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

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: ML20234B857 ML20239A681 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
References
RTR-NUREG-1150, RTR-NUREG-1264, RTR-NUREG-CR-4273, RTR-NUREG-CR-4926 NUDOCS 8709180085
Download: ML20239A673 (4)

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UNITED STATES f

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" NUCLEAR REGULATORY COMMISSION 4j S, '

' WASHINGTON, D. C. 20555

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SEP 161987 C l' 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

l Q91g8j870916 ~

l 1264 C PDR I

l

w NUREG-1264 1

Containment Integrity Research Program Plan Manuscript Completed: July 1987 Date Published: August 1987 Division of En0 neering i

Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Washington, DC 20555

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l 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.

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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, DC.

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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.*

1 i

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.

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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-ment Penetration - Final Report,"

Sandia National Laboratories, NUREG/

CR-3855, SAN 084-7139, April 1985.

• Available in the NRC Public Document Room,1717 H Street NW., Washington, DC.

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