ML17252A246

From kanterella
Revision as of 13:31, 29 June 2018 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
Jump to navigation Jump to search
Dresden Unit 3, Letter Submitting Reportable Occurrence Number 050-249/1976-23 in Accordance with Technical Specifications, Section 6.6.B
ML17252A246
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 11/04/1976
From: Stephenson B B
Commonwealth Edison Co
To: Keppler J G
NRC/RGN-III
References
BBS Ltr. #76-775
Download: ML17252A246 (3)


See also: IR 05000249/2019076

Text

.**. Comrnonv.h

Edison * Dresde,1

Nuclear Power Station R.R. #i Morris, Illinois

60450 Telephone

815/942-2920

BBS Ltr. #76-775 November

4, 1976 Mr. James Keppler,

Regional

Director

Directorate

of

Operations

-.Region

III U. S. Nuclear Regulatory

Commission

799 Roosevelt

Road Glen Ellyn, Illinois

60137 Enclosed

please find Reportable

Occurrence

report number 50-249/1976-23.

This report is being submitted

to your office in accordance

with the Dresden Nuclear

Station Techriical

Section 6.6.B. A n n . : . *1Y) _/) .. * -I-. .. . B. Stephensori

  • tation Superintendent.

. Dresden Nuclear Power Station BBS :jo Enclosure

cc: Director

of Inspection

& *Enforcement

. Direct'or

of Management

Information

& Program Control File/NRC

. LICENSEE

EVd\JT REPOR. *. -. . * .. ' CONTROL BLOCK: I ' I *.1 1. I I (PLEASE PRll'JT ALL REQUIRED

INFORMATION)

' 1 6 .* '*. LICENSEE

  • < NAME .@El I I I L. ID IR I s 13 I 7 8 9 ' 14 CATEGORY

REPORT TYPE. LICENSE NUMBER 10101-10101010101-10101

15 25 REPORT SOURCE OOCl\ET NUM6ER * LICENSE TYPE 1!1111111111

26 ' 30 EVENT TYPE 10131 '31 ' 32' EVENT* DATE REPORT DATE lof1 I coN1 I I I 7 8 57 58' llJ 59 LLl 60

61 68 11 IOIOl?l71(,l

.*II II 1014171(,

L 69 74 75 80 EVENT DESCRIPTION

. (filg].lD!JRtAJ.G-

REFUELING-

OUTAGE LDC.AL l.t:Ak-:-RATE

TESTING;

  • LPC/ PRtrnARV

I 7* 8' 9 . ' 80. lol31 ltSO.L..ATION'.

CA*IE:CI<

VfU;V* 3-!S-O/-J.5&

£XHtBtT£.D

A l...EAr<AC-£

RAT£. ... U!J' I, 7 Ei' 9 ' . ,. ' ' ' ' 80 IEXC£$$'0F

/HT:; T£CH SP£.C. /_JM/{ OF

SC'l="H.

TH*

VAL.VE: I 7 8 9 ' ' ' ' ' ' 80 10'51 lusED VO f6R<YYI THE. 4'?'-Psf(:;

DECAY 7EST BouJVDl1R..Y

.. fYlANuALf

7 8 9 i ' ' ' ' ' ' ' " 80 lolsl I VAt..VE'.'

3-15°0! -:Y,,B J 1-lfJD A $ IGNI FICA NT WATER HC/IJ) PR£s£NTj

CONSEQLJOJT1..y,,

I 7 8 9. * . . . PRIME * . (5,£* /IT!FICHEV

-<;;ft£GT)

80 . * SYSTEM CAUSE COMPONENT

COMPON!:NT

-. . CODE CODE * COMPONENT

CODE SUPPLIER

MANUFACTURER

VIOLATION

@0 ISIFLlsJ

1v1AIL1v1£1x1

lt!J

L'Ll 7 8 9 10 ' 11 12 17 ' 43 44 4 7 48 . CAUSE DES.CA!PTION l::TJ1£ VA/..-1/E

f:fll L-UR.6

CAUSED Bi EXCESS I 116 ])15C-To

-SEAi

J 7 8 9 ' 80 lo'91 l1r1cs J.£AK-fK-G:

A77R.t8UIED,

.. To TH£ PREsEl'JCG.*

OE DtRTA*No

I 7 8 9 ' ', ' ' ' 80. '

(iE1 .I S:CRATc.HC:S

OtJ THE

$£fl'0 APPARENTLY

IHE REs()t,..T

oF.Jv'ORWl,fiL

.W£AR. J ' 7 ;*, 8 9,: FACILllY

' METHOD OF '

. co ' STATUS * % .. POWER OTHER STATUS -OISCOVEAY

  • DISCOVERY

DESC.RIPTION

EE] , lHJ * l O 16 l 61 *1..__"'""-'.AJ'--A

_ ___,I . lBJ ,__,,..-.N-.;,..11'-'--.

_ ___,! . 7. ** 0** 9* * .10 * * 12 13 44 ** 45 **. 46 so FORM OF ACTIVITY

CONTENT *RELEASED

OF RELEASE AMOUNT OF ACTIVITY

rn . lZJ * *I.__*

__ ______. I LOCATION

OF RELEASE 7 8 9 10 11 44 45 ' 80 PERSONNEL

EXPOSURES

NUMBER * * TYPE DESCRIPTION lo Io JO I : .

7 * *a s 11 * 12.. 13 ea. '. PERS'ONNEL

INJURIES

NUMBER . OESCRIPTION

v. [EJ*1n10.l.ol

L--..;. .. _**-* _A_f1_. _* --------------------J 7 8 11 12 80 OFFSITE CONSEQUENCES

.Elfil I A/A 7 8 9 80 . LOSS

DAMAGE . TO FACILITY

TYPE .DESCRIPTION

  • A)ff' 7 8 9 10 80 PUBLICITY

l:illl 7 8

ADDITIONAL

FACTOfiS

(1JUJ /v*>0' 7 89 80 EEi 7 89 BC NAME: __ R;._A_/i_V_])_o_'-_*

  • _?_1: ...... 1 _c_.* _w_c._:-_r_D_M_'E----'R"-.

PHONE: £xT. d...G 5

, . . ... .. ,. '* .. ;; . . ; ** EVENT DESCRIPTION

(Continued)

the as-found

leakage of 61.0 SCFH was attributed

entirely

to leakage through check valve 1501-25B.

A second leak test using valves 1501-26B,

i501-22B,

and 1001-SB as boundaries

yielded a leakage rate of 4.2 SCFH: Since .the second test volume included

the volume of the previous

test, total through-leakage

for the penetration

was well under the Tech Spec limit. A similar valve on Unit-2 failed 16cal

testing in early 1975. (50-249/1976-23)

CAUSE DESCRIPTION.

(Continued)

The valve was disassembled,

the seat was lapped, and the packing and _Flexitallic

gasket were replaced.

Leak-rate

testing of the reassembled

valve was satisfactory.

In 1975, a test/drain

line was installed

on this penetration

which permitted

leak-rate

testing of check valve 3-1501-25B

for the first time since unit oper-ation began. Since this valve has performed*

satisfactorily

over a period of . several years, testing of this vaLve on an approximately

annual basis should permit timely identification

of a recurring

problem.

  • Valve 3-15.0l-25B

is a 16-inch tilting disc check valve, manufactured

by.Atwood

and Morrill Company,

Inc.