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Category:Letter
MONTHYEARIR 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 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 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 ML23339A1762023-12-0505 December 2023 Notification of NRC Baseline Inspection and Request for Information (05000265/2024001) ML23319A3342023-11-20020 November 2023 Regulatory Audit in Support of License Amendment Requests to Adopt TSTF 505, Revision 2 and 10 CFR 50.69 RS-23-104, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-17017 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000254/20230032023-11-0909 November 2023 Integrated Inspection Report 05000254/2023003 and 05000265/2023003 RS-23-113, Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 262023-10-20020 October 2023 Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 26 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans ML23206A0382023-09-21021 September 2023 Proposed Alternative to the Requirements of the ASME Code IR 05000254/20230112023-09-20020 September 2023 Safety-Conscious Work Environment Issue of Concern Team Inspection Report 05000254/2023011 and 05000265/2023011 RS-23-089, Sixth Ten-Year Interval Inservice Testing Program2023-09-0505 September 2023 Sixth Ten-Year Interval Inservice Testing Program RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs RS-23-086, Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-08-28028 August 2023 Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval SVP-23-038, Owner'S Activity Report Submittal Fifth 10-Year Interval 2023 Refueling Outage Activities2023-08-14014 August 2023 Owner'S Activity Report Submittal Fifth 10-Year Interval 2023 Refueling Outage Activities IR 05000254/20230022023-08-0808 August 2023 Integrated Inspection Report 05000254/2023002 and 05000265/2023002 ML23216A0362023-08-0707 August 2023 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and RFI ML23178A0742023-08-0707 August 2023 Issuance of Amendment Nos. 296 and 292 Adoption of TSTF-416 Low Pressure Coolant Injection (LPCI) Valve Alignment Verification Note Location ML23216A0562023-08-0404 August 2023 Information Meeting (Open House) with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Quad Cities Nuclear Power Station, Units 1 and 2 SVP-23-031, Regulatory Commitment Change Summary Report2023-07-14014 July 2023 Regulatory Commitment Change Summary Report ML23181A1062023-06-30030 June 2023 Postponement- Information Meeting (Open House) with a Question-And-Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Quad Cities Nuclear Power Station ML23179A1932023-06-28028 June 2023 07122023 Letter-Significant Public Meeting to Discuss NRC End-of-Cycle Performance Assessment of Quad Cities Nuclear Plant for Performance for 2022 Calendar Year ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III IR 05000254/20234012023-06-26026 June 2023 Cyber Security Inspection Report 05000254/2023401 and 05000265/2023401 IR 05000265/20230402023-06-22022 June 2023 Reissue Quad Cities Nuclear Power Station 95001 Supplemental Inspection Supplemental Report 05000265/2023040 and Follow Up Assessment Letter RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23167B1722023-06-16016 June 2023 95001 Supplemental Inspection Report 05000265/2023040 and Follow-Up Assessment Letter RS-23-059, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-06-0808 June 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RS-23-060, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2023-06-0808 June 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML23144A3632023-05-26026 May 2023 Information Meeting (Open House) with a Question and Answer Session to Discuss NRC 2022 End-of-Cycle Plant Performance Assessment of Quad Cities Nuclear Power Station, Units 1 and 2 RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling IR 05000254/20234022023-05-15015 May 2023 Security Baseline and ISFSI Inspection Reports 05000254/2023402, 05000265/2023402, 07200053/2023401 ML23033A4042023-05-15015 May 2023 Exemption from the Requirements of 10 CFR Part 2, Section 2.109(B) Related to Submission of Subsequent License Renewal Application Letter ML23132A2022023-05-12012 May 2023 Annual Radiological Environmental Operating Report ML23125A0612023-05-0808 May 2023 Proposed Alternative to the Requirements of the ASME Code IR 05000254/20230012023-05-0808 May 2023 Integrated Report 05000254/2023001 and 05000265/2023001 RS-22-067, 10 CFR 50.46 Annual Report2023-05-0404 May 2023 10 CFR 50.46 Annual Report ML23118A3472023-05-0101 May 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Correction of Amendment No. 193 Adoption of TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration EPID L-2022-LLA-0143 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI SVP-23-018, Radioactive Effluent Release Report for 20222023-04-28028 April 2023 Radioactive Effluent Release Report for 2022 RS-23-068, Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell2023-04-28028 April 2023 Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell ML23110A0622023-04-25025 April 2023 Transmittal of Final Quad Cities Nuclear Power Plant, Unit 1 Accident Sequence Precursor Report (Licensee Event Report 254-2022-001) ML23081A0382023-04-25025 April 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration 2024-02-05
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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 facilitys 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 stations 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 stations 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 Commissions 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 licensees 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 NRCs 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 NRCs 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 N RIII 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