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Gentlemen:
The enclosed Information Notices; No. 82-04, " Potential Delay of Certain AGASTAT E-7000 Series Time Delay Relays" and No. 82-05 " Increasing Frequency of Drug Related Incidents" are forwarded to you for information.
No written response is required.
if.you desire additional information regarding this matter, please contact this office.
Sincerely, j
(3-Ronald C. Hay s Regional Administrator
Enclosures:
IE Information Notice to. 82-04, with 2 Attachments IE Information Notice t-o. 82-05 with 1 Attachment CONTACT:
S. Ebneter (215) 337-5283 l
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LIST OF HOLDERS OF NUCLEAR POWER REACTOR OPERATING LICENSES AND CONSTRUCTION PERMITS RECEIVING IE INFORMATION NOTICE NOS. 82-04 AND 82-05 Baltimore Gas and Electric Company Docket Nos. 50-317 '
"' ATTN: Mr. A. E. Lundvall, Jr.
50-318Ar Vice President, Supply P. O. Box 1475 Baltimore, Maryland 21203 1
, Boston Edison Company M/C Nuclear Docket No. 50-293 '
" ATTN:
Mr. William D. Harrington Senior Vice President, Nuclear 800 Boylston Street Boston, Massachusetts 02199
. Connecticut Yankee Atomic Power Company Docket No. 50-213y ATTN:
Mr. W. G. Counsil Senior Vice President - Nuclear Engineering and Operations P. O. Box 270 Hartford, Connecticut 06101 Consolidated Ediso, Company of Docket Nos. 50-03-t' New York, Inc.
50-247 t-
-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. 50-3344'
,, ATTN:
Mr. J. J. Carey Vice President Nuclear Division P. O. Box 4 Shippingport, Pennsylvania 15077 GPU Nuclear Corporation Docket No. 50-219'I
-ATTN:
Mr. P. B. Fiedler Vice President and Director Oyster Creek Nuclear Generating Station P. O. Box 388 Forked River, NJ 08731
t 2
Maine Yankee Atomic Power Company Docket No. 50-309 4
ATTN: Mr. John H. Garrity Senior Director Nuclear Engineering and Licensing 83 Edison Drive Augusta, Maine 04336 GPU Nuclear Corporation Docket No. 50-289-V sATTN:
Mr. H. D. Hukill Vice President and 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 DocketNo.50-220-f-
/ 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 E 4
ATTN:
Mr. W. G. Counsil 50-245
Senior Vice President - Nuclear 50-423-F-Engineering and Operations Group P. O. Box 270 Hartford, Connecticut 06101
./ Philadelphia Electric Company DocketNos.50-277-k-ATTN:
Mr. S. L. Daltroff 50-278 Vice President
-4' Electric Production 2301 Market Street Philadelphia, Pennsylvania 19101
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,f ower Authority of the State of New York Docket No. 50-286
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P 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-A' James A. FitzPatrick Nuclear Power Plant
" ATTN: Mr. Corbin A. McNeill, Jr.
Resident Manager P. O. Box 41 Lycoming, New York 13093
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Public Service Electric and Gas Company DocketNos.50-272i' ATTN: Mr. Richard A. Uderitz 50-311 v/
Vice President - Nuclear 1
Mail Code TISA P. O. Box 570 Newark, New Jersey 07101 Rochester Gas and Electric Corporation Docket No. 50-244 -
1
"' ATTN: Mr. John E. Maier Vice President Electric and Steam Production 89 East Avenue Rochester, New York 14649 Vermont Yankee Nuclear Power Corporation Docket No. 50-271-r
,f' ATTN: Mr. Robert L. Smith Licensing Engineer 1671 Worcester Road Framingham, Massachusetts 01701
, Yankee Atomic Electric Company Docket No. 50-29 i' s/ ATTN: Mr. James A. Kay Senior Engineer-Licensing 1671 Worcester Road Framingham, Massachusetts 01701 Duquesne Light Company DocketNo.50-412-b
< ATTN: Mr. E. J. Woolever Vice President Nuclear Construction Robinson Plaza Building No. 2 Suite #210, PA Route 60 Pittsburgh, Pennsylvania 15205 dersey Central Power & Light Company Docket No. 50-363 t' fATTN: Mr. J. T. Carroll Acting Director Oyster Creek Nuclear Generating Station P. O. Box 388 Forked River, New Jersey 08731
4 Long Island Lighting Company Docket No. 50-322 <
ATTN: Mr. M. S. Pollock j
Vice President - Nuclear 175 East Old Country Road Hicksville, New York 11801 Niagara Mohawk Power Corporation Docket No. 50-410 P j 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. 50-3874 pATTN: Mr. Norman W. Curtis 50-388&
Vice President Engineering and Construction - Nuclecr 2 North Ninth Street Allentown, Pennsylvania 18101 Philadelphia Electric Company Docket Nos. 50-352T
- ATTN: Mr. John S. Kemper 50-353-P Vice President Engineering and Research 2301 Market Street Philadelphia, Pennsylvania 19101 F
Public Service Electric & Gas Company Docket Nos. 50-354
/TTN:
Mr. T. J. Martin 50-355 t 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 -4 Chairman and Chief Executive Officer 1000 Elm Street Manchester, New Hampshire 03105
DESIGNAT ORIGIHAL
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SSINS No.:
6835 Accession No.:
8202040107 IN 82-04 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT 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:
On February 2,1982, the Control Product Division, Am.erace Corporation informed 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 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.
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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
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action as necessary.
No specific action or response is required at this time.
If you have any questions regarding this matter, please contact the Administrator of the appropriate NRC Regional Office.
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List of customers to whom applicable relays were shipped. i 5'/Jo y 2.
Recently issued IE Information Notices
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CONTRCL PRODUCTS DIVI $10N AMERACE CORPORATION.1000 H4CKORY STREET IN 82-04 y
GRAFTON. WISCONSIN 53C24 (414; 377-0800 Marcti 1Q. 1982 i
February 2, 1982 Page 1 of 7 I
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
^
veek of 1981 and the 3rd week of 1982.
Extended-performance Quality Assurance tests have deter-mined that pneumatic timing diaphragms mantiactured by one of two diaphragm suppliers exhibit a time and temperature based, bleod-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 sup? ier consti-l tuted about 20'f. of our production and may have 3een 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 qualificution 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 I
assistance in returning the listed items, please contact me.
Yours very truly, CONT.30L PRODUCTS DIVISION l
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M. Q. Martin Quality Assurance Manager MQM/vf l
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CUSTOMER NAMES
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i IN 82-04 GENERAL ELECTRIC COMPANY l'. arch 10.1982 175 Curtner Ave M/C 016 Page 2 of 7 San Jose, CA 95125 i
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
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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 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 l
BROWN-BOVERI
. COULD INC.
4371 County Line Road Chalfont, PA 18914 Attn:
QA Manager l
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- CUSTOMER NAMES Attachm:nt 1
_a IN 82-04 il March 10,1992 GENERAL ELECTRIC COMPANY Page 3 of 7 F.O. Box 2149 1114 Old Concord Road NC 28144 Salisbury, Manager H
Attu:
QA J
- i FLORIDA POWER CORPORATION P.O. Box 14042 j
St. Petersburg, FL 33733 Attn:
QA Manager FLORIDA POWER CORPORATION P.O. Box 219 Crystal Rivar FL 32629 Attn:
Pam Mullins FISCHBACK LORD ELECTRIC COMPANY BOX 771 Hanford #2 Richland, WA 99352 Attn:
Cordon Kittle, Purchasing Agent WESTINGHOUSE ELECTRIC CORPORATION SWITCHGEAR DIVISION A
700 Braddock Avenue E. Pittsburgh, PA 15112 Attn: A. S. Merrill, Switchgear Purchasing 10NN l
COMSIP CUSTOMLINE a
1418 E. Linden Avenue Linden, NJ 07036 l
Attn:
QA Manager COLT INDUSTRIES I
FAIRBANKS MORSE i,
701 Lawton Avenue Beloit,QA Manager WI 53551 l
Attn:
PHILADELPHIA ELECTRIC CO.
P. O. Box 8699 l 'i 2301 Market Street N3-2 lI Philadelphia, PA 19109 ll Attn:
Designer in Charge a
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CUSTOMER NAMES Attachment'l IN 82-04 P. arch 10, 1982 J,
BECHTEL POWER CORPORATION Page 4 of 7 P.O. BOX 60860 1
Terminal Annex
'3 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 CENERAL ELECTRIC COMPANY
'1 P. O. Box 488 Agency Road Burlington, Iowa 52601 Attn:
E. F. McMillan
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TOLEDO EDISON COMPANY 300 Madison Avenue
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Toledo, OH 43652 Attn:
QA Director
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INDIANA & MICHIGAN ELECTRIC CO.
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P.O. BOX 60 Fort Wayne, IN 46801 Attn:
QA Manager RELIANCE ELECTRIC 4900 Lewis Road Stone Mountain, GA 30083 s
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 i
Hartford, CT 06101 Attn:
Norman Thomas (W24)
CUSTOMER NAMES-A2tachment 1 IN 82-04
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.ad 10,1982 14NG ISLAND LIGHTING COMPANY Page 5 of 7 Old Country Road Mineola, W 11530 j
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
,9 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 AMERACE N.V.
P.O. Bcx 13 Industrielaan -
Ille Industriezone 9440 - EREMBODEGEM Belgium Attn:
Mr. Rudy De Schaepmeester SYSTEMS CONTROL CORPORATION P.O. Box 788 i
NO US #2 Iron Mountain, MI 49801 i
Attn:
QA Manager 5
HARLO CORPORATIdN CONTROL PANEL DIVISION 4210 Ferry Street Grandville, MI 49418 Attn:
QA Manager WESTINGHOUSE ELECTRIC CORPORATION CENET.AL CONTROL DIVISION 3900 West 41st Street i
Chicago, IL 60632 Attn:
QA Manager 9
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_ CUSTOMER N.W S M 82 04
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SOUTHERN CALIFORNIA EDISON COMPANY
. March 10,1982
% Bechtel Power Corporation Page 6 of 7 P.O. Box 450 i
CA 92672 San Clemente,l Walters, Field Purchasing Attn:
M5 Gai OMAHA PUBLIC POWER DISTRICT 1623 Harney Street Omaha, NB 68102 j
Attn:
QA Manager i
FLORIDA POWER & LIGHT COMPANY j
% Ebasco Backfit i
P.O. Box 2108' Ft. Pierce, FL.
33450 At.tn:
QA Manager VERMONT YANKEE NUCLEAR POWER P.O. Box 157 e
Vernon, Vermont 05354 Attn:
Greg Gillmore, Purchasing t
VIRGINIA ELECTRIC & POWER CO.
SURRY POWER STATION Route 650 Off HWY 10 Surry, VA 23883 l
Attn:
Purchasing Agent BECHTEL POWER CORPORATION i
P. O. Box 384 Route 11 5 Miles NE of Berwick l
Berwick, PA 18603 Attn:
Mr. I. E. Booher
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TENNESSEE VALLEY AUTHORITY 285 Haney Building l}
Chattanooga, TN. 37401 Attn:
QA Manager
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COMSIP 2
3030 Red Hat Lane j
Whittier, CA 90601 i
Attn:
QA Manager i
ALABAMA POWER COMPANY
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P. O. BOX 2641 Birmingham, AL 35291 Attn:
Mr. J.W. McGowan, QA Manager
IN 82-04 GOULD March 10,1982 2002 Bethel Road Page 7 of 7
,i Finksburg, MD 21048
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Attn:
QA Manager e
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IN 82-04 March 10, 1982 RECENTLY ISSUED IE INFORMATION NOTICES Information Subject Date Issued to Notice No.
Issued 82-03 Environmental Tests of 03/04/82 All power reactor Electrical Terminal facilities holding Blocks an OL or CP 82-01 Auxiliary Feedwater Pump 02/26/82 All power reactor Rev. 1 Lockout Resulting from facilities holding Westinghoue W-2 Switch an OL or CP Circuitry Modification 80-32 Rev. 1 Clarification of Certain 02/12/82 All facility, Requirements for Exclu-materials and sive Use Shipments of Part tJ licensees Radioactive Materials 81-37 Rev. 1 Unnecessary Radiation 02/9/82 Selected Material Exposures to the Licensees Public and Washers During Events Involving Thickness and Level Measuring Devices 82-02 Westinghouse NBFD 1/27/82 All holders of a Relay Failures in power reactor Reactor Protection OL or CP Systems at Certain Nuclear Power Plants 82-01 Auxiliary Feedwater 01/26/82 All holders of a Pump Lockout Resulting power reactor from Westinghouse W-2 CL or CP Switch Circuit Modi-fication 81-39 EPA Crosscheck Program 12/23/81 All holders of a Low-Level Radiciodine 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
SSINS do.:
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 Ccmmission (NRC) and ei*her published or to be published in the Safeguards Summary Event List (NUREG 2525),
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 1930; 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 conscruction, 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, phencyclidine and methaqualone have also been reported.
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
Attachm:nt
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IN 82-05 March 10, 1982 RECENTLY ISSUED IE INFOR4ATION NOTICES I
Information Subject Date Issued to Notice No.
Issued 82-04 Potential Deficiency of 03/10/82 All power reactor Certain AGASTAT E-7000 facilities holding Series Time-Delay Relays and OL or CP 82-03 Environmental Tests of 03/04/82 All power reactor Electrical Terminal facilities holding Blocks an OL or CP 82-01 Auxiliary Feedwater Pump 02/26/82 All power reactor Rev. 1 Lockout Resulting from facilities holding Westinghoue W-2 Switch an OL or CP Circuitry Modification 80-32 Rev. 1 Clarification of Certain 02/12/82 All facility, Requirements for Exclu-materials and sive Use Shipments of Part 50 licensees Radioactive Materials 81-37 Rev. 1 Unnecessary Radiation 02/9/87.
Selected Material Exposures to the Licensees Public and Washers During Events Involving Thickness and Level Measuring Devices 82-02 Westinghouse NBFD 1/27/82 All holders of a Relay Failures in power reactor Recctor Protection OL or CP Systems at Certain Nuclear Power Plants 82-01 Auxiliary Feedwater 01/26/82 All holders of a Pump Lockout Resulting power reactor from Westinghouse W-2 OL or CP Switch Circuit Modi-fication 81-39 EPA Crosscheck Program 12/23/81 All holders of a Low-Level Radiciodine power reactor In Water Intercomparison OL or CP Study