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| number = ML17252A246
| number = ML17252A246
| issue date = 11/04/1976
| issue date = 11/04/1976
| title = Dresden Unit 3, Letter Submitting Reportable Occurrence Number 050-249/1976-23 in Accordance with Technical Specifications, Section 6.6.B
| title = Letter Submitting Reportable Occurrence Number 050-249/1976-23 in Accordance with Technical Specifications, Section 6.6.B
| author name = Stephenson B B
| author name = Stephenson B
| author affiliation = Commonwealth Edison Co
| author affiliation = Commonwealth Edison Co
| addressee name = Keppler J G
| addressee name = Keppler J
| addressee affiliation = NRC/RGN-III
| addressee affiliation = NRC/RGN-III
| docket = 05000237, 05000249
| docket = 05000237, 05000249
Line 14: Line 14:
| page count = 3
| page count = 3
}}
}}
See also: [[followed by::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 G~ Keppler, Regional Director Directorate of R~gulatory 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.
815/942-2920  
This report is being submitted to your office in accordance with the Dresden Nuclear Powe~ Station Techriical ~pecifications, Section 6.6.B.
BBS Ltr. #76-775 November 4, 1976 Mr. James Keppler, Regional Director Directorate  
A   n n.: .*1Y).. _/) ~. * -I- .
of  
h un~              ~
Operations  
                                                  . B. Stephensori
-.Region III U. S. Nuclear Regulatory  
* tation Superintendent.       .
Commission  
Dresden Nuclear Power Station BBS :jo Enclosure cc:   Director of Inspection & *Enforcement
799 Roosevelt  
    . Direct'or of Management Information & Program Control File/NRC
Road Glen Ellyn, Illinois 60137 Enclosed please find Reportable  
 
Occurrence  
                              ~*                                                  .     LICENSEE EVd\JT REPOR.                                                   *.         -. .                 *..
report number 50-249/1976-23.  
                                  ' CONTROL BLOCK:                         I '           I *.1 1. I I                                             (PLEASE PRll'JT ALL REQUIRED INFORMATION)
This report is being submitted  
                                                                        '   1                             6 LICENSEE                                                                                                                 LICENSE                        EVENT
to your office in accordance  
        * <                         NAME                                                       LICENSE NUMBER                                                TYPE                          TYPE
with the Dresden Nuclear  
        .@El II I L. ID IR I s 13 I                                       10101-10101010101-10101                                              1!1111111111 10131 7       8 9                                         ' 14           15                                                      25          26                          ' 30 '31 ' 32' REPORT            REPORT CATEGORY                 TYPE.         SOURCE                   OOCl\ET NUM6ER
Station Techriical  
* EVENT* DATE                               REPORT DATE lof1 IcoN1 I I I llJ LLl                                                     101s101~101~1~191                              11 IOIOl?l71(,l                             .*II   II 1014171(, L 7        8            57        58'              59            60          61                                    68      69                                     74     75                           80 EVENT DESCRIPTION .
Section 6.6.B. A n n . : . *1Y) _/) .. * -I-. .. . B. Stephensori  
(filg].lD!JRtAJ.G-                         REFUELING- OUTAGE                                   LDC.AL l.t:Ak-:-RATE TESTING; *LPC/                                                     PRtrnARV           I 7*       8' 9       .                                                   '                                                                                                                                 80.
* tation Superintendent. . Dresden Nuclear Power Station BBS :jo Enclosure  
7 lol31Ei' 9ltSO.L..ATION'.
cc: Director of Inspection  
CA*IE:CI<
& *Enforcement . Direct'or  
VfU;V       3-!S-O/-J.5&
of Management  
                                                                                                                                &#xa3;XHtBtT&#xa3;.D                 A         l...EAr<AC-&#xa3; RAT&#xa3;.... U!J'
Information  
                                                                                                                                                                                '      '                        80 I,
& Program Control File/NRC
7
. LICENSEE EVd\JT REPOR. *. -. . * .. ' CONTROL BLOCK: I ' I *.1 1. I I (PLEASE PRll'JT ALL REQUIRED INFORMATION)  
        ~ IEXC&#xa3;$$'0F /HT:; T&#xa3;CH SP&#xa3;.C. /_JM/{ OF .J.Cf.~f!/_. SC'l="H. TH OTH~g*. VAL.VE:
' 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
8 9'           ' ' ''       '                                                                                                                                                                   80 I
15 25 REPORT SOURCE OOCl\ET NUM6ER * LICENSE TYPE 1!1111111111
10'581      lusED             VO             f6R<YYI THE. 4'?'-Psf(:; PRESSUfV~                                          DECAY                 7EST BouJVDl1R..Y .. fYlANuALf 7           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
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  
* SYSTEM         CAUSE                                                           COMPONENT                 COMPON!:NT                                               -             .
.*II II 1014171(, L 69 74 75 80 EVENT DESCRIPTION . (filg].lD!JRtAJ.G-
                      . CODE         CODE
REFUELING-
* COMPONENT CODE                   SUPPLIER               MANUFACTURER                     VIOLATION
OUTAGE LDC.AL l.t:Ak-:-RATE  
        @0 ISIFLlsJ                                         1v1AIL1v1&#xa3;1x1                               lt!J             1A1s1*~1s1                                L'Ll 7       8 9       10           ' 11                 12                                 17     ' 43             44                         47                48
TESTING; *LPC/ PRtrnARV I 7* 8' 9 . ' 80. lol31 ltSO.L..ATION'.  
                  . CAUSE DES.CA!PTION
CA*IE:CI<  
        ~ l::TJ1&#xa3; VA/..-1/E f:fll L-UR.6 'WA~ CAUSED Bi EXCESS I 116 ])15C-To -SEAi 1-&#xa3;AKAG-~.                                                                                                                    J 7       8 9                                                 '                                                                                                                                           80 lo'91 l1r1cs J.&#xa3;AK-fK-G: i,.JA~ A77R.t8UIED, ..To TH&#xa3; PREsEl'JCG.* OE DtRTA*No
VfU;V* 3-!S-O/-J.5&  
* SIYIAL-t~                                                                                                                I 7       8 9                 '                                                                                                                         ', '                                       ' ' 80. '
&#xa3;XHtBtT&#xa3;.D  
,.~.: (iE1 .I S:CRATc.HC:S OtJ THE Vf/LV~ $&#xa3;fl'0 APPARENTLY IHE REs()t,..T oF.Jv'ORWl,fiL .W&#xa3;AR. J
A l...EAr<AC-&#xa3;  
  ' '' 7 ;*, 8 9 ,: FACILllY         ''       ''             '                                                 METHOD OF                                 '   'Js:t:E-:/rrjA~/t;F,.P ~}:/.!)            . co
RAT&#xa3;. ... U!J' I, 7 Ei' 9 ' . ,. ' ' ' ' 80 IEXC&#xa3;$$'0F  
                        ' STATUS                * %.. POWER                             OTHER STATUS       -   OISCOVEAY
/HT:; T&#xa3;CH SP&#xa3;.C. /_JM/{ OF  
* DISCOVERY DESC.RIPTION EE] , 9*lHJ
SC'l="H. TH*  
* lO 16 l *6112                *1..__"'""-'.AJ'--A_      ___,I44 .** lBJ           ,__,,..-.N-.;,..11'-'--.---~..,.-.-'-._-_                                 ___,!
VAL.VE: I 7 8 9 ' ' ' ' ' ' 80 10'51 lusED VO f6R<YYI THE. 4'?'-Psf(:;  
    . 7.
DECAY 7EST BouJVDl1R..Y  
* 0**                         * .10
.. fYlANuALf  
* 13                                       45     **. 46                                                                           so FORM OF ACTIVITY         CONTENT rn .lZJ 7        8
7 8 9 i ' ' ' ' ' ' ' " 80 lolsl I VAt..VE'.'  
                      *RELEASED 9
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  
OF RELEASE
-<;;ft&#xa3;GT)  
* l~J 10          11 AMOUNT OF ACTIVITY
80 . * SYSTEM CAUSE COMPONENT  
                                                              *I.__*--~N_ll_ _______.
COMPON!:NT  
44 I
-. . CODE CODE * COMPONENT  
45    '
CODE SUPPLIER MANUFACTURER  
LOCATION OF RELEASE 80 PERSONNEL EXPOSURES NUMBER           *
VIOLATION  
* TYPE               DESCRIPTION
@0 ISIFLlsJ 1v1AIL1v1&#xa3;1x1  
        ~            lo Io JO11I : *~                        . ~-.....::.JtJ_tt~--,---.,.---------~-------~-~-"-'-'-'-:-'-'------__.___,
lt!J  
7 * *a        s                            12.. 13                                                                                                                                                      ea.
L'Ll 7 8 9 10 ' 11 12 17 ' 43 44 4 7 48 . CAUSE DES.CA!PTION l::TJ1&#xa3; VA/..-1/E  
            '.      PERS'ONNEL INJURIES NUMBER .               OESCRIPTION            v.
f:fll L-UR.6  
[EJ*1n10.l.ol                            L - -.
CAUSED Bi EXCESS I 116 ])15C-To -SEAi  
                                                        ; ._ * * -
J 7 8 9 ' 80 lo'91 l1r1cs J.&#xa3;AK-fK-G:  
* _A_f1_._*- - - - - - - - - - - - - - - - - - - - J 7        8  ~                11      12                                                                                                                                                                80 OFFSITE CONSEQUENCES
A77R.t8UIED, .. To TH&#xa3; PREsEl'JCG.*  
      .Elfil I                      A/A 7        8 9                                                                                                                                                                                            80
OE DtRTA*No *  
                  . LOSS ~F;l DAMAGE . TO FACILITY TYPE        .DESCRIPTION *
I 7 8 9 ' ', ' ' ' 80. ' (iE1 .I S:CRATc.HC:S  
        ~ .~                                            A)ff' 7        8 9            10                                                                                                                                                                              80 PUBLICITY l:illl8 7            81..;_---L.~L-----------------,-------------'-----.,---~--'-----"------.---::-2~J ADDITIONAL FACTOfiS (1JUJ                                    /v*>0' 7      89                                                                                                                                                                                              80 EEi89 7                                                                                                                                                                                                      BC NAME: _ _            R;._A_/i_V_])_o_'-_**_?_1:...... 1 _c_.*_w_c._:-_r_D_M_'E----'R"-.---~ PHONE: &#xa3;xT.                                      d...G 5
OtJ THE  
 
$&#xa3;fl'0 APPARENTLY  
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 leak~rate testing in early 1975. (50-249/1976-23)
IHE REs()t,..T  
CAUSE DESCRIPTION. (Continued)
oF.Jv'ORWl,fiL .W&#xa3;AR. J ' ''7 ;*, 8 9 ,: FACILllY '' '' ' METHOD OF ' . co ' STATUS * % .. POWER OTHER STATUS -OISCOVEAY  
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.
* DISCOVERY  
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    .
DESC.RIPTION  
several years, testing of this vaLve on an approximately annual basis should permit timely identification of a recurring problem.
EE] , lHJ * l O 16 l 61 *1..__"'""-'.AJ'--A
* Valve 3-15.0l-25B is a 16-inch tilting disc check valve, manufactured by.Atwood and Morrill Company, Inc.
_ ___,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.
}}

Latest revision as of 08:07, 24 February 2020

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 G~ Keppler, Regional Director Directorate of R~gulatory 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 Powe~ Station Techriical ~pecifications, Section 6.6.B.

A n n.: .*1Y).. _/) ~. * -I- .

h un~ ~

. 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 LICENSE EVENT

  • < NAME LICENSE NUMBER TYPE TYPE

.@El II I L. ID IR I s 13 I 10101-10101010101-10101 1!1111111111 10131 7 8 9 ' 14 15 25 26 ' 30 '31 ' 32' REPORT REPORT CATEGORY TYPE. SOURCE OOCl\ET NUM6ER

  • EVENT* DATE REPORT DATE lof1 IcoN1 I I I llJ LLl 101s101~101~1~191 11 IOIOl?l71(,l .*II II 1014171(, L 7 8 57 58' 59 60 61 68 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.

7 lol31Ei' 9ltSO.L..ATION'.

CA*IE:CI<

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

£XHtBtT£.D A l...EAr<AC-£ RAT£.... U!J'

' ' 80 I,

7

~ IEXC£$$'0F /HT:; T£CH SP£.C. /_JM/{ OF .J.Cf.~f!/_. SC'l="H. TH OTH~g*. VAL.VE:

8 9' ' ' ' 80 I

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. CAUSE DES.CA!PTION

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LOCATION OF RELEASE 80 PERSONNEL EXPOSURES NUMBER *

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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 leak~rate 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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