05000237/LER-1979-017, Forwards LER 79-017/01T-0

Forwards LER 79-017/01T-0

ML17173A747
Person / Time
Site:	Dresden
Issue date:	04/09/1979
From:	Stephenson B COMMONWEALTH EDISON CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML17173A749	List: 05000237/LER-1979-017, Forwards LER 79-017/01T-0
References
79-312, NUDOCS 7904170165
Download: ML17173A747 (3)

LER-1979-017, Forwards LER 79-017/01T-0

Event date:
Report date:
2371979017R00 - NRC Website

text

Commo.lth Edison Dresden Nu r Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 BBS LTR f/79-312 April 9, 1979 James G. Keppler, Regional Director Directorate of Regulatory Operations - Region III U.S. Huclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 Reportable Occurrence Report #79-017/0iT-0, Docket #050-237 is hereby submitted to your office in accordance with DresdeD Nuclear Power Station Technical Specification 6.6.B.l.(c), abnormal degradation discovered in fuel cladding, reactor coolant pressure boundary, or primary containment.

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B. B. Stephenson Station Superintendent Dresden Nuclear Power Station BBS:lcg Enclosure cc:

Director of Inspection & Enforcement Director of Management Information & Program Control

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coN'TRoL BLOCK: I

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!PLEASE PRINT o.PE ALL _REQUIRED 1NFORMAT10N1 1

6 m Ii IL ID IR Is I 2 101 0 I 0 I -I 0 I 0 I 0 I 0I01-10 I 0 1014 I 1I1 I 1I1 101 I 10 8

9 LICtNSi:E COQE 14 15 LICENSE NUMB.ER 25 26 LICENSE TYPE JO 57 CAT 58 w;owt~**

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~:~~~ ~©10 1s10 10 10 12 13 17 101 o I 3 I 2 11 I 1 I 9 IG)I o I 4 Io I 9 I 1 I 9 IG) 60 61 DOCKET NUMBER 63 69 eVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@

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I Measured leakage of volume bounded by containment isolation valves A0-2-1601-23,24,60, I

~I 61, 62 & 63 was 1660 SCFH.

This exceeds the T.S. limits for single containment isola-1

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I tion valve allowable leakag'?, total for testable penetrations and isolation valves and!

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I maximum allowable containment leak rate..

The leakage was into the secondary contain-

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I ment and resulted in no danger to public health and safety.

Similar events

50-237/

m r 76-10 & 50-249/76-16.

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rs9 SYSTEM

• CODE

CAUSE

CAUSE CODE SUBCODE CDMPONENTCODE COMP.

SUBC006 VALVE SUBCOOE 00 IS I DI@ LU@ w@ Iv !A IL Iv IE Ix 1@ w@ w@

9 10 11

12.

13 18 SEQUENTIAL OCCURRENCE REPORT NO.

CODE I o 11 I 1 I I /I I o I r I 24 26.

2 7 28 29 LER/RO CVENTYEAR REPORT I 7 I 9 I NUMBER 21 22 23 19 REPORT TYPE L.:EJ JO 20 l.=1 31 ACTION FUTURE EFFECT SHUTDOWN r.;:::.,

ATTACHMENT NPRD-4 PRIME COMP.

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33 34 35 36 37 40 41 42 43 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

REVISION NO.

LQJ 32 COMPONENT MANUFACTURER I PI 3 I 4 I 0 I@:

44 47 iCfJOJ I Leakage identified from A0-:2-1601-60 shaft seals. Seals will be repaired and the valve9 I 1 J l I I retested prior to startup. If other sources of l'?akage are identified, a supplemen.tal I II 1 I 2 I I 1 I 3 I report will be submitted.

A0-2-1601-60:

18" rubber seated butterfly valve, model No.

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DISCOVERY.

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. LOCATION OF RELEASE @

80 PERSONNEL EXPOSURES

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9 11 12 13 80

. PERSONNEL INJURIES

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NUMBER DESCRIPTION~

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LOSS OF OR DAMAGE TO FACILITY t4J\\

TYPE

DESCRIPTION

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80 M. Parcell NAME DF PR~PARER ----------------'~-

PHONE: __ X_-_2_6_5__________ ~

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ATTACHMENT TO LICENSEE EVENT REPORT 79-017/0lT-0 COMHONWEALTH EDISON COHPANY (CWE)

DRESDEN UNIT 2 (ILDRS 2)

DOCKET ff 050-237 The measured leakage of a local leak rate test of the volume bounded by containment isolation valves A0-2-1601-23, 24, 60, 61, 62 & 63 was 1660 SCFH.

This leak rate is in excess of the allowable leak rate for a con-tainment isolation valve (29.38 SCFH), the. total for testable penetra-tions and isolation valves (176.29 SCFH) and maximum containment leak rate (783.5 SCFH) (T.S; 4.7.A.2.e).

Leakage was identified from the shaft.seals of A0-2-1601-60 which is an 18" rubber se~ted butterfly valve.

Since this leakage is into the secondary containment and is within the capacity.of the standby gas treatment system (4000 CFM),

this event presented no danger to public.health and safety.

The shaft seals will be repaired prior to unit startup and the volume retested.

If it is-determined that all the excess leakage was not through the A0-2-1601-60 shaft seals, a supplmental report will be submitted.