05000270/LER-1980-006-03, /03L-0:on 800625,at 40% Full Power,Valve 2LP21 Failed to Open Electrically on Command.Caused by Loose Setscrew on Motor Driven Pinion.Screw Repaired
| ML16148A338 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/26/1980 |
| From: | Jackie Jones DUKE POWER CO. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML16148A339 | List: |
| References | |
| LER-80-006-03L-02, LER-80-6-3L-2, NUDOCS 8007290830 | |
| Download: ML16148A338 (2) | |
| Event date: | |
|---|---|
| Report date: | |
| 2701980006R03 - NRC Website | |
text
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8007290830 DOCDATE: 80/06/26 NOTARIZED: NO DOCKET FACIL:50*270 Oconee Nuclear Station, Unit 2, Duke Power Co.
05000270 AUTH.NAME AUTHOR AFFILIATION JONES,J.L.
Duke Power Co.
RECIPNAME RECIPIENT AFFILIATION Region 2, Atlanta.Office of the Director SUBJECT: LER 80-006/03L-0:on 800625atL40% full powerrvalve 2LP21 failed to open electrically on command.Caused by loose setscrew on motor driven pinionScrew repaired.
DISTRIBUTION CODE: A002S COPIES RECEIVED:LTR ENCL SIZE:
TITLE: Incident Reports NOTES:M Cunningham:all amends to FSAR & changes to Tech Specs.
05000270 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL ACTION:
- REIDR, 05 1
1 FAIRTILEM. 06 2
2 INTERNAL: A/D COMP&STRUCT
- 1.
1 A/D ENV-TECH 1
1 A/D MATL & QUAL 1
1 A/D OP REACTORS 1
1 A/D PLANT SYS 1
1 A/D RAD PROT 1
1 A/D SFTY ASSESS 1
1 A/D TECHNOLOGY 1
1 ACC EVAL BR 1
1 AEOD 10 10 AUX SYS BR 1
1 CHEM ENG.BR 1
1 CONT SYS BR 1
1 CORE PERF BR 1
1 D/DIRHUM FAC S 1
1 DIRENGINEERING 1
1 DIRHUM FAC SFY I
1 DIRSYS INTEG 1
1 EFF TR SYS BR 1
1 EMERG PREP 1
1 EQUIP QUAL BR 1
1 GEOSCIENCES 1
1 HUM FACT ENG BR 1
1 HYD/GEO BR 1
1 I&C SYS BR 1
1 I&E 09 2
2 JORDANE,/IE 1
1 LIC GUID BR 1
1 LIC QUAL BR 1
1 MATL ENG BR 1
1 MECH-ENG BR 1
1 MPA 11 3
3 NRC PDR 02 1
1 OP EX EVAL.BR 3
3 OR ASSESS BR 1
1 POWER SYS BR 1
1 PROC/TST REV BR 1
1 QA BR 1
1 RAD ASSESS BR 1
1 REACT SYS B' 1
1 01 1
1 REL & RISK A BR 1
SFTY PROGEVAL 1
1 SIT ANAL BR 1
1 STRUCT ENG BR 1
I SYS INTERAC:BR 1
1 EXTERNAL:-ACRS 16 16 LPDR 03 1
1 NSIC 04 1
1 TERA:DOUG MAY 1
1 JUL 3 1980 TOTAL NUMBER OF COPIES REQUIRED: LTTR 82 ENCL 82
MNC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION (7-771 LICENSEE EVENT REPORT EXHIBIT A CONTROL BLOCK:
(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
[i IlSI CIN IEI El ZI Of0 -10 10.1 010 101-101 00(411 III 1'10Li 7
8 9
LICENSEE CODE 14 16 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CONT 1u131 LL LO 15 1010 Of 21710 (1612 15 1810 eI0 161216 1810 760 1
DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES O-27 With the unit at 40% FP, the valve 2LP21 failed to open electrically upon r-o 3 command. The valve was opened manually and declared inoperable. The problem was corrected and the valve declared operable within 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, well within o the 24-hour limit of Technical Specification 3.3.2.b(2).
This incident was rO 6
Inot significant with respect to safe operation, and the health and safety of o the public were not affected.
SYSTEM
CAUSE
CAUSE
- Camp, VALVE CCDE CODE SUBCOOE COMPONENT CODE SUBCOOE SUCODE 109 SIFI L
1g o L@
[ I A L
L V O P 7
8 9
10 11 12 13 Is 19 20 SEU E YENTIAL OCCURRENCE REPORT REVISION.
LE/R f-VTYA REPORT NO.
cooDE TYPE NO.
NUMBER L 10 j
1I1J tJ LkL2J II LiJ 10 s o 22 23 24 2s 27 0 u0 21 2
ACTION FUTURE EFFECT SHUTDOWN S2.ATgMN
- - APCOOET TAKN C71N N PkN MEHO 14UF SUaMITTED F OR SUBa.
S1UPPLIER0 MANUFACTURER E X(3 1 Zlo I JD L 10" 010l 1i L 1(2 L I/--\\IOI 33 2.4 as 28 27 0
41 42 3
CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 4
[
IThe setscrew on a motor-driven pinion was loose.
This could have resulted L from previous repair work done or from a combination of vibration and age.
1 2The loose screw was repaired and the valve returned to service. Operability
___of the valve was verified.
The LPI valve motors on the other units will be SI checked for similar deficiencies as soon as possible.
7 a89 FACILITY g
TATUS
%POWER OTHER STATUS DISCHOVVYI DISCOVERY DESCRIPTION SON s ~J 1 4j 01!l NA f
[B 10[Preventive Maintenance Testing 7
89 10 12 13
'4 48 41 ACTIVITY CONTENT LOC RELEASED OP RELEASE AMOUNT OF ACTIVITYL F1 6 1
IZIII NA 2
I NA 7
88 10 1 1 44 46 S
PERSONNEL EXPOSURES s
r__
NUMBER TYPE
DESCRIPTION
.)
EiI71 -o 10 01z 1(9 NA 7
8 9 Ii 12 1238 PERSONNEL INJURIES s
NUMBER DESCRIPTIO 11 0 0-1)L0 NA LOSS OF OR DAMAGE TO FACILI TY(
so I.IT 1
TV PE..
ESC RPtION U@L~J NA 7
a89 10 PUSUCQ~trrio 47 s
itSUE DESCITO MAC USE ONLY 1-2701 U L
NA 7
89 E9 10 8
4 L
0 PHNE
(
NB Pen ea nn RELESEDOF RLEAEPAMOUNTO L.JoeTIVITY(04~37-89 PERSON OL EXOOUEE NUBE YP DsRITOI~