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Escalated Enforcement Actions Issued to Reactor Licensees - B

Beaver Valley 1 & 2 - Docket Nos. 050-00334; 050-00412

NRC Action Number(s) and
Facility Name
Action Type
(Severity) &
Civil Penalty
(if any)
Date
Issued
Description
EA-06-152
Beaver Valley 1 & 2
NOV and
(ORDER)
12/19/2006 On December 19, 2006, a Notice of Violation (NOV) and a Confirmatory Order (Effective Immediately) were issued as part of a settlement agreement that was prepared as a result of an Alternative Dispute Resolution (ADR) session that was held to resolve the results of an investigation of deliberate wrongdoing by a former contract mechanical engineer. The NOV includes two violations (categorized as one Severity Level III problem) which are cited against 10 CFR Part 50, Appendix B, Criterion III, "Design Control," and the licensee’s procedures for engineering changes and design interface reviews and evaluations. Based on the ADR session, both parties agreed, among other things, that: (1) the former contract engineer deliberately failed to adhere to procedural requirements; (2) the licensee took multiple corrective actions to prevent recurrence; (3) there was a need for additional corrective actions at the licensee’s facilities as well as an opportunity for other licensees in the industry to learn from this incident; (4) in light of the corrective actions the licensee has taken and has committed to take, the NRC would issue a Severity Level III violation with no civil penalty; and (5) the NRC would issue a Confirmatory Order confirming the agreement.
EA-06-215
Beaver Valley 1 & 2
NOV
(White)
12/12/2006 On December 12, 2006, a Notice of Violation was issued for a violation associated with a WHITE Significance Determination Process finding involving an inadequate emergency preparedness implementing procedure that would be used during certain emergency conditions to assess the offsite radiological consequences for the purpose of developing protective action recommendations (PAR). The violation was cited against 10 CFR 50.47(b)(9) because the licensee’s emergency plan failed to have an adequate method for assessing actual and potential offsite consequences of a radiological emergency.
EA-03-054
Beaver Valley 1 & 2
NOV
(White)
07/10/2003 On July 10, 2003, a Notice of Violation was issued for a violation involving a white SDP finding involving the inability of the licensee's emergency response organization to meet Emergency Preparedness Plan (EPP) staffing requirements during emergencies. The violation cited the failure (identified during an unannounced drill) of the on-site Emergency Response Organization to augment radiation protection technicians within the required times to cover four radiation protection functions.
EA-02-041
Beaver Valley 1 & 2
NOV
(White)
06/24/2002 On June 24, 2002, a Notice of Violation was issued for a violation associated with a White SDP finding involving the public alert and notification system. The violation cited the failure to establish a means to provide early notification to the public because a majority of personal home alerting devices were degraded or removed.
EA-00-045
EA-00-053
Beaver Valley 1 & 2
NOV
(SL III)
05/03/2000 On May 3, 2000, a Notice of Violation was issued for two Severity Level III violations and one Severity Level III problem. This first Severity Level III violation was based on the failure to correct a condition adverse to quality involving the service water and river water pump vacuum break check valves that rendered a SW pump inoperable. The second Severity Level III violation involved the failure to perform an adequate design review of a temporary modification to the filtered water system (a source of seal water to the RW pumps). The Severity Level III problem was based on design deficiencies associated with the seal water supply to the RW pumps, and the failure of the RW pump testing program to identify one of those deficiencies.
EA-99-212
Beaver Valley 1 & 2
NOV
(SL III)
10/21/1999 Multiple violations involving failure to implement corrective actions to prevent biofouling of the service water system, and failure to provide adequate acceptance criteria in the procedure for chemical treatment of the service water sytem.
EA-97-517
Beaver Valley 1 & 2
NOV
(SL III)
01/06/1998 Failure to prevent repetitive gas binding of high head safety injection pump.
EA-97-255
Beaver Valley 1 & 2
NOV
(SL III)
07/03/1997 Misread technical specification surveillances.
EA-97-076
Beaver Valley 1 & 2
NOV
(SL III)
03/24/1997 This action was based on numerous failures to follow procedures and implement appropriate work controls involving configuration control, failure to take appropriate corrective actions for past configuration control problems, and for operators inadvertently deenergizing the waste decay tank oxygen analyzers.
EA-96-462;
Beaver Valley 1 & 2

 

NOVCP
(SL III)

$100,000
03/10/1997 The action was based on (1) a Severity Level III problem related to deficiencies associated with inadequate control of leak sealant repairs on the Unit 2 reactor head vent system (HVS) and (2) a Severity Level III violation related to the licensee's failure to correct an adverse condition to quality at Unit 1 involving the operation of the reactor with two out of three pressurizer power operated relief valve (PORV) block valves shut for 13 years.
EA-96-244
Beaver Valley 1 & 2
NOV
(SL III)
09/11/1996 AMSAC failure.
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Big Rock Point - Docket No. 050-00155

NRC Action Number(s) and
Facility Name
Action Type
(Severity) &
Civil Penalty
(if any)
Date
Issued
Description
EA-97-197
Big Rock Point
NOV
(SL III)
08/12/1997 Breakdown in radiation protection program.
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Braidwood 1 & 2 - Docket Nos. 050-00456; 050-00457

NRC Action Number(s) and
Facility Name
Action Type
(Severity) &
Civil Penalty
(if any)
Date
Issued
Description
EA-06-081
Braidwood
NOV
(White)
06/29/2006 On June 29, 2006, a Notice of Violation associated with a White SDP finding was issued for a finding involving multiple failures by the licensee to adequately evaluate the radiological hazards associated with the leaks from the circulating water blowdown line vacuum breakers and to assess the environmental impact of the resultant onsite and offsite tritium contamination.
EA-02-118
Braidwood 1
NOV
(White)
07/23/2002 On July 23, 2002, a Notice of
Violation was issued for a
violation associated with a white
SDP finding involving pressurizer
power operated relief valve
(PORV) air accumulator check
valve failures. The violation cited
the licensee's failure to correct
and prevent recurrence of the
Unit 1 PORV air accumulator
check valves leak-through, a
significant condition adverse to
quality.
EA-00-010
Braidwood 1 & 2
NOV
(SL III)
05/18/2000 On May 18, 2000, a Notice of Violation was issued for a Severity Level III violation based on a radiation protection technician deliberate failure to follow required procedures when he activated the alarms on the portal monitors a total of 14 times and failed to contact the radiation protection department before leaving the station.
EA-97-265
Braidwood 1 & 2
NOVCP
(SL III)

$ 55,000
10/03/1997 Violation of TS surveillance requirements.
EA-97-110
Braidwood 1 & 2
NOV
(SL III)
10/02/1997 Appendix R - safe shutdown concerns.
EA-96-070
Braidwood 1 & 2
NOVCP
(SL III)

$100,000
05/16/1996 Severity Level III problem involving failure to properly control the configuration and alignment of plant systems and the failure to promply identify and correct recurrent problems in the area of plant configuration control.
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Browns Ferry 1, 2 & 3 - Docket Nos. 050-00259; 050-00260; 050-00296

NRC Action Number(s) and
Facility Name
Action Type
(Severity) &
Civil Penalty
(if any)
Date
Issued
Description
EA-04-063
Browns Ferry 1, 2 & 3
NOV
(SL III)
05/12/2004 On May 12, 2004, a Notice of Violation was issued for a Severity Level III violation involving four examples of a failure to adhere to the requirements of 10 CFR 50, Appendix B, Criterion V. All four examples were associated with the Long-Term Torus Integrity Program and involved failure to evaluate or incorporate numerous deficient welds into Deficiency Fix Requests sketches; failure to perform numerous repairs on the correct welds; omission of numerous welds requiring repair from Work Orders; and failure of Quality Control to independently verify the correct location of numerous weld repairs.
EA-00-163
Browns Ferry 1, 2 & 3
NOV
(SL III)
10/27/2000 On October 27, 2000, a Notice of Violation was issued for a severity Level III violation involving the failure to perform required evaluations for out-of-tolerance measuring and test equipment.
EA-96-199
Browns Ferry 1, 2 & 3
NOV
(SL III)
08/01/1996 Violation of TS 3.5.F.1 inoperability of RCIC from inadequate design And inadequate post-modification testing.
EA-95-252
Browns Ferry 1, 2 & 3
NOVCP
(SL III)

$ 80,000  

W/drawal
of CP

02/20/1996 Discrimination.
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Brunswick 1 & 2 - Docket Nos. 050-00325; 050-00324

NRC Action Number(s) and
Facility Name
Action Type
(Severity) &
Civil Penalty
(if any)
Date
Issued
Description
EA-07-024
Brunswick
NOV
(White)
04/20/2007 On April 20, 2007, a Notice of Violation was issued for a violation associated with a White SDP finding involving: (1) inadequate corrective actions to prevent a repeat failure of the #9 main crankshaft bearing on emergency diesel generator (EDG) #1: (2) the failure to follow the foreign material exclusion procedure during maintenance performed on EDG #1; and (3) the failure to promptly identify and implement adequate actions to prevent EDG #1 from tripping on low lubricating oil pressure. These conditions ultimately contributed to an EDG #1 trip and a bearing failure during a Unit 2 loss-of-offsite-power event. The violation was cited against Technical Specification 3.8.1, “AC Sources-Operating,” because EDG #1 was inoperable from October 30 to November 7, 2006. As a result, while Unit 1 was operating in Mode 1, only three of four EDGs were operable for a period in excess of 7 days.
EA-04-076
Brunswick 2

NOV
(White)

  
06/02/2004 On June 2, 2004, a Notice of Violation was issued for a violation associated with a White SDP finding involving the failure to take adequate corrective action for conditions adverse to quality associated with the No. 3 emergency diesel generator (EDG 3) jacket water cooling (JWC) system. The corrective maintenance performed to stop a pipe coupling leak on the JWC supply line to the turbo charger for EDG 3 failed to correct the leak. The violation also cited the failure to comply with Technical Specification 3.8.1, AC Sources Operating, because due to the ongoing leak the EDG 3 was inoperable while the plant was in Mode 1 for a period in excess of seven days.
EA-04-028
Brunswick 1 & 2

NOVCP
(SL II)

$88,000  
04/07/2004 On April 7, 2004, a Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $88,000 was issued for a Severity Level II violation for discriminating against the former Corporate Superintendent of Site Access Authorization for Carolina Power & Light for raising safety concerns.
EA-97-056
Brunswick 1 & 2

NOV
(SL III)
04/24/1997 Several access authorization and fitness-for-duty violations.
EA-96-442
Brunswick 1 & 2
NOV
(SL III)
12/13/1996 The action was based on two violations. The first violation involved the failure to operate Unit 2 within steady state reactor core power level limit of 2436 (Mw) (thermal) and during power operation. The second violation involved the failure to maintain the calculated Average Planar Linear Heat Generation Rate (APLHGR) within the limits of Technical Specification 3.2.1. The violations were categorized as A Severity Level III problem.
EA-96-354
Brunswick 1 & 2
NOVCP
(SL III)

$150,000
11/19/1996 Programmatic EQ issues.
EA-96-181
Brunswick 1 & 2
NOV
(SL III)
07/12/1996 SW pump failed due to galvanic corrosion of bolt mod. 10 affected pumps which established conditions for the corrosion.
EA-96-054
Brunswick 1 & 2
NOV
(SL III)
04/04/1996 Failure to identify presumptive positive drug test results during on-site pre-screening operations.
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Byron 1 & 2 - Docket Nos. 050-00454; 050-00455

NRC Action Number(s) and
Facility Name
Action Type
(Severity) &
Civil Penalty
(if any)
Date
Issued
Description
EA-08-046
Byron 1 & 2
NOV (White) 04/01/2008 On April 1, 2008, a Notice of Violation (NOV) was issued for violations associated with a White Significance Determination Finding. The NOV involved violations of 10 CFR Part 50, Appendix B, Criterion XVI, “Corrective Actions”, and 10 CFR Part 50, Appendix B, Criterion III, “Design Control”. Specifically, the licensee failed to take timely corrective actions after the identification of extensive corrosion on essential service water riser pipes and failed to verify the adequacy of the methodology and design inputs in calculations that supported the decision to accept three degraded essential service water riser pipes for continued service.
EA-05-159
Byron 1 & 2

NOV (SL III) 10/27/2005 On October 27, 2005, a Notice of Violation was issued for a Severity Level III problem involving violations of the Byron Station Technical Specifications. Specifically, an engineer engaged in deliberate misconduct when he failed to perform assigned surveillances of ventilation systems and falsified the records to show the surveillances as completed, a violation of 10 CFR 50.9, "Completeness and Accuracy of Information."
EA-02-124
Byron 1 & 2

(ORDER applies to
multiple Exelon and
AmerGen facilities)
ORDER 10/03/2002 On October 3, 2002, an immediately effective Confirmatory Order was issued to Exelon and AmerGen in order to confirm certain commitments to assure the Licensees' compliance with the Commission's employee protection regulations, 10 CFR 50.7. In view of the Confirmatory Order and consent by the Licensees thereto, dated September 27, 2002, the NRC exercised its enforcement discretion pursuant to Section VII.B.6 of the NRC Enforcement Policy, and refrained from issuing a Notice of Violation or proposing a civil penalty.
EA-97-446
Byron 1 & 2
NOV
(SL III)
11/25/1997 Multiple examples of fire protection analyses deficiencies.
EA-97-264
Byron 1 & 2
NOVCP
(SL III)

$ 55,000
10/03/1997 Violation of TS surveillance requirements.
EA-96-508
Byron 1 & 2
NOVCP
(SL III)

$100,000
07/27/1997 Four violations categorized as two Severity Level III problems related to the identification of excessive silt accumulation in the essential service water (ESW) cooling tower basins and the river screen house intake channel. The first problem involved the failure to (1) translate design configuration information into volumetric requirements for the ESW cooling tower makeup calculation and (2) develop an appropriate acceptance criteria for surveillance procedures to assure ESW operability. The second problem involved two failures to take appropriate corrective actions for conditions adverse to quality involving the silt accumulation and degraded ESW trash racks.
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