05000324/LER-1980-072-03, /03L-0:on 800915,during Auto Scram Test,Control Rod 38-15 Took 13-s to Insert Fully Versus Specified Requirement of 7-s.Cause Is Undetermined.Subsequent Test Was Satisfactory

/03L-0:on 800915,during Auto Scram Test,Control Rod 38-15 Took 13-s to Insert Fully Versus Specified Requirement of 7-s.Cause Is Undetermined.Subsequent Test Was Satisfactory

ML20008E260
Person / Time
Site:	Brunswick
Issue date:	10/10/1980
From:	Tollison A CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20008E254	List: 05000324/LER-1980-072, Forwards LER 80-072/03L-0 05000324/LER-1980-072-03, /03L-0:on 800915,during Auto Scram Test,Control Rod 38-15 Took 13-s to Insert Fully Versus Specified Requirement of 7-s.Cause Is Undetermined.Subsequent Test Was Satisfactory
References
LER-80-072-03L-01, LER-80-72-3L-1, NUDOCS 8010240472
Download: ML20008E260 (2)

LER-1980-072, /03L-0:on 800915,during Auto Scram Test,Control Rod 38-15 Took 13-s to Insert Fully Versus Specified Requirement of 7-s.Cause Is Undetermined.Subsequent Test Was Satisfactory

Event date:
Report date:
3241980072R03 - NRC Website

text

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

77)

LICENSEE EVENT REPORT CONTROL BLOCK: l l

l l

l l

l@

(PLEASE PRINT OR TYPE ALL REQUIRED INFCRMATIONI 1

6

@ l N l C l B l E l P l 2 l@l 010 l-l0 l0 l0 l0 l0 l-l0 l0 l@l 4 l 1 l 1 l 1l 1lhl l

l@

7 8 9 LsCENSEE COCE 14 15 LICENSE NUMSER 25 26 LICENSE TYPE JO 57 CAT 58 CON'T Ev',"c' l L l@l 0 l 5 l 0 l - l 0 l 3 I 214 }@l 01911 I 5 I 810 @l 110 l 1 l 0 l 8 l 0 l@

lolil i

8 60 41 OOCKET NJMBER 64 69 EVENT OATE 74 75 REPORT OATE 80 EVENT DESCRIPTION AND PROB A8Li CONSEQUENCES h o 2 l During the auto scram test required by IE Bulletin 80-17, control rod 38-15 took l

I o 13 I l 13 secer.l. to fully insert versus the specify.i inquirement of less than or equal l

l o 141 1 to seven seconds. The rod was declared inoperable and was electrically disarmed I

lo Is1 I as per Technical Specifications. This event did not affect the health or safety l

l ETin i of the public l

10171 l I O ie l l Technical Specifications 3.1.3.2, 6.9.1.9b l

E OCE S BC E COMPONENT COOE SUSCodE S

COE lol91 lR lB l@ Wh Wh l C l 0l N l R l 0 l D lh Wh W h 7

8 9

10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION EVENT YEAR REPORT NO.

COOE TYPE N O.

@ y"LER/ROl218l 0l

[-.-j l 0l 7l 2l l/l 1013l lL l l-l l0l u'Mg 22 23 24 26 27 28 29 30 31 32 N AC O CNP T

MET HOURS SB IT FOR 8.

SUPPLIE MANUF CTURER tzJ@L7J@

tz_1@

L1J@

l01010101 ITI@

Ivi@

lNI@

1c1018l01@

33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h 11 101 l A definite cause to this event could not be determined.

A subsecuent scran test I

u.LLJ l of the rod vielded a satisfactorv insertion time of less thnn Revon cornM e-Thn I

ml rod was then declared operable and was returned to service.

I I i t 31 l l

li l41 l l

7 8 9 80 1

ST S

% POWER OTHER STATUS 015 RY DISCOVERY OESCRIPTION Ii 15 l Wh l Ol 0l 0lhl N/A l

(,,C_jhl Special Testing l

ACTIVITY COPTENT R n EASEO CrnELEASE AMOUNT OF ACTIVITY.

LOCATION OF RELEASE l lsl W @ W @l N/A l

l N/A l

PERSONNEL EXPOS ES NUMBER TYPE DESCRtPTION l,,Ll.l.,ll0l0 l0lh W hl N/A l

PERSONNELINJU IES NUV8E R OESCRtPTION l0l0 W hl N/A l

1 H 7

8 9 11 12 go LOSS OF OR DAMAGE TO FACILITY TYPE OESCRIPTION ITTTl I.yJ@l N/A l

)

7 8 9 10 go i

ISSUE

DESCRIPTION

e [1,l o,]

hl N/A l

llllllllll lll5 0IO24U[odR,,,R,n A. C. hmson, A.

19 457-9521 PHONE:

i

s.

LER ATTACHMENT - RO NO. 2-80-72 Facility: BSEP Unit No. 2 Event Date:

9-15-80 An investigation determined two factors that may have caused the control rod to have an out-of-specification insertion time. These two factors were excessive leakage of the rod drive unit seals or foreign debris within the seal area of the rod drive unit. Since the rod was successfully inserted during the subse-quent scram test, the drive unit seals are not believed to be the cause of this event. It is, therefore, thought that foreign debris in the drive unit seal area prevented the rod from properly scramming during the initial test. This

._ debris was apparently flushed from the rod drive seals during the test and sub-sequent scram test of the rod. This control rod will be monitored for signs of abnormal characteristics during insert and withdrawal evolutions and during any scheduled reactor scram where the rod is initially in a withdrawn position.

Based upon the results of monitoring, a determination will be made on whether to rebuild the rod drive unit during the next refueling outage.

O

~

=

t

• =

a se m

O O

E o

m a

.e-

- q.-*.

- em