ML17252A246: Difference between revisions

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


=Text=
=Text=
{{#Wiki_filter:.**. Comrnonv.h  
{{#Wiki_filter:.**. Comrnonv.h Edison
Edison * Dresde,1 Nuclear Power Station R.R. #i Morris, Illinois 60450 Telephone  
* 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  
815/942-2920  
-.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.
BBS Ltr. #76-775 November 4, 1976 Mr. James Keppler, Regional Director Directorate  
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
of  
* tation Superintendent. . Dresden Nuclear Power Station BBS :jo Enclosure cc: Director of Inspection  
Operations  
& *Enforcement . Direct'or of Management Information  
-.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   
& Program Control File/NRC   
. LICENSEE EVd\JT REPOR. *. -. . * .. ' CONTROL BLOCK: I ' I *.1 1. I I (PLEASE PRll'JT ALL REQUIRED INFORMATION)  
. 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  
' 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
15 25 REPORT SOURCE OOCl\ET NUM6ER * LICENSE TYPE 1!1111111111  
* 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  
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  
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61 68 11 IOIOl?l71(,l  
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REFUELING-
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* DISCOVERY  
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DESC.RIPTION  
*_?_1: ...... 1 _c_.* _w_c._:-_r_D_M_'E----'R"-.
EE] , lHJ * l O 16 l 61 *1..__"'""-'.AJ'--A  
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_ ___,! . 7. ** 0** 9* * .10 * * 12 13 44 ** 45 **. 46 so FORM OF ACTIVITY CONTENT *RELEASED  
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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   
PHONE: &#xa3;xT. d...G 5   
, . . ... .. ,. '* .. ;; . . ; ** EVENT DESCRIPTION (Continued)  
, . . ... .. ,. '* .. ;; . . ; ** EVENT DESCRIPTION (Continued) the as-found leakage of 61.0 SCFH was attributed entirely to leakage through check valve 1501-25B.
the as-found leakage of 61.0 SCFH was attributed  
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)
entirely to leakage through check valve 1501-25B.  
CAUSE DESCRIPTION. (Continued)
A second leak test using valves 1501-26B, i501-22B, and 1001-SB as boundaries  
The valve was disassembled, the seat was lapped, and the packing and _Flexitallic gasket were replaced.
yielded a leakage rate of 4.2 SCFH: Since .the second test volume included the volume of the previous test, total through-leakage  
Leak-rate testing of the reassembled valve was satisfactory.
for the penetration  
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*
was well under the Tech Spec limit. A similar valve on Unit-2 failed 16cal  
satisfactorily over a period of . several years, testing of this vaLve on an approximately annual basis should permit timely identification of a recurring problem.
testing in early 1975. (50-249/1976-23)  
* Valve 3-15.0l-25B is a 16-inch tilting disc check valve, manufactured by.Atwood and Morrill Company, Inc.}}
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 14:04, 17 August 2019

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
Commonwealth Edison Co
To: James Keppler
NRC/RGN-III
References
BBS Ltr. #76-775
Download: ML17252A246 (3)
v • d • e


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.
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