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Overpressurization Test of a 1:4-Scale Prestressed Concrete Containment Vessel Model (NUREG/CR-6810,

On this page:Publication InformationAbstractDownload complete documentNUREG/CR-6810 (PDF - 79.7 MB) * * An index to the Data list, which is larger than 3 MB, is provided in Appendix I. Those desiring the complete Data CD can order the CD version of the report (which contains t...

Bulletin 80-24: Prevention of Damage Due to Water Leakage Inside Containment (October 17, 1980 India

SSINS No.: 6820 Accession No.: 8008220270 ...

Information Notice No. 94-25: Failure of Containment Spray Header Valve to Open due to Excessive Pre

UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION WASHINGTON, D.C. 20555 March 25, 1994 NRC IN...

Engineered Covers for Waste Containment: Changes in Engineering Properties and Implications for Long

On this page:Publication InformationAbstractDownload complete documentNUREG/CR-7028, Volume 1 (PDF - 21.12 MB)Publication InformationManuscript Completed: July 2010 Date Published: December 2011Prepared by: C.H.Benson1, W.H. Albright2, D.O. Fratta1, J.M. Tinjum1, E. Kucukkirca...

Information Notice No. 79-24, Overpressurization of Containment of a PWR Plant after a Main Steam Li

IN79024 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 September 23, 1979 MEMORANDUM FOR: ...

An Approach for Estimating the Frequencies of Various Containment Failure Modes and Bypass Events (N

On this page:Publication InformationAbstractDownload complete documentNUREG/CR-6595, Rev. 1 (PDF - 213 KB)Publication InformationManuscript Completed: September 2004Date Published: October 2004Prepared by: W.T. Pratt, V. Mubayi, T.L. Chu, G. Martinez-Guridi, and J. Lehner Ene...

SCDAP/RELAP5 Thermal-Hydraulic Evaluations of the Potential for Containment Bypass During Extended S

On this page:Publication InformationAbstractDownload complete documentNUREG/CR-6995 (PDF - 12.1 MB)Publication InformationManuscript Completed: February 2010 Date Published: March 2010Prepared by: C.D. Fletcher, R.M. Beaton, V. V. Palazov, and D.L. Caraher R.W. Shumway (Consul...

Information Notice No. 94-57 - IN 94-57: Debris in Containment and the Residual Heat Removal System

UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION WASHINGTON, D.C. 20555 August 12, 1994 NRC INFORMATION NOTICE 94-57: DEBRIS IN CONTAINMENT AND THE RESIDUAL HEAT REMOVAL SYSTEM Addressees All holders of operating licenses...

Comparison of Dynamic Characteristics of Fukushima Nuclear Power Plant Containment Building Determin

On this page:Publication InformationAbstractDownload complete documentNUREG/CR-4432 (PDF - 2.24 MB)Publication InformationManuscript Completed: September 1985Date Published: October 1985Prepared by: M.G. Srinivasan, C.A. Kot, and B.J. HsiehArgonne National Laboratory 9700 Sout...

Characterization and Head-Loss Testing of Latent Debris from Pressurized-Water-Reactor Containment B

On this page:Publication InformationAbstractDownload complete documentNUREG/CR-6877 (PDF - 4.97 MB)Publication InformationManuscript Completed: August 2004Date Published: July 2005Principal Investigator: B.C. LetellierPrepared by: M. Ding 1, A. Abdel-Fattah 1, S. Fisher1 , B....

Completion of Containment Performance Improvement Program and Forwarding of Insights for Use in the

July 6, 1990 TO: ALL LICENSEES HOLDING OPERATING LICENSES AND CONSTRUCTION PERMITS FOR NUCLEAR POWER REACTOR FACILITIES EXCEPT LICENSEES FOR BOILING WATER REACTORS WITH MARK I CONTAINMENTS SUBJECT: ...

Posttest Analysis of the NUPEC/NRC 1:4 Scale Prestressed Concrete Containment Vessel Model (NUREG/CR

On this page:Publication InformationAbstractDownload complete documentNUREG/CR-6809 Cover through page xxvi (Front Matter) (PDF - 374 KB) Chapter 1, Introduction (PDF - 6.7 MB)Chapter 2, Final Pretest Analysis (PDF - 3.7 MB)Chapter 3, Test Measurements (PDF - 414 KB)Chapter ...

Information Notice No. 84-74: Isolation of Reactor Coolant System from Low-pressure Systems Outsid

SSINS No.: 6835 IN 84-74 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFI...

Bulletin 78-04: Environmental Qualification of Certain Stem Mounted Limit Switches Inside Reactor Co

UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D. C. 20555 February 21, 1978 ...

Information Notice No. 89-36:Excessive Temperatures in Emergency Core Cooling System Piping Located

UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION WASHINGTON, D.C. 20555 April 4, 1989 ...

Information Notice No. 90-07: New Information Regarding Insulation Material Performance and Debris B

UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION WASHINGTON, D.C. 20555 January 30, 1990 Informati...

Aluminum Chemistry in a Prototypical Post-Loss-of-Coolant-Accident, Pressurized-Water-Reactor Contai

On this page:Publication InformationAbstractDownload complete documentNUREG/CR-6915 (PDF - 19.2 MB)Publication InformationManuscript Completed: August 2006 Date Published: December 2006Principal Investigator: M. KlaskyPrepared by: M. Klasky, J. Zhang, M. Ding, and B. Letellier...

Information Notice No. 93-34 – IN 93-34: Potential for Loss of Emergency Cooling Function due to a C

UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION WASHINGTON, D.C. 20555 April 26, 1993 NRC INFORM...

Information Notice No. 92-35: Higher Than Predicted Erosion/Corrosion in Unisolable Reactor Coolant

UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION WASHINGTON, D.C. 20555 May 6, 1992 NRC INFORMA...

Information Notice No. 88-76: Recent Discovery of a Phenomenon Not Previously Considered in the Desi

UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION WASHINGTON, D.C. 20555 September 19, 1988 ...

Bulletin 77-04: Calculational Error Affecting The Design Performance of a System For Controlling pH

NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D. C. 20555 November 4, 1977 ...

Resolution of Generic Safety Issue 188: Steam Generator Tube Leaks or Ruptures Concurrent with Cont

On this page: Publication InformationAbstractDownload complete documentNUREG - 1919 (PDF - 1.12 MB)Publication InformationManuscript Completed: December 2006Date Published: August 2009Prepared by: E. ReicheltOffice of Nuclear Regulatory Research U.S. Nuclear Regulatory Commiss...

Information Notice No. 94-38: Results of a Special NRC Inspection at Dresden Nuclear Power Station U

UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION AND OFFICE OF NUCLEAR MATERIALS SAFETY AND SAFEGUARDS WASHINGTON, D.C. 20555 May 27, 1994 NRC INFORMATION NOTICE 94-38: RESULTS OF A SPECIAL NRC INSPECTION AT DRESDEN NUCLEAR POW...

Effects of Degradation on the Severe Accident Consequences for a PWR Plant with a Reinforced Concret

On this page:Publication InformationAbstractDownload complete documentNUREG/CR-7149 (PDF - 1.77 MB)Publication InformationManuscript Completed: July 2010Date Published: Jun3 2013Prepared by: J. P. Petti, D. A. Kalinich, J. Jun, K.C. Wagner Sandia National Laboratories Operated...

Information Notice No. 93-34 - IN 93-34, Supplement 1:Potential for Loss of Emergency Cooling Functi

UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION WASHINGTON, D.C. 20555 May 6, 1993 NRC IN...