ML17252A265

Letter Submitting Reportable Occurrence Number 050-249/1976-33 in Accordance with Technical Specifications, Section 6.6.B

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

~;: *!~-=-

I

'ii'-

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~

Station Superintendent Dresden Nuclear Power _Station 0 BBS:jo Enclosure cc: Director of Inspection & Enforcement Director of Management-Information & Program Control File/NRC 12519

.... ' \Y::.J

- LICENSEE EVENT REPORT e 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..

7. 8 9 . i . . . .

ATTEmPTS To TIG-HTEN TH£

.... *. . . 80 I

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

~

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 *

.. 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 7 B'

~.

9.

10101s 1 10 . 12 13 Nil 44 rn.J 45 . 46

.AIA 80 I

. FORM OF ACTIVITY CONTENT

.rn7 . 8.

. RELEASED lZJ . lZJ I 9 .

OF RELEASE

. 10 11 AMOUNT OF ACTIVITY Alfi*

44

.45 ,: .

LOCATION OF RELEASE

.____ _ _M~'A_.____________,_1 80 PERSONNEL EXPOSURES

. NUMBER TYPE DESCRIPTION

• rrEJ 10 IO IOI ~ .._____ M_:4_______________--'"-_ _ _ ___.

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

• '° *

.... \

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.