ML17252A265: Difference between revisions

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See also: [[see also::IR 05000249/2019076]]


=Text=
=Text=
{{#Wiki_filter:I  
{{#Wiki_filter:I  
'ii'-Commonwe'9  
'ii'-Commonwe'9 Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 Docket Fl\e .....
Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone  
* BBS Ltr. #76-865 December 8, 1976 ' Mr. James G._ Keppler, Regional _Director . Directorate of Regulatory Operations  
815/942-2920  
-Region III \\U. S. Nuclear Regulatory Commission 799 Roosevelt Road iGlen Ellyn,* Illinois 60137 \ Enclosed please find Reportable Occurrence report number 50-249/1976-33.
Docket Fl\e ..... * BBS Ltr. #76-865 December 8, 1976 ' Mr. James G._ Keppler, Regional _Director . Directorate  
This report is being submitted to your office in accordance with the Dresden Nuclear Power Station Technical BBS:jo Enclosure cc: Director of Inspection  
of Regulatory  
& Enforcement Station Superintendent Dresden Nuclear Power _Station Director of Management-Information  
Operations  
-Region III \\U. S. Nuclear Regulatory  
Commission  
799 Roosevelt  
Road iGlen Ellyn,* Illinois 60137 \ Enclosed please find Reportable  
Occurrence  
report number 50-249/1976-33.  
This report is being submitted  
to your office in accordance  
with the Dresden Nuclear Power Station Technical  
BBS:jo Enclosure  
cc: Director of Inspection  
& Enforcement  
Station Superintendent  
Dresden Nuclear Power _Station Director of Management-Information  
& Program Control File/NRC 12519 0   
& Program Control File/NRC 12519 0   
.... ' \ ' -LICENSEE EVENT REPORT e Y::.J " .... CONTROL BLOCK :I .... __,.___._.__..____.___,I  
.... ' \ ' -LICENSEE EVENT REPORT e Y::.J " .... CONTROL BLOCK :I .... __,.___._.__..____.___,I
[PLEASE PR:NT ALL REQUIRED INFORMATION)  
[PLEASE PR:NT ALL REQUIRED INFORMATION)
I . 1 6 LICENSEE UC.EN SE. EVENT NAME LICENSE NUMBER @El IIILl.DIRISl31  
I . 1 6 LICENSEE UC.EN SE. EVENT NAME LICENSE NUMBER @El IIILl.DIRISl31 10101-10101 1010.1-10101 . TYPE ;
10101-10101  
* TYPE l.lfltltltltl,l 131 7 99* 14. 15 25. 26 30 . 31 32 CATEGORY REPORT TYPE. REPORT SOLJRCE DOCKET NUMBER . EVENT QA TE REPORT CATE @12]coN'T 1* I I LbJ lbJ 11 It 7 8' 57 58 59 60 61 68 . 69 74 75 80 . EVENT DESCRIPTION  
1010.1-10101 . TYPE ; * TYPE l.lfltltltltl,l  
@lg] I DURING-A RbUTI tJE OPERATOR INS'PECTION., TH&#xa3; IHREAD&#xa3;D C.ONNEC. TtoN * . , 7*. 8 9 . . . . . . . . 80 10131 L(uN10N) 'BETW&#xa3;EN THE VAJ-V&#xa3; AND TH&#xa3; JNSTRurn*.NT 1>tPING-FOLJN]} To I 7. 8 9 . 80 @E). I 'BE. i.EAl<JNG-ON ISOJ..,AT/ON CONP&#xa3;NSER.
131 7 99* 14. 15 25. 26 30 . 31 32 CATEGORY REPORT TYPE. REPORT SOLJRCE DOCKET NUMBER . EVENT QA TE REPORT CATE @12]coN'T  
STEAM I-IN&#xa3; FLOW SENSOR, iN5TRumEN"fl 7 8 9. . . . . . 80 l.LfNE , 1so1-AT1of\/
1* I I LbJ lbJ  
Fl-OW CHGCI<. VAJ.,VE" 3-t30t-23..
11 It  
ATTEmPTS To TIG-HTEN TH&#xa3; I 7. 8 9 . i . . . . .... *. . . 80 lolsl I UNION CAUSED (11&#xa3; LEAKAG-&#xa3; TO !NCR&#xa3;AS&#xa3;.
7 8' 57 58 59 60 61 68 . 69 74 75 80 . EVENT DESCRIPTION  
THE ISOLATION CONDENSER WAS I 7 8 9 PRIME . . (SEG ' ATTACHE-.D .s !-+&#xa3;ET) 80 SYSTEM CAUSE COMPONENT COMPONENT CODE CODE COMPONENT CODE SUPPUEA MANUFACTURER*  
@lg] I DURING-A RbUTI tJE OPERATOR INS'PECTION., TH&#xa3; IHREAD&#xa3;D C.ONNEC. TtoN * . , 7*. 8 9 . . . . . . . . 80 10131 L(uN10N) 'BETW&#xa3;EN THE VAJ-V&#xa3; AND TH&#xa3; JNSTRurn*.NT  
1>tPING-
FOLJN]} To I 7. 8 9 . 80 @E). I 'BE. i.EAl<JNG-
ON ISOJ..,AT/ON  
CONP&#xa3;NSER.  
STEAM I-IN&#xa3; FLOW SENSOR, iN5TRumEN"fl 7 8 9. . . . . . 80 l.LfNE , 1so1-AT1of\/  
Fl-OW CHGCI<. VAJ.,VE" 3-t30t-23..  
ATTEmPTS To TIG-HTEN TH&#xa3; I 7. 8 9 . i . . . . .... *. . . 80 lolsl I UNION CAUSED (11&#xa3; LEAKAG-&#xa3; TO !NCR&#xa3;AS&#xa3;.  
THE ISOLATION  
CONDENSER  
WAS I 7 8 9 PRIME . . (SEG ' ATTACHE-.D .s !-+&#xa3;ET) 80 SYSTEM CAUSE COMPONENT  
COMPONENT  
CODE CODE COMPONENT  
CODE SUPPUEA MANUFACTURER*  
' VIOLATION  
' VIOLATION  
@0 IS IB I l.SJ l'P I 1 IP lf:lx IXI IMl3IO13 I lllJ 7 8 9 10. 11 12 17 43 44 . . 47 48 CAUSE DESCRIPTION (ol0! l:DuR1NG-OVTAG&#xa3; fYllttN/ENANCE.  
@0 IS IB I l.SJ l'P I 1 IP lf:lx IXI IMl3IO13 I lllJ 7 8 9 10. 11 12 17 43 44 . . 47 48 CAUSE DESCRIPTION (ol0! l:DuR1NG-OVTAG&#xa3; fYllttN/ENANCE.
PEf?EORfYl&#xa3;D  
PEf?EORfYl&#xa3;D ON VALVE' .3-1.301-13, T/.i&#xa3; UNtoAI I 7 8 9 . . . . . 80 @&sect;"I APPARENTLY BECAME CROSS-THREADE.D.
ON VALVE' .3-1.301-13, T/.i&#xa3; UNtoAI I 7 8 9 . . . . . 80 @&sect;"I APPARENTLY  
3 'PROVIDING A LEAkAGE PATH. TH&#xa3; .LEIH<d * .. 7 B 9
BECAME CROSS-THREADE.D.
* 80 IAGt BECAmE APPARENT &#xa3;0UOW/NG.
3 'PROVIDING  
THE 1000-PSI HYDROSTATIC . I ] _., B g FACILITY METHOD OF (SE&#xa3; ftTT p,Ut&#xa3;f> S H&#xa3;&#xa3;T) BO STATUS % POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION EEJ 10101s 1 Nil rn.J .AIA I 7 B' 9. 10 . 12 13 44 45 . 46 80 . FORM OF ACTIVITY CONTENT . RELEASED OF RELEASE AMOUNT OF ACTIVITY -, LOCATION OF RELEASE 1 .. . rn lZJ . lZJ I Alfi* . .___ ___
A LEAkAGE PATH. TH&#xa3; .LEIH<d * .. 7 B 9 * 80 IAGt BECAmE APPARENT &#xa3;0UOW/NG.  
_________
THE 1000-PSI HYDROSTATIC . I ] _., B g FACILITY METHOD OF (SE&#xa3; ftTT p,Ut&#xa3;f> S H&#xa3;&#xa3;T) BO STATUS % POWER OTHER STATUS DISCOVERY  
___,_ 7 . 8. 9 . . 10 11 44 .45 ,: . 80 PERSONNEL EXPOSURES . NUMBER TYPE DESCRIPTION  
DISCOVERY  
DESCRIPTION  
EEJ 10101s 1 Nil rn.J .AIA I 7 B' 9. 10 . 12 13 44 45 . 46 80 . FORM OF ACTIVITY CONTENT . RELEASED OF RELEASE AMOUNT OF ACTIVITY -, LOCATION OF RELEASE 1 .. . rn lZJ . lZJ I Alfi* . .___ ___  
_________  
___,_ 7 . 8. 9 . . 10 11 44 .45 ,: . 80 PERSONNEL  
EXPOSURES . NUMBER TYPE DESCRIPTION  
*rrEJ 10 IO IOI ..__ ___ M_:4 _______________  
*rrEJ 10 IO IOI ..__ ___ M_:4 _______________  
--'"-____ __. 7 8 _9 . 11 12 13 80 PERS"ONNEL  
--'"-____ __. 7 8 _9 . 11 12 13 80 PERS"ONNEL INJURIES NUMBER DESCRIPTION EE] 1010101 7 8 9 11 12 80 OFFSITE CONSEQUENCES .E]fil NA 7 8 9 . 80 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION lZJ 11 7 "' 8 *9 'C *10 ' **-* 80 PUBLICITY
INJURIES NUMBER DESCRIPTION  
[ill] NA 7 8 9 80 ADDITIONAL FACTORS NA .7 8 9 80 . [iliJ 7 8 9 80   
EE] 1010101  
*'&deg;
7 8 9 11 12 80 OFFSITE CONSEQUENCES .E]fil NA 7 8 9 . 80 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION lZJ 11 7 "' 8 *9 'C *10 ' **-* 80 PUBLICITY  
* CJ .... \ '/I
[ill] NA 7 8 9 80 ADDITIONAL  
* EVENT DESCRIPTION (Continued) immediately isolated from the reactor. The HPCI system had been demonstrated .to be operable.
FACTORS  
This is not a repetitive event. (50-249/1976-33)
NA .7 8 9 80 . [iliJ 7 8 9 80   
CAUSE DESCRIPTION (Continued) of the reactor vessel. The union was rethreaded and reinstalted, and the if?olatic:m condenser was returned to service. No further corrective action was indicated.}}
*'&deg; * CJ .... \ '/I * EVENT DESCRIPTION (Continued)  
immediately  
isolated from the reactor. The HPCI system had been demonstrated .to be operable.  
This is not a repetitive  
event. (50-249/1976-33)  
CAUSE DESCRIPTION (Continued)  
of the reactor vessel. The union was rethreaded  
and reinstalted, and the if?olatic:m  
condenser  
was returned to service. No further corrective  
action was indicated.
}}

Revision as of 14:04, 17 August 2019

Letter Submitting Reportable Occurrence Number 050-249/1976-33 in Accordance with Technical Specifications, Section 6.6.B
ML17252A265
Person / Time
Site: Dresden  
Issue date: 12/08/1976
From: Stephenson B
Commonwealth Edison Co
To: James Keppler
NRC/RGN-III
References
BBS76-865 050-249/1976-33
Download: ML17252A265 (3)
v • d • e


Text

I

'ii'-Commonwe'9 Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 Docket Fl\e .....

  • BBS Ltr. #76-865 December 8, 1976 ' Mr. James G._ Keppler, Regional _Director . Directorate of Regulatory Operations

-Region III \\U. S. Nuclear Regulatory Commission 799 Roosevelt Road iGlen Ellyn,* Illinois 60137 \ Enclosed please find Reportable Occurrence report number 50-249/1976-33.

This report is being submitted to your office in accordance with the Dresden Nuclear Power Station Technical BBS:jo Enclosure cc: Director of Inspection

& Enforcement Station Superintendent Dresden Nuclear Power _Station Director of Management-Information

& Program Control File/NRC 12519 0

.... ' \ ' -LICENSEE EVENT REPORT e Y::.J " .... CONTROL BLOCK :I .... __,.___._.__..____.___,I

[PLEASE PR:NT ALL REQUIRED INFORMATION)

I . 1 6 LICENSEE UC.EN SE. EVENT NAME LICENSE NUMBER @El IIILl.DIRISl31 10101-10101 1010.1-10101 . TYPE ;

  • TYPE l.lfltltltltl,l 131 7 99* 14. 15 25. 26 30 . 31 32 CATEGORY REPORT TYPE. REPORT SOLJRCE DOCKET NUMBER . EVENT QA TE REPORT CATE @12]coN'T 1* I I LbJ lbJ 11 It 7 8' 57 58 59 60 61 68 . 69 74 75 80 . EVENT DESCRIPTION

@lg] I DURING-A RbUTI tJE OPERATOR INS'PECTION., TH£ IHREAD£D C.ONNEC. TtoN * . , 7*. 8 9 . . . . . . . . 80 10131 L(uN10N) 'BETW£EN THE VAJ-V£ AND TH£ JNSTRurn*.NT 1>tPING-FOLJN]} To I 7. 8 9 . 80 @E). I 'BE. i.EAl<JNG-ON ISOJ..,AT/ON CONP£NSER.

STEAM I-IN£ FLOW SENSOR, iN5TRumEN"fl 7 8 9. . . . . . 80 l.LfNE , 1so1-AT1of\/

Fl-OW CHGCI<. VAJ.,VE" 3-t30t-23..

ATTEmPTS To TIG-HTEN TH£ I 7. 8 9 . i . . . . .... *. . . 80 lolsl I UNION CAUSED (11£ LEAKAG-£ TO !NCR£AS£.

THE ISOLATION CONDENSER WAS I 7 8 9 PRIME . . (SEG ' ATTACHE-.D .s !-+£ET) 80 SYSTEM CAUSE COMPONENT COMPONENT CODE CODE COMPONENT CODE SUPPUEA MANUFACTURER*

' VIOLATION

@0 IS IB I l.SJ l'P I 1 IP lf:lx IXI IMl3IO13 I lllJ 7 8 9 10. 11 12 17 43 44 . . 47 48 CAUSE DESCRIPTION (ol0! l:DuR1NG-OVTAG£ fYllttN/ENANCE.

PEf?EORfYl£D ON VALVE' .3-1.301-13, T/.i£ UNtoAI I 7 8 9 . . . . . 80 @§"I APPARENTLY BECAME CROSS-THREADE.D.

3 'PROVIDING A LEAkAGE PATH. TH£ .LEIH<d * .. 7 B 9

  • 80 IAGt BECAmE APPARENT £0UOW/NG.

THE 1000-PSI HYDROSTATIC . I ] _., B g FACILITY METHOD OF (SE£ ftTT p,Ut£f> S H££T) BO STATUS % POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION EEJ 10101s 1 Nil rn.J .AIA I 7 B' 9. 10 . 12 13 44 45 . 46 80 . FORM OF ACTIVITY CONTENT . RELEASED OF RELEASE AMOUNT OF ACTIVITY -, LOCATION OF RELEASE 1 .. . rn lZJ . lZJ I Alfi* . .___ ___

_________

___,_ 7 . 8. 9 . . 10 11 44 .45 ,: . 80 PERSONNEL EXPOSURES . NUMBER TYPE DESCRIPTION

  • rrEJ 10 IO IOI ..__ ___ M_:4 _______________

--'"-____ __. 7 8 _9 . 11 12 13 80 PERS"ONNEL INJURIES NUMBER DESCRIPTION EE] 1010101 7 8 9 11 12 80 OFFSITE CONSEQUENCES .E]fil NA 7 8 9 . 80 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION lZJ 11 7 "' 8 *9 'C *10 ' **-* 80 PUBLICITY

[ill] NA 7 8 9 80 ADDITIONAL FACTORS NA .7 8 9 80 . [iliJ 7 8 9 80

  • '°
  • CJ .... \ '/I
  • EVENT DESCRIPTION (Continued) immediately isolated from the reactor. The HPCI system had been demonstrated .to be operable.

This is not a repetitive event. (50-249/1976-33)

CAUSE DESCRIPTION (Continued) of the reactor vessel. The union was rethreaded and reinstalted, and the if?olatic:m condenser was returned to service. No further corrective action was indicated.

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