05000324/LER-1981-068-03, /03L-0:on 810715,reactor Coolant Conductivity Found Greater than Allowable Limits.Caused by Flange Leak in RWCU Sys Effluent Strainer Blowdown Line Which Necessitated Isolating Sys.Leak Repaired.Coolant Conductivity Reduced

From kanterella
(Redirected from ML20010A947)
Jump to navigation Jump to search
/03L-0:on 810715,reactor Coolant Conductivity Found Greater than Allowable Limits.Caused by Flange Leak in RWCU Sys Effluent Strainer Blowdown Line Which Necessitated Isolating Sys.Leak Repaired.Coolant Conductivity Reduced
ML20010A947
Person / Time
Site: Brunswick Duke Energy icon.png
Issue date: 07/29/1981
From: Pastva M
CAROLINA POWER & LIGHT CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20010A944 List:
References
LER-81-068-03L, LER-81-68-3L, NUDOCS 8108130155
Download: ML20010A947 (1)


LER-1981-068, /03L-0:on 810715,reactor Coolant Conductivity Found Greater than Allowable Limits.Caused by Flange Leak in RWCU Sys Effluent Strainer Blowdown Line Which Necessitated Isolating Sys.Leak Repaired.Coolant Conductivity Reduced
Event date:
Report date:
3241981068R03 - NRC Website

text

366 U. S. NUCLE AR REGULATORY COMMISSION LICENSEE EVENT REPORT CONTROL BLOCK: l l

l l

l l

l (PLEASE PRINT OR TYPE alt REQUIRED INFORMATION) 1 O

lN lC l B lE lP l 2 l@l 0l 0l -l 0l 0l 0l 0l 0l -l 0l 0l@l 4 l 1l 1l 1l 1l@l l

l@

8 9 LICENSEE CODE 14 15 LICENSE NUYBER 25 26 LICENSE TYPE Jo

$ 1 CA T 58 ON' r EnN l L hl 0l 5l0[-l0l3l2l4@l0 [7 l1 l5 l8 l1 @l 0l 7l 2l 9l 8l 1l@

/

8 60 61 DOCKET NUMBER 68 69 EVENT DATE F4 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h g lDuring normal operation while performing routine reactor coolant analysis, it was l

2

discovered that reactor coolant conductivity was greater than 2.0 pmho/cm. Reactor l

2 gy4y [ coolant conductivity remained > 2.0 pnho/cm for 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> with a maximum recorded l

2 gvalue of 3.12 pmho/cm. This event did not affect the health and safety of the public.[

g,,

10161I l

10171 l 1

l0isl l Technical Specifications 3.4.4, 6.9.1.9b 80 l

7 8 9 SYSTEM

CAUSE

CAUSE COYP VALVE CODE CODE SUBCODE COMPONENT CODE SUBCO E SUBCODE l C l Cdh ]@ l Cl@ l P l I l P l E l X l X l@ {l@ y @

o 9

/

8 9

10 11 12 13 18 1 (J 20 SEQUENTI AL OCCURRENCE REPOh1 REVISION LER RO EVENT YEAR REPORT NO.

CODE TYPE NO.

@ REP l8l1l l 0l 6l 8l y

l0l3l lL l 8

l0l RT

_ 21

//

23 24 16 21 3

73 30 31 32 TAK N AC ON ON PL ANT 1 T HOURS S8 IT FOR B.

SUPPLI E R MANUFACTURER lB l@ W @

W@

l Zl@

l0l0l0l0l l_NJ @

lYl@

lYl@

lGl0l8l0l@

33 J4 35 Jb 3/

40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h Iil0l(This event resulted due to a flange leak in the RWCU System effluent strainer blowdown l lilil lline which necessitated isolating the system.

The leak was repaired. the RWCU System I i 2 lwas returned to service and the reactor coolant conductivity was reduced to < 2 umho/ l 2

h l 3 l l cm. A program to improve the reliability of RWCU System components is currently in l

i 4 lprogress which will allow better vessel chemistry contrc1.

l 7

8 9 80 STA S

% POWER OTHER STATUS ISCO ERY DISCOVERY DESCRIPTION li 15 l W@ l 0l 8l 8l@l NA l

l A l@l Routine Reactor Coolant Analysis l

ACTIVITY CONTENT HELEASED OF RELE ASE AVOUNT OF ACTIVITY LOCATION OF RELEASE 11 16 l W @ y@l NA l

l NA l

1 8 9 to 11 44 45 80 PFHSONNEL F XPOSURES NUMBE R TYPE DE SCHt PTION

.li l 71 l 0 l 0 l 0 l@[Z_j@l NA l

PERSONNE L INJU IES oESCRiP riON @

NuvatR L'hJ I o l o l o l@l NA l

P 8 9 11 12 80 L OSS OF OR DAVAGE TO FACILITY TYPE C E SC RIP TION 8 IM W@l NA l

t 8 9 10 80 t' SUE E SC RIP T ION [110]

hl NA l

lllllllllllll5 68 "

8 ';

8108130155 810729 AnER PHONE: 919-457-9521 2

- PDR ADOCK 05000324 M. J. Pastva. Jr.

,S PDR o