Morning Report for April 28, 1999
Headquarters Daily Report APRIL 28, 1999 *************************************************************************** REPORT NEGATIVE NO INPUT ATTACHED INPUT RECEIVED RECEIVED HEADQUARTERS X REGION I X REGION II X REGION III X REGION IV X PRIORITY ATTENTION REQUIRED MORNING REPORT - HEADQUARTERS APRIL 28, 1999 MR Number: H-99-0038 NRR DAILY REPORT ITEM GENERIC COMMUNICATIONS Subject: INFORMATION NOTICE 99-13 IS BEING ISSUED APRIL 29, 1999 NRC INFORMATION NOTICE 99-13: INSIGHTS FROM NRC INSPECTIONS OF LOW-AND MEDIUM-VOLTAGE CIRCUIT BREAKER MAINTENANCE PROGRAMS, dated April 29, 1999 The NRC is issuing this information notice to summarize observations made and insights gained during inspections of licensee circuit breaker maintenance programs. Technical contacts: Stephen Alexander, NRR Amar Pal, NRR 301- 415-2995 301- 415-2760 E-mail: sda@nrc.gov E-mail: anp@nrc.gov David Skeen, NRR S.K. Mitra, NRR 301- 415-1174 301- 415-2783 E-mail: dls@nrc.gov E-mail: skm1@nrc.gov _ HEADQUARTERS MORNING REPORT PAGE 2 APRIL 28, 1999 Licensee/Facility: Notification: Part 21 Database MR Number: H-99-0039 Westinghouse Date: 04/28/99 Subject: Part 21 - Defects in modeling for main steam line break analysis Discussion: VENDOR: Westinghouse PT21 FILE NO: 99-21-0 DATE OF DOCUMENT: 02/22/99 ACCESSION NUMBER: SOURCE DOCUMENT: EN 35392 REVIEWER: PECB, T. Greene NEW ISSUE. On February 22, 1999, the Ginna licensee reported (Event Notification 35392) being notified by its nuclear steam supply system vendor, Westinghouse Electric Company, of two modeling errors in the analysis for a main steam line break (MSLB) that affected calculated peak containment pressure nonconservatively. With an assumed single failure of a feedwater control valve, the errors are (1) not taking into account the full amount of energy released to containment by the flashing of high-temperature feedwater downstream of the motor-operated isolation valves after feedwater flow is isolated and (2) mistakenly using 15 seconds for the time required to isolate feedwater flow rather than the intended 85 seconds (5 seconds for signal delay and 80 seconds for valve stroke time). On March 24, 1999, the licensee confirmed that this item is reportable under 10 CFR Part 21 (Licensee Event Report 50-244/99-01). The licensee performed analyses and set administrative limits to support continued operation of the plant until the planned 1999 refueling outage beginning March 1, 1999. The licensee is continuing to work with Westinghouse to assess safety consequences and implications of this event. _ HEADQUARTERS MORNING REPORT PAGE 3 APRIL 28, 1999 Licensee/Facility: Notification: Part 21 Database MR Number: H-99-0040 Coltec Date: 04/28/99 Subject: Part 21 - Missing lube oil drain port in Model 730 turbocharger Discussion: VENDOR: Coltec PT21 FILE NO: 99-22-0 DATE OF DOCUMENT: 04/09/99 ACCESSION NUMBER: SOURCE DOCUMENT: EN 35567 REVIEWER: PECB, D. Skeen NEW ISSUE. On April 9, 1999, the Ginna licensee reported a manufacturing deficiency in a replacement turbocharger (Model 730) supplied by Coltec Industries. A drain port in the intermediate casing on the turbine end of the turbocharger was missing. This drain port conducts lubricating oil from the shaft and bearings back to the engine sump. Without this drain port, lubricating oil was being directed into the engine cylinders through the exhaust manifold piping, which could have resulted in serious engine damage. The licensee discovered the problem when oil was observed dripping from the cylinders after the turbocharger was installed and the pre-lube system was placed in operation. The staff discussed this issue with a quality assurance representative from Coltec Industries' Fairbanks Morse/ALCO Engine Division. The standard turbocharger for ALCO Model 251 emergency diesel generators used in the nuclear power industry is the Model 720. The Model 730 turbocharger (slightly larger than the 720) was developed expressly for Ginna by ALCO. The turbocharger is manufactured for Coltec by a subsupplier. Coltec performed an investigation of the subsupplier but was unable to determine a root cause for the failure to mill out the drain port in the intermediate casing. The Model 730 turbocharger is not a normal production component and is only manufactured on an as-needed basis, which could be a contributing factor since it is manufactured so infrequently. This issue does not appear to be a generic concern, since Coltec supplies the Model 730 turbocharger only to Ginna in the nuclear industry, and no similar problems with the Model 720 or other turbochargers have been reported. _ HEADQUARTERS MORNING REPORT PAGE 4 APRIL 28, 1999 Licensee/Facility: Notification: Part 21 Database MR Number: H-99-0041 Cooper Energy Date: 04/28/99 Subject: Part 21 - Enterprise diesel generator connecting rod assemblies with prestressed fasteners suspected to be of incorrect length Discussion: VENDOR: Cooper Energy PT21 FILE NO: 99-23-0 DATE OF DOCUMENT: 04/12/99 ACCESSION NUMBER: SOURCE DOCUMENT: EN 35580 REVIEWER: PECB, T. Koshy NEW ISSUE. On April 12, 1999, the vendor Cooper Energy Services reported a potential defect in connecting rod assemblies, which are components of DSRV-16-4 Enterprise diesel generator systems. Assemblies built after September 1986 either use or have been converted to use prestressed fasteners to attach the rod box to the master rod. These assemblies, part number P/N 1A-7802, include prestressed fasteners of suspected incorrect length. Affected nuclear power plants are Vogtle (engine serial number S/N 76021-4) and Perry (engine serial number S/N 75051-2). In addition, utilities with DSRV-4 engines who have purchased replacement connecting rod assemblies with part numbers P/N 1A-6280 or P/N 1A-6281 after September 1986 and have converted or plan to convert the bolts to prestressed fasteners could also be affected. These nuclear power plants include: Plant Engine Serial Number Grand Gulf S/N 74033-6 Harris S/N 74046-9 Catawba S/N 75017-20 Perry S/N 75051-4 Comanche Peak S/N 76001-4 Vogtle S/N 76021-4 The manufacturer suggests the inspection of potentially affected assemblies in the next refueling outage. _
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021