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Gentlemen:
The enclosed Information Notice 82-01, " Auxiliary Feedwater Pump Lockout Resulting from Westinghouse W-2 Switch Circuit Modification," is forwarded to you for information. No written response is required.
If you desire additional information, reg irding this matter, please contact this office.
Sincerely, FFns(>N.
h nald C. Haynes Regional Administrator
Enclosure:
IE Information Notice No. 82-01 with 1 Attachment CONTACT:
S. Ebneter (215) 337-5283 a
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LIST OF HOLDERS OF NUCLEAR POWER REACTOR OPERATING LICENSES AND CONSTRUCTION PERMITS RECEIVING IE INFORMATION NOTICE NO. 82-01 Baltimore Gas and Electric Company Docket Nos. 50-317 ATTN:
Mr. A. E. Lundvall, Jr.
50-318 Vice President, Supply P. O. Box 1475 Baltimore, Maryland 21203 Boston Edison Company M/C Nuclear Docket No. 50-293 ATTN: Mr. A. V. Morisi Nuclear Operations Support Manager 800 Boylston Street Boston, Massachusetts 02199 Connecticut Yankee Atomic Power Company Docket No. 50-213 ATTN: Mr. W. G. Counsil Vice President - Nuclear Engineering and Operations P. O. Box 270 4
Hartford, Connecticut 06101 Consolidated Edison Company of Docket Nos.50-036' New York, Inc.
50-247 /
ATTN: Mr. John D. O'Toole Vice President - Nuclear Engineering'and Quality Assurance 4 Irving Place New York, New York 10003 Duquesne Light Company Docket No. 50-334 ATTN: Mr. J. J. Carey Vice President Nuclear Division P. O. Box 4 Shippingport, Pennsylvania 15077
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Jersey Central Power and Light Company Docket No. 50-219 l
ATTN: Mr. Philip R. Clark Vice President - Nuclear GPU Nuclear 100 Interpace Parkway Parsippany, New Jersey 07054
2 Maine Yankee Atomic Power Company Docket No. 50-309 ATTN: Mr. John H. Garrity Senior Director Nuclear Engineering and Licensing 83 Edison Drive Augusta,-Maine 04336 GPU Nuclear Corporation Docket No. 50-289 ATTN:
Mr. H. D. Hukill Vice President tad Director of TMI-1 P. O. Box 480 Middletown, Pennsylvania 17057 GPU Nuclear Corporation Docket No. 50-320 ATTN: Mr. J. J. Barton Acting Vice President and Director of TMI-2 P. O. Box 480 Middletown, Pennsylvania 17057 Niagara Mohawk Power Corporation Docket No. 50-220 ATTN: Mr. T. E. Lempges Vice President Nuclear Generation 300 Erie Boulevard West Syracuse, New York 13202 Northeast Nuclear Energy Company Docket Nos. 50-336 ATTN: Mr. W. G. Counsil 50-245 Senior Vice President - Nuclear 50-423 Engineering and Operations Group P. O. Box 270 Hartford, Connecticut 06101 Philadelphia Electric Company Docket Nos. 50-277 ATTN:
Mr. S. L. Daltroff 50-278 Vice President Electric Production 2301 Market Street Philadelphia, Pennsylvania 19101 Power Authority of the State of New York Docket No. 50-286 Indian Point 3 Nuclear Power Plant ATTN: Mr. J. C. Brons Resident Manager P. O. Box 215 Buchanan, New York 10511
3 Power Authority of the State of New York Docket No. 50-333 James A. FitzPatrick Nuclear Power Plant ATTN: Mr. Corbin A. McNeill, Jr.
Resident Manager P. O. Box 41 Lycoming, New York 13093 Public Service Electric and Gas Company Docket Nos. 50-272 ATTN: Mr. F. W. Schneider 50-311 Vice President - Production 80 Park Plaza - 15A Newark, New Jersey 07101 Rochester Gas and Electric Corporation Docket No. 50-244 ATTN: Mr. John E. Maier Vice President Electric and Steam Production 89 East Avenuo Rochester, New York 14649 Vermont Yankee Nuclear Power Corporation Docket No. 50-271 ATTN: Mr. Robert L. Smith Licensing Engineer 1671 Worcester Road Framingham, Massachusetts 01701 Yankee Atomic Electric Company Docket No. 50-29 ATTN: Mr. James A. Kay Senior Engineer-Licensing 1671 Worcester Road Framingham, Massachusetts 01701 Duquesne Light Company Docket No. 50-412 ATTN: Mr. E. J. Woolever Vice President 435 Sixth Avenue Pittsburgh, Pennsylvania 15219 Jersey Central Power & Light Company Docket No. 50-363 ATTN: Mr. J. T. Carroll Acting Director Oyster Creek Nuclear Generating Station P. O. Box 388 Forked River, New Jersey 08731 Long Island Lighting Company Docket No. 50-322 ATTN:
Mr. M. S. Pollock Vice President - Nuclear 175 East Old Country Road Hicksville, New York 11801
4 Niagara Mohawk Power Corporation Docket No. 50-410 ATTN: Mr. Gerald K. Rhode Vice President System Project Management c/o Miss Catherine R. Seibert 300 Erie Boulevard, West Syracuse, NY.13202 Pennsylvania Power & Light Company Docket Nos. 50-387 ATTN:
Mr. Norman W. Curtis 50-388 Vice President Engineering and Construction - Nuclear 2 North Ninth Street Allentown, Pennsylvania 18101 Philadelphia Electric Company Docket Nos. 50-352 ATTN: Mr. John S. Kemper 50-353 Vice President Engineering and Research 2301 Market Street Philadelphia, Pennsylvania 19101 Public Service Electric & Gas Company Docket Nos. 50-354 ATTN:
Mr. T. J. Martin 50-355 Vice President Engineering and Construction 80 Park Plaza - 17C Newark, New Jersey 07101 Public Service Company of New Hampshire Docket Nos. 50-443 ATTN: Mr. W. C. Tallman 50-444 Chairman and Chief Executive Officer 1000 Elm Street Manchester, New Hampshire 03105 4
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DESIGNATED ORIGINAL Certified By ML[LC V
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~ZMFctstATs on McTs ci, SSINS No.:
6835 Accession No.:
8107230043 9
IN 82-0 o
4 UNITED STATES
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NUCLEAR REGULATORY COMMISSION 2
p OFFICE OF INSPECTION AND ENF09 CEMENT 2- % 8 y
WASHINGTON, D.C.
20555 January 25, 1982 9
IE INFORMATION NOTICE NO. 82-01:
AUXILIARY FEEDWATER PUMP LOCK 0UT S
FROM WESTINGHOUSE W-2 SWITCH CIRCUI,f'I K g MODIFICATION Description of Circumstances:
On September 14, 1981, Commonwealth Edison's Zion Unit 2 was conducting a normal plant cooldown to begin a refueling outage.
The reactor coolant system was operating at 350 psig and 250 F.
Both residual heat removal (RHR) systems were operating to remove decay heat and control reactor coolant system temperature.
Steam generator water levels dropped below the 10% low level auxiliary feedwater (AFW) pump auto-start setpoint, and the motor-driven AFW pumps activated as designed. The operator placed the control switches in the pull-to-lock-out position to stop the AFW pumps.
Later, to control the rate of plant cooldown, the operator tried to increase the cooldown rate by feeding water to the steam generators. The AFW pumps would not restart on command.
The power supply circuit breaker for one of the pumps was momentarily racked out to the disconnect position and then racked back in for service. As a result of this procedure, the AFW pump restarted.
No further problems were encountered during the plant cooldown operation.
Investigation into the problem revealed that the licensee's modification to the Westinghouse W-2 control switch used with the AFW pumps differed from that recommended in IE Bulletin 80-20 (IEB).
IEB 80-20, entitled " Failures of Westinghouse Type W-2 Spring Return to Neutral Control Switches," recommended using only the existing green status light to provide early detection of an open circuit caused by a neutral position (auto-start) contact failure of the control switch. However, in this application, the licensee's modification included both the red and green status lights. This resulted in a sneak circuit path which prevented AFW pump restart under certain circumstances.
Following an auto-start of the AFW pump and the subsequent securing of that pump by placing the control switch in the pull-to-lock-out position, the licensee found that a live continuous circuit existed between the red light and the anti pump coil.
This sneak current path prevented deenergization of the anti pump coil (circuit reset) that is necessary for pump restart.
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IN 82-01 January 25, 1982 Page 2 of 2 The licensee reports that, following the initial circuit modification, the sneak path was noted to cause the red indicating light to glow only dimly when the control switch was placed in the pull-to-lock-out or trip positions (see Figures 1 through 3 and Table 1).
However, the sneak path was not fully analyzed at that time, and ne detailed function testing of the modified circuit was performed. Note that when the red light is used to 1.dicate " pump on," as in this application, the light should not go on when the control switch has been placed in either the pull-to-lock-out or trip positions.
Circuit modifications may have been made at various plants in response to information in IEB 80-20. These modifications, where different from IEB 80-20 recommendations, may have caused sneak paths with various degrees of impact that may not have been detected by previous engineering analysis or post-installation testing.
This information notice is provided as an early notification of a potentially significant matter.
It is expected that recipients will review the information for applicability to their facilities. No specific action or response is required at~this time.
If you have any questions regarding this matter, please contact the Regional Administrator of the appropriate NRC Regional Office.
Attachments:
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Attachment IN 82-01 January 26, 1982 RECENTLY ISSUED IE INFORMATION NOTICES Information Subject Date Issued to Notice No.
Issued 82-01 EPA Crosscheck Program 12/23/81 All holders of a Low-Level Radioiodine power reactor In Water Intercomparison OL or CP Study 81-38 Potentially Significant 12/17/81 All holders of a Equipment Failures power reactor Resulting from Contam-OL or CP tamination of Air Operated Systems 81-37 Unnecessary Radiation 12/15/81 Selected Material Exposures to the Public Licensees and Workers During Events Involving Thickness and Level Measuring Devices 81-36 Replacement Diaphrams 12/3/81 All holders of a for Robertshaw Valve power reactor (Model No. VC-210)
OL or CP 81-35 Check Valve Failures 12/2/81 All holders of a power reactor OL or CP 81-34 Accidental Actuation 11/16/81 All holders of a of Public Notification power reactor System OL or CP 81-33 Locking Devices 11/9/81 All holders of a Inadequately Installed power reactor on Main Steam Isolation OL or CP Valves 81-32 Transfer and/or 10/23/81 All holders of Disposal of Spent material licenses Generators as designated by IE 81-31 Failure of Safety 10/8/81 All holders of a Injection Valves to power reactor Operate Against OL or CP Differential Pressure 81-30 Velan Swing 9/28/81 All holders of a Check Valves power reactor OL or CP
.