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Category:Letter
MONTHYEARML24151A3842024-10-31031 October 2024 – Issuance of Amendment Nos. 264 and 226 Support to Digital Modernization Project Installation (EPID L-2023-LLA-0025) and Exemption from the Requirements of 10 CFR 50.62 ML24303A2782024-10-29029 October 2024 10 CFR 50.46 Annual Report ML24303A0902024-10-29029 October 2024 Operator Licensing Examination Approval ML24299A2642024-10-25025 October 2024 Response to Request for Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding Primary Containment Leakage Technical Specifications IR 05000352/20240122024-10-17017 October 2024 Commercial Grade Dedication Inspection Report 05000352/2024012 and 05000353/2024012 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 ML24274A2372024-10-0707 October 2024 – Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding Primary Containment Leakage Technical Specifications ML24278A3022024-10-0404 October 2024 Supplement to License Amendment Request to Revise Technical Specifications and Exemption Request from Requirements of 10 CFR 50.62 ATWS Rule to Support the Digital Modernization Project Installation - Rev Unit 2 Technical Spec ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24263A0032024-09-27027 September 2024 Generation Station, Units 1 and 2 – Regulatory Audit Plan Supporting Review of the Component Interface Module System of the Limerick Digital Instrumentation and Controls License Amendment Request (EPID L-2022-LLA-0140) (Redacted) ML24243A0482024-09-19019 September 2024 Generation Station, Unit Nos. 1 and 2 - Schedule Update for License Amendment Request to Replace Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection System ML24215A4042024-09-18018 September 2024 Request for Withholding Information from Public Disclosure IR 05000352/20244202024-09-16016 September 2024 – Security Baseline Inspection Report 05000352/2024420 and 05000353/2024420 RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024 Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds IR 05000352/20250102024-09-10010 September 2024 Information Request for Quadrennial Baseline Comprehensive Engineering Team Inspection; Notification to Perform Inspection 05000352/2025010 and 05000353/2025010 ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification IR 05000352/20230022024-09-0404 September 2024 Reissued Integrated Inspection Report 05000352/2023002 and 05000353/2023002 IR 05000352/20240052024-08-29029 August 2024 Updated Inspection Plan for Limerick Generating Station, Units 1 and 2 (Report 05000352/2024005 and 05000353/2024005) ML24241A1952024-08-28028 August 2024 License Amendment Request for Modification to Technical Specification 3.6.1.2 and Main Steam Isolation Valve Leakage Rate Requirements ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 ML24163A3902024-08-14014 August 2024 Request for Withholding Information from Public Disclosure IR 05000352/20240022024-08-12012 August 2024 Integrated Inspection Report 05000352/2024002 and 05000353/2024002 ML24220A2392024-08-12012 August 2024 Correction to Technical Specification Page 3/4 3-11 in Amendment No. 225 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 ML24204A0712024-07-29029 July 2024 Issuance of Amendment Nos. 263 and 225 Technical Specifications for Main Steam Line Tunnel Temperature ML24208A1592024-07-25025 July 2024 Regulatory Audit Plan Supporting Review of the System Development Portion of Limerick Digital Instrumentation and Controls License Amendment Request (EPID L-2022-LLA-0140) - Non-Proprietary ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification ML24201A1662024-07-19019 July 2024 Response to Request for Additional Information for License Amendment Request for Proposed Changes to the Technical Specification Isolation Actuation Instrumentation Tables and New Turbine Enclosure Main Steam L ML24199A1842024-07-15015 July 2024 RAI-LAR for Limerick EPID: L-2024-LLA-0079- Use This Version 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 ML24180A1572024-06-28028 June 2024 Request to Return and Replace WEC Documents (EQ-EV-386-GLIM, EQ-QR- 433-GLIM, and APP-GW-GLR-611), to Meet 10CFR2.390 Request to Withdraw from Public Disclosure Requirements ML24170A7702024-06-20020 June 2024 Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, Opportunity for Hearing(Epid L-2024-LLA-0079) LTR 05000352/LER-2024-003, Core Operating Limits Report Thermal Limit Exceeded for Unit 1 Fuel Bundle GGK1232024-06-18018 June 2024 Core Operating Limits Report Thermal Limit Exceeded for Unit 1 Fuel Bundle GGK123 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 ML24166A1142024-06-14014 June 2024 Response to Requests for Additional Information (RAIs 15 Through 23) for License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related Analog Control Systems ML24165A2642024-06-13013 June 2024 License Amendment Request for Proposed Changes to the Technical Specification Isolation Actuation Instrumentation Tables and New Turbine Enclosure Main Steam Line Tunnel Temperature TS 3/4.7.9 ML24151A2012024-06-10010 June 2024 Request for Withholding Information from Public Disclosure ML24151A2882024-06-10010 June 2024 Request for Withholding Information from Public Disclosure 05000352/LER-2024-001, Leakage for the Unit 1 `B Outboard Main Steam Isolation Valve Exceeded Technical Specification Limit2024-06-10010 June 2024 Leakage for the Unit 1 `B Outboard Main Steam Isolation Valve Exceeded Technical Specification Limit 05000352/LER-2024-002, Invalid Actuation Due to a Trip of 1B Reactor Protection System Circuit Breaker2024-06-10010 June 2024 Invalid Actuation Due to a Trip of 1B Reactor Protection System Circuit Breaker ML24150A0242024-05-29029 May 2024 Notification of Commercial Grade Dedication Inspection (05000352/2024012 and 05000353/2024012) and Request for Information ML24149A2112024-05-28028 May 2024 Supplement to License Amendment Request to Revise Technical Specifications and Exemption Request from Requirements of 10CFR50.62 ATWS Rule to Support the Digital Modernization Project Installation ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 IR 05000352/20243022024-05-20020 May 2024 Revised Initial Operator Licensing Examination Report 05000352/2024302 and 05000353/2024302 RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report IR 05000352/20240012024-05-0707 May 2024 Integrated Inspection Report 05000352/2024001 and 05000353/2024001 ML24124A0432024-05-0303 May 2024 Response to Requests for Additional Information (RAIs 9 Through 14) for License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related Analog Control Systems with RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024 Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds 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 ML24114A3222024-04-23023 April 2024 Supplement to License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection System (PPS) - Pivot to Unit 2024-09-06
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BOULEVARD, SUITE 100 KING OF PRUSSIA, PENNSYLVANIA 19406-2713 October 18, 2012 EA-12-190 Mr. Michael J. Pacilio Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer, Exelon Nuclear 4300 Winfield Rd.
Warrenville, IL 60555
SUBJECT:
NRC INVESTIGATION REPORT NO. 1-2012-030
Dear Mr. Pacilio:
This letter refers to the investigation by the U. S. Nuclear Regulatory Commission (NRC) Office of Investigations (OI) conducted at Exelon Nuclears (Exelons) Limerick Generating Station (Limerick). The OI investigation, which was completed on August 29, 2012, was conducted to determine whether a contract foreman employed by Shaw deliberately failed to follow procedures on the use of electronic dosimetry (ED) after the loss of his ED at Limerick. The investigation was initiated after Exelon informed the NRC, on February 23, 2012, that a contract foreman had used a crew members ED to re-enter a Radiological Controlled Area (RCA) after the foreman realized he had lost his ED within the RCA. This was contrary to Exelon procedures which required the use of personal dosimetry and the immediate notification of radiation protection (RP) personnel of any lost ED.
Based on the evidence gathered during the OI investigation, the NRC concluded that on February 23, 2012, the contract foreman deliberately failed to follow the ED procedures when he requested that one of his crew members (who had not yet logged out of the RCA) provide the foreman with his (the crew members) ED, so that the foreman could go back into the RCA and find his (the foremans) ED. This was contrary to requirements in the Limerick operating license, and resulted in a violation. Specifically, Technical Specification 6.8.1 requires that written procedures be established, implemented, and maintained covering the activities recommended in Regulatory Guide 1.33, Appendix A, Revision 2, dated February 1978; Regulatory Guide 1.33, Appendix A, Revision 2, dated February 1978, Item 7.e recommends the establishment of written Radiation Protection procedures for personnel monitoring activities in radiation areas; and, Exelon Procedure RP-AA-1008, Revision 2, Section 4, requires, in part that the loss of personal dosimetry be immediately reported to RP.
The NRC concluded, based on the evidence gathered during the OI investigation, that the foremans actions were deliberate. This conclusion was based on the foremans admission to OI that he had received training on the correct ED procedure; his experience working in the RCA; his acknowledgement that he should not have asked to borrow the crew members ED to re-enter the RCA to look for his own; and his acknowledgement that he should have reported
M. Pacilio 2 the issue to RP staff immediately. Based on evidence gathered during the OI investigation, the NRC did not conclude that the crew members actions were willful.
Because the foremans violation was willful, it was evaluated under the NRCs traditional enforcement process using the factors set forth in Section 2.3.2 of the NRC Enforcement Policy.
After careful consideration of these factors, the NRC concluded that this violation should be classified at Severity Level (SL) IV. In reaching this decision, the NRC considered that the significance of the underlying violation was minor because, while the foreman was in possession of the wrong ED, he entered an area of the RCA where dose rates were very low and he was in that area for a very short period of time. In addition, he still had his TLD on his person when he re-entered the RCA. However, the NRC decided to increase the significance of this violation to SL IV since it was willful and the NRC regulatory program is based, in part, on licensees and their contractors acting with integrity.
In accordance with Section 2.3.2 of the Enforcement Policy, and with the approval of the Director, Office of Enforcement, this issue has been characterized as a non-cited violation, because: (1) the violation was identified by the licensee; (2) the violation involved the acts of an individual who, while a supervisor to the crew member, would not have been considered a licensee official with oversight of regulated activities as defined in the Enforcement Policy; (3) the violation did not involve a lack of management oversight and was the isolated action of the employee; and (4) significant remedial action commensurate with the circumstances was taken by the licensee. Regarding the corrective actions, Exelon conducted an internal investigation to determine the cause and appropriate corrective actions and took disciplinary action with respect to both the foreman and the crew member.
The NRC has concluded that information regarding the reason for the violation, the corrective actions taken and planned to correct the violation and prevent recurrence, and the date when full compliance was achieved is already adequately addressed on the docket in this letter.
Therefore, you are not required to respond to this letter unless the description herein does not accurately reflect your corrective actions or your position. If you contest this NCV or its significance, you should provide a response within 30 days of the date of this letter, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN.: Document Control Desk, Washington, D.C. 20555-0001, with copies to the Regional Administrator, Region I, 2100 Renaissance Boulevard, Suite 100, King of Prussia, PA 19406; the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555-0001; and the NRC Resident Inspector at Limerick.
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter, its enclosure, and your response, if you choose to provide one, will be available electronically for public inspection in the NRC Public Document Room and from the NRCs Agency-wide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html.
M. Pacilio 3 Should you have any questions regarding this letter, please contact Mr. Paul Krohn at 610-337-5120.
Sincerely,
/RA/
Darrell J. Roberts, Director Division of Reactor Projects Region I Docket Nos.: 50-352, 50-353 License Nos.: NPF-39, NPF-85 cc: Distribution via ListServ
M. Pacilio 3 Should you have any questions regarding this letter, please contact Mr. Paul Krohn at 610-337-5120.
Sincerely,
/RA/
Darrell J. Roberts, Director Division of Reactor Projects Region I Docket Nos.: 50-352, 50-353 License Nos.: NPF-39, NPF-85 cc: Distribution via ListServ DOC NAME: S:\Enf-allg\Enforcement\Proposed-Actions\Region1\Limerick HP Proc NCV-IV EA-12-190.docx X Non-Sensitive X Publicly Available X SUNSI Review/
Sensitive Non-Publicly Available OFFICE RI/ORA RI/DRP RI\DRS RI\DRS RI\OI RI/ORA ADeFrancisco/
NAME P Krohn/ PGK* J Noggle/ JDN* C Miller/ CGM* J Teator/ JAT* K Farrar/ KLF*
AED*
DATE 10/02/12 10/02/12 10/03/12 10/03/12 10/04/12 10/10/12 OFFICE RI\ORA OE NRR OGC RI/DRP J Steffes via E Monteith NLO NAME D Holody/ DJH* J Bowen via email D Roberts/
email via email DATE 10/10/12 10/16/12 10/16/12 10/16/12 10/17/12
- Concurrence on previous sheet OFFICIAL USE COPY
M. Pacilio 4 Distribution:
W. Dean, RI, RA D. Lew, DRA D. Roberts, DRP J. Clifford, DRP C. Miller, DRS P. Wilson, DRS J. Noggle, DRS P. Krohn, DRP D. Screnci / N. Sheehan, OPA K. Farrar, RI D. Holody, RI R. Urban, RI M. McLaughlin, RI C. Crisden, RI A. Rosebrook, RI S. Ibarrola, DRP N. McNamara / D. Tifft, RI E. DiPaolo, SRI J. Hawkins, RI N. Esch, AA C. ODaniell, RI J. Steffes, OE J. Bowen, NRR J. Teator, OI M. Holmes, OI D. Gallagher, OI E. Monteith, OGC R1DRPMail Resource ROPreports Resource RidsNrrPMLimerickResource R1 OE Files (with concurrences)