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American Electric Power Service Corporation g
D. C. Cook 1, 2 (50-315, 50-316)
Cincinnati Gas and Electric Company Zimmer (50-358)
The Cleveland Electric Ill.uminating Company
" Perry 1, 2 (50-440, 50-44'1)
-Commonwealth Edison Company -
1, 2 (5,0-4$6, p -)457)
Braidwood Byron 1, 2 (50-454, 50-455 j
Dresden 1, 2, 3 (50-ft$, 50-23), 50-249j La Salle 1, 2 (50-3 73,,50-374) /
Quad-Cities 1, 2,(50-254, 50-265)
Zion 1, 2 (50-295, 50-3'04)
- Consumers Power Company Big Rock Point p0-155)
Pallt,ades (50-255)
Midland 1, 2 (50-3f9, 50-330) s G
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Dairyland Powe,r Corporation p
LACBWR (50-469)
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The Detroit Edison Company P;
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_ 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)
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Prairie Island 1, 2 (50-282, 50-306)
/ Public Service of Indiana
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Marble Hill 1, 2 (50-546, 50-547)
Toledo Edison Company, u
Davis-Besse 1 (50-34~6) v Union Electric Company Callaway 1, 2 (40-48'3, 50-486)
- Wisconsin Electric Powor Company /
Point Beach 1, 2 (50-266, 50-301) s Wisconsin Public, Service Corporation Kewaunee (50-305)
Illinois Department of Nuclear Safety g
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g SSINS No.: 6835 Accession No.:
8202040107 IN 82-04 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMEVT WASHINGTON, D.C.
20555 March 10, 1982 IE INFORMATION NOTICE NO. 82-04: POTENTIAL DEFICIENCY OF CERTAIN AGASTAT E-7000 SERIES TIME-DELAY RELAYS Description of Circumstances:
l On February 2, 1982, the Control Product Division, Amerac9 Corporation informed l
the U.S. Nuclear Regulatory Commission that approximately 20 percent of their AGASTAT E-7000 Series time-delay relays manufactured during the period between July 15, 1981 to January 12, 1982 may not operate properly.
Quality Assurance tests performed to ascertain acceptable performance over ex-tended time periods have determined that the pneumatic timing diaphragm manu-factured by one of two diaphragm suppliers exhibited a bleed-out of a fluid substance as a function of time and temperature. This substance may affect the diaphragm seal on the relays operated at high temperatures for extended periods, resulting in shorter time delays than those set on the relay dial. Although the l
temperature required to initiate significant bleed-out would not be encountered in the majority of these relay applications, it is within the range of nuclear safety qualification tests required by IEEE-323 and IEEE-344.
In a letter dated February 2, 1982, the Control Products Division of Amerace Corporation requested users to return all of the discussed relays for inspection and possible replacements. Copies of the letter and a list of the users are enclosed.The Control Products Division records do not identify individual nuclear power plants because most shipments were made to nuclear steam supply system (NSSS) suppliers, vendors, panel manufacturers, architects and engineers and utilities.
This information notice is provided as an early notification of a potentially significant matter.
It is expected that recipients will review the infor-mation for possible applicability to their facilities and take appropriate action as necessary. 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.
Attachaents:
1.
List of customers to whom applicable relays were shipped.
2.
Recently issued IE Information Notices
control PRODUCTS DIVIStoN Attaciunen t I AMERACE CORPORATION.1000 HICKORY STREET s
G A AFTON WISCONSIN 53024 (414) 377-0800 IN 82-04 February 2, 1982 Page 1 of 7 In accordance with 10CFR21 we are notifying you and the NRC of the following situation regarding some of the Agastat E7000 Series time-delay relays manufactured between the 24th week of 1981 and the 3rd week of 1982.
Extended-performance Quality Assurance tests have deter-mined that pneumatic timing diaphragms manufactured by one of two diaphragm suppliers exhibit a time and temperature based, bleed-out of a fluid substance.
This substance may affect the diaphragm seal on relays operated at high temperatures for ex-tended periods, resulting in shorter time delays than those set on the relay dial.
Relays containing diaphragms from this supplier consti-tuted about 20% of our production and may have been shipped to fill your purchase order (s) as listed on the attached printout.
Although the temperature required to initiate significant bleed-out would not be encountered in the majority of normal product applications it is within the range of nuclear safety related qualification tests.1 We are, therefore, asking you to return all E7000 relays from subject order (s), to my atten-tion, for inspection and possible replacement.
Serial numbers of all E7000 Series relays received by you during the time period concerned are attached.
Please acknowledge receipt of this notice.
If you need assistance in returning the listed items, please contact me.
Yours very truly, CONT 40L PRODUCTS DLVISION p}
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Y-
/W M. Q. Martin Quality Assurance Manager MQM/vf IIEEE 323 and IEEE 344
CUSTOMER NAMES IN 82-04 GENERAL ELECTRIC COMPANY March 10, 1982 175 Curtner Ave M/C 016 Page 2 of 7 San Jose, CA 95125 Attn:
Jerrold B. Morris GENERAL ELECTRIC COMPANY Buckhorn Exit I85 - Rt 1374 P.O. Box 489 Mebane, NC 27302 Attn:
QA Manager L. K. COMSTOCK P. O. Box 1094 Monroe, MI 48161 Attn:
QA Manager SOUTH CAROLINA ELECTRIC & GAS CO.
P.O. Box 764 Columbia, SC 29218 Attn:
Mr. Sam Cash - QA Representative AUTOMATIC SWITCH COMPANY Hanover Road Florham Park, NJ 07932 Attn:
QA Manager EATON CORPORATION Cutler-Hammer Division 1349 Bryn Mawr Avenue Itasca, IL 60143 3
Attn:
QA Manager NORTHERN STATES POWER COMPANY 414 Nicollet Mall Minneapolis, MN 54401 Attn:
QA Manager VIRGINIA ELECTRIC POWER COMPANY P.
O., Box 537 Richmond, VA 23204 Attn:
QA Manager BROWN-BOVERI
, GOULD INC.
4371 County Line Road Chalfont, PA 18914 Attn:
QA Manager
CUSTOMER NAMES ittachment 1 IN 82-04 March 10, 1952 GENERAL ELECTRIC COMPANY Page 3 of 7 P.O. Box 2149 1114 Old Concord Road Salisbury, NC 28144 Attn:
QA Manager FLORIDA POWER CORPORATION P.O. Box 14042 St. Petersburg, FL 33733 Attn:
QA Manager FLORIDA POWER CORPORATION P.O. Box 219 Crystal River, FL 32629 Attn:
Pam Mullins FISCHBACK LORD ELECTRIC COMPANY BOX 771 Hanford #2 Richland, WA 99352 Attn:
Gordon Kittle, Purchasing Agent WESTINGHOUSE ELECTRIC CORPORATION SWITCHGEAR DIVISION 700 Braddock Avenue E. Pittsburgh, PA 15112 Attn: A. S. Merrill, Switchgear Purchasing 10NN COMSIP CUSTOMLINE 1418 E. Linden Avenue Linden, NJ 07036 I
Attn:
QA Manager COLT INDUSTRIES FAIRBANKS MORSE 701 Lawton Avenue Beloit, WI 53551 Attn:
QA Manager PHILADELPHIA ELECTRIC CO.
P. O. Box 8699 2301 Market Street N3-2 Philadelphia, PA 19109 Attn:
Designer in Charge
CUSTOMER NAMES IN 82-04 BECHTEL POWER CORPORATION March 10, 1982 P.O. BOX 60860 Page 4 of 7 Terminal Annex Los Angeles, CA 90060 Attn:
QA Manager FRANK ELECTRIC CORPORATION P.O. Box 69 Willow Springs Lane Road #5 York, PA 17405 Attn:
QA Manager GENERAL ELECTRIC COMPANY P. O. Box 488 Agency Road Burlington, Iowa 52601 Attn:
E. F. McMillan TOLEDO EDISON COMPANY 300 Madison Avenue Toledo, OH 43652 Attn:
QA Director INDIANA & MICHIGAN ELECTRIC CO.
P.O. BOX 60 Fort Wayna, IN 46801 Attn:
QA Manager t
RELIANCE ELECTRIC 4900 Lewis Road Stone Mountain, GA 30083 Attn:
Ms C. Eakin MERCURY CO. OF NORWOOD, INC.
Subsidiary of Fischbach & Moore, Inc.
P.O. Box 1687 10 Burke Drive Brockton, MA 02403 Attn:. Lawrence P. Capron, QA Manager NORTHEAST NUCLEAR ENERGY CO.
CONNECTICUT YANKEE ATOMIC POWER CO.
P.O. Box 270 Hartford, CT 06101 Attn:
Norman Thomas (W24)
CUSTOMER NAMES LONG ISLAND LIGHTING COMPANY Old Country Road
, 1982 Mineola, NY 11530 Page 5 of 7 Attn:
QA Manager BELOIT POWER SYSTEMS DIVISION OF LITTON INDUSTRIES 555 Lawton Avenue Beloit, WI 53511 Attn:
Roger Churchill, Purchasing Agent WISCONSIN PUBLIC SERVICE COMPANY 700 N. Adams Street P.O. Box 700 i
Green Bay, WI 54305 Attn:
Purchasing Department SHOREHAM NUCLEAR POWER STATION P.O. Box 618 North County Road Wading River, NY 11792 Attn:
Mr. B.R. McCaffray, Project Engineer LILCO Project Office A)'ERACE N.V.
P.O. Box 13 Industrielaan -
Ille Industriezone 9440 - EREMBODEGEM Belgium Attn:
Mr. Rudy De Schaepmeester SYSTEMS CONTROL CORPORATION P.O. Box 788 NO US #2 Iron Mountain, MI 49801 Attn:
QA Manager HARLO CORPORATION CONTROL PANEL DIVISION 4210 Ferry Street Grandville, MI 49418 Attn:
QA Manager WESTINGHOUSE ELECTRIC CORPORATION GENERAL CONTROL DIVISION 3900 West 41at Street Chicago, IL 60632 Attn:
QA Manager
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CUSTOMER NAMF.S SOUTHERN CALIFORNIA EDISON COMPANY IN 82-04
% Bschtel Powar Corporation l'. arch 10, 1982 P.O. Box 450 Page 6 of 7 San Clemente, CA 92672 Attn:
MS Gail Walters, Field Purchasing OMAHA PUBLIC POWER DISTRICT 1623 Harney Street Omaha, NB 68102 Attn:
QA Manager FLORIDA POWER & LIGHT COMPANY
%.Ebasco Backfit P.O. Box 2108' Ft. Pierce, FL.
33450 Attn:
QA Manager VERMONT YANKEE NUCLEAR POWER P.O. Box 157 Vernon, Vermont 05354 Attn:
Greg Gillmore, Purchasing VIRGINIA ELECTRIC & POWER CO.
SURRY POWER STATION Route 650 Off HWY 10 Surry,.VA 23883 Attn:
Purchasing Agent BECHTEL POWER CORPORATION P. O. Box 384 Route 11 5 Miles NE of Berwick Berwick, PA 18603 Attn:
Mr. I. E. Booher TENNESSEE VALLEY AUTHORITY 285 Haney Building Chattanooga, TN 37401 Attn:
QA Manager COMSIP 3030 Red Hat Lane Whittier, CA 90601 Attn:
QA Manager ALABAMA POWER COMPANY P. O. BOX 2641 Birmingham, AL 35291 Attn:
Mr. J.W. McGowan, QA Manager
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IN 82-04 March 10, 1982 GOUG Page 7 of 7 2002 Bethel Road Finksburg, MD 21048 Attn:
QA Manager t
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IN 82-04 March 10, 1982 RECENTLY ISSUED IE INFORMATION NOTICES Information Date of Notice No.
Subject Issue Issued to 82-03 Environmental Tests of 03/04/82 All power reactor Electrical Terminal Blocks facilities holding an OL or CP 82-01 Auxiliary Feedwater Pump 02/26/82 All power reactor Rev. 1 Lockout Resulting from facilities holding Westinghouse W-2 Switch an OL or CP Circuitry Modification 80-32 Clarification of Certain 02/26/82 All facility, Rev. 1 Requirements for Exlusive-materials and Use Shipements of Radio-Part 50 licensees active Materials 82-02 Westinghouse NBFD Relay 01/27/82 All power reactor Failures in Reactor facilities holding Protection Systems at an OL or CP-Certain Nuclear Power Plants 82-01 Auxiliary Feedwater Pump 01/22/82 All power reactor Lockout Resulting from facilities holding Westinghouse W-2 Switch an OL or CP Circuit Modification 81-39 EPA Crosscheck Program -
12/23/81 All power reactor Low Level Radioiodine in facilities holding Water Test Program an OL or CP 81-38 Potentially Significant 12/16/81 All power reactor Equipment Failures Resulting facilities holding from Contamination of Air-an OL or CP Operated Systems 81-37 Unnecessary Radiation 12/15/81 All power reactor Exposure to the Public and facilities holding Workers During Events byproduct material Involving Thickness and licenses Level Measuring Devices 81-36 Replacement Diaphragms for 12/3/81 All power reactor Robertshaw Valve (Model facilities holding No. VC-210) an OL or CP OL = Operating License CP = Construction Permit
SSINS No.:
6835 Accession No.:
8202040104 IN 82-05 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 March 10, 1982 IE INFORMATION NOTICE NO. 82-05:
INCREASING FREQUENCY OF DRUG-RELATED INCIDENTS Description of Circumstances:
Based on data reported to the Nuclear Regulatory Commission (NRC) and either published or to be published in the Safeguards Summary Event List (NUREG-0525),
the number of drug-related incidents in which licensee or contractor employees were arrested or terminated has increased dramatically in the past year. During the last 5 years, the increasing trend is as follows:
two in 1977; none in 1978; one in 1979; five in 1980; and twelve in 1981. Thus far in 1982, Regional Pre-liminary Notifications dealing with at least four new drug-related incidents have been issued. The reported incidents implicate a range of licensee or con-tractor personnel, including personnel in construction, operations and security.
The reported incidents are widespread geographically, and involve power reactor sites in each of the five NRC regions.
Reported incidents have involved both onsite use or possession of drugs and personnel reporting to work under the influence of controlled substances.
Marijuana was the most frequently reported controlled substance involved in these events; however, incidents involving amphetamines, cocaine, hashish, j
phencyclidine and methaqualone have also been reported.
t Given the alarming increase in reported drug-related incidents, the wide range of personnel implicated, and the pervasiveness of the reports on a national basis, the Office of Inspection and Enforcement (IE) has established a Drug Abuse Task Force to address the problem on a generic basis.
IE has given top priority to the prompt and effective development of a generic approach to the problem of possible drug (including alcohol) abuse by licensee or contractor personnel. As such, IE solicits relevant licensee experience in this undertaking.
Teams from the Task Force are presently gathering information in a series of visits to selected licensees to discuss the drug problem and possible generic approaches that would best address the problem.
The Task Force is also collaborating with other members of the NRC staff to explore several regulatory approaches to the drug problem. The information obtained from the series of utility visits will be factored into the results of the inter-office efforts.
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.
Attachment:
Recently issued IE Information Notices
(
l4 i
Attachment IN 82-05 March 10, 1982 RECENTLY ISSUED IE INFORMATION NOTICES Information Date of Notice No.
Subject Issue Issued to 82-04 Potential Deficiency of 03/10/82 All power reactor Certain AGASTAT E-7000 facilities holding Series Time-Delay Relays an OL or CP 82-03 Environmental Tests of 03/04/82 All power reactor Electrical Terminal Blocks facilities holding an OL or CP 82-01 Auxiliary Feedwater Pump 02/26/82 All power reactor Rev. 1 Lockout Resulting from facilities holding Westinghouse W-2 Switch an OL or CP Circuitry Modification 80-32 Clarification of Certain 02/26/82 All facility, Rev. 1 Requirements for Exlusive-materials and Use Shipements of Radio-Part 50 licensees active Materials 82-02 Westinghouse NBFD Relay 01/27/82 All power reactor Failures in Reactor facilities holding Protection Systems at an OL or CP Certain Nuclear Power Plants 82-01 Auxiliary Feedwater Pump 01/22/82 All power reactor Lockout Resulting from facilities holding Westinghouse W-2 Switch an OL or CP Circuit Modification 81-39 EPA Crosscheck Program -
12/23/81 All power reactor Low Level Radioiodine in facilities holding Water Test Program an OL or CP 81-38 Potentially Significant 12/16/81 All power reactor Equipment Failures Resulting facilities holding from Contamination of Air-an OL or CP Operated Systems 81-37 Unnecessary Radiation 12/15/81 All power reactor Exposure to the Public and facilities holding Workers During Events byproduct material Involving Thickness and licenses Level Measuring Devices OL = Operating License CP = Construction Permit
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