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M d N 81-5 herican Electric Power Service Corporation D. C. Cook 1, 2 (50-315, 50-316)
Cincinnati Gas and Electric Ccmpany Zimmer (50-358)
The Cleveland Electric Illuminating Company Perry 1, 2 (50-440, 50-441)
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Commonwealth Edison Company 3)
N Braidwood 1, 2 (50-456, 50-457) f f
Byron 1, 2 (50-454, 50-455) 8[g
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Dresden 1, 2, 3 (50-10, 50-237, 50-249)
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La Salle 1, 2 (50-373, 50-374)
Quad-Cities 1, 2 (50-254, 50-265)
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Zion 1, 2 (50-295, 50-304) q b
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Consumers Power Company
/NI Big Rock Point (50-155)
Falisades (50-255)
Midland 1, 2 (50-329, 50-330)
Dairyland Power Corporation LACBWR (50-409)
The Detroit Edison Company Fermi 2 (50-341)
Illinois Power Company Clinton 1, 2 (50-461, 50-462)
Iowa Electric Light and Power Company Duane Arnold (50-331)
Northern Indiana Public Service Company Bailly (50-367)
Northern States Power Company Monticello (50-263)
Prairie Island 1, 2 (50-282, 50-306)
Public Service of Indiana Marble 11111 1, 2 (50-546, 50-547)
Toledo Edison Company Davis-Besse 1 (50-346)
Union Electric Company Callaway 1, 2 (40-483, 50-486)
Wisconsin Electric Power Company Point Beach 1, 2 (50-266, 50-301)
Wisconsin Public Service Corporation Kewaunee (50-305) 8111130766 811112 gDRADOCK 05000010 Illinois Department of Nuclear Safety PDR Gary N. Wright, Manager, Nuclear Facility Safety I E 6 1sigA
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- o SSINS No.:
6835 Accession No.:
8107230036 IN 81-33 UNITED STATES NUCLEAR REGULATORY COMMISSION 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 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 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 matter that is still under review by_the NRC staff.
If NRC evalu-ation so indicates, further licensee action may be requested.
In the interir.,
we expect that licensees will review this infornation for applicability to their facilities. We suggett that licensees with these Atwood and Morrill valves verify that the locking pl stes are bent sufficieatly to engage the flats of the hexagonal nuts and perform their locking function.
l No written response to this information notice is requested.
If you need additional information, please contact the Director of the appropriate NRC Regional Office.
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PAGE g ee 2
' Attachment 2 IN 81-33 November 9, 1981
'RECENTLY ISSUED IE INFORMATION NOTICES
'Information Date of
' Notice No.
Subject Issue
' Issued to 81-32 Transfer and/or Disposal 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 facilitics with an OL or CP 81-29 Equipment Qu&lification 9/23/81
.All power reactor Testing Experience facilities with an OL or CP 81-28 Failure of Rockwell-Edwsrd 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 81-26 Compilation of Health 9/3/81 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 Bearing 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
.