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Category:Letter
MONTHYEARML24025A0922024-01-25025 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 IR 05000334/20230112023-12-0404 December 2023 Age-Related Degradation Inspection Report 05000334/2023011 and 05000412/2023011 L-23-229, Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports2023-11-29029 November 2023 Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports IR 05000334/20233012023-11-27027 November 2023 Initial Operator Licensing Examination Report 05000334/2023301 L-23-247, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-11-17017 November 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 IR 05000334/20230032023-11-0606 November 2023 Integrated Inspection Report 05000334/2023003 and 05000412/2023003 L-23-227, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 20232023-10-20020 October 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 2023 ML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23198A3592023-10-0202 October 2023 Issuance of Amendment Nos. 322 and 212 Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident (EPID L-2022-LLA-0129) - Nonproprietary IR 05000334/20234022023-09-29029 September 2023 Security Baseline Inspection Report 05000334/2023402 and 05000412/2023402 (Cover Letter Only) ML23237B4222023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Letter Regarding Order Approving Transfer of Licenses and Draft Conforming License Amendments ML23269A1242023-09-27027 September 2023 Request for Withholding Information from Public Disclosure IR 05000334/20234012023-09-21021 September 2023 Cybersecurity Inspection Report 05000334/2023401 and 05000412/2023401 (Cover Letter Only) ML23263A0192023-09-20020 September 2023 Operator Licensing Examination Approval ML23243A9272023-09-19019 September 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report ML23249A1842023-09-18018 September 2023 Authorization and Safety Evaluation for Alternative Request No. 2-TYP-4-RV-06 L-23-208, Submittal of Discharge Monitoring Report Cnpdes), Permit No. PA00256152023-09-14014 September 2023 Submittal of Discharge Monitoring Report Cnpdes), Permit No. PA0025615 L-23-167, Twenty-Third Refueling Outage Inservice Inspection Summary Report2023-09-13013 September 2023 Twenty-Third Refueling Outage Inservice Inspection Summary Report L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023 Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments IR 05000334/20230052023-08-31031 August 2023 Updated Inspection Plan for Beaver Valley Power Station Units 1 and 2 (Report 05000334/2023005 and 05000412/2023005) L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023 Quality Assurance Program Manual ML23129A1722023-08-25025 August 2023 Request for Withholding Information from Public Disclosure for Beaver Valley Power Station, Units 1 and 2; Davis Besse Nuclear Power Station, Unit 1; and Perry Nuclear Power Plant, Unit 1 IR 05000334/20230022023-08-0909 August 2023 Integrated Inspection Report 05000334/2023002 and 05000412/2023002 ML23219A0592023-08-0707 August 2023 Steam Generator Inspection Reports - Spring 2023 Spring Refueling Outrage L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-179, Submittal of Discharge Monitoring Report, (NPDES) Permit No. PA00256152023-07-18018 July 2023 Submittal of Discharge Monitoring Report, (NPDES) Permit No. PA0025615 ML23188A0982023-07-17017 July 2023 Correction to the Safety Evaluation Issued Related to Amendment Nos. 321 and 211 Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time ML23188A0672023-07-10010 July 2023 Project Manager Assignment L-23-165, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-06-26026 June 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-23-139, Response to Request for Additional Information Regarding Fall 2022 180-Day Steam Generator Tube Inspection Report2023-06-13013 June 2023 Response to Request for Additional Information Regarding Fall 2022 180-Day Steam Generator Tube Inspection Report ML23157A1072023-06-0707 June 2023 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000334/2023011 and 05000412/2023011 ML23143A0272023-05-23023 May 2023 Licensed Operator Positive Fitness-For-Duty Test L-23-055, Submittal of the Updated Final Safety Analysis Report, Revision 342023-05-23023 May 2023 Submittal of the Updated Final Safety Analysis Report, Revision 34 ML23102A1472023-05-22022 May 2023 Issuance of Amendment Nos. 321 and 211 Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time L-23-065, Annual Financial Report2023-05-22022 May 2023 Annual Financial Report ML23135A7872023-05-19019 May 2023 Summary of Conference Calls Regarding the Spring 2023 Steam Generator Tube Inspections L-23-137, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-05-18018 May 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 ML23124A1742023-05-17017 May 2023 Energy Harbor Fleet Vistra License Transfer - Request for Withholding Information from Public Disclosure for Commance Peak Plant, Units 1 & 2, Beaver Valley Station, Units 1 & 2, Davis Besse Station, Unit 1 and Perry Plant, Unit 1 L-23-125, Cycle 24 Core Operating Limits Report2023-05-17017 May 2023 Cycle 24 Core Operating Limits Report ML23124A3882023-05-16016 May 2023 Summary of Regulatory Audit in Support of License Amendment Request to Revise Technical Specification 5.6.3, Core Operating Limits Reports (COLR) and TS 4.2.1 Fuel Assemblies ML23129A0112023-05-16016 May 2023 Notice of Consideration of Approval of Indirect and Direct License Transfer for Comanche Peak Plant, Units 1 & 2, Beaver Valley Station, Units 1 & 2, Davis Besse Station, Unit 1 and Perry Plant, Unit 1 (EPID L-2023-LLM-0000) (Letter) L-23-132, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-10010 May 2023 Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations IR 05000334/20230012023-05-0808 May 2023 Integrated Inspection Report 05000334/2023001 and 05000412/2023001 L-23-129, Response to Request for Additional Information for 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations2023-05-0505 May 2023 Response to Request for Additional Information for 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations ML23118A3812023-04-28028 April 2023 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations L-23-115, Submittal of 2022 Annual Radioactive Effluent Release Report, 2022 Annual Radiological Environmental Operating Report, and 2022 Annual Environmental Operating Report (Non-Radiological2023-04-27027 April 2023 Submittal of 2022 Annual Radioactive Effluent Release Report, 2022 Annual Radiological Environmental Operating Report, and 2022 Annual Environmental Operating Report (Non-Radiological L-23-126, Discharge Monitoring Report (Npdes), Permit No. PA00256152023-04-22022 April 2023 Discharge Monitoring Report (Npdes), Permit No. PA0025615 CP-202300181, ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI, Corrected Affidavit for Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-04-20020 April 2023 ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI, Corrected Affidavit for Application for Order Consenting to Transfer of Licenses and Conforming License Amendments ML23107A2502023-04-18018 April 2023 Requalification Program Inspection 2024-01-25
[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
ber 14, 2007
SUBJECT:
BEAVER VALLEY POWER STATION, UNIT 1 - OPERATOR AND SENIOR REACTOR OPERATOR INITIAL EXAMINATION REPORT NO. 05000334/2007-301
Dear Mr. Sena:
This report transmits the results of the reactor operator (RO) and senior reactor operator (SRO)
licensing examination conducted by the NRC during the period of November 9 - 16, 2007. This examination addressed areas important to public health and safety and was developed and administered using the guidelines of the Examination Standards for Power Reactors (NUREG-1021, Revision 9).
Based on the results of the examination, eleven of twelve applicants passed all portions of the examination. One SRO upgrade did not pass the written exam. The twelve applicants included four ROs, six instant SROs, and two upgrade SROs. Mr. Todd Fish, NRC Chief Examiner, discussed performance insights observed during the examination with Mr. Brian Tuite and other members of your training staff on November 16, 2007. On December 10, 2007, final examination results, including individual license numbers for the applicants who passed all portions of the exam, were given during a telephone call between Mr. R. Brooks of your training staff and Mr. D. Silk (NRC).
In accordance with 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 document management system (ADAMS). These records include the final examination and are available in ADAMS (Master File - Accession Number ML072040334; RO and SRO Written Examination with Answer Key - Accession Number ML073340190; Final Section A Operating Exam -
Accession Number ML073340251; Final Section B Operating Exam - Accession Number ML073340286; and Final Section C Operating Exam - Accession Number ML073340322).
ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Mr. Should you have any questions regarding this examination, please contact me at (610) 337-5046, or by E-mail at MDS1@NRC.GOV.
Sincerely,
/RA/
Marvin D. Sykes, Chief Operations Branch Division of Reactor Safety Docket No: 50-334 License No: DPR-66 Enclosure: Initial Examination Report No. 05000334/2007-301
M
SUMMARY OF FINDINGS
ER 05000334/2007301; exam dates 11/9/2007 and 11/12-16/2007; BVPS-1; Initial Operator
Licensing Examination. Eleven of twelve applicants passed the examination. One SRO upgrade failed the written exam. The twelve applicants included four ROs, six SRO instants, and two SRO upgrades.
The written examinations were administered by the facility and the operating tests were administered by three NRC region-based examiners.
A. Inspector Identified Findings No findings of significance were identified.
B. Licensee Identified Findings No findings of significance were identified.
ii
REPORT DETAILS
REACTOR SAFETY
Mitigating Systems - Reactor Operator (RO) and Senior Reactor Operator (SRO) Initial License Examination
a. Scope
of Review The NRC examination team developed the written and operating initial examination and together with BVPS-1 training and operations personnel verified or ensured, as applicable, the following:
- The examination was prepared and developed in accordance with the guidelines of Revision 9 of NUREG-1021, "Operator Licensing Examination Standards for Power Reactors. A review was conducted both in the Region I office and at the BVPS-1 plant and training facility. Final resolution of comments and incorporation of test revisions were conducted during and following the onsite preparation week.
- Simulation facility operation was proper.
- A test item analysis was completed on the written examination for feedback into BVPS-1s systems approach to training program.
- Examination security requirements were met.
The NRC examiners administered the operating portion of the examination to all applicants from November 12 - 16, 2007. The written examination was previously administered by the BVPS-1 training staff on November 9, 2007.
b. Findings
Grading and Results Eleven of twelve applicants passed all portions of the initial licensing examination. One SRO upgrade failed the written exam. The twelve applicants included four ROs, six SRO instants, and two SRO upgrades. The facility submitted comments related to two questions on the written exam. A summary of the facility comments and NRC resolution of those comments are provided as Attachment 2.
Examination Administration and Performance No findings of significance were identified.
4OA6 Exit Meeting Summary
On December 10, 2007, the NRC provided examination results to BVPS - 1 training representatives via telephone. License numbers for the applicants who passed all portions of the exam were also provided during this call.
The NRC expressed appreciation for the cooperation and assistance that was provided during the preparation and administration of the examination by the licensees training staff.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
ATTACHMENT ONE
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee Personnel
M. Mouser Operations Manager Unit 1
B. Tuite Training Manager
R. Brooks Exam Development Lead
T. Gaydosik Initial License Lead
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
ITEM NUMBER TYPE DESCRIPTION
NONE NA NA
ATTACHMENT TWO
Facility Post Exam Comments
Common Question #41
Facility Comment: This question asked the applicants to determine how the loss of
instrument air would affect auxiliary feedwater (AFW) system operation
and the subsequent action an operator would take. The facility asserted
that conditions given in the question stem (the conditions said the plant
was in Mode 3) were subject to interpretation, i.e., the given conditions
did not make clear whether the plant was in Mode 3 and starting up, or in
Mode 3 following a trip from rated power. Based on two interpretations of
plant conditions in Mode 3, therefore, the question had two correct
answers.
NRC Response: Comment accepted. A (an additional correct answer) & B (original
correct answer) will both be considered correct. The examiner reviewed
the exhibits provided by the facility and determined that operation of the
AFW system depends on whether the operator is in Mode 3, just starting
up or in Mode 3, post reactor trip. The original question was designed
based on the plant being in Mode 3 during a start up. Under these
conditions there would be no decay heat. However, if the plant were in
Mode 3 just after a reactor trip, then decay heat would require the
operator to adjust AFW flow, and, per procedure, leave only the turbine
driven AFW pump running. Since plant conditions provided in the
question were plausible for Mode 3 and starting up, as well as for Mode 3
just after a reactor trip at power, an applicant could reasonably answer
the question two different ways. Therefore, there are two correct
answers.
SRO Question #18
Facility Comment: This question asked the SRO applicants to integrate plant conditions due
to a loss of coolant accident, then enter emergency procedures and
determine how the pressurizer power operated relief valves (PORVs)
were to be operated. The conditions given in the stem were ambiguous
such that the question had two correct answers.
NRC Response: Comment accepted. B (an additional correct answer) & D (original
correct answer) will both be considered correct. The examiner reviewed
the information provided by the facility and determined that operation of
the PORVs - to isolate them or to allow them to operate automatically -
depends on whether the operator believes the PORVs are open or
closed. The original question was designed based on the PORVs being
closed, therefore choice D was the correct answer. However, if the
PORVs were not closed, and in fact were the source of the loss of
coolant, then the correct response is for the operator to isolate those
valves, which makes B also a correct answer. The conditions provided
in the question do not give PORV status, e.g., The PORVs are
closed(open)., nor do the provided plant parameters indicate whether
PORVs are open or closed. Therefore, given the ambiguity of the plant
conditions, an applicant could reasonably choose two different and
correct answers to the question.
Attachment