ML19309G967
| ML19309G967 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 04/17/1980 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Counsil W CONNECTICUT YANKEE ATOMIC POWER CO. |
| References | |
| NUDOCS 8005080069 | |
| Download: ML19309G967 (1) | |
Text
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NUCLEAR REGULATORY COMMISSION
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a nina or, Russia, eEnnsvevania is4os April 17, 1980 Docket No. 50-213 Connecticut Yankee Atomic Power Company ATTN:
Mr. W. G. Counsil Vice President - Nuclear Engineering and Operations P. O. Box 270 Hartford, Connecticut 06101 Gentlemen:
The enclosed IE Bulletin No. 80-09, "Hydramotor Actuator Deficiencies," is forwarded to you for action.
A written response is required.
If you desire additional information regarding this matter, please contact the Office of Inspection and Enforcement, Washington, D.C.
Sincerely,
/
Boyce H. Grier Director
Enclosures:
1.
IE Bulletin No. 90-09 with Attachment 2.
List of Recently Issued IE Bulletins CONTACT:
W. Laudan (301-492-7551) cc w/encls:
R. Graves, Plant Superintendent D. G. Diedrick, Manager of Quality Assurance J. R. Himmelwright, Licensing Safeguards Engineer
l ENCLOSURE 1 i
SSINS No. 6820 UNITED STATES Accession No.:
NUCLEAR REGULATORY COMMISSION 8002280659 0FFICE OF INSPECTION AND ENFORCEMENT m
g c,
WASHINGTON, D.C.
20555 oo S
IE Bulletin No. 80-09 Date:
April 17, 1980 Page 1 of 2 HYDRAMOTOR ACTUATOR DEFICIENCIES i
ITT General Controls (ITT-GC) reported to the NRC two (2) problem areas pertain-l ing to their Models AH-90 and NH-90 Series Hydramoto' Actuators.
The NH-90 designators depicts nuclear class 1E design.
Eithe. of the problems reported 1
could affect the operation of safety-related equipment installed in nuclear power facilities:
A.
On December 7,1979, ITT-GC reported the use af 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 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-96 series hydramotor actuators represent the actual spring or hyaraulic 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 crotruction 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-i 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 Attach-ment No. 1.
Since some of the Original Equipment Manufacturers (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:
IE Bulletin No. 80-09 Date:
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 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 sized 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.
l 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 with a copy to the regional office.
Approved by GAO, B180225 (R0072); clearance expires 7/31/80.
Approval was given under a blanket clearance specifically for identified generic problems.
Attachment
Attachment to IE Bulletin 80-09 Attachment No. 1 Customers Quantities 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 Pr3 ducts Santa Ana, CA 16 Posi Seal International, Inc.
No. Stonington, CT 14 Powers Regulator Co.
Port 1_and, OR 1
Powers Regulator Co.
Skokie, IL 74 Ruskin Manufacturing Co.
Grandview, MO 4
Valtek, Inc.
Springville, UT 9
TOTAL 368 i
ENCLOSURE 2 IE Bulletin No. 80-09 Date: April 17, 1980 Page 1 of 1 RECENTLY ISSUED IE BULLETINS Bulletin Subject Date Issued Issued To No.
80-02 Inadequate Quality 1/21/80 All BWRs with an Assurance for Nuclear Operating License Supplied Equipment (OL) or Construction Permit (CP) 80-03 Loss of Charcoal From 2/6/80 All Power Reactor Standard Type II, 2 Inch, Facilities with an Tray Adsorber Cells OL or CP 80-04 Analysis of a PWR Main 2/8/80 All Power Reactor Steam Line Break with Facilities with an Continued Feedwater Ad-OL or CP dition 79-01B Environmental Quali-2/29/80 All Power Reactors fication of Class IE with an OL except Equipment SEP Plants 80-05 Vacuum Conditions 3/10/80 All PWR Power Reactor Resulting in Damage to Facilities with an Chemical Volume Control OL or CP System (CVCS) Holdup Tanks 80-06 Engineered Safety 3/13/80 All Power Reactor Feature (ESF) Reset Facilities with an Controls OL (For Action)
All Power Rcactor Facilities with a CP (For Information)79-03A Longitudinal Weld 4/4/80 All Power Reactor Defects in ASME Facilities with an SA-312, Type 304 OL or CP Stainless Steel Pipe 80-07 BWR Jet Pump Assembly 4/4/80 BWR 3 & 4's with OL Failure (For Action)
BWR's with CP (For Information) 80-08 Examination of Con-4/7/80 All Power Reactor tainment Liner Facilities with an Penetration Welds OL or CP
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