ML19309G660
| ML19309G660 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 04/21/1980 |
| From: | Carroll D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Wright G ILLINOIS, STATE OF |
| References | |
| NUDOCS 8005070315 | |
| Download: ML19309G660 (2) | |
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UNITED STATES NC j
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NUCLEAR REGULATORY COMMISSION o
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%,.....,e GLEN ELLYN, ILLINOIS 60137 APR 211980 State of Illinois Department of Public Health ATTN:
Mr. Gary N. Wright, Chief Division of Nuclear Safety 535 West Jefferson Street Springfield, IL 62761 Gentlemen:
The attached IE Bulletin No. 80-09 titled "Hydramotor Actuator Deficiencies" was sent to the licensees listed below on April 17, 1980 for action:
American Electric Power Service Corporation Indiana and Michigan Power Company D. C. Cook 1, 2 (50-315, 50-316)
Cincinnati Gas & Electric Company Zimmer (50-358)
Cleveland Electric Illuminating Company Perry 1, 2 (50-440, 50-441)
Commonwealth Edison Company Braidwood 1, 2 (50-456, 50-457)
Byron 1, 2 (50-454, 50-455)
Dresden 1, 2, 3 (50-10, 50-237, 50-249)
LaSalle 1, 2 (50-373, 50-374)
Quad-Cities 1, 2 (50-254, 50-265)
Zion 1, 2 (50-295, 50-304)
Consumers Power Company Big Rock Point (50-155)
Midland 1, 2 (50-329, 50-330)
Palisades (50-255)
Dairyland Power Cooperative LACBWR (50-409)
Detroit Edison Company Fermi'2 (50-341)
Illinois Power Company Clinton 1, 2 (50-461, 50-462)
I Those on Attached List Iowa Electric Light & Power Company f' r Duane Arnold (50-331)
Northern Indiana Public Service Company
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Bailly (50-367)
Northern States Power Company Monticello (50-263)
Prairie Island 1, 2 (50-282, 50-306)
Public Service of Indiana Marble Hill 1, 2 (50-546, 50-547)
Toledo Edison Company Davis-Besse 1 (50-346)
Union Electric Company Callaway 1, 2 (50-483, 50-486)
Wisconsin Elactr@c Power Company Point Beach 1, 2 (50-266, 50-301)
Wisconsin Public Service Corporation Kewaunee (50-305)
Sincerely, i
orothy a roll, Acting Chief Administrative Branch
Enclosure:
IE Bulletin No. 80 09 cc w/cncl:
Mr. D. W. Kane, fargent & Lundy Central Files Reproduction Unit NRC 20b Local PDR NSIC j
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9 SSINS No. 6820 UNITED STATES Accession No.:
NUCLEAR REGULATORY COMMISSION 8002280659 0FFICE OF INSPECTION AND ENFORCEMENT 3
c' WASHINGTON, D.C.
20555 S
bc April 17, 1980 IE Bulletin No. 80-09 HYDRAMOTOR ACTUATOR DEFICIENCIES 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 problems 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. 1 springs in the actuators.
The incorrect spring material does not meet the design strength and upon actuation of greater than 3 inches stroke, a l
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 reported that the ITT-GC " Selection Nomograph" for AH-90 and NH-90 series 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 permit 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 (0EM'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:
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- l IE Bulletin No. 80-09 April 17, 1980 V
Page 2 of 2 Review system functional testing to determining that equipment a.
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 term 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 with defective springs or which were sizea by the " Selection Nomograph" without accounting for internal friction and hydraulic resistance.
Said reevaluation should assure that the actuators will perform their intended 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 permanent 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 permit should report to the NRC 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 addressed to:
U. S. Nuclear Regulatory Commission Director of Reactor Construction Inspection, 0.I.E.
Washington, D.C.
20555 A copy of the report should be sent to the Region Office.
Approved by GAO, B180225 (R0072); clearance expires 7/31/80.
Approval was given under a blanket clearcnce specifically for identified generic problems.
i f
g Attachment No. 1 Customers Quaiitities ACDC Inc, Cincinnati, OH 27 American Warming & Ventilating Co., Inc.
Maumee, OH 145 Copes Vulcan, Inc.
Lake City, PA 2
Fisher Controls Co., Inc.
Marshalltown, IA 38
?
Fisher Controls Co., Inc.
Corapolis, PA 4
General Signal Corporation West Warwick, RI 2
ITT Hammel-Dahl Warwick, RI 4
Joy Manufacturing New Philadelphia, OH 18 Masoneilan International, Inc.
Norwood, MA 10 Pacific Air Products Santa Ana, CA 16 Posi Seal International, Inc.
No. Stonington, CT 14 Powers Regulator Co.
I Pertland, OR 1
Powers Regulator Co.
Skokie, IL 74 Ruskin Manufacturing Co.
Grandview, M0 4
l l
Valtek, Inc.
Springville, UT 9
TOTAL 368
p IE Bulletin No. 80-09 Enclosure j
April 17, 1980 RECENTLY ISSUE 0 IE BULLETINS Bulletin Subject Date Issued Issued To No.
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 6dR 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
.3-05 Vacuum Condition Resulting 3/10/80 All PWR power reactor
^
In Damage To Chemical Volume faci?itics 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 l
Continued Feedwater nearing licensing Addition 80-03 Loss of Charcoal From 2/6/80 All holders of Power j
Standard Type II, 2 Inch, Reactor OLs and cps Tray Adsorber Cells 80-02 Inadequate Quality 1/21/80 All BWR licenses with Assurance for Nuclear a CP or OL Supplied Equipment 80-01 Operability of ADS Valve 1/11/80 All BWR phwer reactor Pneumatic Supply facilities with and OL 79-01B Environmental Qualification 1/14/80 All power reactor of Class IE Equipment facilities with an OL 79-28 Possible Malfunction of 12/7/79 All power reactor l
Namco Model EA 180 Limit facilities with an Switches at Elevated OL or a CP Temper tures
.