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Category:Enforcement Action
MONTHYEARIR 05000388/20210122021-03-0404 March 2021 EA-20-131: Susquehanna Steam Electric Station, Unit 2 - NRC Investigation Report No. 1-2020-001 and NRC Inspection Report No. 05000388/2021012 IR 05000387/20190032019-11-12012 November 2019 Integrated Inspection Report 05000387/2019003 and 05000388/2019003 and Independent Spent Fuel Storage Installation Inspection Report 07200028/2019001 ML15173A2972015-06-22022 June 2015 EA-15-022 Susquehanna Final Significance Determination for a White Finding with Assessment Follow-up and Notice of Violation (Inspection Report No. 05000387/2015504 and 05000388/2015504) ML15167A1482015-06-16016 June 2015 EN-15-020, Issuance of Final Significance Determination and Notice of Violation to Susquehanna Nuclear, LLC, Susquehanna Steam Electric Station, Units 1 & 2, (EA-15-022) IR 05000387/20130122013-08-28028 August 2013 NRC Inspection Report 05000387/2013012 and 05000388/2013012; and Notice of Violation IR 05000387/20114032011-03-28028 March 2011 IR 05000387-11-403, 05000388-11-403, on 02/07/2011 - 02/11/2011, Susquehanna Steam Electric Station, Access Control, Protective Strategy Evaluation. (Letter Only) IR 05000387/20100082010-12-16016 December 2010 Final Significance Determination of White Finding, with Assessment Follow-up - Susquehanna Steam Electric Station (NRC Inspection Report No. 05000387/2010008 and 05000388/2010008), Dated December 16, 2010 IR 05000387/20090042010-01-28028 January 2010 EA-09-248, Susquehanna, Notice of Violation (NRC Inspection Report Nos. 05000387/2009004 and 05000388/2009004) ML0908505012009-03-26026 March 2009 EN-09-016 - Order Prohibiting Involvement in NRC-Licensed Activities ML0718303172007-07-0202 July 2007 EA-07-083, Susquehanna Steam Electric Station - NRC Investigation Report No. 1-2006-047 2021-03-04
[Table view] Category:Letter
MONTHYEARIR 05000387/20240102024-11-13013 November 2024 Biennial Problem Identification and Resolution Inspection Report 05000387/2024010 and 05000388/2024010 IR 05000387/20245012024-11-13013 November 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000387/2024501 and 05000388/2024501 IR 05000387/20240032024-11-12012 November 2024 Integrated Inspection Report 05000387/2024003 and 05000388/2024003 PLA-8135, Specification 5.5.12, Primary Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type Leak Rate Testing Frequencies and Permanently Extend the Drywell Bypass Leakage Test Frequency - PLA-81352024-11-0101 November 2024 Specification 5.5.12, Primary Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type Leak Rate Testing Frequencies and Permanently Extend the Drywell Bypass Leakage Test Frequency - PLA-8135 ML24289A1252024-10-22022 October 2024 – Authorized Alternative to Requirements of the ASME OM Code PLA-8145, Biennial 10 CFR 50.59 and 72.48 Summary Report and Changes to Regulatory Commitments - PLA-81452024-10-21021 October 2024 Biennial 10 CFR 50.59 and 72.48 Summary Report and Changes to Regulatory Commitments - PLA-8145 ML24291A1562024-10-16016 October 2024 Missed Annual Inventory Required by 40 CFR 266, Subpart in PLE 0026645 PLA-8148, Registration for the Use of Spent Fuel Storage Casks 311, 308, and 3102024-10-15015 October 2024 Registration for the Use of Spent Fuel Storage Casks 311, 308, and 310 PLA-8142, Registration for the Use of Spent Fuel Storage Casks 306, 309, and 307 - PLA-81422024-09-18018 September 2024 Registration for the Use of Spent Fuel Storage Casks 306, 309, and 307 - PLA-8142 PLA-8141, Response to Request for Additional Information Regarding Relief Request 1RR06, PLA-81412024-09-18018 September 2024 Response to Request for Additional Information Regarding Relief Request 1RR06, PLA-8141 ML24260A2312024-09-17017 September 2024 Senior Reactor and Reactor Operator Initial License Examinations 05000387/LER-2024-002, B Diesel Generator Inoperable Due to Failed Excitation System Linear Reactor2024-09-16016 September 2024 B Diesel Generator Inoperable Due to Failed Excitation System Linear Reactor ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 ML24233A2192024-09-0303 September 2024 – Authorized Alternative to Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code IR 05000387/20240052024-08-29029 August 2024 Updated Inspection Plan for Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2024005 and 05000388/2024005) 05000387/LER-2023-004-01, Manual Reactor Scram Due to Degraded Main Condenser Vacuum2024-08-26026 August 2024 Manual Reactor Scram Due to Degraded Main Condenser Vacuum 05000387/LER-2024-001-01, Main Steam Isolation Valve Leakage Due to Valve Body Seat Wear2024-08-21021 August 2024 Main Steam Isolation Valve Leakage Due to Valve Body Seat Wear IR 05000387/20240022024-08-12012 August 2024 Integrated Inspection Report 05000387/2024002 and 05000388/2024002 ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification PLA-8117, 23rd Refueling Outage Owners Activity Report (PLA-8117)2024-07-23023 July 2024 23rd Refueling Outage Owners Activity Report (PLA-8117) ML24197A0982024-07-15015 July 2024 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000387/2024010 and 05000388/2024010 ML24127A2262024-05-29029 May 2024 Issuance of Amendment Nos. 288 and 272 Adoption of TSTF-563 PLA-8126, Response to Request for Confirmation of Information Regarding Relief Request 1RR062024-05-29029 May 2024 Response to Request for Confirmation of Information Regarding Relief Request 1RR06 PLA-8122, Annual Radiological Environmental Operating Report (PLA-8122)2024-05-28028 May 2024 Annual Radiological Environmental Operating Report (PLA-8122) 05000387/LER-2024-001, Main Steam Isolation Valve Leakage2024-05-23023 May 2024 Main Steam Isolation Valve Leakage PLA-8115, Relief Request IRR06 One Time Extension to the Fourth 10-Year Inservice Testing Program Interval (PLA-8115)2024-05-23023 May 2024 Relief Request IRR06 One Time Extension to the Fourth 10-Year Inservice Testing Program Interval (PLA-8115) IR 05000387/20240012024-05-13013 May 2024 Integrated Inspection Report 05000387/2024001 and 05000388/2024001 IR 05000387/20244042024-05-0707 May 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000387/2024404 and 05000388/2024404 PLA-8095, 2023 Annual Radiological Environmental Operating Report (PLA-8095)2024-04-22022 April 2024 2023 Annual Radiological Environmental Operating Report (PLA-8095) ML24082A1372024-04-22022 April 2024 Issuance of Amendment Nos. 287 and 271 Adoption of TSTF-568, Revision 2 and Associated Technical Specification Changes PLA-8094, Radioactive Effluent Release Report and Offsite Dose Calculation Manual PLA-80942024-04-22022 April 2024 Radioactive Effluent Release Report and Offsite Dose Calculation Manual PLA-8094 PLA-8101, Re 2023 Annual Report of Radiation Exposure2024-04-22022 April 2024 Re 2023 Annual Report of Radiation Exposure PLA-8102, Annual Environmental Operating Report (Nonradiological) PLA-81022024-04-11011 April 2024 Annual Environmental Operating Report (Nonradiological) PLA-8102 PLA-8113, Response to Request for Additional Information Regarding Relief Request 4RR-11 (PLA-8113)2024-04-11011 April 2024 Response to Request for Additional Information Regarding Relief Request 4RR-11 (PLA-8113) PLA-8112, Relief Request 4RR-11 Relief from End of Interval Boundary Leakage Test PLA-81122024-04-0909 April 2024 Relief Request 4RR-11 Relief from End of Interval Boundary Leakage Test PLA-8112 PLA-8110, Submittal of Unit 1 Cycle 24 Core Operating License Report (Pla 8110)2024-04-0404 April 2024 Submittal of Unit 1 Cycle 24 Core Operating License Report (Pla 8110) PLA-8100, Property Insurance Program (PLA-8100)2024-04-0101 April 2024 Property Insurance Program (PLA-8100) PLA-8098, Annual Financial Report (PLA-8098)2024-04-0101 April 2024 Annual Financial Report (PLA-8098) PLA-8109, Supplement to Request for Exemption from Certain Requirements of 10 CR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance (PLA-8109)2024-03-21021 March 2024 Supplement to Request for Exemption from Certain Requirements of 10 CR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance (PLA-8109) PLA-8107, Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance2024-03-19019 March 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance ML24067A2512024-03-19019 March 2024 Authorized Alternative to Requirements of the ASME Code ML24044A2532024-03-14014 March 2024 Associated Independent Spent Fuel Storage Installation – Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0077 (Security Notifications, Reports, and Recordkeeping & Suspicious Activity Reporting)) IR 05000387/20240112024-02-29029 February 2024 Commercial Grade Dedication Inspection Report 05000387/2024011 and 05000388/2024011 IR 05000387/20230062024-02-28028 February 2024 Annual Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2 (Reports 05000387/2023006 and 05000388/2023006) ML24039A1882024-02-27027 February 2024 Issuance of Amendment Nos. 286 and 270 Changes to Technical Specifications for Control Rods ML24037A3072024-02-22022 February 2024 Summary of Regulatory Audit in Support of Relief Request 5RR-02 PLA-8099, Proof of Financial Protection and Guarantee of Payment of Deferred Premiums (PLA-8099)2024-02-13013 February 2024 Proof of Financial Protection and Guarantee of Payment of Deferred Premiums (PLA-8099) IR 05000387/20230042024-02-0707 February 2024 Integrated Inspection Report 05000387/2023004 and 05000388/2023004 05000387/LER-2023-004, Manual Reactor Scram Due to Degraded Main Condenser Vacuum2024-01-0909 January 2024 Manual Reactor Scram Due to Degraded Main Condenser Vacuum 2024-09-06
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Text
March 4, 2021
SUBJECT:
SUSQUEHANNA STEAM ELECTRIC STATION - UNIT 2 - NRC INVESTIGATION REPORT NO. 1-2020-001 AND NRC INSPECTION REPORT NO.
05000388/2021012
Dear Mr. Berryman:
This letter refers to an investigation conducted by the U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (OI) at the Susquehanna Nuclear, LLC (Susquehanna Nuclear)
Susquehanna Steam Electric Station (SSES). The investigation, which was completed on September 30, 2020, was conducted to evaluate the circumstances of a March 24, 2019 event in which two non-licensed operators (NLOs) entered the SSES Unit 2 drywell, a posted locked high radiation area (LHRA), without the escort or surveillance of a radiation protection technician (RPT), contrary to the requirements of site technical specifications and procedures.
Based on the evidence gathered during the OI investigation, the NRC determined that two Severity Level IV (SL IV) violations of NRC requirements occurred. Specifically, SSES Unit 2 Technical Specification (TS) 5.4.1 states, in part, that written procedures shall be established, implemented, and maintained covering the applicable procedures recommended in Regulatory Guide 1.33, Rev. 2, Appendix A, February 1978, which, in part, recommends radiation protection procedures for access control to radiation areas. The related site procedure RP-180, Radiological Postings, Labelings, and Markings, Step 5.9.5 requires ensuring that a high radiation area is enclosed by a barricade, while step 5.2.2 provides that an RPT may be posted to provide positive control over access to such an area in lieu of the barricade. On March 24, 2019, SSES staff assigned a contract RPT to control access to the Unit 2 drywell, which was posted as a LHRA. However, the RPT left the area unattended and did not ensure the drywell entrance was barricaded. Based on the results of the investigation, the NRC determined that the RPT acted deliberately.
Additionally, SSES Unit 2 TS 5.7.2.d.iii.a states, in part, that for HRAs with dose rates greater than 1.0 rem/hour at 30 cm from the source or from any surface penetrated by the radiation, but less than 500 rads/hour at 1 m from the radiation source or from any surface penetrated by the radiation, each individual entering such an area shall, in part, be under the surveillance (as specified in the Radiation Work Permit (RWP) or equivalent) of an individual qualified in radiation protection (RP) procedures. RWP No. 20192307, DW Operations Activities, requires that constant RP coverage is required when personnel have access to areas 1R/hr or changing radiological conditions. However, on March 24, 2019, while the Unit 2 drywell entrance was unattended, two NLOs operating under RWP No. 20192307 entered the drywell without RP coverage and had access to areas 1R/hr or changing radiological conditions. Based on the results of the NRC investigation, the NRC did not identify deliberate misconduct on the part of the NLOs
The NRC determined that the willful action by the RPT to leave the drywell access area unattended which allowed two NLOs to enter the drywell without the required RP coverage, caused the licensee to violate a license condition by failing to follow SSES Unit 2 technical specifications. The NRC did not identify any separate licensee performance deficiencies. The ROPs significance determination process does not specifically consider willfulness in its assessment of licensee performance. Therefore, it is necessary to address the violations using traditional enforcement to adequately deter non-compliance. In evaluating the severity level of the violations, the NRC considered the examples in the NRC Enforcement Policy and also considered that, absent willfulness, the significance of this unescorted drywell entry would be assessed as green using Inspection Manual Chapter 0609, Appendix C, Occupational Radiation Safety Significance Determination Process. Based on these considerations, the NRC determined that the violations are appropriately categorized at SL IV, which reflects that the issue resulted in relatively inappreciable potential safety consequences.
After considering the factors set forth in Section 2.3.2.a of the Enforcement Policy, these violations are being treated as non-cited violations (NCVs). Namely, the violations were non-repetitive, and the licensee entered the violations into the corrective action program. Further, the licensee restored compliance immediately upon identification. Specifically, upon identifying that the NLOs had entered the drywell without a RP escort, SSES staff retrieved the individuals and evaluated any dose impacts. As identified by the licensee, the NLOs were signed in on the proper RWP and were wearing the appropriate dosimetry. They did not access the highest dose rate areas of the drywell and did not receive dose rate or accumulated dose alarms.
Therefore, the event did not result in unplanned or excess radiation exposure. Additionally, although the violations resulted from the willful actions of the RPT, the NRC considered that they were identified by the licensee, involved the isolated actions of a non-supervisory worker, and resulted in remedial action commensurate with the circumstances (the RPT was removed from the drywell access control duty and is no longer working at SSES).
In accordance with NRC Inspection Manual Chapter 0305, Operating Reactor Assessment Program, Section 13.02.b, the NRC will follow up the violation using Inspection Procedure 92702, Follow-up on Traditional Enforcement Actions Including Violations, Deviations, Confirmatory Action Letters, Confirmatory Orders, and Alternative Dispute Resolution Confirmatory Orders.
You are not required to respond to this letter. However, if you contest the violations or significance of these NCVs, you should provide a response within 30 days of the date of this letter, with the basis for your denial, to the Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington DC 20555-0001, with copies to: (1) the Regional Administrator, Region 1, 2100 Renaissance Boulevard, Suite 100, King of Prussia, PA 19406; (2) the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001; and (3) the NRC Senior Resident Inspector at SSES.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) Section 2.390 of the NRCs Rules of Practice, a copy of this letter will be available electronically for public inspection in the NRC Public Document Room and from the NRCs Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. To the extent possible, your response, if you choose to provide one, should not include any personal privacy or proprietary, information so that it can be made available to the public without redaction.
B. Barryman
Please note that final NRC investigation documents, such as the OI report described above, may be made available to the public under the Freedom of Information Act (FOIA), subject to redaction of information appropriate under the FOIA. Requests under the FOIA should be made in accordance with 10 CFR 9.23, Requests for Records. Additional information is available on the NRC website at http://www.nrc.gov/reading-rm/foia/foia-privacy.html.
This enforcement action will be administratively tracked under NRC Inspection Report No.
05000388/2021012. Should you have any questions regarding this letter, please contact Mr.
Christopher Lally of the NRC staff at Christopher.lally@nrc.gov.
Sincerely, Daniel S. Collins, Director Division of Reactor Projects
Docket Nos. 50-388 License Nos. NPF-22
Enclosure: As described
cc: Distribution via ListServ Daniel S. Collins Digitally signed by Daniel S.
Collins Date: 2021.03.04 10:15:03 -05'00'
SUBJECT: NRC INVESTIGATION REPORT NO. 1-2020-001 AND NRC INSPECTION REPORT NO. 05000388/2021012 Dated March 4, 2021
Distribution:
Public D. Lew, RA R. Lorson, DRA D. Collins, DRP B. Pham, DRP P. Krohn, DRS M. Ferdas, DRS C. Lally, DRP L. Casey, DRP C. Highley, DRP, SRI M. Rossi, DRP, RI D. Hochmuth, DRP, AA D. Screnci / N. Sheehan, PAO J. Weil, OCA B. Klukan, ORA R. McKinley, ORA C. Crisden, ORA D. Garvin, RI D. Tifft, RI Enforcement Coordinators RII, RIII, RIV (M. Kowal, J. Cameron, J. Groom)
T. Steinfeldt, OGC D. Jones, OE M. Haire, RI, OEDO B. Hughes, NRR F. Gore, OI R1ORAMail Resource R1DRPMailResource R1 OE Files (with concurrences)
RidsNrrPMSusquehanna Resource RidsNrrDorlLpl1-2 Resource RidsOEMailCenter Resource ROPreportsResource@nrc.gov DOC NAME: https://usnrc-my.sharepoint.com/personal/mmm3_nrc_gov/Documents/MMM3/Shared Enforcement/Final Actions/SQ LIC LHRA NCV EA-20-131.docx ADAMS Accession Number: ML21005A317 X
SUNSI Review/ MMM
X Non-Sensitive
Sensitive
X Publicly Available
Non-Publicly Available
OFFICE RI/ORA RI/ DRP RI/ORA RI/ ORA OE OGC NAME M McLaughlin/
MMM C Lally via email B Klukan via email R McKinley via email D Jones via email T Steinfeldt NLO via email DATE 1/13/21 1/29/21 2/09/21 2/02/21 2/25/2021 2/25/2021 OFFICE RI/ DRP
NAME D Collins/
DATE 03/02/2021
- See previous concurrence OFFICIAL RECORD