ML20041E458
| ML20041E458 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde, Humboldt Bay, 05000000 |
| Issue date: | 03/04/1982 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| Shared Package | |
| ML20041E451 | List: |
| References | |
| NUDOCS 8203100553 | |
| Download: ML20041E458 (1) | |
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y March 4, 1982 Docket Nos. 50-528, 50-529, 50-530 Arizona Public Service Company P. O. Box 21666 Phoenix, Arizona 85036 Attention: Mr. E. E. Van Brunt, Jr.
Vice President, Nuclear Projects Gentlemen:
The enclosed information notice provides early notification of test results that may have safety significance.
It is expected that recipients will review the information notice for possible applicability to their facilities.
If you have any questions regarding this matter, please contact this office.
Sincerely, l0 L
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'N R. H.' Engelken Regional Administrator
Enclosure:
IE Information Notice No. 82-03 cc w/ enclosure:
F. W. Hartley, APS G. C. Andognini, APS 8203100553 820204 PDR ADOCK 05000133 G
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SSINS: 6835
- LAccession;.No.:
8202040111; IN 82-03
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OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, DC 20555 March 4, 1982 IE INFORMATION NOTICE N0. 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 29605 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 enclosedandopenterminalblocksofthetypeusegatTMI-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 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 plane 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 leakage currents when blocks were directly exposed to chemicals and steam.
The NRC recognizes that 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-i 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.
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In view of the above,, licensees'are reminded that.the plant preventive maintenance program in use at their facilites should assure-(1) proper operation of all essential components is achieved throughout the life of the plant; and (2) that periodic inspection of those t'erminations and terminal blocks for cleanliness and installation integrity is performed following~any maintenance activity affecting them.
y TheOfficeofInspectibn'and[Enforcementhasgeneralinspectionprocedureswhich are used by inspectors to monitor compliance with the above Standards, Guides, and recommendations. Terminal.bl.ocks are specifically identified as an example of a component which must' be inspected for. cleanliness during construction of the power plant.
No specific action or respon" 's reouired at thisi ime.
If you have any Do-questions regarding this mar.
, please contact the Regional Administrator of the appropriate NRC Regionai Of fice.
Attachment:
Recently issued IE Information Notices.
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Q Attachment Ifl 82-03 March 4, 1982 RECENTLY ISSUED IE INFORMATI0fl fl0TICuS 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 60-32 Clarification of Certain 02/26/82 All facility, Rev. 1 Reauirements for Exlusive-materials and Use Shipements of Radio-Part 50' licensees active Materials 82-02 Westinghouse flBFD Relay 01/27/82 All power reactor Failures in Reactor facilities holding Protection Systems at an OL or CP Certain fluclear 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 flo. 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