Technical Evaluation of the Proposed Design Modifications and Technical Specification Changes for the R.E. Ginna Nuclear Power Plant

Technical Evaluation of the Proposed Design Modifications and Technical Specification Changes for the R.E. Ginna Nuclear Power Plant

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Published: 1980

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The present design uses undervoltage relays to sense the loss of offsite power. There are no Class 1E loads on the 4160-volt buses. This design consists of two relays per 480-volt Class 1E bus (two Class 1E buses per redundant load group) for the first level of undervoltage protection. An undervoltage condition (loss-of-voltage) will result in isolating the Class 1E buses from all offsite sources, initiating emergency diesel generator start and load shedding on the Class 1E buses, permitting closure of the diesel generator supply breakers, and lastly, the loads will be automatically time-sequenced onto the buses. Actuation begins with loss of voltage to 368 volts (77% of 480 volts). The existing system does not bypass the load-shedding feature once the emergency diesel generators are energizing the Class 1E buses. The licensee has proposed a design change which includes automatic degraded voltage protection. This modification consists of the addition of two time-delayed, undervoltage relays on each 480-volt Class 1E bus, to provide the second level of undervoltage protection.


Technical Evaluation of the Proposed Design Modifications and Technical Specification Changes on Grid Voltage Degradation (Part A) for the Pilgrim Nuclear Power Station

Technical Evaluation of the Proposed Design Modifications and Technical Specification Changes on Grid Voltage Degradation (Part A) for the Pilgrim Nuclear Power Station

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Published: 1980

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This report documents the technical evaluation of the proposed design modifications and Technical Specification changes for protection of Class 1E equipment from grid voltage degradation for the Pilgrim Nuclear Power Station. The review criteria are based on several IEEE standards and the Code of Federal Regulations. The evaluation compares the submittals made by the licensee with the NRC staff positions and the review criteria and presents the reviewer's conclusion on the acceptability of the proposed system.


Technical Evaluation of the Proposed Design Modifications and Technical Specification Changes on Grid Voltage Degradation for the H.B. Robinson Nuclear Generating Plant

Technical Evaluation of the Proposed Design Modifications and Technical Specification Changes on Grid Voltage Degradation for the H.B. Robinson Nuclear Generating Plant

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Published: 1980

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This report documents the technical evaluation of the proposed design modifications and technical specification changes on grid voltage degradation for the H.B. Robinson Nuclear Generating Plant Unit 2. The review criteria are based on IEEE Std. 279-1971, IEEE Std. 308-1974, and General Design Criterion 17 of the Code of Federal Regulations, Title 10, Part 50, Appendix A requirements for determining the acceptability of the proposed system to protect the Class 1E equipment from degradation of grid voltages.