Part 21 Report - 1997-872
ACCESSION #: 9711040085
LICENSEE EVENT REPORT (LER)
FACILITY NAME: River Bend Station PAGE: 1 OF 6
DOCKET NUMBER: 05000458
TITLE: Cracked Emergency Diesel Generator Valve Adjusting Screw
Assembly Swivel Pads
EVENT DATE: 09/26/97 LER #: 97-007-00 REPORT DATE: 10/23/97
OTHER FACILITIES INVOLVED: DOCKET NO: 05000
OPERATING MODE: 5 POWER LEVEL: 0%
THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR
SECTION:
50.73(a)(2)(v), 50.73(a)(2)(vii), OTHER: 10 CFR 21
LICENSEE CONTACT FOR THIS LER:
NAME: D.N. Lorfing, Supervisor - Licensing TELEPHONE: (504) 381-4157
COMPONENT FAILURE DESCRIPTION:
CAUSE: B SYSTEM: EK COMPONENT: CPLG MANUFACTURER: C634
REPORTABLE NPRDS: N
SUPPLEMENTAL REPORT EXPECTED: NO
ABSTRACT:
On September 26, 1997, at 1715 hours, with the plant in mode 5
(refueling) and the reactor at 0% power, the Division I (Div II) and
Division II (Div II) emergency diesel generators (EDGs) were declared
inoperable. Multiple valve adjusting screw assembly swivel pads
(VASASPs) in the Div I EDG were found to be cracked, and was attributed
to a manufacturing defect. Although the EDG would have been able to
start and run following a loss of offsite power, an engineering
evaluation conservatively postulated that in the event of a gross failure
of the VASASP, the EDG may not have be able to run for the 30 days
assumed in the accident analysis. Since the VASASPs in both the Div I
and the Div II EDGs were manufactured from the same material lot, the
condition was suspected to exist in both EDGs. Subsequent inspection of
the Div II EDG on September 28, 1997, confirmed that four VASASPs were
cracked. Based on the results of this inspection, the condition was
reported at 1000 hours pursuant to 10 CFR 50.72(b)(2)(iii) as a condition
which alone could have prevented the fulfillment of a safety function.
This report is submitted pursuant to 10 CFR 50.73(a)(2)(v). Because the
same manufacturing defect caused the VASASP cracks in both EDGs, this
event is also reportable pursuant to 10 CFR 50.73(a)(2)(vii). Core
alterations were suspended while both EDGs were inoperable, and the
VASASPs in the Div I and Div II EDGs were replaced with improved
components. VASASPs removed from the two EDGs will be returned to the
vendor for analysis. A review of the vendor's failure analysis report
will be performed to determine the need for additional corrective
actions. Because the EDGs did not experience a gross failure of the
VASASPs, the safety significance of this event is considered low.
END OF ABSTRACT
TEXT PAGE 2 OF 6
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Reported Condition
On September 26, 1997, at 1715 hours, with the plant in mode 5
(refueling) and the reactor at 0% power, the Division I (Div I) and
Division II (Div II) emergency diesel generators (EDGs) (EK) were
declared inoperable. Multiple valve adjusting screw assembly swivel pads
(VASASPs) (CPLG) in the Div I EDG were found to be cracked, and was
attributed to a manufacturing defect.
The valve adjusting screw assembly (VASA) is a threaded screw which
allows a fine adjustment of the valve clearance or lash. The VASA
transmits the rocker arm motion to the valve stem, thereby opening and
closing the intake and exhaust valves at the specified timing. At the
base of the VASA, where it meets the valve stem, is the VASASP. The
VASASP is a mushroom-shaped socket which connects to the VASA. The
VASASP rotates and tilts on the ball end of the VASA in order to keep
itself properly aligned with the valve stem through the cyclic motion of
the rocker arm (see Figure I for a photograph of a VASA).
Although the EDG would have been able to start and run following a loss
of offsite power, an engineering evaluation conservatively postulated
that in the event of a gross failure of the VASASP, the EDG may not be
able to run for the 30 days required by the accident analysis. Since the
VASASPs in both the Div I and Div II EDGs were manufactured from the same
material lot, the condition was suspected to exist in both EDGs.
Subsequent inspection of the Div II EDG on September 28, 1997, confirmed
that four VASASPs were cracked. Based on the results of this inspection,
the condition was reported at 1000 hours pursuant to 10 CFR
50.72(b)(2)(iii) as a condition which alone could have prevented the
fulfillment of a safety function of a system required to mitigate the
consequences of an accident. This report is submitted pursuant to 10 CFR
50.73(a)(2)(v). Because the same manufacturing defect caused the VASASP
cracks in both EDGs, this event is also reportable pursuant to 10 CFR
50.73(a)(2)(vii) as an event where a single cause or condition caused two
independent trains or channels to become inoperable in a single system
designed to mitigate the consequences of an accident.
Investigation
On September 15, 1997, at 2359 hours, during an inspection of the Div I
EDG, the VASASP for the cylinder number 5 exhaust valve was found to be
cracked. Other Div I EDG VASASPs were inspected and no additional cracks
were found. A metallurgical analysis determined that the failure of the
VASASP was due to a high strength, low toughness material being subjected
to a low magnitude impact in the presence of a notch. The cracked VASASP
was replaced. Following a post-maintenance run of the Div I EDG on
September 26, 1997, at 0830 hours, two additional cracked VASASPs were
identified. Both the Div I and the Div II EDG were declared inoperable
at 1712 hours, on September 26, 1997. The VASASPs on the Div I EDG were
replaced with improved assemblies. The Div I EDG was tested and returned
to operable status at 1544 hours on September 27, 1997.
TEXT PAGE 3 OF 6
The Div II EDG was inspected on September 28, 1997, at 0959 hours and
four additional valves were found to have cracked screw assembly swivel
pads. VASASPs on the Div II EDG were replaced on October 1, 1997, with
improved assemblies, and the EDG was returned to operable status.
The cracked VASASPs were material lot number VV64 with 1F26 screws. The
vendor (Cooper-Enterprise) stated that lot VV64 swivel pads had waivers
for discrepancies identified during the manufacturing process. The
waivers had been dispositioned within the vendor's 10 CFR 50, Appendix B
program prior to the material's shipment to River Bend Station (RBS).
The vendor indicated that, among other discrepancies, the material was
harder than specifications allowed. RBS examined questionable VASASPs
removed from service, using liquid dye penetrant. A total of ten cracked
VASASPs were found, each with a 1F26 screw and a lot VV64 swivel pad.
Forty-five of the 64 VASASPs removed from service were of this
configuration; none of the remaining VASASPs (with different
configurations) experienced any cracks. The cracks were confined to the
upper or swaged area of the VASASP. No VASASP cracked to the point of
being unrestrained by the adjusting screw.
Root Cause
The root cause of this event is a manufacturing defect. Specifically,
the swivel pad portion of the VASASP (which forms the socket portion of a
ball-and-socket joint) was over-swaged (rolled) around the VASASP
adjusting screw. The over-swaged condition made the joints too tight and
restricted motion of the assemblies, resulting in small impacts as the
valves were opened.
Two additional contributing causes were identified, as follows:
o The VASASPs were manufactured from an inappropriate material. The
VASASPs should be manufactured from AISI 8620. The VASASPs removed
from service were manufactured from a material equivalent to
SAE/AISI 8660, which is harder and more brittle than 8620.
o The ball portion of the VASASP adjusting screw (which forms the ball
portion of a ball-and-socket joint) was machined incorrectly. The
ball should be machined smooth. The adjusting screws removed from
service exhibited a machined cutback around the horizontal
centerline of the ball. This cutback formed an edge that was
cutting a groove into the upper area inside of the swivel pad.
These three factors, combined, are judged to have caused the VASASPs to
crack. Because the VASASP could not travel freely through its required
range of motion, the adjusting screw would strike the swivel pad at the
edge of the swaged area. This repetitive impingement on the swivel pad
caused cracks to initiate at the groove cut by the improperly machined
screw (second contributing cause, above). The cracks were brittle
fractures due to the high strength, low toughness material used in the
manufacturing process.
Previous Occurrences
No other cracking of the VASASPs has been experienced at RBS.
TEXT PAGE 4 OF 6
The VASASPs have been previously replaced because of abnormal wear of the
valve stems. The VASASPs in both the Div I and Div II EDGs were replaced
in April 1994. The abnormal wear was attributed to the design of the
VASA. The vendor redesigned the VASASP by enlarging the base of the
swivel pad, and the new models were installed.
Corrective Actions
Core alterations were suspended while the two EDGs were inoperable.
The VASASPs in the Div I and Div II EDGs were replaced with new
components. The vendor informed RBS that the replacement VASASPs were
manufactured from SAE/AISI 8620 material. The vendor also stated that
the adjusting screws were visually inspected by the vendor to ensure
there were no sharp edges on the ball, and that the swivel pads were
manufactured with a special tool that precludes over-swaging. The
replacement VASASPs were functionally inspected by extending the ball
joint and rotating the joint by hand. The VASASPs exhibited proper range
of motion which was smooth and even, indicating no sharp edges or over-
swaging.
The VASASPs removed from the two EDGs will be returned to the vendor for
analysis, by October 31, 1997. RBS management will review the vendor's
failure analysis report to determine if additional corrective actions are
needed. Entergy Operations will monitor the vendor initiatives to ensure
effective corrective actions for the nonconformances and generic
implications identified through the investigation of this event. These
will both be completed by April 30, 1998.
Safety Significance and Implications
The as-found condition of the VASASPs did not affect the past operation
of the EDGs. In all of the observed cracks, the swivel pads remained
fixed to the adjusting screws. The cracks in the swivel pads were not
360 degree circumferential cracks. It is reasonable to expect that the
EDGs could have started at least one additional time without causing the
adjusting screws and the swivel pads to become disengaged. Although
brittle fracture of the upper region of the VASASPs could cause small
pieces of metal to break off, the small pieces would be carried through
the cam region and into the oil sump of the EDG. A protective screen in
the oil sump and an oil filter and oil strainer in the pump discharge
line protect the vital engine components from foreign material. Thus,
the EDGs would have been able to mitigate the immediate consequences of
an accident. The EDGs did not experience a gross failure of the VASASPs,
and so the safety significance of this event is considered low.
While RBS did not experience a complete failure of the VASASPs, it is
postulated that under highly unlikely conditions, the swivel pads could
fail. The swivel pads could become disengaged from the adjusting screws
as a result of the brittle fracture of the upper region. If the valves
were to open out of sequence, the existing clearances and rocker arm
motion would not prevent the unrestrained VASASPs from being displaced
off of the top of the valve stem. This could possibly impact the 30-day
post-accident operation of the EDG.
TEXT PAGE 5 OF 6
Additional Information
The Div I and the Div II EDGs are both Transamerica Delaval, Incorporated
(TDI) model Delaval-DSR 48.
Note: Energy Industry Identification codes are identified in the text as
(*XX*)
TEXT PAGE 6 OF 6
Figure 1. "Photograph of a Valve Adjusting Screw Assembly"
ATTACHMENT TO 9711040085 PAGE 1 OF 2
Entergy Operations, Inc.
River Bend Station
5485 U. S. Highway 61
P.O. Box 220
Entergy St. Francisville, LA 70775
Tel 504 336 6225
Fax 504 635 5068
Rick J. King
Director
Nuclear Safety & Regulatory Affairs
October 23, 1997
U. S. Nuclear Regulatory Commission
Document Control Desk, OP1-17
Washington, DC 20555
Subject: River Bend Station - Unit 1
Docket No. 50-458
License No. NPF-47
Licensee Event Report 50-458/97-007-00
File Nos. G9.5, G9.25.1.3
RBG-44275
RBF1-97-0400
Ladies and Gentlemen:
In accordance with 10CFR50.73, enclosed is the subject report.
Sincerely,
RJK/BFT/bft
enclosure
ATTACHMENT TO 9711040085 PAGE 2 OF 2
Licensee Event Report 50-458/97-007-00
October 23, 1997
RBG-44275
RBF1-97-0400
Page 2 of 2
cc: U. S. Nuclear Regulatory Commission
Region
IV 611 Ryan Plaza Drive, Suite 400
Arlington, TX 76011
NRC Sr. Resident Inspector
P. O. Box 1050
St. Francisville, LA 70775
INPO Records Center
700 Galleria Parkway
Atlanta, GA 30339-3064
Mr. G. Dishong
Public Utility Commission of Texas
1701 N. Congress Ave.
Austin, TX 78711-3326
Louisiana Department of Environmental Quality
Radiation Protection Division
P. O. Box 82135
Baton Rouge, LA 70884-2135
ATTN.: Administrator
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