ML110810064

Notification of Potential Part 21 Re Defective KPR-14G-125 Relays Discovered During Bench Testing

ML110810064
Person / Time
Site:	Fort Calhoun
Issue date:	03/21/2011
From:	Guinn D Omaha Public Power District
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
46688
Download: ML110810064 (2)

Text

03/21/2011 U.S. Nuclear Regulatory Commission OperationsCenter Event Report Pare I Power Reactor Event# 46688 Site: FORT CALHOUN Notification Date I Time: 03/21/2011 13:19 (EDT)

Unit: 1 Region: 4 State: NE Event Date/ Time: 03/18/2011 (CDT)

Reactor Type: (1) CE Last Modification: 03/21/2011 Containment Type: DRY AMB NRC Notified by: DONNA GUINN Notifications: GREG PICK R4DO HQ Ops Officer: CHARLES TEAL PART 21 GROUP Emergency Class: NON EMERGENCY 10 CFR Section:

21.21 UNSPECIFIED PARAGRAPH Unit Scram Code RX Crit Init Power Initial RX Mode Curr Power Current RX Mode 1 N Yes 100 Power Operation 100 Power Operation DEFECTIVE KPR-14DG-125 RELAYS DISCOVERED DURING BENCH TESTING "The following event description is based on information currently available. The condition is reported under 10 CFR 21.21(d)(3)(i).

"Part 21 Report - Potter Brumfield KRP-14DG-125 Relays, supplied by Southern Testing Services (STS) division of Argo Turboserve Corporation (ATC).

"On March 17, 2011, during bench testing of the KRP-14DG-125 Relays, Fort Calhoun Station (FCS) discovered that some of these relays were defective in that one of the contacts would not close properly after energizing and de-energizing the relay coils. If installed in the plant, the improper closure of this contact could defeat the safety function of the relays that provide a signal to the component supported by that contact. This deviation from the design specifications is reportable per 10 CFR 21. FCS does not have any of the affected relays installed in the plant.

"FCS returned the batch of relays to the vendor for further failure modes and effects evaluation and reporting.

"FCS has not provided any of these relays from our stock to any other licensee.

"The vendor and the [NRC] resident inspector have been notified."

PAGE 1 OF 2 NRC FORM 361 U.S. NUCLEAR REGULATORY COMMISSION (12-2000) REACTOR PLANT OPERATIONS CENTER EVENT NOTIFICATION WORKSHEET EN #

NRC OPERATION TELEPHONE NUMBER: PRIMARY - 301-816-5100 or 800-532-3469*, BACKUPS - [1st] 301-951-0550 or 800-449-3694*,

,*,rli* -Ai*--*n n d rA',r1 -Air 1 -1i *  ;*  ; . . ,,+ r-TQ , fl,

• 40 *.1. fl6 NOTIFICATIONR liE _ AILOODR-MANIZA1IObL. UNIT ~ IM EAL ~CALL BACK #

Ft. Calhoun Station 17~ Donna Guinn ~42537337 EVENT lIME & ZONE EVENT DAM 7 PCINERMODE AFTER -

L 03/18/2011 = 10% 1 10 0%l EVENT CLASSIFICATIONS 1-Hr. Non-Emergency 10 CFR 50.72(b)(1) I I v)(A) Safe SID Capability AMA GENERALEMERGENCY GENEC r TS Deviation ADEV E (v)(B) RHR Capability AINB SITE AEEERGENCY Srr/AAEC 4-Hr. Non-Emergency 10 CFR 50.72(b)(2) __j(v)(C) Control of Rad Release AINC ALERT ALEIAAEC WI TS Required SIT) ASHU v)D c idetitaio AIN)

UNUSUAL EVENT LN,,EC J(iv)(A) ECCS Discharge to RCS ACCS -(xii) Offsite Medical NvED

50.72 NON-EMERGENCY (see next columns) .(iv)(B) RPS Actuation (scram) AJ4-S [(,dii) Loss Comm/AsmtlResp ACOM PHYSICAL SECURITY (73.71) ___ - I((x) Ofisite Notification APRE 60-Day Optional 10 CFR 50.73(a)(1)

MATEI Ai RE Bfn 8-Hr. Non-Emergency 10 CFR 50.72(b)(3) Invalid Specified System Actuation ANV FITNESS FOR DUTY HR1T 1(ii)(A) Degraded Condition ADEG Other Unspecified Requirement (Identify)

-OTHERUNSPECIIED . (seelastcolumn) (iiXB) Unanalyzed Condition AUNA 10 CFR 21. 21 (d) (3) (i)

INFORMATION ONLY NIMF [Iiv)(A) Specified System Actuation ASFl DESCRIPTION Include: Systems affected, actuations and their initiating signals, causes, effect of event on plant, actions taken or planned, etc. (Continue on back)

The following event description is based on information currently available. The condition is reported under 10 CFR 21.21(d) (3) (i).

Part 21 Report - Potter Brumfield KRP-14DG-125 Relays, supplied by Southern Testing Services (STS) division of Argo Turboserve Corporation (ATC).

On March 17, 2011, during bench testing of the KRP-14DG-125 Relays, Fort Calhoun Station (FCS) discovered that some of these relays were defective in that one of the contacts would not close properly after energizing and de-energizing the relay coils. If installed in the plant, the improper closure of this contact could defeat the safety function of the relays that provide a signal to the component supported by that contact.

This deviation from the design specifications is reportable per 10 CFR 21. FCS does not have any of the affected relays installed in the plant.

FCS returned the batch of relays to the vendor for further failure modes and effects evaluation and reporting.

FCS has not provided any of these relays from our stock to any other licensee.

The vendor and the resident inspector have been notified.

NOTIFICATIONS YES NO WILL BE ANYTHING UNUSUAL OR YES (Explain above) ~ NO NOTIFICATIONS YES NO WILL BE ANYTHING UNUSUAL OR NRC RESIDENT NOT UNDERSTOOD? YES (Explain above) NO STATE(s) ]DID ALL SYSTEMS LOCAL FUNCTION AS REQUIRED? [] YES NO (Explain above)

OTHER GOV AGENCIES ______ODE M OF OPERATION ESTIMATED n/a ADDITONAL INFO ON BACK MEDIAIPRESS RELEASE i*- UNTIL CORRECTED: 1 RESTART DATE: n/a UYES MNO

____ ____ _ YS N NRC FORM 361 (12-2000) PRINTED ON RECYCLED PAPER