ML17252B191: Difference between revisions

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-Region III Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137
-Region III Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137
* 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::::
* 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 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. BBS:
BBS:
B.B. Stephenson . Station Superintendent .presden Nuclear Power Station Enclosure cc: Director of Inspection  
B.B. Stephenson  
. Station Superintendent  
.presden Nuclear Power Station Enclosure cc: Director of Inspection  
& E.nfor.cement Director of Management Information  
& E.nfor.cement Director of Management Information  
& Program Control File/NRC 11.n1 ***--,. LICENSEE EVENT REPORT ?._. :*'C\J"TROL BLOCK: .___,._l_.....___..
& 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 1-. I 0 I 0 1(2)14 11 11 11 11 101 I I © 9 . LICENSEE.
_ _.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)1 4 1 1 1 1 1 1 1 1 101 I I © 9 . LICENSEE.
CODE,
CODE,
* 14 . 15 LICENSE NUMBER 25 26 . LICENSE.
* 14 . 15 LICENSE NUMBER 25 26 . LICENSE. TYPE JO. 57 CAT 5B J --**
TYPE JO. 57 CAT 5B J --**
L.U©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,*
L.U©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,*
with reactor'-ievel instrument surveillance in progress, level ; 0 13 I I switch LIS 3-263-58B tripped at less than the* Tech.
with reactor'-ievel instrument surveillance in progress, level ; 0 1 3 I I switch LIS 3-263-58B tripped at less than the* Tech.
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.
limit (Table 3.2.1) of 84 I 0 1 4 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.:
There was no effect on public health J 0 lo I I or safety. Previous occurrences.:
R.O. 76-57/031-0,.
R.O. 76-57/031-0,.
Line 39: Line 35:
* SUSCODE 11IN1s1T IR 1u I@ L:J@} L:J@ 11 12 13 L=J 23 SHUTDOWN METHOD SEQUENTIAL*
* SUSCODE 11IN1s1T IR 1u I@ L:J@} L:J@ 11 12 13 L=J 23 SHUTDOWN METHOD SEQUENTIAL*
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
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
* 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.
* 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. Subsequent tests were performed, and each time the results were satisfactory.
Subsequent tests were performed, and each time the results were satisfactory.
DIS* 500-2 will continue to* be done monthly. 47 I I :=IIIJ *---------------------------------------------------8 9 FACILITY f:i(j\ METHOD OF STATUS % POWER OTHFR STATUS . DISCOVERY DISCOVERY DESCRIPTION  
DIS* 500-2 will continue to* be done monthly.
@ , Instrument Mechanic Surveillance so 1° 1 8 1 4 l@I NtA
47 I I :=IIIJ *---------------------------------------------------8 9 FACILITY f:i(j\ METHOD OF STATUS % POWER OTHFR STATUS . DISCOVERY DISCOVERY DESCRIPTION  
* I L!J@I *a 9 10 12 45 "" 46-*
@ , Instrument Mechanic Surveillance so 1° 18 14 l@I NtA
ACTIVITY CONTENT OF RELEASC: ..>.MOUNT OF ACTIVITY L2J@ N/A ' . I 8. 9 10 11 . 44 PERSONNEL EXPOSURES  
* I L!J@I *a 9 10 12 45 ""46-*
*(.;";;\ NUMBER DESCRIPTION m 1° 1° 1° 1021L:J 8 9 11 12  
ACTIVITY CONTENT OF RELEASC:  
..>.MOUNT OF ACTIVITY L2J@ N/A ' . I 8. 9 10 11 . 44 PERSONNEL EXPOSURES  
*(.;";;\
NUMBER DESCRIPTION m 1° 1° 1° 1021L:J 8 9 11 12  
?ERSONNEL INJURIES f,;:;\ N/A LOCATION*OF RELEASE @. 45 80 N/A NUMBER DESCRIPTIONa  
?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,;":;\  
/ 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,;":;\  
: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}}
: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}}

Revision as of 15:22, 7 July 2018

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 B
Commonwealth Edison Co
To: Keppler J G
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 BBS LTR. /180-507 June 13, 1980 James G. Keppler, Regional Director Directorate of Regulatory Operatfop.s

-Region III Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137

  • 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 vent the fulfillment of the functional requirements of.affected systems. BBS:

B.B. Stephenson . Station Superintendent .presden Nuclear Power Station 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 1-. I 0 I 0 1(2)1 4 1 1 1 1 1 1 1 1 101 I I © 9 . LICENSEE.

CODE,

  • 14 . 15 LICENSE NUMBER 25 26 . LICENSE. TYPE JO. 57 CAT 5B J --**

L.U©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,*

with reactor'-ievel instrument surveillance in progress, level ; 0 1 3 I I switch LIS 3-263-58B tripped at less than the* Tech.

limit (Table 3.2.1) of 84 I 0 1 4 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 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

  • SUSCODE 11IN1s1T IR 1u I@ L:J@} L:J@ 11 12 13 L=J 23 SHUTDOWN METHOD SEQUENTIAL*

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

  • 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. Subsequent tests were performed, and each time the results were satisfactory.

DIS* 500-2 will continue to* be done monthly. 47 I I :=IIIJ *---------------------------------------------------8 9 FACILITY f:i(j\ METHOD OF STATUS % POWER OTHFR STATUS . DISCOVERY DISCOVERY DESCRIPTION

@ , Instrument Mechanic Surveillance so 1° 1 8 1 4 l@I NtA

  • I L!J@I *a 9 10 12 45 "" 46-*

ACTIVITY CONTENT OF RELEASC: ..>.MOUNT OF ACTIVITY L2J@ N/A ' . I 8. 9 10 11 . 44 PERSONNEL EXPOSURES

  • (.;";;\ NUMBER DESCRIPTION m 1° 1° 1° 1021L:J 8 9 11 12

?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,;":;\

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
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