ML17252A246: Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:.**. Comrnonv.h  
{{#Wiki_filter:.**. Comrnonv.h  
Edison * Dresde,1  
Edison * Dresde,1 Nuclear Power Station R.R. #i Morris, Illinois 60450 Telephone  
Nuclear Power Station R.R. #i Morris, Illinois  
60450 Telephone  
815/942-2920  
815/942-2920  
BBS Ltr. #76-775 November  
BBS Ltr. #76-775 November 4, 1976 Mr. James Keppler, Regional Director Directorate  
4, 1976 Mr. James Keppler,  
Regional  
Director  
Directorate  
of  
of  
Operations  
Operations  
-.Region  
-.Region III U. S. Nuclear Regulatory  
III U. S. Nuclear Regulatory  
Commission  
Commission  
799 Roosevelt  
799 Roosevelt  
Road Glen Ellyn, Illinois  
Road Glen Ellyn, Illinois 60137 Enclosed please find Reportable  
60137 Enclosed  
please find Reportable  
Occurrence  
Occurrence  
report number 50-249/1976-23.  
report number 50-249/1976-23.  
Line 43: Line 34:
Station Techriical  
Station Techriical  
Section 6.6.B. A n n . : . *1Y) _/) .. * -I-. .. . B. Stephensori  
Section 6.6.B. A n n . : . *1Y) _/) .. * -I-. .. . B. Stephensori  
* tation Superintendent.  
* tation Superintendent. . Dresden Nuclear Power Station BBS :jo Enclosure  
. Dresden Nuclear Power Station BBS :jo Enclosure  
cc: Director of Inspection  
cc: Director  
& *Enforcement . Direct'or  
of Inspection  
& *Enforcement  
. Direct'or  
of Management  
of Management  
Information  
Information  
& Program Control File/NRC   
& Program Control File/NRC   
. LICENSEE  
. LICENSEE EVd\JT REPOR. *. -. . * .. ' CONTROL BLOCK: I ' I *.1 1. I I (PLEASE PRll'JT ALL REQUIRED INFORMATION)  
EVd\JT REPOR. *. -. . * .. ' CONTROL BLOCK: I ' I *.1 1. I I (PLEASE PRll'JT ALL REQUIRED  
' 1 6 .* '*. LICENSEE * < NAME .@El I I I L. ID IR I s 13 I 7 8 9 ' 14 CATEGORY REPORT TYPE. LICENSE NUMBER 10101-10101010101-10101  
INFORMATION)  
' 1 6 .* '*. LICENSEE  
* < NAME .@El I I I L. ID IR I s 13 I 7 8 9 ' 14 CATEGORY  
REPORT TYPE. LICENSE NUMBER 10101-10101010101-10101  
15 25 REPORT SOURCE OOCl\ET NUM6ER * LICENSE TYPE 1!1111111111  
15 25 REPORT SOURCE OOCl\ET NUM6ER * LICENSE TYPE 1!1111111111  
26 ' 30 EVENT TYPE 10131 '31 ' 32' EVENT* DATE REPORT DATE lof1 I coN1 I I I 7 8 57 58' llJ 59 LLl 60  
26 ' 30 EVENT TYPE 10131 '31 ' 32' EVENT* DATE REPORT DATE lof1 I coN1 I I I 7 8 57 58' llJ 59 LLl 60  
61 68 11 IOIOl?l71(,l  
61 68 11 IOIOl?l71(,l  
.*II II 1014171(,  
.*II II 1014171(, L 69 74 75 80 EVENT DESCRIPTION . (filg].lD!JRtAJ.G-
L 69 74 75 80 EVENT DESCRIPTION  
. (filg].lD!JRtAJ.G-
REFUELING-
REFUELING-
OUTAGE LDC.AL l.t:Ak-:-RATE  
OUTAGE LDC.AL l.t:Ak-:-RATE  
TESTING;  
TESTING; *LPC/ PRtrnARV I 7* 8' 9 . ' 80. lol31 ltSO.L..ATION'.  
*LPC/ PRtrnARV  
I 7* 8' 9 . ' 80. lol31 ltSO.L..ATION'.  
CA*IE:CI<  
CA*IE:CI<  
VfU;V* 3-!S-O/-J.5&  
VfU;V* 3-!S-O/-J.5&  
Line 75: Line 55:
RAT&#xa3;. ... U!J' I, 7 Ei' 9 ' . ,. ' ' ' ' 80 IEXC&#xa3;$$'0F  
RAT&#xa3;. ... U!J' I, 7 Ei' 9 ' . ,. ' ' ' ' 80 IEXC&#xa3;$$'0F  
/HT:; T&#xa3;CH SP&#xa3;.C. /_JM/{ OF  
/HT:; T&#xa3;CH SP&#xa3;.C. /_JM/{ OF  
SC'l="H.  
SC'l="H. TH*  
TH*  
VAL.VE: I 7 8 9 ' ' ' ' ' ' 80 10'51 lusED VO f6R<YYI THE. 4'?'-Psf(:;  
VAL.VE: I 7 8 9 ' ' ' ' ' ' 80 10'51 lusED VO f6R<YYI THE. 4'?'-Psf(:;  
DECAY 7EST BouJVDl1R..Y  
DECAY 7EST BouJVDl1R..Y  
.. fYlANuALf  
.. fYlANuALf  
7 8 9 i ' ' ' ' ' ' ' " 80 lolsl I VAt..VE'.'  
7 8 9 i ' ' ' ' ' ' ' " 80 lolsl I VAt..VE'.'  
3-15&deg;0! -:Y,,B J 1-lfJD A $ IGNI FICA NT WATER HC/IJ) PR&#xa3;s&#xa3;NTj  
3-15&deg;0! -:Y,,B J 1-lfJD A $ IGNI FICA NT WATER HC/IJ) PR&#xa3;s&#xa3;NTj CONSEQLJOJT1..y,, I 7 8 9. * . . . PRIME * . (5,&#xa3;* /IT!FICHEV  
CONSEQLJOJT1..y,,  
I 7 8 9. * . . . PRIME * . (5,&#xa3;* /IT!FICHEV  
-<;;ft&#xa3;GT)  
-<;;ft&#xa3;GT)  
80 . * SYSTEM CAUSE COMPONENT  
80 . * SYSTEM CAUSE COMPONENT  
COMPON!:NT  
COMPON!:NT  
-. . CODE CODE * COMPONENT  
-. . CODE CODE * COMPONENT  
CODE SUPPLIER  
CODE SUPPLIER MANUFACTURER  
MANUFACTURER  
VIOLATION  
VIOLATION  
@0 ISIFLlsJ  
@0 ISIFLlsJ 1v1AIL1v1&#xa3;1x1  
1v1AIL1v1&#xa3;1x1  
lt!J  
lt!J  
L'Ll 7 8 9 10 ' 11 12 17 ' 43 44 4 7 48 . CAUSE DES.CA!PTION l::TJ1&#xa3; VA/..-1/E  
L'Ll 7 8 9 10 ' 11 12 17 ' 43 44 4 7 48 . CAUSE DES.CA!PTION l::TJ1&#xa3; VA/..-1/E  
f:fll L-UR.6  
f:fll L-UR.6  
CAUSED Bi EXCESS I 116 ])15C-To  
CAUSED Bi EXCESS I 116 ])15C-To -SEAi  
-SEAi  
J 7 8 9 ' 80 lo'91 l1r1cs J.&#xa3;AK-fK-G:  
J 7 8 9 ' 80 lo'91 l1r1cs J.&#xa3;AK-fK-G:  
A77R.t8UIED,  
A77R.t8UIED, .. To TH&#xa3; PREsEl'JCG.*  
.. To TH&#xa3; PREsEl'JCG.*  
OE DtRTA*No *  
OE DtRTA*No  
I 7 8 9 ' ', ' ' ' 80. ' (iE1 .I S:CRATc.HC:S  
*  
I 7 8 9 ' ', ' ' ' 80. '  
(iE1 .I S:CRATc.HC:S  
OtJ THE  
OtJ THE  
$&#xa3;fl'0 APPARENTLY  
$&#xa3;fl'0 APPARENTLY  
IHE REs()t,..T  
IHE REs()t,..T  
oF.Jv'ORWl,fiL  
oF.Jv'ORWl,fiL .W&#xa3;AR. J ' ''7 ;*, 8 9 ,: FACILllY '' '' ' METHOD OF ' . co ' STATUS * % .. POWER OTHER STATUS -OISCOVEAY  
.W&#xa3;AR. J ' ''7 ;*, 8 9,: FACILllY  
'' '' ' METHOD OF '  
. co ' STATUS * % .. POWER OTHER STATUS -OISCOVEAY  
* DISCOVERY  
* DISCOVERY  
DESC.RIPTION  
DESC.RIPTION  
EE] , lHJ * l O 16 l 61 *1..__"'""-'.AJ'--A  
EE] , lHJ * l O 16 l 61 *1..__"'""-'.AJ'--A  
_ ___,I . lBJ ,__,,..-.N-.;,..11'-'--.  
_ ___,I . lBJ ,__,,..-.N-.;,..11'-'--.  
_ ___,! . 7. ** 0** 9* * .10 * * 12 13 44 ** 45 **. 46 so FORM OF ACTIVITY  
_ ___,! . 7. ** 0** 9* * .10 * * 12 13 44 ** 45 **. 46 so FORM OF ACTIVITY CONTENT *RELEASED  
CONTENT *RELEASED  
OF RELEASE AMOUNT OF ACTIVITY rn . lZJ * *I.__*  
OF RELEASE AMOUNT OF ACTIVITY  
__ ______. I LOCATION OF RELEASE 7 8 9 10 11 44 45 ' 80 PERSONNEL  
rn . lZJ * *I.__*  
__ ______. I LOCATION  
OF RELEASE 7 8 9 10 11 44 45 ' 80 PERSONNEL  
EXPOSURES  
EXPOSURES  
NUMBER * * TYPE DESCRIPTION lo Io JO I : .  
NUMBER * * TYPE DESCRIPTION lo Io JO I : .  
7 * *a s 11 * 12.. 13 ea. '. PERS'ONNEL  
7 * *a s 11 * 12.. 13 ea. '. PERS'ONNEL  
INJURIES  
INJURIES NUMBER . OESCRIPTION  
NUMBER . OESCRIPTION  
v. [EJ*1n10.l.ol  
v. [EJ*1n10.l.ol  
L--..;. .. _**-* _A_f1_. _* --------------------J 7 8 11 12 80 OFFSITE CONSEQUENCES  
L--..;. .. _**-* _A_f1_. _* --------------------J 7 8 11 12 80 OFFSITE CONSEQUENCES .Elfil I A/A 7 8 9 80 . LOSS  
.Elfil I A/A 7 8 9 80 . LOSS  
DAMAGE . TO FACILITY TYPE .DESCRIPTION  
DAMAGE . TO FACILITY  
TYPE .DESCRIPTION  
* A)ff' 7 8 9 10 80 PUBLICITY  
* A)ff' 7 8 9 10 80 PUBLICITY  
l:illl 7 8  
l:illl 7 8  
ADDITIONAL  
ADDITIONAL  
FACTOfiS  
FACTOfiS (1JUJ /v*>0' 7 89 80 EEi 7 89 BC NAME: __ R;._A_/i_V_])_o_'-_*  
(1JUJ /v*>0' 7 89 80 EEi 7 89 BC NAME: __ R;._A_/i_V_])_o_'-_*  
*_?_1: ...... 1 _c_.* _w_c._:-_r_D_M_'E----'R"-.  
*_?_1: ...... 1 _c_.* _w_c._:-_r_D_M_'E----'R"-.  
PHONE: &#xa3;xT. d...G 5   
PHONE: &#xa3;xT. d...G 5   
, . . ... .. ,. '* .. ;; . . ; ** EVENT DESCRIPTION  
, . . ... .. ,. '* .. ;; . . ; ** EVENT DESCRIPTION (Continued)  
(Continued)  
the as-found leakage of 61.0 SCFH was attributed  
the as-found  
entirely to leakage through check valve 1501-25B.  
leakage of 61.0 SCFH was attributed  
A second leak test using valves 1501-26B, i501-22B, and 1001-SB as boundaries  
entirely  
yielded a leakage rate of 4.2 SCFH: Since .the second test volume included the volume of the previous test, total through-leakage  
to leakage through check valve 1501-25B.  
A second leak test using valves 1501-26B,  
i501-22B,  
and 1001-SB as boundaries  
yielded a leakage rate of 4.2 SCFH: Since .the second test volume included  
the volume of the previous  
test, total through-leakage  
for the penetration  
for the penetration  
was well under the Tech Spec limit. A similar valve on Unit-2 failed 16cal  
was well under the Tech Spec limit. A similar valve on Unit-2 failed 16cal  
testing in early 1975. (50-249/1976-23)  
testing in early 1975. (50-249/1976-23)  
CAUSE DESCRIPTION.  
CAUSE DESCRIPTION. (Continued)  
(Continued)  
The valve was disassembled, the seat was lapped, and the packing and _Flexitallic  
The valve was disassembled,  
the seat was lapped, and the packing and _Flexitallic  
gasket were replaced.  
gasket were replaced.  
Leak-rate  
Leak-rate  
Line 173: Line 125:
annual basis should permit timely identification  
annual basis should permit timely identification  
of a recurring  
of a recurring  
problem.  
problem. * Valve 3-15.0l-25B  
* Valve 3-15.0l-25B  
is a 16-inch tilting disc check valve, manufactured  
is a 16-inch tilting disc check valve, manufactured  
by.Atwood  
by.Atwood  
and Morrill Company,  
and Morrill Company, Inc.
Inc.
}}
}}

Revision as of 14:40, 7 July 2018

Dresden Unit 3, Letter Submitting Reportable Occurrence Number 050-249/1976-23 in Accordance with Technical Specifications, Section 6.6.B
ML17252A246
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 11/04/1976
From: Stephenson B B
Commonwealth Edison Co
To: Keppler J G
NRC/RGN-III
References
BBS Ltr. #76-775
Download: ML17252A246 (3)


See also: IR 05000249/2019076

Text

.**. Comrnonv.h

Edison * Dresde,1 Nuclear Power Station R.R. #i Morris, Illinois 60450 Telephone

815/942-2920

BBS Ltr. #76-775 November 4, 1976 Mr. James Keppler, Regional Director Directorate

of

Operations

-.Region III U. S. Nuclear Regulatory

Commission

799 Roosevelt

Road Glen Ellyn, Illinois 60137 Enclosed please find Reportable

Occurrence

report number 50-249/1976-23.

This report is being submitted

to your office in accordance

with the Dresden Nuclear

Station Techriical

Section 6.6.B. A n n . : . *1Y) _/) .. * -I-. .. . B. Stephensori

  • tation Superintendent. . Dresden Nuclear Power Station BBS :jo Enclosure

cc: Director of Inspection

& *Enforcement . Direct'or

of Management

Information

& Program Control File/NRC

. LICENSEE EVd\JT REPOR. *. -. . * .. ' CONTROL BLOCK: I ' I *.1 1. I I (PLEASE PRll'JT ALL REQUIRED INFORMATION)

' 1 6 .* '*. LICENSEE * < NAME .@El I I I L. ID IR I s 13 I 7 8 9 ' 14 CATEGORY REPORT TYPE. LICENSE NUMBER 10101-10101010101-10101

15 25 REPORT SOURCE OOCl\ET NUM6ER * LICENSE TYPE 1!1111111111

26 ' 30 EVENT TYPE 10131 '31 ' 32' EVENT* DATE REPORT DATE lof1 I coN1 I I I 7 8 57 58' llJ 59 LLl 60

61 68 11 IOIOl?l71(,l

.*II II 1014171(, L 69 74 75 80 EVENT DESCRIPTION . (filg].lD!JRtAJ.G-

REFUELING-

OUTAGE LDC.AL l.t:Ak-:-RATE

TESTING; *LPC/ PRtrnARV I 7* 8' 9 . ' 80. lol31 ltSO.L..ATION'.

CA*IE:CI<

VfU;V* 3-!S-O/-J.5&

£XHtBtT£.D

A l...EAr<AC-£

RAT£. ... U!J' I, 7 Ei' 9 ' . ,. ' ' ' ' 80 IEXC£$$'0F

/HT:; T£CH SP£.C. /_JM/{ OF

SC'l="H. TH*

VAL.VE: I 7 8 9 ' ' ' ' ' ' 80 10'51 lusED VO f6R<YYI THE. 4'?'-Psf(:;

DECAY 7EST BouJVDl1R..Y

.. fYlANuALf

7 8 9 i ' ' ' ' ' ' ' " 80 lolsl I VAt..VE'.'

3-15°0! -:Y,,B J 1-lfJD A $ IGNI FICA NT WATER HC/IJ) PR£s£NTj CONSEQLJOJT1..y,, I 7 8 9. * . . . PRIME * . (5,£* /IT!FICHEV

-<;;ft£GT)

80 . * SYSTEM CAUSE COMPONENT

COMPON!:NT

-. . CODE CODE * COMPONENT

CODE SUPPLIER MANUFACTURER

VIOLATION

@0 ISIFLlsJ 1v1AIL1v1£1x1

lt!J

L'Ll 7 8 9 10 ' 11 12 17 ' 43 44 4 7 48 . CAUSE DES.CA!PTION l::TJ1£ VA/..-1/E

f:fll L-UR.6

CAUSED Bi EXCESS I 116 ])15C-To -SEAi

J 7 8 9 ' 80 lo'91 l1r1cs J.£AK-fK-G:

A77R.t8UIED, .. To TH£ PREsEl'JCG.*

OE DtRTA*No *

I 7 8 9 ' ', ' ' ' 80. ' (iE1 .I S:CRATc.HC:S

OtJ THE

$£fl'0 APPARENTLY

IHE REs()t,..T

oF.Jv'ORWl,fiL .W£AR. J ' 7 ;*, 8 9 ,: FACILllY ' METHOD OF ' . co ' STATUS * % .. POWER OTHER STATUS -OISCOVEAY

  • DISCOVERY

DESC.RIPTION

EE] , lHJ * l O 16 l 61 *1..__"'""-'.AJ'--A

_ ___,I . lBJ ,__,,..-.N-.;,..11'-'--.

_ ___,! . 7. ** 0** 9* * .10 * * 12 13 44 ** 45 **. 46 so FORM OF ACTIVITY CONTENT *RELEASED

OF RELEASE AMOUNT OF ACTIVITY rn . lZJ * *I.__*

__ ______. I LOCATION OF RELEASE 7 8 9 10 11 44 45 ' 80 PERSONNEL

EXPOSURES

NUMBER * * TYPE DESCRIPTION lo Io JO I : .

7 * *a s 11 * 12.. 13 ea. '. PERS'ONNEL

INJURIES NUMBER . OESCRIPTION

v. [EJ*1n10.l.ol

L--..;. .. _**-* _A_f1_. _* --------------------J 7 8 11 12 80 OFFSITE CONSEQUENCES .Elfil I A/A 7 8 9 80 . LOSS

DAMAGE . TO FACILITY TYPE .DESCRIPTION

  • A)ff' 7 8 9 10 80 PUBLICITY

l:illl 7 8

ADDITIONAL

FACTOfiS (1JUJ /v*>0' 7 89 80 EEi 7 89 BC NAME: __ R;._A_/i_V_])_o_'-_*

  • _?_1: ...... 1 _c_.* _w_c._:-_r_D_M_'E----'R"-.

PHONE: £xT. d...G 5

, . . ... .. ,. '* .. ;; . . ; ** EVENT DESCRIPTION (Continued)

the as-found leakage of 61.0 SCFH was attributed

entirely to leakage through check valve 1501-25B.

A second leak test using valves 1501-26B, i501-22B, and 1001-SB as boundaries

yielded a leakage rate of 4.2 SCFH: Since .the second test volume included the volume of the previous test, total through-leakage

for the penetration

was well under the Tech Spec limit. A similar valve on Unit-2 failed 16cal

testing in early 1975. (50-249/1976-23)

CAUSE DESCRIPTION. (Continued)

The valve was disassembled, the seat was lapped, and the packing and _Flexitallic

gasket were replaced.

Leak-rate

testing of the reassembled

valve was satisfactory.

In 1975, a test/drain

line was installed

on this penetration

which permitted

leak-rate

testing of check valve 3-1501-25B

for the first time since unit oper-ation began. Since this valve has performed*

satisfactorily

over a period of . several years, testing of this vaLve on an approximately

annual basis should permit timely identification

of a recurring

problem. * Valve 3-15.0l-25B

is a 16-inch tilting disc check valve, manufactured

by.Atwood

and Morrill Company, Inc.