ML17252B191: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
 
(StriderTol Bot change)
 
(11 intermediate revisions by the same user not shown)
Line 2: Line 2:
| 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 14: Line 14:
| document type = Letter, Licensee Event Report (LER)
| document type = Letter, Licensee Event Report (LER)
| page count = 2
| page count = 2
| revision = 0
}}
}}
=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 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

Retrieved from "https://kanterella.com/w/index.php?title=ML17252B191&oldid=2509142"