ML17252A251

From kanterella
Revision as of 12:18, 4 February 2020 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Transmittal of Reportable Occurrence Report No. 50-249/1976-30
ML17252A251
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 11/22/1976
From: Stephenson B
Commonwealth Edison Co
To: James Keppler
NRC/RGN-III
References
BBS Ltr. #76-815 50-249/1976-30
Download: ML17252A251 (3)


Text

    • ~-- *-**-.

Commonwe4 Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920

~gulatory Docket File BBS Ltr. #76-815 November 22, 1976 Mr. James G. Keppler, Regional Dlrector Djrectorate of Regulatory Operations - Region 111 U. S. Nuclear Regulatory Commission 799 Roosev~lt Road Glen Ellyn, 11 l inois 60137 Enclosed please find Reportable OccurreMce report number 50-249/1976-30.

This report is being submitted to your office in accordance with the Dresden Nuclear Power Station Technical Specifications, Section 6~6.B. *

~~-

<"'"'1

~"'-

.. .c~~""""-

. Ste enson Station Superintendent

.Dresden Nuclear P6wer Siatfon BBS :jo Enclosure cc: Director of Inspection & Enforcement Directcir of Management Information & Program C6ntrol Fi 1e/NRC 12111

_,,

  • LICENSEE EVENT REPORT e CONTROL BLO~K: I I~

1 I I I I 6

[PLEASE PRINT ALL REQUIRED INFORMATION)

LICENSEE LICENSE EVENT

__ NAME LICENSE NUMBER TYPE TYPE

--~~II IL ID IRIS 13 I 10101-IOIOIOI 010!-IOIQJ l-41 I I I I I I I I 10131 7 8 9 . 14 . 15 25 26 30 31 32 REPORT REFORT CATEGORY TYPE. SOURCE DOCKET NUMBER EVENT OA TE REPORT DATE

  • @E]_coN'T I I I l!J L6J IOl5IOl~lbl21~191 II IOl~l~l7lbl l/lflf IWl7101
7. 8 57 58 59 60 61 68 . 69 74 75 BU EVENT DESCRIPTION

[Qlli) I DVRJAJG-- REFUE/..JN<;. OVTl-IG-£ }..J)C:ff L /...Elll<-RAT£ 7-Gst/)JG-., THE. Tl P PURGE .J 7 8 9 . . 80

@El I CHECK VALVE EXHIBITED A LEAK.AG-£ 'RATE OE I ~g- SCFH (T£CH SP£C Ltm1T: 19.3~11 7 8 9 . . 80 lol41 I SC£H). TH£ VALY£ WBS REMOVE:D FRom "TH£ SYsTE.M AND CLEANED WITH I 7 8 9

  • 80

~: lcomPR£SSE]) litR .. FOLLDWJNG- R£1NSTAJ..J.,,flTJON OE rkt=. VA.l..VE, TESTING: YIELDED l

' 7 8 9 . .

  • 80

.{filfil WELL E: l.J I ERfrt1SS1 f:. LlfYJ T THIS 15 TE FtRS 1 0 9 PHJMe (SEE ltTTflCH£.1) SNcE.T 00 SYSTEM CAUSE COMPONENT. COMPONENT CODE . CODE COMPONENT CODE SUPPLIER MANUFACTURER VIOLATION

~ II IF I l&J Iv I A IL Iv I£ Ix I lfil IX 1't I q I'! I LYJ 7 8 9 10 11 12 . 17 43 44 47 48 CAUSE DESCRIPTION (oj0j I TH£ VALY£ l..EAkAGE WAS APPARENTJ..Y CAUS£D BY PIRT ON TIIE BALl OB.. Ti-uzJ.

7 8 9 . . ' . . .  : 80 7

lo191.8 9lscAl/NG--

ABEA. AS 5TATEJ) ABOVE, THE VALV£ wes CLEANED WITH CQfYIPRs.<"££D

'. . . 80 I

~ I AIR} w /TH SATISFACTORY. RE5:.Ul-T5.. PUF?ING- R£f\GTOR OPERATION, THE TI p . ' I METHOD o~

7. 8 9 FACILITY (SE.£ l!TTAGHED <;;ffE"ET) eo .

STATUS 'lli POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION fil] WJ IO IO lo I I NA lliJ _I___--'-M-~_-.*_ _ _ _ _ _ _ J 7 8 9 10 12 13 . 44 45 . 46 80

.FORM OF ACTIVITY *. CONTENT 7

rn 8 RELEASED

-lb.I 9

OF RELEASE LbJ I....._

10 11 AMOUNT OF ACTIVITY

__;M_l'l_ _ __.

44 AJA

. LOCATION OF* RELEASE 45 80 j

PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION (fill0* Io 1 9

  • Io Io11I lZJ 12

._____.;.::.M:..:...:~--_..;..,;----------------~----~

13 80 PERS"ONNEL INJURIES NUMBER DESCRIPTION VE 1010101 7 .. 8 .9 11 12 Nit 80 O.FFSITE CONSEQUENCES

.[ill] ft 7 8 9 . BO LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION E@.lb.J M 7 8 9 . 10 80 PUBLICITY

(£0 7 B 9 80 ADDITIONAL FACTORS

~8 7 9 80

[iliJ 7 89 BC NAME: £[)WARD .l. [;ECK!NG"£"R PHONE: £ XT, d..(, 5

/

EVENT DESCRIPTION (Continued) time this valve has been local leak-rate tested since unit operations began.

(50-249/1976-30)

CAUSE DESCRIPTION (Continued) purge line is 'connected to the nitrogen makeup system, which is maintained at approximately 100 PSIG. Consequently, it is considered extremely improbable that any through-leakage would otcur, even with drywell pressure at the design limit of 48 PSIG. The safety significance of this event is further minim1zed by the physical size of the*purge 1 ine (1/4 - inch). To ensure the timely identification of a recurring problem, surveillance testing of the Tl.P* purge

~heck valves has been added to the refueling outage LLRT procedures for both Units 2 and 3. The valve is a 1/4 - inch ball check valve, model C400-10S,

  • manufactured by Manetrol. . .

-~ ... . ::: ... . . ~