ML20032D183
| ML20032D183 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek, Cooper, Arkansas Nuclear, River Bend, Waterford, South Texas, Comanche Peak, Fort Calhoun, Fort Saint Vrain  |
| Issue date: | 11/12/1981 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | ARKANSAS POWER & LIGHT CO., GULF STATES UTILITIES CO., HOUSTON LIGHTING & POWER CO., KANSAS GAS & ELECTRIC CO., LOUISIANA POWER & LIGHT CO., NEBRASKA PUBLIC POWER DISTRICT, OMAHA PUBLIC POWER DISTRICT, PUBLIC SERVICE CO. OF COLORADO, TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| References | |
| NUDOCS 8111130473 | |
| Download: ML20032D183 (2) | |
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' UNITED STATES y1 NUCLEAR REGULATORY COMMISSION h
REGION IV
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l Gentlemen:
The enclosed IE Information flotice:provides early 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 bulletin or circular recom-mending or requesting specific licensee actions may be issued.
If you have questions regarding this matter, please contact this office.
Sincerely, Karl V..Seyfrit Director
Enclosures:
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IE Information Notice No. 81-33 2.
List of Recently Issued IE Information Notices 8111130473 811112 gDRADOCK05000g
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l IE INFORMATION NOTICE N0 81-33:
LOCKING DEVICES INADEQUATELY INSTALLED ON MAIN STEAM ISOLATION VALVES Licensee Facility / Docket Number Arkansas Power and Light.Conpany Arkansas Nuclear One,' Unit 1 & 2 Little Rock, Arkansas 50-313; 50-368 Nebraska Public Power District Cooper Nuclear Station Columbus, Nebraska 50-298 0maha Public Power District Fort Calhoun Station Omaha, Nebraska 50-285 Public Service Company of Colorado Fort St. Vrain Generating Station Denver, Colorado 50-267 Gulf States Utilities River Bend Beaumont, Texas 50-458; 50-459 Houston Lighting & Power Company South Texas Project Houston, Texas 50-498; 50-499 Kansas Gas & Electric Company Wolf Creek Wichita, Kansas STN 50-482 Louisiana Power & Light Company Waterford-3 New Orleans, Louisiana 50-382 Texas Utilities Generating Company Comanche Peak Steam Electric Station Dallas, Texas 50-445; 50-446
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8107230036 IN 81-33 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 November 9, 1981 IE INFORMATION NOTICE N0. 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 (821-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 No. 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 raentioned 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 matter 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 information for applicability to their facilities. We suggest that licensees with these Atwood and Morrill valves verify that the locking plates are bent sufficienth; 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 NRC Regional Office.
Attachment:
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_3 i o IE Information Notice No. 81-33 November 9, 1981 LISTING OF RECENTLY ISSUED IE INFORMATION NOTICES Information Subject Date Issued To Notice No. Issued 81-25 Open Equalizing Valve 8/24/81 All power reactor of Differential Pressure facilities with an Transmitter Causes Reactor Operating License (0L) Scram and Loss of Redundant or Construction Permit (CP) Safety Signals. 81-26 Compilation of Health 8/28/81 All power reactor facilities Physics Related Information with an Operating License Items (0L) or Construction Permit (CP) 81-27 Flammable Gas Mixtures 9/3/81 All power reactor facilities in the Waste Gas Decay with an Operating License i Tanks in PWR Plants (0L) or Construction Permit (CP) 81-28 Failure of Rockwell-Edward 9/3/81 All power reactor facilities Main Steam Isolation Valves with an Operating License-(GL) or Construction Permit (CP) 81-29 Equipment Qualification 9/24/81 All power reactor facilities with an Operating License (OL) or Construction Permit (EP) 81-30 Velan Swing Check Valves 9/28/81 All power reactor facilities with an Operating License (0L) or Construction Permit (CP) l 81-31 Failure of Safety Injection 10/8/81 All power reactor facilities Valves to Operate Against with an Operating License Differential Pressure (OL) or Construction Permit (CP) 81-32 Transfer and/or Disposal of 10/23/81 All medical licensees Spent Generators Enclosure l l Fw
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