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, 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, Crane
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:

A computer program is a basic component as defined in 10 CFR 21 when used in

safety-related design activities.

In addition, control measures are required

to prevent the use of incorrect or defective material, parts, and components

as discussed in Criterion VIII of Appendix B to 10 CFR 50.

Similarly, measures

are required to ensure that conditions adverse to quality, such as deficiencies

and nonconformances, are promptly identified and corrected as discussed in

Criterion XVI, Appendix B, 10 CFR 50.

Utilities holding a CP or OL have the primary responsibility to ensure that

computer code errors are adequately reviewed and their impact on past and

present safety-related design calculations are evaluated.

As an example, a recent 10 CFR 21 report to the NRC identified an error in the

Rayleigh frequency calculation contained in the GT STRUDL computer code which

resulted in numerous safety-related systems having to be reanalyzed.

The error

was found during performance of an analysis check on a previously completed

Duct Support and was related to the method used by the program to select seismic

design loads. The code, marketed by the Control Data Corporation (Service

Bureau) and technically supported by its author, Georgia Institute of Technology, is used throughout the nuclear industry, primarily in the analysis and design

of pipe supports and general building structural design. A thorough review and

evaluation of affected designs, in addition to applicable vendors that may have

used GT STRUDM in safety-related applications, is currently being performed by

several CP holders. One CP holder recently reported that this error affected

960 calculations.

However, program users and Service Bureau subscribers such

as Licensees, A/E's and NSSS organizations who did not specify the requirements

of 10 CFR 21 in their contract with the service bureau may not be aware of this

error.

Another example involved the discovery by a nuclear fuels manufacturer of an

input error in a loss-of-coolant-accident (LOCA) code used to calculate the

effects of fuel rod heatup. This computer code error was identified during

performance of a fuel reload analysis.

The error resulted in the value of

fuel rod decay heat generation being too low, causing the calculated peak

cladding temperature (PCT)

to be unconservative.

Corrected calculations showed

that the value of PCT exceeded 2200'F, resulting in several licensees having

to reduce power to comply with the provisions of 10 CFR 50.46.

Several documents are available which may be useful to licensees when reviewing

computer code controls used by vendors engaged in safety-related activities.

NUREG-0040, "Licensee Contractor and Vendor Inspection Status Report," published

quarterly by the NRC provides a detailed, technical and programmatic review of

organizations engaged in supplying safety-related equipment or services to

licensed facilities. This NUREG discusses important plant safety elements, including computer code usage, maintenance, and error report handling, for firms

such as NSSSs, AEs, and nuclear fuel suppliers.

Documents that also may be

IN 86-77 August 28, 1986 useful include IE Information Notices Nos. 85-52, "Errors In Dose Assessment

Computer Codes and Reporting Requirements Under 10 CFR Part 21" (July 10, 1985)

and 83-31, "Error in the ADLPIPE Computer Program" (May 19, 1983). These two

notices focus primarily on computer code errors and 10 CFR 21 reporting respon- sibility.

No specific action or written response is required by this information notice.

If you have any questions regarding this matter, please contact the Regional

Administrator of the appropriate NRC regional office or this office.

or

Director

DivisiM of Emergency Preparedness

and Engineering Response

R. Pettis, Jr., IE

(301) 492-9039 Attachment:

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

Room Emergency

Systems

In Control

Ventilation

8/28/86

All power reactor

facilities holding

an OL or CP

86-75

86-74

86-73 Incorrect Maintenance

8/21/86

Procedure On Traversing

Incore Probe Lines

Reduction Of Reactor Coolant 8/20/86 Inventory Because Of Misalign- ment Of RHR Valves

Recent Emergency Diesel

8/20/86

Generator Problems

Failure 17-7 PH Stainless

8/19/86

Steel Springs In Valcor

Valves Due to Hydrogen

Embrittlement

Recent Identified Problems

8/19/86

With Limitorque Motor

Operators

All power reactor

facilities holding

an OL or CP

All BWR facilities

holding an OL or CP

All power reactor

facilities holding

an OL or CP

All power reactor

facilities holding

an OL or CP

All power reactor

facilities holding

an OL or CP

86-72

86-71

86-70

Spurious System Isolation

Caused By The Panalarm Model

86 Thermocouple Monitor

8/18/86 All GE BWR

holding an

facilities

OL or CP

86-69

Scram Solenoid Pilot Valve

(SSPV) Rebuild Kit Problems

Stuck Control Rod

86-68

8/18/86

8/15/86

8/15/86 All BWR

holding

All BWR

holding

facilities

an OL or CP

facilities

an OL or CP

86-67 Portable Moisture/Density

Gauges: Recent Incidents And

Common Violations Of Require-

All NRC licensees

authorized to possess, use, transport, and

store sealed sources

ments For Use, Transportation, And Storage

OL = Operating License

CP = Construction Permit