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Category:Letter
MONTHYEARGO2-24-004, License Amendment Request to Revise Emergency Plan2024-01-30030 January 2024 License Amendment Request to Revise Emergency Plan IR 05000397/20230042024-01-29029 January 2024 Integrated Inspection and Independent Spent Fuel Storage Installation Report 05000397/2023004 and 07200035/2023001 GO2-24-003, Relief Requests for the Columbia Generating Station Fifth Ten-Year Interval Inservice Testing2024-01-29029 January 2024 Relief Requests for the Columbia Generating Station Fifth Ten-Year Interval Inservice Testing ML24011A1522024-01-10010 January 2024 March 2024 Emergency Preparedness Exercise Inspection-Request for Information GO2-24-005, Docket No. 50-397 Supplement to Reply to a Notice of Violation; EA-21-1702024-01-0808 January 2024 Docket No. 50-397 Supplement to Reply to a Notice of Violation; EA-21-170 GO2-23-136, Guarantee of Payment of Deferred Premium2023-12-20020 December 2023 Guarantee of Payment of Deferred Premium GO2-23-135, Notice of Readiness for Supplemental Inspection2023-12-14014 December 2023 Notice of Readiness for Supplemental Inspection GO2-23-130, Reply to a Notice of Violation; EA-23-0542023-12-14014 December 2023 Reply to a Notice of Violation; EA-23-054 GO2-23-105, Licensing Basis Document Update and Biennial Commitment Change Report2023-12-12012 December 2023 Licensing Basis Document Update and Biennial Commitment Change Report ML23288A0002023-12-0707 December 2023 Issuance of Amendment No. 272 to Adopt TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position GO2-23-107, Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation2023-12-0505 December 2023 Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation GO2-23-126, Docket No. 50-397 Voluntary Response to Regulatory Issue Summary 2023-012023-11-28028 November 2023 Docket No. 50-397 Voluntary Response to Regulatory Issue Summary 2023-01 GO2-23-121, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-27027 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000397/20230122023-11-20020 November 2023 Commercial Grade Dedication Inspection Report 05000397/2023012 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV IR 05000397/20230102023-11-0909 November 2023 Biennial Problem Identification and Resolution Inspection Report 05000397/2023010 IR 05000397/20230932023-11-0101 November 2023 Final Significance Determination of a White Finding, Notice of Violation and Follow-Up Assessment Letter; NRC Inspection Report 05000397/2023093 ML23299A2072023-10-26026 October 2023 Biennial Requalification Inspection Request for Information IR 05000397/20230032023-10-25025 October 2023 Integrated Inspection Report 05000397/2023003 IR 05000397/20230112023-10-0404 October 2023 License Renewal Phase 2 Report 05000397/2023011 IR 05000397/20234012023-09-11011 September 2023 Security Baseline Inspection Report 05000397/2023401 GO2-23-097, In-Service Inspection Summary Report for the Twenty-Sixth Refueling Outage (R26)2023-09-0606 September 2023 In-Service Inspection Summary Report for the Twenty-Sixth Refueling Outage (R26) ML24032A2182023-09-0101 September 2023 Information Request, Security IR 2024401 GO2-23-100, Technical Specification Section 5.6.4 Post Accident Monitoring Instrumentation 14-Day Report for Inoperable Suppression Pool Level Indication2023-08-31031 August 2023 Technical Specification Section 5.6.4 Post Accident Monitoring Instrumentation 14-Day Report for Inoperable Suppression Pool Level Indication GO2-23-056, Application to Revise Technical Specifications to Adopt TSTF-230, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2023-08-29029 August 2023 Application to Revise Technical Specifications to Adopt TSTF-230, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling IR 05000397/20230052023-08-22022 August 2023 Updated Inspection Plan for Columbia Generating Station (Report 05000397/2023005) - Mid Year Letter IR 05000397/20230022023-08-0101 August 2023 Integrated Inspection Report 05000397/2023002 GO2-23-093, Supplement to Reply to a Notice of Violation: EA-21-1702023-07-27027 July 2023 Supplement to Reply to a Notice of Violation: EA-21-170 ML23206A2442023-07-25025 July 2023 Energy Northwest Columbia Generating Station, Response to Apparent Violation in NRC Inspection Report 05000397/2023092; EA-23-054 GO2-23-068, Notification of Completion of Commitments Required Prior to Entry Into the Period of Extended Operation2023-07-19019 July 2023 Notification of Completion of Commitments Required Prior to Entry Into the Period of Extended Operation GO2-23-090, Reply to a Notice of Violation2023-07-12012 July 2023 Reply to a Notice of Violation ML23143A1202023-06-27027 June 2023 Request Number 4ISI-11 to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Regarding Alternate Examination of Reactor Vessel Welds GO2-23-073, Notification of NPDES Permit Issuance2023-06-26026 June 2023 Notification of NPDES Permit Issuance ML23163A2502023-06-12012 June 2023 Summary of Changes and Analysis for Revision 41 of Plant Procedures Manual 13.8.1 Emergency Dose Projection System Operations GO2-23-072, Cycle 27 Core Operating Limits Report2023-06-0505 June 2023 Cycle 27 Core Operating Limits Report ML23157A2702023-06-0101 June 2023 4-2022-011 -022 Letter - OI Closure to Licensee IR 05000397/20230922023-06-0101 June 2023 NRC Inspection Report 05000397/2023092 and Preliminary White Finding IR 05000397/20230902023-06-0101 June 2023 Final Significance Determination of a White Finding, Notice of Violation and Follow-Up Assessment Letter; NRC Inspection Report 05000397/2023090 GO2-23-055, Independent Spent Fuel Storage Installation, 2022 Annual Radiological Environmental Operating Report2023-05-15015 May 2023 Independent Spent Fuel Storage Installation, 2022 Annual Radiological Environmental Operating Report IR 05000397/20230012023-05-0505 May 2023 Integrated Inspection Report 05000397/2023001 - April 26, 2023 GO2-23-006, License Amendment Request to Clean-Up Operating License and Appendix a Technical Specifications2023-05-0101 May 2023 License Amendment Request to Clean-Up Operating License and Appendix a Technical Specifications IR 05000397/20233012023-05-0101 May 2023 NRC Examination Report 05000397/2023301 GO2-23-053, 2022 Annual Environmental Operating Report2023-04-26026 April 2023 2022 Annual Environmental Operating Report GO2-23-057, 2022 Annual Radioactive Effluent Release Report2023-04-25025 April 2023 2022 Annual Radioactive Effluent Release Report ML23110A2642023-04-20020 April 2023 Request for Information License Renewal Phase 2 Inspection GO2-23-012, Application to Revise Technical Specifications to Adopt Tstf-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2023-03-27027 March 2023 Application to Revise Technical Specifications to Adopt Tstf-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position GO2-23-041, Generation Station - Level of Financial Protection - Annual Reporting Requirement2023-03-15015 March 2023 Generation Station - Level of Financial Protection - Annual Reporting Requirement GO2-23-038, Plant Decommissioning Fund Status Report2023-03-15015 March 2023 Plant Decommissioning Fund Status Report ML23013A0812023-03-15015 March 2023 Issuance of Amendment No. 270 Revision to Technical Specifications to Adopt TSTF 505, Revision 2, Provide Risk-Informed Extended Completion Times-RITSTF Initiative 4B GO2-23-034, Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.462023-03-13013 March 2023 Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.46 2024-01-08
[Table view] Category:License-Operator Examination Report
MONTHYEARML23045A1092023-02-14014 February 2023 NRC Initial Operator Licensing Examination Approval 05000397/2023301 ML21040A5302021-02-17017 February 2021 CGS20211301-Exam Approval LTR-jck IR 05000397/20193012019-04-23023 April 2019 NRC Examination Report 05000397/2019301 IR 05000397/20173012017-04-10010 April 2017 NRC Examination Report 05000397/2017301 ML16109A2102016-04-18018 April 2016 Notification of NRC Initial Operator Licensing Examination 05000397/2017301 IR 05000397/20153012015-06-30030 June 2015 Er 05000397/2015301; on 04/24/2015 - 06/17/2015; Columbia Generating Station; Initial Operator Licensing Examination Report IR 05000397/20113012011-06-23023 June 2011 Er 05000397/11-301, on 04/22/11 - 05/13/11, Columbia Generating Station, Initial Operator Licensing Examination Report IR 05000397/20093022009-11-0404 November 2009 Er 05000397-09-302, on October 5, 2009; Columbia Generating Station; Initial Operator Licensing Examination Report IR 05000397/20093012009-04-21021 April 2009 Er 05000397-09-301; March 13 - April 9, 2009; Columbia Generating Station; Initial Operator Licensing Examination Report IR 05000397/20063012006-12-27027 December 2006 Er 05000397-06-301; 11/27/06 - 12/05/2006; Columbia Generating Station; Initial Operator Licensing Examinations IR 05000397/20053012005-07-12012 July 2005 Er 05000397-05-301; 06/13/05; Columbia Generating Station; Retake Operator Licensing Examination Report ML0409200332004-03-30030 March 2004 Generic Fundamentals Section of the Written Operator Licensing Examination IR 05000397/20033012003-04-0909 April 2003 Er 50-397/03-301; Energy Northwest; 3/27-4/7/2003; Columbia Generating Station; Initial Operator Licensing Examination IR 05000397/20023012002-11-0808 November 2002 Er 05000397-02-301, on October 4-18, 2002, Energy Northwest, Columbia Generating Station, Initial Operator Licensing Examination 2023-02-14
[Table view] |
Text
ber 8, 2002
SUBJECT:
COLUMBIA GENERATING STATION - NRC EXAMINATION REPORT 50-397/02-301
Dear Mr. Parrish:
On October 17, 2002, the NRC completed initial examinations at your Columbia Generating Station. The enclosed report documents the examination findings, which were discussed on October 17, 2002, with Messrs. Gary Hendricks, Randy Guthrie, and other members of your staff.
The examination included the evaluation of six applicants for reactor operator licenses and nine applicants for senior operator licenses. We determined that 14 of the 15 applicants satisfied the requirements of 10 CFR Part 55, and the appropriate licenses have been issued.
In accordance with 10 CFR 2.790 of the NRCs "Rules of Practice," a copy of this letter, its enclosure(s), and your response will be made available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
//RA//
Anthony T. Gody, Chief Operations Branch Division of Reactor Safety Docket: 50-397 License: NPF-21
Enclosure:
NRC Inspection Report 50-397/02-301
Energy Northwest -2-
REGION IV==
Docket: 50-397 License: NPF-21 Report No.: 50-397/02-301 Licensee: Energy Northwest Facility: Columbia Generating Station Location: Richland, Washington Dates: October 4-17, 2002 Inspectors: T. F. Stetka, Senior Operations Engineer, Operations Branch H. F. Bundy, Senior Operations Engineer, Operations Branch R. E. Lantz, Senior Emergency Preparedness Inspector, Plant Support Branch T. O. McKernon, Senior Operations Engineer, Operations Branch Approved By: Anthony T. Gody, Chief Operations Branch Division of Reactor Safety
-2-SUMMARY OF FINDINGS Columbia Generating Station NRC Examination Report 50-397/02-301 ER 50-397/02-301; on October 4-17, 2002; Energy Northwest, Columbia Generating Station; Initial Operator Licensing Examination.
NRC examiners evaluated the competency of six applicants for reactor operator licenses and nine applicants for senior operator licenses at the Columbia Generating Station. The licensee developed the written and operating examination using NUREG-1021, "Operator Licensing Examination Standards for Power Reactors," Revision 8, Supplement 1. Licensee proctors administered the written examination to all applicants on October 4, 2002. The NRC administered the operating tests on October 8-17, 2002.
Cornerstone: Human Performance No findings of significance were identified (Section 40A4.1).
Report Details 4. OTHER ACTIVITIES (OA)
4OA4 Initial Operator License Examination
.1 Operator Knowledge and Performance a. Examination Scope On October 4, 2002, the licensee proctored the administration of the written examination to all 15 applicants. The licensee staff graded the written examinations, analyzed the results, and presented their analysis to the NRC on October 21, 2002.
The NRC examination team administered the operating examinations to the 15 applicants on October 8-17, 2002. Each reactor operator applicant participated in two dynamic simulator scenarios, a control room and facilities walkthrough test consisting of ten system tasks, and an administrative test consisting of one task or two questions in five areas. The six instant senior operator applicants participated in three scenarios, a control room and facilities walkthrough test consisting of ten system tasks, and an administrative test consisting of one task or two questions in five areas. The three applicants that were upgrading their reactor operator license to a senior operator license participated in two scenarios, a control room and facilities walkthrough test consisting of five system tasks and an administrative test consisting of one task or two questions in five areas.
b. Findings All applicants passed all parts of the operating examinations. The applicants demonstrated good 3-way communications, alarm response, and peer checking. For the written examinations, 14 of the 15 applicants passed the examination. The average written examination score for reactor operator applicants was 87.3 percent, and the average score for senior operator applicants was 89.1percent. The reactor operator applicant scores ranged from 76 to 95 percent, and the senior operator applicant scores ranged from 84 to 95 percent.
The licensee conducted a performance analysis for the written examinations with emphasis on seven questions missed by half or more of the applicants and submitted this analysis to the chief examiner for review. After reviewing the licensees analysis, the chief examiner concluded that all but one question were valid and that there were no apparent training deficiencies. The one question that was not valid, Question Ex02008 (Number 11 on the reactor operator examination and Number 12 on the senior operator examination), had the answer incorrect on the answer key. This answer key error was corrected and examination grades changed as applicable. There were no post-examination comments on examination questions. The analysis identified no common knowledge deficiency. No remediation training was determined to be necessary following the examinations. The text of the examination questions and the performance analysis may be accessed in the ADAMS system as noted in the attachment to this report.
-2-No findings of significance were identified.
.2 Initial Licensing Examination Development The licensee developed the written examination in accordance with NUREG-1021, Revision 8, Supplement 1, using facility training and operations staff on the security agreement to prepare and validate the examination.
.2.1 Examination Outline and Examination Package a. Examination Scope The facility licensee submitted the integrated examination outlines on June 6, 2002.
The chief examiner reviewed the submittal against the requirements of NUREG-1021, Revision 8, Supplement 1, and provided comments to the licensee. The facility licensee submitted the final draft examination package on August 13, 2002. The chief examiner reviewed the draft submittal against the requirements of NUREG-1021, Revision 8, Supplement 1, and provided comments to the licensee on the examination on September 9, 2002. The NRC conducted an onsite validation of the operating examinations and provided further comments during the week of September 23, 2002.
The licensee satisfactorily completed comment resolution on October 2, 2002.
b. Findings Region IV approved the initial examination outline and advised the licensee to proceed with the operating examination development.
The examiners determined that the written and operating examinations initially submitted by the licensee were within the range of acceptability expected for a proposed examination.
No findings of significance were identified.
.3 Simulation Facility Performance a. Examination Scope The examiners observed simulator performance with regard to plant fidelity during the examination validation and administration.
b. Findings No findings of significance were identified.
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.4 Examination Security a. Examination Scope The examiners reviewed examination security both during the onsite preparation week and examination administration week for compliance with NUREG-1021 requirements.
Plans for simulator security and applicant control were reviewed.
b. Findings No findings of significance were identified.
.4OA5 Management Meeting Exit Meeting Summary The chief examiner presented the examination results to Messrs. Gary Hendrick, Operations Production Manager, and Randy Guthrie, Operations Training Manager, at the conclusion of the operating examination on October 17, 2002. The licensee acknowledged the findings presented.
The licensee did not identify as proprietary any information or materials examined during the examination.
ATTACHMENT KEY POINTS OF CONTACT Licensee N. Patrou, Operations Initial Training Lead S. Hutchison, Senior Training Specialist J. Redwine, Simulator Training Specialist C. Golightly, Simulator Supervision NRC G. Repogle, Senior Resident Inspector ADAMS DOCUMENTS REFERENCED Accession No. ML023110529: Written examination for reactor and senior reactor operators Accession No. ML023110531: Written examination performance analysis Accession No. ML023110530: Written examination applicant questions