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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& £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 | 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& | |||
£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. | |||
}} | }} |
Revision as of 13:31, 29 June 2018
ML17252A246 | |
Person / Time | |
---|---|
Site: | Dresden |
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.