Escalated Enforcement Actions Issued to Reactor Licensees - S
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- Saint Lucie 1 & 2
- Salem 1 & 2
- San Onofre 2 & 3
- Seabrook 1
- Sequoyah 1 & 2
- South Texas 1 & 2
- Summer
- Surry 1 & 2
- Susquehanna 1 & 2
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-18-066 St. Lucie Nuclear Power Plant |
NOVCP | 09/12/2019 | On September 12, 2019, the NRC issued a Notice of Violation and Proposed Imposition of Civil Penalty (CP) in the amount of $232,000 to Florida Power and Light (FPL, Licensee) for a Severity Level II violation of NRC requirements involving employee protection. The violation involved a company executive deliberately discriminating against a contract employee for engaging in a protected activity in the Spring of 2017. Specifically, a contract employee who raised safety concerns during the St. Lucie Nuclear Plant (St. Lucie) refueling outage had a scheduled work assignment to the Turkey Point Nuclear Plant cancelled shortly after submitting a condition report at St. Lucie. The NRC determined that the actions of FPL management were, in part, based on the contractor's engagement in a protected activity. |
| EA-14-131 Saint Lucie Plant |
NOV (White) |
11/19/2014 | On November 19, 2014, the NRC issued a Notice of Violation associated with a White Significance Determination Process finding to the Florida Power and Light Company (FPL or licensee) for a violation identified at its St. Lucie Plant. The violation involved the failure to comply with Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix B, Criterion III, "Design Control" and Criterion XVI, "Corrective Action." Specifically, the licensee failed to install internal flood barriers in conduits that penetrated the Unit 1 Reactor Auxiliary Building (RAB) exterior wall at elevations below the design flood height and did not to identify the missing barriers during flooding walkdowns performed in response to the NRC's "Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident." The missing flood barriers were identified when the St. Lucie site experienced a period of unusually heavy rainfall on January 9, 2014, and approximately 50,000 gallons of water entered the RAB through two of the degraded conduits. The NRC also issued a Severity Level III Notice of Violation to FPL for a violation of 10 CFR 50.9(a) involving the licensee's failure to provide the NRC with complete and accurate information in its 10 CFR 50.54(f) response and a 10 CFR 50.73 report that described the safety significance of the degraded and missing flood penetration seals. |
| 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. |
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). |
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-18-155 San Onofre |
NOVCP (SL II & III) |
03/25/2019 |
On March 25, 2019, the NRC issued a Notice of Violation and Proposed Imposition of Civil Penalty (CP) in the amount of $116,000 to Southern California Edison Company for two violations of NRC requirements related to an August 3, 2018 fuel-loading incident at San Onofre Nuclear Generating Station. The first violation was Severity Level (SL) II violation involving the failure to ensure important to safety equipment was available to provide redundant drop protection features for a spent fuel canister during downloading operations. Specifically, the licensee inadvertently disabled the redundant important to safety downloading slings while lowering canister 29 into the storage vault. During the approximately 45 minute time frame, the canister rested on a shield ring unsupported by the redundant downloading slings at approximately 18 feet above the fully seated position. This failure to maintain redundant drop protection placed canister 29 in an unanalyzed condition because the postulated drop of a loaded spent fuel canister is not analyzed in the final safety analysis report. In addition, a SL III violation involving the failure to make a timely notification to the NRC Headquarters Operations Center for the August 3, 2018, disabling of important to safety equipment. Specifically, the licensee failed to notify the NRC after an event that occurred on August 3, 2018, in which the licensee inadvertently disabled the redundant important to safety downloading slings while lowering spent fuel canister 29 into the storage vault, which resulted in the canister resting on a shield ring unsupported by the redundant downloading slings at approximately 18 feet above the fully seated position for approximately 45 minutes. |
| 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. |
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. |
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-14-003 Sequoyah Nuclear Plant |
NOV (SL III) $70,000 |
03/09/2015 | On March 9, 2015, the NRC issued a Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $70,000 to Tennessee Valley Authority for a Severity Level III Problem involving two violations. The first violation involved the failure to conduct compensatory fire watches as required by TVA corporate procedures and 10 CFR 50.48. Specifically, on multiple occasions during October and November 2012, hourly fire watches required as compensatory measures for fire protection equipment that was out of service in the Emergency Diesel Generator Building were not performed. In addition, the designated fire watch foremen willfully failed to have proper oversight of fire watch activities. The second violation involved the failure to maintain complete and accurate records as required by 10 CFR 50.9(a). Specifically, on multiple occasions during the same time frame, fire watch patrol records were falsified when individuals initialed that fire watches were completed when in fact, these fire watches had not been performed. |
| 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. |
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-24-117 South Texas Project Electric Generating Station, Unit 2 |
NOV (White) |
01/21/2025 | On January 21, 2025, the NRC issued a notice of violation to South Texas Project Nuclear Operating Company (licensee) associated with a white significance determination process finding at South Texas Project Electric Generating Station. The white finding, an issue of low-to-moderate safety significance, involved the licensee’s failure to demonstrate that the performance of a Unit 2 load center breaker, had been effectively controlled through the performance of appropriate preventive maintenance such that the component remained capable of performing its intended function as required by Title 10 of the Code of Federal Regulations (CFR), Part 50.65, “Requirements for monitoring the effectiveness of maintenance at nuclear power plants.” |
| EA-19-054 South Texas Project Electric Generating Station, Units 1 and 2 |
NOV (SL III) |
02/23/2021 | On February 23, 2021, the NRC issued a severity level III Notice of Violation to South Texas Project Nuclear Operating Company’s South Texas Project Electric Generating Station, Units 1 and 2, for a violation of Title 10 of the Code of Federal Regulations (CFR) Part 50.9(a) and Appendix B to 10 CFR Part 50, for the failure to maintain complete and accurate information in the form of a written statement that was collected as part of a root cause evaluation for a refueling mishap. |
| EA-16-216 STP Nuclear Operating Company South Texas Project Electric Generating Station |
NOV (SL III) |
08/18/2017 | On August 18, 2017, the NRC issued a Severity Level Ill Notice of Violation to STP Nuclear Operating Company for violations of 10 CFR 50.9, "Completeness and accuracy of information" and 10 CFR 50.48, "Fire protection". Specifically, the Notice of Violation involved two examples of failing to implement fire protection program written procedures for fire watches; and three examples of failing to ensure that fire protection documents were complete and accurate in all material respects. |
| 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. |
Summer - Docket No. 050-00395
| NRC Action Number(s) and Facility Name |
Action Type (Severity) & Civil Penalty (if any) |
Date Issued |
Description |
|---|---|---|---|
| EA-23-093 Virgil C. Summer Nuclear Station |
NOV (White) |
12/21/2023 | On December 21, 2023, the NRC issued a notice of violation associated with a white significance determination process finding to Dominion Energy (licensee) at the Virgil C. Summer Nuclear Station. The white finding, an issue of low-to-moderate safety significance, involved the licensee’s failure to identify and correct the failure mechanism resulting in cracked piping/fittings in the emergency diesel generator (EDG) fuel oil lines, a condition adverse to quality, and a violation of Title 10 of the Code of Federal Regulations (10 CFR) 50, Appendix B, Criterion XVI, “Corrective Action.” This eventually led to the failure of the ‘A’ EDG fuel oil piping during testing on November 2, 2022. |
| EA-22-039 Virgil C. Summer Nuclear Station |
NOV (White) |
10/18/2022 | On October 18, 2022, the NRC issued a notice of violation associated with a white significance determination process finding to Dominion Energy (licensee) at Virgil C. Summer Nuclear Station. The white finding, an issue of low-to-moderate safety significance, involved the licensee’s failure to adequately assess erratic emergency diesel generator (EDG) governor operation which resulted in an inoperable EDG. This failure to document the EDG performance is a violation of 10 CFR 50, Appendix B, Criterion XVI and since this inoperable EDG exceeded the licensee’s technical specification (TS) allowed outage time, a TS violation was also issued. |
| 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. |
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-20-057 Surry 1 & 2 |
NOV (White) |
07/30/20 | On July 30, 2020, the NRC issued a Notice of Violation to Virginia Electric and Power Company (Licensee), associated with a White Significance Determination Process finding. The white finding, an issue of low to moderate safety significance, involved the failure of the Surry Power Station Unit 2 turbine-driven auxiliary feedwater (TDAFW) pump discharge check valve during surveillance testing. Specifically, from November 23, 2005, to November 20, 2019, the licensee did not analyze common failure or maintenance patterns to determine their significance and to identify potential failure mechanisms of the valve when establishing its check valve condition monitoring program in accordance with the 2004 ASME Code for Operation and Maintenance of Nuclear Power Plants, Mandatory Appendix II, as required by 10 CFR Part 50.55a(f)(4). As a result, all three Unit 2 auxiliary feedwater pumps were declared inoperable, and the safety function was considered lost until the TDAFW line was isolated. |
| 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. |
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-24-111 Susquehanna Steam Electric Station |
NOV (White) |
01/27/2025 | On January 27, 2025, the NRC issued a notice of violation to Susquehanna Nuclear, LLC (licensee) associated with a white significance determination process finding at Susquehanna Steam Electrical Station, Units 1 and 2. The white finding, an issue of low-to-moderate safety significance, involved the licensee’s failure to promptly identify and correct a condition adverse to quality for the 'B' emergency diesel generator (EDG), which resulted in the inoperability of the EDG. This failure to correct a condition adverse to quality was contrary to Title 10 of the Code of Federal Regulations, Part 50, Appendix B, Criterion XVI, "Corrective Action" and licensee Technical Specifications. |
| EA-15-022 Susquehanna Steam Electric Station |
NOV (White) |
06/22/2015 | On June 22, 2015, the NRC issued a Notice of Violation associated with a White Significance Determination Process finding to Susquehanna Nuclear, LLC. The finding was associated with the failure to implement the 15-minute assessment, classification, and declaration period for a potential loss of Reactor Coolant System (RCS) barrier emergency action level (EAL) at the Susquehanna Steam Electric Station (Susquehanna), Units 1 and 2. Specifically, Susquehanna interpreted the 15-minute assessment, classification, and declaration clock to start when operator actions were, or were expected to be, unsuccessful in isolating an RCS leak rather than upon the time when the EAL thresholds were exceeded. Susquehanna's incorrect interpretation of the 15-minute assessment and declaration period degraded its ability to make a timely Site Area Emergency declaration. The Notice of Violation involved the failure to comply with the requirements of 10 CFR 50.47(b)(4),"Emergency Plans," 10 CFR 50.54(q)(2), "Conditions of License," and 10 CFR 50, Appendix E, Section IV.C.2., "Emergency Planning and Preparedness for Production and Utilization Facilities." |
| 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 |
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. |
Page Last Reviewed/Updated Tuesday, February 25, 2025
Page Last Reviewed/Updated Tuesday, February 25, 2025