Evaluation criteria and procedure for nuclear power plant temporary loads/temporary conditions

American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP

Volumn 339, Issue , 1996, Pages 57-61

  Tang, H T ^a   Minichiello, J C ^b   Olson, D E ^c  

^a ELECTRIC POWER RESEARCH INSTITUTE   (United States)

^b Oakbrook Terrace   (United States)

^c SARGENT AND LUNDY LLC   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

LAWS AND LEGISLATION; MAINTENANCE; REACTOR REFUELING; STRUCTURAL ANALYSIS; STRUCTURAL LOADS;

STRUCTURES SYSTEMS AND COMPONENTS (SSCS); TEMPORARY LOADS;

NUCLEAR POWER PLANTS;

EID: 0030416514     PISSN: 0277027X     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Review

References (27)

1. Nuclear Regulatory Commission. Title 10 of the Code of Federal Regulations, Chapter 50, Part 72, "Immediate notification requirements for operating nuclear power plants."
2. Nuclear Regulatory Commission, Title 10 of the Code of Federal Regulations, Chapter 50, Part 73, "Licensee eveat report system."
3. Nuclear Regulatory Commission, NUREG 1022, "Licensee Event Report System - Description of System and Guidelines for Reporting."
4. Nuclear Regulatory Commission, Generic Letter 91-18, "Information to licensees regarding two NRC inspection manual sections on resolution of degraded and nonconforming conditions and on operability." November 1991.
5. Electric Power Research Institute (EPRI), "Guidelines and Criteria for Nuclear Piping and Support Evaluation and Design," EPRI Report TR-101968. a) Volume 1 : Integration of Methods and Guidelines to Evaluate Nuclear Piping and Pipe Support Design and Operability Issues; May 1993. b) Volume 2: Operability Criteria for Piping and Supports; April 1993. c) Volume 3: Anchor Bolt Capacity and Installation Tolerances; May 1993. d) Volume 4: Behavior and Failure Mode of Standard Component Supports; May 1993. e) Volume 5: Guidelines for Seismic/Non-Seismic Interface; April 1993. f) Volume 6: Restraint Stiffness Criteria For Piping Analysis; April 1993. g) Volume 7: Effect of Support Design on Nozzle Loads; May 1993. h) Volume 8: Design Guidance for Integral Welded Attachments; May 1993.
6. Electric Power Research Institute (EPRI), "Guidelines and Criteria for Nuclear Piping and Support Evaluation and Design," EPRI Report TR-101968. a) Volume 1 : Integration of Methods and Guidelines to Evaluate Nuclear Piping and Pipe Support Design and Operability Issues; May 1993. b) Volume 2: Operability Criteria for Piping and Supports; April 1993. c) Volume 3: Anchor Bolt Capacity and Installation Tolerances; May 1993. d) Volume 4: Behavior and Failure Mode of Standard Component Supports; May 1993. e) Volume 5: Guidelines for Seismic/Non-Seismic Interface; April 1993. f) Volume 6: Restraint Stiffness Criteria For Piping Analysis; April 1993. g) Volume 7: Effect of Support Design on Nozzle Loads; May 1993. h) Volume 8: Design Guidance for Integral Welded Attachments; May 1993.
7. Electric Power Research Institute (EPRI), "Guidelines and Criteria for Nuclear Piping and Support Evaluation and Design," EPRI Report TR-101968. a) Volume 1 : Integration of Methods and Guidelines to Evaluate Nuclear Piping and Pipe Support Design and Operability Issues; May 1993. b) Volume 2: Operability Criteria for Piping and Supports; April 1993. c) Volume 3: Anchor Bolt Capacity and Installation Tolerances; May 1993. d) Volume 4: Behavior and Failure Mode of Standard Component Supports; May 1993. e) Volume 5: Guidelines for Seismic/Non-Seismic Interface; April 1993. f) Volume 6: Restraint Stiffness Criteria For Piping Analysis; April 1993. g) Volume 7: Effect of Support Design on Nozzle Loads; May 1993. h) Volume 8: Design Guidance for Integral Welded Attachments; May 1993.
8. Electric Power Research Institute (EPRI), "Guidelines and Criteria for Nuclear Piping and Support Evaluation and Design," EPRI Report TR-101968. a) Volume 1 : Integration of Methods and Guidelines to Evaluate Nuclear Piping and Pipe Support Design and Operability Issues; May 1993. b) Volume 2: Operability Criteria for Piping and Supports; April 1993. c) Volume 3: Anchor Bolt Capacity and Installation Tolerances; May 1993. d) Volume 4: Behavior and Failure Mode of Standard Component Supports; May 1993. e) Volume 5: Guidelines for Seismic/Non-Seismic Interface; April 1993. f) Volume 6: Restraint Stiffness Criteria For Piping Analysis; April 1993. g) Volume 7: Effect of Support Design on Nozzle Loads; May 1993. h) Volume 8: Design Guidance for Integral Welded Attachments; May 1993.
9. Electric Power Research Institute (EPRI), "Guidelines and Criteria for Nuclear Piping and Support Evaluation and Design," EPRI Report TR-101968. a) Volume 1 : Integration of Methods and Guidelines to Evaluate Nuclear Piping and Pipe Support Design and Operability Issues; May 1993. b) Volume 2: Operability Criteria for Piping and Supports; April 1993. c) Volume 3: Anchor Bolt Capacity and Installation Tolerances; May 1993. d) Volume 4: Behavior and Failure Mode of Standard Component Supports; May 1993. e) Volume 5: Guidelines for Seismic/Non-Seismic Interface; April 1993. f) Volume 6: Restraint Stiffness Criteria For Piping Analysis; April 1993. g) Volume 7: Effect of Support Design on Nozzle Loads; May 1993. h) Volume 8: Design Guidance for Integral Welded Attachments; May 1993.
10. Electric Power Research Institute (EPRI), "Guidelines and Criteria for Nuclear Piping and Support Evaluation and Design," EPRI Report TR-101968. a) Volume 1 : Integration of Methods and Guidelines to Evaluate Nuclear Piping and Pipe Support Design and Operability Issues; May 1993. b) Volume 2: Operability Criteria for Piping and Supports; April 1993. c) Volume 3: Anchor Bolt Capacity and Installation Tolerances; May 1993. d) Volume 4: Behavior and Failure Mode of Standard Component Supports; May 1993. e) Volume 5: Guidelines for Seismic/Non-Seismic Interface; April 1993. f) Volume 6: Restraint Stiffness Criteria For Piping Analysis; April 1993. g) Volume 7: Effect of Support Design on Nozzle Loads; May 1993. h) Volume 8: Design Guidance for Integral Welded Attachments; May 1993.
11. Electric Power Research Institute (EPRI), "Guidelines and Criteria for Nuclear Piping and Support Evaluation and Design," EPRI Report TR-101968. a) Volume 1 : Integration of Methods and Guidelines to Evaluate Nuclear Piping and Pipe Support Design and Operability Issues; May 1993. b) Volume 2: Operability Criteria for Piping and Supports; April 1993. c) Volume 3: Anchor Bolt Capacity and Installation Tolerances; May 1993. d) Volume 4: Behavior and Failure Mode of Standard Component Supports; May 1993. e) Volume 5: Guidelines for Seismic/Non-Seismic Interface; April 1993. f) Volume 6: Restraint Stiffness Criteria For Piping Analysis; April 1993. g) Volume 7: Effect of Support Design on Nozzle Loads; May 1993. h) Volume 8: Design Guidance for Integral Welded Attachments; May 1993.
12. Electric Power Research Institute (EPRI), "Guidelines and Criteria for Nuclear Piping and Support Evaluation and Design," EPRI Report TR-101968. a) Volume 1 : Integration of Methods and Guidelines to Evaluate Nuclear Piping and Pipe Support Design and Operability Issues; May 1993. b) Volume 2: Operability Criteria for Piping and Supports; April 1993. c) Volume 3: Anchor Bolt Capacity and Installation Tolerances; May 1993. d) Volume 4: Behavior and Failure Mode of Standard Component Supports; May 1993. e) Volume 5: Guidelines for Seismic/Non-Seismic Interface; April 1993. f) Volume 6: Restraint Stiffness Criteria For Piping Analysis; April 1993. g) Volume 7: Effect of Support Design on Nozzle Loads; May 1993. h) Volume 8: Design Guidance for Integral Welded Attachments; May 1993.
13. Electric Power Research Institute (EPRI), "Guidelines and Criteria for Nuclear Piping and Support Evaluation and Design," EPRI Report TR-101968. a) Volume 1 : Integration of Methods and Guidelines to Evaluate Nuclear Piping and Pipe Support Design and Operability Issues; May 1993. b) Volume 2: Operability Criteria for Piping and Supports; April 1993. c) Volume 3: Anchor Bolt Capacity and Installation Tolerances; May 1993. d) Volume 4: Behavior and Failure Mode of Standard Component Supports; May 1993. e) Volume 5: Guidelines for Seismic/Non-Seismic Interface; April 1993. f) Volume 6: Restraint Stiffness Criteria For Piping Analysis; April 1993. g) Volume 7: Effect of Support Design on Nozzle Loads; May 1993. h) Volume 8: Design Guidance for Integral Welded Attachments; May 1993.
14. H.L. Williams, H.T. Tang, and J.C. Minichiello, "A Proposed Relaxation in Reporting Requirements for Operability," ASME PVP-Volume 285; 1994.
15. J.C. Minichiello, H.T. Tang, and HL Williams, "A Proposed Piping System Short Term Operability Criteria," ASME PVP-Volume 285;1994.
16. D.H. Stout, J.M. Tubbs, W.O. Callaway, H.T. Tang, and DA Van Duyne, " Nuclear Piping and Pipe Support Design and Operability Relating to Loadings and Small Bore Pipinp," ASME PVP-Volime 285; 1994.
17. American Society of Civil Engineers. Nuclear Energy Committee, "Control of Scaffolding. Rigging and Temporary/Construction Loads in Nuclear Power Plants," Preliminary Draft, April 1994.
18. D.T. Ward, T.L. Loch, and M. Amin, "Temporary Loads in Operating Nuclear Power Plants," Proceedings of the 5th Symposium on Current Issues Related to Nuclear Power Plant Structures, Equipment, and Piping, Orlando, Florida, December 1994.
19. T.M. Adams, J.D. Stevenson, and "Seismic Operability Evaluation Procedure for Non-Seismic, Non-Safety Nuclear Power Plant Systems," Proceedings of the ASME PVP Conference, July 1995.
20. D.E. Olson, M. Amin, and L.V. Jacques, "Evaluation of Temporary Loads- Approach to Justify Larger Loads with Less Effort," ASME PVP-Volime 285; 1994.
21. D.E. Olson and M. Amin, "Reduced Pipe Loadings for Temporary Conditions - Criteria Development and Application Experiencel" ASME PVP Conference Proceedings, July 1995.
22. Electric Power Research Institute (EPRI), "Probabilistic Seismic Hazard Characterization of Nuclear Plant Sites in the Central and Eastern United States: Resolution of the Charleston Earthquake Issues," EPRI Report NP-6395-D, April 1989.
23. Nuclear Regulatory Commission, Information Notice 95-09, "Use of Inappropriate Guidelines and Criteria for Nuclear Piping and Pipe Support Evaluation and Design," January 1995.
24. Nuclear Regulatory Commission, Letter from R.A. Capra of NRC to D.L. Farrar of Commonwealth Edison Company on "Reduced Seismic Criteria for Temporary Conditions," October 30, 1995.
25. Welding Research Council Bulletin 352, "Independent Support Motion (ISM) method of Modal Spectra Seismic Analysis," April 1990.
26. Nuclear Regulatory Commission, Letter from B.W. Sheron of NRC to G.M. Eisenberg of ASME on "ASME Code Revisions to the Design Rules for Piping Systems," May 24, 1995.
27. American Society of Mechanical Engineers, Code Case N-411, "Alternative Damping Values for Seismic Analysis of Piping System Section III, Division I. Class 1,2,3, "February 1986.