ML20032B954
| ML20032B954 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek, Cooper, Arkansas Nuclear, River Bend, Waterford, South Texas, Comanche Peak, Fort Calhoun, Fort Saint Vrain  |
| Issue date: | 09/25/1981 |
| 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 8111060548 | |
| Download: ML20032B954 (2) | |
Text
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NLCLEAR REGULATORY COMMISSION
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...September 25, 1981
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Gentlemen:
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The enclosed IE Circular is forwarded for your appropriate action.
No l
i written response to this circular is required.
If you have any questions related to this matter, please contact this office.
Sincerely, 77
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..,..-ll.i Karl V. Seyfrit
'l' Director
Enclosures:
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IE Circular No. 81-13 2.
List of Recently Issued i
IE Circulars l 'I l
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.n IE CIRCULAR 81-13 Licensee Facility / Docket Number Arkansas Power and Light Conpany Arkansas Nuclear One, Unit 1 & 2 Little Rock, Arkaidas 50-313; 50-368 Nebraska Public Power District Cooper Nuclear Station Columbus, Nebraska 50-743 Omaha Public Power District Fort Calhoun Station Omaha, Nebraska 50-285 f
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 & Pc ar 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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SSINS No.: 6830 Accession No.:
8107230029 IEC 81-13 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 September 25, 1981 IE CIRCULAR NO. 81-13:
TORQUE SWITCH ELECTRICAL BYPASS CIRCUIT FOR SAFEGUARD SERVICE VALVE MOTORS
Background:
A common wiring discrepancy between the as-designed and as-installed valve motor control circuitry caused, at least in part, a valve malfunction at two operating boiling water reactors.
In each case, an electrical bypass circuit around the valve-open torque switch on a Limitorque valve operator was not installed as designed.
The intent of this bypass feature is to override the valve open or valve-close torque switch circuits to ensure that full motor torque is applied to the valve until it is near full open or full closed.
This is to eliminate the chance of the valve stalling out under emergency conditions before it has completed its travel.
Description of Circumstances:
Brunswick Unit 2 - During a test of the reactor core isolation cooling (RCIC) system at this facility, in March 1978, the injection valve would not open.
The valve and valve motor were checked, cycled and tested; no problems were identified.
In September 1980, following a reactor scram, the same valve failed to fully open.
An inspection of the valve motor control circuitry by the licensee revealed that the electrical bypass circuit wiring around the valve-open torque switch was not installed as designed.
Examination of other RCIC system valves revealed that four of ten similar torque switch bypass circuits had not been installed.
The missing electrical bypasses were installed.
Cooper Station - During a test of the residual heat removal (RHR) system at this facility, in December 1980, one of the RHR loop injection line isolation valves would not open.
The problem was reported to be an incorrect closing torque switch j
setting.
However, it was noted and reported, as unrelated to t >is event, that both Train A and Train B injection valve-open torque switch bypass circuits had not been installed in the valve motor control circuitry as designed.
This discrepancy was corrected.
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IEC 81-13 September 25, 1981 Page 2 of 2 Recommended Action for Holders of Operating Licenses or Construction Permits:
3.
If inspection reveals that required bypass circuits are not installed, installation should be initiated as soon as practicable after the need has been determined.
4.
Establish controls to assure that torque switch bypass circuits are not inadvertently removed and that they are restored if they are removed for maintenance or test.
No written response to this circular is required; however, if discrepancies are found, a report may be required by applicable Technical Specifications or other NRC reporting requirements.
If you need additional information with regard to this subject, please contact the Director of the appropriate NRC Regional Office.
IE Circular No. 81-13 September 25, 1981 RECENTLY ISSUED IE CIRCULARS Circular Subject Date Issued To No.
Issued 81-06 Potential. Deficiency 4/14/81 All power reactor facilities Affecting Certain with an Operating License Foxboro 10 to 50 (OL) or Construction Permit Milliampere Transmitters (CP) 81-04 The Role of Shift Tech-4/30/81 All power reactor facilities nical Advisors and Impor-with an Operating Licenses (OL) tance if Licensee Event or near-term Operating Licenses (0L)
Reports 81-07 Control of Radioacti'.ely 5/14/81 All power reactor Contaminated Material facilities with an Operating License (OL) or Construction Permit (CP) 81-08 Foundation Materials 5/29/81 All power reactor facilities with an Operating License (0L) or Construction Permit (CP) 81-10 Steam Voiding in the 7/2/81 All power reactor facilities Reactor Coolant System with an Operating License (0L) during Decay Heat Removal or Construction Permit (CP)
Cooldown 81-12 41 adequate Periodic 7/22/81 All power reactor facilities Tast Procedure of with an Operating License (0L)
FWR Protection System or Construction Permit (CP)
Enclosure
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