ML17252A246: Difference between revisions
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~* . LICENSEE EVd\JT REPOR. *. -. . *.. | ~* . LICENSEE EVd\JT REPOR. *. -. . *.. | ||
' CONTROL BLOCK: I ' I *.1 1. I I (PLEASE PRll'JT ALL REQUIRED INFORMATION) | ' CONTROL BLOCK: I ' I *.1 1. I I (PLEASE PRll'JT ALL REQUIRED INFORMATION) | ||
' 1 6 LICENSEE LICENSE EVENT | ' 1 6 LICENSEE LICENSE EVENT | ||
* < NAME LICENSE NUMBER TYPE TYPE | * < NAME LICENSE NUMBER TYPE TYPE | ||
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(filg].lD!JRtAJ.G- REFUELING- OUTAGE LDC.AL l.t:Ak-:-RATE TESTING; *LPC/ PRtrnARV I 7* 8' 9 . ' 80. | (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'. | 7 lol31Ei' 9ltSO.L..ATION'. | ||
CA*IE:CI< | CA*IE:CI< | ||
VfU;V 3-!S-O/-J.5& | VfU;V 3-!S-O/-J.5& | ||
£XHtBtT£.D A l...EAr<AC-£ RAT£.... U!J' | £XHtBtT£.D A l...EAr<AC-£ RAT£.... U!J' | ||
' ' 80 I, | ' ' 80 I, | ||
Line 74: | Line 70: | ||
'. PERS'ONNEL INJURIES NUMBER . OESCRIPTION v. | '. PERS'ONNEL INJURIES NUMBER . OESCRIPTION v. | ||
[EJ*1n10.l.ol L - -. | [EJ*1n10.l.ol L - -. | ||
; ._ * * - | ; ._ * * - | ||
* _A_f1_._*- - - - - - - - - - - - - - - - - - - - J 7 8 ~ 11 12 80 OFFSITE CONSEQUENCES | * _A_f1_._*- - - - - - - - - - - - - - - - - - - - J 7 8 ~ 11 12 80 OFFSITE CONSEQUENCES | ||
Line 81: | Line 76: | ||
~ .~ 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: £xT. d...G 5 | ~ .~ 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: £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) | 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) | ||
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several years, testing of this vaLve on an approximately annual basis should permit timely identification of a recurring problem. | 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 11:18, 4 February 2020
ML17252A246 | |
Person / Time | |
---|---|
Site: | Dresden |
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) | |
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'
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7
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8 9' ' ' ' 80 I
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. CAUSE DES.CA!PTION
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' 7 ;*, 8 9 ,: FACILllY ' METHOD OF ' 'Js:t:E-:/rrjA~/t;F,.P ~}:/.!) . co
' STATUS * %.. POWER OTHER STATUS - OISCOVEAY
- DISCOVERY DESC.RIPTION EE] , 9*lHJ
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- I.__*--~N_ll_ _______.
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LOCATION OF RELEASE 80 PERSONNEL EXPOSURES NUMBER *
- TYPE DESCRIPTION
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7 * *a s 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 ~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: £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)
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.
~ ..
- .