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Category:Letter
MONTHYEARIR 05000334/20240112024-10-17017 October 2024 License Renewal Phase IV Inspection Report 05000334/2024011 L-24-015, Twenty-Ninth Refueling Outage Inservice Inspection Summary Report2024-09-17017 September 2024 Twenty-Ninth Refueling Outage Inservice Inspection Summary Report ML24134A1522024-09-17017 September 2024 Exemption from the Requirements of 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule (EPID L-2024-LLE-0005) - Letter L-24-038, License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References2024-09-17017 September 2024 License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References ML24260A1912024-09-16016 September 2024 Operator Licensing Examination Approval IR 05000334/20240052024-08-29029 August 2024 Updated Inspection Plan for Beaver Valley Power Station, Units 1 and 2 (Reports 05000334/2024005 and 05000412/2024005) L-24-188, Submittal of Quality Assurance Program Manual, Revision 302024-08-27027 August 2024 Submittal of Quality Assurance Program Manual, Revision 30 IR 05000334/20244022024-08-22022 August 2024 Security Baseline Inspection Report 05000334/2024402 and 05000412/2024402 (Cover Letter Only) L-24-199, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-08-22022 August 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 IR 05000334/20240102024-08-20020 August 2024 Comprehensive Engineering Team Inspection - Inspection Report 05000334/2024010 and 05000412/2024010 L-24-186, Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024 Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule IR 05000334/20240022024-08-0505 August 2024 Integrated Inspection Report 05000334/2024002 and 05000412/2024002 ML24208A0462024-07-26026 July 2024 NRC Office of Investigations Case No. 1-2023-005 L-24-182, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-07-23023 July 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-161, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-07-19019 July 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-158, Reactor Trip Due to Bypass Feedwater Regulating Valve Failure to Control2024-07-17017 July 2024 Reactor Trip Due to Bypass Feedwater Regulating Valve Failure to Control L-24-014, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling Svstem Evaluation Models2024-07-16016 July 2024 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling Svstem Evaluation Models ML24193A2912024-07-16016 July 2024 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule IR 05000334/20245012024-07-0808 July 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000334/2024501 and 05000412/2024501 L-24-157, Unanalyzed Containment Bypass Condition Due to Degraded River Water Piping2024-07-0202 July 2024 Unanalyzed Containment Bypass Condition Due to Degraded River Water Piping L-24-164, BV-2, Post Accident Monitor Report2024-06-27027 June 2024 BV-2, Post Accident Monitor Report IR 05000334/20244012024-06-26026 June 2024 Material Control and Accounting Program Inspection Report 05000334/2024401 and 05000412/2024401 (Cover Letter Only) L-24-094, Reactor Vessel Surveillance Capsule Withdrawal Schedule2024-06-24024 June 2024 Reactor Vessel Surveillance Capsule Withdrawal Schedule L-24-152, Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations2024-06-17017 June 2024 Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations L-24-114, Automatic Reactor Trip Due to Low Reactor Coolant Flow Caused by Transformer Overexcitation Protection Relay Actuation2024-06-11011 June 2024 Automatic Reactor Trip Due to Low Reactor Coolant Flow Caused by Transformer Overexcitation Protection Relay Actuation L-24-115, Offsite AC Power Source Inoperable Due to Breaker Failure Resulting in Condition Prohibited by Technical Specification2024-06-0606 June 2024 Offsite AC Power Source Inoperable Due to Breaker Failure Resulting in Condition Prohibited by Technical Specification ML24135A2282024-05-29029 May 2024 Review of the Spring 2023 Outage Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F Star Reports ML24135A1702024-05-29029 May 2024 – Steam Generator Tube Inspection - Review of the Spring 2023 Tube Inspection Reports L-24-121, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-05-23023 May 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-021, Cycle 30 Core Operating Limits Report2024-05-23023 May 2024 Cycle 30 Core Operating Limits Report ML24141A1052024-05-20020 May 2024 Senior Reactor and Reactor Operator Initial License Examinations L-24-107, CFR 50.55a Request 1-TYP-5-RRP-l, for Alternative Method of Nondestructive Examination for River Water Outlet Piping Weld Repair2024-05-13013 May 2024 CFR 50.55a Request 1-TYP-5-RRP-l, for Alternative Method of Nondestructive Examination for River Water Outlet Piping Weld Repair IR 05000334/20240012024-05-0808 May 2024 Integrated Inspection Report 05000334/2024001 and 05000412/2024001 L-23-269, Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions2024-05-0707 May 2024 Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions L-24-054, Submittal of 2023 Annual Radioactive Effluent Release Report 2023 Annual Radiological Environmental Operating Report and 2023 Annual Environmental Operating Report (Non-Radiological)2024-04-29029 April 2024 Submittal of 2023 Annual Radioactive Effluent Release Report 2023 Annual Radiological Environmental Operating Report and 2023 Annual Environmental Operating Report (Non-Radiological) L-24-089, Emergency Preparedness Plan2024-04-23023 April 2024 Emergency Preparedness Plan L-24-088, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for March 20242024-04-22022 April 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 for March 2024 ML24101A2752024-04-10010 April 2024 Response to Request for Additional Information Regarding Spring 2023 180-Day Steam Generator Tube Inspection Report L-24-082, Withdrawal of Exemption Request2024-04-0303 April 2024 Withdrawal of Exemption Request L-24-013, Annual Notification of Property Insurance Coverage2024-03-26026 March 2024 Annual Notification of Property Insurance Coverage L-24-064, Submittal of Discharge Monitoring Report (NPDES) Permit No. PA00256152024-03-13013 March 2024 Submittal of Discharge Monitoring Report (NPDES) Permit No. PA0025615 ML24044A0662024-03-0404 March 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0083 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24057A0752024-03-0101 March 2024 the Associated Independent Spent Fuel Storage Installations IR 05000334/20230062024-02-28028 February 2024 Annual Assessment Letter for Beaver Valley Power Station, Units 1 and 2 (Reports 05000334/2023006 and 05000412/2023006) CP-202300502, Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions2024-02-23023 February 2024 Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions L-23-264, Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule2024-02-23023 February 2024 Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule L-24-050, Retrospective Premium Guarantee2024-02-22022 February 2024 Retrospective Premium Guarantee IR 05000334/20230042024-02-12012 February 2024 Integrated Inspection Report 05000334/2023004 and 05000412/2023004 ML24025A0922024-01-25025 January 2024 Requalification Program Inspection L-23-267, Submittal of Discharge Monitoring Report (Npdes), Permit No. PA00256152023-12-18018 December 2023 Submittal of Discharge Monitoring Report (Npdes), Permit No. PA0025615 2024-09-17
[Table view] Category:License-Operator Examination Report
MONTHYEARIR 05000334/20233012023-11-27027 November 2023 Initial Operator Licensing Examination Report 05000334/2023301 IR 05000412/20223012022-06-14014 June 2022 Initial Operator Licensing Examination Report 05000412/2022301 IR 05000334/20213012021-04-0101 April 2021 Initial Operator Licensing Examination Report 05000334/2021301 IR 05000412/20193012019-11-0505 November 2019 Initial Operator Licensing Examination Report 05000412/2019301 IR 05000412/20173012018-01-29029 January 2018 Initial Operator Licensing Examination Report 05000412/2017301 IR 05000334/20163022017-01-0303 January 2017 NRC Initial Operator Licensing Examination Report 05000334/2016302 IR 05000412/20163012016-02-17017 February 2016 Er 05000412/2016301; December 7 to 11, 2015, and December 14, 2015; Beaver Valley Power Station, Unit 2; Initial Operator Licensing Examination Report IR 05000334/20143012014-09-0404 September 2014 Er 05000334/2014301; July 7-14, 2014; Beaver Valley Power Station, Unit 1; Initial Operator Licensing Examination Report IR 05000412/20103012010-09-24024 September 2010 Er 05000412/2010301; August 16 - September 7, 2010; Beaver Valley Power Station, Unit 2; Initial Operator Licensing Examination Report IR 05000412/20083012009-01-26026 January 2009 Er 05000412-08-301, on 12/8-15/2008, Beaver Valley Unit 2; Initial Operator Licensing Examination Report IR 05000334/20073012007-12-14014 December 2007 Er 05000334-07-301, Exam Dates 11/9/2007 & 11/12-16/2007, BVPS-1, Initial Operator Licensing Examination. Eleven of Twelve Applicants Passed Examination. One SRO Upgrade Failed Written Exam. Twelve Applicants Included Four Ros, Six SRO Inst IR 05000334/20053012005-05-0606 May 2005 Er 05000334-05-301 and 05000412-05-301; 2/28/05 to 3/7/05; Beaver Valley Units 1 and 2; Initial Operator Licensing Examination. Ten of Eleven Applicants Passed the Examination, Two Reactor Operators, Seven SRO Instants, and One SRO Upgrade IR 05000412/20023022003-01-31031 January 2003 IR 05000412-02-302; on December 13, 2002 - January 10, 2003; Beaver Valley Power Station, Unit 2; Initial Operator Licensing Examination 2023-11-27
[Table view] |
Text
ary 3, 2017
SUBJECT:
BEAVER VALLEY POWER STATION, UNIT 1 - NRC INITIAL OPERATOR LICENSING EXAMINATION REPORT 05000334/2016302
Dear Mr. Richey:
On November 9, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed an examination at Beaver Valley Power Station, Unit 1. The enclosed examination report documents the examination results, which were discussed on December 15, 2016, with Mr. D. Gibson, Site Training Manager, and other members of your staff.
The examination included the evaluation of 12 applicants for reactor operator licenses, and 10 applicants for instant senior reactor operator licenses. The written and operating examinations were developed using NUREG-1021, "Operator Licensing Examination Standards for Power Reactors," Revision 10. The license examiners determined that all of the applicants satisfied the requirements of 10 CFR Part 55, and the appropriate licenses were issued on December 15, 2016.
No findings were identified during this examination.
In accordance with Title 10 of Code of Federal Regulation (CFR), 10 CFR 2.390 of 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 (PARS) component of NRCs Agencywide Documents Access Management System (ADAMS).
ADAMS is accessible from the NRC website http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Donald E. Jackson, Chief Operations Branch Division of Reactor Safety Docket No.: 50-334
SUBJECT:
BEAVER VALLEY POWER STATION, UNIT 1 - NRC INITIAL OPERATOR LICENSING EXAMINATION REPORT 05000334/2016302
Dear M
SUMMARY
ER 05000334/2016302; 10/31/2016 - 11/14/2016; Beaver Valley Power Station, Unit 1; Initial
Operator Licensing Examination Report Seven NRC examiners evaluated the competency of 12 applicants for reactor operator licenses and 10 applicants for instant senior reactor operator licenses at Beaver Valley Power Station,
Unit 1. The facility licensee developed the examinations using NUREG-1021, "Operator Licensing Examination Standards for Power Reactors," Revision 10. The NRC examiners administered the operating tests on October 31 through November 9, 2016. The written examinations were administered by the facility on November 14, 2016. The NRC examiners determined that all of the applicants satisfied the requirements of 10 CFR Part 55, and the appropriate licenses have been issued.
NRC-Identified and Self-Revealing Findings
No findings were identified.
Licensee-Identified Violations
None.
REPORT DETAILS
OTHER ACTIVITIES (OA)
4OA5 Other Activities (Initial Operator License Examination)
.1 License Applications
a. Scope
The examiners reviewed all 22 license applications submitted by the licensee to ensure the applications reflected that each applicant satisfied relevant license eligibility requirements. The applications were submitted on NRC Form 398, Personal Qualification Statement, and NRC Form 396, Certification of Medical Examination by Facility Licensee. The examiners also audited the eligibility of the applicants to confirm that they reflected the subject applicants qualifications. This audit also focused on control manipulations that provided significant reactivity changes.
b. Findings
No findings were identified.
.2 Operator Knowledge and Performance
a. Examination Scope
On November 14, 2016, the licensee proctored the administration of the written examinations to all 22 applicants. The licensee staff graded the written examinations, analyzed the results, and presented their analysis to the NRC on November 22, 2016.
The NRC examination team administered the various portions of the operating examination to all 22 applicants from October 31 through November 9, 2016. The 12 applicants for reactor operator licenses participated in two or three dynamic simulator scenarios, in a control room and facilities walkthrough test consisting of 11 system tasks, and an administrative test consisting of four administrative tasks. The 10 applicants seeking an instant senior reactor operator license participated in three dynamic simulator scenarios, a control room and facilities walkthrough test consisting of 10 system tasks, and an administrative test consisting of five administrative tasks.
b. Findings
All of the applicants passed all parts of the operating test and the written examination.
For the written examinations, the reactor operator applicants average score was 85.8 percent and ranged from 80.0 to 92.0 percent, the senior operator applicants average score was 84.3 percent and ranged from 80.0 to 93.0 percent. The overall written examination average was 85.1 percent. The text of the examination questions and the licensees post-examination comments may be accessed in the ADAMS system under the accession numbers noted in Attachment 1. In accordance with current NRC policy, the release of this written examination, post-examination comments, and the operating test in ADAMS to the public will be delayed for two years.
Chapter ES-403 and Form ES-403-1 of NUREG 1021 require the licensee to analyze the validity of any written examination questions that were missed by half or more of the applicants. The licensee conducted this performance analysis for 12 questions that met these criteria and submitted the analysis to the chief examiner. This analysis concluded that there were potential generic training program weaknesses that will be tracked by the corrective action program (CR 2016-13494).
The licensee submitted three post-examination question comments on November 22, 2016. The NRC reviewed the facilitys post-exam comment submittal package and accepted facility recommendations on Questions 35, 42, and 71. For Questions 35 and 42, one of the distractors in each question was, after-the-fact, also determined to be a correct answer. For Question 71, it was also determined after-the-fact that the designated correct answer was incorrect and one of the distractors was correct. The answer key was changed so that for Question 35 choices A and B were accepted as correct responses. Question 42 was changed such that choices B and C were accepted as correct responses. Question 71 was changed so that C instead of A was the correct response. The text of the examination questions and the licensees post-examination comments with the NRC resolutions may be accessed in the ADAMS system under the accession numbers noted in the Attachment 1. In accordance with current NRC policy the release of these documents will be delayed for two years.
.3 Initial Licensing Examination Development
a. Examination Scope
The facility licensee developed the examinations in accordance with NUREG-1021, Revision 10. All licensee facility training and operations staff involved in examination preparation and validation were listed on a security agreement. The facility licensee submitted both the written and operating examination outlines on July 29, 2016. The chief examiner reviewed the outlines against the requirements of NUREG-1021, and provided comments to the licensee. The facility licensee submitted the draft examination package on August 30, 2016. The chief examiner reviewed the draft examination package against the requirements of NUREG-1021, and provided comments to the licensee. The NRC conducted an onsite validation of the operating examinations and provided further comments during the week of September 12, 2016.
The licensee satisfactorily completed comment resolution on the week of October 24, 2016.
b. Findings
The NRC 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 were identified.
.4 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 were identified.
.5 Examination Security
a. Examination Scope
The examiners reviewed examination security for examination development and during both the onsite preparation week and examination administration week for compliance with NUREG-1021, Revision 10 requirements. Plans for simulator security and applicant control were reviewed and discussed with licensee personnel.
b. Findings
No findings were identified.
4OA6 Meetings, Including Exit
The chief examiner presented the examination results to Mr. D. Gibson, Site Training Manager, and other members of the licensee's management staff on December 15, 2016. The licensee acknowledged the findings presented.
The licensee did not identify any information or materials used during the examination as proprietary.
ATTACHMENTS:
SUPPLEMENTARY INFORMATION
KEY POINTS OF CONTACT
Licensee Personnel
- P. Eisenmann, Staff Nuclear Operations Instructor - Exam Developer
- T. Gaydosik, Fleet Exam Development Lead
- D. Gibson, Manager Site Training
- M. Klingensmith, Staff Nuclear Operations Instructor - Exam Developer
- G. Pelka, Supervisor Licensed Operator Initial Training
- D. Ronnenberg, Superintendent Operations Training
- S. Snook, Shift Manager - Exam Facility Representative
ITEMS OPENED, CLOSED, AND DISCUSSED
Opened
NONE
Opened and Closed
NONE
Closed
NONE
Discussed
NONE
ADAMS DOCUMENTS REFERENCED