05000270/LER-1980-015-03, /03L-0:on 800916,valve 2LP21 Failed to Open During Performance of Engineered Safeguard Channel Test.Caused by Loose Setscrew on Motor Driven Pinion.Screw Repaired

/03L-0:on 800916,valve 2LP21 Failed to Open During Performance of Engineered Safeguard Channel Test.Caused by Loose Setscrew on Motor Driven Pinion.Screw Repaired

ML16148A363
Person / Time
Site:	Oconee
Issue date:	10/16/1980
From:	Jackie Jones DUKE POWER CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML16148A364	List: 05000270/LER-1980-015, Forwards LER 80-015/03L-0 05000270/LER-1980-015-03, /03L-0:on 800916,valve 2LP21 Failed to Open During Performance of Engineered Safeguard Channel Test.Caused by Loose Setscrew on Motor Driven Pinion.Screw Repaired
References
LER-80-015-03L, LER-80-15-3L, NUDOCS 8010210539
Download: ML16148A363 (2)

LER-1980-015, /03L-0:on 800916,valve 2LP21 Failed to Open During Performance of Engineered Safeguard Channel Test.Caused by Loose Setscrew on Motor Driven Pinion.Screw Repaired

Event date:
Report date:
2701980015R03 - NRC Website

text

REGULA Y INFORMATION DISTRIBUTIOSYSTEM (RIDS)

ACCESSION NBR:8010210539 DOC.DATE: 80/10/16 NOTARIZED: NO DOCKET #

FACIL:50-270 Oconee Nuclear Station, Unit 2, Duke Power Co.

05000270 AUTH.NAME AUTHOR AFFILIATION JONESJ.L.

Duke Power Co.

RECIP.NAME RECIPIENT AFFILIATION Region 2, Atlanta, Office of the Director SUBJECT: LER 80-015/03L-0:on 800916,valve 2LP21 failed to open during performance of engineered safeguard channel test.Caused by loose setscrew on motor driven pinion.Screw repaired.

DISTRIBUTION CODE: A002S COPIES RECEIVED:LTR.

ENCL iL SIZE:,

TITLE: Incident Reports NOTES:M Cunningham:all amends to FSAR & changes to Tech Specs.

05000270 AEODOrnstein:1cc.

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL ACTION:

REIDR..

04 3

3 INTERNAL:; A/D COMP&STRU06 1

1 A/D ENV TECH 07 1

1 A/D MATL & QUO8 1

1 A/D OP REACTOO9 1

1 A/D PLANT SYSIO 1

1 A/D RAD PROT 11 1

1 A/D SFTY ASSE12 1

1 A/D TECHNOLOG13 1

1 ACC EVAL BR 14 1

1 AEOD 2

2 ASLBP/J.HARD

1.

1 AUX SYS BR 15 1

1 CHEM ENG BR 16 1

1 CONT SYS BR 17 1

1 CORE PERF BR 18 1

1 D/DIRHUM FAC19 1

1 DIRENGINEERI20 1

1 DIRHUM FAC $21 1

1 DIRSYS INTEG22 1

1 EFF TR SYS BR23 1

1 EQUIP QUAL BR25 1

1 GEOSCIENCES 26 1

1 I&C.SYS BR 29 1

1 I&E 05 2

2 JORDANE./IE:

1 1

LIC GUID BR 30 1

1 LIC QUAL BR 31 1

1 MATL ENG BR 32 1

1 MECH ENG BR 33 1

1 MPA:

3 3

NRC PDR 02 1

1 OP EX EVAL BR34 3

3 OR ASSESS BR 35 1

1 POWER SYS-BR 36 1

1 S R39 1

1 REACT SYS BR 40 1

1 RE IE01, 1

1 RED & RISK A 41 1

1 EVA42 1

1 STRUCT ENG 8R44 1

1 SYS INTERAC B45 1

1 EXTERNAL: ACRS 46 16 16 LPDR 03 1

1 NSIC 05 1

1 TERA:DOUG MAY 1

1 2 2 1980 TOTAL NUMBER OF COPIES REQUIRED: LTTR ENCL

FRC FORM 38W U.

. NUCLEAR REGULATORY COMMISSIoN LICENSEE EVENT REPORT EXHIBIT A CONTROL BLOCK:

(PLEASE PRINT OR TYPE ALL REQUIRED INFORMAT1ONI o

1N E

E 12 k'D 0 101-100 100 01o01-100 I(5')1411,1(l 1Q0

(

7 0

9 UCENSEa CO0 t4

" 18 UCENSa NUMBER 25 2

UCENUs TYPE so 57 CAT so CONrr EIJ L 4L+/-.X (0 15 101 010121 71 OJ0IO 1 91 116J8 0i)I 10 111 618 1010 60 GI OCCKET NUMBER sS 69 EVENT DATE 74 7

REPORT DATM 8o EVENT OESCRIPTION ANO PROBABLE CONSEQUENCES 10 o 2 On September 16, 1980, valve 2LP2Yfailed to.open during performance of the ES 0 -3 [channel test.

The valve was manually opened and declared inoperable. The o problem was corrected and the.valve declared operable within 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />, well o=

[-within the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> limit of Technical Specification 3.3.2.1d(2).

Thus, this 0 incident was of no significance with regard to safe operation, and the health [and safety of the public were not affected.

7 090 SYTTEM

CAUSE

CAUS Ecamp.

VALVs CCO COod SUBCCOS COMWPOENT CODE SG0COOa SUCCOCa 0

I

@1 [V !A I L VI 10 9J© LOi 812 12 to 19 20 SOUVATIAL OCCURRENCE REPORT ReViSIon.

LgRfllO 1"T1ARRVPOqRT NO.

coca

- rypg pNo.

LL-8 f0'2 WF-24~IS 27 2L 29 L02 ACI UTURE EFFECT SI4UTDCVwN ArrAC,4#NT NPRO-d PRIME Comp.

COMPONENT TAKEN ACTION ON KIANIT PJETHOO NOR JSUBMITTED FOR M %us.

SIJPPUEA MAtdUPFCUen EJi IW 0 I

~

J 1ol00r LI e~J

_0 LII I L'j2 010 f 3

4a s31 44 41 42 43 hA47 CAUSE DESCRIPTION ANO CORRECflVE ACTIONS 1 The failure was caused by a loose setscrew on a motor-driven pinion. VibrationJ 1M Iwould be the most probable reason for the screw.coming out.

The loose screw was repaired and the valve returned to service. Operability of the valve was I Iveri f ied.

7 I9D PACIUTY (1)

METI00 O)

STATUS PotR OTHE STATUS DISCOVERY DISCOVY OCRIPTON II LE 1@

L Of 0 n2 I NAB I ~LU L..LLQ@

NA LJ Engineered Safeguard Channel Testingi 7

9 O12 13 4494 ACTIVITY CONTENT 80 IIEASE0 OF RELEAS AMOUNT OP ACTIVITY C

O D LzJ @ Ill NA NA 7

80 to it PERSONNEL EXPOSUREs NUMBER TYPE

DESCRIPTION

II 0I lololo 1z J&@

NA 7

8 9 11 12 13 PERSONNEL INJURIES NUMBER

DESCRIPTION

[TL]J Iof o

Lf NA 7

a 9 11 12 LOSS OF OR DAMAGE TO FACILITY TYPE

DESCRIPTION

N~

NA 7

8 9 10 rULICITY Co 20 0O~ptpo NA III C!USEIIriI I

10 t

69 O

S 8 0 010 53'

.~~~ ~

~

DISCOVERY~r J

L J ne PO f7OV 4A 3ESC 3I 81ON 7

B1 EnierdSfgar hne0etn