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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 05000387/20230042024-02-0707 February 2024 Integrated Inspection Report 05000387/2023004 and 05000388/2023004 PLA-8096, Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval2024-01-0404 January 2024 Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval PLA-8077, Emergency Plan Revision 67 (PLA-8077)2023-12-27027 December 2023 Emergency Plan Revision 67 (PLA-8077) IR 05000387/20230102023-12-11011 December 2023 Fire Protection Team Inspection Report 05000387/2023010 and 05000388/2023010 PLA-8089, Submittal of Revision to Inservice Testing Program Plan2023-12-0505 December 2023 Submittal of Revision to Inservice Testing Program Plan PLA-8084, Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.22023-11-29029 November 2023 Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.2 ML23345A0682023-11-28028 November 2023 Technical Specification Bases, Manual PLA-8091, Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inseervice Inspection Interval (PLA-8091)2023-11-0808 November 2023 Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inseervice Inspection Interval (PLA-8091) IR 05000387/20230032023-11-0303 November 2023 Integrated Inspection Report 05000387/2023003 and 05000388/2023003 PLA-8082, Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2023-11-0202 November 2023 Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML23291A1132023-10-12012 October 2023 Submittal of Revision 71 to Updated Final Safety Analysis Report and Revision 25 to Fire Protection Review Report ML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23277A0412023-10-0505 October 2023 Notification of Commercial Grade Dedication Inspection (05000387/2024011 and 05000388/2024011) and Request for Information IR 05000387/20233012023-09-20020 September 2023 Initial Operator Licensing Examination Report 05000387/2023301 and 05000388/2023301 ML23254A0242023-09-0606 September 2023 Paragon Energy Solutions LLC, Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) IR 05000387/20230052023-08-31031 August 2023 Updated Inspection Plan for Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2023005 and 05000388/2023005) ML23228A1952023-08-21021 August 2023 Summary of August 10, 2023, Public Observation Meeting Re. Proposed Alternative PLA-8080, Proposed Relief for Valve 251130 (PLA-8080)2023-08-14014 August 2023 Proposed Relief for Valve 251130 (PLA-8080) PLA-8074, Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval2023-08-0303 August 2023 Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval IR 05000387/20230022023-08-0101 August 2023 Integrated Inspection Report 05000387/2023002 and 05000388/2023002 ML23195A1852023-07-27027 July 2023 Correction to Technical Specifications Page 3.3-73 in Amendment No. 265 PLA-8076, Unit 2 - 21st Refueling Outage Owner'S Activity Report (PLA-8076)2023-07-20020 July 2023 Unit 2 - 21st Refueling Outage Owner'S Activity Report (PLA-8076) ML23201A0152023-07-20020 July 2023 Operator Licensing Examination Approval ML23200A1012023-07-19019 July 2023 Notification of Conduct of a Fire Protection Team Inspection ML23193A0062023-07-12012 July 2023 Requalification Program Inspection PLA-8078, Submittal of Unit 2 Cycle 22 Core Operating Limits Report, Revision 1, PLA-80782023-07-0505 July 2023 Submittal of Unit 2 Cycle 22 Core Operating Limits Report, Revision 1, PLA-8078 ML23163A1012023-06-12012 June 2023 10 CFR 50.46 Annual Report (Pla 8065) PLA-8054, Proposed Amendment to Licenses NPF-14 and NPF-22: Remove Control Rod Operability Separation Criteria and Replace Reference to Banked Position Withdrawal Sequence with the Analyzed Rod Position Sequence2023-06-0808 June 2023 Proposed Amendment to Licenses NPF-14 and NPF-22: Remove Control Rod Operability Separation Criteria and Replace Reference to Banked Position Withdrawal Sequence with the Analyzed Rod Position Sequence IR 05000387/20234012023-06-0707 June 2023 Security Baseline Inspection Report 05000387/2023401 and 05000388/2023401 PLA-8073, Proposed Relief Request for the Fifth 10-Year Inservice Inspection Interval2023-06-0101 June 2023 Proposed Relief Request for the Fifth 10-Year Inservice Inspection Interval PLA-8064, Response to NRC Regulatory Issue Summary 2023-01 (PLA-8064)2023-05-17017 May 2023 Response to NRC Regulatory Issue Summary 2023-01 (PLA-8064) ML23132A3212023-05-17017 May 2023 Associated Independent Spent Fuel Storage Installation - Issuance of Amendment Nos. 285 and 269 Related to Order Approving Transfer of Licenses PLA-8067, Notification of Completion of Emergence from Bankruptcy (PLA-8067)2023-05-17017 May 2023 Notification of Completion of Emergence from Bankruptcy (PLA-8067) IR 05000387/20230012023-05-12012 May 2023 Integrated Inspection Report 05000387/2023001 and 05000388/2023001 PLA-8066, Notification of Planned Closing Date and Information Identified in March 30, 2023 Order, PLA-80662023-05-0808 May 2023 Notification of Planned Closing Date and Information Identified in March 30, 2023 Order, PLA-8066 PLA-8053, Radiation Exposure Information and Reporting System2023-04-27027 April 2023 Radiation Exposure Information and Reporting System PLA-8058, Annual Radiological Environmental Operating Report (PLA-8058)2023-04-26026 April 2023 Annual Radiological Environmental Operating Report (PLA-8058) PLA-8041, Radioactive Effluent Release Report and Offsite Dose Calculation Manual (PLA-8041)2023-04-25025 April 2023 Radioactive Effluent Release Report and Offsite Dose Calculation Manual (PLA-8041) PLA-8047, 2022 Annual Environmental Operating Report (Nonradiological), PLA-80472023-04-19019 April 2023 2022 Annual Environmental Operating Report (Nonradiological), PLA-8047 PLA-8062, Supplement to Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 252F007B, PLA-80622023-04-11011 April 2023 Supplement to Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 252F007B, PLA-8062 PLA-8061, Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 25F007B, PLA-80612023-04-10010 April 2023 Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 25F007B, PLA-8061 ML23090A2302023-03-31031 March 2023 NRC Decommissioning Funding Status Report PLA-8049 PLA-8060, Submittal of Unit 2 Cycle 22 Core Operating Limits Report (PLA-8060)2023-03-30030 March 2023 Submittal of Unit 2 Cycle 22 Core Operating Limits Report (PLA-8060) ML23095A0572023-03-29029 March 2023 NRC Decommissioning Funding Status Report December 31, 2022 PLA-8057, Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments- Supplemental Information, PLA-80572023-03-15015 March 2023 Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments- Supplemental Information, PLA-8057 ML23065A1962023-03-0202 March 2023 EN 56387 Paragon - Part 21 Report Re Defect Identified in Automatic Transfer Switch Pn: NLI-ATS480A400X1 IR 05000387/20220062023-03-0101 March 2023 Annual Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2 (Reports 05000387/2022006 and 05000388/2022006) PLA-8052, (Sses), Proof of Financial Protection and Guarantee of Payment of Deferred Premiums2023-02-13013 February 2023 (Sses), Proof of Financial Protection and Guarantee of Payment of Deferred Premiums IR 05000387/20220042023-02-0808 February 2023 Integrated Inspection Report 05000387/2022004 and 05000388/2022004 ML23010A0882023-01-15015 January 2023 Summary of Regulatory Audit in Support of License Amendment Request to Revise Control Rod Technical Specifications 2024-02-07
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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 3 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, Digitally signed by Daniel S.
Daniel S. Collins Collins Date: 2021.03.04 10:15:03 -05'00'
Daniel S. Collins, Director Division of Reactor Projects Docket Nos. 50-388 License Nos. NPF-22 Enclosure: As described cc: Distribution via ListServ
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 Non-Sensitive X Publicly Available X SUNSI Review/ MMM Non-Publicly Available Sensitive OFFICE RI/ORA RI/ DRP RI/ORA RI/ ORA OE OGC M McLaughlin/ R McKinley via D Jones via T Steinfeldt NAME C Lally via email B Klukan via email MMM email email 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