View source for 05000260/LER-1982-010, Corrected LER 82-010/03L-0 on 811021,during Full Power,Avg Power Range Monitor Output Signal Calibr Was Not Performed within Required Frequency During 811014-28.Caused by Personnel Error.Personnel Instructed to Be More Careful

{{Adams
| number = ML20063C329
| issue date = 03/04/1982
| title = Corrected LER 82-010/03L-0 on 811021,during Full Power,Avg Power Range Monitor Output Signal Calibr Was Not Performed within Required Frequency During 811014-28.Caused by Personnel Error.Personnel Instructed to Be More Careful
| author name = Little G
| author affiliation = TENNESSEE VALLEY AUTHORITY
| addressee name = 
| addressee affiliation = NRC OFFICE OF INSPECTION &amp; ENFORCEMENT (IE REGION II)
| docket = 05000260
| license number = 
| contact person = 
| document report number = LER-82-010-03L-03, LER-82-10-3L-3, NUDOCS 8205040687
| package number = ML20063C288
| document type = LICENSEE EVENT REPORT (SEE ALSO AO RO), TEXT-SAFETY REPORT
| page count = 2
}}
{{LER
| Title = Corrected LER 82-010/03L-0 on 811021,during Full Power,Avg Power Range Monitor Output Signal Calibr Was Not Performed within Required Frequency During 811014-28.Caused by Personnel Error.Personnel Instructed to Be More Careful
| Plant = 
| Reporting criterion = 
| Power level = 
| Mode = 
| Docket = 05000260
| LER year = 2082
| LER number = 10
| LER revision = 
| Event date = 
| Report date = 
| ENS = 
| abstract = 
}}

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                              ,.                                                        LICENSEE EVENT REPORT
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69        E% ENT D ATE                F4          15       REPCrtT D t.TE              80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h RT li 1 R             9        (nveraee Dower rnnen                               I sl2l l_Durine normn1 oger. uith unie ? ne full n nu ai-g ; monitor output signal calibration) was not performed withit3Jhe _ reauired_ frequency.,J ,
1 o I 41 1 (Tech Spec Table 4.1.B) during the period 10/14/81 to 10/28/81. There l
1 3ps) l vas no eff ect on the health or safety of the public because APRM gains 1
3 lc i 1 are monitored and recorded every 12 hours and log review indicates l
O } i j l no APRM gains were out of tolerance. The test was satisf actorily per-l O;4j           [ formed on 10/14 and 10/28. See attachment for previous similar events.                                                                                                                  50 CAUSE                                                                  Co?.'P              vALyr SYSTEtt             CAUSE SUSCODE              SUBCODE CODE                COOE        'JUSCODE                        COMPONENT CODE oIel                                     ,
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                 .                                        io                                                                                                                                        A EVISIO*4 SEQUE N TI AL                              OCCun9ENCC                FtEFOR T REPORT NO.                                     COOE                        TYPE                             NO.
tgp gg        EVENT YE AR h,aggr _ 231812]                     22 l-I 23 1011101 24              26 Ld 27 10 13 i 28           23 Lt_.1 3J L-J 31 101 32 ATTACHMENT              NPRO 4             PRi?.'E CO'.'P.             COMPONENT ACTION FUTURE                      EF5ECT             SHUTDOWN                                           SUBMIT T ED         FOHf t hud.            SUPPUER                  MANUFACTURER T A A E T.      AC TION           ONPLANT              VETHOU                    HOURS           u LZ_]h            Io 10 Io Io I                     LvJ@                 IN      l@             {Z_j@              lZ l9 l 9 I 947 l(
LnJ@l 3J              34 n ih          I Z lh 35                  30               31                          40    4i                    42                    43                  44 cAUSE DESCR:PTION AND CORRECTIVE ACTIONS h l
1 10ll Personnel error.                                   Personnel involved were instructed to be more enrefn1 I
1  Iij lwhen scheduline. Derformine. and routine surveillance instrucefons in
!    [ > i .. ; I the future. The existing surveillance program is fully adeauate                                                                                                                                       -
                                                                                                                                                                                                                     )
lilli i considering the few occurrences and the number of SI's performed I
li 1 1 l (approximately 14,000/yr) and no further recurrence control is planned.                                                                                                                            80 1            8 u OTHEH STATUS                 DISCO            Y                                DISCOVEHY DESCRIPTION STA                      ". POWER l1 I5j lElh l0l9l9lhl                                                        NA                     l          lAlhl                   Plant Services Observation                                               l
     '                                   CO TENT A Yt'll T Y                                                                                                                           LOCATION CF RELE ASE AEt EASED OF nELC ASE                              AMOUNT OF ACTIVITY NA                                                                       I I i l8> l [_Zj h l Z l@l                                                     NA l                l PE nzNsEl E wustSEs t;UU51E H                           OCSCRIPitON l
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7.-[' '    -TGnnessee Valley Authority                                            Form BF 17 -
Browns Ferry Nuclear Plant BF 15.2 2/17/82 LER SUPPLEMENTAL INFORMATION BFRO 260 / 82010         Technical Specification Involved  Table 4.1.B' Reported Under Technical Specification 6.7.2.b. (3)
* Date Due NRC 03/10/82 b
Event Narrative:
During normal operation with units 1 & 2 at approximately full power and unit 3 in refueling outage, SI 4.1.B.2 for unit 2 was not performed from 10/14/81 to
    ~            10/28/81. Technical Specification Table 4.1.B requires this SI to be performed once every seven days.
There was no effect on public health and safety. APRM gains are constantly monitored by the nuclear engineers and recorded once every 12 hours and Surveillance Instruction 4.1.B.2 for unit 2 was performed on 10/14/81 and 10/28/81. Maintenance personnel were instructed to be more careful when
_            scheduling SI's in the future.
Regarding the actual missed performance of the SI, no further recurrence control is required as described in the LER. However, we are investigating the reason p             for the delay in recognizing that the SI was missed, and will take necessary L,1          actions to correct the situation.
p-
!l
* Previous Similar Events:
'J LER No. - 259/79023, 259/79029, 259/80009, 259/80057, 259/80068, 296/80017 and
  ,            260/81010 J
U J
\~
t i     t J
Retention: /criod - Lifetime; Responsibility - Document Control Supervisor
  ~
* Revision: hM 7-
,
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