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Category:Letter
MONTHYEARRS-24-098, Units 1 and 2 - Supplement to License Amendment Request to Revise Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel Assembly Storage, 4.3.1, Fuel Storage, Criticality2024-10-23023 October 2024 Units 1 and 2 - Supplement to License Amendment Request to Revise Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel Assembly Storage, 4.3.1, Fuel Storage, Criticality ML24291A0012024-10-17017 October 2024 Submittal of Core Operating Limits Report, Cycle 25 RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - 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 RS-24-095, Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals2024-10-10010 October 2024 Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24263A1272024-09-23023 September 2024 – Request for Additional Information (EPID 2023-LLA-0136) - Non-Proprietary IR 05000456/20240112024-09-12012 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000456/2024011 and 05000457/2024011 ML24164A0032024-09-10010 September 2024 Issuance of Amendment Nos. 235 and 235 Revision of Technical Specifications for the Ultimate Heat Sink ML24227A0522024-08-29029 August 2024 Audit Plan for LAR to Remove ATWS Mtc Limit IR 05000456/20240052024-08-29029 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2024005 and 05000457/2024005) ML24225A1112024-08-13013 August 2024 Notification of NRC Fire Protection Team Inspection Request for Information ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000456/20240022024-08-0808 August 2024 Integrated Inspection Report 05000456/2024002 and 05000457/2024002 ML24172A1252024-07-26026 July 2024 Environmental Assessment and Finding of No Significant Impact Related to a Requested Increase in Ultimate Heat Sink Temperature (EPID L-2024-LLA-0075) - Transmittal Letter ML24179A3262024-07-23023 July 2024 LTR - Constellation - SG Welds and Nozzles (L-2023-LLR-0053, L-2023-LLR-0054, L-2023-LLR-0055, L-2023-LLR-0056) ML24163A3922024-06-25025 June 2024 Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, & Opportunity for a Hearing (EPID L-2024-LLA-0075)- Letter 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 ML24164A2132024-06-13013 June 2024 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Braidwood Nuclear Plant RS-24-057, License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink2024-06-0404 June 2024 License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink IR 05000456/20240102024-05-31031 May 2024 License Renewal Phase 1 Report 05000456/2024010 RS-24-044, License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed2024-05-28028 May 2024 License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed RS-24-043, Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications2024-05-24024 May 2024 Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications 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 RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report ML24136A0132024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report ML24136A2452024-05-15015 May 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000457/2024004 ML24128A1212024-05-0707 May 2024 Response to Braidwood and Dresden FOF Dates Change Request (2025) ML24122A6522024-05-0101 May 2024 Submittal of 2023 Annual Radioactive Effluent Release Report 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 IR 05000456/20243012024-04-29029 April 2024 NRC Initial License Examination Report 05000456/2024301; 05000457/2024301 ML24116A0052024-04-25025 April 2024 Transmittal of Braidwood Station, Unit 1, Core Operating Limits Report, Braidwood Unit 1 Cycle 25 RS-24-026, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR)2024-04-25025 April 2024 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR) IR 05000456/20240012024-04-24024 April 2024 Integrated Inspection Report 05000456/2024001 and 05000457/2024001 ML24113A1272024-04-22022 April 2024 Audit Plan in Support of Review of LAR Revision of TS 3.7.15, 3.7.16, and 4.3.1 (EPID: L-2023-LLA-0136) (Non-Proprietary) IR 05000457/20240902024-04-19019 April 2024 Final Significance Determination for 2b Auxiliary Feedwater Pump Diesel Engine Fuel Oil Dilution Issue - NRC Inspection Report 05000457/2024090 ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition RS-24-034, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-04-10010 April 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML24094A2692024-04-0303 April 2024 Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Report, WCAP-17451-P, Revision 2, Reactor Internals Guide Tube Wear Westinghouse Domestic Fleet Operational Projections 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 ML24057A0372024-03-26026 March 2024 Proposed Alternative from Certain Requirements Contained in the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI RS-24-024, Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2024-03-22022 March 2024 Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds ML24067A3252024-03-0707 March 2024 U.S. Department of Energy, Office of Legacy Management, 2023 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites ML24066A0122024-03-0606 March 2024 Operator Licensing Examination Approval Braidwood Station, Units 1 and 2, March 2024 IR 05000456/20244012024-03-0505 March 2024 Cyber Security Inspection Report 05000456/2024401 and 05000457/2024401 (Public) IR 05000456/20230062024-02-28028 February 2024 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2023006 and 05000457/2023006) ML24057A3022024-02-26026 February 2024 Regulatory Conference Supplemental Information ML24047A2382024-02-20020 February 2024 Regulatory Conference to Discuss Risk Associated with 2b Auxiliary Feedwater Pump Diesel Engine Fuel Oil Leak RS-24-013, Response to Request for Additional Information Regarding Proposed Alternative to Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-02-13013 February 2024 Response to Request for Additional Information Regarding Proposed Alternative to Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators IR 05000456/20230042024-02-0202 February 2024 Integrated Inspection Report 05000456/2023004 and 05000457/2023004 2024-09-23
[Table view] Category:Notice of Violation
MONTHYEARML14105A3382014-05-0101 May 2014 Sliv Notice of Violation IR 05000456/20130082013-11-14014 November 2013 IR 05000456-13-008; 050000457-13-008; 09/09/2013 - 10/29/2013; Braidwood Station, Inservice Inspection ML12314A0832012-11-0808 November 2012 Nuclear Regulatory Commission Integrated Inspection Report 05000456-12-004; 05000457-12-004 and Notice of Violation IR 05000456/20120082012-09-24024 September 2012 IR 05000456-12-008, 05000457-12-008; 07/25/2012 ?09/07/2012; Braidwood Station, Units 1 and 2; Routine Triennial Fire Protection Baseline Inspection and Notice of Violation ML12269A1882012-09-24024 September 2012 IR 05000456-12-008, 05000457-12-008; 07/25/2012 ?09/07/2012; Braidwood Station, Units 1 and 2; Routine Triennial Fire Protection Baseline Inspection and Notice of Violation ML1106009032011-02-28028 February 2011 IR 05000456-10-503, 05000457-10-503; on 06/16/2010 - 02/10/2011; Braidwood Station, Units 1 & 2; Results of NRC Emergency Action Level and Emergency Plan Changes Inspection and Follow-up of Unresolved Item 05000456-09-005-07; 05000457-09-00 IR 05000456/20100082010-02-25025 February 2010 EA-09-259, Braidwood Nuclear Power Station, Unit 1, Final Significance Determination for a White Finding; Notification of Follow-up Assessment; and Notice of Violation; NRC Inspection Report No. 05000456/2010008 ML0712201272007-05-0101 May 2007 IA-07-015, Hess, Notice of Violation IR 05000456/20060122006-06-29029 June 2006 EA-06-081, Braidwood Nuclear Power Plant, Units 1 and 2; Final Significance Determination for a White Finding and Notice of Violation (NRC Inspection Report Nos. 05000456/2006012; 05000457/2006012) ML0618100132006-06-29029 June 2006 EA-06-081, Braidwood Nuclear Power Plant, Units 1 and 2; Final Significance Determination for a White Finding and Notice of Violation (NRC Inspection Report Nos. 05000456/2006012; 05000457/2006012) ML0610107442005-12-19019 December 2005 NRC E-mail from Steven Orth to Braidwood Communications Team Bwd IEPA Violation ML0610107002005-12-16016 December 2005 Illinois Environmental Protection Agency Ltr to Exelon - Violation Notice W-2005-00537 ML1017302052005-12-16016 December 2005 Ltr from M. Garretson to J. Petro Violation Notice Exelon Generation - Braidwood Station Violation Notice No. W-2005-00537 IR 05000456/20020032002-07-23023 July 2002 IR 05000456-02-003, IR 05000457-02-003, on 02/04/2002 -02/22/2002, Braidwood Station Units 1 & 2. NOV - Final Significance Determination for White Finding 2014-05-01
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Text
May 1, 2007 IA-07-015 Michael R. Hess
[HOME ADDRESS DELETED UNDER 10 CFR 2.390]
SUBJECT:
NOTICE OF VIOLATION
Dear Mr. Hess:
The Nuclear Regulatory Commission (NRC) has received a letter dated March 7, 2007, from the Braidwood Station, operated by Exelon Nuclear, informing us of your confirmed positive test for an illegal drug, marijuana. This letter will be placed in your 10 CFR Part 55 docket file.
This confirmed positive test identified a violation of 10 CFR 55.53, Conditions of Licenses and Exelon Nuclears Fitness-for-Duty Program, which is required by 10 CFR 26.20. The purpose of the Commission's Fitness-for-Duty (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 illegal drugs is a serious matter which undermines the special trust and confidence placed in you as a licensed operator. Therefore, the violation is categorized at Severity Level III in accordance with the NRC Enforcement Policy because the use of illegal drugs by licensed operators is a significant regulatory concern. This violation is described in the enclosed Notice of Violation (Notice). Please note that, in accordance with 10 CFR 26.27(b), future similar violations will substantially affect your authorization for unescorted access to the protected area of a licensed facility.
The purpose of this letter is to make clear to you the consequences of your violation of NRC requirements governing FFD as a licensed operator. You are required to respond to this letter and should follow the instructions specified in the enclosed Notice when preparing your response. In your response, you should document the specific actions taken and any additional actions you plan to prevent recurrence in order to ensure your ability and willingness to carry out the special trust and confidence placed in you as a licensed operator of a nuclear power facility. After reviewing your response to this Notice, including your proposed corrective actions, the NRC will determine whether further NRC enforcement action is necessary to ensure compliance with NRC regulatory requirements.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," Part 2, Title 10 of the Code of Federal Regulations, enforcement actions are made available electronically for public inspection in the NRC Public Document Room or from the NRCs document system (ADAMS),
accessible from the NRC Web site at www.nrc.gov. A copy of this letter and the enclosed
M. Hess Notice of Violation with your address removed will be made available to the Public after 45 days unless you provide a sufficient basis to withdraw this violation. The NRC also includes significant enforcement actions on its Web site at www.nrc.gov. In addition, this letter will be maintained by the Office of Enforcement in an NRC Privacy Act system of records, NRC-3, Enforcement Actions Against Individuals. The NRC-3 system notice, which provides detailed information about this system of records, can also be accessed from the NRC Web site at www.nrc.gov.
Should you have any questions concerning this action, please contact Hironori Peterson, Chief Operations Branch. Mr. Peterson can be reached at either the address listed above or at telephone number (630) 829-9707.
Sincerely,
/RA by Anne T. Boland Acting for/
Cynthia D. Pederson, Director Division of Reactor Safety Docket No. 55-31018 License No. OP-30480-4
Enclosure:
Notice of Violation cc w/encl: Christopher M. Crane President and Chief Nuclear Officer Exelon Nuclear CERTIFIED MAIL RETURN RECEIPT REQUESTED FILE NAME: G:\EICS\07-072 - SLIII - Braidwood Operator FFD.wpd W Publicly Available G Non-Publicly Available G Sensitive W Non-Sensitive To receive a copy of this document, indicate in the box: "C" = Copy w/o att/encl "E" = Copy w/att/encl "N" = No copy OFFICE RIII E OGC1 E D:OE2 E RIII N RIII E NAME Weil Jones Carpenter OBrien Boland for Pederson DATE 04/30/07 04/19/07 04/30/07 05/01/07 05/01/07 OFFICIAL RECORD COPY 1
No legal objection received from G. Longo, in 04/19/2007 e-mail to C. Weil, RIII.
2 HQ concurrence received by e-mail from David Solorio, OE, on 04/30/2007.
Letter from C. Pederson to M. Hess dated May 1, 2007
SUBJECT:
NOTICE OF VIOLATION DISTRIBUTION:
ADAMS (PARS) NOT FOR PUBLIC RELEASE UNTIL 45 DAYS FROM THE SECY DATE THIS LETTER UNLESS APPROVED EARLIER BY THE OCA DIRECTOR, OFFICE OF ENFORCEMENT L. Reyes, EDO W. Kane, DEDR C. Carpenter, OE D. Solorio, OE M. Burrell, OE D. Starkey, OE J. Caldwell, RIII G. Grant, RIII C. Pederson, RIII M. Satorius, RIII A. Boland, RIII S. West, RIII L. Chandler, OGC B. Jones, OGC J. Dyer, NRR D. Holody, Enforcement Officer, RI C. Evans, Enforcement Officer, RII K. OBrien, Enforcement Officer, RIII K. Fuller, Enforcement Officer, RIV R. Pascarelli, Enforcement Coordinator, NRR S. Imboden, Enforcement Coordinator, NRR D. Furst, Enforcement Contact, NSIR E. Brenner, OPA H. Bell, OIG H. Peterson, RIII R. Skokowski, RIII S. Ray, RIII C. Weil, RIII RIII:PA R. Lickus, RIII J. Lynch, RIII J. Kweiser, RIII OEWEB OEMAIL State of Illinois
NOTICE OF VIOLATION Michael R. Hess Docket No. 55-31018
[HOME ADDRESS DELETED License No. OP-30480-4 UNDER 10 CFR 2.390] IA-07-015 As a result of a notification from the Braidwood Station, operated by Exelon Nuclear, dated March 7, 2007, a violation of NRC requirements was identified. In accordance with the NRC Enforcement Policy, the violation is listed below:
10 CFR 55.53(d) provides that operator and senior operator licenses are subject to, and the licensee shall observe, all applicable rules, regulations and orders of the Commission.
10 CFR 26.20(a) provides, in part, that each nuclear power plant licensee subject to 10 CFR Part 26 shall establish and implement written policies and procedures designed to meet the general performance objectives and specific requirements of 10 CFR Part 26, and include an overall description of the licensees fitness-for-duty (FFD) policy which must address use of illegal drugs.
Exelon Nuclear Procedure No. SY-AA-102, Revision 10, dated January 10, 2007, Exelons Nuclear Fitness-for-Duty Program, implements 10 CFR Part 26.
Section 4.4.2, Cut-Off Levels for Exelon Fitness-for-Duty Program, of Exelon Procedure SY-AA-102 provides, in part, that the cut-off level for certain substances including cannabinoids (marijuana) has been set at 15 ng/ml for a confirmatory FFD test.
10 CFR 26.27(b)(2) provides, in part, that lacking any other evidence to indicate the use, sale, or possession of illegal drugs onsite, a confirmed positive test result must be presumed to be an indication of offsite drug use.
10 CFR 55.53(j), provides, in part, that a reactor operator or a senior reactor operator licensee shall not use, possess, or sell any illegal drugs.
Contrary to the above, on January 26, 2007, you reported for duty at the Braidwood Station, operated by Exelon Nuclear, after having used an illegal substance, marijuana.
Specifically, on January 26, 2007, Exelon Nuclear required you to submit a specimen for a random FFD test. Initial analysis of your specimen indicated the presence of marijuana. Exelon Nuclear subsequently submitted your January 26, 2007, specimen to a laboratory for confirmatory testing and the results of the confirmatory testing were reported to Exelon Nuclear on January 29, 2007. The confirmatory laboratory testing indicated that marijuana (36 ng/ml) was present in your specimen, which exceeded the 15 ng/ml cut-off level for confirmatory testing of marijuana established in Section 4.4.2 of Exelon Nuclear Procedure SY-AA-102.
This is a Severity Level III Violation (Supplements I and VII).
Notice of Violation Pursuant to the provisions of 10 CFR 2.201, Michael R. Hess (Licensee) is hereby required to submit a written statement or explanation to the U.S. Nuclear Regulatory Commission, ATTN: Regional Administrator, Region III, 2443 Warrenville Road, Suite 210, Lisle, IL 60532-4352, with a copy to the Enforcement Officer at the same address, and marked "Open by Addressee Only" and a copy to the NRC Resident Inspector at the Braidwood Station, with a similar marking within 30 days of the date of the letter transmitting this Notice of Violation (Notice). This reply should be clearly marked as a "Reply to a Notice of Violation; IA-07-015," and should include for each violation: (1) the reason for the violation, or, if contested, the basis for disputing the violation, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved. If an adequate reply is not received within the time specified in this Notice, an Order or a Demand for Information may be issued as to why the license should not be modified, suspended, or revoked, or why such other action as may be proper should not be taken. Where good cause is shown, consideration will be given to extending the response time.
If you contest this enforcement action, you should also provide a copy of your response, with the basis for your denial, to the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001.
Because your response will be made available electronically for public inspection in the NRC Public Document Room or from the NRCs document system (ADAMS), accessible from the NRC Web site at www.nrc.gov, to the extent possible, it should not include any personal privacy, proprietary, or safeguards information so that it can be made available to the public without redaction. If personal privacy or proprietary information is necessary to provide an acceptable response, then please provide a bracketed copy of your response that identifies the information that should be protected and a redacted copy of your response that deletes such information. If you request withholding of such material, you must specifically identify the portions of your response that you seek to have withheld and provide in detail the bases for your claim of withholding (e.g., explain why the disclosure of information will create an unwarranted invasion of personal privacy or provide the information required by 10 CFR 2.390(b) to support a request for withholding confidential commercial or financial information). If safeguards information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21. In addition, this letter will be maintained by the Office of Enforcement in an NRC Privacy Act system of records, NRC-3, Enforcement Actions Against Individuals. The NRC-3 system notice, which provides detailed information about this system of records, can be accessed from the NRC Web site at www.nrc.gov.
Dated this 1st day of May 2007