Information Notice 1979-36, Computer Code Defect in Stress Analysis of Piping Elbow

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Computer Code Defect in Stress Analysis of Piping Elbow
ML031180207
Person / Time
Site: 05000000
Issue date: 12/31/1979
From:
NRC/OI
To:
References
IN-79-036, NUDOCS 7910250519
Download: ML031180207 (2)


UNITED STATES SSINS No.: 6870

NUCLEAR REGULATORY COMMISSION Accession No:

OFFICE OF INSPECTION AND ENFORCEMENT 7910250519 WASHINGTON, D.C. 20555 December 31, 1979 IE Information Notice No. 79-36 COMPUTER CODE DEFECT IN STRESS ANALYSIS OF PIPING ELBOW

Description of Circumstances

The NRC was informed on December 17, 1979 that a computer code, NUPIPE, used

in the stress analysis of pipinq systems contained a defect which could result

in incorrect stress values at one end of pipinq elbows. This defect was iden- tified from discussions with a user of NUPIPE and the NUPIPE code developers.

The stress calculation error can occur when a flexible joint is modeled atdefect the

end of an elbow (ELBOW-ELASTOJT connection in NUPIPE terminology). This

in the N1IPIPE code is in the transformation of the loads in the ELASTOJT coordin- ate axis to the piping ELBOW coordinate axis. The incorrect coordinate axis

loads

transformation may incorrectly interchange the torsion and bending moment

on the pipinq elbow. This can result in the incorrect assignment of the stress

intensification factor for the individual moments. The correct stress may be

hiaher or lower than calculated by NUPIPE, depending on the loading condition.

Four conditions must exist for the possibility of the calculation of an incorrect

stress in the NUPIPE code:

1. an USAS B31.1.0 - 1967 Code analysis is being done, and

2. an ELBOW-ELASTOJT connection exists, and

3. an absolute sum of two load cases is beinq calculated, and

local

4. the ELBOW torsional moment axis does not align with the ELASTOJT

x-axis.

Webster, Possible users of the NUPIPE code include the code developer, Stone and currently

using the Cybernet system. The NRC is

EG&G (Idaho Falls), and those

reviewing the extent of usage of the NUPIPE code and the generic implications

occur in

for other facilities. There is a potential for a similar defect to

other piping analysis computer codes.

siqnif- This Information Notice is provided as early notification of a possible for

icant matter. It is expected that recipients will review the information

in

possible applicability to their facilities. No specific action is requested

further

response to this Information Notice. If NRC evaluations so indicate, licensee actions may be requested or required. If you have any questions

NRC

regarding this matter, please contact the Director of the appropriate

Reaional Office.

No written response to this IE Information Notice is required.

-7 IE Information Notice No. 79-36 Enclosure

December 31, 1979

RECENTLY ISSUED

IE INFORMATION NOTICES

Information Subject Date Issued To

Notice No. Issued

79-35 Control of Maintenance 12/31/79 All power reactor facilities

and Essential Equipment with an OL or CP

79-34 Inadequate Design of 12/27/79 All holders of power reactor

Safety-Related Heat OLs and CPs

Exchangers

79-33 Improper Closure of 12/21/79 All power reactor facilities

Primary Containment holding OLs and CPs

Access Hatches

79-32 Separation of Electrical 12/21/79 All power reactor facilities

Cables for HPCI and ADS holding OLs and CPs

79-31 Use of Incorrect Amplified 12/13/79 All holders of power reactor

Response Spectra (ARS) OLs and CPs

79-30 Reportinq of Defects and 12/6/79 All power reactor facilities

Noncompliance, 10 CFR Part 21. holding OLs and CPs and

vendors inspected by LCVIP

79-29 Loss of NonSafety-Related 11/16/79 All power reactor facilities

Reactor Coolant System holding OLs or CPs

Instrumentation During

Operation

79-28 Overloading of Structural 11/16/79 All power reactor facilities

Elements Due to Pipe Support with an OL or CP

Loads

79-27 Steam Generator Tube . 11/16/79 All power reactor facilities

Ruptures At Two PWR holding OLs and CPs

Facilities79-12A Attempted Damaqe To New 11/9/79 All Fuel Facilities, Fuel Assemblies research reactors, and

power reactors with an

OL or CP

79-26 Breach of Containment 11/5/79 All power reactor facilities

Inteqrity holdinq OLs and CPs