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{{#Wiki_filter:.**. Comrnonv.h Edison
{{#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  
* 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.
-.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.
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
A   n n.: .*1Y).. _/) ~. * -I- .
* tation Superintendent. . Dresden Nuclear Power Station BBS :jo Enclosure cc: Director of Inspection  
h un~              ~
& *Enforcement . Direct'or of Management Information  
                                                  . B. Stephensori
& Program Control File/NRC
* tation Superintendent.       .
. LICENSEE EVd\JT REPOR. *. -. . * .. ' CONTROL BLOCK: I ' I *.1 1. I I (PLEASE PRll'JT ALL REQUIRED INFORMATION)  
Dresden Nuclear Power Station BBS :jo Enclosure cc:   Director of Inspection & *Enforcement
' 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
    . Direct'or of Management Information & Program Control File/NRC
* 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'.
                              ~*                                                  .     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.
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7
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* SYSTEM CAUSE COMPONENT COMPON!:NT  
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-. . CODE CODE
        .
* COMPONENT CODE SUPPLIER MANUFACTURER VIOLATION  
* SYSTEM         CAUSE                                                           COMPONENT                 COMPON!:NT                                               -             .
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                      . CODE         CODE
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OE DtRTA*No
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* I 7 8 9 ' ', ' ' ' 80. ' (iE1 .I S:CRATc.HC:S OtJ THE  
                  . CAUSE DES.CA!PTION
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* DISCOVERY DESC.RIPTION EE] , lHJ
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* l O 16 l 61 *1..__"'""-'.AJ'--A
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                        ' STATUS                 * %.. POWER                             OTHER STATUS       -   OISCOVEAY
* 12 13 44 ** 45 **. 46 so FORM OF ACTIVITY CONTENT *RELEASED OF RELEASE AMOUNT OF ACTIVITY rn . lZJ * *I.__*
* DISCOVERY DESC.RIPTION EE] , 9*lHJ
__ ______. I LOCATION OF RELEASE 7 8 9 10 11 44 45 ' 80 PERSONNEL EXPOSURES NUMBER *
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    . 7.
7 * *a s 11
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* 13                                       45     **. 46                                                                           so FORM OF ACTIVITY         CONTENT rn .lZJ 7        8
: 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
                      *RELEASED 9
* 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_'-_*  
OF RELEASE
*_?_1: ...... 1 _c_.* _w_c._:-_r_D_M_'E----'R"-.
* l~J 10          11 AMOUNT OF ACTIVITY
PHONE: &#xa3;xT. d...G 5
                                                              *I.__*--~N_ll_ _______.
, . . ... .. ,. '* .. ;; . . ; ** EVENT DESCRIPTION (Continued) the as-found leakage of 61.0 SCFH was attributed entirely to leakage through check valve 1501-25B.
44 I
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)
45    '
LOCATION OF RELEASE 80 PERSONNEL EXPOSURES NUMBER           *
* TYPE               DESCRIPTION
        ~            lo Io JO11I : *~                        . ~-.....::.JtJ_tt~--,---.,.---------~-------~-~-"-'-'-'-:-'-'------__.___,
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            '.     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 ~F;l DAMAGE . TO FACILITY TYPE       .DESCRIPTION *
        ~ .~                                            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
 
        .
        ;
                                                            **
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)
CAUSE DESCRIPTION. (Continued)
The valve was disassembled, the seat was lapped, and the packing and _Flexitallic gasket were replaced.
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.
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     .
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*
several years, testing of this vaLve on an approximately annual basis should permit timely identification of a recurring problem.
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.
* Valve 3-15.0l-25B is a 16-inch tilting disc check valve, manufactured by.Atwood and Morrill Company, Inc.}}
., .
... ..
,.
*
~  ..
;;  .}}

Revision as of 19:31, 29 October 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 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'.

' .

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8 9' ' ' ' 80 I

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.

  • SYSTEM CAUSE COMPONENT COMPON!:NT - .

. CODE CODE

  • COMPONENT CODE SUPPLIER MANUFACTURER VIOLATION

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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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