ML19345C149
| ML19345C149 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 11/14/1980 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | William Jones OMAHA PUBLIC POWER DISTRICT |
| References | |
| NUDOCS 8012040014 | |
| Download: ML19345C149 (1) | |
Text
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UNITED STATES PDR:HQ 1[.b " !
NUCLEAR REGULATORY COMMISSION LPDR 3
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l REGloN IV
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411 RYAN Pt.AZA c AtVE. SUITE 1000 AAUNGToN. TEXAS 76011 ATE Novemoer 14, 1980
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52 Docket No.
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Cmaha Puolic ?cwer District E
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ATTN:
W. C. Jones, Division ~ Manager -
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m Production Coerations 1523 Harney Street Omaha, Neoraska 58102 Gentlemen:
Enclosed is IE Sulletin No. 30-23 wnien recuires action by you wi.h regarc to your nuclear power facility.
In order to assist tne NRC in evaluating tne value/ impact of each bulletin on licensees, it would be helpful if you would provide us an estimate of tne manpcwer expended in conduct of tne review and preparation of ne recor (s) recuirec by the bulletin.
Please astimate separately 2e mancower associated with corrective actions necessary following identificaticn of preolems througn tne bulletin.
Should you nave any cuestions regarcing this bulletin or de actions re-quired oy you, clease contact this office.
Sincerely, 4
darl 'I.
Seyfrit
[/
Director
Enclosures:
1.
IE.3ulletin No. 30-23 2.
List of Recently Issued IE Bulletins cc:
S. C. Stevens, Manager Fort Calhoun Station Post Office Sox 98 Fort Calhoun, Neoraska 58102 l
i 8012040 0'
w SSINS No.:
6820 Act.ssion No.:
8008220257 IES 80-23 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPEZION AND ENFORCEMENT WASHINGTON, D.C.
20555 IE BULLET!N NO. 80-23 Novemoer 14, 1980 Page 1 of 3 FAILURES OF SOLEN 0ID VALVES MANUFACTURED 3Y 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 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 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 adoressed herein were ourporteoly designed as Class IE ccmponents. 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 magnat 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 foliows.
CUSTCMER P.O. NO.
VALVE P/N 0T7 Anchor-Oarling P-827 V70900-21-1,-3 24 N663 V70900-21-1 6
Anchor-Darling (Italy)
Cesare Bonetti 1535/79 V70900-21-3 10 Duke Fower 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 Ralpn Hiller HA-187-0 V70900-21-3 la Mill Power E52462-73 V70900-21-1,-3 20 Omaha 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
w 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 varnisn.
Sample coils of the new design are scheduled to undergo qualification tests.
We do not know the particulars of these tests, but Valcor has scneduled 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 i.iside containment and two outside.
This substitution was made because the reiginal solenoid valves did not meet the requirements of IE Bulletin No.
79-0.
However, subsequent to the replacer 1nt, Fort Calhoun has experienced five failures of these Valcor solenoid va es.
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 SE TAKEN SY 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, tne total number of such solenoid valves used, and evaluate acceptability of cer.tinued 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 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 sucn 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 shall periodically test the coils for potential turn-to-turn shorts in a manner tnat will not violate any LCO or cause any undesirable transient.
The tests should account for coil resistanceengngesduetotemperatureeffectsattributedtotheenviron-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 normally energized made; (b) Weekly for solenoid valves operated in a normally deenergized mode.
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v 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 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 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.
? termine whether Valcor solenoid valves having P/N's V70900-21-1 or -3 art to be used to perform safety-related functions at your facility.
If so, a report addressing this 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 wnich 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 where 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 tnese 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 coerating license.
The above regeested reports shall be submitted to the director of the apprc9riate 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, B180225(R0072); clearance expires November 30, 1980.
Approval was given under a blanket clearance specifically for identified generic problems.
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IE Bulletin No. 80-23 Novemoer 14, 1980 RECENTLY ISSUED IE BULLETINS Bulletin Subject Date Issued Issued To No.
80-20 Failures of Westingnouse 7/31/80 To each nuclear Type W-2 Spring Return power facility in to Neutral Control your,sgion having Switches an Operating License (OL) or a Construction Permit (CP)
Sup. 3 Failure of Control Rods 8/22/80 All SWR power reactor
.to 30-17 to Insert During a Scram facilities holding at a SWR Operating Licenses (OLs) or Construction Permits (cps) 79-26 Baron Loss from BWR 8/29/80 All SWR power facilities Rev. 1 control blades with an Operating License (0L) 80-22 Automation Industries, 9/11/80 All radiography Model 200-520-008 sealea 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 (OL) or Construction Permit (CP) 80-21 Valve yokes supplied by 11/5/80 All light water Malcolm Foundry Company, Inc.
reactor facilities holding OLs or cps Enclosure i
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