ML19327A812

LER 87-082-01:on 890620,discovered That Reactor Trip Breaker Had Been swapped-out on 871017 W/O Performing Response Time Test for Breaker Being Installed.Caused by Procedural Inadequacy.Procedure revised.W/891013 Ltr

ML19327A812
Person / Time
Site:	Vogtle
Issue date:	10/13/1989
From:	Hairston W, Odom R GEORGIA POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
ELV-00970, ELV-970, LER-87-082, LER-87-82, NUDOCS 8910180175
Download: ML19327A812 (5)

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Lp' - wuciear operatons 0054 d Docket No.- 50-424

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U. S. ' Nuclear Regulatory Commission -

. ATTN: Document Control Desk l Washington, D. C. 20555 -

Gentlemen:' l

~V0GTLE ELECTRIC GENERATING PLANT

. . LICENSEE EVENT-REPORT

' FAILURE TO TEST BREAKERS RESULTS IN i TECHNICAL' SPECIFICATIONS-VIOLATION p

In'accordance with 10 CFR 50.73, Georgia Power Company-_hereby submits the i enclosed revised report related to an event which occurred on May' 10, 1989.

This revision?is necessary to correct a typographical error.

Sincerely, F ,

, gjmp W. G. Hairston, III WGH,III/NJS/gm

Enclosure:

LER 50-424/1987-082-01

<* xc: Georaia' Power Comoany

, ;Mr. C. K. McCoy Mr;'G. Bockhold, Jr.

H Mr. P.' D. Rushton l- Mr. R. M. Odom j-, ' NORMS u ll. S. ' Nuclear Reaulatory Commission

l. Mr. -S. D. Ebneter, Regional Administrator

-Mr. J. B. Hopkins, Licensing Project Manager Mr. J. F. Rogge, Senior Resident Inspector, Vogtle

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LICENSEE EVENT REPORT (LER) ""'''"'

f ACILITY NAME til .. DOCKET NUMSE R (2) . PAGE I33 Vogtle Electric- Generating Plant - Unit 1 o ls i o t o l'o l 4 2 l 4 t lorl0 l4 TITLE I4)

FAILURE TO PERFORM RESPONSE TIME TEST RESULTS IN TECHNICAL SPECIFICATION VIOLATION ,

EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER F ACILITIES INVOLVED IS)

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20 40eleH1Hv) 50.7*gN2 Hun 90.73teH2Hai LICENSEE CONTACT FOR TH18 LER Hll NJ.ME TELEPHONE NUMBER ARE A CODE R. M. 000M, NUCLEAR SAFETY AND COMPLIANCE 41014 81216l- 131 21011 COMPLETE ONE LINE FOR EACH COMPONENT F AILURE DESCRigED fN THis REPORT H31 IA CAUSE SYSTEM COMPONENT "#%^C* . Rfo$pg[ft , CAUSE sv8 TEM COMPONENT MA%AC-REP yO PR 4

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l I l I I I 'l I l l l 1 1 I SUPPLEMENTAL REPORT EXPECTED H41 MONTH DAY YEAR 3 YES (If yes, comoMw iXPECTfD SUOMISSION DA TEJ NO l l l AS$TLACT (Limft 80 fMP speces. i.e.. easwommerery fifisen orpespose typewestwa Aaeal OSI On 6-20-89, plant personnel were reviewing the maintenance history associated with the Unit I reactor trip breakers (RTB's)-when it was discovered that a RTB had been swapped-out without performing a response time test for the breaker being installed. This swap-out occurred on 10-17-87 and involved the replacement of breaker serial No. 02YN0728-4, which was installed in the main RTB "B" cubicle, with breaker serial No. 860.759-1. Therefore, from 10-17-87 until the replacement of breaker 860.759-1 on 3-6-88, the minimum channels l operable requirements of Technical Specification 3.3.1 were not met as far as response time testing is concerned.

The root cause of this event is considered to be procedural inadequacy in that Procedure 27765-C, " Westinghouse Type DS-416 Circuit Breaker Maintenance", did not contain instructions for performing a response time bench test. Procedure l 27765-C, implements the RTB PM program, and this procedure has been changed to

! address response time testing requirements.

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A. REQUIREMENT FOR REPORT T$is report 11s required per 10 CFR 50.73(a)(2)(1): because the unit. operated in a condition prohibited by the Technical Specifications (T.S.). : Technical t

Specification'3.3.1 requires that: "As a minimum, the Reactor Trip System-instrumentation channels- and interlocks of Table 3.3-1 shall be' OPERABLE....with response times within their limit value".-

On 10-17-87,-a reactor trip breaker (RTB) was changed-out without performing

, a valid response time test for the breaker being installed; therefore, until

-. replacement of this breaker on 3-6-88 the minimum channels operable

• requirements of T. S. 3.3.1 were not met as far as response time testing is l concerned.

-B. UNIT STATUS AT TIME OF EVENT- l At the time of the breaker change-out on 10-17-87, Unit l'was in Mode 5 with ,

an 18-day maintenance outage in progress.

• C. DESCRIPTION-On 6-20-89, plant personnel were reviewing the maintenance history l associated with the Unit 1 RTB's when it was discovered that on 10-17-87, a RTB had been swapped-out without performing a response time test for the breaker being installed.

l' l- On-10-16-87, an inspection of the breaker installed in the main RTB "B" 4 cubicle (i.e., breaker serial No. 02YN0728-4) indicated that a weld on the L breaker pole shaft lacked proper fusion. Therefore, on 10-17-87, breaker 02YN072B-4 was swapped-out with a spare breaker (i.e., breaker serial No.

L 860.759-1) obtained from the Nuclear Operations warehouse. Prior to L installation, breaker 860.759-1 was inspected por the instructions of L Procedure 27765-C, " Westinghouse Type 05-416 Circuit Breaker Maintenance";

[ however, these instructions did not specify performing a response time bench l test and no special provision was made to perform such a test at that. time.

Subsequently, on 3-6-88, breaker 860.759-1 was removed from the RTB "B" cubicle and another spare breaker (i.e., breaker serial No. 860.759-2) was l' installed in its place. On this occasion, the need for performing a response time test for the breaker being installed was recognized. A special test procedure was attached to the associated work order, and a response time bench test was completed for breaker 860.759-2 in addition to l performing the inspections specified by Procedure 27765-C. Similarly, a l

response time bench test was performed for breaker 860.759-1 after its removal from the RTB "B" cubicle and an acceptable response time was indicated.

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D. CAUSE OF EVENT ,

Technical Specification Surveillance Requirement 4.3.1.2 states.that "The REACTOR. TRIP SYSTEM RESPONSE TIME of each Reactor trip function shall. be demonstrated to be' within'its limits at least once per 18 months."

Procedure 54721-1, "1HS-40002 (Manual Reactor Trip) TAD 0T", is. the designated Unit 1 procedure for. demonstrating the response time of the reactor trip breakers as a part of the total reactor trip system response  ;

time.- Procedure 54721-1 is intended to be performed on an 18-month frequency during refueling outages with the breakers installed in the switchgear. Procedure 54721-1 was performed on 1-30-87, prior to initial fuel-load for Unit 1,.and then-again on 10-21-88 during the first Unit I refueling outage.

Procedure 27765-C contains instructions for performing both 6-month and 18-month PM inspections of the reactor trip breakers. These inspections are +

. performed with the breaker removed from the switchgear and located in a

• special test area within the maintenance shop. At the time of this event, Procedure 27765-C did not contain any~ instructions for performing a response-

. time' bench test for the breaker being inspected. <

For the breaker swap-out which occurred on 10-17-87, it was not recognized  :

that the response times obtained on 1-30-87 per Procedure 54721-1 could be impacted and therefore no response time bench test was performed on that occasion.

( The root cause for this event is therefore considered to be procedural L inadequacy in that Procedure 27765-C does not contain instructions for performing a response time bench test.

A contributing cause was the failure of Work Planning personnel to adequately review the work order for Technical Specification compliance.

E. ANALYSIS OF EVENTS Wh'en proper response time testing was performed, breaker 860.759-1 tested ..

successfully. Additionally, reactor trip report records indicate no l abnormal response times during reactor trips which occurred while the

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inadequately tested RTB was in service. Based on these considerations, L there was no adverse effect on plant safety or public health and safety as a result of this event.

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F. ' CORRECTIVE ACTIONS

, '; 1. Procedure 27765-C, " Westinghouse Type DS-416 Circuit Breaker Maintenance", implements the RTB PM program. This procedure has recently been' revised to address response time testing requirements.

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2. Personnel who. reviewed the work order were counseled regarding the 4 importance of T. S. compliance.  ;

'G. ADDITIONAL INFORMATION i

1. Failed Components-None

2. Previous Similar Events None ,

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