ML17252A234
| ML17252A234 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 07/15/1976 |
| From: | Stephenson B Commonwealth Edison Co |
| To: | James Keppler NRC/RGN-III |
| References | |
| BBS Ltr. #76-533 50-249/1976-10 | |
| Download: ML17252A234 (3) | |
Text
CommonweA Edison Dresden Nuclea~wer Station R.R. #1 Morris, lllinoi~ 6045~
Telephone 8'15/942-2920 BBS Ltr. #76-533 July 15, 1976 sEGf/V£D JUL2J1976 ~
U1'4 NUet.!A Mr. James G. Keppler, Regional Director Directorate of Regulatory Operations - Region III U. S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, r-llinois 60137 COMM R REGULAroar lllall ISS ION
. Secuilii
~
Enclosed please find Reportable Occurrence report number 50-249/1976-10.
This report is being submitted to your off ice in accordance with the Dresden Nuclear Power Station Technical Specifications, Section 6.6.B.
~-==--~
~~y~~
B. B. Stephenson Station Superintendent Dresden Nuclear Power Station BBS:jo Enclosure cc:
Director of Inspection & Enforcement Director of Management Information & Program Control File/NRC 7320
REPORTe CONTROL BLOCK: I 1
LICENSEE EVENT I I I I I CPLEAsE PRlf.IT ALL REQUIRED INFORMATION)
. LICENSEE NAME
@El 11" I L ID IR I S 13 I 7
8 9 14 CATEGORY
@ill CONT I I I 7
8 57 58 REPORT TYPE.
IC I 59 EVENT DESCRIPTION.
6 LICENSE NUMBER LICENSE TYPE 10101-10101010101-10101 1-41II111 I! I 15 25 26 30 REPORT SOURCE I h-I 60 DOCKET NUMBER 101s101~1012141q1 EVENT DATE 101~111~17IGI 61.
68 69 74
-EVENT TYPE 10131 31 32 REPORT DATE Io 17 1 t 13 17 I eo I 75 80
@.::@) lvv12.1NG-A RouT1~J£ 1NsrEc.T1otJ. RAc:1oR. VJl1T£"R wAs FutNP 7o eE J.£f1K.1NG-FR.om CL£ANUP I 7. 8 9 y
80
@EJ INoiJ-RF.G.£""AlcRAT1V HAT G"XOtAf.JGER 3B-ld.04Bc ti-1 WfiT"fS APOCeRff)'To BE J..£111<1!1/G-I 7
8 9 80.
[0141 I (Ro1YJ GE-iwr=:raJ n-1£ OIONJ/Eb. CDv& 8JJD THE CHflNNEb-7US£ r.HE"E:T WArr.RBox. t!CPT EXCfillNEE.d 7
8 9 i
80
~
hB-l;:lDYB !WA-S /Mr"lltDlf\\TfL'/ IS0bBTE:D. yJHEtJTtlC GHA,..JNEL (OVf'f?. (ivA$ RFmoyf)2, -rwo CR.ti.CK( v~'t:1:I 7
8 9 80 lol61 lfoVAJD iN TH~ WHD ;[OIN(tJ(r 1110::-
STlllNJ.£S~ S'fe£L :D1A.PHR.AG/Y1 SH1£lD Pt..rrrE To TH CHP.NN1-11..>a£ S~l[CT.I 7
8 9 PRME
($££" f'.'TTACl*ffD 9!Cf/) 80 SYSTEM CAUSE COMPONENT COMPONENT CODE CODE COMPONENT CODE SUPPLIER MANUFACTURER VIOLATION
@0 ICIGI ~ IHITIED<ICIHI lt{_J 1Sllll4151 lblJ 7
8 9 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION
~ I 1"HE cRP.cK~ wcRi;-- Aeea RE/*1TLV ov~ED _ sy e 1..e.ck aE m1s10N tN THF WELD. c
.... R1Nn;NG=,ed 7
8 9 SQ
~ I IPJEJ...DtNG.- 1 ANP n:sr;N<Y OFIH *AFfc*crED /1REA vJt:RE t'ER..Foema:> AccoRD1flU'Y To 8PPRovE)) QuA1...1Tv I 7
8 9 80
~
IPRoC£DURL Ht:AT E::.J<.OJANCr-.;&. 3B-J'.l.04R WM fYl!1,..,u,:l!c.1"uR77 IN srRurifE:RS wais ccRP,,'TYPE NU-1~-bHJ 7
8 9 80 EEl 7
8 FACILITY STATUS
~
9 FORM OF
% POWER 1017141 10 12 13 ACTIVITY CONTENT OTHER STATUS Nf/
44 rn RELEASED OF RELEASE AMOUNT OF ACTIVITY lZJ lKJI L...;,, _
__._N."'-'-'fi __
7 8
9 10. 11 44 PERSONNEL EXPOSURES NUMBER TYPE
~ 1010101 0 DESCRIPTION A 7
8 9 11 12 13 PERS'ONNEL INJURIES NUMBER DESCRIPTION METHOD OF DISCOVERY till 45 45 46 DISCOVERY DESCRIPTION NA 80 LOCATION OF RELEASE A.Ill 80 80 EEJ lo lo IOI.__~_N_A~~~~~~~~~~~~~~~~~~~~
7 8 9 11 12 80 OFFSITE CONSEQUENCES
. GE Nit 7
8 9 80 LOSS OR DAMAGE JO FACILITY TYPE DESCRIPTION
~.l.lJ NA 7
8 9 10 80 PUBLICITY Em 7
8 9 80 ADDITIONAL FACTORS GE]
NA 7
8 9 80
[iliJ 7
8 9 00 NAME: £. L. SECf<JN(.,£f<.
- --------**-*\\-**
EVENT DESCRIPTION (Continued)
The diaphragm acts as a seal inside the heat exchanger.
Leakage was contained with-in a controlled area and was routinely processed by the radwaste system.
The cracks were ground out, and the affected area was rewelded and dye-penetrant tested.
No discontinuities were noted, The heat exchanger was successfully leak-tested and was subsequently returned to service.
In ~ay, 1972, a crack was discovered and repaired at a different location in the sam~ circumferential diaphragm-to-tube sheet weld.
No other failures of this nature/have occurred on the cleanup non-regenerative heat exchangers on Units 2 and 3.
(50-249/1976-10)