ML19345C244
| ML19345C244 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 11/14/1980 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Nichols T SOUTH CAROLINA ELECTRIC & GAS CO. |
| References | |
| NUDOCS 8012040212 | |
| Download: ML19345C244 (1) | |
Text
[pitz UNITED STATES P' -
NUCLEAR REGULATORY COMMISSION l
4 REGION ll "e
101 M ARIETTA ST.. N.W.. SUITE 3100 g
e ATLANTA. GEORGIA 30303 7;3 S
NOV 141980 n
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In Reply Refer To:
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,N 50-395) 2.
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South Carolina Electric and Gas Company y
s]d ATTN:
T. C. Nichols, Jr., Vice President
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m Power Production and Systems Operations P. O. Box 764 Columbia, SC 29218 Gentlemen:
Enclosed is IE ' Bulletin No. 80-23 wlich requires action by you with regard to your nuclear power facility.
In order to assist the hhc in evaluating the value/ impact of each bulletin on licensees, it would be helpful if you would provide us on estimate of the manpower 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 questions regarding this bullatin or the actions re-quired by you, please contact this office.
Sincerely,
'D[h x f'~
James P. O'Reilly Director
Enclosures:
1.
List of Recently issued IE Bulletins cc w/ encl:
A. A. Smith, Site QA Coordinator J. B.-Knotts, Jr
- 0. S. Bradham, Manager Nuclear Operations O
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onoao ag - - - - - _ - - - _ - - - - --
SSINS No.:
6820 Accession No.:
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8008220257 UNITED STATES.
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NUCLEAR REGULATORY COMMISSION C
y OFFICE OF INSPECTION AND ENFORCEMENT D
D WASHINGTON, D.C.
20555 November 14, 1980 IE Bulletin No. 80-23: FAILURES OF SOLENCIu ULVES MANUFACTURED BY VALCOR ENGINEERING CORPORATION Introducti 3:
Valcor Engineering Corporation (Valcor) has submitted 10 CFR Part 21 Reports addressing failures of Valcor solenoid 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 val res having part numbers (P/N's) V70900-21-1 and V/0900-21-3.
The information presented in this bulletin is intended to shed light on the defective solenoid valves so that appropriate actions can be taken to circum-vent the degradation of any safety-related system using such solenoid valves.
DISCUSSION:
The specific Valcor solenoid valves addressed herein were purportedly designed as Class IE components. However, in light of the reported failures, it appears that neither the design nor the qualification tests were adequate for Class IE se rvice. 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 continuously 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.
Valcor 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.
CUSTOMER P.O. NO.
VALVE P/N QTY Anchor-Darling P-827 V70900-21-1,-3 24 Anchor-Darling N663 V70900-21-1 6
Cesare Bonetti (Italy) 1535/79 V70900-21-3 la Duke Power Company E95188-11 V70900-21-3
.Gd 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 g-+[
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 the polyvinyl varnish. Sample coils of the new design are scheduled to undergo qualification tests. We do not know the particulars of these tests, but Valcor has scheduled the first phase of these tests for completion by F
= 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. This 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 experienced five failures of these Valcor solenoid valves. Each failure involved a. solenoid valve located inside contain-ment and designed for operation in the normally energized mode. These two factors.(i.e., continuously 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.
Det coine 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, iuentify the safety-related systems using these solenoid valves, the total number of such_ solenoid valves used, and evaluate acceptability of continued operation with potentially defective soletoid 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.
should include factors such as (a) operator's ability to promptly identify a failing or failed solenoid valve, (b) effect of solenoid valve failures
+
i 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 i
declaration to this effect within thirty (30) days of the date of this bulletin and you need not respond to the remainirg items.
2.
Licensees of operating plants using the aforementioned solenoid valvas in safety-related applications shall periodically test the coils for potential turn-to-turn shorts in a manner that will not violate any LCO a
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:
{
'(a) Daily for~ solenoid valves operated in a norally energized mode; i-(b) Weekly for solenoid valves operated in a normally deenergized mode.
I i
1
e IEB 80-23 November 14, 1980
.f Pages 3 of 3 Whenever the tests indicate that ten percent or more of the coil tu have been shorted, said solenoid valve, or its coil, shall be replac d rns with a new unit, f
e 3.
Licensees of operating plants shall submit a report within forty-fiv (45) dayi of the date of this bulletin describing their longer term e
will be implemented. corrective action plan and the date by which the corrective action should include the replacement of the' coils with fully qualified c New solenoid valve assemblies (i.e., a repaired unit with a its safety-related application per the applicoil or a completely replacement cable requirements of IEEE-323-1974, IEEE 344-1975, IEEE 382-1972 and IE Bulletin No.79-01B and supplements thereto.
ACTIONS TO BE TAKEN BY HOLDERS OF CONSTRUCTION PERMITS:
1.
Determine whether Valcor solenoid valves having P/N's V70900-21-1 or are to be used to perform safety-related functions at your facility
-3 If so, a report addressing this matter shall be submitted by the earli of the two following dates:
of this bulletin; (a) within ninety (90) days of the date er to recieve an opera (b) two weeks prior to the date by which you expect ting License.
The above report should indicate your plans to replace said valves prior to commencing operation, if this is the case.
Otherwise, if you propose to commence operation prior to replacing said valves, the report should indicate the safety related systems where such valves are to be u and should include an evaluation of the acceptability of operating with
- sed, 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 r l t d systems and subsequent operator actions required, and the preventive
-eae seasures you plan to implement to circumvent the. effects of failures of these valves.
If no such vclves are to be used in your facility, submit a negative declaration to this effect within forty-five (45) days of the date of this bulletin but prior to the date by which you expect to receiv operating license.
e an The above requested reports shall be submitted to the director of th appropriate NRC region within time stipulated for each item in the thi e
bulletin.
A copy of each report shall be forwarded to the Director s
United States Nuclear Regulatory Commission, Washington
, Division i
. C. 20555.
I Approved by GAO, B180225(R0072); clearance expires November 30, 1980 was given under a blanket clearance specifically for identified generic probl ems.
i
a sT l
IEB 80-23 November 14, 1980 RECENTLY ISSUED IE BULLETINS Bulletin No.
Subject Date Issued Issued To 80-23 Failures of Solenoid Valves 11/14/80 All nuclear power Manufactured by Valcor facilities with an Engineering Corporation OL or CP 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 IE Equipment facilities with an OL 80-22 Automation Industries, 9/11/80 All radiography Model 200-520-005 Sealed-licensees source Connectors 79-26 Boron Loss from BWR 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 1
Reactor Protective Systems either an OL or a CP of Operating Nuclear Power Plants Designed by Combus-tion Engineering 80-18 Maintenance of Adequate 7/24/80 All PWR power reactor Minimum Flow Thru Centrifugal facilities holding OLs Charging Pumps Following and to those PWRs Secondary Side High Energy nearing licensing Line Rupture