ML18139B181
| ML18139B181 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  |
| Issue date: | 03/11/1981 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Ferguson J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| References | |
| NUDOCS 8103200314 | |
| Download: ML18139B181 (3) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION In Reply Refer To:
RII:JPO 50-338, 50-339 50-404 I 50-405
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REGION II 101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 MAR 11.1981 Virginia Electric and Power Company ATTN: J. H. Ferguson
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Ri chmond, VA 23261 Gentlemen:
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The enclosed IE Information Notice No. 81-06 contains information that may be applicable to your facility regarding the failure of an !TE Model K-600 cir-cuit breaker.
No specific action or response is requested at this ti me; however, pending the results of NRC staff evaluations of this matter, further licensee actions may be requested.
Should you have any questions regarding this information notice, please contact this office.
Enclosures:
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Sincerely,
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'Di re*ctor *'*
- 1.
IE Information Notice No. 81-06
- 2.
List of Recently Issued IE Information Notices cc w/encl:
W. R. Cartwright, Station Manager P. G. Perry, Senior Resident Engineer J. L. Wilson, Manager f
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e UNiTED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 March 11, 1981 SSINS No. :
6835 Accession No.:
8011040269 IN 81-06 IE Information Notice No. 81-06:
FAILURE OF ITE MODEL K-600 CIRCUIT BREAKER
Purpose:
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a matter thcit *c6~ld adversely affect the safety of nuclear power plants.
Toward this end, this information notice alerts holders of operating licenses and construction permits of a possibly generic deficiency involving Model K-600 circuit breakers manufactured by ITE.
Description of Circumstance:
By letter dated February 20, 1981, the Sacramento Municipal Utility District informed us that, while performing preventive maintenance on electrical circuit breakers at its Rancho Seco facility, an ITE Model K-600 breaker was observed not to trip.
An investigation revealed that a tripping coil wire had slipped out of its terminal.
Further examinations revealed that the coil wire size was AWG 20, whereas the. mating lug. was sized for AWG 16-14 wire.
A check of.
other ITE electrical breakers indicated that the problem may be generic.
Subsequent *to the Je.tter,.. the Sacramento Municipal Utility District infor.med.
us orally thit ITE M6del K-1600 breake~s have the same def~ciency and th~t Model K-3000 breakers may be similarly affected.
. *. * *.. :::'Jhe*:..in{or:ma:.ti:9:n pr()\\ii.de.tj*.~Y:: t~e*. Sacr.a~~n.to Mu~i:~Jpal. *W\\iJ'J:tY._DJ:st\\;.ct-_:i s -:i;ire~*..
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- *.* limirra*rY*and will be followed by *a complete rep*ort*.
Conseq*uent:ly', we have* not yet evaluated the safety signi:ficance of this event.
Nevertheless, the information herein is being provided as an early notification of a possibly significant event.
Although no specific action or response is requested at this time, recipients should review the information for possible applicability to their facilities.
If NRC evaluations so indicate, further licensee actions may be requested.
If you have any questions regarding the information contained herein, please contact the Director of the appropriate NRC Regional Office.
Attachment:
Recently issued IE Information Notices
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/ 'JI Information Notice No. 81-05 RECENTLY ISSUED
- IE INFORMATIQij NOTICES*
Subject Degraded DC System at Palisades Date of Issue 2/10/81 e
Attachment IN 81-06 March 11, 1981 Issued to All power reactor facilities with an OL or* CP 81-04 Cracking in Main Steam 2/27/81 All power reactor Lines facilities with
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81-03 Checklist for Licensees 2/12/81 All power reactor Making Notifications of facilities with an Significant Events in OL
- 81-02 81-01
. 80-45 Accordance with 10 CFR 50.72 Transportation of.
Radiography Devices Possible Failures of General Electric Type HFA Relays Potential Fa1lu_re _of,_..
Capability 1/23/81 1/16(81
.12/17/80_
A 11 Radiography licensees All power reactor facilities with an OL or CP.
All PWR facilities
- with*an OL*or*cp**
80.-~4. *..
- ... *. Actua.t i.on.. of.* ECCS. in. *the-
. : *12/16/80:... All P.WR faci. l i t.i es *.........
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- .,..-.... Rec*; rcul at ion** Macie **wh, :1 e.:
- _: *.::, ; *->*_..,_....- - :-. _.. **with-* -an_f 0~: of.. CP_..:: -. :*. -- *..,:_:. *. *. ::,*..---:.-,.
80-43 80-42 80-41 in.Hot.Shutdown Failures of the Continuous Water.Level Monitor for the Scram Discharge Volume at Dresden Unit No. 2 Effect of Radiation on Hydraulic Snubber Fluid Failure of Swing Check Valve in the Decay Heat Removal System at Davis-Besse Unit No. 1 OL- = Operating Li-cen ses* *