05000325/LER-1979-053-03, /03L-0:on 790804,reactor Core Isolation Cooling Steam Isolation Valve F007 Would Not Open While Performing Penetrant Tests 10.1.1 & 10.2.Caused by Oxidation of Surfaces of Breaker Pickup Coil.Surfaces Cleaned

From kanterella
(Redirected from ML19207C015)
Jump to navigation Jump to search
/03L-0:on 790804,reactor Core Isolation Cooling Steam Isolation Valve F007 Would Not Open While Performing Penetrant Tests 10.1.1 & 10.2.Caused by Oxidation of Surfaces of Breaker Pickup Coil.Surfaces Cleaned
ML19207C015
Person / Time
Site: Brunswick Duke Energy icon.png
Issue date: 08/28/1979
From: Tollison A
CAROLINA POWER & LIGHT CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19207C011 List:
References
LER-79-053-03L-01, LER-79-53-3L-1, NUDOCS 7909060317
Download: ML19207C015 (2)


LER-1979-053, /03L-0:on 790804,reactor Core Isolation Cooling Steam Isolation Valve F007 Would Not Open While Performing Penetrant Tests 10.1.1 & 10.2.Caused by Oxidation of Surfaces of Breaker Pickup Coil.Surfaces Cleaned
Event date:
Report date:
3251979053R03 - NRC Website

text

.. '

A R ULATORY COMMISSION (7 77)

LICENSEE EVENT REPORT CONTROL BLOCK:

l l

l l

l lh (pLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6

Nl cl nl rl p 1 l@l 0 0

- l 0 0 0l 0 0 - l010 @l4 1 1l1l1 @l l@

0 1

7 8 3 LICENSEE CODE 14 15 LICENSE NUYBER 25 26 LICENSt TYPE JO S; Ce.T $8 CON'T o il s$RC lLl@ 0l5 0 -l0 31215 @l01810 4l7191@ 0 9 2l8l7l9 g 8

7 8

60 61 DOCKET NUYS ER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBADLE CONSEQUENCES h o

2 While performing PT's 10.1.1 and 10.2. RCIC flow test and pump and valve ouerability I o

3 l check, the RCIC steam isolation valve F007 would not open.

This makes the RCIC systed

[ inoperable, o

4 o

s I i

0 6

l l

0 7

l l

0 8

l l

7 8 9 80 SYSTEM

CAUSE

CAUSE COMP.

VALVE COCE CODE SUSCODE COMPONENT CODE SUBCODE SU8COCE o

9 lC Fl@ W@ l X l@ lC lK lT lB K lR lh W@ l Zl@

7 3

9 10 11 12 13 18 19 20 SEQUENTI AL OCCURRENCE REPORT REVISION LE R RO EVENT YE AR REPORT NO.

CODE TYPE NO.

@ REPgRT [7 9l l_l l0l5l3l

]/l l 0l 3[

l Ll l_l l 0l 21 22 23 24 26 27 28 29 30 31 32 TAKEN A ON O PLANT TH HOURS 22 S B ITT D FO P. d 8.

SU PP LI E MANLFACT RER l X lgl34Glg jZlQ lZ[@

l0l0 0lUl [Y g [Y g lN[g lG 8l0lg 0

33 3b 36 3/

40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h IUpon investigation. it was found that the surfaces of the breaker pick-up coil had l

i o

1 i

oxidized. These surfaces were cleaned and all wirinz connections were checked riche I l Maintenance Instruction 10-2K is being revised to include these contact points for I

i

?

i 3

i cleaning and tightness checks when these 480 volt breakers are inspected. As a maiorilty I of our 480 volt breakers are the same as the F007 breaker and as this is the (CON'T) l i

4 7

8 9 fs0 ST S

% POWER OTHE R STATUS Dis OV RY DISCOVERY DESCRIPTION J @ !0 8 l 1 l@l NA l

l B l@l Periodic Test i

s AC TI VITY CO TENT RELEASED OF RELE ASE AVOUNT OF ACTIVITY LOCATION OF RELEASE l Zl@

l NA l

l NA l

1 6

7 8 9 10 11 44 45 go PERSONNEL EXPOSURES NLUBER TYPE

DESCRIPTION

l0l0l0l@lZl@lNA l

i 7

2 8

,ERsONNE L,N;u' RIES NUV8ER

DESCRIPTION

d * > "h'* Q

('e 1 ' ' ' '

0l0l0l@lNA l

i 4

OsS OF OR OLOE ?O FACIUTY 1909060 3/7 TYPE C ESCnip TION d

l Zi@l NA l

1 9

7 d 9 10 80 llL_j

@lDESCniPTION iSS e

NA l

llllllllll ll []

7 8 9 10 68 69 80 g NAVE OF PREPARER A. C. To111 son, Jr.

S PHONE:

LER CONTINUATION - Ro# 1-79-053 Facility:

BSEP Unit No. 1 Event Date:

8-4-79 first such occurance at Brunswick Steam Electric Plant, this is condidered an isolated event and no further action is required.

0I.~ >0 'd0