ML19351G421

LER 81-006/03L-0:on 810117,main Steam Line D Radiation Monitor Failed & During Repairs Line a Monitor Cable Was Disconnected.Caused by Technician Error.Techniques Reviewed W/Technicians

ML19351G421
Person / Time
Site:	Peach Bottom
Issue date:	02/13/1981
From:	Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
LER-81-006-03L, LER-81-6-3L, NUDOCS 8102230669
Download: ML19351G421 (1)

Text

{{#Wiki_filter:- -- - ~ ~ " - ~ U.S. NuCL f AH HEGuLATGHY COMMISSION I LICENSEE EVENT REPORT l j CON 1HuL ULOCK: l i l l l l l]e (PLEAsE PRINT OR TYF 4 ALL HEQulHED INFORMATION) l0 l t8 l9 lP l LICENSEE l A l P CODE l 8 l S l 2 l@l 0 l0 l- LICENSE 14 15 l0 l0 NUMBERl0 l0 l0 l- l0 l020 l@l4l1 26 l1 l1 l1 l@lbl LATl bdl@ LICENSE TYPE Ju CON'T loIiI 3",M Ql0 l 5 10 l- 10 l2 I7 i 7 l@l 0 l 1 l 1 l 7 l 8 l 1 l@l 012 l 1 l 3 l 8 l 1 l@ 41 60 61 DOCKET NUVBER 68 b3 EVENT DATE 74 7b HEPORT DATE 80 EVENT DEsCniPTION AND PROBABLE CONSEOuENCES h lo lzl 1 With the plant at power the 'D' main steam line (MSL) rad monitor failed l-l- 1T1 I in the tripped condition, and was maintained tripped per Tech. Spec. I J 10187 I Tabl e 3.1.1. During repairs the ' A' monitor cable was erroneously dis- 1 i in t sj i connected. A plant shutdown was initiated per Tech. Spec. Tabic 3.1.1. l lo le 1 i until the monitor was returned to service in approximately 2 hours. Be- I l o l 71 I cause the 'D' monitor remained tripped durina the event, the required l I O ,s i i protective action would have been initiated on MSL hiah rad levels. I

       ?         8 9                                                                                                                                                                               80 SYSTEM                  CAUSE          CAUSE CODE                                                                                                     COMP.           VALVE CODE         SUBCODE                      COYPONENT CODE                        SUSCODE          SUBCODE

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10 11 12 13 18 19 20 SEQUE N TI AL OCCURRENCE REPORT REVISION LE EVENT YEAR REPORT NO. CODE TYPE NO. O a'R?S RO L8111 1-1 I o lo 161 l-l l28 0l 3l y t_j l 0l _2a 2/ 2J 74 2b // ?J Ju 31 32 AK A T ON ON PL A T TH HOURS S B IT D FO b B. SUPPLIE MANUFACTURER lHl@lXl@ JJ J4 lBl@ J's l,_Z,j@ l 0 l0 l0 l2 l 3/ lN 41 l@ [Y l@ lN l@ lG l0 l8 l0 l@ 4G 42 43 44 4) CAUSE CESCRIPTioN AND CORRECTIVE ACTIONS [I.) OJ L _Ilm cause was technician error. Reoair work was beina done hurried 1v due l L.LL Jl to extremelv hioh temocratures in ih? area a it was assumed the 'D' I

     ,,,,,I                monitor was next to the 'D' MS line. Proper instrument identification                                                                                                      i j ilaj l               techniques were reviewed with the technicians. The rad monitor cables                                                                                                     l l i 14 I i             will be more clearly marked during the next appropriate outage.                                                                                                           l_

I B 9 80 STA S  % POWE R OTHER STATUS Di O RY DISCOVERY DESCRIPTION !I i l'> l l El@ l 0 l 3 l 0 l@l N/A l l Al@l ' Operator Observation l A TiVITY CONTENT RELE ASE D OF RELE ASE AMOUNT OF ACTIVITY LOCATION OF RELEASE l1 l6ul 9[_Zj @ [,Z_j@l

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NAME EPARER

• Y PHONE:
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                                                                                                ;

Mr. Boyce H. Grier, Director No. 2-81-06/3L , Office of Inspection & Enforcement, Region 1 i U.S. Nuclear Regulatory Conrnission I 631 Park Avenue King of Prussia, PA 19M6

Dear Mr. Grier:

This L.E.R. concerns loss of a main steam line radiation monitor j while a half logic trip was inserted due to another monitor being inoperable. (

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I Governing Tech. Spec. is Table 3.1.1. . L}}