ML17266A142: Difference between revisions

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{{#Wiki_filter:0 NRC FORM 144 I7 77 I LICENSEE EVENT REPORT U.S.NUCLEAR RECULATORY COMMISS'ION I Qi*:~l I (Pl EASE PRINT OR TYPE AI.L RECUIRED INFORMATIONI
{{#Wiki_filter:0 NRC FORM 144                                                                                                                           U. S. NUCLEAR RECULATORY COMMISS'ION I7 77 I o>> o~ll LICENSEE EVENT REPORT
[0Dl]Irl r 1311 31 11 r 0 Ol-OIOIOI Ol Ol-0 0 r 411 1 11 1 Qr~Qr o Q L CEASES COQE 4.5&CENSE NUMS'ER 1$S LICENSE,YFE JO Sr C*e$4 CON'T o>>o~ll o>>I I o QQCKKT NVMSER 4$49 EVENT QATE 24 1$AEFQRT OATS SO EVENT OESCRIPTIQN ANO FRCBABI.E CONSKCUENCES Qlo~0 ro ed to full insertion.
                                                                *: ~l I I
Action in CEA 22 was restored to it's normal position within 1 hour.Tq was found to be.044 and action on TS 3.2.4.a was initiated..
Qi                  (Pl EASE PRINT OR TYPE AI.L RECUIRED INFORMATIONI
T was determined to be within limits in less than 5 hours.No other core limits were'exceeded.
[0Dl] Irl r 1311                             31 11 r   o      0     Ol       OIOIOI Ol Ol                       0 0       Qr      411         1 11 1           Qr~Qr o>>
~03 accordance with T.S.3~1~3.1.e was initiated and REACTOR POWER was REDUCED SYSTEM CAUSE CAUSE COMP.VALVE CQQE CQQE SVSCQQE CCMFQNKNT CQQE SU4CQQK SUSCQQK rrrr>>e Lie L>>e~e LJe Bate 9 IO I I I1 l1 IS IS'O SEQUENTIAL OCCVRRKNCK REPORT REVISIQN~LERIRO EVENT YKAA RKFORT NO.CQQE TYtE~Qrr>>ra lr~80+~00 2+~~03+1+QB 1I 11'11 14 14 11 25 19 10 11 11 ACTION FUTURE EFFECT SI4UTQOWN AT~ACIIMENT NFAQA tRIME CQMF.CQMFQNKNT TAKEN ACTION CN PLANT METIIQQ IIQVA$22$USMITTKQ FQIIM>US.SVtt ER MANUFACTUAEA roer>>e r>>e~e''re~e~re~e 22 34~40 41 44 47 CAUSE OESCRIPTION ANO CORRECTIVE ACTIONS22 d ed due to a failed 15V ower su 1 (ower rate mod SU-UNI-~09 30A-BV)in the coil power programmer.
L CEASES COQE               4     .5                     &CENSE NUMS'ER                         1$       S       LICENSE,YFE           JO     Sr C*e $4 CON'T QQCKKT NVMSER               4$     49       EVENT QATE             24       1$
No cause for this failure could be~0 1 The reactor was return'ed to 100%power.Similar occurrences were reported~0 4 as LERs 335-76-37, 78-21 and 79-6 1 4 9 determined.
I AEFQRT OATS I
Immediate corrective action was to replace the power supply.r U METHQQ QF OISCOVERY Me 45 45 NA NA M.A.Scho man.4 9 F 4C I UTY~STATVS'\POWER QnIER STATUS Q30 EK LrJQ>>LLL~~O~NA 7 9 9 IO I2 I 1 ACnVITY CQNTLNT RELEASEQ Ol'EI EA5K AMOUNT OP ACTIVITY QSS E~Z Q33~ZQ34 NA 1 1 9 IO II PEASQNNEI.
SO o
EXtQSVRES NUMSER TYFK QESCRIPTIQN Q39~oo o Q>>~zQrr 7 5 4 I I I'1 11 tERSQNNKL INJURIES EZI~oo 0 Q LCSS OF CR QAMAQK 0 FACILITY Q43 TYF'K QESCRIFTIQN
EVENT OESCRIPTIQN ANO FRCBABI.E CONSKCUENCES Qlo
~ZQ2 T 4 1'O FVSLIC'TY ISSVKQ QESCRltT:ON
                        ~0                                                                                               ro       ed     to   full insertion.                         Action in
~S LN'0 NA 4 9 IO QISCQVERY QESCRltnQN Q32 0 erator Observation LQCAnoN ot RELEASE QSB NA NRC USE ONLY 49 49 SO 305-552-3802 PHONE: B009910%Ee'IIO\*r,44r 4'*',~r'I r r~r~pt r i~r'-'~'r~f'r~" r}}
                        ~03              accordance with T. S.                                3 ~ 1 ~ 3. 1. e was          initiated            and REACTOR                  POWER        was REDUCED CEA 22 was                   restored to it's normal position within                                                   1   hour. Tq was found to be .044 and action on TS 3.2.4.a was initiated.. T                                                                       was determined to be within limits in less than 5 hours. No other core                                                                       limits were'exceeded.
                                                                                                                    ~e
                          ~0    1         The      reactor              was return'ed                to    100%      power.            Similar occurrences were reported
                          ~0 4            as LERs 335-76-37,                              78-21 and 79-6 1       4 9 SYSTEM             CAUSE           CAUSE                                                         COMP.             VALVE
                                                                                                                                                                            'O CQQE               CQQE         SVSCQQE                   CCMFQNKNT CQQE                     SU4CQQK           SUSCQQK
                          ~09                                rrrr>>e Lie L>>e 9           IO           II            I1             l1                                 IS LJe Bate IS SEQUENTIAL                             OCCVRRKNCK           REPORT                           REVISIQN ~
                                                                                      +                                                                                                +
                                                                                                                            're ~e ~e LERIRO     EVENT YKAA                                 RKFORT NO.                                 CQQE               TYtE     ~
Qrr>>ra lr               ~80 1I                    '11
                                                                                                      ~00 14 2             +~             ~03                   +1 10                11 QB 11 11                                       14         11             25       19 tRIME CQMF.
                                                                                              ~e '
ACTION FUTURE                     EFFECT           SI4UTQOWN                                   AT ~ ACIIMENT         NFAQA                                     CQMFQNKNT IIQVA$ 22                                                 SVtt TAKEN ACTION roer>>e r>>e 22           34 CN PLANT            METIIQQ
                                                                                                                        ~
40
                                                                                                                                        $ USMITTKQ 41 FQIIM >US.
                                                                                                                                                                                ~re    ER 44 MANUFACTUAEA 47 CAUSE OESCRIPTION ANO CORRECTIVE ACTIONS 22 d                 ed due           to   a   failed         15V         ower su 1                   ( ower         rate         mod SU-UNI-30A-BV)           in the coil                   power programmer.                         No cause             for this failure could                               be determined.                     Immediate             corrective action                       was     to replace the power supply.
4   9 F 4C I UTY ~                                                                     METHQQ QF STATVS               '\ POWER                         QnIER STATUS Q30         OISCOVERY                                QISCQVERY QESCRltnQN Q32 EK LrJQ>>
7        9    9 ACnVITY LLL~~O~
IO CQNTLNT I2     I1 NA                            Me 45 0    erator Observation RELEASEQ       Ol'EI EA5K                   AMOUNTOP ACTIVITYQSS                                                          LQCAnoN ot RELEASE            QSB E       ~Z       Q33     ~ZQ34                         NA                                                                      NA 1       1   9                 IO           II                                                         45 PEASQNNEI. EXtQSVRES NUMSER               TYFK       QESCRIPTIQN Q39
                                        ~oo             o Q>>~zQrr II      I'1         11 NA 7        5    4 tERSQNNKL INJURIES EZI ~oo                       0   Q LCSS OF CR QAMAQK 0 FACILITY TYF'K         QESCRIFTIQN                   Q43 NA T        4
                                        ~ZQ2 1       'O FVSLIC'TY                                                                                                                                       NRC USE ONLY ISSVKQ         QESCRltT:ON       ~S r
LN'0         IO NA 49   49 U
4    9                                                                                                                                                                            SO M. A. Scho                man .                              PHONE:
305-552-3802 B009910                         %
pt ~r Ee'IIO
  \
r,44r 4'** ', ~   r i       ~   r   '-   '             ~     '       r ~f           '                      '
I          r                                  r  ~        r r~ " r}}

Latest revision as of 17:38, 29 October 2019

LER 80-002/03L-0:on 800104,during Normal Operations,Control Element Assembly Dropped to Full Insertion,Causing Tq to Exceed Core Limits.Caused by Failure of 15-volt Power Supply in Coil Power Programmer.Power Supply Replaced
ML17266A142
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 02/01/1980
From: Schoppman M
FLORIDA POWER & LIGHT CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML17207A833 List:
References
LER-80-002-03L, LER-80-2-3L, NUDOCS 8002210386
Download: ML17266A142 (1)


Text

0 NRC FORM 144 U. S. NUCLEAR RECULATORY COMMISS'ION I7 77 I o>> o~ll LICENSEE EVENT REPORT

  • ~l I I

Qi (Pl EASE PRINT OR TYPE AI.L RECUIRED INFORMATIONI

[0Dl] Irl r 1311 31 11 r o 0 Ol OIOIOI Ol Ol 0 0 Qr 411 1 11 1 Qr~Qr o>>

L CEASES COQE 4 .5 &CENSE NUMS'ER 1$ S LICENSE,YFE JO Sr C*e $4 CON'T QQCKKT NVMSER 4$ 49 EVENT QATE 24 1$

I AEFQRT OATS I

SO o

EVENT OESCRIPTIQN ANO FRCBABI.E CONSKCUENCES Qlo

~0 ro ed to full insertion. Action in

~03 accordance with T. S. 3 ~ 1 ~ 3. 1. e was initiated and REACTOR POWER was REDUCED CEA 22 was restored to it's normal position within 1 hour. Tq was found to be .044 and action on TS 3.2.4.a was initiated.. T was determined to be within limits in less than 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. No other core limits were'exceeded.

~e

~0 1 The reactor was return'ed to 100% power. Similar occurrences were reported

~0 4 as LERs 335-76-37, 78-21 and 79-6 1 4 9 SYSTEM CAUSE CAUSE COMP. VALVE

'O CQQE CQQE SVSCQQE CCMFQNKNT CQQE SU4CQQK SUSCQQK

~09 rrrr>>e Lie L>>e 9 IO II I1 l1 IS LJe Bate IS SEQUENTIAL OCCVRRKNCK REPORT REVISIQN ~

+ +

're ~e ~e LERIRO EVENT YKAA RKFORT NO. CQQE TYtE ~

Qrr>>ra lr ~80 1I '11

~00 14 2 +~ ~03 +1 10 11 QB 11 11 14 11 25 19 tRIME CQMF.

~e '

ACTION FUTURE EFFECT SI4UTQOWN AT ~ ACIIMENT NFAQA CQMFQNKNT IIQVA$ 22 SVtt TAKEN ACTION roer>>e r>>e 22 34 CN PLANT METIIQQ

~

40

$ USMITTKQ 41 FQIIM >US.

~re ER 44 MANUFACTUAEA 47 CAUSE OESCRIPTION ANO CORRECTIVE ACTIONS 22 d ed due to a failed 15V ower su 1 ( ower rate mod SU-UNI-30A-BV) in the coil power programmer. No cause for this failure could be determined. Immediate corrective action was to replace the power supply.

4 9 F 4C I UTY ~ METHQQ QF STATVS '\ POWER QnIER STATUS Q30 OISCOVERY QISCQVERY QESCRltnQN Q32 EK LrJQ>>

7 9 9 ACnVITY LLL~~O~

IO CQNTLNT I2 I1 NA Me 45 0 erator Observation RELEASEQ Ol'EI EA5K AMOUNTOP ACTIVITYQSS LQCAnoN ot RELEASE QSB E ~Z Q33 ~ZQ34 NA NA 1 1 9 IO II 45 PEASQNNEI. EXtQSVRES NUMSER TYFK QESCRIPTIQN Q39

~oo o Q>>~zQrr II I'1 11 NA 7 5 4 tERSQNNKL INJURIES EZI ~oo 0 Q LCSS OF CR QAMAQK 0 FACILITY TYF'K QESCRIFTIQN Q43 NA T 4

~ZQ2 1 'O FVSLIC'TY NRC USE ONLY ISSVKQ QESCRltT:ON ~S r

LN'0 IO NA 49 49 U

4 9 SO M. A. Scho man . PHONE:

305-552-3802 B009910  %

pt ~r Ee'IIO

\

r,44r 4'** ', ~ r i ~ r '- ' ~ ' r ~f ' '

I r r ~ r r~ " r