Information Notice 1986-77, Computer Program Error Report Handling

Computer Program Error Report Handling

ML031250196
Person / Time
Site:	Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Skagit, Marble Hill
Issue date:	08/28/1986
From:	Jordan E NRC/IE
To:
References
IN-86-077, NUDOCS 8608250318
Download: ML031250196 (4)

SSINS No.: 6835 IN 86-77 UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF INSPECTION AND ENFORCEMENT

WASHINGTON, D.C. 20555 August 28, 1986 IE INFORMATION NOTICE NO. 86-77: COMPUTER PROGRAM ERROR REPORT HANDLING

Addressees

All nuclear power reactor facilities holding a construction permit or an

operating license and nuclear fuel manufacturing facilities.

Purpose

This notice is to alert addressees that errors are being identified in computer

programs used during safety-related design activities. These design activities, including facility modifications and reload calculations, may be invalidated by

errors found in computer programs used to support safety-related design calcula- tions. While these errors are contained in error reports prepared by computer

service bureaus, licensees using the program as a basis for safety-related

activities may not be aware that a significant number of errors are being iden- tified. It is expected that recipients will review the information for applica- bility to their quality assurance programs and consider actions, if appropriate, to preclude similar problems from occurring at their facilities. However, suggestions contained in this information notice do not constitute NRC require- ments; therefore, no specific action or written response is required.

Description of the Circumstances:

During reviews of the implementation of computer program error report handling

procedures at various architect engineering companies (A/Es), nuclear steam

supply system companies (NSSS), and nuclear fuel manufacturing facilities, the

NRC has learned that there are a significant number of errors being found in

computer programs used for safety-related design. Further, users (Licensees, A/E's) may not be implementing appropriate measures to ensure that these errors

do not invalidate safety-related calculations already completed, in progress, or to be conducted at a future date.

The computer program errors have usually been found by individual program users

and reported to the computer service bureaus which subsequently report these

errors to all customers using the program, provided that the requirements of

10 CFR 21 are specified in contracts between the service bureaus and affected

customers.

8608250318

IN 86-77 August 28, 1986 Discussion:

in 10 CFR 21 when used in

A computer program is a basic component as defined control measures are required

safety-related design activities. In addition, parts, and components

to prevent the use of incorrect or defective material, to 10 CFR 50. Similarly, measures

as discussed in Criterion VIII of Appendix B to quality, such as deficiencies

are required to ensure that conditions adverse corrected as discussed in

and nonconformances, are promptly identified and

Criterion XVI, Appendix B, 10 CFR 50.

to ensure that

Utilities holding a CP or OL have the primary responsibility

their impact on past and

computer code errors are adequately reviewed and

present safety-related design calculations are evaluated.

identified an error in the

As an example, a recent 10 CFR 21 report to the NRC STRUDL computer code which

Rayleigh frequency calculation contained in the GT to be reanalyzed. The error

resulted in numerous safety-related systems having on a previously completed

was found during performance of an analysis check

the program to select seismic

Duct Support and was related to the method used by Corporation (Service

Data

design loads. The code, marketed by the Control Georgia Institute of Technology, Bureau) and technically supported by its author, the analysis and design

is used throughout the nuclear industry, primarily in A thorough review and

design.

of pipe supports and general building structural vendors that may have

evaluation of affected designs, in addition to applicable

currently being performed by

used GT STRUDM in safety-related applications, is that this error affected

several CP holders. One CP holder recently reported Bureau subscribers such

960 calculations. However, program users and Service

not specify the requirements

as Licensees, A/E's and NSSS organizations who did may not be aware of this

bureau

of 10 CFR 21 in their contract with the service

error.

fuels manufacturer of an

Another example involved the discovery by a nuclear used to calculate the

input error in a loss-of-coolant-accident (LOCA) code was identified during

effects of fuel rod heatup. This computer code error resulted in the value of

performance of a fuel reload analysis. The error the calculated peak

fuel rod decay heat generation being too low, causing Corrected calculations showed

cladding temperature (PCT) to be unconservative. in several licensees having

that the value of PCT exceeded 2200'F, resulting CFR 50.46.

to reduce power to comply with the provisions of 10

to licensees when reviewing

Several documents are available which may be usefulsafety-related activities.

computer code controls used by vendors engaged in

Status Report," published

NUREG-0040, "Licensee Contractor and Vendor Inspection and programmatic review of

quarterly by the NRC provides a detailed, technicalequipment or services to

organizations engaged in supplying safety-related plant safety elements, licensed facilities. This NUREG discusses important report handling, for firms

including computer code usage, maintenance, and error

that also may be

such as NSSSs, AEs, and nuclear fuel suppliers. Documents

IN 86-77 August 28, 1986 85-52, "Errors In Dose Assessment

useful include IE Information Notices Nos. Under 10 CFR Part 21" (July 10, 1985)

Computer Codes and Reporting Requirements Program" (May 19, 1983). These two

and 83-31, "Error in the ADLPIPE Computer and 10 CFR 21 reporting respon- notices focus primarily on computer code errors

sibility.

required by this information notice.

No specific action or written response ismatter, please contact the Regional

If you have any questions regarding this office or this office.

Administrator of the appropriate NRC regional

or Director

DivisiM of Emergency Preparedness

and Engineering Response

Office of Inspection and Enforcement

R. Pettis, Jr., IE

(301) 492-9039 Attachment: List of Recently Issued IE Information Notices

Attachment 1 IN 86-77 August 28, 1986 LIST OF RECENTLY ISSUED

IE INFORMATION NOTICES

Informati on Date of

Notice No. Subject Issue Issued to

86-76 Problems Noted In Control 8/28/86 All power reactor

Room Emergency Ventilation facilities holding

Systems an OL or CP

86-75 Incorrect Maintenance 8/21/86 All power reactor

Procedure On Traversing facilities holding

Incore Probe Lines an OL or CP

86-74 Reduction Of Reactor Coolant 8/20/86 All BWR facilities

Inventory Because Of Misalign- holding an OL or CP

ment Of RHR Valves

86-73 Recent Emergency Diesel 8/20/86 All power reactor

Generator Problems facilities holding

an OL or CP

86-72 Failure 17-7 PH Stainless 8/19/86 All power reactor

Steel Springs In Valcor facilities holding

Valves Due to Hydrogen an OL or CP

Embrittlement

86-71 Recent Identified Problems 8/19/86 All power reactor

With Limitorque Motor facilities holding

Operators an OL or CP

86-70 Spurious System Isolation 8/18/86 All GE BWR facilities

Caused By The Panalarm Model holding an OL or CP

86 Thermocouple Monitor

86-69 Scram Solenoid Pilot Valve 8/18/86 All BWR facilities

(SSPV) Rebuild Kit Problems holding an OL or CP

86-68 Stuck Control Rod 8/15/86 All BWR facilities

holding an OL or CP

86-67 Portable Moisture/Density 8/15/86 All NRC licensees

Gauges: Recent Incidents And authorized to possess, Common Violations Of Require- use, transport, and

ments For Use, Transportation, store sealed sources

And Storage

OL = Operating License

CP = Construction Permit