ML20058A368
| ML20058A368 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 10/01/1990 |
| From: | Pleniewicz R COMMONWEALTH EDISON CO. |
| To: | Davis A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| 90-026-00, 90-26, BYRON-90-0974, BYRON-90-974, NUDOCS 9010260036 | |
| Download: ML20058A368 (5) | |
Text
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i October 1, 1990 LTRI BYRON 90-0974 FILE:
2.07.400 Mr. A. Bert Davis Regional Administrator Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137
SUBJECT:
Byron Unit 2 Operating License NPF-66, Docket No. 50-455 Reporting of Emergency Diesel Generator railures Dear Mr. Davist This report is submitted in accordance with Byron Station Unit 2 Operating License NPF-66 Appendix A, Technical Specification 4.8.1.1.3, reporting of Diesel Generator Tailures.
This report addresses one valid test and failure experienced on the 2A Diesel Generator (DG). The criteria to determine valid and nonvalid tests and failures is in accordance with section C.2.e of Regulatory Guide 1.108.
The attached Deviation Investigation Report DIR 06-02-90-026 provides a-i summary of the event, and the corrective action taken. On August 15, 1990, I
the 2'A Diesel Generator was declared inoperable because the 410L cylinder did not maintain firing pressure and temperature. The failure occurred during surveillance testing while obtaining engine analysis data for the pending 5 year maintenance inspection. The 2A DG was unavailable for approximately 24' hours for investigation and repair of the problem.
The failure was the first failure within the previous twenty valid tests for the 2A DG, therefore the 2A DG remained on monthly test frequency in accordance with Technical Specification Table 4.5-1.
The failure was also the fifth valid failure within the previous one hundred valid tests for the Unit 2 Diesel Generators.
9010260036 901001 PDR ADOCK 05000455 5
PNV R. Pleniewies Station Manager Byron Nuclear Power 6$tation RP/TGB/kc l
cca Byron Station NRC Senior Resident Inspector j
U;S.:NRC Document ControlsDesk, Washington,D$,C.
I INPO Record Center bgECoDistributionList (i %
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OCUtatt0N INvt191GAf t0N REPORT (0!R)
Factitty Name TEE h on Nuclear Power Station 1 10Fl 0 1 3 Title ZA diesel Generator 10L Cylinder Dislocated Puthrod due to Cn11anand Nvdraulle lifter EVENT DATE DIR NUDGER REPORY Daft
/;
// $tQV(NTIAL
// REVl$10N
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Pt')N t H DAY YEAR _
$TA UNIT YEAR HUPSER h
NUDGER PONTH DAY YEAR 1
h, P0wta Q,,,[9 1 l$
9 10 0 16 0 12 9 10 0 12 16 0 10 0 19 1 10 9 10 lE 10 CONTACI FOR THIS DIR gggg if LEPHONE NUPSER AREA CODE
. G. $(auffer. Assistant fachnical Staff Suaerviser Ent. 2274 8l 1l5 2l3l4l-l$l4l4l 1 COMPLETE ONE LINE FOR EACH COMPON[N A LURE D[$CR! BED IN TH13 REPORT CAU$t
$Y$ FEM COMPONENT MANUFAC-REPORTABLE
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CAU$t
$Y$ftM COMPONENT MANUFAC-PEPORTABLE TURER TO NPRDS
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TURER TO NPpD$
1 I i l I i I
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I I I I I 1 1 1
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I I I I i
$UPPLEMENTAL REPORT EXFECTED MDNTH DAY VEAD P
O
$UBMt$$10N l YES tif vet. comalete EXPECTED StaM15$10N Daft)
Ul 40 1io 0 9 TEXT Energy Industry leentification System (t!!$) codes are identified in the text as (XX)
A.
PLANT CONDifl0NS PRIOR TO EVENT _:
Event Date/ flee _ B-15-90 /_ 1200 Unit 1 MODE 1
- _ power Omerau g_,,,
Rm Power j81 RC$ (AB) Temperature / Pressure normal oRRutdn2_.
Onit 2 MODE 1
_P wer eneration Rx power 50%
RC$ (AB) Tempeerature/ Pressure normal eneratiao 2
B.
OCSCRIPT10N OF EVENT 1 On August 15,1990 at 1200, with Unit Two opera *ing at 50% Reactor Power, en engine snelyu. was teing performed on the 2A Diesel Generator (OG) (EK) la preparation for the Unit Two Refueling Outage.
The engine had been running for approximately 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> at 100% lead when cylinder ten lef t (10L) exhaust temperatur' dropped to 300 degrees Fahrenheit, iiring pressure was also found to be approntmately 0 psig.
Cooper Bessemer personnel, who were performing the engine analysis, suspected a failed injector or injector pump. Fuel to the affected cylinder was isolated. The engine run was continued with 19 cylinders operating for an additional hour to complete the engine analysis and trouble shooting of the problem.
$1nce the problem could not be identified and corrected, the 2A Olesel Generator was unloaded and given a normal $f0P signal to allow the engine to cool down.
At l'ho an B 15-90, Technical Specification timiting Condition f or Operation Action Requirement (LC0ARI IPOS 0. t.1 la was initiated. Huclear work Request B78775 was initiated to conduct repairs.
On Cooper Bessemer personnel recommendation, Mechanical Maintenance personnel Installed a new injector and a new injector pump.
The ZA Olesel Generator was restarted with no change in cylinder ten left firing pressure or exhaust temperature. The engine was again shutdown using a normal $f0P signal. Mechanical Haintenance at 'he ellrection of Cooper Bessemer rersanael. lattiated another investigation. Barnvae*
e= amination revealed intake valves that were not completely closing on the 10L cylinder.
There were no systems or components inoperable at the beginning of this event which contributed to this event.
No manual or automatic safety system actuations occurred as a result of this event. Operator actions did not contribute to this event.
(0431R/0076R)
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DEVIATION IWvtlf!GAf!ON REP 0af Itx? CONTINUAfl0N
+
a Form eav 2 4 FACILITY NAME Dit Wusare PaGE
$EQUENTIAL REV!$10N STA ladIf YEAR
-a pasara 8vran Nuclear Pouer stattaa 0 16 0 12 9 10 0l216 0IO 2
0F 013 VtXT Energy Industry Identification System (t!!$) codes are identified in the tout as (KK) 1 C.
CAU$t or EVENTt i
The intermediate cause for the failure was intake valves on the ten left cylinder were not going o mpletely closed during the compression stroke of that cylinder. With intake valves slightly open, no heat g; i
compression was taking place. and the fuel /elr almture was not igniting.
The root cause of the failure was a pushrod which had become dislocated from the rocker are socket. the pushrod was still actuating the rocker are and therefore actuating the valves in the open direction, but was not allowing the rocker are full travel in the closed direction which in turn was preventing the valves from closing completely. Cooper Bessemer concluded that the cause of the pushrod becoming dislocated was a momentarily collapsed hydraulic lif ter which released tension on the rocker are allowing the pushrod to pop out of the rocker are socket.
I D,
$AFETY ANALY11$1 There were no safety consequences as a result of this event. The 29 Diesel Generator, as well as both 1A and IB Diesel Generators, were operable at the time of the event, and would have provided any necessary safety function if required under more severe conditions.
E.
CORRECT 1YE ACTION $t The ZA 10L cylinder intake rocher are assembly and pushred were removed and inspected for any adverse wear or damage and none was found. Seth hydravite lif ters on the valve actuating end of the rocker arms were replaced even though no damage or signs of f ailure were identified. Intake valve springs were tested and found to be normal. Cooper Sessemer personnel assisted Byron Station Mechanical Maintenance personnel in the removal, inspection, and replacement of all components. Upon completion of the maintenance activities the 2A Olesel Generator was run and analysis performed on the ten lef t cylinder using the En-tronics Control En-Spec 3000 Engine Analyser. No abnormal conditions were detected. This indicated proper l
corrective action was taken. This event is considered to be an isolated event. Therefore, no further corrective actions are warranted.
a 9
E e
e (0631R/0076R)
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Drv!ATION INVEST! GAT!0N REPORT TEXT CONTINUATION Fere 2av 2.0.
DIA latere Par.E
$EQUENTIAL REVISION STA tailf YEAR NLaare wants h an Nuclear Pasar statlan 0 16 0 12 9 10 012l6 0 l0 3
0F 013 TEXT Energy Industry identification System (E!!$) codes are identified in the tout as (KX)
F.
RECURRING EYLeif$ SEARCH Ale ANALY$!$:
a)
EVENT SEARCH (DIR. LER) l No previous occurrences.
b)
Igtf1TRY SEARCH (CPEX's NPRDS)
One occurrence of a bent pushrod was found. However, the root cause was unrelated to this event.
c) tfd Not applicable, d)
ANALY11$
No adverse trend identified.
G.
COMPONENT FAILURE DATA:
Although no components were identified as failed, the hydraulic ilf ters were replaced as preventive actions.
MODEL MFG PART MANUFACTURER tillEKLATURE NLSEER NUPSEA.
Cooper Bessemer Hydraulic Lifter KSV-20T 2-02V-004-001 H.
OTHER RELATED 00Cl#ENTS:
None.
I EFFECTIVENESS REVIEW:
Nont $cheduled.
J.
ADDITIONAL DATA:
a)
Affected Technical Specification: 3/4.3.1.1.2 b)
Procedures: Nene, i
c)
Cause Code: KPEM (Other) d)
Equipment Involved:
2A Diesel Generator Valve Train e)
Other: Rocker arm.
(0631R/0076R) e
-w-,
DEv!ATION REPORT DVR NO.
06 - 02 90 - 026 9
STA tlNIT YEAR M.
r rm Rev 2.L o
'Ah l TITLE OF DEV!ATION 2A Diesel Generator 10L Cylinder OCCURRED
.8-15-90..
1200 Dinlacated Punkrad due ta Callaanad Hvdraulle lif ter DATE TIME
$Y$ TEM AFFECTED PLANT $TATUS AT TIME OF EVENT TESTING R'/8775 MODE
'1 POWER (%).
50%
WORK REQUE$T NO.
l K l l
lNO DESCRIPTION OF EVENT 4
While performing engine analysis, af ter 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> at 100% load, cylinder 10L enhaust temperature dropped to
- 300'F. Firing pressure also dropped to - 0 P$1. Fuel to the cylinder was disconnected and the run was completed on 19 cylinders. The DG was declared inoperable at 1300.
I POTENTIALLY $1GNIFICANT EVENT PER N00 O!RECTIVE OP.10 YES NO g
g,g 10CFR50.72 NRC RED PHONE l
l' NOTIFICATION MADE l
l4MOUR l K lNO gg RESPontiatE tuPERvf10R T, Bardauakaa DATE B-15-90 PART2l OPERATING ENGINEER'$ C099ENT$
' NWR generated. Intake valve (s) seem to be the probles.
l X l NOTIFICATION 30 DAY REPORTA8LE/19sFR g
REGION !!!
DATE TIME
~"~
5 DAY REPORT PER 10CFR21 l
l N50 DATE TIME 4
ANNUAL /$PECIAL REPORT REQUIRED g
g W O CO N TE E F W IM M A.I.R. 8 IF A80VE NOTIFICATION !$ PER 10CFR21 E.R. 8 TELECOPY CECO CORPORATE OFFICER DATE TIME PRELIMINARY REPORT COMPLETED AW REVIEWED Th==ma E. Glarich 8-15 00 OPERATING ENGINEER DATE /
//
A Y Y,'
- f = Y fe J 9/
CI C
Y EV RESOLUTION APPROVED AND W/ab M 6 AUTHORIZED FOR DI$fRIBUTION A
$TATION MANAGER OATE 5176 (rorm 15-52-1) 4/12/90
,sCUMENT 10 (0631R/0076R)
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