ML17296B136
| ML17296B136 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 10/31/1980 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| References | |
| NUDOCS 8012170844 | |
| Download: ML17296B136 (14) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION V 1990 N. CALIFORNIASOULEVARD SUITE 202, WAINUTCREEK PLAZA WALNUTCREEK, CALIFORNIA94596 October 31,1980 oA'ocket Nos. 50-528, 50-529, 50-530 Arizona Public Service Company P. 0.
Box 21666 Phoenix, Arizona 85036 Attention:
Hr. E.
E.
Van Brunt, Jr.
Vice President, Nuclear Projects Gentlemen:
The enclosed Information Notice provides early notification of an event that may have safety significance.
Accordingly, you should review the Information Notice for possible applicability to your facility.
No specific action or response is requested at this time; however, contingent upon the results of further staff evaluation, a Bulletin or Circular recom-mending or requesting specific licensee actions may be issued.
If you have questions regarding this matter, please contact me.
Sincerely, gr'~C Ciyj ~
R.
Enge1ken Director
Enclosures:
l.
IE Information Notice No. 80-39 2.
Recently issued IE Information Notices cc w/enclosures:
F.
W. Hartley, APS
UNITED STATES NUCLEAR REGULATORY CO!1MISS ION OFFICE OF INSPECTION AHD ENFORCEMENT
';!ASHIHGTON, D.
C.
20555 SSIHS No.:
6835 Accession Ho.:
8008220245 IN 80-39 October 31 1980 IE INFORMATION NOTICE HO. 80-39:
MALFUNCTION OF'SOLENOID VALVES MANUFACTURED BY VALCOR ENGINEERING CORPORATION PURPOSE:
The intent of this Information Notice is to alert holders of construction permits and ooeratina licenses for nuclear power plants of a potentially generic problem involvinq the malfunctioning of certain solenoid valves manu-factured by the Valcor Engineering Corporation (Valcor).
The solenoid valves so involved are designated as Valcor Valve Model Ho. V52600-554-1.
Valcor has informed us that these valves have only been supplied to the McGuire facility;
- however, since these valves were substituted for solenoid valves of another manufacturer that did not meet the requirements of IE Bulletin Ho. 79-01 and its amendments, licensees and holders of construction permits should take into account the problem identified in this Information Notice prior to making any similar substitution.
BACKGROUND:
By T'l!X dated June 27, 1980, Valcor submitted a preliminary 10 CFR Part 21 Report addressing the malfunctioning of Valcor solenoid valves at the McGuire facility.
The malfunctioning valves have been identified as Valcor Valve Model No. 52600-554-1.
This TWX was subsequently followed by a letter dated July 3, 1980, transmitting a more detailed Part 21 Report entitled,"guality Assurance Report",
a copy of which is attached hereto as Enclosure Ho. l.
In brief, the malfunction appears to be an intermittent type wherein the valve fails to cycle from OPEN to CLOSE to OPEN immediately after a sustained period ofoperation in the energized (OPEN) mode.
Although the valves are rated for "continuous operation",
Valcor contends that the valves were not designed to meet the operating conditions requiring the immediate cycling from OPEN to CLOSE to OPEN after a sustained period of continuous energization.
A major source of the problem, therefore, may be a misunderstanding of the term "continuous operation".
By letter dated July 14, 1980 to Duke Power Company, Valcor'ransmitted its recommendations in this matter entitled, "Outline-Suggested Modification Procedures",
a copy of which is attached hereto as Enclosure Ho. 2.
Enclosures:
1.
equality Assurance Report 2.
Outline - Suggested Modification Procedures.
RECENTLY ISSUED IE INFORMATION NOTICES IN 80-39 October 31
, 1980 Informati on Notice No.
80-36 80-35 Subject Failure of steam aenerator suooort bolting Leaking and dislodged Iodine-124 implant seeds Date o
Issue 10/10/80 10/10/80 Issued to All nuclear power reactor facilities holding OLs or CPs All categories G and Gl medical licensees 80-34 80-33 Boron dilution of r eactor 9/26/80 coolant during steam generator decontamination Determination of tel etherapy 9/15/80 timer accuracy All pressurized water reactor facilities holding power reactor OLs All teletherapy (G3) licensees 80-32 80-31 80-30 80-29 Supplement to 80-06 80-28 Clarification of certain requirements for Exclu-sive-use shipments of radioactive materials t1aloperation of Gould-Brown Boveri Type 480 volt type C-600S and K-DON 600S circuit breakers Potential for unaccept-able interaction between the control rod drive scram function and non-essential control air at certain GE BHR facilities Broken studs on Terry turbine steam inlet flange Notification of siqnificant events at operating power reactor fac i lities Prompt'eporting of required information to NRC 8/12/80 8/27/80 8/19/80 8/7/80 7/29/8Q 6/13/80 All NRC and agreement state licensees All light water reactor facilities holding OLs or CPs All boiling water reactor facilities holding power reactor OLs or CPs.
All light water reactor facilities holding power reactor OLs or CPs*
All holders of reactor and near-term OL applicants All applicants for and holders of nuclear power reactor CPs
+ Operating Licenses or Construction Permits
~ ~
EHCLOSllRE NO.
1.0 VAt COB KNotNKERtNG CORPORPT)oh 1 LAWASNCI AOAO. SAAlNGSIKLO HEW JKASEY 0709 '= U.S.A. ~ L101l 167ISAR TWX 7'l0 996.5979
~ CABLS'ALCOA UA"XTY ASSURANCE R~ORT'UBJ CT1 NRC 10CFR21 Reporting Refe ance:
Valco TWX to NRC dated 6/27/80 2a On June 27, 1980, the Duke Powe Company advised that a failure to actuate valve Part No. V52600-554-1 affects a safety-related system.
It'was reposed that this valve failed to cycle ~ediately following a sustained period of.
continuous energization.
Valcor advised Dyke.that the valve was not designed to meet this operating condition.
The Duke power company indicated that the above part 97as installed in McGuire Nuclear station Sos.
1 and 2 as part of the Diesel Generator Control Air Solenoid Valve System providing instrument, air to the Diesel System-.
- Eight, valves are involved, reference 3b below.
Valve failure to actuate could impair function of the Diese1 Generator which prOVideS pOwer tO Safety-related eleCtriCal COmpcnentS.
3, Valco has reviewed its records and determined that. this potential problem is isolated to the follot ing valves shipped to the Duke Power comoany fo>> McGuire Nuclear Station Nos.
1 and 2:
a.
b.
Ca Customer P.O.
No.
C45389 (N12145)
C45389 (N12145)
C45389 (NL3163D)
C45389 (h123. 45)
C45389 (N13163)
Customer I.ist Part No.
04D-050 (V52600-570"1) 040-052 (V52600-554-l.)
040-053 (V52500-5"5"2) 04D 053 (V52600-555"2) 04C-054 (V52600-5542-1) g~uar.sit 22 1 to 22 1 to 8 10, 11, 12 lto8 1 to 6 10"76 10-76 5-78 10-76 2 78 h.
C45389 (N13163C)
(B3NC)
(Sll
~
ZC)
C~")g9 04D-055 (V52600-5542-2) 4 (V55(YO-a)5l-l)...,.
",6.
(V5 I380-H20 1) 17 1 to 4 '-78 1 a7')8) 12)13, 5 79 a
J 1 to 17 '-79
f I
VAL.CO/ KNOlNEKplNG CO'afar.
g s ~an e
Re oz't Page 2
I S
$~ject zo a rec"irene""
or imedia e cycliag following continuous ezergizatxon valccr ecommends that valves be upgraded by replacement of internal bonnet asserLbly parts.
Xns alled valves will require press' shutdown.
Valcor has ccrmenced preparation of modi ication insta:ctions and will xepor" to Quke 2ower by July 3.4; 1980.
1;i g
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S
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I l
C ENCLOSURE NO. 2 V'~LCQ~ Kf~GfMF.ERtKG CORPORA,t'iOL' LAWRENCE ROAO. SPRINGFIELD. HEW JERSEY 07081. LLS.A ~ Q0) I <57 8400 VPrX 910-990 9976 CABLE:
VALCOR'UTLINE
- SUGGESTED MODI0 ICATION P ROCEDURES REFERE'ACE: Valcox NRC 10CFR21 Report dated 7-3-80.
NOTE:
A new Solenoid Assembly that will meet the new criteria without affecting the valve Cv is not readily available.
All valves noted'in the above referenced report can be modified in the Iield-or at Valcor; -by -replacement o
the Bonnet Assembly.
The valves are to be re identitied by adding a revision letter to Valcor valve Part, No.
on nameplate.
The modification to be coordinated with the Authorized Nuclear Inspector.
- 2.
Installed valves will reauire pressure shutdown.'
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Modification by list Paxt Numbers as noted in the referenced report.
b.
Co List P/N 04D-050 (V52600-570-1).
Dis-assemble valve.
Replace Bonnet Ass'y with Bonnet Ass'y P/N V52661-570-1-1.
Re-assemble valve and per"oxm Hydro
& Operational tests.
Estimated valve Cv change from 25 tn 18.
List P/N 04D-052 (V52600-554-1).
Dis-assemble valve.
Replace Bonnet Ass'y with Bonnet Ass'y P/N V52661-554-1-1.
Re-assemble valve and perform Hvdro 6 Operational tests.
Valve Cv will change
.rom 2. 5 to l.2.
List P/N 04D-053 (V52600-555-2).
Dis~ssemble valve.
Replace Bonnet Ass'y with Bonnet Ass'y P/N V52661-5551-1-1.
Re-assemble valve and perform Hydro
& Operational tests.
Valve Cv will change from 3 to 2.
Valve similar to 04D-222.
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OUTLINE - SUGGESTED HODlPECATZON PROCEDURES d>>
List P/N 04D-053 (V52600-555-2).
Dis-assemble valve.
-5551-1-1.
Replace Bonnet Ass'y with Bonnet. Ass'y P/N V52661-Re-assemble valve and perform Hydro
& Operational tests.
Valve Cv will change from 3 to 2.
Valve will be similar to 04D-222.
List. ~/N 04D-054 (V52600-5542-1)
Dis-assemble valve.
-554-1-1; Reolace Bonnet Ass'y with Bonnet Ass'y P/N V52661-Pe-assenkle valve and perform Hydro 5 Operational tests.
Valve Cv vill change from 3 to 2.
List P/N 04D-055 (V52600-5542-1).
Dis-assemble valve.
554 1
1 ~
R 1 ce Bonnet Ass'y with Bonnet Ass'y P/N V52661-ep ace o
Re-assemble valve and Perform Hydro
& Operational test S ~
Valve Cv will change from 3 to 2.
List P/N 04D-056 (V52600-555l-l).
Dis-assemble valve.
6 -5551-1<<1.
Replace Bonnet. Ass'y with Bonnet. Ass'y P/N V526 1-Re-assemble valve and perform Hydro 6 Operational tests.
Valve Cv will change from 3 to 2.
Valve will be similar to 04D-222.
List P/N 04D-057 (V57300 5220-1).
Dis'assemble valve.
Replace Bonnet Ass'y with Bonnet Ass'y P/N V573661-5220>> >>l.
Re-assemble valve and perform Hydro R Operational tests.
Valve Cv will change from 3 to 2.
Valve wi11 be similar to 04D-223.
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