ML19345C250
| ML19345C250 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 11/14/1980 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Crane P PACIFIC GAS & ELECTRIC CO. |
| References | |
| NUDOCS 8012040230 | |
| Download: ML19345C250 (1) | |
Text
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UNITED STATES
[
NUCLEAR REGULATORY COMMISSION g
REGION V o
1990 N. CALIFORNIA 80ULEVARD SUITE 202, WAUJUT CREEK PLAZA
- ,,,e WALNUT CREEK. CALIFORNIA 94596 Movember 14, 1980
-r Docket Nos. 50-275, 50-323
~d2 3,
Pacific Gas and Electric Company 77 Beale Street San Francisco, California 94106 Attention: Mr. Philip A. Crane, Jr.
Assistant General Counsel
~
Gentlemen:
Enclosed is IE Bulletin No. 80-23 which requires action by you with regard to your nuclear power facility (ies) with an ocerating license or constructicn permit.
In order to assist the NRC in evaluating the value/ impact of each bulletin on licensees, it would be helpful if you would provide us an estimate of the manpcwer expended in conouct of the review and preparaticn of the report (s) recuired by the bulletin. Please estimate separately the manpower associated with corrective actions necessary following identification of problems througn the bulletin.
Should you have any questicas regarding this bulletin or the action required by you, please centact this office.
Sincerely,
[f.YQ$
R. H. Engelken Director
Enclosures:
1.
Recently issued IE Bulletins cc w/ enclosures:
E. B. Langley, Jr., PG&E W. Raymond, PG&E R. C. Thornberry (Diablo Canyon), PG&E
SSIlls No.: 6820 Accession No.:
8008220257 IEB 80-23 UNITED STATES m-D g,
t, NUCLEAR REGULATORf CCMMISSION g
2 J rt _
CFFICE OF INSPECTION AtiD Ei; FORCE"ENT oo UASHIMGTON, D.C.
20555
==
Introduction:==
Valcor Engineering Corporation (Valcor) has submitted 10 CFR Part 21 Reports addressing failures of Valcor scienoid valves used at nuclear ocwer facilities.
These failures have occurred at nuclear facilities owned by Cuke Pcwer Ccmpany and Craha Public Power District, and are purcortecly limited to solencid valves having part numcers (P/tt's) V70900-21-1 and V70900-21-3.
The information presented in this bulletin is intended to shed light en the defective solenoid valves so tnat appropriate actions can ce taken to circum-vent the cegradation of any safety-reiateo system using sucn solenoid valves.
DISCUSSION:
The scecific Valccr solenoid valves accressea herein were purportedly designed-as Class IE ccmponents.- Mcwavar, in light of the reportec failures, it appears that neither the design nor the cualification tests were acequate for Class IE service. Valect his attributed the failures to a la ant defect in the magnet wire. E 'or believes that this defect manifests itself wnen the solenoid valves as entinuously energized at elevated temperatures by an inccmpata-bility y acen the magr.et wire's polyvinyl varnish coating anc the wire's polyim f insulation which causes a dielectric breakdown leading to turn-to-turn shorts within the coil.
^
Valccr states that the above inccccatability is limited to solenoid valves having P/N's V70900-21-1 and V70900-21-3, and that all custcmers affected by the aforementioned defect have been notified. A listing of Valcor cusemers so notified and valves purchased follcws.
CUSTCPER 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 10 Duke Pcwer Company E95183-11 V70900-21-3 100 Duke (Mill Pcwer)
C-97733 V70900-21-1,-3 335 Cuke Pcwer 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 Cmata 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 Pages 2 of 3 l
Valcar's corrective actions include making arrangements for replacing existing te;h with a newly designed coil using a 997 silicone w.rnish 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 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 exoerienced 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 facters (i.e., continuously energized moce of operation and a somewhat elevated temperature inside containment) tend to support Valcor's contention regarding the failure mechanism.
1.:TIONS TO BE TAKEN BY LICENSEES:
1.
Determine whether Valcor solenoid valves having P/N's V70900-21-1 or -3 are used to perfom any safety-related function at your facility.
If so, identify the safety-related systems using these solenoid valves, the toul number of such solenoid valves used, and evaluate acceptability of continued 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 saic 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 operating plants using the aforementioned solanoid valves in safety-related applications rqall periodically test the coils for t
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 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 normally energized mode; (b). Weekly for solenoid valves operated in a normally deenergized mode.
O IEB 80-23 November 14, 980 Pages 3 of 3 Whenever the tests indicate that ten cercent 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 coerating plants shall submit a report within forty-five (45) days of the date of this bulletin describing their longer term corrective acticn plan and the date by which the corrective actions will be imolemented. 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 comoletely new unit) shall be demonstrated to be qualified for its safety-related acolicaticn cer the acclicable recuirements of IEEE 222-1974, IEEE 344-1975, IEEE 382-1972 and IE Bulletin No.79-01B and supplements thereto.
ACTICNS TO BE TAKEN BY HOLDERS OF CONSTRUCTION PERMITS:
1.
Cetermine whether Valcor solenoid valver having P/N's V70900-21-1 or -3 are to be used to perform safety-relatea functions at your facility.
If so, a report accressing this matter snall be submitted by the earlier of the two folicw 1 cates:
(a) within ninety (90) days of the date of this bulletin; to) two weeks prior to the date by which you expect to receive an operating. License..
The above report should indicate your plans to replace said valves crier to commencing cperation, if this is the case. Othemise, if you prcpose to ccmmence operation prior to replacing said valves, the report should indicate the safety-related systems where such valves are to be used, and snould include an evaluation of the acceptability of operatinp with potentially defective valves. This evaluaticn 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 ycu 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 declaraticn 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 NP.C region within time stipulated for each item in the this bulletin. A cooy of each report shall be forwarded to the Director, Division of Reactor Operations Inspection, Office of Inspection and Enforcement, United States Nuclear Regulatory Cennission, Washington, D. C. 20555.
ApprovedbyGAO,B180225(R0072); clearance expires November 30, 1980. Approval was given under a blanket clearance specifically for identified generic problems.
IEB 80-23 November 14, 1980 RECEilTLY ISSUED IE BULLETINS Bulletin No.
Subject Date Issued Issued To 80-22 Automation Industries.
9/11/80 All radicgraphy 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 CLs or cps Supolement 3 Environmental cualificaticn 10/24/80 All power reactor to 79-108 of Class 1E Equipment facilities with an OL Supplement 2 En<ironmental Oualification 9/30/80 All power reactor to 79-01B af Class IE Equipment facilities with an OL 80-22 Autcmatien Industries.
9/11/80 All radiography Model 200-520-008 Sealed-licensees scu e Connectcrs 79-26 Beren Loss frcm BWR 8/29/80 All BWR pcwer Revision 1 Centrol Blades facilities with an OL 80-20 Failures of Westinghouse 7/31/80 Tc each nuclear Type W-2 Spring Return pcwer facility in to Neutral Control Switches ycur "egion having an OL cr a CP 80-19 Failures of Mercury-7/31/80 All nuclear power Wetted Matrix Relays in facilities having Reactor Protective Systems either an OL or a CP of Cperat';.g 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 CLs Charging Pumps Following and to those PWRs Secondary Side High Energy nearing licensing Line Rupture 1