ML18085A215
| ML18085A215 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 10/31/1980 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Schneider F Public Service Enterprise Group |
| References | |
| NUDOCS 8011140076 | |
| Download: ML18085A215 (6) | |
Text
Docket Nos. Sfr-272 50-311
- UNITED STATES UCLEAR REGULATORY COMMISSION.
REGION I 631 PARK AVENUE KING OF PRUSSIA, PENNSYL.VANIA 19406 October 31, 1980 Public Service Electric. and Gas Company
. ATTN:
Mro F. w.* Schneider Vice President - Production 80 Park Plaza - 15A Newark, New Jersey 07101 Gentlemen:
The enc:.lased IE Circular No. 80*23, "Potential Defects in Beloit Power Systems Emergency Generators," is forwarded to you.for information.
No written response is required. If you desire additional information regarding this mattar, please contact this office.
Si ncere*ly,
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Grter DiM!ctor*
Enclosures:
- 1.
IE Circular No. 80-23 with one enclosure z_
List of Recently Issued IE. Circulars CONTACT:
E. G. Greenman (Zl.5-337-5267) cc w/encls:
F. P. Librizzi, General Manager - Electric Production E. N. Schwalje, Manager - Quality Assurance R. L. Mittl, Gener.al Manager - Licensing and Environment H. J. Midura, Manager - Salem Generating Station R. A. Uderitz, General Manager - Fuel Supply Department 07<;
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UNITIED STATES.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D. C. 20555 Oct~ber 31, 1986 SSINS No.: 6830 Accession. No.:
8008220243 IEC 80-23 IE Circular No. 80-23 POTENTIAL DEFECTS IN BELOIT POWER SYSTEMS EMERGENCY GENERATORS BACKGROUND This circular addresses a potential deficiency involving the field leads of generators manufactured by Beloit Power Systems.
It is.known that the *subject
- generators have been coup 1 ed with Fairbanks Morse diesel engines for use in nuclear.power faC:ilities; however, it is not known whether they have been coupled with other diesel engines for such use.
Accordingly, the intent of this Circular *is to notify all nuclear power facilit*ies of the potential defect and to assure that appropriate remedial actions are taken, if needed.
The Nuclear Regulatory Commission was first informed of the potential defect by a phone call from Mr. R. H. Beadle of the Fairbanks Morse Engine D1vision of Colt Industries to Mr. D. W. Hayes of Region III on September 19, 1980.
On September 20, 1980, a.conference call was held between the NRC Duty Officer, personnel from Prairie Island Nuc.lear Power Station, Mr. Beadle of Fairbanks Morse and Mr. C. Evenson of Beloit Power Systems, the principal spokesman.
The purpose of this call was to describe an inspection method which Prairie Island personnel could use to examine the field lead assemblies of their gen-erators for the potential defect.
(We have since been informed by the Resident Inspector that the field lead assemblies of the Prairie Island generators di.d not. have the suspected defects.)
In order to disseminate this information on.a timely basis, the NRC Duty Officer at Bethesda called those operating facilities which he knew were using the suspect generators on September 20 and 21, 1980.
The information conveyed included a description of the potential defect and a description of the aforementioned inspection method.
The operating facilities called were:
FACILITY Calvert Cliffs 1 and 2 Crystal River 3 Hatch 1 and 2 Duane Arnold North Anna 1 and 2 Millstone 1 and 2 Robinson 2 Prairie Island Vermont Yankee Peach Bottom 2 and 3 Arkansas Nuclear One, Unit 2 NO. OF UNITS 3
2 5
2 4
3 2
2 2
4 2
- e.
lEC.80-23 October*31, 1980 Page 2 of 3 These phone calls were subsequently followed up with a Part 21 Report dated September 22, 1980 from Mr. J. M. Moriarty, Manager, Utility Sales, Fairbanks Morse Engine Division.
Information conveyed in the Part 21 Report.included the fol lowing *excerpts:
11A Beloit Power Systems generator in commercial service at Sitka, Alaska lost its field because a* lead between the collector rings and the field coils shorted to the rotor and burned in two pieces at the point of the short.**. Subsequent examination of another generator of identical design at the same installation showed frayed insulation *at a clamp (same loca-
"tion as the. burn through) which secures the lead to the rotor.
This unit was operating satisfactorily but if the insulation damage were to pr.ogress the possibility of grounding the lead to the rotor exists.
11 "To determine if the problem.might exist at other lOcations our chief electrical engineer was sent to Provo, Utah which has four generators of identical design.
He has reported by phone that two of the four at Provo
. have frayed insulatfon at the clamp but that there was no indication of loss of field. 11 "Concurrent with our inspection at Provo, Beloit Power Systems was asked to evaluate the cause of frayed insulation and alS.o if any other generators might have the same problem.-
Their verbal report to us is that the cause of fraying is poor workmanship in installation of the clamps and that there are other generators of *identical design in this area.
Specifically the eight generators shipped to Limerick (Philadelphia Electric) are of the identical design in the area where poor workmanship is known to have caused a problem.
11 "Our plan is to i.nspect the Limerick generators and repair any poor workmanship which may be found.
Beloit Power Systems also reports verbally *that the design in this area for 5 arid 6 frame alternators has been similar for a number of years and it is therefore possible that the problem may extend to operating units.
11 RECOMMENDED ACTIONS FOR HOLDERS OF CONSTRUCTION PERMITS OR OPERATING LICENSES:
- l.
Determine whether or not your facility uses emergency generators manufactured by Beloit Power Systems, having frame sizes 5 or 6, as part of the o.nsite emergency power system; if not:, you need not pursue this matter further.
2..
If your facility uses generators manufactured by Beloit Power Systems you should inspect the connections between the.collector rings and the field coils in the field lead assemblies o.f the generators for frayed
- insulation at the clamps and make needed repairs per the enclosed* instruc-tion sheet, 11Inspection Procedures for Generator Field Leads".
The inspections should be completed as soon as practical and conducted within the constraints of the Technical Specifications.
- 3.
If the inspection reveals the need for repair or dressing of the -leads, said repair should be initiated at operating facilities as soon as practicable after the need has been determined but no later than ten (10) days thereafter, provided the unit is capable of performing its function
IEC S0-23 October 31, 1980 Page 3.of 3 without the repair.
Otherwise, the repair should be initiated immediately after the need has been identified.
Needed repair work should be coordinated with Beloit Power Systems as stated in the inspec-tion procedure.
- 4.
If.the inspection reveals the need for repair or dressing of leads at facilities holding Construction Permits, said repair should be initiated at the licensee's earliest convenience and.coordinated with Beloit Power Systems.
Enclosure:
"Inspection.Procedure for Generator Field Leads"
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Enclostire to IE Circular 80-23.
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'field 1~a.di: to dete~in: ~;f tha pas:ibie f'ie!d ?rob.lam lr't'i)Ort~d "o1 Co1 t Indust.r\\e:. e~"i sr.~ ~r.<1 ac:;*ress4!d i ~ J~RC Reg\\ ster-i77BZ.
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Vi~uat ly 1oca~ U-.E:- rcter f)e\\d 1E~ci~ at t.:O,e: C:Jl1ecU)r ring a~~ty.
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io~te the 9(!ner~tor. by bt11oi-in~ the e~gine ovnr by band. Ynt.1~
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(~ing ra~ed or 'l:IO'm *:tlcng ~~.~~.s}. lt trl11 ~
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hl!CU~ar-J tn ra~ th<l' el~s to d3*tar=iM thi$.
Al~ ilnsce.<t t~ im-J!r ~1e* amnect:5on$ beni~ t.;e "f'a.n for $1~$ of irr3;J'l.a.-
ticn d<!t:!~ior~tion as t..~ 'M!sul t of cent.act.
- 5.
~ger* the main ro~ '1ir.d1n;s -:-to 9T"""'~l'Ki t"irot.Jtjh t~ co'i1i!etor i ri~ asse:~1y. !t wn1 b3 net:.:'!~!.ary t.c nise ~~~ ~.lS~-"?5 to 1
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Tr~ ~waJ ')li:id*:ng ~r:~ulat1on ~s!stl:r.a 1:i -.
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- 5. SZiculd a cindition be ftrund~ as out1ined in rlo. 4 J~,. i*~
wi11 be ne;3ssa.-y to ~...m:rve t~ c1a&n?in9 devic~ iilnd in:p:.~t f'urthet'.
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Provide co~lete inspee'tion report..
After which. BPS \\911l advi sa bes; t re~ i r pr"Oe':!dure 1 f n~c~s= ry *.
REVIDJED AND APPR1JV£D:
-~-u7 go Mtt
October 31, 1980
- RECENTLY ISSUED *
. IE CIRCULARS
- .Circular Date of No.
Subject
.Issue.
80-22 Confirmation of 10/2/80
- Emp 1 oyee Qua 1 i f.i cations 80-21 Regulation of 9/10/80 Ref ue 1 i ng Crew.s 80-20 Changes in Safe-Slab 8/21/80 Tank Dimensions 80-19 Noncompliance with 8/26/80 Licensee Requirements 80-18 10 CFR 50.59 Safety 8/~2/80 Evaluations for Changes to Radioactive Waste Treatment Systems 80-17 Fuel Pin Damage Due to Water 7/23/80 Jet from Baffle Pl ate Corner*
80-16 Operational Deficiencies In 6/27/80 Rosemount Model 510DU Trip Units And Model 1152 Pressure Transmitters 80-15 Loss of Reactor Coolant Pump 6/20/80 Cooling and Natural Circula-tion Cooldown 80-14 Radioactive Contamination of 6/24/80 Plant Demineralized Water System*and Resultant Internal Contaminatfon of Personnel 80-13 Grid Strap Damage in 5/18/80 Westinghouse Fuel Assemblies 80-12 Valve-Shaft-To-Actuator Key 5/14/80 May Fall Out of Place When Mounted Below Horizontal Axis
- 9
- Enclosure 2 ISsued to A 11 ho*l de.rs of a power reactor 01 or CP All holders of a power reactor OL or CP