ML19345C153
| ML19345C153 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/14/1980 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Cavanaugh W ARKANSAS POWER & LIGHT CO. |
| References | |
| NUDOCS 8012040024 | |
| Download: ML19345C153 (1) | |
Text
O W RAL FILES d'# %
UNITED STATES POR:HQ 4,
'POR f. g-NUCLEAR REGULATORY COMMISSION i ;
TIC 5,,
j REGION IV NSIC 7,
./i 611 RYAN PLAZA onlVE, $UITE 1000 h,
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AAUNGTON. TEXAS 75011 STATE j
Novemcer 14, 198,0 3
Cocket Nos.
50-313 1
50-368 Q
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fh Arkansas Power and Light Company 5
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ATTN: Mr. William Cavanaugn III Q
ro
' lice Presicent of Generation e
N and Construction
?. O. Box 551 Little Rock, Arkansas 72203 Gentlemen:
Enclosed is IE Sulletin No. 80-23 wnicn requires action by you with regard to your nuclear ;:cwer facilities.
In orcer to assis: the NRC in evaluating :ne value/ impact of eacn bulletin on licensees, i would be heloful if you would crovice us an estimate of the mancewer excenced in conduct of :ne review and creparation of the report (s) recuired y the bulletin. Please estimate separately the mancewer associated wi n corrective actions necessary folicwing identification of proolems througn the culletin.
Should you have any questions regarding this bulletin or the actions re-quired oy ycu, please contact this office.
Sincerely, Karl '/. Seyfri:
Direc.or
Enclosures:
1.
Lis: of Recently Issuea IE Bulletins 7
cc:
James ?. O'Hanlon, ?lant Manager Arkansas Nuclear One
?. O. Box 508 Russellville, Arkansas 72801 f019040
,oli
p-1 ik.J SSINS No.:
6820 Accession No.:
8008220257 IES 80-23 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 IE BULLETIN N0. 80-23 November 14, 1980 Page 1 of 3 FAILURES OF SOLEN 0ID VALVES MANUFACTURED BY VALCOR ENGINEERING CORPORATION
==
Introduction:==
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 Duxe Power Company and Omaha Public Power District, and are purportedly limited to solenoid valves having part numbers (P/N's) V70900-21-1 and V70900-21-3.
The information presented in this bulletin is intended to shed light on the defective solenoid valves so that approcriate 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 :he reported failures, it appears tnat 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 continuously energized at elevated *.emperatures by an incompata-bility between the magnet wire's polyvinyl varn'sh 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.
CUSTCMER P.O. NO.
VALVE P/N QTY Anchor-Dar1ing P-827 V70900-21-1,-3 24 N663 V70900-21-1 5
Anchor-Darling (Italy)
Cesare Bonetti.
1535/79 V70900-21-3 10 Duke Power 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 V70900-21-3 14 Mill Power E52462-73 V70900-21-1,-3 20 Omana Public Power Dist.
43472 V70900-21-3 19 Stone and Webster L000 #43 V70900-21-3 8
Copes Vulcan 911,553 V70900-21-1 4
TOTAL 610
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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 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 Novemoer 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 wnich 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 experie!.ced 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.
Determine wnether 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 tnese solenoid valves, the total numoer of sucn solenoid valves used, and evaluate acceptability of continued operation with potentially defective solenoid valves.
A report of the results of the evaluation of conti'nued operation shall be suomitted within ten (10) days of the r' ate 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 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 operati*ng plants using the aforementioned solenoid valves in safety-related applications shall periodically test the coils for potential turn-;.o-turn shorts in a manner that will not violate any LCO or cause any undesirable transient.
The tests should account for coil resistancechgngesduetotemoeratureeffectsattributedtotheenviron-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 scnedule is recommended until the units are replaced with qualified units:
(a) Daily for solenoid valves operated in a normally energized mode; (b) Weekly for solenoid valves operated in a normally deenergized mode.
.Qr l
l IE3 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 action plan and the date by which the corrective actions will be implemented.
As a minimum, the longer term corrective measuret should include the replacement of the coils with fully qualified coils.
i 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 application per the applicable 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 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 shall be sucmitted by the earlier of the two following dates:
(a) within ninety (90) cays of the date of this bulletin; (b) two weeks prior to the date by which you expect to recieve an operating 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 wnere such valves are to be used, and should include an evaluation of the acceptability of operating 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 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 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 Commission, Washington, D. C. 20555.
Approved by GAO, 3180225(R0072); clearance expires Novuber 30, 1980.
Approval was given uncer a blanket clearance specifically for identified generic problems.
6~
IE Bulletin No. 80-23 November 14, 1980 RECENTLY ISSUED IE EULLETINS Bulletin Subject Date Issued Issued To No.
80-20 Failures of Westinghouse 7/31/80 To each nuclear Type.W-2 Spring Return power facility in to Neutral Control your region having Switches an Operating License (OL) or a Construction Permit (CP)
Sup. 3 Failure of Control Rods 8/22/80 All BWR power reactor to 80-17 to Insert During a Scram facilities holding at a BWR Operating Licenses (OLs) or Construction Permits (cps) 79-26 Soron Loss from SWR 8/29/80 All SWR power facilities Rev. 1 control blades with an Operating License (OL) 80-22 Automation Industries, 9/11/80 All radiography Model 200-S20-008 sealed licensees sources connectors Sup. 2 Environmental Qualifica-9/30/80 All power reactor to 79-013 tion of Class IE facilities with an Equipment Operating License (OL) or Construction Perait (CP)
Sup. 3 Environmental Qualifica-10/24/80 All power reactor to 79-108 tion of Class IE facilities with an Equipment Operating License (OL) or Construction Permit (CP) 80-21 Valve yokes supplied by 11/6/80 All light water Malcolm Foundry Company, Inc.
reactor facilities holding Ols or cps i
Enclosure f
l
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