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Farley 1 & 2 - Docket
Nos. 050-00348; 050-00364
NRC Action Number(s) and
Facility Name |
Action Type
(Severity) &
Civil Penalty
(if any) |
Date
Issued |
Description |
EA-08-192
Farley 1 & 2 |
NOV
(White) |
09/04/2008 |
On September 4, 2008, a Notice of Violation was issued for a violation
associated with a White Significance Determination Finding to Southern
Nuclear Operating Company, as a result of overhaul of its 1B emergency
diesel generator (EDG) at the Joseph M. Farley Nuclear Plant. The
violation cited the licensee for failure to install a new exhaust
header system correctly, as required by vendor documents, causing
the 1B EDG to be declared inoperable. |
EA-07-173
Farley 2 |
NOV
(Yellow) |
10/31/2007 |
On October 31, 2007, a Notice of Violation was issued for a violation
associated with a Yellow Significance Determination finding involving
a violation of 10 CFR 50, Appendix B, Criterion XVI.
Specifically, the licensee failed to promptly identify and correct
a significant condition adverse to quality that resulted in the Unit
2 containment sump suction to residual heat removal pump 2A, an encapsulated
valve, failing to stroke full open during testing on April 29, 2006,
and on January 5, 2007. The licensee did not assure that the causes
of the condition, including rust/corrosion accumulation on valve
components in the valve encapsulation dating back to 2001, were determined
and corrective action taken to preclude repetition. |
EA-07-155
Farley 1 & 2 |
NOV
(White) |
08/17/2007 |
On August 17, 2007, parallel White finding was issued to Southern
Nuclear Operating Company as a result of inspections at the Joseph
M. Farley Nuclear Plant. The parallel White finding was identified
during a supplemental inspection to assess the licensee’s evaluation
associated with unreliability and unavailability reporting in the
Support Cooling Water Systems Performance Indicator (PI) within the
Mitigating Systems Performance Index (MSPI). Failures of the licensee’s
existing safety-related breakers associated with this PI predominantly
contributed to the indicator crossing the threshold to White in the
second quarter of 2006. This PI was subsequently reported Green in
the 3rd quarter of 2006. The supplemental inspection for the White
PI identified significant weaknesses related to the thoroughness
and quality of several root cause evaluations that challenged the
licensee’s ability to implement effective overall corrective
actions. The licensee’s evaluations of the individual failures
that contributed to the White PI did not effectively review for systemic
aspects of circuit breaker failures. In addition, more recent problems
were identified concerning the thoroughness of design reviews for
the installation of new breakers. Based on these NRC-identified weaknesses,
a parallel PI inspection finding (White) was opened to allow the
NRC to continue to monitor activities in this area. |
EA-96-410
Farley 1 & 2 |
NOVCP
(SL III)
$ 50,000 |
12/04/1996 |
The action involved a violation related to the implementation of
10 CFR Part 50 Appendix R and the licensee's Fire Protection Program.
Specifically, three examples were identified in which the licensee
failed to assure that one-hour fire barriers, in this case Kaowool
enclosures, were installed on Unit 1 electrical cables associated
with systems required for safe shutdown. The violation was categorized
as a Severity Level III violation. |
Fermi 2 - Docket No. 050-00341
NRC Action Number(s) and
Facility Name |
Action Type
(Severity) &
Civil Penalty
(if any) |
Date
Issued |
Description |
EA-01-092
Fermi 2 |
NOV
(White) |
09/14/2001 |
On September 14, 2001, a Notice of Violation was issued for a violation
associated with a White SDP finding involving a catastrophic bearing
failure of the emergency diesel generator (EDG). The violation was
cited against the licensee's failure to establish adequate design
control measures for modifying the oil sight glass indicator and associated
piping for the EDG outboard bearing. |
EA-99-263
Fermi 2 |
NOV
(SL III) |
12/15/1999 |
Violation based on the licensee's failure to comply with their Commission-approved
physical security plan that resulted in a loaded handgun being entered
into the protected area of the facility. |
EA-97-201
Fermi 2 |
NOVCP
(SL III)
$ 50,000 |
09/23/1997 |
Multiple corrective action deficiencies. |
EA-96-095
Fermi 2 |
NOVCP
(SL III)
$ 50,000 |
05/21/1996 |
Backleakage through discharge check valve for DGSW pump frozen under
certain weather conditions resulting in the inoperability of the pump
and associated diesel generator. |
FitzPatrick - Docket
No. 050-00333
NRC Action Number(s) and
Facility Name |
Action Type
(Severity) &
Civil Penalty
(if any) |
Date
Issued |
Description |
EA-99-325
FitzPatrick |
NOV
(White) |
03/20/2000 |
On March 20, 2000, a Notice of Violation was issued in conjunction
with a White SDP finding involving a high pressure coolant injection
(HPCI) system overspeed event. The violation cited the licensee's
failure to identify and correct problems with the HPCI system. |
Fort Calhoun - Docket
No. 050-00285
NRC Action Number(s) and
Facility Name |
Action Type
(Severity) &
Civil Penalty
(if any) |
Date
Issued |
Description |
EA-07-194
Fort Calhoun |
NOV
(White) |
12/07/2007 |
On December 7, 2007, a Notice of Violation was issued for violations
associated with a White Significance Determination finding involving
a violation of 10 CFR 50, Appendix B, Criterion XVI, and a violation
of the Fort Calhoun Technical Specifications. Specifically, the licensee
failed to promptly identify and correct a significant condition adverse
to quality involving high resistance across the field flash contacts
of a relay in the Train A emergency diesel generator voltage regulator
circuit and failed to provide a written procedure for maintenance
that could affect the performance of safety-related EDG voltage regulator
relay auxiliary contacts. |
EA-07-047
Fort Calhoun |
NOV
(White) |
05/29/2007 |
On May 29, 2007, a Notice of Violation was issued
for a violation associated with a White Significance Determination
Finding involving the improper installation of the valve disk of
a Containment Spray Header Isolation Valve. The improper installation
resulted in a condition in which the actual position of the valve
was nearly opposite of the indicated position.
This condition resulted in an inoperable train of the containment
spray system for an entire operating cycle and also provided a reactor
coolant system diversion flow path if shutdown cooling was initiated
following certain postulated accident conditions. The violation was
cited against 10 CFR Part 50, Appendix B, Criterion V, “Instructions,
Procedures, and Drawings,” for conducting maintenance activities
without procedures that were appropriate to the circumstances. Specifically,
the maintenance and post-maintenance procedures did not require actions
to verify the correct orientation of the valve. |
EA-05-038
Fort Calhoun |
NOV
(White)
|
04/15/2005 |
On April 15, 2005, a Notice of Violation was issued for a violation
associated with a White SDP finding involving a violation of 10 CFR
Part 50, Appendix B, Criterion XVI, and Fort Calhoun Technical Specification
2.7(1). Specifically, the licensee failed to investigate a drop in
diesel generator output voltage at the conclusion of a surveillance
test. In addition, the licensee failed to properly respond to an
Emergency Facility Computer System alarm that annunciated for low
diesel generator output voltage when the diesel generator output
breaker was opened. |
EA-02-123
Fort Calhoun |
NOV
(White) |
07/30/2002 |
On July 30, 2002, a Notice of Violation was issued for a violation
associated with a white SDP finding involving the failure to prevent
radiation levels from exceeding the Department of Transportation and
NRC limits on the external surface of a radioactive waste shipment
package. |
EA-97-432
Fort Calhoun |
NOVCP
(SL III)
$110,000 |
10/24/1997 |
Inoperable containment spray system due to personnel error during
surveillance. |
EA-97-251
Fort Calhoun |
NOVCP
(SL III)
$ 55,000 |
07/30/1997 |
Appendix R violations. |
EA-96-204
Fort Calhoun |
NOV
(SL III) |
07/31/1996 |
Disabled LTO function of pressurizer PDR's during pressurizer cooldown,
disabling primary system overpressure protection. |
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