ML17296B117
| ML17296B117 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 11/06/1980 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| References | |
| NUDOCS 8012120209 | |
| Download: ML17296B117 (5) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION V 1990 N. CALIFORNIABOULEVARD I 6~I'0 Ol5fAIOI/f'fotl SUITE 202, WALNUTCREEK PLAZA ilgjfgfg
+JAN WALNUTCREEK, CALIFORNIA94596 November 6, 1980
)pg} /mt [O pg Docket Nos. 50-528, 50-529, 50-530 US INC DISTRIBUTIONS@Vggg BRANCH Arizona Public Service Company P. 0.
Box 21666 Phoenix, Arizona 85036 Attention:
ter.
E.
E. Van Brunt, Jr.
Vice President, Nuclear Projects Gentlemen:
y D
The enclosed IE Bulletin No. 80-21 requires your action with regard to your power reactor facility(ies) holding an operating license or a construction permit.
Should you have questions concerning this bulletin or the actions required of you, please contact this office.
Sincerely,
Enclosures:
1.
Recently Issued IE Bulletins cc w/enclosures:
F. M. Hartley, APS
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UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT llASHINGTON, D.C.
20555 SSINS No.:
6820 Accession No.:
8008220246 IEB 80-21 November 6, 1980 IE BULLETIN NO. 80-21:
VALVE YOKES SUPPLIED BY MALCOLM FOUNDRY COMPANY, INC.
Descri tion of Circumstances:
On June 17, 1980, Pennsylvania Power and Light Company notified IE Region I that cracks had been discovered in the yokes of a number of valves in the residual heat removal (RHR) system at their Susquehanna Steam Electric Station.
The potential for common-mode failure of the yokes on several valves in redundant, safety-related trains of the RHR system consti tutes a failure mode whereby all RHR functions could be simultaneously lost.
Specifically, the cracks were located in the radii at the yoke mounting flange-to-yoke vertical section interface.
An analysis and evaluation of the most severely cracked valve yoke was performed by the valve manufacturer, Anchor Darling Valve Company.
They concluded that the cracking was not due to casting defects, but rather was due to the yoke material not having the proper mechanical.properties.
Purchased as ASTM A-216, Grade llCB material, the actual valve yoke material had tensile and yield
.strengths below the minimum values listed in the ASTM material specification.
The cracked valve yokes were all cast by Malcolm Foundry Company, Inc., of
- Newark, New Jersey.
The foundry is no longer in business.
Anchor Darling has begun a program of verifying the tensile strengths of the other valve yokes cast by Malcolm and used on Anchor Darling valves at Susquehanna.
To date, approximately half of the valve yokes have been tested.
Of those tested, over 25 percent of the valve yokes have revealed Brinell hard-ness values significantly below the appropriate value obtained from the approxi-mate relationship 'of Brinell hardness to tensile strength included in ASTM.
Specification A-370.
These additional valve yokes are on a wide range of valve sizes and are from a number of different purchase orders placed with Malcolm over a period of at least ten months during 1974 and 1975.
Thus, it appears that the problem is not isolated to one heat of material or to one short time period.
Anchor Darling intends to replace the defective valve yokes at Susquehanna and to begin a testing program at other nuclear power plants under construction where valves with valve yokes cast by Malcolm have been provided.
Since Malcolm Foundry Company, Inc., is no longer in business, the NRC staff cannot determine directly if Malcolm has provided valve parts to other valve manufacturers for use in nuclear power plants.
Actions To Be Taken b
Addressees:
For all power reactor licensees or holders of construction permits the following actions are required:
IEB 80-21 November 6, 1980 Page 2 of 2 1.
Determine if any of the active valves in use or planned for use in safety-related systems at your facility have valve parts cast by Malcolm Foundry
- Company, Inc.
If no valves are identified as having potentially faulty material, indicate that this is the case and ignore the remaining questions.'.
Licensees having active safety-related valves with potentially faulty material shall immediately visually inspect for cracks all normally accessible valve parts (i.e.,
those which can be inspected during reactor operation).
3.
Licensees or permit holders having active safety-related valves with potentially faulty material shall identify the manufacturer(s) of these valves and either:
a ~
Verify that all valve parts cast by tlalcolm have mechanical proper ties in accordance with the ASTM material specification; if such is noi the case, then comply with either b. or c. below also.
b.
Replace the defective materials and/or valves.
c.
Identify any other corrective actions that may be exercised and the basis for such actions.
For plants with an operating license, the results of your initial determination (i tem 1), visual inspection results (item 2);
a list of affected valve manu-facturers, your planned action (item 3), and the schedule for accomplishing this action shall be reported within thirty days of the date of this bulletin to the Director of the appropriate NRC Regional Office with a copy sent to the NRC Office of Inspection and Enforcement, Division of Reactor Construction Inspection,
'Hashington, DC 20555.
For plants with a construction permit, the results of your initial determination (item 1),
a list of affected valve manufacturer(s),
your planned action (item
- 3) and the schedule for accomplishing this action shall be reported within sixty days of the date of this bulletin to the Director of the appropriate NRC Regional Office with a copy sent to the NRC Office of Inspection and Enforcement, Division of Reactor Construction Inspection, Washington, DC 20555.
Compliance with this bulletin by the licensees does not relieve the affected valve manufacturers from the reporting requirements of 10 CFR Part 21.
If you desire additional information regarding this matter, please contact the appropriate IE Regional Office.
Approved by GAO, B180225 (R0072); clearance expires November 30, 1980.
Approval was given under a blanket clearance specifically for identified generic problems.
RECENTLY ISSUED IE BULLETINS IEB 80-21 November 6, 1980 Bulletin No.
Subject Date Issued Issued To Supplement 3
to 79-10B Supplement 2
to 79-01B 80-22 79-26 Revision 1
80-20 80-19 80-18 Environmental gualification of Class lE Equipment Environmental gualification of Class 1E Equipment Automation Industries, Model 200-520-008 Sealed-source Connectors Boron Loss from BHR Control Blades Failures of llestinghouse Type ll-2 Spring Return to Neutral Control Switches Failures of Mercury-lletted Matrix Relays in-Reactor Protective Systems of Operating Nuclear Power Plants Designed by Combus-tion Engineeririg Maintenance of Adequate Minimum Flow Thru Centrifugal Charging Pumps Following Secondary Side High Energy Line Rupture 10/24/80 9/30/80 9/11/80 8/29/80 7/31/80 7/31/80 7/24/80 All power reactor facilities with an OL All power reactor facilities with an OL All radiography licensees All BWR power facilities with an OL To each nuclear power facility in your region having an OL or a CP All nuclear power facilities having either an OL or a CP All PHR power reactor facilities holding OLs and to those PMRs nearing licensing Supplement 2
to 80-17 Supplement 1
to 80-17 80-17 Failures Reve'aled by Testing Subsequent to Failure of Control Rods to Insert During a Scram at a BilR Failure of Control Rods to Insert During a Scram at a BllR Failure of Control Rods to Insert During a Scram at a BllR 7/22/80 7/18/80 7/3/80 All BWR power reactor facilities holding OLs All BllR power reactor facilities holding OLs All Bl1R power reactor facilities holding OLs