ML20083B696
| ML20083B696 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse |
| Issue date: | 10/01/1990 |
| From: | Claflin D EG&G IDAHO, INC., IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY |
| To: | Resner J NRC OFFICE OF ADMINISTRATION (ADM) |
| Shared Package | |
| ML20081D760 | List: |
| References | |
| FOIA-90-512, RTR-NUREG-CR-5602 DJC-163-90, NUDOCS 9109250168 | |
| Download: ML20083B696 (5) | |
Text
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INEhr Idaho National Engineering Laboratory October 1, 1990 Ms. Jo Ann Resner l
Division of Freedom of Information & Publications Services U.S. Nuclear Regulatory Commission Washington DC 20555 t
TRANSMITTAL OF REPORT FOR PRINTING: NUREG/CR-5603, " PRESSURE-DEPENDENT FRAGILITIES FOR PIPING COMPONENTS - PILOT STUDY ON DAVIS-BESSE NUCLEAR POWER STATION" - DJC-163-90
Dear Ms. Resner:
Enclosed is the camera-ready copy for the rubject report, as well as the NRC Form 335 and a copy of the Form 426A.
The original Fer?. 426A was sent to Dr. G. R. Burdick concurrently with shipment of the camera copy.
If you require anything else or have any questions, please call me on FTS 583-1199.
I Very truly ours, t he a
Dale J. g aflin O Publications Processing Enclosures As stated cc: Ms. S. L. Zeigler, 00E-ID /
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1 NUREG/CR-5603 2GG-2607 RM, RG Pressure-Dependent Fragilities for Piping Components -
Pilot Study on Davis-Besse Nuclear Power Station Prepared by D. A. Wesley, T. R. Kipp*, D. K. Nakaki, H. Hadidi-Tamjed ABB Impell Corporation 27401 Los Altos, Suite 480 Mission Viejo, CA 92691 Under Subcontract to:
Idaho National Engineering Laboratory EG&G Idaho, Inc.
Idaho Falls, ID 83415
- Currently with EQE, Inc., Costa Mesa, CA Prepared for Division of Safety issue Resolution Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Washington, DC 20555 NRC FIN B-5699 7
Under DOE Contract No. DE-AC07-761D01570
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ABSTRACT The capacities of four, low pressure fluid systems to withstand pressures and temper-atures above the design levels were established for the Davis Besse nuclear power station. The results will be used in evaluating the probability of plant damage from interfacing System Loss of Coolant Accidents (ISLOCA) as part of the probabilistic risk assessment of the Davis Besse nuclear power station undertaken by EG&G Idaho, Inc.
Included in this evaluation are the tanks, heat exchangers, filters, pumps, valves, and flanged connections for each system. The probabilities of failure, as a function ofinternal pressure, are evaluated as well as the variabilities associated with them. Leak rates or leak areas are estimated for the controlling modes of failure. The pressure capacities for the pipes and vessels are evalvmd using limit-state analyses for the various failure modes considered. The capacities are dependent on several factors, including the material properties, modeling assumptions, and the pcstulated failure criteria. The failure modes for gasketed flange conne-"ons, valves, and pumps do not lend them-selves to evaluation by conventional structural mechanics techniques and evaluation must 'ely primarily on the results from ongoing gasket research test programs and available vendor information and test data, O
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