ML20041E559
| ML20041E559 | |
| 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, 05000000, Zimmer, Bailly, Marble Hill |
| Issue date: | 03/04/1982 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| NUDOCS 8203110079 | |
| Download: ML20041E559 (1) | |
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O American 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 g
Braidwood 1, 2 (50-456, 50-457) p Byron 1, 2 (50-454, 50-455)
Dresden 1, 2, 3 (50-10, 50-237, 50-249)
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La Salle 1, 2 (50-373, 50-374)
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- 88EaMIRMmMAR1 'O 198>
Quad-Cities 1, 2 (50-254, 50-265)
Zion 1, 2 (50-295, 50-304) tu Consumers Power Company Big Rock Point (50-155)
Palisades (50-255)
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Midland 1, 2 (50-329, 50-330)
Dairyland Power Corporation LACBWR (50-409)
The Detroit Edison Company Fermi 2 (50-341)
Illinois Power Company Clinton 1, 2 (50-461, 50-462)
Iowa Electric Light and Power Company Duane Arnold (50-331) l Northern Indiana Public Service Company Bailly (50-367) l Northern States Power Company Monticello (50-263) i Prairie Island 1, 2 (50-282, 50-306) l Public Service of Indiana Marble Hill 1, 2 (50-546, 50-547)
Toledo Edison Company Davis-Besse 1 (50-346) om Union Electric Company i
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Callaway 1, 2 (40-483, 50-486) 88 go Wisconsin Electric Power Company o
Point Beach 1, 2 (50-266, 50-301)
&NC Og Wisconsin Public Service Corporation wo Kewaunee (50-305)
W om Illinois Department of Nuclear Safety
$$e Gary N. Wright, Manager, Nuclear Facility Safety rE 31
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4 SSINS: 6835 Accession No.:
8202040111 IN 82-03 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, DC 20555 March 4, 1982 IE INFORMATION NOTICE NO. 82-03: ENVIRONMENTAL TESTS OF ELECTRICAL TERMINAL BLOCKS Discussion:
This information notice pertains to the results of NRC sponsored research con-ducted on electrical terminal blocks (type CF-1518 and CR 20605 General Electric and type FWM States). These may be typical of those utilized in many nuclear power plants. The research program was conducted at Sandia Laboratories in Albuquerque, NM and consisted of approximately 600 individual tests made on enclosed and open terminal blocks of the type used at TMI-2.
The terminal blocks
'were subjected to 100% humidity conditions at 186*F which were the conditions experienced by some terminal blocks during the TMI-2 accident.
(Note: To date, there has been no evidence of terminal block failure at TMI-2 during the TMI-2 accident or after). No tests at other LOCA conditions were conducted. Terminal block performance under the test conditions was measured by monitoring electrical terminal to ground leakage current with terminal to ground voltages of 120, 240 and 480 volts. Some terminal blocks were installed in metal enclosures with a 6 mm pressure relief hole. These metal enclosures were mounted in a horizontal planc during the tests.
Some tests were made by simulating chemical spray and various contaminants that may be found on terminal blocks and could result in electrolytic leakage paths in nuclear power plants. The results of these tests indicated instances of leakaga currents when blocks were directly exposed to chemicals and steam.
The NRC recognizes thct the use of properly designed terminal blocks inside con-tainment is an option of the applicant. NRC requires qualification of all elec-trical connections, cable splices as well as terminal blocks, for accident con-ditions.
It is recognized that cleanliness of terminations and terminal blocks in circuits important to safety is of concern to designers, constructors, and licensees.
The cleanliness aspects are addressed in Appendix B of 10 CFR 50.
These regula-tions require the licensee to establish appropriate procedures based upon manu-facturer's and constructor's recommendations, operating experience, and specific component characteristics to assure that equipment is stored, installed, and maintained in an acceptable state. To this end, IEEE-336, ANS 3.2, and ANSI 45.2.3 Standards and NRC Regulatory Guide 1.39 are being used by designers, constructors, and operators of power plants which address the installation, cleanliness, and on going maintenance of Class 1E electrical components, including terminal blocks.
IN 82-03 l
March 4, 1982 Page 2 of 2 In view of the above, licensees are reminded that the plant preventive maintenance program in use at their facilities should assure (1) proper operation of all essential components is achieved throughout the life of the plant; and (2) that periodic inspection of those terminations and terminal blocks for cleanliness and installation integrity is performed following any maintenance activity affecting them.
The Office of Inspection and Enforcement has general inspection procedures which are used by inspectors to monitor compliance with the above Standards, Guides, and recommendations. Terminal blocks are specifically identified as an exampir, of a component which must be inspected for cleanliness during construction of the power plant.
i 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:
i Recently issued IE Information Notices 4
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Attachment IN 82-03 March 4, 1982 RECENTLY ISSUED IE INFORMATION NOTICES Information Date of Notice No.
Subject Issue Issued to 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 of Exclusive-materials and Use Shipments 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 Die 7 ragms for 12/3/81 All power reactor 5
Robertshaw Valve (Model facilities holding No. VC-210) an OL or CP 81-35 Check Valve Failures 12/2/81 All power reactor facilities holding an OL or CP OL = Operating License CP = Construction Permit