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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Commonwe'9 Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920
\\~gulatory Docket Fl\e
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BBS Ltr. #76-865 December 8, 1976
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Mr. James G._ Keppler, Regional _Director
. Directorate of Regulatory Operations - Region III
\\U. S. Nuclear Regulatory Commission 799 Roosevelt Road iGlen Ellyn,* Illinois 60137
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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 Specificatio:~~*B.
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Station Superintendent Dresden Nuclear Power _Station 0 BBS:jo Enclosure cc: Director of Inspection & Enforcement Director of Management-Information & Program Control File/NRC 12519
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- LICENSEE EVENT REPORT e
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CONTROL BLOCK :I....__,.___._.__..____.___,I [PLEASE PR:NT ALL REQUIRED INFORMATION) 1 6 I .
LICENSEE UC.EN SE. EVENT NAME LICENSE NUMBER . TYPE ;
- TYPE
@El IIILl.DIRISl31 10101-10101 1010.1-10101 l.lfltltltltl,l 131 7 99* 14. 15 25. 26 30 . 31 32 REPORT REPORT CATEGORY TYPE. SOLJRCE DOCKET NUMBER . EVENT QA TE REPORT CATE
@12]coN'T 1* I I LbJ lbJ 101s101-101~141ql 11 It IOIKl?l~I 111;2..101~17101 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- WA~. 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..
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ATTEmPTS To TIG-HTEN TH£
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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 7 8 9 10.
l.SJ 11 l'P I 1 IP lf:lx IXI 12 17
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43 IMl3IO13 I 44 . . 47 lllJ 48 CAUSE DESCRIPTION (ol0!8 7
l:DuR1NG- OVTAG£ fYllttN/ENANCE. PEf?EORfYl£D ON VALVE' .3-1.301-13, T/.i£ UNtoAI 9 . . . . . 80 I
@§"I APPARENTLY BECAME CROSS-THREADE.D.3 'PROVIDING A LEAkAGE PATH. TH£ .LEIH<d *
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- 80
~ IAGt BECAmE APPARENT £0UOW/NG. THE 1000-PSI HYDROSTATIC T~ST . I
] _., B g FACILITY METHOD OF (SE£ ftTT p,Ut£f> S H££T) BO STATUS % POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION EEJ 7 B'
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10101s 1 10 . 12 13 Nil 44 rn.J 45 . 46
.AIA 80 I
. FORM OF ACTIVITY CONTENT
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. RELEASED lZJ . lZJ I 9 .
OF RELEASE
. 10 11 AMOUNT OF ACTIVITY Alfi*
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44
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.45 ,: .
LOCATION OF RELEASE
.____ _ _M~'A_.____________,_1 80
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PERSONNEL EXPOSURES
. NUMBER TYPE DESCRIPTION
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7 8 _9 . 11 12 13 80 PERS"ONNEL INJURIES NUMBER DESCRIPTION 7
EE]8 9101010111 12~--N'.-~-----~-----------~~ 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
--~I NA 80 .
.7 8 9
[iliJ 7 8 9 80
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'/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.