05000259/LER-1983-066, Updated LER 83-066/03X-1:on 831112,interlock That Prevents Bridge Travel Over Core W/One Rod Withdrawn & Fuel Grapple Extended Failed to Operate,Resulting in Loss of Rod Block Function.Caused by Improper adjustment.W/840309 Ltr

Updated LER 83-066/03X-1:on 831112,interlock That Prevents Bridge Travel Over Core W/One Rod Withdrawn & Fuel Grapple Extended Failed to Operate,Resulting in Loss of Rod Block Function.Caused by Improper adjustment.W/840309 Ltr

ML20087H043
Person / Time
Site:	Browns Ferry
Issue date:	03/09/1984
From:	Holder E, Jones G TENNESSEE VALLEY AUTHORITY
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
LER-83-066-03X, LER-83-66-3X, NUDOCS 8403200213
Download: ML20087H043 (6)

LER-2083-066, Updated LER 83-066/03X-1:on 831112,interlock That Prevents Bridge Travel Over Core W/One Rod Withdrawn & Fuel Grapple Extended Failed to Operate,Resulting in Loss of Rod Block Function.Caused by Improper adjustment.W/840309 Ltr

Event date:
Report date:
2592083066R00 - NRC Website

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• UPDATE REPORT PREVIOUS REPORT DATE 12/8/83 ConTRot stock: l l l l l lh (PLEASE PRINT on TYPE ALL REQUIREo INFoRMdTIoN) l il ti LICENSEE n i n CODE i v i i l@l n I n i I n LsCENa i n i NOVUEH n i n l a l_10 I n l@l411 11 li li l@l_I Si CAI bel@

c i 7 8 9 84 lb JS 26 LICENSE TYPE JG CO'J'T f3T71 0' LLJ@l 01 s lDOCKET o l 010121 s 19 l@l i EVENT ii li 121813 l@l 74 73 i I I PEPOHT DATE I I 80 l@

1 4 60 61 NUY8EH OS 63 DATE EVENT DESCRIPTION AND PRODABLE CONSEQUENCES h During refuel outage, while performing SI 4.10. A.1, the interlock that I in 12 l l g 3 ; prevents bridge travel over the core with one rod withdrawn and fuel g= apple 1

,,,,,g extended failed to operate. This resulted in a loss of rod block function f

, ,, g with the platform over the core (T.S. 3 10.A.1). There are no redundant I

, ;o gi g systems. There was no effect on the health and safety of the public. I O 7 10181 l

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KEr ACT O ON L ti MET b HOUHs S BP IT FORlbUS. $ PPLIE MAN CTURER lJ_j@34W @ W@ W@ l0 l 0l 0l 0l 37

[,Y_j @ lY l@ lN l@ lG l 0 l 8 l 0 i J3 3h 36 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h The lever arm on limit switch No. 1 (GE Part No. CR 115GW307) was found to b-gl i

, ,  ; improperly adjusted. The cause is unknown. The lever arm was ad.iusted ar3 SI I

, , , [ 4.10.A.1 was successfully completed. SI 4.10.A.1, Step 18, was revised to gg verify that licit switches 1 and 2 actuate for both CW and CCW rotation and to g ,, , y Erify the limit switch's lever arms are installed and adjusted properly.

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PE n50NNEL EXPO $URES NUun E H DE SCRIPTION --

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^ g ADOCK 05000259 s T ' " E CY>^P"T v'O, ' ACT V @ PDR f'~I'Il(_gjhl t NA 7 a ? 10 '

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NAVE OF PREPARER E. T.' Holder PHONE: (205) 729-0885'

, Tenn

ssea Vclley Authority . Form BF 17 m

. Browns Fcrry Nucl:ar Plant BF 15.2 2/19/82 LER SUPPLEMENTAL INFORMATION BFRO 2sg /_ 83066 R1 Technical Specification Involved 3.10.A.1

. . ~ .

Reported Under Technical Opecification r,aM.h.(2)

• Date Due NRC 4/1/84 Event Narrative:

Unit 2 was operating at 73 percent power and both units 1 and 3 were in

' I refueling outages. While performing SI 4.10. A.1 on unit 1,the interlock limit switch No. 1 failed to stop the bridge from traversing over the core '

with one rod withdrawn, the fuel grapple extended, and the mode switch in refuel. This resulted in a loss of the rod block function with the platform over the core (T.S. 3 10.A.1). The SI was stopped and bridge moved from over the core. The lover arm on limit switch No. 1 (GE Part No. CR 115GW307) was found to be improperly adjusted. The cause is unknown as the interlock switches were checked for ' proper adjustment, tightness, and operationally tested in previous steps of SI 4.10.A.1. SI 4.10.A.1, Step 18, was revised to verify that limit switches 1 and 2 actuate for both CW and CCW rotation and to verify the limit switch's lever arms are installed and adjusted properly.

4 C3 '

. = . .. . .

~,

• P_revious Similar Events:

LER BFRO-50-259/7727 I LER BFRO-50-260/8054 LER BFRO-50-296/8053 LER BPRO-50-259/8301

.  ?'

^'

r-1 Retention: ')eriod - Lifetime; Responsibility - Document Control Supervisor j

• Revision : ((

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't, , ,f,n. me; t'.sile .iu t bo ".* '

+4.r ns' F. rry Nucle.ir .  !

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W) F..rm is F-7 BF 1 itF 11.'

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Instr.uction Number ny gt t ag,gi is l' nit . No.1, _1. 3 .

llin:orv f 1:i visn'ns t For IH T Til!*? _REFtfELI!;G INTERLOCKS Itse (sn'v)

A pp rova,lJa ts . \ f f_iglyil l'a gi s 2/_01/84 3, 3A

. 17 /DalB't // 2. 2 W m3Al C

• J 2/08/83 4, 4A, 5. SA.

J 210Bl_O / 6, l_1_, _ 12 , 13 1:<:as0n For INvision _ For reoccurrence coitrol '

_of LER 50-259/83366

/

/

/

/

1

] Pages Atfecteil 3. 3A

• j . .

p aOQAls ls thisaudit, change in response etc.? Yes to an LEll. IE Bulletin N!'C Inspection !!cport,

?

x No (If yes. specify document under-reason for revision.)

Chanie in procedural detail ot' FSAll or other licensing document? '

} Yes No J  ; New instruction? Yes No X

tif yes to either question, a t!SQD is required. )

• ls this a work plan initiated change?

Yes (Work Plan No. ) X No Fire Protection System involved? Yes No _ x (if yes, review and signatu're of fire protection engineer is requit;cd.) ~

l-

• [

'l l .. 4 Fire Protection Engineer -

Was this change tr,ade to meet a NRC commitment?

(if'yes'. refer to BF 2.3 for proper identification ofYes x the change.Y No Security System involved? Yes No X (If yes, review and signature of Public Safety Services Supervisor is required.)

g Public Safety Services Supervisor, f- b / 1/20/84 Pappared.Dy

(/ Date 1

/. /d / /d/

PORC 'hairman l'a te f _

/ 1A / 1/20/84

_ 'Submntifd By Date .

<J '

' Plant' ' perintendent

• / M

/Dt/te/

Retention: Period - Lifetime; Responsibility

" (Note: - Document Control Supervisor If this is a new instruction or tnstruction deletion, document control will update the source document matrix.)

• Revision

_ _ _ _ _ - - - -- )

q --

f1

., [% hPay,n 3 T,F S1 4.LO.A.t FEB 1 is.;

SI 4.10.A.1 Refueling Interlockn runctional Te>it fl0T!*.: Omit steps 10 through 17 unless the nervice platform in over the coro and the jib crane in attached. hhe appropriate entrien in nituations 2 and 3 of the data sheet.

I5IC/C

!RC Rpt 10. Check that the modo awitch in in " Refuel", that all control rodn D9/80-40 the refuelir.

are fully inuerted, (except as noted in Step 1) and that platform is over thn pool.

11. Withdraw one control rod one notch.

12. Attempt to load jib crano holut with a 313 lb. load (underwater weight.) Obnorve that hoist cannot be landed.

_ 13. Fill in situation 2 on data sheet.

NRC/C -

NRC Rpt 14. Inceet all control roda (except au noted in Step 1.)

2)9/80-40 15,1.oad jib crano holut with the 313 lb load.

16. Attempt to withdraw ene control rod one notch. Ohnerve a rod .

block. Transfer mode nwitch to "Startup." Attempt to withdraw one control rod one notch. Observe rod block.

17. Fill in nituation 3 on the data sheet and remove the load from the jib crane.

18. Check the following conditionu:

. IIRC/C CAUTION: Verify that the refueling platforn interlock limit NRC kpt switches actuate for both clock-wine and counter 259/83066 clock-wise operation. (If not, then adjust actuator to do so.)

Verify that ti,e wheel on the actuator arm trailu the actuator pin dhen moving toward the core.

• *

• KC/h"R KLTS /17YG'l .

4. 'MGVfXTURfM 4Ml BEAT

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TCNRO costb Q .*

. Acr.;ura tw nwm Vority that clie actuator arm is adjusted so that the

, contactsarefn(1)thenormalpositionwhenthecam is not under the limit nuitch and (2) the non-normal position when the cam is under the switch.

.<.<~. .

F

"' [,

/<pa;',o lA s EF SI 4.LO.A.1 FEB 119M SI 4.10.A.1 Refueling Interlocks Punctional Test (Continued)

NRC/C Prior to the performance of any further steps, verify NRC Rpt th::t refuel floor maintenance electricians have checked 2f>0 /8054 the refueling platforn interlock limit switches for condition and tightness of set screw on the actuatin;;

am of both limit uwitches,

n.  !! ode switch in "Startup"

b. Refueling platform over pool NRC/C '

NRC Rpt "c . All control rods fully inserted, (except as noted in Step 1)

~

259/80-40 and one control rod celected.

19. %ve refueling platform toward core. Observe pintform motion in blocked as it approaches core.

20. F111 in situation 4 on the data sheet.

21. Attempt to withdraw one rod one notch. Observe rod block.

22. Fill in situation 5 en the data cheet.

23.  !!ove refueling platform toward pool to clear refuelim; interlock.

24. 111thdraw two control rods one notch each.

IKrfE: Scicct control rods in accordance with rod worth minimizer patterna.

~~.

e

• Rovision 3 .__

1 1 +

s P

~ TENNESSEE VALLEY- AUTHORITY Browns Ferry Nuolsar Plant F. O. Box 2000 '

Decatur, Alabama 35602 March 9, 1984 34ggis M0:52 ,

4 Mr.. James P. 0'Reilly, Regional Administrator U. S. Nuclear Regulatory Cona.ission Region II 101 Marietta Straet, Suite 3100

, Atlanta, Georgia 30303 -

Dear Mr. 0'Reilly 4

. TENNESSEE VALLEY AUTHORITY - BROWNS PERRY NUCLEAR PLANT UNIT 1 - DOCKET No.250-259 - FACILITY OPERATING LICENSE DPR REPORTABLE 0CCURRENCE REPORT BFRO-50-259/03066 R1.

References H. J. Orsen's memorandum to you dated December 8, .1983

~

The enclosed report provides followup information concerning interlook that t prevents bridge travel-over the core with one rod withdrawn <and fuel' grapple 3xtended. failed to operate. This_ report la submitted in_

accordance with'-Browns Ferry Unit 1 Technical Specifloation 6.7.2.b.(2).

~

-Very truly yours, ,

TENNESSEE VALLEY AUTHORITY g ,

/ G. T. Jones ,

dr ?ower. Plant Superintendent

^

Browns Ferry Polear Plant Enclosure oo (Enclosu* , "

U. S.; Nut esulatory Commission

' Document Lt iDesk "o

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Washington D. 20555 , , ,

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, . ..'NRC Inspector, Browns Ferry Nuclear Plant -

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