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Category:Note
MONTHYEARML12024A3472012-01-30030 January 2012 Teleconference Summary for Davis-Besse Nuclear Power Station Regarding the Environmental License Renewal Application Review ML0730201272007-03-0909 March 2007 Hand Written Telecon Notes ML0619801032006-07-0707 July 2006 OI Notes ML0412801022004-05-0606 May 2004 Note 05/06/2004 to All Region III Facility Training Managers Re Reprint of NRC Form 396 ML0404804932004-02-10010 February 2004 G20040092 - NRC Oversight of Davis-Besse Boric Acid Leakage and Corrosion During the April 2000 Refueling Outage (Case No. 03-02S) - Note to W. Travers from N. Diaz ML0411400072004-01-0303 January 2004 Partially Withheld Citizens Response Regarding the Restart of the Davis-Besse Nuclear Power Plant ML0311102552003-04-0808 April 2003 Note to Ellis from Mike Regarding Report Concerning Davis Besse ML0310401162003-03-31031 March 2003 Handwritten Notes & Computations on B&W Plant Operating Histories ML0310401112003-03-31031 March 2003 Handwritten Notes on Industry History of RCS Pressure Transients (ORNL Search Results of Scss Databases) ML0310401052003-03-31031 March 2003 Notes on Telecon with Authors of GSI-191 Study ML0324003602002-11-16016 November 2002 Exit Meeting Notes ML0224007252002-08-29029 August 2002 Meeting Notes (hand-written) ML0224003122002-08-27027 August 2002 Draft Inserts Regarding Review of Licensee Responses to Bulletin 2001-01 on Circumferential Cracking of Control Rod Drive Mechanism Nozzles ML0224003262002-08-27027 August 2002 Draft Davis-Besse Bulletin 2001-01, Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles, Response and Staff Interaction with Licensee ML0224003562002-08-27027 August 2002 Dates of Davis-Besse Interactions and Hand Written Technical Notes Crack Growth Rates ML0224003592002-08-27027 August 2002 Tech Reviewer'S Notes Regarding Operating History and Attached Failure Time Evaluation Curve ML0224008442002-08-27027 August 2002 C-Note Davis-Besse Bulletin 2001-01, Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles, Response and Staff Interaction with the Licensee ML0315607352002-07-23023 July 2002 07-23-02 - Status of SDP for Davis-Besse RPV Head (to: Commissioner Assistants; from: J W Craig) ML0311103042002-05-28028 May 2002 to Steve from Mark ML0235702202002-03-25025 March 2002 Davis-Besse Reactor Vessel Head (to: Commissioner Assistants; from: J W Craig) ML0235702662002-03-21021 March 2002 INES Rating of Davis-Besse Reactor Head Degradation Event (to: Commissioner Assistants; from: J W Craig) 2012-01-30
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i UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Va cA~774 r I-L
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FAILURE TIME EVALUATION (3180C, 95/50) 360 I I II I I
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Figure 24 Variation of time to failure as a function of initial crack length, for the base case of 318:C, 95/50, crack growth rate.
6.7.3.2 Uncertainties and Sensitivity Studies in the absence of definitive data, the use of parametric values of crack growth rate can provide an understanding of the impact of various assumptions on the evaluation within the context of relevant values of the parameters. For the case of CRDM nozzle cracking, the effect of initial flaw size on the operating time to achieve the critical flaw sizes has been considered in Figure 24. The key parameter with a high level uncertainty is the crack growth rate.
At least three issues affect the selection of the crack growth rate, the environmental conditions, the operating temperature and the statistical basis for the selected crack growth rate. For OD circumferential cracking in CRDM nozzles, Section 6.2.1 concluded that PWSCC conditions are a reasonable approximation to the conditions thought to exist in the annulus between the nozzle and the RPV head, and as such crack growth data for PWSCC conditions are used in this analysis. [As noted in Section 6.2.1, field confirmation of the annulus conditions should be pursued by the industry to eliminate any uncertainty regarding the annulus conditions.]
As described in Section 6.3, the effect of operating temperature on the crack growth rate can be assessed using an Arrhenius extrapolation. For the case of CRDM nozzle conditions, MRP-48 (Ref. 15) indicates that RPV heads are operating in the temperature range from 286C to 318"C (547'F to 605'F). The base case described in Section 6.2.7.2.2 used 318"C (605WF).