ML17296B067
| ML17296B067 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 11/14/1980 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| References | |
| NUDOCS 8012040215 | |
| Download: ML17296B067 (10) | |
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UNITEDSTATES NUCLEAR'REGULATORYCOMMISSION REGION V'990 N. CALIFORNIABOULEYARD, SUITE202,'ALNUTCREEK PLAZA WALNUTCREEK, CALIFORNIA94599.
November 14, I980 Docket Hos. 50-528, 50-'29
& 50-530 Arizona Puhl,fc. Service. Company P. 0.
Box 21666 Phoenix, Arfzona 8503&..
Attention.
Nr. E. E Van Brunt Jr.
Vice President, Nuclear Projects Gentl'emen."
Enclosed is IE: Bulletin No. 80-23. which. requires aciion by you. with regard to'our nuclear power facility(ies) wfth an'perating license or construction: permit In order to assist the NRC in evaluating, the value/impact of each bulletin on Ticensees it would: be helpful: ffyou. woutd provide us an esiimaie of the manpower expended in conduct of the review and preparation o, the report(s) required. by ihe bulletin Please. estimate. separaiely the manpower associaied with corrective. actions. necessary.
following., identification of problems. ihrougn-the buTletfn.
Should you. have. any questions regarding this. bulletin: or the acti orr. required; by you, piease contact this office..
SfncereTy, R'
Engelken'.
Mr,ector
Enclosures:
l.
IE Bul'Tetfn No.
80'-23.
Recently issued; IE. Bulletfns.
cc w/enclosures:
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UHITED STATES NUCLEAR REGULATORY CCMMISSION OFFICE OF INSPECTION AND ENFORCEMEHT
<IASHIHGTON', D.C.
20555 SSINS No.:
6820 Accession No.:
8008220257 IEB 80-23 November 14, 1980 IE Bulletin Ho 80-23:-
FAILURES-OF SOLENOID VALVES MANUFACTURED BY VALCOR'NGINEERING CORPORATION
==
Introduction:==
YaTcor Engineering: Corporation'(Yalcor) 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. Di:strict,, and are purportedly l*imited. to solenoid valves. tl'aving. part. numbers.(P/H's)'70900-21-L and V70900-21-3.
The information. presented, in this; bulletin i'" intended to shed light on the defective solenoid valves'o that; appropriate actions can be. taken'o circum-vent the. degradation: of any. safety-related; system. using such solenoid. valves..
DISCUSSIOH:
The specific. YaTcor; 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:.
Yalcor has attributed. the failures'o-a latent. defect. in the.. magnet wire.,
VaT'cor believes. that this defect manifests; itself'when the; solenoid valves are continuous'ly. energized:.at. elevated. temperatures, by an. incompata-.
bility between. the. magnet wire's polyvinyl varnish coating and: the wire's polyimide insul'ati'orr.which;-causes
- a. dielectric. breakdown
'leafing-. ta turn-to-turn: shorts. within: the coi'7 Valcor states thatthe above inccmpatabiTity. is. limited to. solenoid va'l'ves.
having P/W's V70900.-2I;1:. and V70900'-2X-3'nf that; all customers affected by the aforementioned'- defect, have. been notifiedisting of VaTcor customers, so notified', and'aTves:
purchased folTows.
CUSTOMER h
Anchor-Oar 1 ing Anchor-Darling Cesare Bonetti (Italy):
Duke Power.
Company Duke (Mill, Power)
Duke-Power Company Ralph Hi.lier.
Mill Power Omaha Public Power Dist.
Stone: and, Webster Copes, Vulcarr-
'P.O; I'lO';
P.-827.'663" 1535/79'E95188'-Il; C-97733 E9 7822-11 HA-187-0 E5 2462-73 43472 LQOO,;43 9II.',553 VALVE P/N V70900-21-1,-3, V70900-'2I'.-1 V70900-21-3 Y70900-21. V70900'-21.-1,-3 Y70900-.21-3 V70900-21.-3 V70900-21-i,-3:
. Y70900-21-3 V70900-21-3 V70900-21-. I:
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4 TOTAL 610
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IEB 80-23 November 14, 1980 Pages 2 of 3 Valcor's corrective actfons include making arrangements for replacing existing coils with a newly designed coil using a 997 silicone varnish coating fnstead of the polyvinyl varnish.
Sample coils of the new design are scheduled to undergo qualification tests.
Me do not know the particulars of these tests, but Yalcor has scheduled the first phase of these tests for completfon by November 15, 1980, and has identified the second phase as arr on-going aging test..
Fort, Calhoun has replaced twelve of fts original solenoid valves. with VaTcor type V70900-21-3 valves, ten, of which are located inside containment and. two outside.
This. substitution was made because the. orfgfnaT soTenafd valves did not meet the requirements of IE Bulletfn No. 79-01.
However, subsequent ta the replacement, Fort Calhoun has experienced five faflures of these Yalcor solenoid valves Each failure. involved a saTenoid valve. located inside contain-ment and designed'or operation: in the; normally energized mode.
These two factors (i.e., continuously energized made. of, operatian and.
- a. somewhat elevated temperature; inside containment) tend, ta support Val'cor's contention regarding the. failure, mechanism.
ACTIONS TO HE TAKEN BY LICENSEES:
I Oetermine whether.
Valcor. solenoid valves having P/N's V70900-21-1 ar -3 are used. ta perform any safety-related function at:your facility.
If sa, identify 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 solenoid valves.
A report of the results of'he, evaluation af, continued operatiorr shall he submitted. within. ten (.10, days: of the date of this bulletin and should include-factors'uch as. (a operator's. ability to promptly identify a failing ar failed salenofd valve, (b)'ffect of solenofd, valve faf.lures.
on safety-related.
systems antt subsequent operator actions. required and (c) possible. degradatfon af'he: power supply, servfng a. failed salenoid valve and the effects on. other components.
served. by said power supply.
If no such solenaid valves. are used., yau need'nly. submit a, negative declaration ta-this effect withfn. thirty (30) days of the date af this buITetfn and. you need not respond; ta the remaining, ftems.
2 Licensees oF operating-plants using the aforementioned. soTenoid valves. in safety-related'pplfcatfons shal'1.- perfodicaTTy test the cof1s far potential turn-to-turn shorts fn a; manner that, wfTT not vioTate any LCO or cause any undesfrable transient.
The tests should account for coil resistance eh~noes.
due to temperature effects attributed to: the environ-ment and ta I R losses fn the cafT to provide. accurate indications of changes in resistance due to tur n-to-turn shorts.
These tests are. to be initiated: within ten (10); days of the date of this bulletin-.
The foTlowing schedule is recommended untiT. the, unfts are replaced with qualified unfts:
(a)
Oaily for solenoid vaIves operated irr a normaTIy energized mode; (b)
Meekly for salenofd valves operated. fry a normaTly deenergfzed mode
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IEB 80-23'ovember 14, 1980 Pages 3 of 3 hhenever the tests indicate that ten percent or more of the coil turns have been shorted', said solenoid valve, or fts coil, shalT be reolaced 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. fncl'ude the replacement af. the coils with fully qualified coils.
New solenoid valve assemblies (i.e. a repaired unit with a replacement coil or z completely new unit) shalt be. demanstrated ta be-quaTiffed for i s safetv-reTated apolfcation per the aoolfcable-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 salenoid: valves having P/N's Y70900-21-1 or -3 are to be used. ta perform safety-reIated. functions at your facility.
If so, a report addressing, this matter shall be submitted by the ear1ier of the twa fo11owing aates=
(a) within ninety (90) days of the date of this bulletin," (b) two weeks'rior ta the date by. which you expect to receive an operating License.
The above ~eport. shou1d indicate your plans to replace said, vaTves prfor to commencing, operation,. if this is the case.
Otherwise, if you.
propose to commence operation prior to. replacing said; vaTves,, the report should indicate the safety-related systems. where such valves are to be. used and. should: include arr evaluation>> a$ the acceptability of operatina with potential1y defectfve valves..
Thfs, evaTuatfon should; address factors such as your proposed. test pTan operator's. abfTfty ta promptly identify
- a. failing ar fangled valve-effect af solenoid valve. failure on safety-related systems and. subsequent operator actions required., and the; preventive
~ measures you pTan to implement ta. circumvent the. effects of fafTures
'f these valves.
If no such; valves are; to: be used. in, your facfTfty., submit. a: negative.
declaration ta'his: effect within forty-ffve (45) days of'he date of this buTTetfn but prior ta the date by, which you expect to receive an operating license; The above requested'eports shalT be submitted. ta the directar of the appropriate NRC, region, within time stfpulatect for each Item in the thfs bulletin.
A copy of each report shall. be forwarded; ta the Director,. Division af Reactor Operations Insoectfon, Offfce of Inspectfon: and Enforcement,.
United States Nuclear Regulatory Camnfssfon, Mashfngton, 0.. C. 20555'.
Approved by GAO, B180225(R0072);.
clearance expires. November 30, 1980.
Approval was given under a, blanket clearance specfffcaTly for identified generic problems.
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Bu eton No.
Subject RECENTLY ISSUED IE BULLETINS Date Issued IEB 80-23 November 14, 1980 Issued To 80-22 Automation Industries, Model 200-520-008 Sealed-Source Connector s 9/11/80 All radiography licensees 80-21 Supplement 3'o 79-1QB Supplement 2
to 79-01B 80-22 Environmental'ualification 10/24/80 oF Class 1E Equipment Envi ronmental equal.i fication 9/30/80 of Class 1E Equipment Automati on Industry es Model 200-520-008 Sealed-source Connector.s.
9/11/80 Yalve yokes supplied. by 11/6/80 Mal'coTm Foundry Company Inc.
AT1 Tight water reactor facilities holding OLs or CPs-All power reactor facilities with an OL A'll power reactor facilities. with an OL AT1 radiography licensees 79-26 Revision 1
80-20 Boron Loss from BNR Control. Blades Failures of >lesNnghouse Type W-2 Spring Return to Neutral ControT. Switches 8/29/80 7/31/80 A1T BMR power facilities with.
an OL To, each, nuclear power facility in.
your. region-having an OL or a CP 80-19 80-18
?/3I/80 Failures of Mercury-tletted Matrix ReTays in:
Reactor Protective Systems of Operating Nuclear Power Plants. Designed'y.: Combus; tion; Engineering Maintenance of'dequate 7/24/80 Minimum FTow, Thru CentrifugaT Charging Pumps Following Secondary Side High Energy Line Rupture ATT nuclear power-faciTities having.
ei.ther an,OL or a CP'TT; PklR. power-reactar faci1ities hoTdfng OLs and to. those PNRs nearing licensing