United States Nuclear Regulatory Commission - Protecting People and the Environment

Escalated Enforcement Actions Issued to Reactor Licensees - M

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Maine Yankee - Docket No. 050-00309

NRC Action Number(s) and
Facility Name
Action Type
(Severity) &
Civil Penalty
(if any)
Date
Issued
Description
EA-96-299
Maine Yankee Atomic Power Station
NOVs 10/8/1998 The violation stemmed from an Independent Safety Assessment of the Maine Yankee facility conducted in 1996 and Office of Investigations (OI) investigations from late 1995 through late 1997.

Massachusetts Institute of Technology - Docket No. 050-00020

NRC Action Number(s) and
Facility Name
Action Type
(Severity) &
Civil Penalty
(if any)
Date
Issued
Description
EA-03-155
Massachusetts Institute of Technology Research Reactor
NOV
(SL III)
10/31/2003 On October 31, 2003, a Notice of Violation was issued for a Severity Level III violation involving the failure of a reactor control operator to be present at the controls at all times during the operation of the facility, in that he was sleeping for approximately 30 minutes.

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McGuire 1 & 2 - Docket Nos. 050-00369; 050-00370

NRC Action Number(s) and
Facility Name
Action Type
(Severity) &
Civil Penalty
(if any)
Date
Issued
Description
EA-09-252
McGuire 1 & 2
ORDER 06/02/2010 On June 2, 2010, an immediately effective Confirmatory Order was issued to Duke Energy Carolinas, LLC. (Duke Energy), to confirm commitments made as a result of an Alternative Dispute Resolution mediation session held on March 29, 2010. This enforcement action is based on two violations of NRC requirements at the McGuire Nuclear Station, which included a contract employee introducing and using marijuana inside the Protected Area and a contract employee failing to immediately report the event to Duke Energy management. Duke Energy agreed to take the following actions: (1) develop a summary of lessons learned from the facts and circumstances surrounding the apparent violations and communicate this summary to its fleet wide employees; (2) perform a self-assessment of the adequacy of the programs and processes in place to detect and deter the introduction of illegal drugs and alcohol into the Protected Area of Duke Energy's nuclear stations and implement appropriate enhancements in accordance with Duke Energy's corrective action program; and (3) prior to December 31, 2010, perform an effectiveness review of the corrective actions identified in (1) and (2) above. This is in addition to several other corrective actions already completed by Duke Energy. In consideration of these commitments, and the corrective actions already completed by Duke Energy, the NRC agreed that the non-compliances will be characterized as a violation of 10 CFR Part 26, with a significance of Severity Level IV.
EA-08-220
McGuire 1 & 2
NOV
(White)
10/27/2008 On October 27, 2008, a Notice of Violation was issued for a violation associated with a White Significance Determination Finding involving a violation of 10 CFR 50, Appendix B, Criterion XVI. The violation involved the failure to take adequate corrective action related to the service water strainer backwash system. Specifically, a plant modification implemented to address a macro-fouling concern associated with the service water strainers (1) utilized non-safety-related instrument air to support backwash operations, and (2) did not account for the impact on timely operator response following a safety injection signal or loss of instrument air. As a result, there was a lack of reasonable assurance that the service water system would have been capable of performing its safety-related function during a time of high fouling potential. The finding does not represent a current safety concern because temporary modifications and appropriate procedural changes have been made to address periods of potential macro-fouling.
EA-97-411
McGuire 1 & 2
NOV
(SL III)
09/26/1997 Unauthorized access.
EA-96-080 &
EA-96-100
McGuire
NOV
(SL III)
05/09/1996 Failure to maintain adequate procedures to ensure adequate freeze protection.

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Millstone 1, 2 & 3 - Docket Nos. 050-00245; 050-00336; 050-00423

NRC Action Number(s) and
Facility Name
Action Type
(Severity) &
Civil Penalty
(if any)
Date
Issued
Description
EA-11-047
Millstone 2
NOV
(White)
08/08/2011 On August 8, 2011, the NRC issued a White Significance Determination Process finding and Notice of Violation (NOV) for two violations to Dominion Nuclear Connecticut, Inc. as a result of inspections at the Millstone Power Station Unit 2. The finding was based on multiple human performance errors, and the NOV was based on two violations which involved the licensee's failure to meet its Technical Specifications requirements. Together these failures caused and exacerbated the February 12, 2011, unanticipated eight percent reactor power increase during the main turbine control valve testing.
EA-02-014
Millstone 1
NOVCP
(SL II)

$288,000
06/25/2002 On June 25, 2002, a Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $288,000 was issued for a Severity Level II violation involving the failure to: (1) keep adequate records of special nuclear material (SNM), (2) establish adequate procedures for control and accounting of SNM, and (3) conduct adequate physical inventories of SNM.
EA-00-236
Millstone 2
NOV
(White)
12/06/2000 On December 6, 2000, a Notice of Violation was issued for a violation associated with a White SDP finding involving the degraded condition of the turbine-driven auxiliary feedwater (TDAFW) pump. The violation was based on the licensee's failure to promptly correct a significant condition adverse to quality involving the speed control mechanism for the TDAFW.
EA-96-151
Millstone 2 & 3
NOV
(SL III)
05/25/1999 Violations associated with refueling operations and the spent fuel pool.
EA-98-325
Millstone 1, 2 & 3
NOV
(SL III)
04/06/1999 Discrimination against two supervisors.
EA-97-461
Millstone 1, 2 & 3
NOVCP
(SL II)

$ 88,000
03/09/1999 Violation involving the discrimination against two contractor employees.
EA-98-468
Millstone 2
NOV
(SL III)
02/18/1999 Violation of NRC requirements involving the auxiliary feedwater (AFW) system.
EA-98-179
Millstone 3
NOV
(SL III)
05/06/1998 Failure to maintain the post accident sampling system (PASS) operational within technical specification (TS) requirements.
EA-97-562
Millstone 3
NOVCP
(SL III)

$ 55,000
03/09/1998 Design problem with potential for air injection to charging and safety injection pumps.
EA-96-034
Millstone 2 & 3
NOVCP
(SL II)

$2,100,000
12/10/1997 Three Severity Level II and one Severity Level III problems consisting of multiple individual violations.
EA-97-104
Millstone 1, 2 & 3
NOVCP
(SL III)

$ 55,000
06/11/1997 Security issues.
EA-96-439
Millstone 1, 2 & 3
ORDER 10/24/1996 Order requiring independent oversight of company's implementation of resolution of station employee's safety concerns.
EA-96-059
Millstone 2 & 3
NOVCP
(SL III)

$100,000
06/04/1996 Discrimination against individual.

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Monticello - Docket No. 050-00263

NRC Action Number(s) and
Facility Name
Action Type
(Severity) &
Civil Penalty
(if any)
Date
Issued
Description
EA-13-096
Monticello Nuclear Generating Plant
NOV
(Yellow)
08/28/2013 On August 28, 2013, the NRC issued a Notice of Violation (NOV) to Northern States Power Company, Minnesota for a violation of Technical Specification Section 5.4.1, Procedures, associated with a Yellow Significance Determination Process finding involving the failure of Monticello personnel to maintain a flood plan to protect the site against external flooding events. Specifically, from February 29, 2012, to February 15, 2013, the site failed to maintain flood Procedure A.6, "Acts of Nature," such that it could support the timely implementation of flood protection features within the 12-day timeframe credited in the design basis, as stated in the updated safety analysis report.
EA-09-010
Monticello
NOV
(SL III)
05/28/2009 On May 27, 2009, a Notice of Violation was issued for a Severity Level III problem involving incomplete and inaccurate information in the renewal application for a Senior Reactor Operator's (SRO) license. Specifically, on September 11, 2008, Monticello Nuclear Generating Plant submitted NRC Form 396 for renewal of an SRO license certifying that the individual met the medical requirements. The NRC renewed the SRO license based on NRC Form 396, which only requested a corrective lenses license restriction. Later in November 2008, the NRC received a license restriction change request for the same SRO to add a "Must Take Medication as Prescribed to Maintain Medical Qualifications" license restriction. During the review of the licensing action, the NRC discovered that the SRO both started taking medication and notified the Monticello medical staff in July 2004. The licensee failed to notify the NRC of this change in medical condition. This is a violation of 10 CFR 50.74(c), which requires the licensee to notify the appropriate Regional Administrator within 30 days of a permanent disability or illness of a licensed operator. As a result of the inaccurate information contained in the renewal request, the NRC renewed the SRO license. This is a violation of both 10 CFR 50.9 and 10 CFR 55.23. Title 10 CFR 50.9, states, in part, "Information provided to the Commission…shall be complete and accurate in all material respects" and 10 CFR 55.23, states, in part, that to certify the medical fitness of the applicant, an authorized representative of the facility licensee shall complete and sign NRC Form 396, "Certification of Medical Examination by Facility Licensee."

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Page Last Reviewed/Updated Thursday, December 04, 2014