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


=Text=
=Text=
{{#Wiki_filter:I  
{{#Wiki_filter:I  
'ii'-Commonwe'9  
~;: *!~-=- 'ii'-
Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone  
Commonwe'9 Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920  
815/942-2920  
\\\\~gulatory Docket Fl\\e BBS Ltr. #76-865 December 8, 1976 Mr. James G._ Keppler, Regional _Director  
Docket Fl\e ..... * BBS Ltr. #76-865 December 8, 1976 ' Mr. James G._ Keppler, Regional _Director . Directorate  
. Directorate of Regulatory Operations - Region III  
of Regulatory  
\\\\U. S. Nuclear Regulatory Commission 799 Roosevelt Road iGlen Ellyn,* Illinois 60137  
Operations  
\\
-Region III \\U. S. Nuclear Regulatory  
Enclosed please find Reportable Occurrence report number 50-249/1976-33.
Commission  
This report is being submitted to your office in accordance with the Dresden Nuclear Power Station Technical Specificatio:~~*B.
799 Roosevelt  
~&{f~f~
Road iGlen Ellyn,* Illinois 60137 \ Enclosed please find Reportable  
BBS:jo Enclosure cc:
Occurrence  
Director of Inspection & Enforcement Station Superintendent Dresden Nuclear Power _Station Director of Management-Information & Program Control File/NRC 12519 0  
report number 50-249/1976-33.  
 
This report is being submitted  
' \\
to your office in accordance  
LICENSEE EVENT REPORT e Y::.J CONTROL BLOCK :I.... __,.___._.__..____.___,I
with the Dresden Nuclear Power Station Technical  
[PLEASE PR:NT ALL REQUIRED INFORMATION)
BBS:jo Enclosure  
I 1
cc: Director of Inspection  
6 LICENSEE UC.EN SE.
& Enforcement  
EVENT NAME LICENSE NUMBER  
Station Superintendent  
@El IIILl.DIRISl31 10101-10101 1010.1-10101 TYPE TYPE l.lfltltltltl,l 131 7
Dresden Nuclear Power _Station Director of Management-Information  
99*
& Program Control File/NRC 12519 0
: 14.
.... ' \ ' -LICENSEE EVENT REPORT e Y::.J " .... CONTROL BLOCK :I .... __,.___._.__..____.___,I  
15
[PLEASE PR:NT ALL REQUIRED INFORMATION)  
: 25.
I . 1 6 LICENSEE UC.EN SE. EVENT NAME LICENSE NUMBER @El IIILl.DIRISl31  
26 30. 31 32 CATEGORY REPORT TYPE.
10101-10101  
REPORT SOLJRCE DOCKET NUMBER EVENT QA TE REPORT CATE  
1010.1-10101 . TYPE ; * TYPE l.lfltltltltl,l  
@12]coN'T 1*
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  
I I LbJ lbJ 101s101-101~141ql 11 It IOIKl?l~I 111;2..101~17101 7
1* I I LbJ lbJ  
8' 57 58 59 60 61 68. 69 74 75 80  
11 It  
. EVENT DESCRIPTION  
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
@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  
* 7*. 8 9  
1>tPING-
.. 80 10131 L(uN10N) 'BETW£EN THE VAJ-V£ AND TH£ JNSTRurn.NT 1>tPING-WA~. FOLJN]} To I
FOLJN]} To I 7. 8 9 . 80 @E). I 'BE. i.EAl<JNG-
: 7.
ON ISOJ..,AT/ON  
8 9 80  
CONP&#xa3;NSER.  
@E). I 'BE. i.EAl<JNG-ON ISOJ..,AT/ON CONP&#xa3;NSER. STEAM I-IN&#xa3; FLOW SENSOR, iN5TRumEN"fl 7
STEAM I-IN&#xa3; FLOW SENSOR, iN5TRumEN"fl 7 8 9. . . . . . 80 l.LfNE , 1so1-AT1of\/  
8 9.
Fl-OW CHGCI<. VAJ.,VE" 3-t30t-23..  
80  
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  
l.LfNE, 1so1-AT1of\\/ Fl-OW CHGCI<. VAJ.,VE" 3-t30t-23.. ATTEmPTS To TIG-HTEN TH&#xa3; I
CONDENSER  
: 7. 8 9 i
WAS I 7 8 9 PRIME . . (SEG ' ATTACHE-.D .s !-+&#xa3;ET) 80 SYSTEM CAUSE COMPONENT  
80 lolsl I UNION CAUSED (11&#xa3; LEAKAG-&#xa3; TO !NCR&#xa3;AS&#xa3;. THE ISOLATION CONDENSER WAS I
COMPONENT  
7 8 9 PRIME (SEG ' ATTACHE-.D.s !-+&#xa3;ET) 80 SYSTEM CAUSE COMPONENT COMPONENT CODE CODE COMPONENT CODE SUPPUEA MANUFACTURER* '
CODE CODE COMPONENT  
VIOLATION  
CODE SUPPUEA MANUFACTURER*  
@0 IS IB I l.SJ l'P I 1 IP lf:lx IXI  
' 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.  
IMl3IO13 I lllJ 7
PEf?EORfYl&#xa3;D  
8 9 10.
ON VALVE' .3-1.301-13, T/.i&#xa3; UNtoAI I 7 8 9 . . . . . 80 @&sect;"I APPARENTLY  
11 12 17 43 44..
BECAME CROSS-THREADE.D.
47 48 CAUSE DESCRIPTION (ol0! l:DuR1NG-OVTAG&#xa3; fYllttN/ENANCE. PEf?EORfYl&#xa3;D ON VALVE'.3-1.301-13, T/.i&#xa3; UNtoAI I 7
3 'PROVIDING  
8 9 80  
A LEAkAGE PATH. TH&#xa3; .LEIH<d * .. 7 B 9 * 80 IAGt BECAmE APPARENT &#xa3;0UOW/NG.  
@&sect;"I APPARENTLY BECAME CROSS-THREADE.D.3 'PROVIDING A LEAkAGE PATH. TH&#xa3;.LEIH<d *  
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 B 9 80  
DISCOVERY  
~
DESCRIPTION
IAGt BECAmE APPARENT &#xa3;0UOW/NG. THE 1000-PSI HYDROSTATIC T~ST.
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* . .___ ___
I  
_________  
]
___,_ 7 . 8. 9 . . 10 11 44 .45 ,: . 80 PERSONNEL  
_., B g FACILITY METHOD OF (SE&#xa3; ftTT p,Ut&#xa3;f> S H&#xa3;&#xa3;T)
EXPOSURES . NUMBER TYPE DESCRIPTION  
BO STATUS  
*rrEJ 10 IO IOI ..__ ___ M_:4 _______________  
% POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION EEJ
--'"-____ __. 7 8 _9 . 11 12 13 80 PERS"ONNEL  
~.
INJURIES NUMBER DESCRIPTION  
10101s 1 Nil rn.J  
EE] 1010101  
.AIA I
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  
7 B'
[ill] NA 7 8 9 80 ADDITIONAL  
: 9.
FACTORS  
10.
NA .7 8 9 80 . [iliJ 7 8 9 80
12 13 44 45  
*'&deg; * CJ .... \ '/I * EVENT DESCRIPTION (Continued)  
. 46 80  
immediately  
. FORM OF ACTIVITY CONTENT  
isolated from the reactor. The HPCI system had been demonstrated .to be operable.  
. RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE 1  
This is not a repetitive  
. rn lZJ. lZJ I Alfi*
event. (50-249/1976-33)  
M~'A_. _________ ___,_
CAUSE DESCRIPTION (Continued)  
7. 8.
of the reactor vessel. The union was rethreaded  
9.  
and reinstalted, and the if?olatic:m  
. 10 11 44  
condenser  
.45,:.
was returned to service. No further corrective  
80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION  
action was indicated.
*rrEJ 10 IO IOI ~..__ ___
}}
M_:4 _______________ --'"-____
7 8 _9.
11 12 13 80 PERS"ONNEL INJURIES NUMBER DESCRIPTION EE] 1010101 ~--N'.-~-----~-----------~~
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  
--~I NA  
.7 8 9 80.
[iliJ 7
8 9 80  
 
*'&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.}}

Latest revision as of 11:35, 8 January 2025

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

\\\\~gulatory 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 Specificatio:~~*B.

~&{f~f~

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 101s101-101~141ql 11 It IOIKl?l~I 111;2..101~17101 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-WA~. 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 T~ST.

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*

M~'A_. _________ ___,_

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 ~--N'.-~-----~-----------~~

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

--~I 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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