ML003739468
| ML003739468 | |
| Person / Time | |
|---|---|
| Issue date: | 04/30/1995 |
| From: | Office of Nuclear Regulatory Research |
| To: | |
| References | |
| RG-1.118, Rev 3 | |
| Download: ML003739468 (4) | |
Text
U.S. NUCLEAR REGULATORY COMMISSION Revision 3 April 1995 K REGULATORY GUI DE OFFICE OF NUCLEAR REGULATORY RESEARCH REGULATORY GUIDE 1.118 (Draft was issued as DG-1028)
PERIODIC TESTING OF ELECTRIC POWER AND PROTECTION SYSTEMS A. INTRODUCTION Systems," requires, in part, that electric power systems Section 50.55a, "Codes and Standards," of important to safety be designed to permit periodic test 10 CFR Part 50, "Domestic Licensing of Production ing, including periodic testing of the performance of and Utilization Facilities," requires in paragraph (h), the components of the system and the system as a "Protection Systems," that protection systems meet whole. The testing should be carried out under condi the requirements set forth in Institute of Electrical and tions as close to design as practical and should involve Electronics Engineers Standard 279,1 "Criteria for the full operational sequence, including operation of Protection Systems for Nuclear Power Generating Sta portions of the protection system, as well as the trans tions." Section 4.9 of IEEE Std. 279-1971 requires, in fer of power among the nuclear power unit, the offsite part, that means be provided for checking the opera power system, and the onsite power system. Criterion tional availability of each protection system input sen XI, "Test Control," of Appendix B, "Quality Assur sor during reactor operation and includes examples of ance Criteria for Nuclear Power Plants and Fuel Re how this can be accomplished. Section 4.10 of IEEE processing Plants," to 10 CFR Part 50 requires, in part, Std. 279-1971 requires, in part, that capability be pro that a test program be established to ensure that all vided for testing and calibrating protection system testing, including operational testing required to dem equipment other than sensors and indicates when such onstrate that systems and components will perform sat isfactorily in service, is identified and performed in ac equipment must be tested during reactor operation.
cordance with written test procedures.
General Design Criterion 21, "Protection System Reliability and Testability," of Appendix A, "General This regulatory guide describes a method accept Design Criteria for Nuclear Power Plants," to 10 CFR able to the NRC staff for complying with the Commis Part 50 requires, in part, that the protection system be sion's regulations with respect to the periodic testing of the electric power and protection systems.
designed to permit its periodic testing during reactor operation, including a capability to test channels inde The Advisory Committee on Reactor Safeguards pendently to determine failures and losses of redun has been consulted concerning this guide and has con dancy that may have occurred. General Design Criteri curred in the regulatory position.
on 18, "Inspection and Testing of Electric Power Any information collection activities mentioned in 1Copies may be purchased from the Institute of Electrical and Electronics Engineers, 345 East 47th Street, New York, NY this regulatory guide are contained as requirements in 10017. 10 CFR Part 50, which provides the regulatory basis USNRC REGULATORY GUIDES The guides are Issued in the following ten broad divisions:
Regulatory Guides are Issued to describe and make available to the public such Information as methods acceptable to the NRC staff for Implement ing specific parts of the Commission's regulations, techniques used by 1. Power Reactors 6. Products the staff in evaluating specific problems or postulated accidents, and 2. Research and Test Reactors 7. Transportation data needed by the NRC staff In Its review of applications for permits and 3. Fuels and Materials Facilities 8. Occupational Health licenses. Regulatory guides are not substitutes for regulations, and com 4. Environmental and Siting 9. Antitrust and Financial Review pliance with them is not required. Methods and solutions different from 5. Materials and Plant Protection 10. General those set out in the guides will be acceptable if they provide a basis for the findings requisite to the issuance or continuance of a permit or license by Copies of issued guides may be purchased from the Government Printing the Commission. Office at the current GPO price. Information on current GPO prices may This guide was Issued after consideration of comments received from the be obtained by contacting the Superintendent of Documents, U.S.
public. Comments and suggestions for Improvements In these guides are Government Printing Office, P.O. Box 37082, Washington, DC encouraged at all times, and guides will be revised, as appropriate, to 20402-9328, telephone (202)512-2249.
accommodate comments and to reflect new Information or experience.
Written comments may be submitted to the Rules Review and Directives Issued guides may also be purchased from the National Technical Infor Branch, DFIPS, ADM, U.S. Nuclear Regulatory Commission, Washing mation Service on a standing order basis. Details on this service may be ton, DC 20555-CO1. obtained by writing NTIS, 5285 Port Royal Road, Springfield, VA 22161.
for this guide. The information collection requirements (1) Temporary jumper wires may be used in 10 CFR Part 50 have been approved by the Office of with safety systems that are provided Management and Budget, Approval No. 3150-0011. with facilities specifically designed for the connection of portable test equip B. DISCUSSION ment. These facilities shall be consid ered part of the safety system and shall IEEE Std. 338-1987,1 "Criteria for the Periodic meet all the requirements of IEEE Std.
Surveillance Testing of Nuclear Power Generating Sta 338-1987.
tion Safety Systems," was prepared by Working Group 3.0 of Subcommittee 3, "Operations, Surveillance and (2) Removal of fuses or opening a breaker is Testing," of the IEEE Nuclear Power Engineering permitted only if such action causes trip Committee and was approved by the IEEE Standards of the associated channel or actuation of Board on September 10, 1987 (reaffirmed in 1993). the logic of the associated load group.
The standard provides design and operational criteria for the performance of periodic testing as part of the (3) Test procedures or administrative con surveillance program of nuclear power plant safety sys trols shall provide for verifying the open tems. The periodic testing consists of functional tests circuit or verifying that temporary con and checks, calibration verification, and time response nections are restored after testing.
measurements, as required, to verify that the safety system performs to meet its defined safety functions. 3. The description for a logic system functional test, The system status, associated system documentation, as noted in Section 6.3.5 of IEEE Std. 338-1987, test intervals, and test procedures during operation are implies that the sensor is included. A logic system also addressed. functional test is to be a test of all logic compo nents (i.e., all relays and contacts, trip units, solid C. REGULATORY POSITION state logic elements, etc.) of a logic circuit, from as close to the sensor as practicable up to but not in Conformance with the requirements of IEEE Std. cluding the actuated device, to verify operability.
338-1987, "Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety Systems," provides a method acceptable to the NRC D. IMPLEMENTATION staff for satisfying the Commission's regulations with respect to periodic testing of electric power and protec The purpose of this section is to provide informa tion systems if the following exceptions are complied tion to applicants and licensees regarding the NRC with: staff's plans for using this guide.
- 1. The definitions of "safety systems," "safety func Except in those cases in which an applicant pro tion," and "safety group" in IEEE Std. poses an acceptable alternative method for complying 603-1991,1 "Criteria for Safety Systems for Nu with specified portions of the Commission's regula clear Power Generating Stations," are used instead tions, the method described in this guide will be used in of the definitions in IEEE Std. 338-1987. the evaluation of submittals in connection with applica tions for construction permits and operating licenses. It
- 2. Both Sections 5(15) and 6.4(5) of IEEE Std. will also be used to evaluate submittals from operating 338-1987 are replaced by the following: reactor licensees that propose system modifications voluntarily initiated by the licensee if there is a clear Procedures for periodic tests shall not require nexus between the proposed modifications and this makeshift test connections except as follows: guidance.
1.118-2
VALUE/IMPACT STATEMENT A draft Value/Impact Statement was published with the draft of this guide when it was published for public comment (Task DG-1028, September 1994).
No changes were necessary, so a separate value/impact statement for the final guide has not been prepared. A copy of the draft value/impact statement is avail able for inspection or copying for a fee in the Commission's Public Document Room at 2120 L Street NW., Washington, DC, under Task DG-1028.
1.118-3
UNITED STATES FIRST CLASS MAIL POSTAGE AND FEES PAID NUCLEAR REGULATORY COMMISSION USNRC WASHINGTON, D.C. 20555-0001 PERMIT NO. G-67 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE, $300