ML19338E591: Difference between revisions
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' 771 LICENSEE EVENT REPORT CONTnOL BLOCK: l 1 | |||
' 771 | |||
LICENSEE EVENT REPORT | |||
CONTnOL BLOCK: l 1 | |||
l l I l l lh 6 | l l I l l lh 6 | ||
(ptgAsg pelNT OR TYPE ALL KEQUiRED INFORMATION) lo lils l9 NI El Fi 01 Sl 14 ll@l0 lo lo 1010 lo uCENstNvMSER lo lo 10 lo 25 10 2e l@l411lllllll@l uCENst TV,E J0 $7 I | (ptgAsg pelNT OR TYPE ALL KEQUiRED INFORMATION) lo lils l9 NI El Fi 01 Sl 14 ll@l0 lo lo 1010 lo uCENstNvMSER lo lo 10 lo 25 10 2e l@l411lllllll@l uCENst TV,E J0 $7 I | ||
Line 33: | Line 28: | ||
l0i7l l l | l0i7l l l | ||
l o la I I SE CYo'e' susCME COMPONENT COCE sus CD'E Su E | l o la I I SE CYo'e' susCME COMPONENT COCE sus CD'E Su E | ||
, ioisi LI I A l@ [Ej@ l Al@ l Il Nl S l Tl R l U l@ lS [@ lz l@ 18 19 20 | , ioisi LI I A l@ [Ej@ l Al@ l Il Nl S l Tl R l U l@ lS [@ lz l@ 18 19 20 4 9 10 11 ?2 13 g EVENTvtAA AE M NO QC T N . | ||
4 9 10 11 ?2 13 g EVENTvtAA AE M NO QC T N . | |||
@ sg,gea g noi 81 01 1-1 l24 0121 cl 1/1 10l3l lL l l-l l0l 21 22 23 26 27 28 29 30 31 32 K N AC 0 0 8 t.A N T wouRs 8 ,OR S. su clE VA u,AC RER IBl@lzl@ l zi@ | @ sg,gea g noi 81 01 1-1 l24 0121 cl 1/1 10l3l lL l l-l l0l 21 22 23 26 27 28 29 30 31 32 K N AC 0 0 8 t.A N T wouRs 8 ,OR S. su clE VA u,AC RER IBl@lzl@ l zi@ | ||
22 2 25 las II@ l 0 l 010fd l 27 0 I Yl@ | 22 2 25 las II@ l 0 l 010fd l 27 0 I Yl@ | ||
4, INi@ | 4, INi@ | ||
n INI@ lGl2l2l3l@ | n INI@ lGl2l2l3l@ | ||
CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h | CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h | ||
,, ioil During trouble shooting, it was discovered that wafer #6, contact #1 of the Flow i Dependent Setpoint Selection Switch, a Grayhill 42136-8-2-5N, was making poor contact l. l | ,, ioil During trouble shooting, it was discovered that wafer #6, contact #1 of the Flow i Dependent Setpoint Selection Switch, a Grayhill 42136-8-2-5N, was making poor contact l. l mi | ||
mi | |||
,,,7i i This poor contact fed a 0% power indication into the APO calculator thus making the i i,,3i ] calculator calculate setpoints for 0% power. The switch was cleaned and returned l i,i,i i to service. i | ,,,7i i This poor contact fed a 0% power indication into the APO calculator thus making the i i,,3i ] calculator calculate setpoints for 0% power. The switch was cleaned and returned l i,i,i i to service. i | ||
'sTE7 s,owsm otwensT4rus @ 5'ssEoSSEv' OISCOVERY DESCRI, TION NA lAlgl Operator Observation li I5 I I E l@ ll 10 l0 i2l@lo | |||
'sTE7 s,owsm otwensT4rus @ 5'ssEoSSEv' OISCOVERY DESCRI, TION | |||
NA lAlgl Operator Observation li I5 I I E l@ ll 10 l0 i2l@lo | |||
* l 45 .s s0 l | * l 45 .s s0 l | ||
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'aCnviry | |||
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l 4 ouNrcP 2Cnvirv NA l @ l NA j IiIslIZld,Izl@ses | |||
l 4 ouNrcP 2Cnvirv NA l @ l NA j | |||
IiIslIZld,Izl@ses | |||
. ase~~.t u ,os | . ase~~.t u ,os | ||
, w e..a | , w e..a | ||
' til711010101@lrv,e l @lo:Cai,riS.@ | ' til711010101@lrv,e l @lo:Cai,riS.@ | ||
Line 69: | Line 47: | ||
' ' ' , .scNNet'i~2u'4 s we | ' ' ' , .scNNet'i~2u'4 s we | ||
[i j 31 l 0 l l d. 0 lgloesCai,ne~@ NA | [i j 31 l 0 l l d. 0 lgloesCai,ne~@ NA | ||
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N A.\tE OF PREPARER | N A.\tE OF PREPARER | ||
* / | * / | ||
's' , HON E: | 's' , HON E: | ||
LER 80-020 Omaha Public Power District Fort Calhoun Station Unit No.1 Docket No. 05000285 ATTACHMENT NO. 1 Safety Analysis The Reactor Protection System uses a two-out-of-four to trip logic. One channel at a time may be bypassed, placing the system in a two-aut-of-three to trip logic. When the setpoint was found out of tolerance, the system was immediately placed in the two-aut-of-three logic mode. Therefore, the function of the R.P.S. was only slightly degraded as the other three channels were operable during this time and A, B and C channels had setpoints within tolerance. At no time would the R.P.S. have failed to perform its design functions, that is, to safely shutdown the reactor. See attachment 2 for further technical information. | LER 80-020 Omaha Public Power District Fort Calhoun Station Unit No.1 Docket No. 05000285 ATTACHMENT NO. 1 Safety Analysis The Reactor Protection System uses a two-out-of-four to trip logic. One channel at a time may be bypassed, placing the system in a two-aut-of-three to trip logic. When the setpoint was found out of tolerance, the system was immediately placed in the two-aut-of-three logic mode. Therefore, the function of the R.P.S. was only slightly degraded as the other three channels were operable during this time and A, B and C channels had setpoints within tolerance. At no time would the R.P.S. have failed to perform its design functions, that is, to safely shutdown the reactor. See attachment 2 for further technical information. | ||
V | V | ||
\' ) | \' ) | ||
N | N | ||
LER 80-020 Omaha Public Power District Fort Calhoun Station Unit No.1 Docket No. 05000285 ATTACHMENT NO. 2 Corrective Action One of the inputs to the APD calculator is from the flow dependent setpoint selector switch. The switch is normally used in the 4-pump position only and is only moved out of that position to perform surveil-lanc.e on the RPS. The switch on "0" channe' was making poor contact on one contact which fed the APD calculator information that indicated the reactor was at the 0% power setpoints. The switch was cleaned by rotating several times through full travel and returned to 4-pump operation. The applicable portions of the APD surveillance test, ST-RPS-12, F.2, were performed to prove operability of the reactor pro-tective system. No further corrective action is anticipated. | LER 80-020 Omaha Public Power District Fort Calhoun Station Unit No.1 Docket No. 05000285 ATTACHMENT NO. 2 Corrective Action One of the inputs to the APD calculator is from the flow dependent setpoint selector switch. The switch is normally used in the 4-pump position only and is only moved out of that position to perform surveil-lanc.e on the RPS. The switch on "0" channe' was making poor contact on one contact which fed the APD calculator information that indicated the reactor was at the 0% power setpoints. The switch was cleaned by rotating several times through full travel and returned to 4-pump operation. The applicable portions of the APD surveillance test, ST-RPS-12, F.2, were performed to prove operability of the reactor pro-tective system. No further corrective action is anticipated. | ||
1 | 1 | ||
\' | \' | ||
\: | \: | ||
e , | e , | ||
LER 80-020 Omaha Public l'ower District-Fort Calhot.n Station Unit No.1 Docket No. U5000285 i | LER 80-020 Omaha Public l'ower District-Fort Calhot.n Station Unit No.1 Docket No. U5000285 i | ||
ATTACHMENT NO. 3 Failure Data This is the first occurrance of setpoints being out of tolerance due to a selector switch malfunction. | ATTACHMENT NO. 3 Failure Data This is the first occurrance of setpoints being out of tolerance due to a selector switch malfunction. | ||
J i | J i | ||
! l 1 | ! l 1 | ||
l i | l i | ||
Line 115: | Line 74: | ||
\ | \ | ||
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i | i i , , | ||
i , , | |||
I | I | ||
%p | %p | ||
+ , - - | + , - - | ||
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Latest revision as of 13:25, 31 January 2020
ML19338E591 | |
Person / Time | |
---|---|
Site: | Fort Calhoun |
Issue date: | 09/08/1980 |
From: | Core M OMAHA PUBLIC POWER DISTRICT |
To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
Shared Package | |
ML19338E590 | List: |
References | |
LER-80-020-03L, LER-80-20-3L, NUDOCS 8010030418 | |
Download: ML19338E591 (4) | |
Text
-- . . .
' 771 LICENSEE EVENT REPORT CONTnOL BLOCK: l 1
l l I l l lh 6
(ptgAsg pelNT OR TYPE ALL KEQUiRED INFORMATION) lo lils l9 NI El Fi 01 Sl 14 ll@l0 lo lo 1010 lo uCENstNvMSER lo lo 10 lo 25 10 2e l@l411lllllll@l uCENst TV,E J0 $7 I
CAT l@
se 7 uCENsetCCDE is CON'T lolil ,","c! l60 L l@l015 l010 10 l2 l8 1568 )@l 01910 l 51 81 O l@l RE, 74 75 019101818 ORT DATE do l O l@
7 3 61 OOCK ET NuMe Em 69 EVENT OA TE
, EVENT DESCRIPTION AND PROB A8LE CONSEQUENCES h
. l o ! 2, I During normal power operation, it was discovered by ooerator observation that the i t o ia; i Axial Power Distribution (APD) setpoints on 0 channel were out of tolerance in the i ioi4i i non-conservative direction. The other three channels were operable at the time and l lo isi i would have provided a necessary trip of the reactor if necessary. Technical l lo is i i Specification 1.3(8), Table 1.1, item 8, and Figure 1.2 aoplies. l l
l0i7l l l
l o la I I SE CYo'e' susCME COMPONENT COCE sus CD'E Su E
, ioisi LI I A l@ [Ej@ l Al@ l Il Nl S l Tl R l U l@ lS [@ lz l@ 18 19 20 4 9 10 11 ?2 13 g EVENTvtAA AE M NO QC T N .
@ sg,gea g noi 81 01 1-1 l24 0121 cl 1/1 10l3l lL l l-l l0l 21 22 23 26 27 28 29 30 31 32 K N AC 0 0 8 t.A N T wouRs 8 ,OR S. su clE VA u,AC RER IBl@lzl@ l zi@
22 2 25 las II@ l 0 l 010fd l 27 0 I Yl@
4, INi@
n INI@ lGl2l2l3l@
CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h
,, ioil During trouble shooting, it was discovered that wafer #6, contact #1 of the Flow i Dependent Setpoint Selection Switch, a Grayhill 42136-8-2-5N, was making poor contact l. l mi
,,,7i i This poor contact fed a 0% power indication into the APO calculator thus making the i i,,3i ] calculator calculate setpoints for 0% power. The switch was cleaned and returned l i,i,i i to service. i
'sTE7 s,owsm otwensT4rus @ 5'ssEoSSEv' OISCOVERY DESCRI, TION NA lAlgl Operator Observation li I5 I I E l@ ll 10 l0 i2l@lo
- l 45 .s s0 l
'aCnviry Co'#T Nr
. u isio .< u is. toc 2 nan c, ..u23. @
l 4 ouNrcP 2Cnvirv NA l @ l NA j IiIslIZld,Izl@ses
. ase~~.t u ,os
, w e..a
' til711010101@lrv,e l @lo:Cai,riS.@
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' ' ' , .scNNet'i~2u'4 s we
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'g o, og,1),.,cjio ,4Ciurv g NA FGTl I z'I@l
? 8 '9- 10 go l
i , i o i {1'h' "*" "O NA 8010 030'tf S i ii ""b i "b i lj 7 4 9 10 a 68 69 80 ;
N A.\tE OF PREPARER
- /
's' , HON E:
LER 80-020 Omaha Public Power District Fort Calhoun Station Unit No.1 Docket No. 05000285 ATTACHMENT NO. 1 Safety Analysis The Reactor Protection System uses a two-out-of-four to trip logic. One channel at a time may be bypassed, placing the system in a two-aut-of-three to trip logic. When the setpoint was found out of tolerance, the system was immediately placed in the two-aut-of-three logic mode. Therefore, the function of the R.P.S. was only slightly degraded as the other three channels were operable during this time and A, B and C channels had setpoints within tolerance. At no time would the R.P.S. have failed to perform its design functions, that is, to safely shutdown the reactor. See attachment 2 for further technical information.
V
\' )
N
LER 80-020 Omaha Public Power District Fort Calhoun Station Unit No.1 Docket No. 05000285 ATTACHMENT NO. 2 Corrective Action One of the inputs to the APD calculator is from the flow dependent setpoint selector switch. The switch is normally used in the 4-pump position only and is only moved out of that position to perform surveil-lanc.e on the RPS. The switch on "0" channe' was making poor contact on one contact which fed the APD calculator information that indicated the reactor was at the 0% power setpoints. The switch was cleaned by rotating several times through full travel and returned to 4-pump operation. The applicable portions of the APD surveillance test, ST-RPS-12, F.2, were performed to prove operability of the reactor pro-tective system. No further corrective action is anticipated.
1
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\:
e ,
LER 80-020 Omaha Public l'ower District-Fort Calhot.n Station Unit No.1 Docket No. U5000285 i
ATTACHMENT NO. 3 Failure Data This is the first occurrance of setpoints being out of tolerance due to a selector switch malfunction.
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