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{{#Wiki_filter:.**. 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   
{{#Wiki_filter:.**. Comrnonv.h  
. 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& &#xa3;XHtBtT&#xa3;.D A l...EAr<AC-&#xa3; RAT&#xa3;. ... U!J' I, 7 Ei' 9 ' . ,. ' ' ' ' 80 IEXC&#xa3;$$'0F /HT:; T&#xa3;CH SP&#xa3;.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&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 -<;;ft&#xa3;GT) 80 . * SYSTEM CAUSE COMPONENT COMPON!:NT -. . CODE CODE * COMPONENT CODE SUPPLIER MANUFACTURER VIOLATION @0 ISIFLlsJ 1v1AIL1v1&#xa3;1x1 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 f:fll L-UR.6 CAUSED Bi EXCESS I 116 ])15C-To -SEAi J 7 8 9 ' 80 lo'91 l1r1cs J.&#xa3;AK-fK-G: A77R.t8UIED, .. To TH&#xa3; PREsEl'JCG.* OE DtRTA*No * I 7 8 9 ' ', ' ' ' 80. ' (iE1 .I S:CRATc.HC:S OtJ THE $&#xa3;fl'0 APPARENTLY IHE REs()t,..T oF.Jv'ORWl,fiL .W&#xa3;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: &#xa3;xT. d...G 5   
Edison * Dresde,1  
, . . ... .. ,. '* .. ;; . . ; ** 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.
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&  
&#xa3;XHtBtT&#xa3;.D  
A l...EAr<AC-&#xa3;  
RAT&#xa3;. ... U!J' I, 7 Ei' 9 ' . ,. ' ' ' ' 80 IEXC&#xa3;$$'0F  
/HT:; T&#xa3;CH SP&#xa3;.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&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  
-<;;ft&#xa3;GT)  
80 . * SYSTEM CAUSE COMPONENT  
COMPON!:NT  
-. . CODE CODE * COMPONENT  
CODE SUPPLIER  
MANUFACTURER  
VIOLATION  
@0 ISIFLlsJ  
1v1AIL1v1&#xa3;1x1  
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  
f:fll L-UR.6  
CAUSED Bi EXCESS I 116 ])15C-To  
-SEAi  
J 7 8 9 ' 80 lo'91 l1r1cs J.&#xa3;AK-fK-G:  
A77R.t8UIED,  
.. To TH&#xa3; PREsEl'JCG.*  
OE DtRTA*No  
*  
I 7 8 9 ' ', ' ' ' 80. '  
(iE1 .I S:CRATc.HC:S  
OtJ THE  
$&#xa3;fl'0 APPARENTLY  
IHE REs()t,..T  
oF.Jv'ORWl,fiL  
.W&#xa3;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: &#xa3;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.
}}
}}

Revision as of 13:31, 29 June 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.