ML20033C773
| ML20033C773 | |
| 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: | 10/08/1981 |
| 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 8112040184 | |
| Download: ML20033C773 (1) | |
Text
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~EG;rtJ SI-bl Anterican 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 (50-455, 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)
Palisades (50-255)
Midland 1, 2 (50-329, 50-330)
Dairyland Power Corporation LACBWR (50-409)
The Detroit Edison Company Fermi 1 (50-341)
Illinois Power Company Clinton 1, 2 (50-461, 50-462) l l
Iowa Electric Light and Power Company l
Duane Arnold (50-331)
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Northern Indiana Public Service Company l
Bailly (50-367)
Northern States Power Cornpany Monticello (50-263)
Prairie Island 1, 2 (50-282, 50-306) i-Public Service of Indiana l
Marble Hill 1, 2 (50-546, 50-547)
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Toledo Edison Company g
I Davis-Besse 1 (50-346)
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Union Electric Company
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g, Callaway 1, 2 (40-483, 50-486) i I
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Wisconsin Electric Power Company Point Beach 1, 2 (50-266, 50-301) b.
[*[N Wisconsin Public Service Corporation Kewaunee (50-305)
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Illinois Department of Nuclear Safety 8112040184 811008 Gary N. Wright, Manager, Nuclear Facility Safety {DRADOCK0500
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SSINS No.:
6835 Accession No.:
8107230032 IN 81-31 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 October 8, 1981 INFORMATION NOTICE NO. 81-31:
FAILURE OF SAFETY INJECTION VALVES TO OPERATE AGAINST DIFFERENTIAL PRESSURE Description of Circumstances:
Both trains of the San Onofre Unit 1 safety injection system were found to be inoperable when challenged under actual operating conditions on September 3, 1981.
Following manual reactor trip from 88% power due to steam generator flow and level oscillations caused by a regulated power supply failure, low primary system pressure caused a safety injection initiation signal.
The licensee reported that operators dispatched to the auxiliary building following the safety injection initiation signal found that neither of the safety injection valves, located in the discharge of both trains of the safety injection pumps, i
had opened as required.
There were no adverse consequences in this particular event since there was no less of coolant accident.
The reactor pressure remained above the safety injection pump's shutoff head and therefore no actual injection of water would have occurred if the valves had opened.
However, had reactor pressure decreased and actual injection been required, injection flow would not have been automatically available as designed.
l The valves which failed to open are 14-inch Anchor Darling, Series 600, stain-I less steel, Part No. SI-50-WDD valves using Greer Hydraulics No. 832210 actuators.
Tests were conducted on these valves in the as-found condition following this event and both valves failed to open against the 1,200 psi differential pressure which would normally exist across the valves following a safety injection signal.
Pressure was lowered until one valve opened with a 520 psid and the other at i
80 psid.
Subsequent tests were performed after readjusting the valve packing to determine the cause of the failure.
These tests also failed to provide con-sistent opening against a 1,200 psid.
System modifications and further testing is under way to provide the necessary reliability for the safety injection system.
These valves had been regularly tested at each refueling outage, but the tests i
ware not required to be performed with differential pressure across these valves, i
There may be systems and components at other facilities that are et periodical-ly tested under the differential pressure conditions at which they are designed t
to operate.
Consequently, we suggest that recipients of this notice take appro-priate steps to determine whether or not situations similar to the above could exist at the recipients' plant (s).
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IN 81-31 October 8, 1981 Page 2 of 2 This information notice is provided as an early notification of a significant safety matter that is still under review by the NRC staff.
If it is determined that c.ctions are required, such as additional periodic tests with differential pressure or other actions, you will be notified in an appropriate manner.
In the meantime, no response to this notice is required.
If you have questions regardirg this matter, please contact the Director of the appropriate Regional Office.
Attachment:
Recently issued Infor. nation Notices
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Attachment IN 81-31 October 8. 1981 RECENTLY ISSUED IE INFORMATION NOTICES Information Date of Notice No.
Subject Issue Issued to 81-30 Velan Swing Check Valves 9/28/81 All power reactor facilities with an OL or CP 81-29 EquipmentQualification 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
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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 81-2f Compi'ation 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 Ali 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 o* 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 OL = Operating License CP = Construction Permit