ML19332A916

RO 80-062:on 800907,during Reactor Core Isolation Cooling Flow Rate Test at 150 Psig Pressure,Rcic Turbine Tripped on High Exhaust Pressure.Caused by Manually Operated Stop Check in Exhaust to Torus Found in Locked Closed Position

ML19332A916
Person / Time
Site:	Brunswick
Issue date:	09/08/1980
From:	Tollison A CAROLINA POWER & LIGHT CO.
To:
References
BSEP-80-1471, RO-80-062, RO-80-62, NUDOCS 8009180570
Download: ML19332A916 (3)

Text

-

,. Taleccpied 9-8-80 W

E Carolina Power & Light Company g,-_ _ _ **"";

I m _.' : .-m Brunswick Steam Electric Plant P. O. Box 10429 Southport, N. C. 28461 s

September 8, 1980 FILE: B09-13516 SERIAL: BSEP/80-1471 Mr. James P. O'Reilly, Director U. S. Nuclear Regulatory Commission Region II ,

101 Marietta Street, suite 3100

• Atlanta, Georgia 30303 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 & 2 LICENSE NOS. DPR-71 AND DPR-62 DOCKET NOS. 50-325 AND 50-324 CONFIRMATION FACSIMILE OF AN IMMEDIATELY REPORTABLE EVENT (2-80-62)

Dear Mr. O'Reilly:

1 This f acsimile confirms the conversation between Mr. A. C. Tollison, Jr. , General

. Manager, and Mr. Paul Kellogg of your office, at 102C on September 8, 1980.

At 2015 hours0.0233 days <br />0.56 hours <br />0.00333 weeks <br />7.667075e-4 months <br /> on September 7,1980, while performing the Unit No. 2 RCIC Flow Rate Test at 150 psig reactor pressure, the RCIC turbine tripped on high turbine exhaust pressure. An investigation revealed the manually operated stop check in the RCIC turbine exhaust to the torus was locked in the closed position. In addition the manually operated stop check in the HPCI turbine exhaust to the torus was checked and also found in the locked closed position.

Both valves are normally required to be in the locked open position, and were immediately locked open upon discovery. Each valve had been previously checked locked open prior to reactor startup. An investigation is underway to determine the cause of the improperly positioned valves.

Also reported during this conversation, per IE Bulletin 80-17, vas the return to service of the "A" loop of RER service water for Unit No. 1 on Friday, September 5, 1980.

Unit No. 2 RCIC is also out of service due to a flow controller problem and HPCI is still out of service due to a problem with its control valve. These prob-  ;

le=s are currently being worked and it is anticipated that they will be corrected te '$t or early tomorrow.

Very truly yours, d 1 80091806?O A.C.Tollison,/r.,GeneralManager J

Brunswick Steam Electric Plant RMP/=cg 5 cc: Mr. R. A. Hartfield Mr. V. Stello, Jr.

r m v u nes cr> U. a. WUGLc4 CGGuLAUort r COMMISS60N (7 77)

. LICENSEE EVENT REPORT CONTGOL BLOCK: l 1

I I I l l 6

lh (PLEASE PRINT C3 TYiE ALL REQUIRED INFOIMATION) 7 8 9 LICENSEE CCDE le 15 LICENSE NUMBER 25 26 LICENSE TYPE J0 57 O T be CON T IoIiI 3[,c l @l Di 6l Old (D l 3l 2.l f@l l l l l l @J O!ol91O 13l@

7 6 60 61 DOCKET NUMBER 68 63 EVENT DATE 14 75 REPORTDATE 80 EVENT DESCRIPTION ANO PAOBABLE CONSEQUENCES h F5TD I I n o Ial l 526 MAUS LrQ_ l 10141 I I lolSi i l I o 161 l l l0l7}l l 10181 l l 7 8 9 40 SYSTEM CAust CAUSE COMP, VALV E COOE COCE SUSCODE COMPONENT CODE SUSCOCE SUSCOCE 1o191 7 8 I

9 I

IJ l@ U@ l l@ l 11 12 tJ i I I I I 18 I l@ L_i @

id 19 20 SYOUE NTI AL OCCURRENCE REPCRT REVISION

_ EVENT YE AR REPORT NO COCE T4PE N O.

@ s*LE 3gt RisIC RO 22 l-l [ 01612.1 l-l l I I I I L-1 L_J

_ 21 23 24 ;6 27 23 29 JJ JI J2 TA E' A T ON ON PL ANT Y T HOURS $8 3 FO h 8. SL 8PLI E MAN FAC1URER I

JJ l@l34 l@ l 25 l@ !_J@

36 l

31 I I I 40 I I el l@ l l@ l l@ l I I I l@

42 13 44 47 CAUSE DESCRIPT!ON ANO CORRECTIVE ACTIONS h Iiloll I li til i I I'I~lI [

WI l luiI i s ActLITY STATUS N80WER OTHER STA TUS h

h YE THCO OF DISCO %ERY DISCOv f RY DESCRIPTION l'le i I l@ l I i l@l i I l@l i A Ti%ITY CONTENT B0 AELEASE3 Or aELE ASE AUCUNT OF ACTIVITY LOCATION OF RELEASE l' l e l LJ @ l l@l i 3 TJ i I I tt 44 45 go

• E ASONNEL Ex7CSLaES h vBER TV'E D E SCRIPT 1CN I' ! ~ l I  ! I I I l

• E a SONN E L uhES O

%.v9Ea OESCRIPTiON@

iol

?

i i l@i i 11 2 gn ik',h ' h*;$,f;\ '#

I 1 >I I l@l

' I

' 30 KE E = at cg NRC USE ONLY ,

LdJ Lfl '

i IIiIIIii!!!!l1 6d 69 30 -

N AYE CC *AED ARER pWCNE: $,

e_

NRC FO1M so6 U, S. NUCLEAD REGULATO,'lY COMMISSION (7 7H LICENSEE EVENT REPORT CONTROL BLOCK: l t

l  ! I I I 6

Ih (PLEASE PRINT CR TYPE ALL REQUIREO INPORMATl!N)

ITTTl l I l l I I l l l l@l26 l@l57 CAT 58I@

I I l@l15 I I l I I l l l l l 7 8 9 UCENSEE CODE se LICENSE NUMBEH 25 LecENSE TYPE Jo CON T 7

o i 6

$ v% i60 l@lol fl Dlo l ol3l AlYl@l 61 DOCK ET NUV8 E R 68 69 l I I EVENT OATE I I l@l7581 ol 74 ol 91 d lT80I@

REPORTDATE EVENT DESCRIPTION ANO PROB ABLE CONSEQUENCES h f7TT1 I I toialI 4*e TJ24AJS L P@_. I 10141 l l 10161 l l I o 16 I l I 1o171 1 I l ois i ! I 7 8 9 80 Sv5 TEM CAUSE CAUSE C OvP. VALVE CODE CODE SU8C00E COMPONENT CODE SUSCCOE Sv8C00E 10191 7 8 I

9 I

to l @ L_J @ L_l O I 11 12 13 I  ! I I I l@ L_J@ L_J @

18 19 20 S EQUEN TI AL OCCt.:R R E NCE ;tCPORT REVIS30N LERo EVENTvfAR REPORT NO CODE TVPE NO.

G .,ag.j"o . ITl01 21 l_I 101612.1 1-I I I I I I l-l l I 22 2J 24 26 27 28 29 J0 31 JJ T EN A T ON ON PLA T t Tb HOURS Sei FCR 3. SLP Li MANhF C LRER l

JJ l@l34 l@ l J4 l@ l J6 l@ l 3/

I I I 40 I L_j@

43 l

l@ l l@ l l l l l@

42 43 44 47 CAUSE DESCRIPTION ANO CORRECTIVE ACTIONS h li lo l l I LLLL]I I LLL_I I I tilaiI l tit 4i l I 8 9 80 SYANS NPowER OTHER STA TUS is Y DISCOVsRY DESCRIPTION 1 I s I L_J@ l I i J@l i I l@l I a C TIVITY CO TENT AuCUNT OF ACTIVITY LOCATION OF RELEASE li lo lRELE I l ASE@n l OF RELE ASEl@l I l I i

6 ) 13 11 44 45 l

1. iRSCNNEL EXPCSVRES 80 b vssR DESCRIPTION J l i-l I I I l@lTYPE l @l I

• EaSCNNEL N;L IES

. 99ER DESCRtPTICN 1- l-l i I I l@l42 I

$ ? 11 80

.CES C8 OR C AVAGE TO 840!LITV

"*E C E SCRipTicN 1 131 I l@l l 8 1 .

80 ESCR ** 'ON NRC USE ONLY ,

titJ IAs181 9 ) .

I IiIiIIIIIIIIIi 69 69 80 %

N AVE OF *aE* A AER PHONE. j l

.