NUREG-1264, Forwards List of Refs from NUREG-1264.Circled Refs Must Be Placed in Pdr.Refs 7,10 & 28 Encl.Ref 4 Already in PDR as Ref J.10.3 of NUREG-1150
| ML20239A673 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 09/16/1987 |
| From: | Costello J NRC |
| To: | Rich Smith NRC |
| Shared Package | |
| ML20234B866 | List: |
| References | |
| RTR-NUREG-1150, RTR-NUREG-1264, RTR-NUREG-CR-4273, RTR-NUREG-CR-4926 NUDOCS 8709180085 | |
| Download: ML20239A673 (4) | |
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NOTE FOR: Richard Smith
- FROM: Jim Costello
SUBJECT:
REFERENCES FOR THE PDR Enclosed are:
- 1. A list of references from NUREG-1264 with those that must be inserted l into the PDR encircled.
- 2. Copies of References 7, 10, and 28. Reference 4 has already been inserted '
as Reference'J.10.3 of NUREG-1150.
Thanks for your help.
Jim Costello, SSEB:DE cc: w/o enclosures:
Louise Gallagher l
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Containment Integrity Research Program Plan Manuscript Completed: July 1987 Date Published: August 1987 Division of En0 ineering Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Washington, DC 20555
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- 25. W. E. Baker and J. G. Bennett, " Buckling Investigation of Ring-Stiffened Cylindrical Shells with Reinforced Openings Under Unsymmetrical Axial Loads," Los Alamos National Laboratory, NUREG/CR-3135, LA_-9646-MS, March 1983.
- 26. E. Meller and D. Bushnell, " Buckling of Steel Containment Shells," _1-4, Lockheed Palo Alto Research Laboratory report, LMSC 0812950, September 1982.
- 27. W. E. Baker and T. A. Butler, "A Study of the Effects of Penetration Framing on Steel Containment Buckling Capacity," Los Alamos National Laboratory, NUREG/CR-4892, LA-10977-MS, May .937.
- 28. J. G. Bennett, "An Assessment of Loss-of-Containment Potential j Because of Knuckle Buckling for 4:1 Steel Containment Heads," Los Alamos National Laboratory, NUREG/CR-4926, LA-10972-MS, Advance Copy.*
- 29. H. T. Tang and S. W. Tagart, " Containment and Piping 'Research,"
Proceedings of the Fourteenth Water Reactor Safety Information Meeting, i NUREG/CP-0082, Vol. 5, pp. 523-529, February 1987. {
- 30. R. J. Budnitz et al., "An Approach to the Quantification of Seismic Margins in Nuclear Power Plants," Appendix C. Lawrence Livermore National Laboratory, NUREG/CR-4334, UC10 20444, August 1985.
- 31. L. Greimann et al. , "Probabilistic Seismic Resistance of Steel Contain-ments," lowa State University, NUREG/CR-3127, January 1984.
Available in the NRC Public Document Room, 1717 H Street NW. , Washington, ! .:
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REFERENCES
- 1. U.S. Nuclear Regulatory Commission (USNRC), " Reactor: Safety Study--An Assessment of Accident Risks in U.S. Comercial Nuclear Pcwer Plants "
WASF-1400(NUREG-75/014), October 1975.
- 2. M. Silberberg et al., " Reassessment of the Technical Bases for' Estimating Source Terms," NUREG-0956, July 1986.
- 3. USNRC, " Reactor Risk Reference Document," NUREG-1150, Vol. 3, Draft for ll Comment, February 1987. !
- 4. K. R. Perkins et al., " Containment Loading for Severe Accidents in BVRs !'
with a Mark I Containment," Brookhaven National Laboratory Report, Novem-ber 1984.*
- 5. P. J. Pelto et al., " Reliability Analysis of Containment Isolaticn ,
Systems," Battelle Pacific Northwest Laboratories, NUREG/CR-4220, j PNL-5432, June 1985.
- 6. USNRC, " Policy Statement on Severe Reactor Accidents," Federa_1_ Register, Vol. 50, p. 32138, August 8, 1985. ,
- h. USNRC, " Implementation Plan for the Severe Accident Policy Statement and the Regulatory Uses of New Source-Term Information," December 1986.*
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- 8. J. F. Kiefner et al., " Failure Stress Levels of Flaws in Pressurized Cylinders," Progress in Flaw Growth and Fracture Toughness Testing, ASTM STP536, American Society for Testing and Materials, pp. 461-481, 1973.
- 9. D. B. Clauss, D. S. Horschel, and T. E. Blejwas, " Insights into the Behavior of LWR Steel Containment Buildings During Severe Accidents," ';
Nuclear Engineering and Design, Vol.100, No. 2, March 1987. ]
- 10. L. Greimann, F. Fanous, and D. Bluhm, " Crack Propagation in High Strain Regions of Sequoyah Containment," Ames Laboratory, NUREG/CE-4273, Ames, Iowa, Draft, July 1985.* b
- 11. L. N. Koenig, " Leakage Potential Through Mechanical Penetrations in a Severe Accident Environment," Proceedings of the Third Workshop on Con-tainment Integrity (Washington, DC), NUREG/CP-0076, August 1986
- 12. M. H. Shackelford et al., " Characterization of Nuclear Reactor Contain- ,
Sandia National Laboratories, NUREG/
ment Penetration - Final Report,"
CR-3855, SAN 084-7139, April 1985.
- Available in the NRC Public Document Room,1717 H Street NW., Washington, DC.
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