ML20072F602

Final Deficiency Rept Re Intermittent lock-up of Ga Co Radiation Monitoring Display RM-23.Initially Reported on 830215.GA Co Reviewing RM-23 Design & Conducting Addl Tests. Also Reportable Per Part 21

ML20072F602
Person / Time
Site:	Seabrook
Issue date:	03/16/1983
From:	Devincentis J PUBLIC SERVICE CO. OF NEW HAMPSHIRE, YANKEE ATOMIC ELECTRIC CO.
To:	Starostecki R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
REF-PT21-83 10CFR-050.55E, 10CFR-50.55E, SBN-493, NUDOCS 8303240366
Download: ML20072F602 (2)

Text

c' SEABROOK STATION I %N 1671 Worcemer Road Pubuc Service of New HompeNro *

[" "

March 16, 1983 S BN-493 T.F. Q2.2.2 United States Nuclear Regulatory Commission Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, PA 19406 Attention: Mr. Richard W. Starostecki, Director Division of Resident and Project Inspection

References:

(a) Construction Permit CPPR-135 and CPPR-136, Docket Nos. 50-443 and 50-444 (b) Telecon of February 15, 1983, A. L. Legendre Jr. (YAEC) to Jim Wiggins (NRC Region I)

Subject:

Final 10CFR50.55(e) Report; General Atomic RM-23 Display

Dear Sir:

On February 15, 1983, a potentially reportable 10CFR50.55(e) item was reported [ Reference (b)] regarding the General Atomic RM-23 Display.

It has been determined that this item is reportable under 10CFR50.55(e).

The following information is provided per 10CFR50.55(e)(3) and is considered to be the final report on this item.

Description of the Deficiency During start-up of a CA Technologies Inc. (CA) Radiation Monitoring System at a nuclear power plant, an intermittent lock-up of the RM-23 display was reported. This lock-up causes the " Channel Activity" display to f reeze at the most recent activity value for each channel. Initially, it was thought that this condition was an anomaly related to the specific installation. However, since the RM-23 is safety-related, CA has conducted further studies, and the results of these studies have led them to suspect that a general design problem with the RM-23 may exist.

GA har: determined that this possible defect is reportable pursuant to the requirements of 10CFR21, has notified the NRC.

8303240366 830316 PDR ADOCK 05000443 /

S PDR },}

1000ElmSt.,P.O. Box 330 Manchester.NHO3105 Telephone (603)669-4000 TWX7102207595 V

[ 9' United States Nuclear Regulatory Commission March 16, 1983 Attention: Mr. Richard W. Starostecki Page 2 Analysis of Safety Implications The RM-23 display does provide safety-related radiation parameter information to plant personnel; however, a lock-up of the RM-23 display would not effect the automatic safety function which is initiated by radioiogical conditions at the radiation monitor itself which is uneffected by the display lock-up.

Corrective Action GA is reviewing the RM-23 design and conducting additional sof tware tests in the field and at GA to determine if a generic design problem exists, and if it does, to determine the erlet nature of the problem so it can be resolved expeditiously.

For the RM-23 displays which are installed in Safety Cabinets, modifications, as necessary, will be made prior to delivery to Seabrook Station. For the RM-23P portable display units, modifications will be made in he field at the time of the Unit I radiation monitoring system start-up.

Very truly yours, YANKEE ATOMIC ELECTRIC COMPA!'Y M

^

J. DeVincentis Project Manager ALL/fsf cc: Atomic Sefety and Licensing Board Service List Director, Office of Inspection and Enforcement Washington, DC 20555

., . - , - , - . - , . , . .- -