United States Nuclear Regulatory Commission - Protecting People and the Environment

Morning Report for April 28, 1999

                       Headquarters Daily Report

                         APRIL 28, 1999

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                    REPORT             NEGATIVE            NO INPUT
                    ATTACHED           INPUT RECEIVED      RECEIVED

HEADQUARTERS        X
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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

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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.

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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.

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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.

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