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| {{Adams
| | #REDIRECT [[05000259/LER-1981-016, Forwards LER 81-016/01T-0]] |
| | number = ML20004D566
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| | issue date = 06/05/1981
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| | title = Updated LER 81-016/01T-1:on 810501,during Test,Fire Pump Automatic Start Logic Found Inoperable.Caused by Wiring Removed from Terminal Points in Main Relay Panel 52,during Mod of Panel.Permanent Wire Replaced.Work Plan Revised
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| | author name =
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| | author affiliation = TENNESSEE VALLEY AUTHORITY
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| | addressee name =
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| | addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
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| | docket = 05000259
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| | license number =
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| | contact person =
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| | document report number = LER-81-016-01T, LER-81-16-1T, NUDOCS 8106090537
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| | package number = ML20004D560
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| | document type = LICENSEE EVENT REPORT (SEE ALSO AO RO), TEXT-SAFETY REPORT
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| | page count = 2
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| }}
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| {{LER
| |
| | Title = Updated LER 81-016/01T-1:on 810501,during Test,Fire Pump Automatic Start Logic Found Inoperable.Caused by Wiring Removed from Terminal Points in Main Relay Panel 52,during Mod of Panel.Permanent Wire Replaced.Work Plan Revised
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| | Plant =
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| | Reporting criterion =
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| | Power level =
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| | Mode =
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| | Docket = 05000259
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| | LER year = 1981
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| | LER number = 16
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| | LER revision = 0
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| | Event date =
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| | Report date =
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| | ENS =
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| | abstract =
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| }}
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| =text=
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| {{#Wiki_filter:~
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| , Update R2 port - Prsvious Report Data 5/12/81 U. S. NUCLE AR REGULATORY COMMISSION
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| LICENSEE EVENT REPORT o
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| l l lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) lo ltl l Al Ll B l Rl Fl 1 l@l 0 l 0 l-l 0 l 0 l 0 l 0 l 0 l-l 0 l 0 l@l 4 l 1 l 1 l 1 l 1 l@l l
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| LICENSEE CODE le 1$
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| LICENSE NUMBER 25 26 LICENSE TYPE JO 57 CAT 58 CON'T CL 1.J
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| 3 60 61 00CKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRl* TION AND PROBABLE CONSEQUENCES h l o l 2 l l During post-modification tests on a new sprinkler system. the fire oumo automatic I
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| go l3; l start logic was found inoperable.
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| T.S. 3.11..A.l.b requires operable logic. One fire I
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| .[ o l 4 ; Ipump was running at the time the inoperability was discovered. The pump was kept l
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| I io ls; l running while the automatic-start circuit was repaired. Manual start capability
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| ]
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| Io is ] lwas operable. Units 1, 2, and 3 were affected. There was no danster to the health l
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| lolij jor safety of the public. There are no redundant systems. There were no previous I
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| iojg; lsimilar events.
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| I 80 i
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| a9 JYSTEM
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| ==CAUSE==
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| CAUSE COMP.
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| VALV E CODE CODE SUSCODE COMPONENT CODE SUSCODE SU8 CODE m
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| p el 9
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| 10 11 12 13 18 19 20 SEQUEN TI AL OCCURRENCE REPORT REVISION LERiRO EVENT YE4R REPORT No.
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| CODE TYPE N O.
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| @ aEPORT l 8l 1l l_l l 0l 1l 6l l/l l0l1l l Tl l-l [1]
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| 21 22 23 24 26 27 28 29 30 31 32 TAK N AC O O PLANT MET HOURS 22 S8 i FOR 8.
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| SUPPL E MANUFAC RER lCl@l_Zj@
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| JJ J4 JS 36 37 40 43 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS lijoll Wiring was removed from terminal points in main relay panel 52, interrupting power to I g,i,j l fire pump auto-start circuit, probably while performing a modification in the canel.
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| I
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| ,,,,,g ermanent wire was replaced immediately. Workplan was revised to caution electriciansI P
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| g lco consult with cognizant engineer prior to removing existing wiring.
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| [
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| li t il i l
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| i 8 9 80 T1 s TPOWER OTHE A STATUS 015 y RY DISCOVERY DESCRIPTION W [Z_j @ l Ol Ol 0lhl NA l
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| l,C.,_l@l l
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| Soecin1 test A T:VirY CO TENT AELE ASED OF RELE ASE AMOUNT OF ACTIVITY LOCATION OF RELEASE W lZl@ W @l NA l
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| l NA l
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| t g 9 10 13 44 45 80 PERSONNEL F APOSURES t
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| NOPeR E R TYPE DESCRIPTION ^
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| l li l il 10 l 010 l@l Zi@l NA l
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| PE nSO~~E'L IN;U'JiES oESCRiPnON@
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| NuMnER l
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| i 4 1 TO 80 NhC USE ONLY e tsuPfifjN e;;ui81 LN_
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| 4 1 to 68 69 80 ;
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| o NAME OF PREP ARER PHONE:
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| 8106090 W
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| o.
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| ~ Tcnnessee Valley Authority Form BF-17 Browns Ferry Nuclear Plant BF 15.2 3/24/81 LER SUPPLEMENTAL INFORMATION BFRO 259 / 81016 R1 Technical Specification Involved 3.11.A.l.b Reported Under Technical Specification 6.7.2.a(2)
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| Date of Occurrence 5/8/81 Time of Occurrence 1550 Unit 1, 2, and 3 Identification and Description of Occurrence:
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| Power (120V AC preferred) lifted to fire pump auto-initiation. The exact duration the circuit had been inoperable could not be determined. However, it is probable that the wiring was removed during the modification activity, making the duration 2 weeks ur less.
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| Conditions Prior to Occurrence:
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| Unit 1 refueling outage.
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| Unit 2 at 99%.
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| Unit 3 at 100%.
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| Action specified in the Technical Specification Surveillance Requirements met due to inoperable equipment. Describe.
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| Reterminated power supply.
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| Apparent Cause of Occurrence:
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| Wiring was removed from terminal points in main relay panel 52 resulting in the interruption of power to the fire pump auto-start circuit. Although it could not definitely be determined how the wiring was removed, it is suspected that the wires were removed during performance of a molification in tne panel.
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| Analysis of Occurrence:
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| There was no danger to the health or safety of the public, no release of activity, no damage to the plant or equipment, and n) resulting significant chain of events.
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| I l
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| ==Corrective Action==
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| l
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| ~
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| workplan requiring the electricians to consu'; the cognizanc engineer prior Replaced permanent wiring immediately. Precautions have been added to the l
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| to removing any existing wiring.
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| I l
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| Failure Data:
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| Notic
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| * Retention. Period - Lifetime; Responsibility - Document Control Supervisor l
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| * Revision:
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| {{LER-Nav}}
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