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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 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& &#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   
. 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.
, . . ... .. ,. '* .. ;; . . ; ** 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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Revision as of 14:04, 18 May 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)
v • d • e


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.

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