ML19345C245

Forwards IE Bulletin 80-23, Failures of Solenoid Valves Mfg by Valcor Engineering Corp. Requires Estimate of Manpower Associated W/Corrective Actions

ML19345C245
Person / Time
Site:	Rancho Seco
Issue date:	11/14/1980
From:	Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:	Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT
References
NUDOCS 8012040220
Download: ML19345C245 (1)

Text

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77c UNITED STATES

't NUCLEAR REGULATORY COMMISSION E

REGION V 0[

1990 N. CALIFORNIA SOULEVARD 9,

%,,,* p SUITE 202, WALNUT CREEK PLAZA 4

WALN'JT CR EEK, CALIFORNIA 94808 November 14, 1980

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Docket No. 50-312 3

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Sacramento Municipal Utility District P. O. Box 15830 Sacramento, California 95813 Attention: Mr. John J. Mattimoe Assistant General Manager Gentiemen:

Enclosed is IE Bulletin No. 80-23 which requires action by you with regard to your nuclear power facility (tes) with an operating license or construction permit.

In order to assist the NRC in evaluating the value/ impact of each bulletin on licensees, it would be helpful if you would provide us an estimate of the manpcwer expended in conduct of the review and preparation of the report (s) required by the bulletin. Please estimate separately the manpower associated with corrective actions necessary following identification of problems through the bulletin.

Should you have any questicns regarding this bulletin or the action required by you, please centact this office.

Sincerely,

%dS%

i R. H. Engelken Director

Enclosures:

1.

IE Bulletin No. 80-23 l

2.

Recently issued IE Bulletins cc w/ enclosures:

R. J. Rodriguez, SMUD L. G. Schwieger, SMUD Q

80120ao Mc

. i__ 1 SSINS No.: 6820 Accession No.:

8008220257 IEB 80-23 UNITED STATES NUCLEAR REGULATORY CCMMISSION OFFICE OF INSPECTION AND ENFORCEMENT 3

a WASHINGTON, D.C.

20555 November 14, 1980 IE Bulletin No. 80-23: FAILURES OF SOLEN 0ID VALVES MANUFACTURED BY VALCOR ENGINEERING CORPORATION

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Introduction:==

Valcor Engineering Corporation (Valcor) has submitted 10 CFR Part 21 Reports addressing failures of Valcor scienoid valves used at nuclear power facilities.

These failures have occurred at nuclear facilities owned by Duke Power Company and Omaha Public Power District, and are purportedly limited to solenoid valves h~aving part numbers (P/N's) V70900-21-1 and V70900-21-3.

The infomation presented in this bulletin is intended to shed light on the defective solenoid valves so tnat appropriate actions can be taken to circum-vent the cegracation of any safety-relatea system using sucn solenoid valves.

DISCUSSION:

The specific Valcor solenoid valves adoressed herein were purportedly' designed as Class IE ccmponents..Hcwever, in light of t.ie reported failures, it appears that neither the design nor the qualification tests were adequate for Class IE service. Valcor has attributed the failures to a latent defect in the magnet wire. Valcor believes that this defect manifests, itself when the solenoid valves are continucusly energized at elevated temperatures by an incompata-bility between the magnet wire's polyvinyl varnish coating and the wire's polyimide insulation which causes a dielectric breakdown leading to turn-to-turn shorts within the coil.

Valect states that the above incompatability is limited to solenoid valves having P/N's V70900-21-1 and V70900-21-3, and that all customers affected by the aforementioned defect have been notified. A listing of Valcor customers so notified and valves purchased follows.

CUST0*ER P.O. NO.

VALVE P/M QTY l

Anchor-Darling P-827 V70900-21-1,-3 24 Anchor-Darling -

N663 V70900-21-1 6

Cesare Bonetti (Italy) 1535/79 V70900-21-3 10 Duke Pcwer Company E95188-11 V70900-21-3 100 Duke (Mill Power)

C-97733 V70900-21-1,-3 335 Duke Power Company E97822-11 V70900-21-3 70 Ralph Hiller HA-187-0 V70900-21-3 14 Mill Power E52462-73 V70900-21-1,-3 20 Omaha Public Power Dist.

43472 V70900-21-3 19 Stone and Webster LOOO #43 V70900-21-3 8

Copes Vulcan 911,553 V70900-21-1 4

TOTAL 610

IEB 80-23 November 14, 1980 Pages 2 of 3 Valcor's corrective actions include making arrangements for replacing existing coils with a' newly designed coil using a 997 silicone varnish coating instead of t't.e polyvinyl varnish. Sample coils of the new design are scheduled to undergo qualification tests. We do not know the particulars of these tests, 3

- but Valcor has scheduled the first phase of these tests for completion by November 15, 1980, and has identified the second phase as an on-going aging test.

Fort Calhoun has replaced twelve of its original solenoid valves with Valcor type V70900-21-3 valves, ten of which are located inside containment and two outside. Thfs substitution was made because the original solenoid valves did not meet the requirements of IE Bulletin No. 79-01. However, subsequent to the replacement, Fort Calhoun has exoerienced five failures of these Valcar solenoid valves. Each failure involveo a solenoid valve located inside contain-ment and designed for operation in the normally energized mode. These two factors -(i.e., continucusly energized mode of operation and a somewhat elevated temperature inside containment) tend to support Valcor's contention regarding the failure mechanism.

ACTIONS TO BE TAKEN BY LICENSEES:

1.

Determine whether Valcor solenoid valves having P/N's V70900-21-1 or -3 are used to perform any safety-related function at your facility.

If so, identify the safety-related systems using these solenoid valves, the total nuter of such solenoid valves u~ sed, and evaluate i

acceptability of continued operation with potentially defective solenoid valves. A report of the results of the evaluation of continued operation shall be submitted.within ten (10) days of the date of this bulletin and 1

should irclude factors such as (a) operator's ability to promptly identify a failing or failed solenoid valve (b) effect of solenoid valve failures on safety-related systems and subsequent operator actions required, and (c) possible degradation of the power supply serving a failed solenoid valve and the effects on other components served by said power supply.

If no such solenoid valves are used, you need only submit a negative declaration to this effect within thirty (30) days of the date of this bulletin and you need not respond to the remaining items.

2.

Licensees of operating plants using the aforementioned solenoid valves in safety-related applications shali periodically test the coils for potential turn-to-turn shorts in a manner that will not violate any LCO or.cause any undesirable transient. The tests should account for coil resistance chgnges due to temperature effects attributed to the environ-ment and to I R losses in the coil to provide accurate indications of changes in resistance due to turn-to-turn shorts.

These tests are to be initiated within ten (10) days of the date of this bulletin. The following schedule is recommended until the units are replaced with qualified units:

l (a) Daily for solenoid valves operated in a norwally energized mode; (b) Weekly for solenoid valves operated in a normally deenergized mode.

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IEB 80-23 November 14, 1980 Pages 3 of 3 Whenever the tests indicate that ten percent or more of the coil turns have been shorted, said solenoid valve, or its coil, shall be replaced with a new unit.

3.

Licensees of operating plants shall submit a report within forty-five (45) days of the date of this bulletin describing their longer term corrective acticn plan and the date by which the corrective actions will be imolemented. As a minimum, the longer term corrective measures should include the replacement of the coils with fully qualified coils.

New solenoid valve assemblies (i.e., a repaired unit with a replacement coil or a completely new unit) shall be demonstrated to be qualified for its safety-related acolication cer the accifcable requirements of IEEE 323-1974, IEEE 344-1975, IEEE 382-1972 and IE Bulletin No.79-01B and supplements thereto.

ACTICNS TO BE TAKEN BY HOLDERS OF CONSTRUCTION PERMITS:

1.

Cetermine wnether Valcor solenoid valves having P/N's V70900-21-1 or -3 are to be used to perform safety-related functions at your facility.

If so, a report addressing this matter snall be submitted by the earlier of the two following dates:

(a) within ninety (90) days of the date of this bulletin; (b) two weeks prior to the date by which you expect to receive an operating License.

The above report should indicate your plans to replace said valves prio-to ccm.encing operation, if this is the case. Otherwise, if you propose to cccmence operaticn prior to replacing said valves, the report should indicate the safety-related systems where such valves are to be used, and should include an evaluation of the acceptability of operatina with potentially defective valves. This evaluation should address factors such as your proposed test plan, operator's ability to promptly identify a failing or failed valve, effect of solenoid valve failure on safety-related systems and subsequent operator actions required, and the preventive measures you plan to implement to circumvent the effects of failures of these valves.

If no such valves are to be used in your facility, submit a negative declaraticn to this effect within forty-five (45) days of the date of this bulletin but prior to the date by which you expect to receive an operating license.

The above requested reports shall be submitted to the director of the appropriate NRC region within time stipulated for each item in the this bulletin. A copy of each report shall be forwarded to the Director, Division of Reactor Operations Inspection, Office of Inspection and Enforcement, United States Nuclear Regulatory Cemission Washington, D. C. 20555.

Approved by GAO, B180225(R0072); clearance exoires November 30, 1980. Approval was given under a blanket clearance specifically for identified generic problems.

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IEB 80-23 November 14, 1980 RECEMTLY ISSUED IE BULLETINS Bulletin No.

Subject Date Issued Issued To 80-22 Automation Industries, 9/11/80 All radiography Model 200-520-008 Sealed-licensees Source Connectors 80-21 Valve yokes supplied by 11/6/80 All light water Malcolm Foundry Company, Inc.

reactor facilities holding OLs or cps Supplement 3 Environmental Qualification 10/24/80 All power reactor to 79-10B of Class IE Equipment facilities with an OL Supplement 2 Environmental Qualification 9/30/80 All power reactor to 79-01B of Class 1E Equipment facilities with an OL 80-22 Autcmation Industries, 9/11/80 All radiography Model 200-520-008 Sealed-licensees source Connectors 79-26 Baron Lost, frcm BNR 8/29/80 All BWR power Revision 1 Control Blades facilities with an OL 80-20 Failures of Westinghouse 7/31/80 To each nuclear Type W-2 Spring Return power facility in to Neutral Control Switches your region having an OL or a CP 80-19 Failures of Mercury-7/31/80 All nuclear power Wetted Matrix Relays in facilities having Reactor Protective Systems either an CL or a CP of Cperating Nuclear Power Plants Designed by Combus-tion Engineering 80-18 Maintenance of Adequate 7/24/80 All PWR power reactor Minimum Flew Thru Centrifugal facilities holding OLs Charging Pumps Following and to those PWRs j

Secondary Side High Energy nearing licensing Line Rupture

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