Reliability study
Contributors: Grant, G. M.; Poloski, J. P.; Grant, G. M.; U.S. Nuclear Regulatory Commission. Office for Analysis and Evaluation of Operational Data. Division of Safety Programs.; U.S. Nuclear Regulatory Commission. Division of Risk Analysis and Applications.; Idaho National Engineering and Environmental Laboratory.
Publisher: Safety Programs Division, Office for Analysis and Evaluation of Operational Data, U.S. Nuclear Regulatory Commission; Supt. of Docs., U.S. G.P.O. [distributor
Published: 1998
Place of publication: Washington, DC
Language: eng
Format: Microform
Subjects: Nuclear power plants -- United States -- Evaluation.; Pressurized water reactors -- Emergency core cooling systems -- United States -- Reliability.; Boiling water reactors.; Diesel motor -- Reliability.
Notes: "Prepared for Division of Risk Analysis and Applications, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission"--Vols. 4-8.

"Idaho National Engineering and Environmental Laboratory, Lockheed Martin Idaho Technologies Company."

Shipping list no.: 98-1081-M (v. 1), 99-0533-M (v. 2), 99-0756-M (v. 3), 2000-0095-M (v. 4, 6, 8), 2000-0142-M (v. 5), 2000-0119-M (v. 7), 2001-0100-M (v. 9), 2002-0537-M (v. 10-11).

"Date published: August 1998" (v. 1); "Date published: April 1999" (v. 2); "Date published: May 1999" (v. 3); "Date published: September 1999" (v. 4-8); "Date published: October 2000" (v. 9).

"NUREG/CR-5500."

"INEEL/EXT-97-00740."

"INEL-94/0158" (v. 4); "INEL-95/0035" (v. 5); "INEL-95/0478" (v. 6); "INEL-95/0196" (v. 7); "INEL-95/00133" (v. 8), "INEEL/EXT-99-00373" (v. 9).

Includes bibliographical references.

Technical. 01/01/87-12/31/95 (v. 1).

Technical. 1984-1985 (v. 2).

Technical. 01/01/1984-12/31/1995 (v. 3).

Technical. 01/01/87-12/31/93 (v. 4-8).

Microfiche. [Washington, D.C.] : Supt. of Docs., U.S. G.P.O., [1998- <26> microfiches : negative.

E8246.
Table of contents: value: v. 1. Auxiliary/emergency feedwater system, 1987-1995 / prepared by J.P. Poloski ... [et al.]; value: v. 2. Westinghouse reactor protection system, 1984-1995 / prepared by S.A. Eide ... [et al.]; value: v. 3. General Electric Reactor Protection System, 1984-1995 / prepared by S.A. Eide ... [et al.]; value: v. 4. High-pressure coolant injection (HPCI) system, 1987-1993 / prepared by G.M. Grant ... [et al.]; value: v. 5. Emergency diesel generator power system, 1987-1993; value: v. 6. Isolation condenser system, 1987-1993 / prepared by G.M. Grant ... [et al.]; value: v. 7. Reactor core isolation cooling system, 1987-1993 / prepared by J.P. Poloski ... [et al.]; value: v. 8. High-pressure core spray system, 1987-1993 / prepared by J.P. Poloski ... [et al.]; value: v. 9. High-pressure safety injection system, 1987-1997 / prepared by J.P. Poloski ... [et al.].