ML19344F104: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
 
(StriderTol Bot change)
 
(One intermediate revision by the same user not shown)
Line 18: Line 18:
=Text=
=Text=
{{#Wiki_filter:NRC FORM 366
{{#Wiki_filter:NRC FORM 366
                          '
                                     #                                                                                          U.O. MLOAR RONLGiWM N (j )
                                     #                                                                                          U.O. MLOAR RONLGiWM N (j )
e 77 LICENSEE EVENT REPORT                                                                              P CONTROL BLOCK: l                l    l      l    l  l                        (PLEASE PRINT CR TYPE ALL RE*UIRED INFORMATlHN) lT[i] 8l 9Nl YlLICENSEEJl AlCODr. Fl 1lgl50            l 0 l -l 0 l 0LICENSE l 0 l NUMBER 0 l - l 0 l 0 l 0 25lgl 4        26 l 1LICENSE l1l1    TYPE l
e 77 LICENSEE EVENT REPORT                                                                              P CONTROL BLOCK: l                l    l      l    l  l                        (PLEASE PRINT CR TYPE ALL RE*UIRED INFORMATlHN) lT[i] 8l 9Nl YlLICENSEEJl AlCODr. Fl 1lgl50            l 0 l -l 0 l 0LICENSE l 0 l NUMBER 0 l - l 0 l 0 l 0 25lgl 4        26 l 1LICENSE l1l1    TYPE l
Line 27: Line 26:
l5 Tiil l See' attachment for details.
l5 Tiil l See' attachment for details.
I 10171 I l
I 10171 I l
10181 l
10181 l SOOE                CCDE        SL8 CODE              COMPONENT CODE                    SU8C DE          SU      E l0l9l                            l Il Aj@ l Xl@ l Z l@ lX lX lX lX lX lX l@ l Zl@ W @                              18          19              20 7        8                        9        10            11            12            13 SEQUENTIAL                        OCCURRENCE          REPORT                    REVISION EVENT YE AR                              REPORT No.                            CODE              TYPE                        NO.
                                                              #
SOOE                CCDE        SL8 CODE              COMPONENT CODE                    SU8C DE          SU      E l0l9l                            l Il Aj@ l Xl@ l Z l@ lX lX lX lX lX lX l@ l Zl@ W @                              18          19              20 7        8                        9        10            11            12            13 SEQUENTIAL                        OCCURRENCE          REPORT                    REVISION
_
EVENT YE AR                              REPORT No.                            CODE              TYPE                        NO.
LE R/Ro
LE R/Ro
                 @ Re GAT              l8l0l                8            l0l7l0l 26 y
                 @ Re GAT              l8l0l                8            l0l7l0l 26 y
Line 39: Line 34:
41 l Ylg 42 lN l@ lG 43            44 l0 l8 l0 [g 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS
41 l Ylg 42 lN l@ lG 43            44 l0 l8 l0 [g 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS
_l li lol l See attachment.
_l li lol l See attachment.
1 t i      l
1 t i      l 1
                                                                                                -
I n 121 1 l
1 I n 121 1 l
1: 131 l l
1: 131 l l
EE}8 l9 7
EE}8 l9 7
90 STA $                % *t/MER                      oTHER STATUS              IS        RY                        DISCOVERY OESCRIPTION
90 STA $                % *t/MER                      oTHER STATUS              IS        RY                        DISCOVERY OESCRIPTION NA                                                  NA                                                l It IS l l Zl@ l 0 l 0 [ 0 l@l                                                        l    l Z l@l A itVITY CO TENT REteASED Or RELEASE                        AMOUNT OF ACTIVITY                                                    LOCATION OF RELEASE l                    NA                    l          l                  NA                                                  l li l61 W @ l 2l@OES PERSONNEt EsPOS NUv8ER                TYPE        oESCRiPriON @
'
NA                                                  NA                                                l It IS l l Zl@ l 0 l 0 [ 0 l@l                                                        l    l Z l@l A itVITY CO TENT REteASED Or RELEASE                        AMOUNT OF ACTIVITY                                                    LOCATION OF RELEASE l                    NA                    l          l                  NA                                                  l
                                                                                                    "                                                                      "
li l61
      #      *
* W @ l 2l@OES
                              '
PERSONNEt EsPOS
                                                                                        "
NUv8ER                TYPE        oESCRiPriON @
y l 0 l 0 l 0 l@l Z l@l                                      NA                                                                                                          l
y l 0 l 0 l 0 l@l Z l@l                                      NA                                                                                                          l
    '      '                  ''      '            '
                 ' PERSONNEt INJU          IES NUMBER l t l a l l 0 l 0 l 011l@l12 DESCR!PTICN@ NA                                                                                                                    l 80 7      8 9
                 ' PERSONNEt INJU          IES NUMBER l t l a l l 0 l 0 l 011l@l12 DESCR!PTICN@ NA                                                                                                                    l 80 7      8 9
                                 ^                                                              '
                                 ^                                                              '
Line 63: Line 46:
         , g
         , g
                 'S            ''C"'"'"
                 'S            ''C"'"'"
NA                8  00990yl                                              ,    , , , ]]f,y,,,g 80 3 7      8 9            to 68 69 (315) 342-3840 X207                  o fWNXfUT11XJ3JPjN#EL W. Verne Childs                                              PHONE:                                            5,
NA                8  00990yl                                              ,    , , , ))f,y,,,g 80 3 7      8 9            to 68 69 (315) 342-3840 X207                  o fWNXfUT11XJ3JPjN#EL W. Verne Childs                                              PHONE:                                            5,


                                                              ,
POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 ATTACHMENT TO LER 80-070/03L-0                                                  Page    1  of  2 During plant operations, including normal startup, normal operations and periods where the reactor was shutdown, a number of operational problems associated with the Neutron Monitoring System Intermediate Range Monitors (IRM) were encountered. Sunnarized below is a tabulation of each of the problems encountered including a brief statement relating to the actions required by Technical Specifications Table 3.1-1, if applicable.
POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 ATTACHMENT TO LER 80-070/03L-0                                                  Page    1  of  2 During plant operations, including normal startup, normal operations and periods where the reactor was shutdown, a number of operational problems associated with the Neutron Monitoring System Intermediate Range Monitors (IRM) were encountered. Sunnarized below is a tabulation of each of the problems encountered including a brief statement relating to the actions required by Technical Specifications Table 3.1-1, if applicable.
DATE      TIME                        DESCRIPTION /IRM STATUS                    ACTION TAKEN (To meet Technical Specifications Table 3.1-1 requirements) 8/ 9/80  1817      commenced reactor startup/all eight (8) IRM            None Required channels operable 8/10/80  0430      IRM A, B and H failed surveillance /                  Inserted half scrcm on "B" side and IRM C, D,.E, F, and G operable                        verified remaining five (5) IRH's operab[
DATE      TIME                        DESCRIPTION /IRM STATUS                    ACTION TAKEN (To meet Technical Specifications Table 3.1-1 requirements) 8/ 9/80  1817      commenced reactor startup/all eight (8) IRM            None Required channels operable 8/10/80  0430      IRM A, B and H failed surveillance /                  Inserted half scrcm on "B" side and IRM C, D,.E, F, and G operable                        verified remaining five (5) IRH's operab[
8/11/80  1120      Reactor shifted to run mode /IRM A, B and H            Reset half scram as IRM's not required remain inoperable                                      in Run Mode 8/11/80  2215      Ifanual scram as required by Bulletin 80-17/          Inserted half scram    "B" side and IRM A, B, and H remain inoperable                      verified remaining five (5) IRM's operabic 8/12/80  1000      "B" and "H"  IRM's fully operable following re-      Reset half scram placement of signal cable connectors. Connectors had failed due to moisture and/or damage as a result of Control Rod Drive change out work during Refueling Outage,/IRM "A" remains inoperable.
8/11/80  1120      Reactor shifted to run mode /IRM A, B and H            Reset half scram as IRM's not required remain inoperable                                      in Run Mode 8/11/80  2215      Ifanual scram as required by Bulletin 80-17/          Inserted half scram    "B" side and IRM A, B, and H remain inoperable                      verified remaining five (5) IRM's operabic 8/12/80  1000      "B" and "H"  IRM's fully operable following re-      Reset half scram placement of signal cable connectors. Connectors had failed due to moisture and/or damage as a result of Control Rod Drive change out work during Refueling Outage,/IRM "A" remains inoperable.
8/12/80  1130      IRM "C" exhibited erratic response /IRM B, D, E, F. Commenced repair of signal cable connectd G, and H remain operable                              and found the connector center pin had apparently been damaged during previous repair
8/12/80  1130      IRM "C" exhibited erratic response /IRM B, D, E, F. Commenced repair of signal cable connectd G, and H remain operable                              and found the connector center pin had apparently been damaged during previous repair 4
  -
4


   . ATTACHMENT TO LER 80-070/03L-0                                                        Paga    2  cf    2                    j i
   . ATTACHMENT TO LER 80-070/03L-0                                                        Paga    2  cf    2                    j i
DATE      TIME                        DESCRIPTION /IRM STATUS                      ACTION TAKEN                      i t
DATE      TIME                        DESCRIPTION /IRM STATUS                      ACTION TAKEN                      i t
                                                                                                                                    .
8/12/80    1320      IRM  "B" failed surveillance  /IRM D, E, F, G          Commenced investigation of possible test  '
8/12/80    1320      IRM  "B" failed surveillance  /IRM D, E, F, G          Commenced investigation of possible test  '
and 11 remain operable                                  circuit malfunction 8/12/80    1505      Completed repair of IRM "C" cable connector making      None Required                            i IRM "C" fully operable /IRM C, D E, F, G, and 11 operable 8/12/80    1645      1RM  "B" fully operable following adjustment of test    None Required circuit /IRM B, C, D, E, F, G, and 11 operable 8/12/80    1955      Commenced reactor startup.      IRM's fully operable    None Required                            '
and 11 remain operable                                  circuit malfunction 8/12/80    1505      Completed repair of IRM "C" cable connector making      None Required                            i IRM "C" fully operable /IRM C, D E, F, G, and 11 operable 8/12/80    1645      1RM  "B" fully operable following adjustment of test    None Required circuit /IRM B, C, D, E, F, G, and 11 operable 8/12/80    1955      Commenced reactor startup.      IRM's fully operable    None Required                            '
Line 81: Line 60:
'                                  failure was the result of signal cable connector                                                ,
'                                  failure was the result of signal cable connector                                                ,
problem within primary containment /IRM B, C, E, F. C, and 11 operable                                                                                  l 8/13/80    1014      Reactor automatic scram to satisfy the requirements    None Required of NRC Bulletin 80-17/all IRM'a operable except A                                                i and D                                                                                            ,
problem within primary containment /IRM B, C, E, F. C, and 11 operable                                                                                  l 8/13/80    1014      Reactor automatic scram to satisfy the requirements    None Required of NRC Bulletin 80-17/all IRM'a operable except A                                                i and D                                                                                            ,
8/13/80    1444      Commenced reactor startup / All IRM's operable          None Required                            j, except A and D
8/13/80    1444      Commenced reactor startup / All IRM's operable          None Required                            j, except A and D 8/13/80    2310      Reactor in the Run Mode. / All IRM's operable          None Required    (IRM's not required to except A and D                                          be operable when in Run Mode 8/15/80    0945      IRM "B" failed downscale. The  cause in unknown /    None Required as IRM's are not required IRM A, B and D inoperable                              to be operable in the Run Mode At the time of submitting thio LER, IRM "A" is failed. Failure is believed to be due to a failed detector.
,
8/13/80    2310      Reactor in the Run Mode. / All IRM's operable          None Required    (IRM's not required to except A and D                                          be operable when in Run Mode 8/15/80    0945      IRM "B" failed downscale. The  cause in unknown /    None Required as IRM's are not required IRM A, B and D inoperable                              to be operable in the Run Mode At the time of submitting thio LER, IRM "A" is failed. Failure is believed to be due to a failed detector.
i-R: placement is currently planned for the next scheduled plant outage in which the plant is placed in the cold shutdown condition.                                                                                                            >
i-R: placement is currently planned for the next scheduled plant outage in which the plant is placed in the cold shutdown condition.                                                                                                            >
I IRM  "B" is inoperabic (falled downscale). The cause of failure is unknown but believed to be a bad signal cable connector.      Repair will be attempted during the next plant outage which permite entry into the primary containment.
I IRM  "B" is inoperabic (falled downscale). The cause of failure is unknown but believed to be a bad signal cable connector.      Repair will be attempted during the next plant outage which permite entry into the primary containment.
                                                                                                                                    ,
IRM "D"  is failed downscale. Cause of failure is believed to be failure of a signal cable connector or detector.      !
IRM "D"  is failed downscale. Cause of failure is believed to be failure of a signal cable connector or detector.      !
Repair will be attempted during the next plant outage which permits primary containment entry.                                {
Repair will be attempted during the next plant outage which permits primary containment entry.                                {
i A follow-up report will be submitted when the causes of failure and the repair have been completed.                    ;
i A follow-up report will be submitted when the causes of failure and the repair have been completed.                    ;
__ _}}
__ _}}

Latest revision as of 19:01, 15 March 2020

LER 80-070/03L-0:on 800809-15,intermediate Range Monitor Sys Problems Encountered During Plant Shutdown,Startup & Normal Operations.Cause Under Speculation.Followup Rept to Be Submitted
ML19344F104
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 09/08/1980
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
ML19344F099 List:
References
LER-80-070-03L, LER-80-70-3L, NUDOCS 8009120415
Download: ML19344F104 (3)
v • d • e


Text

NRC FORM 366

  1. U.O. MLOAR RONLGiWM N (j )

e 77 LICENSEE EVENT REPORT P CONTROL BLOCK: l l l l l l (PLEASE PRINT CR TYPE ALL RE*UIRED INFORMATlHN) lT[i] 8l 9Nl YlLICENSEEJl AlCODr. Fl 1lgl50 l 0 l -l 0 l 0LICENSE l 0 l NUMBER 0 l - l 0 l 0 l 0 25lgl 4 26 l 1LICENSE l1l1 TYPE l

l 1JD lgl57 CAT $8 lg 7 14 1 CON'T IOl1l EU$n l60b @l 0l 5 l DOCKET 0 l 0NUMB l 0ERl 3 l 3 68l 3 69@l0 EVENT l8 l1DATEl0 l8 l0 @l 0l REPORT 74 75 9l 0lDATE 8l 8l 0l@ 80

> 8 61 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h ITTT1 1 INTERIM REPORT: At various times during plant shutdown, startup and normal operation),

a number of Intermediate Range Monitor System problems were encountered. Not all l Ioial l g o i ., i l are reportable events as such but are listed for clarification. No operation of the l

ol6; l plant in a condition less conservative then that allowed by TS Table 3.1-1 occurred. l l

l5 Tiil l See' attachment for details.

I 10171 I l

10181 l SOOE CCDE SL8 CODE COMPONENT CODE SU8C DE SU E l0l9l l Il Aj@ l Xl@ l Z l@ lX lX lX lX lX lX l@ l Zl@ W @ 18 19 20 7 8 9 10 11 12 13 SEQUENTIAL OCCURRENCE REPORT REVISION EVENT YE AR REPORT No. CODE TYPE NO.

LE R/Ro

@ Re GAT l8l0l 8 l0l7l0l 26 y

27 l 0l 3l 28 29 lLl 30 l-l 31 l0 l 32

_ 21 22 23 24 K N AC O ON PL NT tNh HoVR$ 22 S8 IT FOR 8. SUPPLi MANUF CTURER I3JX I@lJ4X I@ W@ IZi@

JS 36 1010101 37 40 l lYJ@

41 l Ylg 42 lN l@ lG 43 44 l0 l8 l0 [g 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS

_l li lol l See attachment.

1 t i l 1

I n 121 1 l

1: 131 l l

EE}8 l9 7

90 STA $  % *t/MER oTHER STATUS IS RY DISCOVERY OESCRIPTION NA NA l It IS l l Zl@ l 0 l 0 [ 0 l@l l l Z l@l A itVITY CO TENT REteASED Or RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE l NA l l NA l li l61 W @ l 2l@OES PERSONNEt EsPOS NUv8ER TYPE oESCRiPriON @

y l 0 l 0 l 0 l@l Z l@l NA l

' PERSONNEt INJU IES NUMBER l t l a l l 0 l 0 l 011l@l12 DESCR!PTICN@ NA l 80 7 8 9

^ '

m'E ' USC%TfR '^ " @

1 9 y gl NA , l 80 7 8 9 10

, g

'S C"'"'"

NA 8 00990yl , , , , ))f,y,,,g 80 3 7 8 9 to 68 69 (315) 342-3840 X207 o fWNXfUT11XJ3JPjN#EL W. Verne Childs PHONE: 5,

POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 ATTACHMENT TO LER 80-070/03L-0 Page 1 of 2 During plant operations, including normal startup, normal operations and periods where the reactor was shutdown, a number of operational problems associated with the Neutron Monitoring System Intermediate Range Monitors (IRM) were encountered. Sunnarized below is a tabulation of each of the problems encountered including a brief statement relating to the actions required by Technical Specifications Table 3.1-1, if applicable.

DATE TIME DESCRIPTION /IRM STATUS ACTION TAKEN (To meet Technical Specifications Table 3.1-1 requirements) 8/ 9/80 1817 commenced reactor startup/all eight (8) IRM None Required channels operable 8/10/80 0430 IRM A, B and H failed surveillance / Inserted half scrcm on "B" side and IRM C, D,.E, F, and G operable verified remaining five (5) IRH's operab[

8/11/80 1120 Reactor shifted to run mode /IRM A, B and H Reset half scram as IRM's not required remain inoperable in Run Mode 8/11/80 2215 Ifanual scram as required by Bulletin 80-17/ Inserted half scram "B" side and IRM A, B, and H remain inoperable verified remaining five (5) IRM's operabic 8/12/80 1000 "B" and "H" IRM's fully operable following re- Reset half scram placement of signal cable connectors. Connectors had failed due to moisture and/or damage as a result of Control Rod Drive change out work during Refueling Outage,/IRM "A" remains inoperable.

8/12/80 1130 IRM "C" exhibited erratic response /IRM B, D, E, F. Commenced repair of signal cable connectd G, and H remain operable and found the connector center pin had apparently been damaged during previous repair 4

. ATTACHMENT TO LER 80-070/03L-0 Paga 2 cf 2 j i

DATE TIME DESCRIPTION /IRM STATUS ACTION TAKEN i t

8/12/80 1320 IRM "B" failed surveillance /IRM D, E, F, G Commenced investigation of possible test '

and 11 remain operable circuit malfunction 8/12/80 1505 Completed repair of IRM "C" cable connector making None Required i IRM "C" fully operable /IRM C, D E, F, G, and 11 operable 8/12/80 1645 1RM "B" fully operable following adjustment of test None Required circuit /IRM B, C, D, E, F, G, and 11 operable 8/12/80 1955 Commenced reactor startup. IRM's fully operable None Required '

except Channel "A" 8/13/80 0100 IRM "D" failed downscale. Probable cause of downscale None Required

' failure was the result of signal cable connector ,

problem within primary containment /IRM B, C, E, F. C, and 11 operable l 8/13/80 1014 Reactor automatic scram to satisfy the requirements None Required of NRC Bulletin 80-17/all IRM'a operable except A i and D ,

8/13/80 1444 Commenced reactor startup / All IRM's operable None Required j, except A and D 8/13/80 2310 Reactor in the Run Mode. / All IRM's operable None Required (IRM's not required to except A and D be operable when in Run Mode 8/15/80 0945 IRM "B" failed downscale. The cause in unknown / None Required as IRM's are not required IRM A, B and D inoperable to be operable in the Run Mode At the time of submitting thio LER, IRM "A" is failed. Failure is believed to be due to a failed detector.

i-R: placement is currently planned for the next scheduled plant outage in which the plant is placed in the cold shutdown condition. >

I IRM "B" is inoperabic (falled downscale). The cause of failure is unknown but believed to be a bad signal cable connector. Repair will be attempted during the next plant outage which permite entry into the primary containment.

IRM "D" is failed downscale. Cause of failure is believed to be failure of a signal cable connector or detector.  !

Repair will be attempted during the next plant outage which permits primary containment entry. {

i A follow-up report will be submitted when the causes of failure and the repair have been completed.  ;

__ _

Retrieved from "https://kanterella.com/w/index.php?title=ML19344F104&oldid=2604999"