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| | number = ML061080105 | | | number = ML061080105 |
| | issue date = 04/20/2006 | | | issue date = 04/20/2006 |
| | title = Cooper, Memorandum to Docket File, Reason for Postponing Public Meeting Discussing Tornado Design Concerns | | | title = Memorandum to Docket File, Reason for Postponing Public Meeting Discussing Tornado Design Concerns |
| | author name = Benney B J | | | author name = Benney B |
| | author affiliation = NRC/NRR/ADRO/DORL | | | author affiliation = NRC/NRR/ADRO/DORL |
| | addressee name = | | | addressee name = |
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| | docket = 05000298 | | | docket = 05000298 |
| | license number = DPR-046 | | | license number = DPR-046 |
| | contact person = Benney B J, NRR/DLPM, 415-3764 | | | contact person = Benney B, NRR/DLPM, 415-3764 |
| | case reference number = TAC MC8236 | | | case reference number = TAC MC8236 |
| | document type = Memoranda | | | document type = Memoranda |
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| =Text= | | =Text= |
| {{#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}} |
Letter Sequence Meeting |
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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
[Table View] |
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|---|
Category:Memoranda
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Cancelling Numerous Inspection Report Numbers
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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
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Notice of Forthcoming Closed Meeting to Discuss Dam Failure Analysis for Cooper Nuclear Station and Fort Calhoun Station, Unit 1
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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
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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
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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)
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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
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Notice of Meeting with Petitioner Requesting Action Under 10CFR2.206 Regarding Immediate Suspension of Operating Licenses of General Electric Mark 1 Boiling Water Reactors
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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
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S. Wastler Memo Technical Assistance Request - Review of Proposed Amendment to the Cooper Power Station Physical Security Plan (TAC L24478)
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ACRS Review of the Cooper Nuclear Station, License Renewal Application Safety Evaluation Report
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the Nuclear Regulatory Commission Staff Spot-Checks Review of Cooper Nuclear Station June 30, 2010 - Finding of No Potential Issues in Bank Statements
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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
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2024-05-02
[Table view] |
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
