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| issue date = 06/13/1980
| issue date = 06/13/1980
| title = LER 80-024/03L-0 for Dresden Unit 3 Regarding During Normal Operation with Reactor Level Instrument Surveillance in Progress, Level Switch LIS 3-263-58AB Tripped at Less than Tech. Spec. Limit of 84 Inches
| title = LER 80-024/03L-0 for Dresden Unit 3 Regarding During Normal Operation with Reactor Level Instrument Surveillance in Progress, Level Switch LIS 3-263-58AB Tripped at Less than Tech. Spec. Limit of 84 Inches
| author name = Stephenson B B
| author name = Stephenson B
| author affiliation = Commonwealth Edison Co
| author affiliation = Commonwealth Edison Co
| addressee name = Keppler J G
| addressee name = Keppler J
| addressee affiliation = NRC/RGN-III
| addressee affiliation = NRC/RGN-III
| docket = 05000237, 05000249
| docket = 05000237, 05000249
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:Commonwe.Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 BBS LTR. /180-507 June 13, 1980 James G. Keppler, Regional Director Directorate of Regulatory Operatfop.s  
{{#Wiki_filter:Commonwe.Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920
-Region III Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137
* WN l 8 1980 June 13, 1980 BBS LTR. /180-507 James G. Keppler, Regional Director Directorate of Regulatory Operatfop.s - Region III U~S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL         60137 Reportable Occurrence Report iJ 8Q..:.24/03L..:.Q- ~Dock.e.t JI 050-249 , is being submitted to your office in acco:r;dance with Dresden Nuclear Power Station Technical Specification 6.6~B.2(a), reactor protection system or engineered safety feature instrument settings which are found to be less conservative::::
* WN l 8 1980 Reportable Occurrence Report iJ 8Q..:.24/03L..:.Q-JI 050-249 , is being submitted to your office in acco:r;dance with Dresden Nuclear Power Station Technical Specification reactor protection system or engineered safety feature instrument settings which are found to be less conservative::::
than those established by the Technical Specifications but which do not pre':'<;~-..t vent the fulfillment of the functional requirements of.affected systems.
than those established by the Technical Specifications but which do not vent the fulfillment of the functional requirements of.affected systems.
                                        ~~\=)~Ji--
BBS:
B.B. Stephenson   .
B.B. Stephenson  
Station Superintendent
. Station Superintendent  
                                        .presden Nuclear Power Station BBS:
.presden Nuclear Power Station Enclosure cc: Director of Inspection  
Enclosure cc: Director of Inspection & E.nfor.cement Director of Management Information & Program Control File/NRC
& E.nfor.cement Director of Management Information  
 
& Program Control File/NRC 11.n1 ***--,. LICENSEE EVENT REPORT ?._. :*'C\J"TROL BLOCK: .___,._l_.....___..
11.n1 LICENSEE EVENT REPORT
_ _.1_!_...._-'J 0 !PLEASE PRINT OR TYPE'L REQUIREO lNFORMATIONI ro-rna I I I L I D IR Is I 3 IG)I 0 I 0 I -I 0 I 0 I O: I 0 I 0 1-. I 0 I 0 1(2)14 11 11 11 11 101 I I &#xa9; 9 . LICENSEE.
        ?._.   :*'C\J"TROL BLOCK:           .___,._l_.....___.._ _.1_!_...._-'J 0                               !PLEASE PRINT OR TYPE'L REQUIREO lNFORMATIONI ro-rna         I I I L I D IR Is I 3 IG)I                           0   I 0 I - I 0 I 0 I O: I 0 I 0                           I0 I 0   1(2)1 4      11     11   11   11             I I&#xa9; 1-.                                                  101
CODE,
~              9     . LICENSEE. CODE,
* 14 . 15 LICENSE NUMBER 25 26 . LICENSE.
* 14   . 15                           LICENSE NUMBER                             25       26     . LICENSE. TYPE       JO. 57 CAT 5B CON~T
TYPE JO. 57 CAT 5B J --**
;~rl J               :;~~~;      L.U&#xa9;I             01 5       Io I o I o 1~2 I 41                   9   IGI o*         I~ 11 J 9_ 18           Io IG)I or           6 I 1 I o I 8 I o IG) 60           61                 DOCKET NUMBER                         08     69           EVENT DATE             74       75   . REPORT DATE           80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES                                           (iQ\
L.U&#xa9;I 01 5 Io I o I o I 41 9 IGI o* 11 J 9_ 18 Io IG)I or 6 I 1 I o I 8 I o I G) 60 61 DOCKET NUMBER 08 69 EVENT DATE 74 75 . REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES (iQ\ I During normal operation,*
I During normal operation,* with reactor'-ievel instrument surveillance in progress, level 0
with reactor'-ievel instrument surveillance in progress, level ; 0 13 I I switch LIS 3-263-58B tripped at less than the* Tech.
1 3
limit (Table 3.2.1) of 84 I 0 141. I inches. The safety significance of this event was minimal since channel "A" and the )a Is I I redundant Channel "B" instruments were operable.
I   I switch LIS 3-263-58B tripped at less than the* Tech. Spec~ limit (Table 3.2.1) of 84 I0    14 1. I inches.                 The safety significance of this event was minimal since channel "A" and the
There was no effect on public health J 0 lo I I or safety. Previous occurrences.:
)a Is I I redundant                   Channel "B" instruments were operable.                                                       There was no effect on public health J
R.O. 76-57/031-0,.
0 lo I I or         safety.             Previous occurrences.: R.O. 76-57/031-0,. Docket 50-237; 77....,51/031-0 and 80-23/031-0, Docket 50-249.
Docket 50-237; 77....,51/031-0 and 80-23/031-0, Docket 50-249. 80. SYSTEM CODE I I IB I@ 9 10 G\ LEA/RO YEAR "V REPORT I 8 I 0 I NUMBER 21 . 22 ACTION . FUTURE TAKEN ACTION EFFECT ON PLANT CAUSE CAUSE COMP. VALVE CODE SUBCODE COMPONENT CODE SUBCODE
80.
* SUSCODE 11IN1s1T IR 1u I@ L:J@} L:J@ 11 12 13 L=J 23 SHUTDOWN METHOD SEQUENTIAL*
SYSTEM                   CAUSE               CAUSE                                                               COMP.           VALVE CODE                   CODE              SUBCODE                     COMPONENT CODE                         SUBCODE
REPORT NO. I 0 I 2 I 4 I 24" 26. HOURS 18 OCCURRENCE CODE 1.......-1 10 13 27 28 29 19 20 REPORT TYPE 30 31 NPRD-4 FORM ::;us. PRIME COMP: SUPPLIER
* SUSCODE I I IB I@ ~@~@ 11IN1s1T IR 1u I@ L:J@} L:J@
* REVISION NO. 32 COMPONENT MANUFACTUR.E L:J@ L!J I o I o. I o ATTACHMENT SUBMITTED I Ll@ ll:l y 0 1 .o 33 34 . 35 36 3 7 40 41 42 43 44 CAUSE DESCRIPTION AND.CORRECTIVE ACTIONS @ j 1 lo I I The cause of this event is.unknown at this time. The was immediately re-: , I 1 I : 1 I 2 I tested, with satisfactory results.
9            10              11                 12                 13                                   18          19              20 SEQUENTIAL*                                 OCCURRENCE            REPORT                      REVISION G\      LEA/RO    c~VENT YEAR                                          REPORT NO.                                     CODE                  TYPE                        NO.
Subsequent tests were performed, and each time the results were satisfactory.
              "V    REPORT NUMBER I 8 I. 0 I                 L=J                  I 0 I2 I4 I                 1.......-1         10 13                   ~                            ~
DIS* 500-2 will continue to* be done monthly.
21          22            23                  24"              26.      27                 28         29           30             31           32 ACTION . FUTURE                  EFFECT I o I o. I o ~
47 I I :=IIIJ *---------------------------------------------------8 9 FACILITY f:i(j\ METHOD OF STATUS % POWER OTHFR STATUS . DISCOVERY DISCOVERY DESCRIPTION  
SHUTDOWN                                                ATTACHMENT            NPRD-4         PRIME COMP:            COMPONENT TAKEN      ACTION            ON PLANT                  METHOD                        HOURS                  SUBMITTED        FORM ::;us.       SUPPLIER
@ , Instrument Mechanic Surveillance so 1&deg; 18 14 l@I NtA
* MANUFACTUR.E l!J@L~J@
* I L!J@I *a 9 10 12 45 ""46-*
33          34    .
ACTIVITY CONTENT OF RELEASC:  
L:J@
..>.MOUNT OF ACTIVITY L2J@ N/A ' . I 8. 9 10 11 . 44 PERSONNEL EXPOSURES  
35 L!J 36                  37 I 40I~@        41 Ll@ ll:l                           y   0   1 .o 42                 43             44               47 CAUSE DESCRIPTION AND.CORRECTIVE ACTIONS @
*(.;";;\
j 1 lo I I The           cause of this event is.unknown at this time.                                                             The   inst~ument              was immediately re-tested, with satisfactory results.                                                 Subsequent tests were performed, and each time the
NUMBER DESCRIPTION m 1&deg; 1&deg; 1&deg; 1021L:J 8 9 11 12
: , I1 I                                                                                                                                                                                                I
?ERSONNEL INJURIES f,;:;\ N/A LOCATION*OF RELEASE @. 45 80 N/A NUMBER DESCRIPTIONa  
                                                                                                                                                                                                      ~
/ 10 10 jO l@I NA a 9 11 LOSS OF OR DAMAGE TO FACILITY t4J\ TYPE. DESCRIPTION I v::::J zw* L:J@ . . N A 8 9 10 PUBLICITY f:::'\ ISSUEDf,;":;\  
results were satisfactory.                                       DIS* 500-2 will continue to* be done monthly.
:IITJ* LJLl6 N A 8 9 10 . P. Holland 80 NRC USE ONLY *Q I "' I I I I I I I I I I I I 68 69 30.;; X-523}}
: 1  I2 I                                                                                                                                                                                               I
:=IIIJ *---------------------------------------------------
~8             9                                                                                                                                                                                     so FACILITY                                                                         f:i(j\       METHOD OF STATUS               % POWER                             OTHFR STATUS         ~        . DISCOVERY                                   DISCOVERY DESCRIPTION         @        ,
~ ~@ 1&deg; 1 8 14                                     l@I~n---------44_. NtA
* I       L!J@I               Instrument Mechanic Surveillance
    *a       9               10               12                                                         45             ""-*.----'------------------~so 46 ACTIVITY         CONTENT                                                         ~
~RELEASED                  OF RELEASC:                     ..>.MOUNT OF ACTIVITY             ~                                                        LOCATION*OF RELEASE        @.
~ L2J@ ~I                                        N/A             '                     .           I                                 N/A
: 8. 9               10           11           .                                           44           45                                                                                80 PERSONNEL EXPOSURES                                     *(.;";;\
m       8 1&deg; 9
NUMBER        ~TYPE 12 DESCRIPTION ~
1&deg; 1&deg; 111021L:J1~3---------------------~-~-------------8--'0
                    ?ERSONNEL INJURIES                     f,;:;\
N/A NUMBER               DESCRIPTIONa
~ 10 10                     jO   l@I                             NA /                                                                                                                              ~
a     9                 11     .~12:-------------------------~------------~---~
t4J\
zw* L:J@ .
LOSS OF OR DAMAGE TO FACILITY TYPE.       DESCRIPTION               I     v::::J
                                    .             N A 8     9           10                                                                                                                                                                       80 PUBLICITY               f:::'\                                                                                                                             NRC USE ONLY ISSUEDf,;":;\ DESCRIPTION~*                                                                                                                                                                  *Q
:IITJ* LJLl6 8     9           10 N A 68 I I I I I I I I I I I I I "'~
69                         30.;;
                                                                                . P. Holland                                                                            X-523}}

Latest revision as of 07:40, 24 February 2020

LER 80-024/03L-0 for Dresden Unit 3 Regarding During Normal Operation with Reactor Level Instrument Surveillance in Progress, Level Switch LIS 3-263-58AB Tripped at Less than Tech. Spec. Limit of 84 Inches
ML17252B191
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 06/13/1980
From: Stephenson B
Commonwealth Edison Co
To: James Keppler
NRC/RGN-III
References
BBS LTR. #80-507 LER 80-024/03L-0
Download: ML17252B191 (2)
v • d • e


Text

Commonwe.Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920

  • WN l 8 1980 June 13, 1980 BBS LTR. /180-507 James G. Keppler, Regional Director Directorate of Regulatory Operatfop.s - Region III U~S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 Reportable Occurrence Report iJ 8Q..:.24/03L..:.Q- ~Dock.e.t JI 050-249 , is being submitted to your office in acco:r;dance with Dresden Nuclear Power Station Technical Specification 6.6~B.2(a), reactor protection system or engineered safety feature instrument settings which are found to be less conservative::::

than those established by the Technical Specifications but which do not pre':'<;~-..t vent the fulfillment of the functional requirements of.affected systems.

~~\=)~Ji--

B.B. Stephenson .

Station Superintendent

.presden Nuclear Power Station BBS:

Enclosure cc: Director of Inspection & E.nfor.cement Director of Management Information & Program Control File/NRC

11.n1 LICENSEE EVENT REPORT

?._.  :*'C\J"TROL BLOCK: .___,._l_.....___.._ _.1_!_...._-'J 0 !PLEASE PRINT OR TYPE'L REQUIREO lNFORMATIONI ro-rna I I I L I D IR Is I 3 IG)I 0 I 0 I - I 0 I 0 I O: I 0 I 0 I0 I 0 1(2)1 4 11 11 11 11 I I© 1-. 101

~ 9 . LICENSEE. CODE,

  • 14 . 15 LICENSE NUMBER 25 26 . LICENSE. TYPE JO. 57 CAT 5B CON~T
~rl J
;~~~; L.U©I 01 5 Io I o I o 1~2 I 41 9 IGI o* I~ 11 J 9_ 18 Io IG)I or 6 I 1 I o I 8 I o IG) 60 61 DOCKET NUMBER 08 69 EVENT DATE 74 75 . REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES (iQ\

I During normal operation,* with reactor'-ievel instrument surveillance in progress, level 0

1 3

I I switch LIS 3-263-58B tripped at less than the* Tech. Spec~ limit (Table 3.2.1) of 84 I0 14 1. I inches. The safety significance of this event was minimal since channel "A" and the

)a Is I I redundant Channel "B" instruments were operable. There was no effect on public health J

0 lo I I or safety. Previous occurrences.: R.O. 76-57/031-0,. Docket 50-237; 77....,51/031-0 and 80-23/031-0, Docket 50-249.

80.

SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE

  • SUSCODE I I IB I@ ~@~@ 11IN1s1T IR 1u I@ L:J@} L:J@

9 10 11 12 13 18 19 20 SEQUENTIAL* OCCURRENCE REPORT REVISION G\ LEA/RO c~VENT YEAR REPORT NO. CODE TYPE NO.

"V REPORT NUMBER I 8 I. 0 I L=J I 0 I2 I4 I 1.......-1 10 13 ~ ~

21 22 23 24" 26. 27 28 29 30 31 32 ACTION . FUTURE EFFECT I o I o. I o ~

SHUTDOWN ATTACHMENT NPRD-4 PRIME COMP: COMPONENT TAKEN ACTION ON PLANT METHOD HOURS SUBMITTED FORM ::;us. SUPPLIER

  • MANUFACTUR.E l!J@L~J@

33 34 .

L:J@

35 L!J 36 37 I 40I~@ 41 Ll@ ll:l y 0 1 .o 42 43 44 47 CAUSE DESCRIPTION AND.CORRECTIVE ACTIONS @

j 1 lo I I The cause of this event is.unknown at this time. The inst~ument was immediately re-tested, with satisfactory results. Subsequent tests were performed, and each time the

, I1 I I

~

results were satisfactory. DIS* 500-2 will continue to* be done monthly.

1 I2 I I
=IIIJ *---------------------------------------------------

~8 9 so FACILITY f:i(j\ METHOD OF STATUS  % POWER OTHFR STATUS ~ . DISCOVERY DISCOVERY DESCRIPTION @ ,

~ ~@ 1° 1 8 14 l@I~n---------44_. NtA

  • I L!J@I Instrument Mechanic Surveillance
  • a 9 10 12 45 ""-*.----'------------------~so 46 ACTIVITY CONTENT ~

~RELEASED OF RELEASC: ..>.MOUNT OF ACTIVITY ~ LOCATION*OF RELEASE @.

~ L2J@ ~I N/A ' . I N/A

8. 9 10 11 . 44 45 80 PERSONNEL EXPOSURES *(.;";;\

m 8 1° 9

NUMBER ~TYPE 12 DESCRIPTION ~

1° 1° 111021L:J1~3---------------------~-~-------------8--'0

?ERSONNEL INJURIES f,;:;\

N/A NUMBER DESCRIPTIONa

~ 10 10 jO l@I NA / ~

a 9 11 .~12:-------------------------~------------~---~

t4J\

zw* L:J@ .

LOSS OF OR DAMAGE TO FACILITY TYPE. DESCRIPTION I v::::J

. N A 8 9 10 80 PUBLICITY f:::'\ NRC USE ONLY ISSUEDf,;":;\ DESCRIPTION~* *Q

IITJ* LJLl6 8 9 10 N A 68 I I I I I I I I I I I I I "'~

69 30.;;

. P. Holland X-523

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