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 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 Specificatio:~~*B.
~&{f~f~
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
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 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.. 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 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
~.
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*
M~'A_. _________ ___,_
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 ~--N'.-~-----~-----------~~
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
--~I 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.