05000325/LER-1982-122, Supplemental LER 82-122/03L-1:on 821030 & 1104,reactor Recirculation Pump 1A Tripped.On 821101 & 04,reactor Recirculation Pump 1B Tripped.Caused by Spurious Action of ATWS Instrument B21-PS-N045C

Supplemental LER 82-122/03L-1:on 821030 & 1104,reactor Recirculation Pump 1A Tripped.On 821101 & 04,reactor Recirculation Pump 1B Tripped.Caused by Spurious Action of ATWS Instrument B21-PS-N045C

ML20083L271
Person / Time
Site:	Brunswick
Issue date:	04/09/1984
From:	Dietz C, Pastva M CAROLINA POWER & LIGHT CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
BSEP184-0879, BSEP184-879, LER-82-122-03L, LER-82-122-3L, NUDOCS 8404170200
Download: ML20083L271 (2)

LER-2082-122, Supplemental LER 82-122/03L-1:on 821030 & 1104,reactor Recirculation Pump 1A Tripped.On 821101 & 04,reactor Recirculation Pump 1B Tripped.Caused by Spurious Action of ATWS Instrument B21-PS-N045C

Event date:
Report date:
3252082122R00 - NRC Website

text

NRC FORP U. S. NUCLE AR REGULATORY COMMISSION (7 77) s LICENSEE EVENT REPORT (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

CONTROL BLOCK: l 1

l l l l l lh 6

l0 l1l lN l Cl Bl El P l 14 1 lhl 15 0l 0l - l 0 l0 LICENSE l0 l0l NUMBER 0l- l0 l0 25lhl4 26 l1LICENSE l1 l 1 l TYPE 1JO lhl l 57 CAT 58 l@

7 8 3 LICENSEE CODE CCN'T l0l1l 7 8 3[C" lt60 hl 0 l 5 l 0l-DOCKET gC 61 l0 l3NUMBER l2 l 5 hl681 l690 l 3EVENT l 0l8DATEl2 l@[0 l 4 l REPORT 74 75 0 l 9DATE l 8 l 483l@

EVENT OtSCRIPTION AND PROB ABLE CONSEQUENCES h l 012 ] l During steady state plant operation, the following reactor recirculation pump trips occurred concurrent with l 10 l 3 l l the receipt of the ATWS high reactor pressure / low level trip annunciation: On October 30, 1982, IA^ pump l 10l4l l tripped; on November 1,1982, IB pump trippedi on November 4 1982, IA pump tripped twice; and within nine l l0l5l l minutes of the s'econd November 4,1982, event,18 pump tripped. These events did not affect the health l l 0 l6 l l and safety of the public. l l0 l7l l l g a gg g l Technical Specificatiens 3.3 6.1, 3.4.1.1, 3.4.1.3, 6.9.1.9b l 80 7 8 9 SYSTE Y CAUSE CAUSE COY P. VALVE CODE CODE SUSCCOE COMPONENT CODE SUSCOOE SUBCOCE l0l9l lC lB j @ { h lXl h l1 lN l 5 l T l R lU lh l S l@ l Z l h 13 18 13 20 7 8 9 10 11 12 SEQUENTI AL OCCURRENCE REPORT REVISION EVENT YE AR REPORT NO. CCCE TYPE NO.

LER O aygRO s lal2l [-j li12121 (f_j 10l3l It l l-l LLJ 22 2J 24 26 27 28 29 JO 31 32

_ 21 ACTION 8UTURE EFFECT SHUT 00WN ATT AC HM E NT NPRO4 PRIME CCMP. COMPCNENT TAKEN ACTION ON PLANT METHOD HOURS 4 SUSMITTED FORMbuB. SUPPLIER MANUFACTURER lX l 3J l34 Z lh Z l34 lh l36Z lh l/ 3 0 l0l0l0l 40

[ h lYlh lN lh lS l3 l8 l2lh 46 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h l1 l o l l The pump trips resulted from spurious actuation of ATWS instrument 821-PS-N045C caused by moisture l The moisture was removed from the box; the wirino was waterotonfed. I li li j l condensate in the N045C terminal box.

7 y,;yj jand N045C, Model No. 9N-AA45, was returned to service. Unit 1 ATWS reactor pressure instrument terminal l

[1 l3l l boxes will be inspected monthly for moisture until appropriate sealing is performed as per IEB 79-018. l l

U_L4_j i 80 1 8 9 STA S  % PCWE R OTHE R STATUS IS O RY DISCOVERY DESCRIPTION y lClh l0 l4 l0lhl NA l h Operntionni Fvent l 8 3 10 12 13 44 45 46 80 7

ACTIVITY CON TENT fELEASED OF RELEASE AVOUNT OF ACTIVITY LOCATION OF RELEASE l1l6l 7 8 9 h 10 hl 11 NA 44 l l NA 43 80 l

PERSONNEL EXPOSURES NUMBER NA l l t l 7 l l 0 l 0 l 0 h[TYPEZ 13 lhlDESCRIPTICN 80 7 8 9 11 12 PERSONNEL INJURIES NUve!R DESCRIPTION li j a l l 0 l 0 l 0 lh] NA 80 l

7 8 9 11 12 LOSS OF OR OAMAGE TO FACILITY TYPE D E SCR t P TION l 1 l 'l (J_jhl so 7 a s ,0 8404170200 840409 PueuCiTY esuEa O PDR ADOCK 05000325 g PDR NRC usE ONLY 12 l8 a9 l I Nl I@DESCRieTiON US NA l l l l l l l l l l l l I l :*:

7 10 68 63 80 $

• *

• I NAYE CF PAED AaER PHONE:

r NN{kb Db GA m:r.m - - - m=rmaa g 0,a r i Power & Light Company 34 AP --- -m Brunswick Steam Electric Plant P. O. Box 10429 Southport, NC 28461-0429 April 9, 1984 FILE: B09-13510C SERIAL: BSEP/84-0879 Mr. James P. O'Reilly, Administrator U. S. Nuclear Regulatory Commission Region II, Suite 3100 101 Marietta Street N.W.

Atlanta, GA 30303 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 DOCKET NO. 50-325 LICENSE NO. DPR-71 SUPPLEMENT TO LICENSEE EVENT REPORT 1-82-122 Gentlemen:

In accordance with Section 6.9.1.9b of the Technical Specifications for Brunswick Steam Electric Plant, Unit 1, the enclosed supplemental Licensee Event Report is submitted. The original report fulfilled the requirement for a written report within thirty (30) days of a reportable occurrence and both are in accordance with the format set forth in NUREG-0161, July 1977.

Very truly yours, C. R. Dietz, General Manager Brunswick Steam Electric Plant RMP/dgr/LETDR1 Enclosure cc: Mr. R. C. DeYoung NRC Document Control Desk OFFICIAL COPY 3EB C III I