ML19329F930: Difference between revisions
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{{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMiy53ON NRCFORM3h5 O 7.77) | {{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMiy53ON NRCFORM3h5 O 7.77) | ||
LICENSEE EVENT P.EPORT Q .1 CO?.*nOLSLOCK.l l l l l l l (PLEASE KINT OR TYTE ALL REQUIRED INPO%MATION) 1 6 lo t l I Ni ai o f c ! Pl 1 lhl 01 O I - l 0LICENSE i I | LICENSEE EVENT P.EPORT Q .1 CO?.*nOLSLOCK.l l l l l l l (PLEASE KINT OR TYTE ALL REQUIRED INPO%MATION) 1 6 lo t l I Ni ai o f c ! Pl 1 lhl 01 O I - l 0LICENSE i I 8 2 LICENSEE CC35 14 :S l 0 l n l NUMSER 01 n ! - l n25 l n26lhl LACENSE 4 l 1 1 1 TYPE 1 40 I I 57l'h'C-T 68 @ | ||
8 2 LICENSEE CC35 14 :S l 0 l n l NUMSER 01 n ! - l n25 l n26lhl LACENSE 4 l 1 1 1 TYPE 1 40 I I 57l'h'C-T 68 @ | |||
' ~" | ' ~" | ||
CON T | CON T | ||
- Folil : Z,"c' F L }@l 01 5101010 l 21 I l 91@l o l 6 l 01318101@l75 017REPORT 74 l n iDATEi l A l n80 l@ | - Folil : Z,"c' F L }@l 01 5101010 l 21 I l 91@l o l 6 l 01318101@l75 017REPORT 74 l n iDATEi l A l n80 l@ | ||
7 8 63 61 DOCK ET NUM8 ER 68 69 EVENT CATE EVEN f OGSCRIPTION AND PROSABLE CONS 50UENCES h e.n- I | 7 8 63 61 DOCK ET NUM8 ER 68 69 EVENT CATE EVEN f OGSCRIPTION AND PROSABLE CONS 50UENCES h e.n- I | ||
--t c 1 :1 F --On -June 3.1980. while cerformino the isn12tinn ennaancer Anenmaetr | --t c 1 :1 F --On -June 3.1980. while cerformino the isn12tinn ennaancer Anenmaetr t o i 3 i -l- - -sor Calibration and Test, the trio coints of 1 of the 4 reactne hinh l i | ||
t o i 3 i -l- - -sor Calibration and Test, the trio coints of 1 of the 4 reactne hinh l i | |||
pressure isolation cencenser initiation switches were fnund en ha face -- - - 1 lo l4i I | pressure isolation cencenser initiation switches were fnund en ha face -- - - 1 lo l4i I | ||
- d o I &i+- conservative than that specified in T.S.2.3.9. Pressure switch RF-1RA I 1 | - d o I &i+- conservative than that specified in T.S.2.3.9. Pressure switch RF-1RA I 1 | ||
- -i c i e s i which had the, laroest discrenancv. was fnund en *rin ne inAR neig in- ! | - -i c i e s i which had the, laroest discrenancv. was fnund en *rin ne inAR neig in- ! | ||
I O f 7. I stead of 1068 osia as desired. The saferv sinnificanca af the avaer te I I | I O f 7. I stead of 1068 osia as desired. The saferv sinnificanca af the avaer te I I | ||
I o !s I Considered minimal. to | I o !s I Considered minimal. to sa sy:TEV CAUSE COMP. VALVE CAUSE 000; C00E SUSC002 00?/ PONE";* 0005 $UE0001 SUSCOCE loisi i si Ol@ l xi@ W@ it IN is IT IR IU lh [1)h [Zj h 3 10 12 12 18 19 20 4 11 S EQU E NTI AL QCCUPAENCE REPCRT ' tVisl0N 4 | ||
sa sy:TEV CAUSE COMP. VALVE CAUSE 000; C00E SUSC002 00?/ PONE";* 0005 $UE0001 SUSCOCE loisi | |||
EVENTvuR R EPORT NC. C00E TYPE NO. | EVENTvuR R EPORT NC. C00E TYPE NO. | ||
n wEs ao G ;5t.i;; I 81 0122 l-l lo 12121 1/1 1 01 i! Ltj I-I L.q) 32 21 23 24 26 27 23 29 20 31 ACT'ON Pi.' f u n g EssECT SMUTOOWN ATTACMMENT NPRO.4 PRIME COMP. COMPCNENT TAKEN ACTICN CN PLANT METHOO MOUR$ 22 $USMITTED PORM bus. SUP8 LIER MANUPACTURER IEl@lZl@ IZl@ | n wEs ao G ;5t.i;; I 81 0122 l-l lo 12121 1/1 1 01 i! Ltj I-I L.q) 32 21 23 24 26 27 23 29 20 31 ACT'ON Pi.' f u n g EssECT SMUTOOWN ATTACMMENT NPRO.4 PRIME COMP. COMPCNENT TAKEN ACTICN CN PLANT METHOO MOUR$ 22 $USMITTED PORM bus. SUP8 LIER MANUPACTURER IEl@lZl@ IZl@ | ||
| Line 45: | Line 38: | ||
-11 til I ition in that the instruments had effectivalv haan noe nf caruiro in s | -11 til I ition in that the instruments had effectivalv haan noe nf caruiro in s | ||
- I i i 21 ] relaxed condition for about 6 months. The cmrectiva actinn wac en ra- I | - I i i 21 ] relaxed condition for about 6 months. The cmrectiva actinn wac en ra- I | ||
-liistI set the cressure switches to the desired spennine and avarrica the l it 14 I I switches to ensure ornner nneratinn. l 7 8 9 80 ST S % PCWER OTHER $7ATUS Dis RY OlSCOVERY DESCRIPTics l | |||
-liistI set the cressure switches to the desired spennine and avarrica the l it 14 I I | __. l t l 5 l l H lh l 01 01' 0lhl" NA l d hl '' | ||
switches to ensure ornner nneratinn. l 7 8 9 80 ST S % PCWER OTHER $7ATUS Dis RY OlSCOVERY DESCRIPTics l | |||
__. l t l 5 l l H lh l 01 01' 0lhl" | |||
NA | |||
l d hl '' | |||
Sneveillance Test | Sneveillance Test | ||
' ACTiv Tv CO$ TENT RELEAsss CP RELEAst LOCATION CP RELEASE ltl6l j h d hl AMcVNT NA OF ACTIVITY l 45 hl NA ao l | ' ACTiv Tv CO$ TENT RELEAsss CP RELEAst LOCATION CP RELEASE ltl6l j h d hl AMcVNT NA OF ACTIVITY l 45 hl NA ao l | ||
r a e 10 :: 44 | r a e 10 :: 44 | ||
| Line 64: | Line 48: | ||
: 30. ; | : 30. ; | ||
Donald A. Ross 201-499-8784 NAME OF SoE8ARGn PwCNE: { | Donald A. Ross 201-499-8784 NAME OF SoE8ARGn PwCNE: { | ||
sco722o % 3 | sco722o % 3 | ||
yf Jersey Central Power & Light Company | |||
Jersey Central Power & Light Company | |||
'r | 'r | ||
.N (4" () Madison Avenue at Pumh Bowl Road Mornstown, New Jersey 07960 (201)455-8200 OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/80-22/3L Report Date July 1, 1980 Date of Occurrence June 3, 1980 identification of Occurrence Reactor high pressure isolation condenser initiation pressure switches RE-ISA, RE-ISB and RE-15C tripped at a value greater than that specified in the Technical Specifications, Section 2.3.5 This event is considered to be a recortable occurrence as defined in the Technical Specifications, paragraph 6.9.2.b. (1) . | .N (4" () Madison Avenue at Pumh Bowl Road Mornstown, New Jersey 07960 (201)455-8200 OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/80-22/3L Report Date July 1, 1980 Date of Occurrence June 3, 1980 identification of Occurrence Reactor high pressure isolation condenser initiation pressure switches RE-ISA, RE-ISB and RE-15C tripped at a value greater than that specified in the Technical Specifications, Section 2.3.5 This event is considered to be a recortable occurrence as defined in the Technical Specifications, paragraph 6.9.2.b. (1) . | ||
Conditions Prior to Occurrence Reactor coolant temperature 157.l*F Mode switch in refuel | Conditions Prior to Occurrence Reactor coolant temperature 157.l*F Mode switch in refuel | ||
| Line 76: | Line 57: | ||
the RE-15A, RE-158 and RE-15C trip points were found to be less conser-vative than that specified in the Technical Specifications. Surveillance test on the high reactor pressure switches for the isolation condenser system revealed the following data: | the RE-15A, RE-158 and RE-15C trip points were found to be less conser-vative than that specified in the Technical Specifications. Surveillance test on the high reactor pressure switches for the isolation condenser system revealed the following data: | ||
Pressure Switch Desired Setpoint Designation (Head Correction included) As Found As Left RE-15A 1068 1088 1066 RE-158 1068 1081 1068 RE-15C 1066 1077 1064 RE-150 1066 1066 1066 Jersey Central Power & Ught Company is a Member of the General Public UtMties System | Pressure Switch Desired Setpoint Designation (Head Correction included) As Found As Left RE-15A 1068 1088 1066 RE-158 1068 1081 1068 RE-15C 1066 1077 1064 RE-150 1066 1066 1066 Jersey Central Power & Ught Company is a Member of the General Public UtMties System | ||
+t | +t | ||
,=l' Reportable Occurrence No. 50-219/80-22/3L Page 2 July 1, 1990 Apparent Cause of Occurrence The cause of the occurrence can be attrituted to unusual service condition in that the instruments had effectively been out of service for approxi-mately 6 months. The instruments were last tested and calibrated on December 12, 1979 and were found to be operating properly. They had not been tested since the plant was shutdown on January 5, 1980; The instru-ments have been in a relaxed condition since then; except during the hydro-static test of the reactor pressure vessel (performed only 3 days before the test of the pressure switches), i t is noted that the instrument was operating within its design accuracy. | ,=l' Reportable Occurrence No. 50-219/80-22/3L Page 2 July 1, 1990 Apparent Cause of Occurrence The cause of the occurrence can be attrituted to unusual service condition in that the instruments had effectively been out of service for approxi-mately 6 months. The instruments were last tested and calibrated on December 12, 1979 and were found to be operating properly. They had not been tested since the plant was shutdown on January 5, 1980; The instru-ments have been in a relaxed condition since then; except during the hydro-static test of the reactor pressure vessel (performed only 3 days before the test of the pressure switches), i t is noted that the instrument was operating within its design accuracy. | ||
Analysis of Occurrence The safety significance of this event is considered minimal since the pres-sure switches would have actuated but at a higher setpoint. It should also be noted'that the pressure switches would not see this type of service condition during normal plant operation. | Analysis of Occurrence The safety significance of this event is considered minimal since the pres-sure switches would have actuated but at a higher setpoint. It should also be noted'that the pressure switches would not see this type of service condition during normal plant operation. | ||
Corrective Action immediate corrective action was to reset the pressure switches to the desired setpoint and exercise the switches to insure proper operation. No further action is contemplated. | Corrective Action immediate corrective action was to reset the pressure switches to the desired setpoint and exercise the switches to insure proper operation. No further action is contemplated. | ||
Failure Data Barksdale Switch #82T A12SS Proof 1800 psi Adjustable range.50-J200 psi | Failure Data Barksdale Switch #82T A12SS Proof 1800 psi Adjustable range.50-J200 psi N | ||
O}} | |||
Latest revision as of 20:03, 31 January 2020
| ML19329F930 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 07/01/1980 |
| From: | Ross D JERSEY CENTRAL POWER & LIGHT CO. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML19329F927 | List: |
| References | |
| LER-80-022-03L, LER-80-22-3L, NUDOCS 8007110373 | |
| Download: ML19329F930 (3) | |
Text
U.S. NUCLEAR REGULATORY COMMiy53ON NRCFORM3h5 O 7.77)
LICENSEE EVENT P.EPORT Q .1 CO?.*nOLSLOCK.l l l l l l l (PLEASE KINT OR TYTE ALL REQUIRED INPO%MATION) 1 6 lo t l I Ni ai o f c ! Pl 1 lhl 01 O I - l 0LICENSE i I 8 2 LICENSEE CC35 14 :S l 0 l n l NUMSER 01 n ! - l n25 l n26lhl LACENSE 4 l 1 1 1 TYPE 1 40 I I 57l'h'C-T 68 @
' ~"
CON T
- Folil : Z,"c' F L }@l 01 5101010 l 21 I l 91@l o l 6 l 01318101@l75 017REPORT 74 l n iDATEi l A l n80 l@
7 8 63 61 DOCK ET NUM8 ER 68 69 EVENT CATE EVEN f OGSCRIPTION AND PROSABLE CONS 50UENCES h e.n- I
--t c 1 :1 F --On -June 3.1980. while cerformino the isn12tinn ennaancer Anenmaetr t o i 3 i -l- - -sor Calibration and Test, the trio coints of 1 of the 4 reactne hinh l i
pressure isolation cencenser initiation switches were fnund en ha face -- - - 1 lo l4i I
- d o I &i+- conservative than that specified in T.S.2.3.9. Pressure switch RF-1RA I 1
- -i c i e s i which had the, laroest discrenancv. was fnund en *rin ne inAR neig in- !
I O f 7. I stead of 1068 osia as desired. The saferv sinnificanca af the avaer te I I
I o !s I Considered minimal. to sa sy:TEV CAUSE COMP. VALVE CAUSE 000; C00E SUSC002 00?/ PONE";* 0005 $UE0001 SUSCOCE loisi i si Ol@ l xi@ W@ it IN is IT IR IU lh [1)h [Zj h 3 10 12 12 18 19 20 4 11 S EQU E NTI AL QCCUPAENCE REPCRT ' tVisl0N 4
EVENTvuR R EPORT NC. C00E TYPE NO.
n wEs ao G ;5t.i;; I 81 0122 l-l lo 12121 1/1 1 01 i! Ltj I-I L.q) 32 21 23 24 26 27 23 29 20 31 ACT'ON Pi.' f u n g EssECT SMUTOOWN ATTACMMENT NPRO.4 PRIME COMP. COMPCNENT TAKEN ACTICN CN PLANT METHOO MOUR$ 22 $USMITTED PORM bus. SUP8 LIER MANUPACTURER IEl@lZl@ IZl@
.. 34 4, l26Z l@ l010101Ol 37 40 lYl@
et l42Nl@ l43Nl@ IBl0l6l9!@
44 47 CAUSE CESCRl8TICN AND CORRECTIVE ACTIONS @
-~
liiol l The cause of this occurrence can be attrihnted en nnnenal carvica e n n a -- --- - I I
-11 til I ition in that the instruments had effectivalv haan noe nf caruiro in s
- I i i 21 ] relaxed condition for about 6 months. The cmrectiva actinn wac en ra- I
-liistI set the cressure switches to the desired spennine and avarrica the l it 14 I I switches to ensure ornner nneratinn. l 7 8 9 80 ST S % PCWER OTHER $7ATUS Dis RY OlSCOVERY DESCRIPTics l
__. l t l 5 l l H lh l 01 01' 0lhl" NA l d hl
Sneveillance Test
' ACTiv Tv CO$ TENT RELEAsss CP RELEAst LOCATION CP RELEASE ltl6l j h d hl AMcVNT NA OF ACTIVITY l 45 hl NA ao l
r a e 10 :: 44
- ERSONNEL EMPOSURES NUus E .a CESCRIPTION l 8 l 71 l Ol O l O lh[TYPEjhl ,_Z NA l P1850NNEL INJU E3 w MeER DESCRIPTION NA l l1 l *4 l l O l 01 O lhl12 30 7 8 9 11 LC1108 CR OAVAGE TO PAC'Ltiv Typt CESCRtPTION Ill91 d hi 7 e s to NA gC l
"?l,"CR,PT,0,. @ ~ac use o~'v .
,,,UE I ? I '2 l s a 's hl to Umak1v News oplance l CB 69 lllllIIIll lII$
- 30. ;
Donald A. Ross 201-499-8784 NAME OF SoE8ARGn PwCNE: {
sco722o % 3
yf Jersey Central Power & Light Company
'r
.N (4" () Madison Avenue at Pumh Bowl Road Mornstown, New Jersey 07960 (201)455-8200 OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/80-22/3L Report Date July 1, 1980 Date of Occurrence June 3, 1980 identification of Occurrence Reactor high pressure isolation condenser initiation pressure switches RE-ISA, RE-ISB and RE-15C tripped at a value greater than that specified in the Technical Specifications, Section 2.3.5 This event is considered to be a recortable occurrence as defined in the Technical Specifications, paragraph 6.9.2.b. (1) .
Conditions Prior to Occurrence Reactor coolant temperature 157.l*F Mode switch in refuel
. Reactor water level 170" All control rods at '00' Source range monitor ~25 cps Description of Occurrence On Tuesday, June 3,1980, at approximately 1000 bcurs, while performing the "Isolat*on Condenser Automatic Actuation Sensor Calibration and Test",
the RE-15A, RE-158 and RE-15C trip points were found to be less conser-vative than that specified in the Technical Specifications. Surveillance test on the high reactor pressure switches for the isolation condenser system revealed the following data:
Pressure Switch Desired Setpoint Designation (Head Correction included) As Found As Left RE-15A 1068 1088 1066 RE-158 1068 1081 1068 RE-15C 1066 1077 1064 RE-150 1066 1066 1066 Jersey Central Power & Ught Company is a Member of the General Public UtMties System
+t
,=l' Reportable Occurrence No. 50-219/80-22/3L Page 2 July 1, 1990 Apparent Cause of Occurrence The cause of the occurrence can be attrituted to unusual service condition in that the instruments had effectively been out of service for approxi-mately 6 months. The instruments were last tested and calibrated on December 12, 1979 and were found to be operating properly. They had not been tested since the plant was shutdown on January 5, 1980; The instru-ments have been in a relaxed condition since then; except during the hydro-static test of the reactor pressure vessel (performed only 3 days before the test of the pressure switches), i t is noted that the instrument was operating within its design accuracy.
Analysis of Occurrence The safety significance of this event is considered minimal since the pres-sure switches would have actuated but at a higher setpoint. It should also be noted'that the pressure switches would not see this type of service condition during normal plant operation.
Corrective Action immediate corrective action was to reset the pressure switches to the desired setpoint and exercise the switches to insure proper operation. No further action is contemplated.
Failure Data Barksdale Switch #82T A12SS Proof 1800 psi Adjustable range.50-J200 psi N
O