ML20038A686
| ML20038A686 | |
| Person / Time | |
|---|---|
| Site: | Humboldt Bay, Palo Verde |
| Issue date: | 11/09/1981 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| Shared Package | |
| ML20038A675 | List: |
| References | |
| NUDOCS 8111160172 | |
| Download: ML20038A686 (1) | |
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November 9, 1981 Docket Nos. 50-528, 50-529, 50-530 Arizona Public Service Company P. O. Box 21666 Phoenix, Arizona 85036 Attention:
Mr. E. E. Van Brunt, Jr.
Vice President, Nuclear Projects Gentlemen:
The enclosed infarii.ation notice provides ea:ly notification of an event that may have significance. Accordingly, you should review the information notice for possible applicability to your facility.
No specific action or response is requested at this time; however, contingent upon the results of further staff evaluation, a bulletia or circular recomending or requesting specific licensee actions may be issued.
If you have questions regarding this matter, please contact this office.
Sincerely, e.-
..;sa L L. Rews pt R. H. Engelken Director
Enclosure:
IE Information flotice No. 81-33 cc w/ enclosure:
F. W. Hartley, APS G. C. Andognini, Vice President, Electric Operations IEJC c"<'>
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OFFICI AL RECORD COPY
SSINS No.: 6835 Accession No.:
8107230036 IN 81-33 UNITED STATES NUCLEAR REGULATORY COMMIS5 ION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 November 9, 1981 IE INFORMATION NOTICE NO. 81-33: LOCKING DEVICES INADEQUATELY INSTALLED ON MAIN STEAM ISOLATION VALVES Description of Circumstances:
During recent NRC inspections at the Grand Gulf Nuclear Station, Unit 1 (Mississippi Power and Light. Company), and Hartsville No. Al Nuclear Plant (Tennessee Valley Authority), 26" Main Steam Isolation Valves (B21-F022 and B21-F028) manufactured by Atwood and Morrill Company, Inc., were inspected and were found to be deficient in installation of the locking plates.
These valves are fitted with locking plates which ' prevent rotation of hexag-onal nuts caused by vibration after they are tightened to the studs (part no. 26 Figure No. 1).
A tab of the locking plate is bent during installation to engage the flats of the hexagonal nuts ( Figure !!o.1, part nos. 26, 28 and 33).
The purpose of these studs is to couple the shaft from the air operator to the valve stem.
Failure to bend these locking plates properly around the hexagonal nuts could cause the stroke of the valve stem to be lengthened resulting in the inability to properly open or close the valve.
At the facilities mentioned above, these locking plates failed to engage the flat of the hexagonal nuts.
Since these locking plates are installed at the manufacturer's plant, licensees have generally not been inspecting to verify that the locking plates are installed properly.
Therefore, unless the licensee is required to perform valve rework on stem stroke adjustments in accordance with the Atwood and Morrill Instruction Manual, reverification of the valve-related work would not normally be performed.
This IE information notice is provided as an early notification of a potentially significant ma"er that is still under review by the NRC staff.
If NRC evalu-ation so indicates, further licensee action may be requested.
In the interim, we expect that licensees will review this informa. tion for applicability to their facilities. We suggest that licensees with these Atwood and Morrill valves verify that the it' ;ing plates are bent sufficiently to engage the flats of the hexagonal nuts and perform their locking function.
No written response to this information notice is requested.
If you need additional information, please contact the Director of the appropriate f. C T
Regional Office.
Attachments:
1.
Figure 1 2.
Recently issued IE Information Notices
_-~.--.-n.,
IN 81-33 November 9, 1981 RECENTLY ISSUED IE INFORMATION NOTICES Information Date of
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Notice No.
Subject Issue Issued to 81-32 Transfer and/or Discosal of 10/23/81 All medical licensees Spent Generators 81-31 Failure of Safety Injection 10/8/81 All power reactor Valves to Operate Against facilities with an Differential Pressure OL or CP 81-30 Velan Swing Check Valves 9/28/81 All power reactor
'acilities with an OL or CP 81-29 Equipment Qualification 9/23/81 All power reactor Testing Experience facilities with an OL or CP 81-28 Failure of Rockwell-Edward 9/3/81 All power reactor Main Steam Isolation Valves facilities with an OL or CP 81-27 Flammable Gas Mixtures 9/3/81 All power reactor in the Waste Gas Decay facilities with an Tanks in PWR Plants OL or CP S1-26 Compilation of Health 9/1/81 All power reactor Physics Related Information facilities with an Items OL or CP 81-25 Open Equalizing Valve 8/21/81 All power reactor of Differential Pressure facilities with an Transmitter Causes Reactor OL or CP Scram and Loss of Redundant Safety Signals 81-24 Auxiliary Feed Pump 8/5/81 All power reactor Turbine Bee-ing Failures facilities with an OL or CP 81-23 Fuel Assembly Damaged 8/4/81 All power reactor due to Improper Positioning facilities with an of Handling Equipment OL or CP OL = Operating License CP = Construction Permit
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