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{{#Wiki_filter:U. s. NUGLhAH HkGULAT OR Y COMMISSION 17 77)LICENSEE EVENT REPORT
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o i l 8 60 61 DOCKET NUYaER 68 63 EVENT DATE 74 75 REPORT D ATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h o 2 l SEE ATTACHMEf1T I O 3 ll10141 l i O S lll0 l6 l ll0 7l0 8ll7 8 9 80 SYSTEM CAUSE CAUSE COVP.VALVE CODE CODE SU8 CODE COYPONENT CODE SUBCODE SU8 CODE 1 R I B l@ W@ l E l@ l I l N l S l T l R l U l@ l XI@ L_(J @
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o 9?d 9 10 11 12 13 18 19 20 , SEOUEN TI AL OCCURRENCE REPOPT REVISION L EVENT YE AR REPORT NO.
EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h o     2 l           SEE ATTACHMEf1T                                                                                                                                           I O   3 l                                                                                                                                                                       l 10141 l                                                                                                                                                                            i O   S l                                                                                                                                                                      l l0 l6 l l                                                                                                                                                                          l 0    7        l 0  8        l l
CODE TYPE N O.@ yu'E R RO I7l9ll'l0 615ll/l 013 llLl[_]I Ol a Qa;_ 21 22 23 24 26 27 28 29 30 31 32 TAKEf A TO ON PLANT T HOURS SB IT D FOR b B.SUPPLIE MANUFACTURER I A l@l]_]@
7            8 9 80 SYSTEM             CAUSE         CAUSE CODE                                                                                        COVP.         VALVE CODE         SU8 CODE                 COYPONENT CODE                 SUBCODE         SU8 CODE o  9
l 21@L3JO 101010101 LYJ@IV @IN l@l G l0 18 10 l(33 34 35 36 31 40 4i 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h i o l SEE ATTACHMENT 1 li lil I I l i>, ai i i;l i 141 1 1 7 8 9 80 ST US* POW E R OTHER STA TUS DISCOV H.DISCOVERY DESCRIPTION l Cl @ l0 0l2l@
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NAll A l@l Operator Observation l i s''A!TiviTv CO3 TENT
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''*""**''8 RFLE ASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE Q @ l 2 l@l tJA I I NA i c 7 is 9 10 11 44 45 PERSONNEL EXPOSURES 80 NUV8ER TYPE D E SC RIP TION 10l010]@l_Zj@lNA i il'"' PERSONNE t iNau' RIES
                                    ,
''2"" DESCniPTiON@
SEOUEN TI AL                     OCCURRENCE           REPOPT                     REVISION L           EVENT YE AR                               REPORT NO.                           CODE               TYPE                       N O.
NuveER 7 r 10 01 0l@l NA J9 4 a2 i a i 7 8 9 11 12 LOSS OF OR DAVAGE TO FACILITY 80 TYPE D E SCRIP TION v L' L_J Z l@lNA 7 _d 9 10 ISSUE DESCRIPTION 12101 LrL[@l
                    @ yu'E a Qa;R RO     I7l9l                l'             l0 615l                                013 l
*NA I i llIIllll1Ii15 7 8 9 10 68 69 80 3 W. V. Childs NAME OF PREPARER (315)342-3840 o PHONE:*, 7 910100 MB  
_ 21           22         23             24             26 l/l 27           28       29 lLl 30
-.POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET N0. 50-333 ATTACHMENT TO LER 79-065/03L-0 Page 1 of 1 During normal startup operations, the Rod Sequence Control System failed in such a manner as to not allow normal control rod insertion or with-drawal . The scram function for control rods remained unaffected. The lied Sequence Control System maintained control of the rod withdrawal st:quence by not allowing any motion, thus the system performed its ir. tended function as required by Technical Specifications Appendix A, Paragraph 3.3.B.3.a.
[_]
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40   4i             42               43                           47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h i
o l SEE ATTACHMENT 1
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8 RFLE ASED OF RELEASE                         AMOUNT OF ACTIVITY i    c                                                                                                                          LOCATION OF RELEASE 7          is 9 Q @ l 2 l@l tJA 10             11                                           44 I          I 45 NA PERSONNEL EXPOSURES                                                                                                                                     80 NUV8ER             TYPE         D E SC RIP TION i    i 10l010]@l_Zj@lNA                                                                                                                                               l
'           "                   ''        2          "
                  ' PERSONNE t iNau' RIES                                                                                                                                     "
NuveER              DESCniPTiON@                                                                                           7           r 7
i    a 8 9 10       01 0l@l12 11 NA                                                                                             J9 4 a2                       i LOSS OF OR DAVAGE TO FACILITY                                                                                                                                 80 TYPE     D E SCRIP TION                   v NA L' L_J 7_          d 9 Z l@l10 ISSUE       DESCRIPTION
* 12101 LrL[@l                       NA 7           8 9             10 I
68 69 i llIIllll1Ii15 80 3 NAME OF PREPARER W. V. Childs                                                                 (315)342-3840                           o PHONE:                                               *
                                                                                                                                                                                        ,
7 910100 MB
 
  -
.
POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET N0. 50-333 ATTACHMENT TO LER 79-065/03L-0                           Page 1 of 1 During normal startup operations, the Rod Sequence Control System failed in such a manner as to not allow normal control rod insertion or with-drawal . The scram function for control rods remained unaffected. The lied Sequence Control System maintained control of the rod withdrawal st:quence by not allowing any motion, thus the system performed its ir. tended function as required by Technical Specifications Appendix A, Paragraph 3.3.B.3.a.
Since the Rod Sequence Control System maintained control of the withdrawal sequence as noted above, the event did not represent a significant hazard to public health and safety.
Since the Rod Sequence Control System maintained control of the withdrawal sequence as noted above, the event did not represent a significant hazard to public health and safety.
Investigation revealed a failed relay on one of the printed circuit boards associated with Control Rod Group 3.
Investigation revealed a failed relay on one of the printed circuit boards associated with Control Rod Group 3. Replacement of the relay restored normal operation of the system.
Replacement of the relay restored normal operation of the system.
                        .
.1139 153}}
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Revision as of 13:40, 19 October 2019

LER 79-065/03L-0:on 790907,rod Sequence Control Sys Failed, Not Allowing Normal Control Rod Insertion or Withdrawal. Caused by Failed Relay on One Printed Circuit Board. Replacement of Relay Restored Normal Operation of Sys
ML19209B783
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 10/04/1979
From: W. Verne Childs
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19209B781 List:
References
LER-79-065-03L, NUDOCS 7910100453
Download: ML19209B783 (2)


Text

17 77) U. s. NUGLhAH HkGULAT OR Y COMMISSION LICENSEE EVENT REPORT

  • CONTROL BLOCK: l i

l l l l ljh e PLEASE PRINT OR TYPE ALL REQlllRED INFORMATION) o 7

i 8l !9 ?1 l LICENSEE Y l J l CODE A l F l le1 l@l 15 01 Ol - 0 LICENSE l 0l 0lNuvdEH 0 l - l 0 l O l O2b l@l26 4 l UCENSE l i 11 TYPE1 l 1Jo@l$ 7 C lA T bdl@

CON'T o i l 8 E'R$ 60ll l@l0151010101313 61 DOCKET NUYaER l3 l@l 68 019101717191@l 63 EVENT DATE 74 110101417 75 REPORT D ATE l 980l@

EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h o 2 l SEE ATTACHMEf1T I O 3 l l 10141 l i O S l l l0 l6 l l l 0 7 l 0 8 l l

7 8 9 80 SYSTEM CAUSE CAUSE CODE COVP. VALVE CODE SU8 CODE COYPONENT CODE SUBCODE SU8 CODE o 9

? d 1 R I10B l@ W@ l E l@ l I l N l S l T l R l U l@ l19XI@ L_(J 9 11 12 13 18 20

@

,

SEOUEN TI AL OCCURRENCE REPOPT REVISION L EVENT YE AR REPORT NO. CODE TYPE N O.

@ yu'E a Qa;R RO I7l9l l' l0 615l 013 l

_ 21 22 23 24 26 l/l 27 28 29 lLl 30

[_]

31 I Ol 32 TAKEf A TO ON PLANT T HOURS SB IT D FOR b B. SUPPLIE MANUFACTURER I33 A l@l]_]@

34 l3521@ L3JO 36 101010101 31 LYJ@ IV @ IN l@ l44G l0 18 10 l(

40 4i 42 43 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h i

o l SEE ATTACHMENT 1

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l i 141 1 1 7 8 9 80 ST US * .POW E R OTHER STA TUS DISCOV H DISCOVERY DESCRIPTION i s

' '

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"

l l A l@l Operator Observation

l A!TiviTv CO3 TENT

8 RFLE ASED OF RELEASE AMOUNT OF ACTIVITY i c LOCATION OF RELEASE 7 is 9 Q @ l 2 l@l tJA 10 11 44 I I 45 NA PERSONNEL EXPOSURES 80 NUV8ER TYPE D E SC RIP TION i i 10l010]@l_Zj@lNA l

' " 2 "

' PERSONNE t iNau' RIES "

NuveER DESCniPTiON@ 7 r 7

i a 8 9 10 01 0l@l12 11 NA J9 4 a2 i LOSS OF OR DAVAGE TO FACILITY 80 TYPE D E SCRIP TION v NA L' L_J 7_ d 9 Z l@l10 ISSUE DESCRIPTION

  • 12101 LrL[@l NA 7 8 9 10 I

68 69 i llIIllll1Ii15 80 3 NAME OF PREPARER W. V. Childs (315)342-3840 o PHONE: *

,

7 910100 MB

-

.

POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET N0. 50-333 ATTACHMENT TO LER 79-065/03L-0 Page 1 of 1 During normal startup operations, the Rod Sequence Control System failed in such a manner as to not allow normal control rod insertion or with-drawal . The scram function for control rods remained unaffected. The lied Sequence Control System maintained control of the rod withdrawal st:quence by not allowing any motion, thus the system performed its ir. tended function as required by Technical Specifications Appendix A, Paragraph 3.3.B.3.a.

Since the Rod Sequence Control System maintained control of the withdrawal sequence as noted above, the event did not represent a significant hazard to public health and safety.

Investigation revealed a failed relay on one of the printed circuit boards associated with Control Rod Group 3. Replacement of the relay restored normal operation of the system.

.

1139 153