05000424/LER-1990-013

LER 90-013-00:on 900601,discovered That Containment Air Lock Leakage Surveillance Exceeded 6-month Test Interval,Per Tech Spec 4.6.1.3.b.Caused by Personnel Error.Plant Surveillance Tracking Program revised.W/900629 Ltr

ML20055D153
Person / Time
Site:	Vogtle
Issue date:	06/29/1990
From:	Hairston W, Odom R GEORGIA POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
ELV-01821, ELV-1821, LER-90-013, LER-90-13, NUDOCS 9007050028
Download: ML20055D153 (4)

LER-2090-013,

Event date:
Report date:
4242090013R00 - NRC Website

text

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, ', y i y Mig l.MGeorgia Power Company ': i

. M, S fpwf 9 ",333 Pedmont Avenoe

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Post Offce Box 1295 i Dermingham Alabama 35201

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June 29, 1990 " *"# " '*"

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W. G. Hairston, m .-

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'ib Docket No. 50-424 w> '

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UF S. Nuclear- Regulatory Commission ,

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ATTN: ~ Document Control Desk '

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V0GTLE ELECTRIC GENERATING-PLANT LICENSEE EVENT REPORT

$$"ita s, IMPROPER APPLICATION OF GRACE PERIOD T0 i 6

-CONTAINMENT AIR LOCK SURVEILLANCE w a In accordance with 10 CFR 50.73, Georgia Power Company hereby submits the 4 - enclosed report related to an event which was discovered on June 1,1990.

Tu ,s Sincerely, l* gl.; [ll Y

'W. G.LHairston, III

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WGH,III/HWM/gm-y, f# Enclssure

LER 50-424/1990-013 q

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-Reora i a Power Company

. Mr._ C. K. McCoy

Mr.1 G. Bockhold, Jr.

"Mr.' P. D. Rushton Mr.' R. M. Odom .

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, NORMS U. S. Nuclear Reaulatory Commission  ;

Mr. S. D. Ebneter, Regional Administrator Mr.;T. A. Reed, Licensing Project Manager, NRR Mr. B. R. Bonser, Senior Resident Inspector, Vogtle i

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f ACILif Y NAME 111 DoCali NUM98R (2) PAGE 43i f V0GTLE ELECTRIC GENERATING PLANT - UNIT 1 oisioioioi 4 [2 i 4 i joppl3  :

IkPROPER APPLICATION OF GRACE PERIOD TO CONTAINMENT AIR LOCK SURVEILLANC EVENT DAf t t$l LtR NUMet R igi REPORT DATE 17) OTMt m f ACILITill (NVotVf D Eel MONYM OAv YEAR YtAR 50,0 5,A h e6 ggggg gg, 9 g gg; 8 AC8LITV h AMtt DOC *.tT NUMetRt57 g

015101010 1 1 I J 0l6 0 l1 93 9l0 ois,o,o,o, i i l 0 l1 l3 0l0 0l6 2.l 9 9l0 n,,,,,,,, TMis REPORT is sueMiTTID PURSUANT TO TMt RIOuiREMENTs Os 30 CeR I rea.ee ea, er -ere .< eae e."..mes titi MOOT it) 1 20 407thl 20 409:e} SO 73teH21t=) 73 71(bl I

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R. M. 000M, NUCLEAR SAFETY AND COMPLIANCE 4 iO4 i 8 i 2,6 i,32i i Ol i COMPLETE ONE LINE FOR I ACM COMPONENT F AILURE Of AJRiSID IN THIF REPORY (131

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l' l I I l l I I l i I I I I SUPPLEMENT AL REPORT E XPECitD (141 MONTH Dev YEAR YE 5 Ill yes, germere EK9f CTIO SUSVIS$ TON QA TEb NO l l l Ae:YR ACT st,m,e so <oo ec , e . everemmewP r,rr a sme . .= rve r.tr.a w i iisi i

On 6-1-90, a Maintenance engineer disc".ered that the containment air lock ,

leakage surveillance interval had exceeded the 6 month test interval specified l in Technical Specification (TS) 4.6.1.3.b on three previous occasions. On each of these-occasions, a grace period had been applied to the surveillance

. interval; however, a footnote to TS 4.6.1.3.b indicates that the grace period ,

provisions of TS 4.0.2 are not applicable. Therefore, the plant had operated in a condition prohibited by the Technical Specifications. No immediate action was

. required due to this discovery since a grace period was not currently being applied to the surveillance.

The cause of this event was cognitive personnel error involving a failure to incorporate the footnote of TS 4.6.1.3.b into the original scheduling of the

. containment air lock leakage surveillance. Corrective action has been taken to revise the plant surveillance tracking program to incorporate the requirements of the footnote.

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NRC POP 48 8thA - U,8. NUCLEA A G.81ULAT AV COMMISSION APPAOVID OWS NO. 3160410s ii E KTlXt 8. 4/30P92

.' . UCENSEE EVENT REPORT (LER) S"N.'T o',$8EEM"oMa"unv%'f'O.' f?nlO TEXT CONTINUATION 23"A"4','F. M*",inJV"inU.'CU,'MS".'"Mf"f!

MW,'8"JJ Of MANAGEMENT "Wota*a',=?"d@#,

AND SUDGET 1NASHINGTON,DC ^".?i!?

20603 PACILITY 08AMS (1) DOCKlf NUMSER (2) Lth NUMeth (66 PA05 (3) vsaa " t=, "'J?.?:

VEGP - UNIT 1 o ls jo jolo j 4l2l 4 1 9l0 -

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0]0 0l2 or 0 l3 TEXT M mure apose h soeuset use ashausnet 44C Penn JE4'al(1h A. - REQ 91REliENT FOR REPORT This report is required per 10 CFR 50.73 (a)(2)(i) because on three separate occasions, a grace period was ap) lied to the containment air lock leakage.

surveillance although use of suc1 grace period is prohibited by, Technical Specification (TS) 4.6.1.3.b.

B. UNIT STATUS AT TIME OF EVENT At the time of discovery of this event, Unit I was operating in Mode ~1 (power operation) at-100% of rated thermal power. On each occasion that the grace period was applied to the containment air lock leakage surveillance,-

Unit I was operating in Mode 1 and remained in Mode 1 operation until after the eventual performance of the surveillance. There was no inoperable equipment which contributed to the occurrence of this event.

C. DESCRIPTION OF EVENT TS 4.6.1.3.b requires, in part, that each containment air lock be demonstrated operable by conducting an overall air lock leakage test at-least once per 6 months. A footnote is provided to indicate that the surveillance grace period provisions of TS 4.0.2 are not applicable to this surveillance. At the Vogtle Electric Generating Plant, both the containment personnel air lock and the containment escape air lock are~ subject to this surveillance.

On 6-1-90, a Maintenance engineer, in preparing a containment integrated leak rate test report, discovered that the containment air lock leakage surveillance had exceeded the allowable 6 month (184 day) test interval on several occasions. A 202 day test interval from 2-5-87 to 8-26-87, and a 201 day test interval from 7-31-89 to 2-17-90, was found to exist for- the Unit I containment escape air lock. Also, a 225 day test interval from 8-18-87 to 3-30-88 was found to exist for the Unit 1 personnel air lock. No leakage test interval for the Unit 2 containment escape air lock or personnel air lock was found to exceed the allowable 6 month test interval.

The surveillance tracking group was contacted and it was discovered that the grace period provisions of TS 4.0.2 had been applied on each of the above occasions when the allowable test interval was exceeded. Therefore, the plant had operated in a condition prohibited by the Technical Specifications.

No immediate action was required due to discovery of this event since the grace period provisions of TS 4.0.2 were not currently being relied upon to satisfy the requirements of TS 4.6.1.3.b.

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010 textn . w . =cr amawim D. CAUSE Of EVENT The cause of the event was cognitive persoi a involving a failure to incorporate the footnote of TS 4.6.1.3.b ina the original scheduling of the containment air lock leakage surveillance. The footnote of TS 4.6.1.3 b had been shown on the original master list of surveillances prepared prior to implementation of the surveillance tracking program; however, this footnote was overlooked when-the scheduling of individual surveillances occurred. Since this error occurred prior to the initial startup of VEGP Unit 1 in 1987 it cannot be determined if contractor or Georgia Power personnel were responsible. There were no unusual characteristics of the work location that directly contributed to this personnel error.

E. ANALYSIS OF EVENT On the occasions that the grace period was applied to the containment air lock leakage surveillance, the applicable air lock was found to be well within its leakage limits when the surveillance was later performed. Based on this consideration, containment integrity was-not compromised by the application of the grace period and.there was no adverse affect on plant

- safety or public health and safety as a result of this event.

F. ' CORRECTIVE ACTION

1. The plant surveillance tracking program has been revised tt, ensure that the grace period provisions of TS 4.0.2 are no longer applied to the containment air lock leakage surveillance.

2. A review of other surveillances for which application of a grace period is not allowed by the Technical Specifications, was performed and it was verified that a grace period has not been applied to those surveillance G. ADDITIONAL INFORMATION

1. Failed Component Identification None

2. Previous Similar Events None

3. Energy Industry Identification System Codes Reactor Containment Building - NHp NGC Penn 304A (6891

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