|
---|
Category:Letter
MONTHYEARSVP-24-054, Deviation from BWR Vessel and Internals Project (BWRVIP) Guidelines - Inspection of Top Guide Rim Welds2024-09-11011 September 2024 Deviation from BWR Vessel and Internals Project (BWRVIP) Guidelines - Inspection of Top Guide Rim Welds 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 IR 05000254/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Quad Cities Nuclear Power Station (Report 05000254/2024005; 05000265/2024005) RS-24-078, Alternative Request RV-08, Revision 1, Associated with Safety Relief Valve Testing Interval2024-08-20020 August 2024 Alternative Request RV-08, Revision 1, Associated with Safety Relief Valve Testing Interval ML24183A1082024-08-0808 August 2024 – Issuance of Amendment Nos. 302 and 298 Adoption of Tstf-505, Provide Risk Informed Extended Completion Times – RITSTF Initiative 4b SVP-24-049, Owners Activity Report Submittal Sixth 10-Year Interval 2024 Refueling Outage Activities2024-08-0707 August 2024 Owners Activity Report Submittal Sixth 10-Year Interval 2024 Refueling Outage Activities IR 05000254/20243012024-08-0101 August 2024 NRC Initial License Examination Report 05000254/2024301; 05000265/2024301 SVP-24-048, Registration of Use of Casks to Store Spent Fuel2024-07-31031 July 2024 Registration of Use of Casks to Store Spent Fuel RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions SVP-24-043, Registration of Use of Casks to Store Spent Fuel2024-07-0505 July 2024 Registration of Use of Casks to Store Spent Fuel SVP-24-041, Regulatory Commitment Change Summary Report2024-07-0505 July 2024 Regulatory Commitment Change Summary Report ML24162A0982024-07-0303 July 2024 – Issuance of Amendment Nos. 301 and 297 Adoption of 10 CFR 50.69 “Risk Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors” SVP-24-040, Registration of Use of Casks to Store Spent Fuel2024-06-25025 June 2024 Registration of Use of Casks to Store Spent Fuel RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations SVP-24-039, Ile Post Exam Package Letter2024-06-12012 June 2024 Ile Post Exam Package Letter RS-24-053, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed2024-06-0606 June 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed ML24110A0492024-05-28028 May 2024 Audit Report Related to the TSTF-505 and 10 CFR 50.59 Amendments ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 ML24142A3352024-05-21021 May 2024 Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes ML24141A2102024-05-20020 May 2024 Operator Licensing Examination Approval - Quad Cities Nuclear Power Station, May 2024 RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report IR 05000254/20240012024-05-14014 May 2024 Integrated Inspection Report Nos. 05000254/2024001 and 05000265/2024001 RS-24-042, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion2024-05-10010 May 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion SVP-24-034, Annual Radiological Environmental Operating Report2024-05-10010 May 2024 Annual Radiological Environmental Operating Report RS-24-046, 10 CFR 50.46 Annual Report2024-05-0606 May 2024 10 CFR 50.46 Annual Report ML24109A0662024-05-0202 May 2024 – Relief Request I5R-26, Revision 0 RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests SVP-24-029, Radioactive Effluent Release Report for 20232024-04-26026 April 2024 Radioactive Effluent Release Report for 2023 SVP-24-028, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2024-04-26026 April 2024 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report ML24114A1712024-04-23023 April 2024 State of Illinois (IEMA-OHS) Comment Quad Cities HI-STORM Exemption Environmental Assessment SVP-24-024, Corrected Radioactive Effluent Release Report for 20222024-04-0505 April 2024 Corrected Radioactive Effluent Release Report for 2022 IR 05000254/20245012024-04-0505 April 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000254/2024501 and 05000265/2024501 RS-24-032, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion2024-04-0505 April 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report SVP-24-023, Ile Outline Submittal Letter2024-03-29029 March 2024 Ile Outline Submittal Letter RS-24-019, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Completion Times TSTF2024-03-19019 March 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Completion Times TSTF RS-24-020, Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Quad Cities Nuclear Power Station - Holtec MPC-68MCBS2024-03-15015 March 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Quad Cities Nuclear Power Station - Holtec MPC-68MCBS SVP-24-018, Ile Proposed Exam Submittal Letter2024-03-13013 March 2024 Ile Proposed Exam Submittal Letter RS-24-015, Submittal of RP-01 Relief Request Associated with the Sixth Inservice Testing Interval2024-02-29029 February 2024 Submittal of RP-01 Relief Request Associated with the Sixth Inservice Testing Interval IR 05000254/20230062024-02-28028 February 2024 Annual Assessment Letter for Quad Cities Nuclear Power Station, Units 1 and 2 (Report 05000254/2023006 and 05000265/2023006) ML24053A1192024-02-22022 February 2024 Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000265/2024010 and 05000254/2024010 IR 05000254/20230042024-02-0505 February 2024 Integrated Inspection Report 05000254/2023004 and 05000265/2023004 ML24004A0052024-01-17017 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0042 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) RS-24-001, Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2024-01-0303 January 2024 Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval IR 05000254/20234032023-12-22022 December 2023 Public- Quad Cities Nuclear Power Station Security Baseline Inspection Report 05000254/2023403 and 05000265/2023403 IR 05000254/20230102023-12-20020 December 2023 Comprehensive Engineering Team Inspection Report 05000254/2023010 and 05000265/2023010 ML23349A1622023-12-17017 December 2023 Issuance of Amendment Nos. 298 and 294 Increase Completion Time in Technical Specification 3.8.1.B.4 (Emergency Circumstances) RS-23-128, Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-15015 December 2023 Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days RS-23-123, Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-13013 December 2023 Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 2024-09-04
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION LISLE, IL 60532-4352 April 13, 2011
Mr. Kevin B. Cravens [HOME ADDRESS DELETED UNDER 10 CFR 2.390]
SUBJECT:
POSITIVE FITNESS-FOR-DUTY EVENT NOTIFICATION
Dear Mr. Cravens:
This letter refers to an Event Notification (EN45269) made by Exelon Generation Company, LLC, (Quad Cities Generating Station) on August 17, 2009, to the U.S. Nuclear Regulatory Commission (NRC). The event notification was to inform the NRC that you had tested positive for alcohol during a random breathalyzer Fitness-for-Duty (FFD) test conducted on that date while you were inside the protected area of the Quad Cities Nuclear Generating Station. The NRC received additional information from Exelon, dated September 11, 2009, about your confirmed positive FFD test for alcohol and the subsequent actions that were taken.
Based on confirmed positive test results for alcohol and being an NRC licensed operator, the NRC evaluated the circumstances of your actions for enforcement consideration. Title 10 CFR 55.53 (j) states, in part, that a licensee (licensed operator) shall not perform activities authorized by a license while under the influence of alcohol that could adversely affect his ability to safely and competently perform his licensed duties. We understand that at the time of your positive test your operator license was inactive and you were assigned to a plant position where activities authorized by your license were not being performed. Your random FFD test for alcohol exceeded the facility's allowed cutoff level pursuant to 10 CFR Part 26, "Fitness-for-Duty Programs." Although your license was inactive, at the time, as a licensed operator and a supervisor, your actions with respect to being in the plant under the influence of alcohol represented an impairment that may have impacted safety. The NRC takes the safe operation of nuclear power plants very seriously, as operational errors of the station's controls caused by personnel under the influence of drugs or alcohol may impact the health and safety of the general public. Had your license been active and you were called upon to exercise the authority of your license to perform licensed duties under the influence of alcohol, a significant violation of 10 CFR 55.53(j) would have occurred.
The NRC holds Licensed Operators to a higher standard than other persons holding unescorted access to a nuclear power plant because of the nature of their responsibilities. Title 10 CFR 26.4(a)(1) specifically states, in part, that personnel who operate or direct the operation of risk-significant plant equipment are subject to the station's FFD program. Furthermore, 10 CFR 55.53(k) specifically requires licensed operators to participate in the drug and alcohol testing program established pursuant to 10 CFR Part 26. The purpose of the Commission's FFD requirements is to provide reasonable assurance that nuclear power plant personnel work in an environment that is free of drugs and alcohol and the effects of the use of these substances.
The use of alcohol such that an operator exceeds the cutoff limits specified in 10 CFR Part 26, Appendix A, or in the licensee's FFD program, is a serious matter.
K. Cravens Title 10 CFR 55.61(b)(5) states, in part that, "Any license may be revoked, suspended, or modified, in whole or in part: For the sale, use or possession of illegal drugs, or refusal to participate in the facility drug and alcohol testing program, or a confirmed positive test for drugs, drug metabolites, or alcohol in violation of the conditions and cut-off levels established by §55.53(j)." However, taking into account that, at the time of testing, your license was inactive and that you were not directly performing duties or had responsibilities with respect to your senior operator license, the NRC concluded that no violation of 10 CFR 55.53(j) had occurred. Therefore, no action will be taken against your operator license at this time, and no response to this letter is required. However, you should be aware that NRC may take action against your license in the future if you test positive for alcohol while occupying a control room watchstation, or if you are found performing licensed duties unfit as a result of the consumption of alcoholic beverages as noted above from 10 CFR 55.61(b)(5). A copy of this letter will be placed in your 10 CFR Part 55 docket file.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter with your home address removed will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of the NRC's Agency wide Documents Access and Management System (ADAMS). ADAMS is accessible from the Electronic Reading Room page of the NRC's public Web site at http://www.nrc.gov/reading-rm/adams.html.
Should you have any questions concerning this action, please contact Mr. Hironori Peterson of my staff. Mr. Peterson can be reached at either the address listed above or 630-829-9707.
Sincerely, /RA by Gary Shear Acting For/
Steven A. Reynolds, Director Division of Reactor Safety Docket No. 55-32004 License No. SOP-31281 cc: R. Gideon, Site Vice President K. Moser, Training Manager CERTIFIED MAIL
K. Cravens Title 10 CFR 55.61(b)(5) states, in part that, "Any license may be revoked, suspended, or modified, in whole or in part: For the sale, use or possession of illegal drugs, or refusal to participate in the facility drug and alcohol testing program, or a confirmed positive test for drugs, drug metabolites, or alcohol in violation of the conditions and cut-off levels established by §55.53(j)." However, taking into account that, at the time of testing, your license was inactive and that you were not directly performing duties or had responsibilities with respect to your senior operator license, the NRC concluded that no violation of 10 CFR 55.53(j) had occurred. Therefore, no action will be taken against your operator license at this time, and no response to this letter is required. However, you should be aware that NRC may take action against your license in the future if you test positive for alcohol while occupying a control room watchstation, or if you are found performing licensed duties unfit as a result of the consumption of alcoholic beverages as noted above from 10 CFR 55.61(b)(5). A copy of this letter will be placed in your 10 CFR Part 55 docket file.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter with your home address removed will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of the NRC's Agency wide Documents Access and Management System (ADAMS). ADAMS is accessible from the Electronic Reading Room page of the NRC's public Web site at http://www.nrc.gov/reading-rm/adams.html.
Should you have any questions concerning this action, please contact Mr. Hironori Peterson of my staff. Mr. Peterson can be reached at either the address listed above or 630-829-9707.
Sincerely, /RA by Gary Shear Acting For/
Steven A. Reynolds, Director Division of Reactor Safety Docket No. 55-32004 License No. SOP-31281
cc: R. Gideon, Site Vice President K. Moser, Training Manager CERTIFIED MAIL DOCUMENT NAME: G:\DRSIII\DRS\Work in Progress\4-QUAD CITIES Positive FFD With No Violation 2011 final REV 1.docx Publicly Available Non-Publicly Available Sensitive Non-Sensitive To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy OFFICE RIII N RIII NRIII N RIII N NAME HPeterson:jb SOrth JHeck GShear for SReynolds DATE 03/28/11 04/06/11 04/06/11 04/13/11 OFFICIAL RECORD COPY