ML20033A708
| ML20033A708 | |
| Person / Time | |
|---|---|
| Site: | Monticello, Dresden, Davis Besse, Palisades, Perry, Fermi, Kewaunee, Point Beach, Byron, Braidwood, Prairie Island, Callaway, Duane Arnold, Clinton, Cook, Quad Cities, La Crosse, Big Rock Point, Zion, Midland, LaSalle, Zimmer, Bailly, Marble Hill  |
| Issue date: | 09/28/1981 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| REF-SSINS-6835, REF-SSINS-SSINS-6 NUDOCS 8111270123 | |
| Download: ML20033A708 (1) | |
Text
2*E:z s./ //-Jo American Electric Power Service Corporation D. C. Cook 1, 2 (50-315, 50-316)
Cincinnati Gas and Electric Company Zimmer (50-358)
The Cleveland Electric Illuminating Company Perry 1, 2 (50-440, 50-441)-
Commonwealth Edison Company Braidwood 1, 2 (50-4',6, 50-457)
Byron 1, 2 (50-454, 50-455)
Dresden 1, 2, 3 (50-10, 50-237, 50-249)
La Salle 1, 2 (50-373, 50-374)
Quad-Cities 1, 2 (50-254, 50-265)
Zion 1, 2 (50-295, 50-304)
Consumers Power Company Big Rock Point (50-155)
$l Palisades (50-255)
PI Midland 1, 2 (50-329, 50-330) 6 Ub LACBWR (50-409)
L OCT1 gga ]i Dairyland Power Corporation m
9 u.b'$$ESMj,I The Detroit Edison Company s
Fermi 2 (50-341) j9
'I Illinois Power Company Clinton 1, 2 (50-461, 50-462)
Iowa Electric Light and Power Company Duane Aroold (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 Hill 1, 2 (50-546, 50-547)
Toledo Edison Company Ib Davis-Besse 1 (50-346) 3 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)
Illinois Department of Nuclear Safety Gary N. Wright. Manager,. Nuclear Facility Safety 81112'/0123 810928 PDR ADOCK G5000010
/A -
an
~
SSINS No. 6835 Accession No.:
8107230027 IN 81-30 UNITED STATED NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 September 28, 1981 IE INFORMATION NOTICE N0. 81-30: VELAN SWING CHECK VALVES Description of Circumstances:
Recent occurrences with Velan swing check valves are described below.
1.
On June 30, 1981, Public Service Electric & Gas Company reported (LER 81-035/01T) that on June 6,1981, while a leak in the bonnet of a swing check valve in the steam supply to the turbine driven auxiliary feedwater pump at Salem Generating Station, Unit 2, was being repaired, the valve was found to be internally damaged. The valve is a Velan 6-in. swing check valve (Type B14-2114 B-2TS).
The valve disk stud had broken and the valve disk was in the bottom of the valve body.
The valve also had cracks in the disk, cracked bushings, a warped hinge pin, and all hinge pin holes were elongated.
The licensee inspected the corresponding swing check valve in the other steam supply line and discovered similar damage.
An inspection of the corresponding swing check valves on Unit 1 also revealed similar damage (LER 81-059/01T).
The licensee plans to radiologically examine the valves monthly until a reason for the damage can be determined.
2.
On July 31, 1981, Wisconsin Electric Power Company reported (LER 81-010/01T-0) that on July 14, 1981, while a check valve leakage test at the Point Beach Nuclear Plant, Unit 1, was being performed, the check valves closest.to the reactor coolant system in the low head safety injection lines were found to be leaking more than allowed by the leakage acceptance criteria.
The valves are Velan 6-in. 1500 psig ASA swing check valves (Velan Drawing No. 78704).
The valves were disassembled and the disks were found to be stuck in the full-open position due to interference between the disk nut lockwire (disk wire) and the valve body.
The disk nut and its shaft can rotate freely, and, in certain random rotational positions, this interference is likely to occur.
ihe licensee has replaced the disk wire with a cotter pin that will not cause interference with the valve body for any rotational position.
Subsequent inspection of the other check valves in the low head safety injection lines l
t
IN 81-30 September 28, 1981 Page 2 of 2 was performed.
These. valves were found to be closed.
The lock wires were nevertheless replaced with cotter pins.
The drawing for the same valve used at the Prairie Island plant was also checked.
The drawing (Velan Drawing No. 78704) is annotated to require that the -lock wire be tack welded down (so it cannot interfere with the valve body).
Because this detail is not uniform on the subject drawing and can vary from plant to plant, a verification and/or changeout on this locking device may be necessary.
Additional occurrences with Velan swing check valves are described in IE Bulletin 79-04, " Incorrect Weights for Swing Check Valves Manufactured by Velan Engineering Corporation," and in IE Information Notice 80-41, " Failure of Swing Check Valve in the Decay Heat Removal System at Davis-Besse Unit No. 1."
This information is provided as notification of a potentially significant matter.
It is expected that recipients will review the information for possible applicability to their facilities.
No specific action or response is requested at this time.
If you have questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.
Attachment:
Recently issued IE Information Notices
Atttchment IN 81-30 September 28, 1981 RECENTLY ISSUED IE INFORMATION NOTICES Information Date of Notice No.
Subject Issue Issued to 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 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 Signals81-24_
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 81-22 Section 235 and 236 7/31/81 All power research Amendments to the reactor, fuel Atomic Energy Act fabrication and of 1954 reprocessing, and spent fuel storage licensees and applicants 81-21 Potential Loss of Direct 7/21/81 All power reactor Access to Ultimate Heat Sink facilities with an OL or CP OL = Operating License CP = Construction Permit