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SSINS No.: 6835 IN 83-31 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C. 20555 May 19, 1983 Information Notice No. NO 83-31: ERROR IN THE ADLPIPE COMPUTER PROGRAM Addressees: All nuclear power reactor facilities holding an operating license (OL) or construction permit (CP), nuclear steam system (NSS) suppliers, and architect-engineers (AEs). Purpose: This information notice is provided as a notification of an error in the ADLPIPE computer program used for piping analyses. Although DIS/ADLPIPE, Inc. has informed their known users, all potential users of the ADLPIPE computer program may not have received the information. Description of Circumstances: A recent inspection of DIS/ADLPIPE, Inc. was conducted by NRC Region IV in response to a potential 10 CFR Part 21 report to Region IV by Burns and Roe, Inc., that identified an error in the computer code ADLPIPE. The inspection disclosed that DIS/ADLPIPE, Inc. had notified only one user of the code, Burns and Roe. DIS/ADLPIPE verified that the error existed and provided a method of obtaining corrected data. During the inspection DIS/ADLPIPE, Inc. sent a letter of notification to the rest of the known users. According to the DIS/ADLPIPE, Inc. letter, the error involves the stress calculation at reduced outlet tee connections where the computer program option for the 1972 Winter Addenda to the ASME Code for Class 2 components is used. The error was introduced in the May 1974 version of ADLPIPE and was contained in all subsequent versions. The DIS/ADLPIPE, Inc. letter stated that the error affects only calculations performed using the Class 2 component option for the 1972 version of the ASME Code and does not affect calculations performed using the options for the 1974 and 1977 editions of the Code. Based upon this application, the error is not expected to affect reactor coolant system pressure boundary components. The error in the computer program involved the use of the run pipe section modulus for calculating stresses at the branch pipe termination. For the case of reduced outlet tee connections, this causes the stress to be underestimated at the branch side with the magnitude depending on the ratio of run pipe to branch pipe section modulus. . IN 83-31 May 19, 1983 Page 2 of 2 The error can be corrected by a simple hand calculation which multiplies the computer program calculated moment stress at the branch pipe side by the ratio of the run pipe section modulus divided by the branch pipe section modulus. (The section modulus could be calculated in accordance with Section NC-3652.4 of the 1972 Winter Addenda to Section III of the ASME Code.) It is suggested that holders of operating licenses or construction permits review this information for applicability to ASME Code piping analyses at their facilities. No written response to this notice is required. If you have any questions regarding this matter, please contact the Regional Administrator of the appropriate NRC Regional Office, or this office. Edward L. Jordan, Director Division of Emergency Preparedness and Engineering Response Office of Inspection and Enforcement Technical Contact: J. R. Fair, IE 301-492-4509 Attachment: List of Recently Issued IE Information Notices .
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