ML19323B483

LER-80-035/03L-0:on 800410,while Attempting to Switch from Decay Heat Removal Train 1 to Train 2,cooler 2 Outlet Valve Would Not Open.Caused by Malfunctioning of Valve Operator Radial Arm.Radial Arm Was Readjusted

ML19323B483
Person / Time
Site:	Davis Besse
Issue date:	05/07/1980
From:	Makatura L TOLEDO EDISON CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19323B481	List: ML19323B480 ML19323B483
References
LER-80-035-03L, LER-80-35-3L, NUDOCS 8005120429
Download: ML19323B483 (2)

Text

fJ;tC F oRM XG S'"

LICENSEE EVENT REPORT 8005120%

l l l l (PLE ASE PRINT oR TYPE ALL REQUIREO INFORMATION)

CONTROL DLOCK: l l lolil l0 lH jD lB lS l1 l@l0 ]O l010LICEN5E l010'l0 l0 l0 l0 l0 j@l l ]@

26 4l uCLNSE Il 1l 1l 1l@l TYPE JO b1 C A T to 23 14 15 NUVsE*4 3 8 9 L.OENME CODE CC'4*T lojil 3{C"y R

g l L l@l 0 l 5 l 0 l- l0 l 3 l 4 l6 Q0 l4 l1 l0 l8 l0l@l0l5l0l7[8 l0 l@

C3 bJ EVENT OATE 74 75 REPORT DATE 63 7 8 60 61 COCKET NUYdEH EVENT DESCRIPTION AND PROBABLE CONSEGJENCES h1129 hours while attempt l 19 l 2 l l(NP-33-80-43) on 4/10/80 at let Valve DH14A would not open l j o j 3 l lcoval (DUR) Train #1 to DHR Train #2, DHR Cooler #2 Out j

Train #1 was returned to service and Train #2 was declared inoperable.

Jo14llbeyond 20%.

the time.

Therefore, the station did not enter the actior]

j o l s ; lThe station was in Mode 5 at lo lc l l statement of Technical Specification 3.5.2 which requires both DHR trains to be o There was no danger to the health and safety of the public l o 7 ling in Modes 1, 2, and 3.

l DHR Train #1 was operating properly. 'O 1 o la i lor station personnel.

7 8 9 SLBC dE S E SLBCG E COYPONENT CODE E CoOE l0l91 8

lS lF l@ l El@ lB l@ l V l A l L l V l0 l P l@ {@ ] @

9 10 11 12 13 16 OCCURRENCE 19 REPORT.

20 REV8510N 7

SEQUENTI AL TYPE NO.

CODE h gU' LER PO R

,_ EVENT YE AR l l l l_l l REPORT NO.

l3l5l y l0 l3 l g 30 l_l 31 l0 l 32 R 26 21 23 29 22 23 24

_ 28 U A*. FACTLPED B. 5 plt HOURS 22 S E ITT FOR O PLA T tET lAl@ lFl1l3l6 g lB AKEN A T O' l@l34A l@ l35Z I@ lZ 36 l@ l0l0l0l 3/ 40 l @@

di l42Y l@ 43 44 47 33 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h 1: lo l lThe cause of the occurrence can be traced to the radial arm of the valve operat The arm works in a very narrow area and it moved slightly sideways where it made I l,;,jl age.

in its meunting bracket. This restricted its movement to only 20%. l

, 7 l contact with a bolt The valve was declared operable at l g,,.,j lUnder W O 328-80, the radius arm was readjusted.

Toledo Edison is investigating need for further corrections. l

[,54,  ;0750 hours0.00868 days <br />0.208 hours <br />0.00124 weeks <br />2.85375e-4 months <br /> on 4/11/S0. 80 7 8 9 DISCOVERY DESCRIPTIC?J oTHER STATUS IS OV Y

% POWER l ST S l l A lgl operator observation so l1 l5 I b@ l 0l 0 l 0 l@l NA i2 o a 45 4e A!TiviTY CoTnni AMOUNT oF ACTIVITY LOCATION OF RELEASE AELEASED OF RELEASE l i e N^ l I NA **

LZ J @ LZJ@l ' "

PEaSONNEt ExPOSSES NuoeER TvPE OESCRiPTioN@ l NA li l 71 1010101@LZj@l "

' ' ' ,ERSONNEt 2 "

- iNJu' RIES NUYBE R DESCRIPTION @ -

l ,

l FTil 101010 l@l NA 11 12 7 8 9 LOSS OF OR DAVAGE To FACILITY TYPE C E SC RIP TIO N l ,

El Z8 9l@l NA 7 10 NRC USE ONLY 80 PUR L ICI TY -15 ISSUED DESCRIPTION l lIlIIIIllIl!! nai bb! NA to ca 63 .

DVR 80-062 $o LS*0 'H kOt"E* PHONE:

NAME OF PREPARER ,

• R

TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE

- SUPPLEMENTAL INFORMATION FOR LER NP-33-80-43

'l

! DATE OF EVENT: April 10, 1980 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE:

Decay Heat Removal Cooler #2 outlet flow control valve DH14A would not open beyond 20%

The unit was in Mode 5, with Power (MRT) = 0, and Conditions Prior to Occurrence:

Load (Gross MWE) = 0.

i Description of Occurrence: On April 10, 1980 at 1129 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.295845e-4 months <br /> while attempting to switch to #2 Decay Heat Removal Train for maintenance on #1, DH14A would not open beyond 20%. Technical Specification 3.5.2.c requires two independent emergency Being core cooling systems (ECCS) subsystem to be operabic in Modes 1, 2, and 3.

This event is being reported in Mode 5, the unit did not enter the action statement.

l to document a component failure.

l Designation of Apparent Cause of Occurrence: The improper operation of valve DH14A i

l can be attributed to a nochanical component failure. The proximity of the radius ara

' to the bracket mounting bolts allows only marginal clearance. Any movementof of the the radius arm towards the mounting bracket causes binding and limits movement radius arm.

3 I . Analysis of Occurrence: There was no danger to the health and safety of the public or to station personnel. The #1 Decay Heat Removal train was operable during this time.

Corrective Action: Under Maintenance Work Order IC-328-80, the radius arm on the d

valve shaf t was moved away from the mounting bracket, thus providing clearance and allowing the valve to stroke fully. After meeting stroke time acceptance criteria 4

required by Surveillance Test ST 5051.01, the Toledo valve was declared Edison operable andfurther is investigating returned I to service on April 11, 1980 at 0750 hours0.00868 days <br />0.208 hours <br />0.00124 weeks <br />2.85375e-4 months <br />.

corrective action that may be required on this or other similar valves.

Failure Data:

There have been no previously reported failures of this type valve l

operator.

6 1 LER #80-035 i

i i

k