ML19345C154
| ML19345C154 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 11/14/1980 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Millen C PUBLIC SERVICE CO. OF COLORADO |
| References | |
| NUDOCS 8012040027 | |
| Download: ML19345C154 (1) | |
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ATTN: Mr. C. K. Millen d
Senior Vice Presicent P. O. Box 840 Cenver, Colorado 80201 Gentlemen:
Enclosed is IE Sulletin No. 80-~ 3 which requires action oy you wi-n regard 2
to your nuclear ;:cwer facility.
In orcer :o assist tne NRC in evaluating me value/imcact of eacn bulletin on licensees, it would be helpful if you would provide us an estimata of the mancower excended in concuct of me review and Precaration of the recort(s) recuired by the bulletin. Please estimata secarataly :ne manpcwer associated wirl corrective actions necessary folicwing icentificaticn of preolems :nrougn.he bulletin.
Should you have any cuestions regarcing this bulletir or.ne actions re-quirec cy you, please contact this office.
Sincerely, f
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Xarl V. Seyfrit /<
Director Qi Inclosures:
1.
IE Sulletin No. 30-23 2.
List of Recently Issued IE Eulletins c:::
0.
'.4. '.4aremcourg, Nuclear ?recuction Manager Fort St. Vrain Nuclear Static P. 0. Box 368 Platteville, Coloraco 30651 L. 3 rey, Manager, Quality Assurance 8012040 C 2.7
. o SSINS No.:
6820 Access' ion No.:
8008220257 IES 80-23 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 IE SULLETIN NO. 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 ".FR 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 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 cefective solenoid valves so that acpropriate actions can be taken to circum-vent the cegradation of any safety-related system using such solenoid valves.
DISCUSS,*3:
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 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 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-
- urn shorts within the coil.
Valcor states that the above incompatability is limited to solenoid valvas having P/N's V70900-21-1 and V70900-21-3, and that all customers affected by the aforamentioned defect have been notified. A listing of Valcor customers so. notified and valves purchased follows.
CUSTCMER P.O. NO.
VALVE P/N QT_Y 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 Power Company E95188-11 V70900-21-3 100 Ouke (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 143 V70900-21-3 8
Copes Vulcan 911,553 V70900-21-1 A
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IES 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 complotion 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 whicn 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 suoport Valcor's contention regarding the failure mecnanism.
ACTIONS TO BE TAKEN BY LICENSEES:
1.
Determine whether Valcor scienoid valves having ?/N's V70900-21-1 or -3 are used to nerform any safety-related function at your facility.
If so, id-the safety-related systems using these solenoid valves, i
~ 1 number of such solenoic valves used, and evaluate acceptabi': V of continued operation with potentially defective solenoid valves.
A report of the results of the evaluation of continued operation shall be suomitted 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 on safety-related systems and subseqtent operator actions required, and (c) possible degradation of the power supply serving a failed solenoid valve and the effect:. 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 neea not respond to the remaining itenis.
2.
Licensees of operati'ng plants using the aforementioned solenoid valves in safety-related applications shall 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 changes due to temperature effects attributed to the environ-ment and to'li losses in the coil to provide accurate indications of changes in resistance due to turn-to-turn shorts.
i 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 normally energized mode; (b) Weekly for solenoid valves operated in a normally deenergized mode.
IES 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 witn 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 measures snould 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 application per the applicable requirements of IEEE 323-1974, IEEE 344-1975, IEEE 382-1972 and IE Bulletin No. 79-018 and supplements thereto.
ACTIONS TO BE TAKEN SY HOLDERS OF CONSTRUCTION PERMITS:
1.
Determine whether 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 tnis matter shall 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 excect 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 7.fior 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 sucn 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 Insoection, Office of Inspection and Enforcement, United States Nuclear Regulatory Commission, Washington, 3. C. 20555.
Approved by GAC, 8180225(R0072); clearance expires November 30, 1980.
Approval was given under a blanket clearance specifically for identified generic problems.
IE Bulletin No. 80-23 November 14, 1980 RECENTLY ISSUED IE BULLETINS Bulletin Subject Date Issued Issued To No.
80-20 Failures of Westinghouse 7/31/80 To each nuclear Ty,pe 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 Baron Loss from SWR 8/29/80 All BWR power facilities Rev. 1 control blades with an Operating License (0L) 80-22 Automation Industries, 9/11/80 All radiography Model 200-520-008 sealed licensees sources connectors Sup. 2 Environmental Qualifica-9/30/80 All power reactor to 79-018 tion of Class IE facilities with an Equipment Operating License (OL) or Construction Permit (CP)
Sup. 3 Environmental Qualifica-10/24/80 All power reactor to 79-108 tion of Class IE facilities with an Equipment Operating License (0L) 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 Enclosure
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