ML17252A251: Difference between revisions
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{{#Wiki_filter:**~-- *-**-. | {{#Wiki_filter:**~-- *-**-. | ||
Commonwe4 Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 | 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 | ~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. | ||
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. * | This report is being submitted to your office in accordance with the Dresden Nuclear Power Station Technical Specifications, Section 6~6.B. * | ||
~~- | ~~- | ||
<"'"'1 | <"'"'1 | ||
~"'- | ~"'- | ||
.. .c~~""""- | .. .c~~""""- | ||
. Ste enson Station Superintendent | . 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 | .Dresden Nuclear P6wer Siatfon BBS :jo Enclosure cc: Director of Inspection & Enforcement Directcir of Management Information & Program C6ntrol Fi 1e/NRC 12111 | ||
Line 52: | Line 47: | ||
7 8 9 . . ' . . . : 80 7 | 7 8 9 . . ' . . . : 80 7 | ||
lo191.8 9lscAl/NG-- | lo191.8 9lscAl/NG-- | ||
ABEA. AS 5TATEJ) ABOVE, THE VALV£ wes CLEANED WITH CQfYIPRs.<"££D | |||
ABEA. AS 5TATEJ) ABOVE, THE VALV£ | |||
wes | |||
CLEANED WITH CQfYIPRs.<"££D | |||
'. . . 80 I | '. . . 80 I | ||
~ I AIR} w /TH SATISFACTORY. RE5:.Ul-T5.. PUF?ING- R£f\GTOR OPERATION, THE TI p . ' I METHOD o~ | ~ I AIR} w /TH SATISFACTORY. RE5:.Ul-T5.. PUF?ING- R£f\GTOR OPERATION, THE TI p . ' I METHOD o~ | ||
Line 69: | Line 59: | ||
__;M_l'l_ _ __. | __;M_l'l_ _ __. | ||
44 AJA | 44 AJA | ||
. LOCATION OF* RELEASE | . LOCATION OF* RELEASE 45 80 j | ||
45 80 j | |||
PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION (fill0* Io 1 9 | PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION (fill0* Io 1 9 | ||
* Io Io11I lZJ 12 | * Io Io11I lZJ 12 | ||
Line 87: | Line 75: | ||
~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, | ~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. . . | *manufactured by Manetrol. . . | ||
-~ ... . ::: ... . . ~}} | -~ ... . ::: ... . . ~}} |
Latest revision as of 12:18, 4 February 2020
ML17252A251 | |
Person / Time | |
---|---|
Site: | Dresden ![]() |
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~
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. . .
-~ ... . ::: ... . . ~