ML20072H325

Interim Part 21 Rept Re lock-up of RM-23 Display in Radiation Monitoring Sys Giving Erroneous Indication of Channel Activity.Initially Reported on 830223.Problem Software Related.Final Rept Will Be Submitted by 830531

ML20072H325
Person / Time
Site:	Wolf Creek, Callaway, 05000000
Issue date:	03/22/1983
From:	Seiken S STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM
To:	Jay Collins, James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
REF-PT21-83-780-000 10CFR-50.55E, PT21-83-780, PT21-83-780-000, SLNRC-83-016, SLNRC-83-16, NUDOCS 8303290394
Download: ML20072H325 (2)

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o I 94UPPS Standardized Nuclear Unit Power Plant System 5 Choke Cherry Road Rockville, Maryland 20850 mon see soto March 22,1983 SLNRC 83-016 FILE: 0491.10.2 SUBJ: Interim Report: Lock-up of the RM-23 Display in the Radiation Monitoring System (SDR 83-04)

AMr. James G. Keppler Administrator, Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 Mr. John T. Collins Administrator, Region IV U.S. Nuclear Regulatory Commission Suite 1000, Parkway Central Plaza Arlington, Texas 76012 Docket Nos. STN 50-482 and STN 50-483 Gentlemen:

On February 23, 1983, NRC Region III and Region IV representatives were informed by Union Electric Co. (UE) and Kansas Gas and Electric Co. (KGE) respectively, of a deficiency in the Callaway and Wolf Creek Radiation Monitoring Systems. The radiation monitoring system vendor, GA Technologies, Inc., (GA) has also reported the problem pursuant to 10CFR21 reporting requirements. The deficiency involves an RM-23 control room display lockup which could give an erroneous indication et channel activity for ten safety related radiation monitors. The safety related isolation function of the monitors is not affected. For one of the high range radiation monitoring channels (Reg. Guide 1.97, Category

1) there is no redundant means of control room indication.

Preliminary discussions with GA Technologies indicate that the problem is software rather than hardware related. GA has modified the RM-23 software package and tests of this modification are currently being conducted. It is estimated that these tests will continue through most of March, 1983. If the software modification and the test results are deemed sufficiently conclusive, the existing Callaway and Wolf Creek systems will be modified by replacement of currently installed program-mable chips with chips incorporating the modified software.

8303290394 830322 PDR ADOCK 05000482 Ibf S PDR MAR 2 4 E03

SLNRC 83-016 Page Two The SNUPPS Utilities will continue monitoring the GA Technologies testing program, and possible design changes to correct this deficiency, and will keep the NRC informed regarding new developments. In the absence of new developments, a final report is scheduled to be submitted by May 31, 1983.

Very truly yours, f

Idn S. Seiken Manager, Quality Assurance RPW/dck8b12 cc: D. T. McPhee, KCPL G. L. Koester, KGE D. F. Schnell, UE H. W. Roberds, USNRC/WC J. H. Neisler, USNRC/ Cal H. M. Wescott, USNRC Region III s Richard DeYoung, Director I&E Record i

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