ML003739468

Rev 3 (Draft Was Issued as DG-1028) Periodic Testing of Electric Power and Protection Systems

ML003739468
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Issue date:	04/30/1995
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RG-1.118, Rev 3
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U.S. NUCLEAR REGULATORY COMMISSION K REGULATORY GUI 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 Section 50.55a, "Codes and Standards,"

of 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities," requires in paragraph (h),

"Protection Systems," that protection systems meet the requirements set forth in Institute of Electrical and Electronics Engineers Standard 279,1 "Criteria for Protection Systems for Nuclear Power Generating Sta tions." Section 4.9 of IEEE Std. 279-1971 requires, in part, that means be provided for checking the opera tional availability of each protection system input sen sor during reactor operation and includes examples of how this can be accomplished. Section 4.10 of IEEE Std. 279-1971 requires, in part, that capability be pro vided for testing and calibrating protection system equipment other than sensors and indicates when such equipment must be tested during reactor operation.

General Design Criterion 21, "Protection System Reliability and Testability," of Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50 requires, in part, that the protection system be designed to permit its periodic testing during reactor operation, including a capability to test channels inde pendently to determine failures and losses of redun dancy that may have occurred. General Design Criteri on 18, "Inspection and Testing of Electric Power 1Copies may be purchased from the Institute of Electrical and Electronics Engineers, 345 East 47th Street, New York, NY 10017.

USNRC REGULATORY GUIDES 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 the staff in evaluating specific problems or postulated accidents, and data needed by the NRC staff In Its review of applications for permits and licenses. Regulatory guides are not substitutes for regulations, and com pliance with them is not required. Methods and solutions different from 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 the Commission.

This guide was Issued after consideration of comments received from the public. Comments and suggestions for Improvements In these guides are encouraged at all times, and guides will be revised, as appropriate, to accommodate comments and to reflect new Information or experience.

Written comments may be submitted to the Rules Review and Directives Branch, DFIPS, ADM, U.S. Nuclear Regulatory Commission, Washing ton, DC 20555-CO1.

Systems," requires, in part, that electric power systems important to safety be designed to permit periodic test ing, including periodic testing of the performance of the components of the system and the system as a whole. The testing should be carried out under condi tions as close to design as practical and should involve the full operational sequence, including operation of portions of the protection system, as well as the trans fer of power among the nuclear power unit, the offsite power system, and the onsite power system. Criterion XI, "Test Control," of Appendix B, "Quality Assur ance Criteria for Nuclear Power Plants and Fuel Re processing Plants," to 10 CFR Part 50 requires, in part, that a test program be established to ensure that all testing, including operational testing required to dem onstrate that systems and components will perform sat isfactorily in service, is identified and performed in ac cordance with written test procedures.

This regulatory guide describes a method accept able to the NRC staff for complying with the Commis sion's regulations with respect to the periodic testing of the electric power and protection systems.

The Advisory Committee on Reactor Safeguards has been consulted concerning this guide and has con curred in the regulatory position.

Any information collection activities mentioned in this regulatory guide are contained as requirements in 10 CFR Part 50, which provides the regulatory basis The guides are Issued in the following ten broad divisions:

1. Power Reactors

2. Research and Test Reactors

3. Fuels and Materials Facilities

4. Environmental and Siting

5. Materials and Plant Protection

6. Products

7. Transportation

8. Occupational Health

9. Antitrust and Financial Review

10. General Copies of issued guides may be purchased from the Government Printing Office at the current GPO price. Information on current GPO prices may be obtained by contacting the Superintendent of Documents, U.S.

Government Printing Office, P.O.

Box 37082, Washington, DC 20402-9328, telephone (202)512-2249.

Issued guides may also be purchased from the National Technical Infor mation Service on a standing order basis. Details on this service may be obtained by writing NTIS, 5285 Port Royal Road, Springfield, VA 22161.

Revision 3 April 1995 DE

for this guide. The information collection requirements in 10 CFR Part 50 have been approved by the Office of Management and Budget, Approval No. 3150-0011.

B. DISCUSSION IEEE Std. 338-1987,1 "Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Sta tion Safety Systems," was prepared by Working Group 3.0 of Subcommittee 3, "Operations, Surveillance and Testing," of the IEEE Nuclear Power Engineering Committee and was approved by the IEEE Standards Board on September 10, 1987 (reaffirmed in 1993).

The standard provides design and operational criteria for the performance of periodic testing as part of the surveillance program of nuclear power plant safety sys tems. The periodic testing consists of functional tests and checks, calibration verification, and time response measurements, as required, to verify that the safety system performs to meet its defined safety functions.

The system status, associated system documentation, test intervals, and test procedures during operation are also addressed.

C. REGULATORY POSITION Conformance with the requirements of IEEE Std. 338-1987, "Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety Systems," provides a method acceptable to the NRC staff for satisfying the Commission's regulations with respect to periodic testing of electric power and protec tion systems if the following exceptions are complied with:

1. The definitions of "safety systems," "safety func tion,"

and "safety group" in IEEE Std. 603-1991,1 "Criteria for Safety Systems for Nu clear Power Generating Stations," are used instead of the definitions in IEEE Std. 338-1987.

2.

Both Sections 5(15) and 6.4(5) of IEEE Std. 338-1987 are replaced by the following:

Procedures for periodic tests shall not require makeshift test connections except as follows:

(1)

Temporary jumper wires may be used with safety systems that are provided with facilities specifically designed for the connection of portable test equip ment. These facilities shall be consid ered part of the safety system and shall meet all the requirements of IEEE Std. 338-1987.

(2)

Removal of fuses or opening a breaker is permitted only if such action causes trip of the associated channel or actuation of the logic of the associated load group.

(3)

Test procedures or administrative con trols shall provide for verifying the open circuit or verifying that temporary con nections are restored after testing.

3.

The description for a logic system functional test, as noted in Section 6.3.5 of IEEE Std. 338-1987, implies that the sensor is included. A logic system functional test is to be a test of all logic compo nents (i.e., all relays and contacts, trip units, solid state logic elements, etc.) of a logic circuit, from as close to the sensor as practicable up to but not in cluding the actuated device, to verify operability.

D. IMPLEMENTATION The purpose of this section is to provide informa tion to applicants and licensees regarding the NRC staff's plans for using this guide.

Except in those cases in which an applicant pro poses an acceptable alternative method for complying with specified portions of the Commission's regula tions, the method described in this guide will be used in the evaluation of submittals in connection with applica tions for construction permits and operating licenses. It will also be used to evaluate submittals from operating reactor licensees that propose system modifications voluntarily initiated by the licensee if there is a clear nexus between the proposed modifications and this 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 NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 FIRST CLASS MAIL POSTAGE AND FEES PAID USNRC PERMIT NO. G-67 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE, $300