Renewal ML0915604962009-06-10010 June 2009 Summary of Telephone Conference Call Held on May 20, 2009, Between the USNRC Staff and NPPD, Related to a Clarification on Certain RAI (RAI B.1.15-3 and RAI B.1.15-4), for CNS Renewal ML0909704142009-04-30030 April 2009 Summary of Site Audit Related to the Review of the License Review Application for Cooper Nuclear Station, Unit 1 ML0909103082009-04-14014 April 2009 Summary of Public Environmental Scoping Meeting Related to the Review of the Cooper Nuclear Station, Licensed Renewal Application ML1008803542009-03-0909 March 2009 CN -2009-09- Public Forms ML0810900022008-04-22022 April 2008 Summary of Telephone Conference Verbal Authorization for Cooper Relief Request RI-35 ML0807400842008-03-14014 March 2008 Draft Regulatory Guide for Comment ML0707302142007-03-13013 March 2007 Inaccuracy in Response to the Request for Additional Regarding Crediting Service Water for Reactor Equipment Cooling Post Loss-of-Coolant Accident - Cooper 2022-06-06
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Text
April 20, 2006 MEMORANDUM TO: Docket File FROM: Brian Benney, Project Manager /RA/
Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
COOPER NUCLEAR STATION RE: REASON FOR POSTPONING PUBLIC MEETING DISCUSSING TORNADO DESIGN CONCERNS (TAC NO. MC8236)
The NRC planned a public meeting for April 21, 2006, at the Nuclear Regulatory Commission's (NRCs) offices in Rockville, Maryland between the Nebraska Public Power District (the licensee for the Cooper Nuclear Station (CNS)) and the NRC staff from Region IV and the Office of Nuclear Reactor Regulation. The purpose of the meeting was, in part, to discuss the NRC staffs concerns with the adequacy of an informal calculation performed by the licensee that was intended to demonstrate the structural integrity of the safety-related heating, ventilation, and air conditioning (HVAC) ductwork in the diesel generator building at CNS under certain tornado loadings. The NRC staffs review of the calculation found that the high stresses calculated for the ductwork did not demonstrate that the structural integrity of the HVAC ductwork would be maintained. The NRC also believes that the stresses would likely cause failure of the ductwork, and could lead to a condition where the diesel generators may become inoperable. The NRC staff proposed to hold the meeting as soon as possible to establish if the high stresses in the HVAC ductwork represented an immediate safety concern to the CNS facility.
The licensee was aware of the NRC staffs concerns prior to the April 21, 2006, meeting, and, subsequently, performed a new calculation using a different methodology than previously used.
The new calculation is based on an American Society of Civil Engineers (ASCE) paper entitled, Evaluation of the Ultimate Pressure Capacity of Rectangular HVAC Ducts for Nuclear Power Plants, by Bendt W. Wedellsborg, published in the conference proceedings, Structural Engineering in Nuclear Facilities, Volume 2, September 10-12, 1984. The licensees new calculation is intended to demonstrate that the HVAC ductwork will not fail when subjected to the tornado depressurization and repressurization loadings using the design method described in the ASCE paper. The analytical design method in the ASCE paper is correlated with data obtained from testing of HVAC ductwork for another nuclear power plant.
Consequently, the NRC staff decided to postpone the meeting until the first week in May 2006, which would allow the staff sufficient time to review the ASCE paper and the new calculation performed by the licensee. Because the licensee is no longer relying on its initial calculation to ensure the structural integrity of the HVAC ductwork, and instead, is relying on the newly found methodology based on the ASCE paper, the previous calculation is no longer valid and could not justify that there is an immediate safety concern with the CNS HVAC ductwork. Therefore, postponing the meeting for approximately two weeks was deemed appropriate.
Docket No. 50-298
OFFICE LPL4/PM LPL4/LA LPL4/BC NAME BBenney;mxr4 LFeizollahi DTerao DATE 4/19/06 4/16/06 4/20/06