05000414/LER-2002-001, Re Safety Related Plant Component Was Rendered Inoperable as a Result of a Manufacturing Deficiency Identified in a 10 CFR Part 21 Notification
| ML022330440 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 08/12/2002 |
| From: | Gordon Peterson Duke Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 02-001-00 | |
| Download: ML022330440 (8) | |
| Event date: | |
|---|---|
| Report date: | |
| 4142002001R00 - NRC Website | |
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- - I Duke GARY R. PETERSON
- wPower Vice President A Duke Energy Company Duke Power CN01 VP / 4800 Concord Rd York, SC 29745 803 831 4251 803 831 3221 fax grpeters@duke-energy corn August 12, 2002 U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D.C. 20555
Subject:
Catawba Nuclear Station, Unit 2 Docket No. 50-414 Licensee Event Report 414/02-001 Attached is Licensee Event Report 414/02-001 titled "Safety Related Plant Component Was Rendered Inoperable as a Result of a Manufacturing Deficiency Identified in a 10 CFR Part 21 Notification.
There are no regulatory commitments contained in this letter or its attachment.
This event is considered to be of no significance with respect to the health and safety of the public.
If there are any questions on this report, please contact L.J. Rudy at (803) 831-3084.
Since l ly Gary R. Peterson Attachment www duke-energy com
f b
Document Control Desk Page 2 August 12, 2002 xc (with attachment):
Mr. Luis A. Reyes Regional Administrator, Region II U.S. Nuclear Regulatory Commission 61 Forsyth Street, S.W., Suite 23T85 Atlanta, GA 30303 Mr. Chandu P. Patel (addressee only)
U.S. Nuclear Regulatory Commission Mail Stop 08-H12 11555 Rockville Pike Rockville, MD 20852-2738 Mr. Darrell J. Roberts NRC Senior Resident Inspector Catawba Nuclear Station INPO Records Center 700 Galleria Place Atlanta, GA 30339-5957 Marsh & McLennan, Inc.
Mr. Kenneth W. Gannaway 100 N. Tryon Street Charlotte, NC 28202
Abstract
On June 10, 2002, Rotork Controls, Inc. (Rotork) submitted a 10 CFR Part 21 notification to the NRC.
This report described a problem discovered with the NAl type electric valve actuators fitted with an Add-on-Pak 1 (AOP1) assembly, manufactured between 1978 and October 2001, that have a safety related function and are used for end of travel indication. The molded components within the AOP1 assembly have a low level of crystallinity and cannot be confirmed to be of the same specification as those originally tested and qualified in 1978.
The low level of crystallinity could distort in extreme circumstances, causing the actuator switches to reset or fail to operate.
Duke Energy personnel evaluated all existing safety related applications utilizing Rotork actuators.
One application was found to result in an inoperable component due to the concern identified in the notification.
This component is a valve in the Containment Air Release and Addition System.
At the time of this event, this valve was already inoperable due to a problem unrelated to the notification.
The operator for this valve will be replaced during the next Unit 2 refueling outage.
NRC FORM 366 (7-2001)
(if more space is required, use additional copies of (if more space Is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A) (17) quality considerations for personnel entry, or for surveillances that require the valves to be open.
The probability of a DBA occurring during the intervals that valves 2VQ015B and 2VQ016A were open for reasons allowed by Technical Specifications would have been small.
In addition, valve 2VQ015B was unaffected by the issue described in the 10 CFR Part 21 notification.
This event was of no significance with respect to the health and safety of the public.
ADDITIONAL INFORMATION
Within the last three years, only one other LER occurred that was caused by a potential manufacturing defect. ILER 414/01-003 described a reactor trip that occurred as a result of a coil failure in one of the reactor coolant pump motors.
However, the specifics of the two events were dissimilar.
In addition, there have been no LERs within the last three years resulting from 10 CFR Part 21 notifications.
Therefore, this event is considered to be non-recurring in nature.
Energy Industry Identification System (EIIS) codes are identified in the text as [EIIS: XX].
This event is considered reportable to the Equipment Performance and Information Exchange (EPIX) program.
This event is not considered to be a Safety System Functional Failure.
There were no releases of radioactive materials, radiation exposures, or personnel injuries associated with this event.