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| number = ML17252B191
| number = ML17252B191
| 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 15: Line 15:
| page count = 2
| page count = 2
}}
}}
=Text=
{{#Wiki_filter: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&#xa9; 1-.                                                  101
~              9    . LICENSEE. CODE,
* 14    . 15                          LICENSE NUMBER                              25      26    . LICENSE. TYPE      JO. 57 CAT 5B CON~T
;~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\
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&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 08:40, 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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