3-,

..

Ihr

W'4LF CREEK~

-

~.

NUCLEAR OPERATING CORPORATION

- John A. Bailey -Yko PresidentOperations

Ji.ly 27, 1992'

NO 92-0213

IU. S. Nuclear Regulatory CommissionATTN Document Control Desk r11 ail Station P1-137 LVashington,.D. C. 20555

Subject: Docket No. 50-482: Licensee Event Peport 92-011-00i ;.

Gentiement-

Tbe-attached-Licensee Event Report (LER) is being-submitted pursuant to'

10 CFR 50.73 (a) (2)-(1) concerning a Technical Specification violation.

Very truly yours,

v A/l i x 44John A. BaileyVice PresidentOperations

JAB /aem

cc A. T. Howell (NRC), w/aJ. L. Milhoan-(NRC), w/aG. A. Pick (NRC), w/aW. D. Reckley-(NRC),-w/a

f

I

n t'. O '' f %

9208030307 920727 -

PDR ADOCK 05000482 - A' F PDR . fI

PO Box 418 / Durbngton, KS 66839 i Phone:(316) 364-8931f _ g-

An Ecuat Oppunty Emde)er RA EHCVET r/g

. , , . . . .

- - _ _ ..

,

LICENSEE EVENT REPORT (LER).,

14G4LiiV NAML p) Wolf Creek Generatir'g Station o ! c l o l o l o l 41812 |TIor iDEI A AM I NUPA3t h R) L FA L

I'I'E ('8 Personnel Error In Hot Increasing Emergency Diesel Genctator Testing FrequencyFollowing A Valid Failure Results In A Technical Specification Violation

EVE N1 DATE ($) tER JJMBE A f.) FtFFORT DATE (7) OTHER FAcitrTirs iNyot vf 0 tai~

MhfH DAY WAR WAR Tj[g" . , H[$T bulTH DAY YEAR [WT f4mH (s)0151010!o1 I I

0,[f>1|69 2 9 |2 OlL[1 0 |0 0 |7 2 |7 9 |2.

(t1)oislololo! | I- -

CPEHAna THE REPOfff 19 SUFMT1ED PLEUANT To THE F4EOLNtEMENTS t/10 Cf R (Checa one or nwe of the kiaowg)

SAQOC @) } 20 902(b) 20 405(c) 50 73(a)(2)(iv) 73. 71(b)'

R 8

(10) 11010_

20 405(e)(1)(i) $0 36p)(') Sc 73(aH2)(v) 7 3. 71 ' - )

20 4en(a)o no so uten?) 50 73(ananvm own (sg,cuy u, Aba,,an

M. mmg Y~

20.405(alp)(in) [ $0.73(aH2)(9~

50 73(aH2Hvoi)(A) bWw amt M Test NRC forme

' . . ,

gy: > A q - 3g,A)~ '

,

> k [. 20.405(a)(1)(iv) 50.73 t a)(2 )(u) $ 0. 73(a)(2)(vW)(B):

.'

20 405(a)(1)(v) 50 73(aH2)(09_

50 73f aH2)(n)5

LICENG CC.oTACT FOR TH'S LER (12)

NAAE { TElfPt OE P4M1ERAREA CO(E

steve _ G Wlaeman - Supervisor Licensing _QL W Ljl6]Aj-!81S]311COMPLETE ONE LINE FoA EACH COMF"3NCNT F ALLURE DESCR BED N THIS REPORT 03)

Q^a y %^D ~ CME SWTEM CoMUdM ^ ^cmac swine ca.susw q,

.1 l ! l 1l l I i | | 1 l l %'

,

%..I |_1 l l l I l I l l [ l | - ' ' ' ''

SUPPtfMENTAL REPorTT IXPfCTFU O4) [x E tEb AOf!H DAY YLAR

SdWGSON

] ws rer a wn exercrtosuussmoArr> kNo | | |DATE os)ansTRACT gmt u uoo spacre. a, approamatery reeen sunge.ecace typewamen ima) ve)

On June 26, 1992, it was discovered that the testing Jrcaiency for EmergencyDiesel Generator (EDG) "B" had not been increased to at . ast once per seven'

days in accordance with Technical Specifications (T/S) following a validfailure on June 8, 1992 which resulted in greater than four failures in thelast 100 valid tests. The T/S specifies a surveillance frequency based oneach EDG's operating history. Upon discovery, surveillance test procedure y

STS KJ-005B, which is used to satisfy EDG testing requirements, was 8,

| successfully performed at 2356 CDT. Also, the testing frequency of EDG "B"| was increased to once per seven days..

- The root cause of this event was a combinatian 7f cognitive personnel errorand procedural weakness. An utility engincw 1411ed to formally review thenumber of failures in the last 20 and 100 valid tests immediately followingthe valid failure of EDG "B" on June 8, 1992. Procedure ADM 01-0244, "EDG

|- Reliability Monitoring Program," will be revised to indicate that theprocedure is for monitoring failures for T/S Table 4.8-1 and provide

[ requirements to have the required form completed within five days which willallow the seven day testing frequency to be met if accelerated testing inrequired.

|_ _ _

-_ __ _ __ -_ _ _ __- ____-_ ___

_ - _ _ - _ . ____ . _ _ _ .

LICENSEE EVENT REPORT (LER)TEXT CON 11NUATION*

tacun e,wt m mu uuut a m u a um a n.

"Act mst *n NTiAt : REvisoN

. . _ . - .m . _Y_1 . .[(_UM.N_g

Wolf Creek Generating Station o I 51010 I Oy I 812 9 L2~

_01 |1 0 |0 0|2|~

OF QTLKT (6 mue space en envked one sMoomet NRC fome 3MKs) 07)

INTRODUCTION

On June 26, 1992, it was distcvered that the testing f nquency for Emergency) Diesel Generetor (EhG) "B' [EK-DG) had not been increased in accordance with

Technical Specification Surveillance Requirement 4.8.1.1.2 following a validfailure on June 8, 1992. Technical Specification Surveillance Requirement4.8.1.1.2 requires that each EDG be demonsttated operable by the performanceof testing at the frequency specified in Table 4.8-1, ' Diesel Generator Test

Schedule." Technical Specification Table 4.8 1 specifies a required testingfrequency based on the opetating history of the individual EU2. This eventis being reported pursuant to 10 CFR 50.73(a)(2)(1)(B) as a conditionprohibited by the plant's Technical Specifications.

DESCRIPTION OF FVFNT

Technical Spu ification Table 4.8-1 requires, in part, an EDG test frequencyof at least once per 31 days if the number of failures in the last 20 v411dtests is one or less and if the ownber of f ailures in the last 100 validtest is four or less. If the namber of failures is greater than one in thelast 20 valid tests, Technical Specification Table 4.8-1 requires that thetesting frequency oe increased to at least once per seven days. Thisincreasad testing frequency must be maintained until seven consecutivefailure free tests h oe been performed and the number of failures in thelast 20 valid tests has been reduced to one. If +he number of fa11m es inthe last 100 valid tests is greater than four, Te.unical Specification Table

~

4.8-1 also requires that the testing frequency be increased to at least onceper seven days. This incre.ased test frequency nust be maintained until thenumber of failures in the last 100 valid tests has been redcced to four.

In the last 100 valid tests of EDG "B' there have been five valid f ailures.The first occurred on December 19, 1987, and is discussed in Epecial Report87-010, Supplement 1. The second occurred on November 16, 1988, and is

discussed in Special Report 88-002. The third occurred an November 27, 1988

and is discussed in Special Report 88-004. The fourth occurred on December9, 1989 and is discussed in Special Report 89-003. The fifth occurred onJune 8, 1992 and is discussed in Special Report 92-002 Following the fifthvalid failure, the testirg frequency of EDG "B" should. have been increasedto at least once per seven days in accordance with Technical SpecificationTable 4.8-1 because the number of failures in the last 100 valid testt <a s

greater than four. The next scheduled performance should have been June 16,1992 since surveilltace test procedure STS KJ-005B, " Manual / Auto Start.Synchronization, and Loading of Emergency Diesel Generator NE02," which isused to satisf y testing requirement s f or Technical specification 4.8.1.1.2,had previously-been accomplished on June 9, 1992 following repairs to EDG*B'.

||

. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -

_

'

LICENSEE EVENT REPORT (LER), _ 'TEXT CONTINUATION

m w.ws o> auu wow m a m.m m me.

'4 m um~

Wolf Creek Generating Station o 15_j o 1010 ! 418 ! 2 9 | 2 0 |1 |1l 0 |0 0 |3 0h~ ~

oruxi tu m wu., a was m mune nnc rum un on

On June 26, 1992, while reviewing past f ailures of EDG "B" to support thewriting of Special 3eport 92-002, the utility engineer sponsible formonitoring diesel reliability discovered that the testing frequency for EDG"B" should have been increased to at least once per seven days in accordancewith Technical Specification 4.8-1 following the valid failure on June 8,1992. At 1551 CDT, the Control Room was notified of the failure to increasethe testing f requency of EDG "B". The EDG was declared inoperable andTechnical Specification 3.8.1.1 was entered. Technical Specification3.8.1.1 requires, in part, that the inoperable EDG must be restored tooperable status within 72 hours or the unit must be placed in Hot Standbywithin the next 6 hours and in Cold Shutdown within the following 30 hours.At 2356 CDT, EDG "B" was declared operable af ter the successful performanceof surveillance test procedure STS KJ-005B. Also, the schedule for testingEDG "B" was changed to once per seven days.

ROOT CAUSE AND CORRECTIVE ACTIONS

The root cause of this event was a combination of cognitive personnel errorand procedural weakness. An utility engineer failed to formally review thenumber of fallares in the last 20 and 100 valid tests immediately followingthe valid failure on June 8, 1992. This utility engineer is responsible for

; determining the number of failures related to Technical Specification Table4.0-1 and notifying the appropriated organizations if the +esting frequencyneeds to be increased. The engineer did not formally review the number offailures because the engineer was aware that the failure had been properlyclassified as a valid failure and believed that the appropriateorganizations were taking the proper actions. Also, the utility engineerwas aware that the valid failure on June 8, 1992 was the first failure inthe last 20 valid tests but was not aware that between March of 1987 andJune of 1992 100 valid tests had been conuucted with five valid failures.

Procedare ADP 01-0244, "EDG Reliability Monitoring Program," monitors EDG

| reliability to meet the requirements of 10 CFR 50.63. This procedurecurrently requires the number of failures in the last 20 valid tests to be'

liated on a form for all valid failures, but not for the last 100 valid

t aats since it was not developed for the purposes of meeting TechnicalSpecificati requirements. Also, procedure ADM 01-244 does not require

,

! that this information be completed within a certain time frame. Procedure| ADM 01-244 will be revised to indicate that the procedure is for monitoring

tellures for Technical Specification Table 4.8-1 and provide requirements tohave the form completed within five days which will allow the seven day

| testing frequency to be met if accelerated testing is required. Also, inl order to maintain a better awareness of how many failures have occurred, the

form will be modified to require the number of failures in the last 20 and100 valid tewts to be entered for all starts. These revisions will becompleted by August 31, 1992.

!:

|

|

_ _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

| _'

= ,

LICENSEE EVENT llEFORT (LER';.

*' TEXT CONTINUATION

Fe,GILII Y NAML (1) ( AAkt i PAJPA)LH (2) LL4 Ps Adut H p.) PAGt (3)

* Skfifn" - ",5NE

Wolf Creek Generating Station o1510|010141812 9 |2-

0 |1 \1 Olo 0|4 or0 k-

TLM (M more space 3 requkerd. une ad$konni etRc Form M6A'el (17)

ADDITIONAL INFORMATION

At the time of this event, the plant was in Mode 1 Power Operation, at 100percent Reactor power. There was no threat to the health and safety of thepublic. There was no damage to plant equipment or release of radioactivityas a result of this event. EDG reliability remain +d high at all times basedon the number of failures remaining well below trigger values established

-

for meeting the requirements of 10 CFR 50.63.

Licensee Event Report 482/89-001 00 discusses a similar occurrence in whichthe testing frequency of EDG "B" was correctly increased to once per sevendays following the second valid failure in 20 valid tests, but the increasedtesting frequency was stopped prematurely due to a personnel error bylicensed operations personnel. The corrective actions from this previousevant required the Compliance group to verify the number of failures in thelast 20 valid tests followit.g a valid failure. This corrective action wasinadequate for preventing this event.

_

#

)

c - - _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _______