|
|
(6 intermediate revisions by the same user not shown) |
Line 1: |
Line 1: |
| {{Adams | | {{Adams |
| | number = ML12159A083 | | | number = ML12170A936 |
| | issue date = 06/06/2012 | | | issue date = 06/15/2012 |
| | title = IR 05000254-12-301(DRS), 05000265-12-301(DRS), 04/23/2012 - 05/24/2012, Quad Cities Nuclear Power Station, Units 1 and 2, Initial License Examination Report | | | title = IR 05000254-12-301 (DRS) & 05000265-12-301 (Drs), 06/06/2012, Errata to Quad Cities Nuclear Power Station, Units 1 and 2 |
| | author name = Bloomer T E | | | author name = Bloomer T |
| | author affiliation = NRC/RGN-III/DRS/OB | | | author affiliation = NRC/RGN-III/DRS/OB |
| | addressee name = Pacilio M J | | | addressee name = Pacilio M |
| | addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear | | | addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear |
| | docket = 05000254, 05000265 | | | docket = 05000254, 05000265 |
| | license number = DPR-029, DPR-030 | | | license number = DPR-029, DPR-030 |
| | contact person = | | | contact person = Bruce Palagi |
| | document report number = IR-12-301 | | | document report number = IR-12-301 |
| | document type = Inspection Report, Letter | | | document type = Letter |
| | page count = 11 | | | page count = 5 |
| }} | | }} |
|
| |
|
Line 18: |
Line 18: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter: | | {{#Wiki_filter:UNITED STATES une 15, 2012 |
| [[Issue date::June 6, 2012]]
| |
|
| |
|
| Mr. Michael Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO), Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
| | ==SUBJECT:== |
| | | ERRATA TO QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2; NRC INITIAL LICENSE EXAMINATION REPORT 05000254/2012301(DRS); |
| SUBJECT: QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2; NRC INITIAL LICENSE EXAMINATION REPORT 05000254/2012301(DRS); 05000265/2012301(DRS) | | 05000265/2012301(DRS) |
|
| |
|
| ==Dear Mr. Pacilio:== | | ==Dear Mr. Pacilio:== |
| On May 8, 2012, the U.S. Nuclear Regulatory Commission (NRC) completed the initial operator licensing examination process for license applicants employed at your Quad Cities Nuclear Power Station, Units 1 and 2. The enclosed report documents the results of those examinations. An exit meeting was conducted by telephone on May 24, 2012, between Mr. K. Moser, Site Training Director, and Mr. B. Palagi, Chief Operator Licensing Examiner, to review the conduct of the examination. The NRC examiners administered an initial license examination operating test during the week of April 23, 2012. The written examination was administered by the Quad Cities Nuclear Power Station training department personnel on April 30, 2012. Seven Senior Reactor Operator and three Reactor Operator applicants were administered license examinations. The results of the examinations were finalized on May 14, 2012. The applicants passed all sections of their respective examinations and seven senior operator licenses and three operator licenses were issued. The written examination and other related written examination documentation will be withheld from public disclosure for 24 months per your request. In accordance with Title 10 of the Code of Federal Regulations (CFR) 2.390, the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). | | On June 6, 2012, the U.S. Nuclear Regulatory Commission (NRC) issued Initial Examination Report 05000254/2012301; 05000265/2012301 (ML12159A083). In the examination report, the Summary of Findings incorrectly assigned Non-Cited Violation numbers (NCVs) |
| | | 05000254/2012301-01; 05000265/2012301-01. As indicated in the body of the report, the finding that resulted in these NCVs was licensee-identified and, therefore, should not have been assigned numbers. Please replace page 5 of Enclosure 1 and page 1 of the Attachment to Inspection Report 05000254/2301; 05000265/2012301 with the enclosed corrected pages. |
| Sincerely,/RA/
| |
| Tamara E. Bloomer, Acting Chief Operations Branch Division of Reactor Safety Docket Nos. 50-254; 50-265 License Nos. DPR-29; DPR-30
| |
| | |
| ===Enclosures:===
| |
| 1. Operator Licensing Examination Report 05000254/2012301(DRS); 05000265/2012301(DRS)
| |
| | |
| ===w/Attachment:===
| |
| Supplemental Information 2. Simulation Facility Report cc w/encl: Distribution via ListServŽ 1 Enclosure 1 U.S. NUCLEAR REGULATORY COMMISSION REGION III Docket Nos: 50-254; 50-265 License Nos: DPR-29; DPR-30 Report Nos: 05000254/2012301(DRS); 05000265/2012301(DRS) Licensee: Exelon Generation Company, LLC Facility: Quad Cities Nuclear Power Station, Units 1 and 2 Location: Cordova, Illinois Dates: April 23 - May 24, 2012 Inspectors: B. Palagi, Chief Examiner M. Bielby, Examiner C. Moore, Examiner R. Walton, Examiner
| |
| | |
| Approved by: Tamara E. Bloomer, Acting Chief Operations Branch Division of Reactor Safety 2 Enclosure 1
| |
| | |
| =SUMMARY OF FINDINGS=
| |
| IR 05000254/2012301(DRS); 05000265/2012301(DRS); 04/23/2012 - 05/24/2012; Exelon Generation Company, LLC; Quad Cities Nuclear Power Station, Units 1 and 2; Initial License Examination Report. The announced initial operator licensing examination was conducted by regional Nuclear Regulatory Commission examiners in accordance with the guidance of NUREG-1021, AOperator Licensing Examination Standards for Power Reactors,@ Revision 9 - Supplement 1. Examination Summary Ten of ten applicants passed all sections of their respective examinations. Seven applicants were issued senior operator licenses and three applicants were issued operator licenses.
| |
| | |
| (Section 4OA5.1).
| |
| | |
| ===A. NRC-Identified===
| |
| and Self-Revealed Findings No findings of significance were identified.
| |
| | |
| ===B. Licensee-Identified Violations===
| |
| A violation of very low safety significance that was identified by the licensee has been reviewed by the inspectors. Corrective actions planned or taken by the licensee have been entered into the licensee's corrective action program. This violation and corrective action tracking numbers are listed in Section 4OA7 of this report.
| |
| | |
| 1
| |
| | |
| =REPORT DETAILS=
| |
| | |
| {{a|4OA5}}
| |
| ==4OA5 Other Activities==
| |
| | |
| ===.1 Initial Licensing Examinations===
| |
| a. Examination Scope The U.S. Nuclear Regulatory Commission (NRC) examiners and members of the facility licensee's staff used the guidance prescribed in NUREG-1021, "Operator Licensing Examination Standards for Power Reactors," Revision 9 - Supplement 1, to develop, validate, administer, and grade the written examination and operating test. Members of the facility licensee's staff prepared the outline and developed the written examination and operating test. The NRC examiners validated the proposed examination during the week of April 2, 2012, with the assistance of members of the facility licensee's staff. During the on-site validation week, the examiners audited two license applications for accuracy. The NRC examiners, with the assistance of members of the facility licensee's staff, administered the operating test, consisting of job performance measures (JPMs)and dynamic simulator scenarios, during the period of April 23 through 27, 2012. The facility licensee administered the written examination on April 30, 2012.
| |
| | |
| ====b. Findings====
| |
| (1) Written Examination The NRC examiners determined that the written examination, as proposed by the licensee, was within the range of acceptability expected for a proposed examination.
| |
| | |
| Less than 20 percent of the proposed examination questions were determined to be unsatisfactory and required modification or replacement. All changes made to the proposed examination, were made in accordance with NUREG-1021, "Operator Licensing Examination Standards for Power Reactors," and documented on Form ES-401-9, "Written Examination Review Worksheet," which will be available in 24 months electronically in the NRC Public Document Room or from the Agencywide Documents Access and Management System (ADAMS). On May 8, 2012, the licensee submitted documentation noting that there were no post-examination comments for consideration by the NRC examiners when grading the written examination. The final as-administered written examination and answer key will be available in 24 months electronically in the NRC Public Document Room or from ADAMS. The NRC examiners graded the written examination on May 9, 2012, and conducted a review of each missed question to determine the accuracy and validity of the examination questions. (2) Operating Test The NRC examiners determined that the operating test, as originally proposed by the licensee, was within the range of acceptability expected for a proposed examination. Changes made to the operating test, documented in a document titled, AOperating Test Comments,@ as well as the final as administered dynamic simulator scenarios and JPMs, are available electronically in the NRC Public Document Room or from ADAMS.
| |
| | |
| The NRC examiners completed operating test grading on May 14, 2012. (3) Examination Results Seven applicants at the Senior Reactor Operator (SRO) level and three applicants at the Reactor Operator (RO) level were administered written examinations and operating tests. Each of the applicants passed all portions of their examinations and was issued their respective operating license.
| |
| | |
| ===.2 Examination Security===
| |
| a. Scope The NRC examiners reviewed and observed the licensee's implementation of examination security requirements during the examination validation and administration to assure compliance with 10 CFR 55.49, AIntegrity of Examinations and Tests.@ The examiners used the guidelines provided in NUREG-1021, "Operator Licensing Examination Standards for Power Reactors,@ to determine acceptability of the licensee=s examination security activities.
| |
|
| |
|
| ====b. Findings====
| | We apologize for any inconvenience to you and your staff. |
| The licensee identified that, during examination development, the control room simulator's plant process computer was saving sequence of events files on a routine basis. Therefore, had these files been accessed, the integrity of the examination could have been compromised. Although the examination sequence of events files were stored on the simulator process computer, the licensee was able to demonstrate that the files were not readily viewable and required interpretation. Therefore, it was determined that no individuals had an unfair advantage in taking the examination. The inspectors determined that this finding impacted the Mitigating Systems Cornerstone and consulted Inspection Manual Chapter 0609, Appendix I, to assess the impact of this issue on examination security. (4OA7)
| |
| {{a|4OA6}}
| |
| ==4OA6 Meetings==
| |
|
| |
|
| ===.1 Exit Meeting The chief examiner conducted an exit meeting on May 24, 2012, with Mr. K. Moser, Site Training Director, by telephone.===
| | Sincerely, |
| The chief examiner asked the licensee whether any of the material used to develop or administer the examination should be considered proprietary. No proprietary or sensitive information was identified.
| | /RA/ |
| {{a|4OA7}}
| | Tamara E. Bloomer, Acting Chief Operations Branch Division of Reactor Safety Docket Nos. 50-254; 50-265 License Nos. DPR-29; DPR-30 Enclosure: Errata to Inspection Report 05000254/2012301; 05000265/2012301 cc w/encl: Distribution via ListServ' |
| ==4OA7 Licensee-Identified Violations The following violation of very low significance (Green) was identified by the licensee and is a violation of NRC requirements, which meet the criteria of Section VI of the==
| |
|
| |
|
| NRC Enforcement Policy, NUREG-1600, for being dispositioned as a Non-Cited Violation (NCV): Title 10 CFR 55.49, "Integrity of Examinations and Tests," requires, in part, that the licensee shall not engage in activities that compromises the integrity of any application, test, or examination required by 10 CFR Part 55. Contrary to the above,
| | on March 30, 2012, at the Clinton Power Station, the licensee identified that the control room simulators plant process computer model was saving sequence of events files on a routine basis. A licensee investigation determined that the same condition existed at Quad Cities Nuclear Power Station. The licensee determined that some of the files contained examination materials related to examinations required by 10 CFR Part 55. The integrity of a test or examination is considered compromised if any activity, regardless of intent, affected, or, but for detection, would have affected the equitable and consistent administration of the test or examination. |
|
| |
|
| on March 30, 2012, at the Clinton Power Station, the licensee identified that the control room simulator's plant process computer model was saving sequence of events files on a routine basis. A licensee investigation determined that the same condition existed at Quad Cities Nuclear Power Station. The licensee determined that some of the files contained examination materials related to examinations required by 10 CFR Part 55. The integrity of a test or examination is considered compromised if any activity, regardless of intent, affected, or, but for detection, would have affected the equitable and consistent administration of the test or examination.
| | Although the examination materials were compromised, the licensee was able to demonstrate that the files were not readily viewable and required interpretation. |
|
| |
|
| Although the examination materials were compromised, the licensee was able to demonstrate that the files were not readily viewable and required interpretation. Therefore, no individuals had an unfair advantage in taking any NRC-related examinations. This issue was documented in the facility's corrective action program as IR1348733. Corrective actions for this issue included revising the simulator's software to delete data from the sequence of events files being generated by the simulator until a longer term fix is decided. The licensee's corporate procedure TQ-QC-201-0113, "Simulator Examination Security Actions Checklist," will add steps to delete data after simulator resets. The inspectors determined that the failure to control sequence of event files generated by the facility's simulator was a performance deficiency that required a Significance Determination Process evaluation. The inspectors determined that this finding impacted the Mitigating Systems Cornerstone and consulted IMC 0609, Appendix I, to assess the impact of this issue on examination security. The inspectors concluded that a potential examination compromise had occurred and the facility had taken immediate compensatory actions to prevent recurrence of this condition. Based on circumstances described above and the licensee's corrective actions, the inspectors concluded that this finding was of very low safety significance (Green). (NCV 05000254/2012301-01; NCV 05000301265/2012301-01) ATTACHMENT:
| | Therefore, no individuals had an unfair advantage in taking any NRC-related examinations. This issue was documented in the facilitys corrective action program as IR1348733. Corrective actions for this issue included revising the simulators software to delete data from the sequence of events files being generated by the simulator until a longer term fix is decided. The licensees corporate procedure TQ-QC-201-0113, Simulator Examination Security Actions Checklist, will add steps to delete data after simulator resets. |
|
| |
|
| =SUPPLEMENTAL INFORMATION=
| | The inspectors determined that the failure to control sequence of event files generated by the facilitys simulator was a performance deficiency that required a Significance Determination Process evaluation. The inspectors determined that this finding impacted the Mitigating Systems Cornerstone and consulted IMC 0609, Appendix I, to assess the impact of this issue on examination security. The inspectors concluded that a potential examination compromise had occurred and the facility had taken immediate compensatory actions to prevent recurrence of this condition. Based on circumstances described above and the licensees corrective actions, the inspectors concluded that this finding was of very low safety significance (Green). |
|
| |
|
| ==KEY POINTS OF CONTACT==
| | ATTACHMENT: SUPPLEMENTAL INFORMATION 5 Enclosure 1 |
| Licensee
| |
| : [[contact::K. Moser]], Training Director | |
| : [[contact::E. Pannell]], Operations Training Manager
| |
| : [[contact::C. Burkhart]], Examination Lead
| |
| Nuclear Regulatory Commission
| |
| : [[contact::B. Palagi]], Chief Examiner
| |
| : [[contact::M. Bielby]], Senior Examiner
| |
| : [[contact::R. Walton]], Senior Examiner
| |
| ==ITEMS OPENED, CLOSED, AND DISCUSSED==
| |
| Opened, Closed, and Discussed
| |
| ===Opened===
| |
| : 05000254/2012301-01
| |
| : 05000265/2012301-01 NCV Failure to Control Sequence of Event Files Generated by the Facility's Simulator
| |
| ===Closed===
| |
| : 05000254/2012301-01
| |
| : [[Closes finding::05000265/FIN-2012301-01]] NCV Failure to Control Sequence of Event Files Generated by the Facility's Simulator
| |
| ===Discussed===
| |
|
| |
|
| None | | SUPPLEMENTAL INFORMATION KEY POINTS OF CONTACT Licensee K. Moser, Training Director E. Pannell, Operations Training Manager C. Burkhart, Examination Lead Nuclear Regulatory Commission B. Palagi, Chief Examiner M. Bielby, Senior Examiner R. Walton, Senior Examiner ITEMS OPENED, CLOSED, AND DISCUSSED Opened, Closed, and Discussed None 1 Attachment 1 |
|
| |
|
| Attachment
| | Mr. Michael |
| ==LIST OF DOCUMENTS REVIEWED==
| |
| The following is a partial list of documents reviewed during the inspection.
| |
| : Inclusion on this list does not imply that the NRC inspector reviewed the documents in their entirety, but rather that selected sections or portions of the documents were evaluated as part of the overall inspection effort.
| |
| : Inclusion of a document on this list does not imply NRC acceptance of the document or any part of it, unless this is stated in the body of the inspection report.
| |
| : None.
| |
| ==LIST OF ACRONYMS==
| |
| : [[USED]] [[]]
| |
| : [[ADAMS]] [[Agencywide Document Access and Management System]]
| |
| : [[CFR]] [[Code of Federal Regulations]]
| |
| : [[DRS]] [[Division of Reactor Safety]]
| |
| : [[JPM]] [[Job Performance Measures]]
| |
| : [[NRC]] [[]]
| |
| : [[U.S.]] [[Nuclear Regulatory Commission]]
| |
| : [[PARS]] [[Publicly Available Records System]]
| |
| : [[RO]] [[Reactor Operator]]
| |
| SRO Senior Reactor Operator
| |
| Enclosure 2 SIMULATION FACILITY REPORT Facility Licensee: Quad Cities Nuclear Power Station, Units 1 and 2 Facility Docket Nos: 50-254; 50-265 Operating Tests Administered: April 23 - 27, 2012
| |
| The following documents observations made by the NRC examination team during the initial
| |
| operator license examination. These observations do not constitute audit or inspection findings
| |
| and are not, without further verification and review, indicative of non-compliance with
| |
| : [[CFR]] [[55.45(b). These observations do not affect]]
| |
| : [[NRC]] [[certification or approval of the simulation facility other than to provide information which may be used in future evaluations. No licensee action is required in response to these observations. During the conduct of the simulator portion of the operating tests, the following items were observed:]]
| |
| : [[ITEM]] [[]]
| |
| DESCRIPTION SBLC Switch When Standby Liquid Control was actuated the system failed to start. Rod Select Push Button When a rod was selected on the rod select matrix the push button stuck in the down position.
| |
| M. Pacilio -2-
| |
| (PARS) component of
| |
| : [[NRC]] [['s Agencywide Documents Access and Management System (ADAMS), accessible from the]]
| |
| : [[NRC]] [[Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). Sincerely, /]]
| |
| RA/
| |
| Tamara E. Bloomer, Acting Chief
| |
| Operations Branch
| |
| Division of Reactor Safety
| |
| Docket Nos. 50-254; 50-265 License Nos. DPR-29; DPR-30
| |
| Enclosures: 1. Operator Licensing Examination Report 05000254/2012301(DRS); 05000265/2012301(DRS)
| |
| w/Attachment: Supplemental Information 2. Simulation Facility Report cc w/encl: Distribution via ListServŽ DISTRIBUTION w/encl: Michael McCoppin
| |
| RidsNrrDorlLpl3-2 Resource
| |
| RidsNrrPMQuadCities Resource RidsNrrDirsIrib Resource Chuck Casto
| |
| Cynthia Pederson
| |
| Steven Orth
| |
| Jared Heck Allan Barker Carole Ariano
| |
| Linda Linn
| |
| : [[DRPIII]] [[]]
| |
| DRSIII Patricia Buckley
| |
| Tammy Tomczak
| |
| ROPreports.Resource@nrc.gov
| |
| : [[DOCUME]] [[NT NAME:]]
| |
| : [[QUA]] [[2012 301]]
| |
| : [[DRS]] [[OL.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]] [[]]
| |
| : [[RIII]] [[]]
| |
| : [[RIII]] [[]]
| |
| : [[RIII]] [[]]
| |
| : [[NAME]] [[RWalton for BPalagi:cs TBloomer]]
| |
| : [[DATE]] [[06/06/12 06/06/12]]
| |
| : [[OFFICI]] [[AL]]
| |
| : [[RECORD]] [[]]
| |
| : [[COPY]] [[]]
| |
| }} | | }} |
|
---|
Category:Letter
MONTHYEARIR 05000254/20244022024-09-12012 September 2024 Material Control and Accounting Program Inspection Report 05000254/2024402 and 05000265/2024402 (Public) SVP-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 SVP-24-034, Annual Radiological Environmental Operating Report2024-05-10010 May 2024 Annual Radiological Environmental Operating Report 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 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-24-028, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2024-04-26026 April 2024 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report SVP-24-029, Radioactive Effluent Release Report for 20232024-04-26026 April 2024 Radioactive Effluent Release Report for 2023 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 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 IR 05000254/20245012024-04-0505 April 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000254/2024501 and 05000265/2024501 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 ML23340A1552024-03-15015 March 2024 – Issuance of Amendment Nos. 299 and 295 Adoption of TSTF-564, Safety Limit MCPR 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 2024-09-04
[Table view] |
Text
UNITED STATES une 15, 2012
SUBJECT:
ERRATA TO QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2; NRC INITIAL LICENSE EXAMINATION REPORT 05000254/2012301(DRS);
05000265/2012301(DRS)
Dear Mr. Pacilio:
On June 6, 2012, the U.S. Nuclear Regulatory Commission (NRC) issued Initial Examination Report 05000254/2012301; 05000265/2012301 (ML12159A083). In the examination report, the Summary of Findings incorrectly assigned Non-Cited Violation numbers (NCVs)05000254/2012301-01; 05000265/2012301-01. As indicated in the body of the report, the finding that resulted in these NCVs was licensee-identified and, therefore, should not have been assigned numbers. Please replace page 5 of Enclosure 1 and page 1 of the Attachment to Inspection Report 05000254/2301; 05000265/2012301 with the enclosed corrected pages.
We apologize for any inconvenience to you and your staff.
Sincerely,
/RA/
Tamara E. Bloomer, Acting Chief Operations Branch Division of Reactor Safety Docket Nos. 50-254; 50-265 License Nos. DPR-29; DPR-30 Enclosure: Errata to Inspection Report 05000254/2012301; 05000265/2012301 cc w/encl: Distribution via ListServ'
on March 30, 2012, at the Clinton Power Station, the licensee identified that the control room simulators plant process computer model was saving sequence of events files on a routine basis. A licensee investigation determined that the same condition existed at Quad Cities Nuclear Power Station. The licensee determined that some of the files contained examination materials related to examinations required by 10 CFR Part 55. The integrity of a test or examination is considered compromised if any activity, regardless of intent, affected, or, but for detection, would have affected the equitable and consistent administration of the test or examination.
Although the examination materials were compromised, the licensee was able to demonstrate that the files were not readily viewable and required interpretation.
Therefore, no individuals had an unfair advantage in taking any NRC-related examinations. This issue was documented in the facilitys corrective action program as IR1348733. Corrective actions for this issue included revising the simulators software to delete data from the sequence of events files being generated by the simulator until a longer term fix is decided. The licensees corporate procedure TQ-QC-201-0113, Simulator Examination Security Actions Checklist, will add steps to delete data after simulator resets.
The inspectors determined that the failure to control sequence of event files generated by the facilitys simulator was a performance deficiency that required a Significance Determination Process evaluation. The inspectors determined that this finding impacted the Mitigating Systems Cornerstone and consulted IMC 0609, Appendix I, to assess the impact of this issue on examination security. The inspectors concluded that a potential examination compromise had occurred and the facility had taken immediate compensatory actions to prevent recurrence of this condition. Based on circumstances described above and the licensees corrective actions, the inspectors concluded that this finding was of very low safety significance (Green).
ATTACHMENT: SUPPLEMENTAL INFORMATION 5 Enclosure 1
SUPPLEMENTAL INFORMATION KEY POINTS OF CONTACT Licensee K. Moser, Training Director E. Pannell, Operations Training Manager C. Burkhart, Examination Lead Nuclear Regulatory Commission B. Palagi, Chief Examiner M. Bielby, Senior Examiner R. Walton, Senior Examiner ITEMS OPENED, CLOSED, AND DISCUSSED Opened, Closed, and Discussed None 1 Attachment 1
Mr. Michael