ML19309G652
| ML19309G652 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 04/17/1980 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Hines E DETROIT EDISON CO. |
| References | |
| NUDOCS 8005070301 | |
| Download: ML19309G652 (1) | |
Text
.
in, UNITED STATES TIC 4
8
't NUCLEAR REGULATORY COMMISSION 800 07o 3 0/,
5 a
REGION lil g
P, 799 ROOSEVELT ROAD g
GLEN ELLYN. ILLINOlt 8C137 Docket No. 50-341 N1I E The Detroit Edison Company ATTN:
Mr. Edward Hines, Assistant Vice President and Manager Quality Assurance 2000 Second Avenue Detroit, MI 48226 Gentlemen:
The enclosed Bulletin 80-09 is forwarded to you for action. A written response is required.
If you require additional information regarding this matter, please contact this office.
Sincerely, Ah.
James G. Keppler Director
Enclosure:
IE Bulletin No. 80-09 cc: w/ encl:
Central Files Director, NRR/DPM Director, NRR/ DOR PDR Local PDR NSIC TIC Ronald Callen, Michigan Public Service Commission Eugene B. Thomas, Jr.,
Attorney
6 l
l SSINS No. 6820 UNITED STATES Accession No.:
NUCLEAR REGULATORY COMMISSION n.50 3806g n
OFFICE OF INSPECTION A.ND ENFORCEMENT WASHINGTON, D.C.
20555 J
o, :..m
. J l
April 17, 1980 l
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 1
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 l
springs in the actuators.
The incorrect spring material does not meet I
the design strangth and upon actuation of geater 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 sr, rings 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 i
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:
i
IE Bulletin No. 80-09 April 17, 1980 Page 2 of 2 Review system functional testing to determining that equipment a.
using the subject actuators are periodically testell.
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 siied 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 l
within 60 days of the results of actions taken, any corrective actions required, l
and the date when corrective actions were or will be completed.
The report I
should be addressed to:
U. S. Nuclear Regulatory Com.ission Director of Reactor Construction Inspection, 0.I.E.
l Washington, D.C.
20555 A copy of the report should be sent to the Region Office.
l Approved by GAO, B180225 (R0072); clearance expires 7/31/80.
Approval was given under a blanket clearance specifically for identified generic problems.
l
i Attachment No. 1 Customers
, uantities Q
ACDC Inc, Cincinnati, 0H 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 Corporetion West Warwick, RI 2
ITT Hammel-Dahl Warwick, RI 4
Jay Manufacturing
'4ew 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 Portland, OR 1
i Powers Regulator Co.
Skokie, IL 74' Ruskin Manufacturing Co.
Grandview, M0 4
Valtek, Inc.
Springville, UT 9
TOTAL 368 l
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IE Bulletin No. 80-09 Enclosure April 17, 1980 RECENTLY ISSUED 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 BWR Jet Pump Assembly 4/4/80 All GE BWR-3 and Failure BWR-4 facilities with an GL 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 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 Assurance for Nuclear a CP or OL ~
Supplied Equipment 80-01 Operability of ADS Valve 1/11/80 All BWR phwer reactor Pecumatic 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 Namco Model EA 180 Limit facilities with en Switches at Elevated OL or a CP Temperatures
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