United States Nuclear Regulatory Commission - Protecting People and the Environment

Escalated Enforcement Actions Issued to Reactor Licensees - S

A | B | C | D | E | F | G | H | I | J | K | L | M | N | O | P | Q | R | S | T | U | V | W | X | Y | Z

This page includes links to files in non-HTML format. See Plugins, Viewers, and Other Tools for more information.

Saint Lucie 1 & 2 - Docket Nos. 050-00335; 050-00389

NRC Action Number(s) and
Facility Name
Action Type
(Severity) &
Civil Penalty
(if any)
Date
Issued
Description
EA-09-321
Saint Lucie 1 & 2
NOV
(Yellow)
04/19/2010 On April 19, 2010, a Notice of Violation was issued to Florida Power & Light Company for a violation associated with a Yellow Significance Determination Finding as a result of inspections at the St. Lucie Nuclear Plant. The Yellow finding involved the licensee's failure to meet the requirements of 10 CFR 50, Appendix B, Criterion XVI, "Corrective Action." In 2008, the licensee experienced an air in-leakage event into the closed cooling water (CCW) system which affected the system's ability to supply adequate cooling to essential equipment. Their troubleshooting and corrective actions failed to identify the source of the air in-leakage, which resulted in a similar event in 2009.
EA-08-172
Saint Lucie 1 & 2
ORDER 10/20/2008 On October 20, 2008 a Confirmatory Order (effective immediately) was issued to Florida Power & Light Co. to confirm commitments made as a result of an Alternative Dispute Resolution (ADR) settlement agreement, regarding a violation of site security procedures caused by the deliberate actions of one of the security operations supervisors at the licensee's St. Lucie Nuclear Plant. The security operations supervisor willfully permitted two containers into the protected area without conducting the required search of their contents.
EA-98-513
Saint Lucie 1 & 2
NOV
(SL III)
03/31/1999 Inadequate fire protection procedure.
EA-98-064
Saint Lucie 1 & 2
NOV
(SL III)
04/03/1998 Two cases of failure to control unauthorized access to the protected and vital area.
EA-98-009
Saint Lucie 1 & 2
NOVCP
(SL II)

$ 88,000
03/25/1998 Wrong refueling water tank swapover setting.
EA-97-501
Saint Lucie 1 & 2
NOV
(SL III)
12/11/1997 Inadequate PMT caused fan cooler motor to be inoperable.
EA-96-457
Saint Lucie 1 & 2
NOVCP
(SL III)

$ 50,000
01/10/1997 Miswiring; unauthorized individual entry into protected area after termination; emergency preparedness failures involving phone system, procedures and training.
EA-96-249
Saint Lucie 1 & 2
NOV
(SL III)
09/19/1996 A number of related violations of the requirements of 50.59.
EA-96-040
Saint Lucie 1 & 2
NOVCP
(SL III)

$ 50,000
03/28/1996 Licensed operator left the controls without informing his relief of a dilution in progress.

To top of page

Salem 1 & 2 - Docket Nos. 050-00272; 050-00311

NRC Action Number(s) and
Facility Name
Action Type
(Severity) &
Civil Penalty
(if any)
Date
Issued
Description
EA-03-070
Salem 1 & 2
NOV
(White)
05/01/2003 On May 1, 2003, a Notice of Violation was issued for a violation associated with a White SDP finding involving emergency diesel generator (EDG) turbocharger failures. The violation cited the licensee's failure to implement effective corrective actions to preclude repetition of a significant condition adverse to quality associated with the EDG turbocharger failures.
EA-00-018
Salem 1 & 2
NOV
(White)
02/14/2000 On February 14, 2000, a Notice of Violation was issued for failure to comply with a fire protection license condition. It was cited in accordance with the Interim Enforcement Policy for use during the NRC Power Reactor Oversight Process Plant Study. The violation was associated with a finding (failure of the Unit 2 4160Vac switchgear room carbon dioxide fire suppression system to achieve required concentration) that the Significance Determination Process characterized as White.
EA-97-182
Salem 1 & 2
NOV
(SL III)
10/08/1997 Failure to meet 50.59 involving USQs.
EA-96-344
Salem 1 & 2
NOVCP
(SL III)

$100,000
12/11/1996 This action involved three violations related to two specific events concerning the failure to adequately control access to the facility. The first violation was categorized as a Severity Level III violation and involved a keycard photobadge station problem that could have resulted in an unauthorized individual gaining access to the protected and vital areas of the stations. The second event involved two violations where a contractor individual accessed the protected area without an adequate search after the individual had, on three occasions, alarmed two separate metal detectors at the stations' access control point. These two violations were categorized as a Severity Level III problem. Three violations not assessed a civil penalty were also identified involving the licensee's failure to comply with the Security Plan.
EA-96-177
Salem 1 & 2
NOVCP
(SL II)

$ 80,000
12/09/1996 The licensee, through its former manager of NSR, discriminated in December 1992 against a Safety Review Engineer (SRE) and in November 1993 and May 1994 against a former Onsite Safety Review Engineer (OSRE).

To top of page

San Onofre 2 & 3 - Docket Nos. 050-00361; 050-00362

NRC Action Number(s) and
Facility Name
Action Type
(Severity) &
Civil Penalty
(if any)
Date
Issued
Description
EA-13-083
San Onofre
NOV
(White)
12/23/2013 On December 23, 2013, the NRC issued a Notice of Violation associated with a White Significance Determination Process finding identified during an inspection of the San Onofre Nuclear Generating Station, Unit 3. This White finding, an issue of low to moderate safety significance, involves the failure of San Onofre personnel to verify the adequacy of the thermal-hydraulic and flow-induced vibration design of the Unit 3 replacement steam generators, which resulted in significant and unexpected steam generator tube wear and the loss of tube integrity on Unit 3 Steam Generator 3EO-88 after 11 months of operation.
EA-11-083
San Onofre
NOV
(SL III)
08/04/2011 On August 4, 2011, the NRC issued a Notice of Violation to SONGS for a Severity Level III violation involving the failure to certify that the qualifications and status of a senior operator licensee were current and valid and that the senior operator licensee had completed a minimum of 40 hours of shift functions under the direction of an operator or senior operator, as required by 10 CFR 55.53(e) and (f). Specifically, on October 21 and October 27, 2010, the licensee did not certify that qualifications of the senior operator licensee were current and valid and scheduled the senior operator to perform licensed activities (core alterations) as refueling senior operator supervisor while his license was INACTIVE. Additionally, the senior operator was not medically qualified in accordance with ANSI 3.4 (1996) to perform licensed duties.
EA-08-296
San Onofre
NOV
(White)
12/19/2008 On December 19, 2008, a Notice of Violation was issued for a violation associated with a White Significance Determination Finding involving a violation of 10 CFR Part 50, Appendix B, Criterion V, "Instructions, Procedures, and Drawings." Specifically, maintenance and work control personnel failed to develop appropriate instructions or procedures, and failed to include quantitative or qualitative steps to ensure the maintenance activities on safety-related batteries were satisfactorily completed. This failure resulted in a safety-related battery being inoperable between March 2004 and March 25, 2008.
EA-07-232
San Onofre
ORDER 01/11/2008 On January 11, 2008, a Confirmatory Order (Effective Immediately) was issued to Southern California Edison Company (SCE) to formalize commitments made as a result of a successful alternative dispute resolution (ADR) mediation session. The commitments were made by SCE as part of a settlement agreement between SCE and the NRC concerning the falsification, by a contract fire protection specialist at SONGS, of firewatch certification sheets on numerous occasions from April 2001 to December 2006. As part of the settlement agreement, SCE agreed to, in general terms, performing a common cause evaluation of known recent events, conducting a safety culture assessment, conducting training and communications, and developing or enhancing various programs in areas such as ethics, disciplinary process, contract programs, and oversight. In recognition of these actions, and those corrective actions already completed, NRC will refrain from further enforcement action related to this particular case, and may exercise enforcement discretion for the next six months on willful cases that meet the conditions of Section VII.B.4 of the Enforcement Policy, "Violations Identified Due to Previous Enforcement Action." NRC will evaluate the implementation of SCE's commitments during future inspections.
EA-06-149
San Onofre 1
NOV
(SL III)
09/13/2006 On September 13, 2006, a Notice of Violation was issued for a Severity Level III problem involving a transportation event in which a shipment of low specific activity liquid radioactive waste from San Onofre Unit 1 leaked from its transport container in Utah. The violations involved failures to (1) ensure by examination or appropriate tests that the top discharge valve of the tanker was properly closed and sealed; (2) load the tanker to the required fill density; and (3) maintain, fill, and close the tanker so that, under conditions normally incident to transportation, there would be no identifiable release of materials to the environment.
EA-99-242
San Onofre 2 & 3
NOV
(SL III)
12/15/1999 Violation based on the licensee's failure to comply with their technical specifications when they did not recognize a condition that rendered one diesel generator and more than one battery charger inoperable.
EA-98-563
San Onofre 2 & 3
NOV
(SL III)
03/16/1999 Violation of plant technical specifications.
EA-97-585
San Onofre 2 & 3
NOV
(SL III)
02/18/1998 Loss of safeguards contingency plan and several other security issues.

To top of page

Seabrook 1 - Docket No. 050-00443

NRC Action Number(s) and
Facility Name
Action Type
(Severity) &
Civil Penalty
(if any)
Date
Issued
Description
EA-12-093
Seabrook 1
NOV
(White)
08/07/2012 On August 7, 2012, the NRC issued a Notice of Violation to NextEra Energy Seabrook, LLC. (Seabrook) for a violation of 10 CFR 50.54(q)(2), associated with a White Significance Determination Process finding involving Seabrook's failure to identify an performance weakness during the post-exercise critique. Specifically, Seabrook did not identify as a weakness that an incorrect initial Protective Action Recommendation (PAR) had been developed and communicated to the state response organizations. The initial PAR was incorrect for the exercise actual condition (i.e., no release in progress).
EA-09-145
Seabrook 1
NOV
(White)
11/12/2009 On November 12, 2009, the NRC issued a Notice of Violation to NextEra Energy Seabrook, LLC, for a violation of 10 CFR 50, Appendix B, Criterion III, "Design Control," at Seabrook Station. The violation, which is associated with a White Significance Determination Process finding, involved the failure to assure that the design basis of the B emergency diesel generator (EDG) was correctly translated into work instructions and that measures were established for the selection of suitable parts and materials. Specifically, a design change to a flange on a jacket water cooling line to the B EDG turbocharger did not (1) control welding stresses, verify flange alignment, or evaluate vibration effects, (2) address suitability of gasket material, or (3) consider flange performance history. This resulted in failure of the flange during operation of the B EDG, leading to rapid loss of jacket cooling water and inoperability of the EDG.
EA-01-032
Seabrook 1
NOV
(White)
06/29/2001 On June 29, 2001, a Notice of Violation was issued for a violation associated with a White SDP finding involving the emergency diesel generator (EDG). The violation was based on the licensee's failure to take adequate corrective actions to address degraded components associated with the EDG.
EA-98-165
Seabrook 1
NOVCP
(SL III)

$ 55,000
08/03/1999 Violation involving discrimination against an electrician for raising safety issues.
EA-98-073
Seabrook 1
NOV
(SL III)
04/01/1998 Technical Specification and corrective action violation involving control building chillers and other safety related equipment.

To top of page

Sequoyah 1 & 2 - Docket Nos. 050-00327; 050-00328

NRC Action Number(s) and
Facility Name
Action Type
(Severity) &
Civil Penalty
(if any)
Date
Issued
Description
EA-13-045
Sequoyah 1 & 2
NOV 06/04/2013 On June 4, 2013, the NRC issued a Notice of Violation (NOV) to Tennessee Valley Authority for a violation of 10 CFR 50, Appendix B, Criterion III, "Design Control," associated with a White Significance Determination Process finding involving the failure of Sequoyah personnel to translate the design basis related to onsite flooding into specifications, drawings, procedures, and instructions.  Specifically, prior to December 15, 2012, Sequoyah's design documentation for the essential raw cooling water (ERCW) pumping station did not contain information to identify design basis flood barriers to prevent water from flooding the building during a design basis flood.  As a result, the ERCW pump station would not remain functional when subjected to the maximum flood level, the ERCW intake station would not remain dry during flood mode, and portions of the ERCW walls and penetrations would not withstand all static and dynamic forces imposed by the design basis flood.
EA-13-023
Sequoyah 1 & 2
NOV
(White, SL III)
06/04/2013 On June 4, 2013, the NRC issued a Notice of Violation (NOV) associated with a White Significance Determination Process (SDP) finding and a Severity Level III violation to Tennessee Valley Authority (TVA). The White finding, a violation of Technical Specification (TS) 6.8.1, Procedures and Programs, involved the failure of Sequoyah personnel to establish an adequate Abnormal Condition Procedure to implement its flood mitigation strategy. Specifically, prior to September 30, 2009, AOP-N.03, "External Flooding," was inadequate to mitigate the effects of a Probable Maximum Flood (PMF) event, in that earthen dams located upstream of the facility could potentially overtop, causing a subsequent breach and resulting in onsite flooding and the submergence of critical equipment. The Severity Level III violation of 10 CFR 50.72(b)(3)(ii)(B) involved the failure of Sequoyah personnel to report within eight hours an unanalyzed condition that significantly degraded plant safety. Specifically, on December 30, 2009, Sequoyah personnel failed to notify the NRC upon confirmation that a postulated Probable Maximum Flood (PMF) level would exceed the current licensing basis and the design basis PMF flooding event would result in overtopping of critical earthen dam structures upstream of the Sequoyah facility.
EA-08-211
Sequoyah 1 & 2
ORDER 01/05/2009 On January 5, 2009 a Confirmatory Order (effective immediately) was issued to Tennessee Valley Authority to confirm commitments made as a result of an Alternative Dispute Resolution (ADR) settlement agreement, regarding violation of site security procedures caused by the deliberate actions of one contract security supervisor at the Sequoyah Nuclear Plant, who falsified an inventory form to conceal the supervisor's failure to verify inventory as required by licensee procedures.
EA-04-223
Sequoyah 1 & 2
NOV
(White)
01/26/2005 On January 26, 2005, a Notice of Violation was issued for a violation associated with a White finding involving binding problems with the breaker mechanism operated cell slide assembly for the 1A Residual Heat Removal pump. The violation cited the licensee's failure to correct conditions adverse to quality based on the identification of binding problems during previous surveillance testing.
EA-99-234
Sequoyah 1 & 2
NOVCP
(SL II)

$110,000
02/07/2000 On February 7, 2000, a Notice of Violation and Proposed Imposition of Civil Penalty of $110,000 was issued for a Severity Level II violation involving employment discrimination against a former corporate employee, for engaging in protected activities.
CPORDER
$110,000
05/04/2001
EA-98-207
Sequoyah 1 & 2
NOV
(SL III)
06/18/1998 Failure of Identifications/Assessment equipment.
EA-97-409
Sequoyah 1 & 2
NOVCP
(SL III)

$ 55,000

Withdrawal
of CP
12/08/1997 Inoperable DC vital board.
EA-97-232
Sequoyah 1 & 2
NOV
(SL III)
07/10/1997 Inadvertent RCS drain down with numerous deficiencies noted in the area of operation.
EA-96-414
Sequoyah 1 & 2
NOVCP
(SL III)

$100,000
12/24/1996 Reactor trip complications.
CPORDER
$ 50,000
05/23/1997
EA-96-269
Sequoyah 1 & 2
NOVCP
(SL III)

$ 50,000
11/19/1996 Adverse conditions related to the fire protection program were not promptly identified and/or resolved.
CPORDER 03/17/1997
EA-95-199
Sequoyah 1 & 2
NOVCP
(SL I)

$100,000
01/13/1997 Chemistry manager was threatened with termination for raising safety concerns.

To top of page

South Texas 1 & 2 - Docket Nos. 050-00498; 050-00499

NRC Action Number(s) and
Facility Name
Action Type
(Severity) &
Civil Penalty
(if any)
Date
Issued
Description
EA-97-341
South Texas 1 & 2
ORDER 06/09/1998 Discrimination against supervisor and engineer for reporting safety concerns.
EA-96-500
South Texas 1 & 2
NOV
(SL III)
03/27/1997 Leak in ECCS system.
EA-96-133
South Texas 1 & 2
NOVCP
(SL II)

$200,000
09/19/1996 Discrimination.

To top of page

Summer - Docket No. 050-00395

NRC Action Number(s) and
Facility Name
Action Type
(Severity) &
Civil Penalty
(if any)
Date
Issued
Description
EA-12-140
Virgil C. Summer Nuclear Station
CO 03/10/2014 On March 10, 2014, the NRC issued a Confirmatory Order (CO) to South Carolina Electric & Gas Company (SCE&G) to formalize commitments made as a result of an alternative dispute resolution (ADR) mediation session held on October 8, 2013. The commitments were made as part of a settlement agreement between SCE&G and the NRC regarding the apparent violations of 10 CFR 73.56, "Personnel access authorization requirements for nuclear power plants" and 10 CFR 50.9, "Completeness and accuracy of information."  The first violation involved the willful actions of the licensee's access authorization staff, which caused the licensee's access authorization program to fail to provide high assurance that individuals granted unescorted access are trustworthy and reliable, such that they do not constitute an unreasonable risk to public health and safety, as required by 10 CFR 73.56(c).  Specifically, the licensee's access authorization reviewing officials reviewed, adjudicated, and granted an individual unescorted access authorization by relying unreasonably on a falsified PHQ and fabricated court record to determine their trustworthiness and reliability. The second violation involved the willful failure to comply with the requirements of 10 CFR 50.9(a) which, in part, state that "information required by statute or Commission regulations to be maintained shall be complete and accurate in all material respects."  In part, 10 CFR 73.56(o)(2)(i) requires the licensee to retain records of information that must be collected under subparts (d) and (e) of 10 CFR 73.56 that result in the granting of unescorted access for at least 5 years after the licensee terminates, or denies, an individual's unescorted access or unescorted access authorization.  As part of the ADR settlement agreement SCE&G agreed that the issues described above resulted in an individual inappropriately being granted unescorted access to Summer Nuclear Station (SNS), which was inconsistent with the requirements of 10 CFR 73.56(c) and 10 CFR 50.9.  SCE&G did not agree that the two violations were committed willfully.  However, the NRC determined these violations to be willful.  In response to the incident, SCE&G completed a number corrective actions and enhancements, and agreed to complete additional corrective actions and enhancements, as fully discussed in the CO.  The NRC concluded that the corrective actions and enhancements discussed by SCE&G were prompt and comprehensive and addressed the causes.  In consideration of the commitments delineated in the CO, the NRC agreed to fully mitigate a civil penalty and issue a Notice of Violation.
EA-07-079
Summer
NOV
(SL III)
10/12/2007 On October 12, 2007, a Severity Level III Notice of Violation and Exercise of Enforcement Discretion were issued to South Carolina Electric and Gas Company (SCE&G). The violation resulted from changes the licensee made to its Emergency Plan between October 1980 and July 2006. Contrary to 10 CFR 50.54(q) which allows a licensee to make changes to emergency plans without Commission approval when such changes do not decrease the effectiveness of the plans and the plans, as changed, continue to meet the standards of 10 CFR 50.47(b), SCE&G made changes without Commission approval which decreased the effectiveness of their Emergency Plan and resulted in the use of a non-standard scheme of Emergency Action levels.
EA-06-046
Summer
NOV
(White)
05/05/2006 On May 5, 2006, a Notice of Violation associated with a White SDP finding was issued for a finding involving the shipment of radioactive material in a package with radiation levels on an external surface that exceeded applicable regulatory requirements. The Notice of Violation cited the licensee's failure to properly design and prepare for shipment a package containing radioactive material that was transported from the licensee's facility to an offsite waste processing vendor.
EA-01-150
Summer
NOV
(SL III)
08/31/2001 On August 31, 2001, a Notice of Violation was issued for a Severity Level III violation involving the failure to perform an adequate written safety evaluation to determine whether a change to the facility involved an unreviewed safety question.
EA-00-238
Summer
NOV
(White)
12/28/2000 On December 28, 2000, a Notice of Violation was issued for a violation associated with a White SDP finding involving the inoperability of the turbine driven emergency feedwater (TDEFW) pump. The violation cited the licensee's failure to properly follow procedures which resulted in the failure to comply with the technical specification for TDEFW pump operability.

To top of page

Surry 1 & 2 - Docket Nos. 050-00280; 050-00281

NRC Action Number(s) and
Facility Name
Action Type
(Severity) &
Civil Penalty
(if any)
Date
Issued
Description
EA-06-071
Surry 1 & 2
NOV
(White)
07/25/06 On July 25, 2006, a Notice of Violation was issued for a violation associated with a White Significance Determination Process (SDP) finding involving the failure of a licensee's full-scale exercise critique to identify a weakness associated with a risk-significant planning standard which was determined to be a drill/exercise performance-performance indicator opportunity failure. The violation was cited against emergency preparedness planning standards 10 CFR 50.47(b)(4) and 10 CFR 50.47(b)(14) as well as the requirements of 10 CFR Part 50, Appendix E, Section IV.F.2.g, because the licensee failed to identify the above weakness during its emergency exercise critique.
EA-04-005
Surry 1 & 2
NOV
(White)
09/15/04 On September 15, 2004, a Notice of Violation was issued for a violation associated with a White SDP finding involving ineffective safe shutdown procedures during a postulated fire that could have resulted in a reactor coolant pump seal loss of coolant accident. The violation cited the licensee's ineffective alternative shutdown capability and response procedures for a postulated fire in the Emergency Switchgear Room Number 1 and 2.
EA-01-235
Surry 1 & 2
NOV
(White)
12/21/01 On December 21, 2001, a Notice of Violation was issued for a violation associated with a White SDP finding involving failed piston wrist pins and bearings in the Number 3 Emergency Diesel Generator (EDG). The violation cited the licensee's failure to establish measures to assure that conditions adverse to quality were promptly identified and corrected that resulted in the inoperability of the Number 3 EDG.
EA-97-474
Surry 1 & 2
NOV
(SL III)
12/24/1997 Unable to meet requirements of Appendix R,III.G. for postulated control room fire.
EA-97-055
Surry 1 & 2
NOVCP
(SL III)

$ 55,000
08/29/1997 Violations of the Maintenance Rule.
EA-96-231
Surry 1 & 2
NOV
(SL III)
08/16/1996 H2 analyzes inoperable due to inadequate procedure.

To top of page

Susquehanna 1 & 2 - Docket Nos. 050-00387; 050-00388

NRC Action Number(s) and
Facility Name
Action Type
(Severity) &
Civil Penalty
(if any)
Date
Issued
Description
EA-12-216
Susquehanna Steam Electric Station
Berwick, PA
NOV
(SL III)
08/28/2013 On August 28, 2013, a Notice of Violation (NOV) was issued to Pennsylvania Power and Light (PPL) Susquehanna, LLC for a Severity Level III problem for several issues with PPL's process for conducting biennial medical exams for licensed reactor operators (ROs) and reporting changes in RO medical conditions. Between August 2007 and June 2012, eight RO's performed licensed duties when they had permanent disabilities or illnesses that caused them to not meet the requirements of 10 CFR 55.33, "Disposition of an initial application." PPL also provided information to the NRC that was not complete and accurate when they submitted an initial RO application and three NRC licensed operator renewal applications. This was a violation of 10 CFR 50.9, "Completeness and accuracy of information."
EA-10-207
Susquehanna 1 & 2
NOV
(White)
12/16/2010 On December 16, 2010, the NRC issued a White finding to PPL Susquehanna, LLC as a result of inspections at the Susquehanna Steam Electric Plant Unit 1 and 2. The White finding involved inadequate procedures related to the maintenance and operation of the main condenser waterboxes and circulating water system, which resulted in an internal flooding event, a manual scram, and a loss of the normal reactor heat sink. There were no NRC violations associated with the finding.
EA-09-248
Susquehanna 1 & 2
NOV
(SL III)
01/28/2010

On January 28, 2010, a Notice of Violation for a Severity Level III violation was issued to PPL Susquehanna, LLC. This finding involved a violation of 10 CFR Part 55.21 which requires, in part, that the licensed operator receives a medical examination by a physician every two years and meets the requirements of 10 CFR 55.33(a)(1). 10 CFR 55.33(a)(1) states, in part, the medical condition of the applicant will not adversely affect the performance of assigned duties or cause operational errors endangering public health and safety. 10 CFR 55.33(b) states, in part, if an applicant's general medical condition does not meet the minimum standards under 10 CFR 55.33(a)(1), the Commission may approve the application and include conditions in the license to accommodate the medical defect. 10 CFR 55.23 requires, in part, that a facility licensee shall certify the medical fitness of an applicant. PPL certified that it used the guidance of ANSI/ANS 3.4 1983 which describes the health requirements.

Contrary to the above, in 2009, a PPL operator did not meet a certain medical prerequisite for performing NRC-licensed operator activities. Specifically, on three separate occasions, the licensed operator performed duties, even though a change in his license condition existed, as found by a medical examination.

EA-02-216
Susquehanna 1 & 2

NOV
(SL III)
01/13/2003 On January 13, 2003, a Notice of Violation was issued for a Severity Level III violation involving the backfilling of a dry shielded canister with argon, rather than helium, as required by the Certificate of Compliance (CoC) for the dry spent fuel storage system used at Susquehanna.
EA-01-087
Susquehanna 1 & 2
NOV
(White)
09/13/2001 On September 13, 2001, a Notice of Violation was issued for a violation associated with a White SDP finding involving certain emergency preparedness functions for an emergency at the site not being met. The violation involved the failure to ensure that procedures were adequate and staffing levels were maintained to meet the site's emergency plan requirements..
EA-01-012
Susquehanna 1 & 2
NOV
(White)
03/12/2001 On March 12, 2001, a Notice of Violation was issued for a violation associated with a White SDP finding involving a substantial potential for personnel to sustain external radiation exposures in excess of occupational exposure limits. The violation involved the failure to perform an adequate evaluation of radiation hazards to assure that occupational dose limits would not be exceeded.
EA-97-472
Susquehanna 1 & 2
NOVCP
(SL III)

$ 55,000
01/09/1998 Controls over an EDG voltage regulator adjustment knob were insufficient to ensure voltage remained appropriately set at 100%.
EA-96-270;
Susquehanna 1 & 2
NOVCP
(SL III)

$210,000
06/20/1997 Erroneous breaker alignment for "E" diesel generator in violation of procedures, EDG inoperable beyond TS LCO time; operators violations of TS surveillance requirements.

To top of page

Page Last Reviewed/Updated Thursday, December 04, 2014