ML19305D735: Difference between revisions
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{{#Wiki_filter:__ _ _ . | {{#Wiki_filter:__ _ _ . | ||
NRC FORM 386 U. S. NUCLEAR REGULATORY COMMISSION | NRC FORM 386 U. S. NUCLEAR REGULATORY COMMISSION | ||
.wm - | .wm - | ||
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ITTil Ou% L_t_J@l0 i s DOCKET 1010NUMB 10 ER12 is l468l@l69 013EVENT I O DATE I 8 I 8 i 01@l74 75 01312 l s I 81080l@ | ITTil Ou% L_t_J@l0 i s DOCKET 1010NUMB 10 ER12 is l468l@l69 013EVENT I O DATE I 8 I 8 i 01@l74 75 01312 l s I 81080l@ | ||
REPORT DATE 7 8 60 61 , | REPORT DATE 7 8 60 61 , | ||
EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h ml While performing the Normal Control Poom inspection and Shift Turnover Panel Check. I ; | EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h ml While performing the Normal Control Poom inspection and Shift Turnover Panel Check. I ; | ||
i | i | ||
~ | ~ | ||
gl procedure QOS 005-2, the B main steam line radiation monitor was found to be reading l l | gl procedure QOS 005-2, the B main steam line radiation monitor was found to be reading l l | ||
; io ;4; l low. An instrument problem resulting in a lower than normal reading could cause the Bl o 3 l system to trip at a radiation level greater than those established by Technical I i | |||
; io ;4; l low. An instrument problem resulting in a lower than normal reading could cause the Bl | |||
o 3 l system to trip at a radiation level greater than those established by Technical I i | |||
g o is l l Specification 3 1. | g o is l l Specification 3 1. | ||
~ | ~ | ||
The reJandant A, C, and D main steam line monitors were operating i ! | The reJandant A, C, and D main steam line monitors were operating i ! | ||
~ | ~ | ||
Line 52: | Line 45: | ||
@ ll lN l S lT lR lU l@ jJ@ U @ | @ ll lN l S lT lR lU l@ jJ@ U @ | ||
13 18 9 20 | 13 18 9 20 | ||
,,, SEQUENTIAL OCCURRENCE REPORT REVISION | ,,, SEQUENTIAL OCCURRENCE REPORT REVISION LE R/RO EVENT YEAR REPORT NO. CODE TYPE N O. | ||
LE R/RO EVENT YEAR REPORT NO. CODE TYPE N O. | |||
@ ,REgg | @ ,REgg | ||
, l288l0l 22 g23 l 0l0l 7l 24 26 y | , l288l0l 22 g23 l 0l0l 7l 24 26 y | ||
Line 66: | Line 57: | ||
(_E_l @ l 0 l 9 1 6 l @ l NA l lAl@l Operational Event I! | (_E_l @ l 0 l 9 1 6 l @ l NA l lAl@l Operational Event I! | ||
A TIVITY CO TENT l AMOUNT OF ACTIVITY LOCATION OF RELEASE l 1 6 RELEASE | A TIVITY CO TENT l AMOUNT OF ACTIVITY LOCATION OF RELEASE l 1 6 RELEASE | ||
(,,_Z_j @D OP RELEASE NA [Z_j@l I l NA l | (,,_Z_j @D OP RELEASE NA [Z_j@l I l NA l PERSONNEL EXPOS ES NUM8ER TYPE DESCRIPTION i 7 I0l0l0l@lZl@l NA l PERSONNE L INJU IES NUMBER DETCRIPTION 7 | ||
PERSONNEL EXPOS ES NUM8ER TYPE DESCRIPTION | |||
i 7 | |||
i a 8 9 10l0l0l@l 11 12 NA 80 l | i a 8 9 10l0l0l@l 11 12 NA 80 l | ||
, LOSS OF OR DAMAGE TO FACILITY | , LOSS OF OR DAMAGE TO FACILITY | ||
! TYPE DESCRIPTION | ! TYPE DESCRIPTION | ||
]- W@l 7 8 9 10 NA 80 l | ]- W@l 7 8 9 10 NA 80 l | ||
D | D | ||
* 2 O ISSUEJ8l LN E CRIPTION NA q o pa y e: n g,,.h"'l'2 l lllllllllllll; | |||
2 O ISSUEJ8l LN E CRIPTION NA q o pa y e: n g,,.h"'l'2 l lllllllllllll; | |||
! 7 8 9 10 68 69 80 T. | ! 7 8 9 10 68 69 80 T. | ||
NAME OF PREPARER | NAME OF PREPARER PHONE: 3M6-2241 en.1% { | ||
: l. LER NUMBER: LER/R0 80-07/03L-0 ! | : l. LER NUMBER: LER/R0 80-07/03L-0 ! | ||
i | i | ||
: 11. LICENSEE NAME: Comnonweal th Edison Company Quad-Cities Nuclear Power Station Ill. FACILITY NAME: Unit One | : 11. LICENSEE NAME: Comnonweal th Edison Company Quad-Cities Nuclear Power Station Ill. FACILITY NAME: Unit One | ||
; | ; | ||
IV. DOCKET NUMBER: 050-254 | IV. DOCKET NUMBER: 050-254 V. EVENT DESCRIPTION: | ||
On March 8, 1980, while performing Procedure QOS 005-2, Normal Control Room inspection and Shif t Turnover Panel Check, the Unit One B main steam line radiation monitor was found to be reading low. The B main steam line radiation monitor. was , | On March 8, 1980, while performing Procedure QOS 005-2, Normal Control Room inspection and Shif t Turnover Panel Check, the Unit One B main steam line radiation monitor was found to be reading low. The B main steam line radiation monitor. was , | ||
reading about 50 millirem per hour while the A, C and D main steam line radiation monitors were reading about 100 millirem ; | reading about 50 millirem per hour while the A, C and D main steam line radiation monitors were reading about 100 millirem ; | ||
per hour. The low reading on the B main steam line radiation monitor was determined to be the result of the B logarithmic radiation monitor chassis being out of calibration. This ! | per hour. The low reading on the B main steam line radiation monitor was determined to be the result of the B logarithmic radiation monitor chassis being out of calibration. This ! | ||
would cause the B system to trip at a radiation level greater than or equal to seven times the background radiation level ; | would cause the B system to trip at a radiation level greater than or equal to seven times the background radiation level ; | ||
(Technical Specification 3.1, Table 3 1-3). ' | (Technical Specification 3.1, Table 3 1-3). ' | ||
VI. PROBABLE CONSEQUENCES OF THE OCCURRENCE: | VI. PROBABLE CONSEQUENCES OF THE OCCURRENCE: | ||
The safety implications of this event are minimal. The A, C 7 and D main steam line radiation monitoring systems were operational and would have provided the required trips on a high radiation level. | The safety implications of this event are minimal. The A, C 7 and D main steam line radiation monitoring systems were operational and would have provided the required trips on a high radiation level. | ||
Vll. CAUSE: | |||
The cause of this occurrence was equipment failure. The B logarithmic radiation monitor chassis electronically drif ted out of cailbration. The logarithmic radlaiton monitor chassis is a General Electric model 194X629G7 monitor, with a range of zero to one million millirem per hour. | The cause of this occurrence was equipment failure. The B logarithmic radiation monitor chassis electronically drif ted out of cailbration. The logarithmic radlaiton monitor chassis is a General Electric model 194X629G7 monitor, with a range of zero to one million millirem per hour. | ||
l Vill. CORRECTIVE ACTION: | l Vill. CORRECTIVE ACTION: | ||
An instrument mechanic was immediately called to recalibrate the B logarithmic radiation monitor chassis. Thc instrument mechanic calibrated and functionally tested the B logarithmic radiation monitor chassis in accordance with procedure QlS 31-1, Main Steam Line Radiation-Log Rad Monitor Chassis - S.T. - | An instrument mechanic was immediately called to recalibrate the B logarithmic radiation monitor chassis. Thc instrument mechanic calibrated and functionally tested the B logarithmic radiation monitor chassis in accordance with procedure QlS 31-1, Main Steam Line Radiation-Log Rad Monitor Chassis - S.T. - | ||
; 31A. No further corrective actions were deemed necessary-to | ; 31A. No further corrective actions were deemed necessary-to prevent recurrence. Surveillance procedure QOS 005-2 verified that the other logarithmic radiation monitor chassis were , | ||
prevent recurrence. Surveillance procedure QOS 005-2 verified that the other logarithmic radiation monitor chassis were , | |||
; | ; | ||
acceptable. | acceptable. | ||
d | d | ||
} | } | ||
.._}} | .._}} |
Revision as of 13:33, 1 February 2020
ML19305D735 | |
Person / Time | |
---|---|
Site: | Quad Cities |
Issue date: | 03/25/1980 |
From: | Wykoff D COMMONWEALTH EDISON CO. |
To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
Shared Package | |
ML19305D732 | List: |
References | |
LER-80-007-03L-02, LER-80-7-3L-2, NUDOCS 8004150467 | |
Download: ML19305D735 (2) | |
Text
__ _ _ .
NRC FORM 386 U. S. NUCLEAR REGULATORY COMMISSION
.wm -
LICENSEE EVENT REPORT.
CONTROL BLOCK: l l l l l l (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
- f' T'l l8 l9 I L LICENSEE 7 l a l ^CODE l o 11 J@15 01 01UCENSE 14 01 NUM8ER
-l01 0101-1010101@ 25 28 UCENSE 41111li11l@l TYPE JO I
57 CAT 58 l@
COwr -
ITTil Ou% L_t_J@l0 i s DOCKET 1010NUMB 10 ER12 is l468l@l69 013EVENT I O DATE I 8 I 8 i 01@l74 75 01312 l s I 81080l@
REPORT DATE 7 8 60 61 ,
EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h ml While performing the Normal Control Poom inspection and Shift Turnover Panel Check. I ;
i
~
gl procedure QOS 005-2, the B main steam line radiation monitor was found to be reading l l
- io ;4; l low. An instrument problem resulting in a lower than normal reading could cause the Bl o 3 l system to trip at a radiation level greater than those established by Technical I i
g o is l l Specification 3 1.
~
The reJandant A, C, and D main steam line monitors were operating i !
~
fB T- I l normally and would have provided the required high radiation level setpoint trip l lO la l I functions. l ,
7 8 9 80 0E OE SU C E COMPONENT CODE SUSCodE SU E 7
O 9 8
ll lB l@
9 to 11
@ 12
@ ll lN l S lT lR lU l@ jJ@ U @
13 18 9 20
,,, SEQUENTIAL OCCURRENCE REPORT REVISION LE R/RO EVENT YEAR REPORT NO. CODE TYPE N O.
@ ,REgg
, l288l0l 22 g23 l 0l0l 7l 24 26 y
27 l0 l3 l 28 29
[Lj 30 ,
l-l 31
]32 j
f N AC ON O NT ME HOURS 22 SS I FOR B. SU Lt MANUFA RER l Elgl34Zlg Jg 33 35 W@
36 l0l0l0l0l 37 lYl@ ]g 41 lN l@ lG l0 l8 l0 l 40 - 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h l i l 0 l l The B logarithmic radiation monitor chassis electronically drif ted out of l ,
, gl calibration, lhe instrument chassis was recalibrated and functionally tested I ii l 2 I l satisfactorily. ll l 11131 I l Lt l.,4 ] I l l 7 8 9 80 STA % POWER OTHER STATUS 01 O Y DISCOVERY DESCRIPTION l t 5
(_E_l @ l 0 l 9 1 6 l @ l NA l lAl@l Operational Event I!
A TIVITY CO TENT l AMOUNT OF ACTIVITY LOCATION OF RELEASE l 1 6 RELEASE
(,,_Z_j @D OP RELEASE NA [Z_j@l I l NA l PERSONNEL EXPOS ES NUM8ER TYPE DESCRIPTION i 7 I0l0l0l@lZl@l NA l PERSONNE L INJU IES NUMBER DETCRIPTION 7
i a 8 9 10l0l0l@l 11 12 NA 80 l
, LOSS OF OR DAMAGE TO FACILITY
! TYPE DESCRIPTION
]- W@l 7 8 9 10 NA 80 l
D
- 2 O ISSUEJ8l LN E CRIPTION NA q o pa y e: n g,,.h"'l'2 l lllllllllllll;
! 7 8 9 10 68 69 80 T.
NAME OF PREPARER PHONE: 3M6-2241 en.1% {
- l. LER NUMBER: LER/R0 80-07/03L-0 !
i
- 11. LICENSEE NAME: Comnonweal th Edison Company Quad-Cities Nuclear Power Station Ill. FACILITY NAME: Unit One
IV. DOCKET NUMBER: 050-254 V. EVENT DESCRIPTION:
On March 8, 1980, while performing Procedure QOS 005-2, Normal Control Room inspection and Shif t Turnover Panel Check, the Unit One B main steam line radiation monitor was found to be reading low. The B main steam line radiation monitor. was ,
reading about 50 millirem per hour while the A, C and D main steam line radiation monitors were reading about 100 millirem ;
per hour. The low reading on the B main steam line radiation monitor was determined to be the result of the B logarithmic radiation monitor chassis being out of calibration. This !
would cause the B system to trip at a radiation level greater than or equal to seven times the background radiation level ;
(Technical Specification 3.1, Table 3 1-3). '
VI. PROBABLE CONSEQUENCES OF THE OCCURRENCE:
The safety implications of this event are minimal. The A, C 7 and D main steam line radiation monitoring systems were operational and would have provided the required trips on a high radiation level.
Vll. CAUSE:
The cause of this occurrence was equipment failure. The B logarithmic radiation monitor chassis electronically drif ted out of cailbration. The logarithmic radlaiton monitor chassis is a General Electric model 194X629G7 monitor, with a range of zero to one million millirem per hour.
l Vill. CORRECTIVE ACTION:
An instrument mechanic was immediately called to recalibrate the B logarithmic radiation monitor chassis. Thc instrument mechanic calibrated and functionally tested the B logarithmic radiation monitor chassis in accordance with procedure QlS 31-1, Main Steam Line Radiation-Log Rad Monitor Chassis - S.T. -
- 31A. No further corrective actions were deemed necessary-to prevent recurrence. Surveillance procedure QOS 005-2 verified that the other logarithmic radiation monitor chassis were ,
acceptable.
d
}
.._