|
---|
Category:Letter
MONTHYEARIR 05000456/20230042024-02-0202 February 2024 Integrated Inspection Report 05000456/2023004 and 05000457/2023004 ML24025C7242024-01-29029 January 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000456/2024002; 05000457/2024002 IR 05000457/20230112024-01-25025 January 2024 2B Auxiliary Feedwater Pump Diesel Fuel Oil Dilution Report 05000457/2023011 and Preliminary Greater than Green Finding and Apparent Violation ML24018A0362024-01-17017 January 2024 Paragon Energy Solutions, Defect with Detroit Diesel/Mtu Fuel Injectors P/N R5229660 Cat Id 0001390618 RS-24-004, Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-01-11011 January 2024 Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators ML23348A2162023-12-15015 December 2023 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0030 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000456/20200232023-12-15015 December 2023 Baseline Security Inspection Document; 05000456/2023/402; 05000457/2023/402 ML23277A0032023-12-11011 December 2023 Issuance of Amendments Regarding Adoption of TSTF-370 ML23339A0452023-12-0505 December 2023 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000546/2024010 ML23313A1552023-12-0101 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report ML23331A8922023-11-22022 November 2023 Supplement - Braidwood Security Rule Exemption Request ISFSI Docket No. Reference ML23321A0442023-11-17017 November 2023 Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline 05000457/LER-2023-001, Submittal of LER 2023-001-00 for Braidwood Station, Unit 2, Train B Auxiliary Feedwater Pump Was Inoperable Due to Degraded Oil in the Crank Case2023-11-17017 November 2023 Submittal of LER 2023-001-00 for Braidwood Station, Unit 2, Train B Auxiliary Feedwater Pump Was Inoperable Due to Degraded Oil in the Crank Case RS-23-118, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums RS-23-114, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2023-11-0101 November 2023 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds IR 05000456/20230102023-10-18018 October 2023 Functional Engineering Inspection Commercial Grade Dedication Report 05000456/2023010 and 05000457/2023010 IR 05000456/20234012023-10-18018 October 2023 Security Baseline Inspection Report 05000456/2023401 and 05000457/2023401 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 RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections RS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. ML23226A0062023-09-19019 September 2023 Review of License Renewal Commitment Number 10 Submittal ML23180A1692023-09-11011 September 2023 Calvert Cliff Units 1 & 2, and R.E. Ginna Plant - Withdrawal of Proposed Alternatives to American Society of Mechanical Engineers (ASME) Requirements (Epids L-2022-LRR-0074, 0076, 0079, 0091, 0092, 0093 and 0094) IR 05000456/20230052023-08-30030 August 2023 Updated Inspection Plan for Braidwood Station Report 05000456/2023005 and 05000457/2023005 ML23234A2462023-08-25025 August 2023 Confirmation of Initial License Examination IR 05000456/20230022023-08-0303 August 2023 Integrated Inspection Report 05000456/2023002 and 05000457/2023002 ML23188A1292023-07-26026 July 2023 Issuance of Amendment Nos. 233 and 233 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML23087A0762023-07-13013 July 2023 Issuance of Amendment Nos. 232 and 232 Revision of Technical Specifications for the Ultimate Heat Sink ML23191A8442023-07-10010 July 2023 05000456; 05000457 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information 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 RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators 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 ML23110A1152023-06-12012 June 2023 Environmental Assessment and Finding of No Significant Impact Related to a Requested Increase in Ultimate Heat Sink Temperature (EPID L-2023-LLA-0042) (Letter) RS-23-074, Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-06-0909 June 2023 Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023 Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process RS-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube. ML23138A1342023-05-18018 May 2023 Information Meeting with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Braidwood Station and Byron Station ML23132A0472023-05-12012 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report ML23130A0072023-05-10010 May 2023 Submittal of Core Operating Limits Report Cycle 24, Rev. 16 IR 05000456/20230012023-05-0808 May 2023 Integrated Inspection Report 05000456/2023001 and 05000457/2023001 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23118A0202023-04-28028 April 2023 Submittal of 2022 Annual Radioactive Effluent Release Report ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection RS-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 102023-04-20020 April 2023 Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10 RS-23-055, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2023-04-10010 April 2023 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML23095A1292023-04-0505 April 2023 Steam Generator Tube Inspection Report for Refueling Outage 23 ML23094A1352023-04-0404 April 2023 Request for Information for Nrc Commercial Grade Dedication Inspection Inspection Report 05000456/2023010 05000457/2023010 RS-23-052, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-03-24024 March 2023 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations 2024-02-02
[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
[Table view] |
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