ML19309G786
| ML19309G786 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 04/17/1980 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Goodwin C PORTLAND GENERAL ELECTRIC CO. |
| References | |
| NUDOCS 8005070568 | |
| Download: ML19309G786 (1) | |
Text
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'o UNITED STATES
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g NUCLEAR REGULATORY COMMISSION 8005070 3 2
- e REGION V o
g 1990 N. CALIFORNIA BOULEVARD g
e SUITE 202, WALNUT CREEK PLAZA
- .,,e WALNUT CREE K, CALIFORNI A 94596 April 17,1980 Docket flo. 50-344 Portland General Electric Company 121 S. W. Salmon Street Portland, Oregon 97204 Attention: Mr. Charles Goodwin Assistant Vice President Gentlemen:
The enclosed Bulletin 80-09 is forwarded to you for action. A written re-sponse is required.
If you require additional information regarding this matter, please contact this office.
Sincerely, 1
/d%C R. H. Engelken Director
Enclosures:
1.
List of IE Bulletins Recently Issued cc w/ enclosures:
F. C. Gaidos, PGE J. W. Lentsch, PGE C. P. Yundt, PGE
9 I
SSINS No. 6820 UNITED STATES Accession No.:
NUCLEAR REGULATORY C0fC11SSION 8002280659 0FFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 6
April 17, 1980 IE Bulletin No. 80-09 HYDRAM0 TOR ACTUATOR DEFICIENCIES i
ITT General Controls (ITT-GC) reported to the NRC two (2) problem areas pertaining to their Models AH-90 and NH-90 Series Hydramotor Actuators.
The NH-90 designators depicts nuclear class 1E design.
Either of the prob-lems reported could affect the operation of safety related equipment installed in nuclear power facilities:
A.
On December 7,1979, ITT-GC reported the use of springs having incorrect material installed in Models AH-90 and NH-90 Series Hydramotor Actuators.
Instead of 5160 steel, type 1060-1070 steel was used for the No. I springs in the actuators. The incorrect spring material does not meet the design strength and upon actuation of greater than 3 inches stroke, a permanent set occurs resulting in a decreased force output of up to 160 lbs, depending on spring combinations used and specific adjustments made to the actuators.
About 368 defective springs were used between September 1975 and January 1978.
B.
On February 5,1980, ITT-GC repr-ted that the ITT-GC " Selection Homograph" for AH-90 and NH-90 2eries hydramotor actuators represent the actual spring or hydraulic forces only and do not include the effects of friction or residual hydraulic forces.
It has been determined that the actuators can have about 100 lbs. of friction and an additional 40 lbs.
of residual hydraulic pressure. Use of these nomographs may result in selection of actuators undersized for the use intended.
C.
Action to be taken by licensees and construction pemit holders 1.
Each licensee and each holder of a construction permit should determine whether any safety-related system or component in the facility uses an AH-90 or NH-90 series Hydramotor Actuator manu-factured by ITT General Controls.
(Note: To assist in this deter-mination a listing of customers that have purchased said actuators and the number of actuators purchased is appended hereto as Attachment No.1.
Since some of the Original Equipment Manufac-turers (OEM's) may delete the identity of components used in their product, it may be necessary to consult with the OEM to make the required determination.)
2.
Operating facilities using said actuators in safety-related systems should:
l IE Bulletin No. 80-09 April 17, 1980 Page 2 of 2 a.
Review system functional testing to determining that equipment using the subject actuators are periodically tested.
b.
Examine test records to determine whether the functional test results conform to system requirements.
c.
Verify that ample margin exists with respect to thrust delivered to the load for long tem operation considering improper spring material and methods used to select the actuator for a particular application.
d.
Take any corrective actions required by the results of items a.
- b. and c., above.
3.
Facilities with construction permits using said actuators in safety-related systems should:
a.
Reevaluate actuator size selection in light of the possibility of using actuators witn defective springs or which were sized by the " Selection Nomograph" without accounting for internal friction and hydraulic -resistance.
Said reevaluation should assure that the actuators will perform their intendec function.
b.
Modify equipment qualification, preoperational and startup test programs, as necessary, to demonstrate the functional adequacy of the Hydramotor Actuator in light of the aforementioned concerns.
Particular attention should be given to the possi-bility of defective springs taking a pemanent set.
Note: ITT General Controls is presently performing actuator testing on units supplied by one of their customers (American Warming & Ventilating Co. Inc.) and revising the methods used to select actuator application.
Each licensee or holder of a construction pemit should report to the NRC, with a copy to the Regional Director, within 60 days of the results of actions taken, any corrective actions required, and the date when corrective actions were or will be completed. The report should be ad h sed to:
U. S. Nuclear Regulatory Commission, Director of Reactor Constructiu Inspection, 0.I.E.,
Washington, D.C.
20555.
Approved by GAO, B180225 (R0072); clearance expires 7/31/80. Approval was given under a blanket clearance specifically for identified generic pmblems.
Attachment flo.1 Customers Quantities ACDC Inc.
Cincinnati, 011 27 American Harming & Ventilating Co., Inc.
Maumee, Oil 145 Copes Vulcan, Inc.
Lake City, PA 2
Fisher Controls Co., Inc.
Marshalltown, IA 38' Fisher Controls Co., Inc.
j Corapolis, PA 4
t General Signal Corporation West Warwick, RI 2
ITT llammel-Dahl Warwick, RI 4
Jcy Manufacturing flew Philadelphia, Oil 18 Masoneilan International, Inc.
florwood, MA 10 I
Pacific Air Products Santa Ana, CA 16 Posi Seal International, Inc.
flo. Stonington, CT 14 Powers Regulator Co.
Portland, OR 1
Powers Regulator Co.
3 Skokie, Il 74 Ruskin fianufacturing Co.
Grandview, M0 4
Valtek, Inc.
Springville, UT.
9' i
1
. TOTAL 368
~
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IE Bulletin flo. 80-09 Enclosure April 17, 1980 RECENTLY ISSUED IE BULLETIllS Bulletin Subject Date Issued Issued To flo.
80-08 Examination of Containment 4/7/80 All power reactors Liner Penetration Welds with a CP and/or OL no later than 4/7/80 80-07 BWR Jet Pump Assembly 4/4/80 All GE BWR-3 and Failure BWR-4 facilities with an OL
}
80-06 Engineered Safety Feature 3/13/80 All power reactor (ESF) Reset Controls facilities with an OL 80-05 Vacuum Condition Resulting 3/10/80 All PWR power reactor In Damage To Chemical Volume facilities holding Control System (CVCS) Holdup OLs and to those with Tanks a CP 80-04 Analysis of a PWR Main 2/8/80 All PWR reactor facilities Steam Line Break With holding OLs and to those Continued Feedwater nearing licensing i
Addition 80-03 Loss of Charcoal From 2/6/80 All holders of Power Standard Type II, 2 Inch, Reactor OLs and cps Tray Adsorber Cells 80-02 Inadequate Quality 1/21/80 All BWR licenses with Ar.:urance for !!uclear a CP or OL Supplied Equipment 80-01 Operability of ADS Valve 1/11/80 All BWR power reactor Pneumatic Supply facilities with anc OL 79-01B Environmental Qualification 1/14/80 All power reactor of Class IE Equipment facilities wi_th an OL 79-28 Possible Malfunction of 12/7/79 All power reactor Namco Model EA 180 Limit facilities with an Switches at Elevated OL or a CP Temperatures
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