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National Institute of Standards and Technology Center for Neutron Research - Docket No. 050-00184

NRC Action Number(s) and
Facility Name
Action Type
(Severity) &
Civil Penalty
(if any)
Date
Issued
Description
EA-21-148
National Institute of Standards and Technology Center for Neutron Research
Order 08/01/2022 On August 1, 2022, the NRC issued a confirmatory order (CO) to National Institute of Standards and Technology, Center for Neutron Research (licensee) confirming commitments reached as part of an alternative dispute resolution (ADR) mediation settlement agreement between the licensee and the NRC. The ADR mediation and subsequent CO were based on the results of a special inspection in which the NRC identified one apparent violation of Title 10 of the Code of Federal Regulations 50.59, “Changes, tests and experiments,” and six apparent violations of the licensee’s technical specification requirements. The apparent violations involved the exceedance of reactor fuel cladding temperature which resulted in a damaged fuel element. Additionally, the licensee agreed to complete wide-ranging corrective actions and enhancements that are expected to improve reactor safety, as fully described in the CO. In consideration of the corrective actions and commitments outlined in the CO, the NRC agrees not to pursue any further enforcement action associated with the violations. The issuance of this CO is considered as escalated enforcement consistent with the NRC Enforcement Policy.

Nine Mile Point 1 & 2 - Docket Nos. 050-00220; 050-00410

NRC Action Number(s) and
Facility Name
Action Type
(Severity) &
Civil Penalty
(if any)
Date
Issued
Description
EA-14-192
Nine Mile Point Nuclear Station
NOV
(SL III)
04/10/2015 On April 10, 2015, the NRC issued a Notice of Violation to Exelon Generation Company, LLC for a Severity Level III Problem involving two related violations identified as a result of an inspection at its Nine Mile Point Nuclear Station (NMP). The first violation involved the failure on multiple occasions to notify the NRC within 30 days of medical conditions of licensed reactor operators (ROs) and senior reactor operators (SROs) that involved permanent disabilities/illnesses as required by 10 CFR 50.74(c). Specifically, between June 2001 and September 2014, NMP staff was informed that operators were taking prescribed medication for such conditions as hypertension, post-traumatic stress disorder, attention deficit disorder, and asthma. NMP did not report these permanent medical conditions to the NRC when they submitted NRC Form 396 as part of the operators' license application process. Additionally, NMP did not restrict these same licensed ROs and SROs from performing licensed duties when the individuals had disqualifying medical conditions, in accordance with 10 CFR 55.25.  The second violation involved the submittal by NMP of information to the NRC that was not complete and accurate in all material respects as required by 10 CFR 50.9.  Specifically, on multiple occasions between September 2002 and February 2012, NMP submitted applications for operators that certified the medical fitness of the applicants and that did not identify any needed license operator restrictions regarding disqualifying medical conditions or related prescription medication.  Each of the applicants had medical conditions that did not meet the minimum standards of 10 CFR 55.33(a)(1). Subsequently, the NRC based in part on this inaccurate information, issued reactor operator licenses without the required restricting license conditions.
EA-09-262
Nine Mile Point 1
NOV
(White)
11/24/2009 On November 24, 2009, the NRC issued a parallel White finding to Constellation Energy as a result of inspections at Nine Mile Point Nuclear Station Unit 2. This parallel White finding was identified during a supplemental inspection to review the licensee's evaluation of the circumstances that led to the Mitigating Systems Performance Index for the cooling water system crossing the Green to White threshold. The performance indicator crossed the threshold because of service water pump unavailability for maintenance and reliability challenges caused by a November 4, 2008 event where the licensee failed to properly control diving operations while cleaning the intake bays. The inspectors identified significant weaknesses in Constellation's causal analysis for the November 4, 2008 event. Specifically, Constellation failed to identify that the initial work controls put into place for the diving evolution, and subsequent changes made to the work scope, were inadequate and directly contributed to the event. In addition, Constellation failed to identify that governing diving procedures were not followed during the event. Based on these NRC-identified weaknesses, a parallel White inspection finding was opened to allow for the NRC's continued review of Constellation's actions to address the significant weaknesses identified during the supplemental inspection.
EA-07-001
Nine Mile Point 1
NOV
(White)
03/13/2007 On March 13, 2007, a Notice of Violation was issued for a violation associated with a WHITE Significance Determination Process finding involving an activity that compromised the integrity of the annual Licensed Operator Requalification (simulator) exam at Unit 1 for calendar years 2005 and 2006. Specifically, the process used by the licensee to select and validate the simulator exam scenarios resulted in the licensed operators being knowledgeable of a significant portion of the exam prior to its administration, affecting the equitable and consistent administration of the exam. The violation was cited against 10 CFR 55.49, "Integrity of examinations and tests."
EA-03-053
Nine Mile Point 1
NOV
(White)
05/23/2003 On May 23, 2003, a Notice of Violation was issued for a violation associated with a White SDP finding involving degraded piping in the Unit 1 reactor building closed loop cooling (RBCLC) system. The violation cited the licensee's failure to identify the cause, and to take appropriate corrective actions, to preclude repetitive leaks in the Unit 1 RBCLC system.
EA-01-011
Nine Mile Point 1
NOV
(SL III)
05/02/2001 On May 2, 2001, a Notice of Violation was issued for a Severity Level III violation involving the deliberate failure of an NRC-licensed chief shift operator to provide complete and accurate information on health history forms that were required for the Fitness-For-Duty regulations.
EA-99-010
Nine Mile Point 1
NOV
(SL III)
06/29/1999 Failure to comply with technical specification required control room staffing requirements.
EA-97-530
Nine Mile Point 1 & 2
NOVCP
(SL III)

$ 55,000
01/22/1998 Various licensee violations that, collectively represent a breakdown of te licensees radwaste and transportation program.
EA-97-007
Nine Mile Point 1
NOVCP
(SL III)

$ 50,000
11/05/1997 Maintenance Rule base-line inspection violations.
EA-96-474;96-475;96-494; & 96-541
Nine Mile Point 1 & 2
NOVCP
(SL III)

$200,000
04/10/1997 This action is based on three Severity Level III violations/problems involving inadequate design controls and corrective actions, including corrective action deficiencies associated with a reactor pressure vessel overfill event.
EA-96-116
Nine Mile Point 2
NOVCP
(SL II)

$ 80,000
04/24/1996 Discrimination against employee.
EA-96-079
Nine Mile Point 1

NOVCP
(SL III)

$ 50,000

CPORDER
(SL III)

06/18/1996 Design control and 50.59 problems with blowout panels that could result in failure of reactor building structure under certain accident conditions.

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North Anna 1 & 2 - Docket Nos. 050-00338; 050-00339

NRC Action Number(s) and
Facility Name
Action Type
(Severity) &
Civil Penalty
(if any)
Date
Issued
Description
EA-12-033
North Anna 1 & 2
NOV
(White)
05/10/2012 On May 10, 2012, the NRC issued a Notice of Violation to Virginia Electric and Power Company for a violation of Technical Specification 5.4.1.a, “Procedures,” associated with a White Significance Determination Process finding involving Virginia Electric and Power Company’s failure to establish and maintain maintenance procedures appropriate to the circumstances for the safety-related emergency diesel generators (EDGs). Specifically, maintenance procedure 0-MCM-0701-27 did not provide adequate guidance for installation of the jacket water cooling inlet jumper gasket, which resulted in a faulty gasket installation on the Unit 2 “H” (2H) EDG in May 2010. As a result, the 2H EDG failed to perform its safety function when called upon on August 23, 2011.

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Page Last Reviewed/Updated Thursday, August 04, 2022