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United States Nuclear Regulatory Commission - Protecting People and the Environment

Information Notice No. 88-82, Supplement 1: Torus Shells with Corrosion and Degraded Coatings in BWR Containments

                                  UNITED STATES
                          NUCLEAR REGULATORY COMMISSION
                             WASHINGTON, D.C.  20555

                                   May 2, 1989

                                                 AND DEGRADED COATINGS IN 
                                                 BWR CONTAINMENTS


All holders of operating licenses or construction permits for boiling water 
reactors (BWRs).


This information notice updates Information Notice No. 88-82, dated October 
14, 1988, by providing additional insight into the underwater inspection 
method for detecting corrosion and degraded coatings of suppression pool steel
shells in BWR containments.  It is expected that recipients will review the 
information for applicability to their facilities and consider actions, as 
appropriate, to avoid similar problems.  However, suggestions contained in 
this information notice do not constitute NRC requirements; therefore, no 
specific action or written response is required.  


Information Notice No. 88-82 discussed the problem of corrosion and degraded 
coatings in BWR suppression pool steel shells.  The notice indicated that the 
measured corrosion rate of some torus shells exceeds the design corrosion 
rate.  Because torus shell degradation affects containment integrity, BWR 
licensees perform periodic visual inspections of the suppression pool steel 
shells.  These visual inspections can be performed in several different ways. 
Information Notice No. 88-82 stated that the most effective inspection method 
was to drain the torus and inspect it under dry conditions.   


The NRC has obtained additional information about underwater inspection tech-
niques of BWR suppression pool shells that addressees may wish to consider.  
The capabilities of the underwater technique appear to include desludging, 
mapping of critical areas, coating adhesion tests, measurement of dry film 
thickness, and spot repairs of degraded areas.  Potential advantages from the 
technique appear to be reduced radiation exposure of personnel and elimination
of the need for draining the suppression pool.  

.                                                       IN 88-82, Supplement 1
                                                       May 2, 1989
                                                       Page 2 of 2

No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the technical 
contact listed below or the Regional Administrator of the appropriate regional 

                              Charles E. Rossi, Director
                              Division of Operational Events Assessment
                              Office of Nuclear Reactor Regulation

Technical Contact:  Daniel Prochnow, NRR
                    (301) 492-1166

Attachment:  List of Recently Issued NRC Information Notices
.                                                       Attachment IN 88-82, 
                                                       Supplement 1 May 2, 
                                                       1989 Page 1 of 1

                             LIST OF RECENTLY ISSUED
                            NRC INFORMATION NOTICES 
Information                                  Date of 
Notice No._____Subject_______________________Issuance_______Issued to________

89-43          Permanent Deformation of      5/1/89         All holders of OLs
               Torque Switch Helical                        or CPs for nuclear
               Springs in Limitorque                        power reactors. 
               SMA-Type Motor Operators 

88-97,         Potentially Substandard       4/28/89        All holders of OLs
Supp. 1        Valve Replacement Parts                      or CPs for nuclear
                                                            power reactors. 

89-42          Failure of Rosemount          4/21/89        All holders of OLs
               Models 1153 and 1154                         or CPs for nuclear
               Transmitters                                 power reactors. 

89-41          Operator Response to          4/20/89        All holders of OLs
               Pressurization of Low-                       or CPs for nuclear
               Pressure Interfacing                         power reactors. 

88-75,         Disabling of Diesel           4/17/89        All holders of OLs
Supplement 1   Generator Output Circuit                     or CPs for nuclear
               Breakers by Anti-Pump                        power reactors. 

89-40          Unsatisfactory Operator Test  4/14/89        All holders of OLs
               Results and Their Effect on                  or CPs for nuclear
               the Requalification Program                  power reactors. 

89-39          List of Parties Excluded      4/5/89         All holders of OLs
               from Federal Procurement                     or CPs for nuclear
               or Non-Procurement Programs                  power reactors. 

89-38          Atmospheric Dump Valve        4/5/89         All holders of OLs
               Failures at Palo Verde                       or CPs for nuclear
               Units 1, 2, and 3                            power reactors. 

89-37          Proposed Amendments to        4/4/89         All U.S. NRC 
               40 CFR Part 61, Air                          licensees. 
               Emission Standards 
               for Radionuclides 
OL = Operating License
CP = Construction Permit 
Page Last Reviewed/Updated Friday, May 22, 2015