ML17252A265
| ML17252A265 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 12/08/1976 |
| From: | Stephenson B Commonwealth Edison Co |
| To: | James Keppler NRC/RGN-III |
| References | |
| BBS76-865 050-249/1976-33 | |
| Download: ML17252A265 (3) | |
Text
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'ii'-Commonwe'9 Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 Docket Fl\e .....
- BBS Ltr. #76-865 December 8, 1976 ' Mr. James G._ Keppler, Regional _Director . Directorate of Regulatory Operations
-Region III \\U. S. Nuclear Regulatory Commission 799 Roosevelt Road iGlen Ellyn,* Illinois 60137 \ Enclosed please find Reportable Occurrence report number 50-249/1976-33.
This report is being submitted to your office in accordance with the Dresden Nuclear Power Station Technical BBS:jo Enclosure cc: Director of Inspection
& Enforcement Station Superintendent Dresden Nuclear Power _Station Director of Management-Information
& Program Control File/NRC 12519 0
.... ' \ ' -LICENSEE EVENT REPORT e Y::.J " .... CONTROL BLOCK :I .... __,.___._.__..____.___,I
[PLEASE PR:NT ALL REQUIRED INFORMATION)
I . 1 6 LICENSEE UC.EN SE. EVENT NAME LICENSE NUMBER @El IIILl.DIRISl31 10101-10101 1010.1-10101 . TYPE ;
- TYPE l.lfltltltltl,l 131 7 99* 14. 15 25. 26 30 . 31 32 CATEGORY REPORT TYPE. REPORT SOLJRCE DOCKET NUMBER . EVENT QA TE REPORT CATE @12]coN'T 1* I I LbJ lbJ 11 It 7 8' 57 58 59 60 61 68 . 69 74 75 80 . EVENT DESCRIPTION
@lg] I DURING-A RbUTI tJE OPERATOR INS'PECTION., TH£ IHREAD£D C.ONNEC. TtoN * . , 7*. 8 9 . . . . . . . . 80 10131 L(uN10N) 'BETW£EN THE VAJ-V£ AND TH£ JNSTRurn*.NT 1>tPING-FOLJN]} To I 7. 8 9 . 80 @E). I 'BE. i.EAl<JNG-ON ISOJ..,AT/ON CONP£NSER.
STEAM I-IN£ FLOW SENSOR, iN5TRumEN"fl 7 8 9. . . . . . 80 l.LfNE , 1so1-AT1of\/
Fl-OW CHGCI<. VAJ.,VE" 3-t30t-23..
ATTEmPTS To TIG-HTEN TH£ I 7. 8 9 . i . . . . .... *. . . 80 lolsl I UNION CAUSED (11£ LEAKAG-£ TO !NCR£AS£.
THE ISOLATION CONDENSER WAS I 7 8 9 PRIME . . (SEG ' ATTACHE-.D .s !-+£ET) 80 SYSTEM CAUSE COMPONENT COMPONENT CODE CODE COMPONENT CODE SUPPUEA MANUFACTURER*
' VIOLATION
@0 IS IB I l.SJ l'P I 1 IP lf:lx IXI IMl3IO13 I lllJ 7 8 9 10. 11 12 17 43 44 . . 47 48 CAUSE DESCRIPTION (ol0! l:DuR1NG-OVTAG£ fYllttN/ENANCE.
PEf?EORfYl£D ON VALVE' .3-1.301-13, T/.i£ UNtoAI I 7 8 9 . . . . . 80 @§"I APPARENTLY BECAME CROSS-THREADE.D.
3 'PROVIDING A LEAkAGE PATH. TH£ .LEIH<d * .. 7 B 9
- 80 IAGt BECAmE APPARENT £0UOW/NG.
THE 1000-PSI HYDROSTATIC . I ] _., B g FACILITY METHOD OF (SE£ ftTT p,Ut£f> S H££T) BO STATUS % POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION EEJ 10101s 1 Nil rn.J .AIA I 7 B' 9. 10 . 12 13 44 45 . 46 80 . FORM OF ACTIVITY CONTENT . RELEASED OF RELEASE AMOUNT OF ACTIVITY -, LOCATION OF RELEASE 1 .. . rn lZJ . lZJ I Alfi* . .___ ___
_________
___,_ 7 . 8. 9 . . 10 11 44 .45 ,: . 80 PERSONNEL EXPOSURES . NUMBER TYPE DESCRIPTION
- rrEJ 10 IO IOI ..__ ___ M_:4 _______________
--'"-____ __. 7 8 _9 . 11 12 13 80 PERS"ONNEL INJURIES NUMBER DESCRIPTION EE] 1010101 7 8 9 11 12 80 OFFSITE CONSEQUENCES .E]fil NA 7 8 9 . 80 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION lZJ 11 7 "' 8 *9 'C *10 ' **-* 80 PUBLICITY
[ill] NA 7 8 9 80 ADDITIONAL FACTORS NA .7 8 9 80 . [iliJ 7 8 9 80
- '°
- CJ .... \ '/I
- EVENT DESCRIPTION (Continued) immediately isolated from the reactor. The HPCI system had been demonstrated .to be operable.
This is not a repetitive event. (50-249/1976-33)
CAUSE DESCRIPTION (Continued) of the reactor vessel. The union was rethreaded and reinstalted, and the if?olatic:m condenser was returned to service. No further corrective action was indicated.