Information Notice No. 84-86: Isolation Between Signals of the Protection System and Non-Safety-Related Equipment
SSINS No.: 6835 IN 84-86 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C. 20655 November 30, 1984 Information Notice No. 84-86: ISOLATION BETWEEN SIGNALS OF THE PROTECTION SYSTEM AND NON-SAFETY-RELATED EQUIPMENT Addressees: All nuclear power reactor facilities holding an operating license (OL) or construction permit (CP). Purpose: This information notice is provided to alert recipients of potentially significant problems pertaining to isolation between signals of the protection system and non-safety-related equipment. It is expected that recipients will review the information for applicability to their facilities and consider actions, if appropriate, to preclude similar problems occurring at their facilities. However, suggestions contained in this information notice do not constitute NRC requirements and, therefore, no specific action or written response is required. Description of Circumstances: On October 1, 1984, Louisiana Power and Light Company (LP&L) informed the NRC of a potentially significant construction deficiency at Waterford Unit 3. The applicant indicated that the isolation between certain plant protection system (PPS) signals and the plant monitoring computer (PMC) did not meet the design criteria. During routine preoperational trouble shooting, it was determined that a failure in the mercury-wetted relays used in the non-safety-related remote multiplexer equipment of the PMC can cause significant changes in the instrument current loops for containment pressure, steam generator level, and steam generator pressure. The applicant's analysis indicates that relay failures would result in a nonconservative value for containment pressure input to the reactor protection system (RPS) trip. The analysis also indicates that similar failures would result in inaccurate (but probably conservative) values for steam generator pressure and level inputs to the RPS trip. A simulated failure mode in the field has supported the results of the analysis. The immediate corrective action taken by the applicant was to remove those PPS signals from the PMC by disconnecting the PPS analog set point signal cables from the PMC. Long-term corrective actions are being evaluated. 8411280370 . IN 84-86 November 30, 1984 Page 2 of 2 Discussion : The NRC staff has conducted a preliminary review of the Waterford Unit 3 deficiency and has met with the applicant and Combustion Engineering, the nuclear steam supply system vendor, to discuss this matter. One conclusion of the review is that there is a fundamental shortcoming in the design of certain PPS circuits of Waterford Unit 3. The buffer devices in the circuits for containment pressure, steam generator pressure, and steam generator level inputs to the PMC isolate only the "high" side of the electrical signal and not the "low" side (signal return). A simplified schematic of the steam generator level circuit, which is similar to the steam generator and containment pressure circuits, is shown in Enclosure 1 of this notice. The buffer in the circuits is used to transmit analog information regarding bistable set points to the PMC. As shown in the schematic, postulated faults downstream of the buffer devices, such as those caused by failed mercury-wetted relays in the multiplexer equipment, would result in electrical interactions within the transmitter current loop. At Waterford Unit 3, the specific problem is limited to those transmitter current loops with multiple resistors used to provide signals to the PPS. The lack of adequate isolation on the "low" side of the circuits would thus result in adverse interactions and may lead to loss of protection from redundant channels monitoring the same plant variable and/or loss of protection from diverse plant variables. No specific action or written response is required by this information notice. If you have any questions about this matter, please contact the Regional Administrator of the appropriate regional office or this office. Edward L. Jordan, Director Division of Emergency Preparedness and Engineering Response Office of Inspection and Enforcement CONTACT: J. T. Beard, NRR (301) 492-7465 R. N. Singh, IE (301) 492-8985 Enclosures: 1. SG Level Signal 2. List of Recently Issued IE Information Notices
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Page Last Reviewed/Updated Tuesday, March 09, 2021