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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
}
                                      .._}}

Latest revision as of 23:49, 21 February 2020

LER 80-007/03L-0:on 800308,while Performing Control Room Insp & Panel Check,B Main Steam Line Radiation Monitor Found Reading Low.Caused by Logarithmic Radiation Monitor Chassis Electronically Drifting Out of Calibr.Chassis Recalibr
ML19305D735
Person / Time
Site: Quad Cities Constellation icon.png
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

}

.._