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Category:Inspection Report
MONTHYEARIR 05000348/20244012024-09-10010 September 2024 Security Baseline Inspection Report 05000348-2024401 and 05000364-2024401 IR 05000348/20244022024-08-26026 August 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000348/2024402 and 05000364/2024402 IR 05000348/20240052024-08-26026 August 2024 Updated Inspection Plan for Joseph M. Farley Nuclear Plant, Units 1 and 2 - Report 05000348/2024005 and 05000364/2024005 IR 05000348/20240022024-08-12012 August 2024 – Integrated Inspection Report 05000348-2024002 and 05000364-2024002 and Exercise of Enforcement Discretion IR 05000348/20240012024-04-24024 April 2024 Integrated Inspection Report 05000348/2024001 and 05000364/2024001 IR 05000348/20240102024-04-16016 April 2024 NRC Inspection Report 05000348/2024010 and 05000364/2024010 IR 05000348/20240112024-04-12012 April 2024 Fire Protection Team Inspection Report 05000348/2024011 and 05000364/2024011 IR 05000348/20230062024-02-28028 February 2024 Annual Assessment Letter for Joseph M. Farley Nuclear Plant, Units 1 and 2 - Report 05000348/2023006 and 05000364/2023006 IR 05000348/20230042024-02-0909 February 2024 Integrated Inspection Report 05000348/2023004 and 05000364/2023004 and Exercise of Enforcement Discretion IR 05000348/20230402024-01-24024 January 2024 95001 Supplemental Inspection Report 05000348/2023040 and Follow-Up Assessment Letter ML23346A2222023-12-22022 December 2023 Transmittal of Dam Inspection Report - Public IR 05000348/20230032023-10-24024 October 2023 Integrated Inspection Report 05000348/2023003 and 05000364/2023003 IR 05000348/20230912023-10-19019 October 2023 Final Significance Determination of a White Finding and Notice of Violation and Assessment Followup Letter NRC Inspection Report 05000348/2023091 IR 05000348/20234022023-10-18018 October 2023 Security Baseline Inspection Report 05000348/2023402 and 05000364/2023402 IR 05000348/20234412023-10-12012 October 2023 Supplemental Inspection Report 05000348/2023441 and 05000364/2023441 and Follow-Up Assessment Letter (Cover Letter) IR 05000348/20230902023-08-31031 August 2023 NRC Inspection Report 05000348/2023090 and Preliminary White Finding and Apparent Violation IR 05000348/20330012023-08-14014 August 2023 NRC Operator License Examination Report 05000348/203301 and 05000364/2023302 IR 05000348/20230022023-08-10010 August 2023 Integrated Inspection Report 05000348/2023002 and 05000364/2023002, and Apparent Violation IR 05000348/20230102023-06-29029 June 2023 Comprehensive Engineering Team Inspection (CETI) Baseline Inspection Report 05000348/2023010 and 05000364/2023010 IR 05000348/20234402023-05-0505 May 2023 Reissue Farley Units-Final Significance Determination for a Security-Related Greater than Green Finding, Nov and Assessment Followup LTR, IR 05000348/2023440 and 05000364/2023440 - Cover IR 05000348/20230012023-05-0404 May 2023 Integrated Inspection Report 05000348/2023001 and 05000364/2023001 IR 05000348/20230112023-04-13013 April 2023 Biennial Problem Identification and Resolution Inspection Report 05000348/2023011 and 05000364/2023011 IR 05000348/20234012023-03-31031 March 2023 Security Baseline Inspection Report 05000348/2023401 and 05000364/2023401 IR 05000348/20220062023-03-0101 March 2023 Annual Assessment Letter for Joseph M. Farley Nuclear Plant, Units 1 and 2 Report 05000348/2022006 and 05000364/2022006 IR 05000348/20220112023-02-16016 February 2023 NRC Inspection Report 05000348/2022011 IR 05000348/20220902023-02-16016 February 2023 NRC Inspection Report 05000348/2022090 IR 05000348/20220042023-01-23023 January 2023 Integrated Inspection Report 05000348/2022004 and 05000364/2022004 ML22343A0382022-12-13013 December 2022 Notification of Joseph M. Farley Nuclear Plant Comprehensive Engineering Team Inspection (CETI) Baseline Inspection Report 05000348/2023010 and 05000364/2023010 IR 05000348/20224042022-11-29029 November 2022 Security Baseline Inspection Report 05000348/2022404 and 05000364/2022404 IR 05000348/20224402022-11-0707 November 2022 Special Inspection Report 05000348/2022440 and 05000364/ 2022440 and Preliminary Greater than Green Finding and and Apparent Violation (Cover Letter) IR 05000348/20220032022-10-28028 October 2022 Integrated Inspection Report 05000348/2022003 and 05000364/2022003 IR 05000348/20220502022-09-30030 September 2022 Special Inspection Reactive Report 05000348/2022050 and Apparent Violation IR 05000348/20220052022-08-24024 August 2022 Updated Inspection Plan for Joseph M. Farley Nuclear Plant, Units 1 and 2 - Report 05000348/2022005 and 05000364/2022005 IR 05000348/20220022022-08-12012 August 2022 Integrated Inspection Report 05000348/2022002 and 05000364/2022002 ML22214B8262022-08-0404 August 2022 Security Baseline Inspection Report 05000348/2022403 and 05000364/2022403 IR 05000348/20233012022-08-0101 August 2022 Notification of Licensed Operator Initial Examination 05000348/2023301 and 05000364/2023301 IR 05000348/20224022022-07-26026 July 2022 Security Baseline Inspection Report 05000348/2022402 and 05000364/2022402 IR 05000348/20224012022-05-0606 May 2022 Cyber Security Inspection Report 05000348/2022401 and 05000364/2022401 IR 05000348/20220012022-05-0404 May 2022 Integrated Inspection Report 05000348/2022001 and 05000364/2022001 IR 05000348/20220102022-03-22022 March 2022 Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000348/2022010 and 05000364/2022010 IR 05000348/20210062022-03-0202 March 2022 Annual Assessment Letter for Joseph M. Farley Nuclear Plant Units 1 and 2 (Report No. 05000348/2021006 and 05000364/2021006) IR 05000348/20210042022-02-0808 February 2022 Integrated Inspection Report 05000348/2021004 and 05000364/2021004 IR 05000348/20210112021-12-13013 December 2021 Design Basis Assurance Inspection (Programs) Inspection Report 05000348/2021011 and 05000364/2021011 ML21347A4422021-12-13013 December 2021 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000348/2022401; 05000364/2022401 IR 05000348/20214032021-12-0202 December 2021 Security Baseline Inspection Report 05000348/2021403 and 05000364/2021403 IR 05000348/20210032021-11-10010 November 2021 Integrated Inspection Report 05000348/2021003, 05000364/2021003, and 07200042/2021001 IR 05000348/20214022021-09-15015 September 2021 Security Baseline Inspection Report 05000348/2021402 and 05000364/2021402 IR 05000348/20210052021-08-24024 August 2021 Updated Inspection Plan for Joseph M. Farley Nuclear Plant Units 1 and 2 (Report 05000348/2021005 and 05000364/2021005) IR 05000348/20213012021-08-18018 August 2021 NRC Operator License Examination Report 05000348/2021301 and 05000364/2021301 IR 05000348/20210022021-07-30030 July 2021 Integrated Inspection Report 05000348/2021002 and 05000364/2021002 and Exercise of Enforcement Discretion 2024-09-10
[Table view] Category:Letter
MONTHYEARNL-24-0320, License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,.2024-09-27027 September 2024 License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,. NL-24-0349, Units 1 and 2 - 10 CFR 26.719(c)(1) 30-Day Report Blind Performance Test Results Inconsistent with Sample Provided2024-09-20020 September 2024 Units 1 and 2 - 10 CFR 26.719(c)(1) 30-Day Report Blind Performance Test Results Inconsistent with Sample Provided NL-24-0341, Response to Request for Additional Information Related to the Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency2024-09-10010 September 2024 Response to Request for Additional Information Related to the Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency IR 05000348/20244012024-09-10010 September 2024 Security Baseline Inspection Report 05000348-2024401 and 05000364-2024401 ML24247A1102024-09-0505 September 2024 Corporate Notification Letter Aka 210-day Letter NUREG Rev 12 NL-24-0259, License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes2024-09-0404 September 2024 License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes NL-24-0340, Unit 1 - Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1 R322024-09-0404 September 2024 Unit 1 - Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1 R32 ML24242A1332024-08-29029 August 2024 Issuance of Amendment Nos. 250 and 247, Regarding License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, Actions (EPID L-2024-LLA-0098) - Non-Proprietary ML24240A0812024-08-27027 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Revised Completion Time ML24233A0022024-08-27027 August 2024 Request for Withholding Information from Public Disclosure for Joseph M. Farley Nuclear Plant, Units 1 and 2, License Amendment Request Supplement to Change Technical Specification 3.6.5, Containment Air Temperature Actions IR 05000348/20240052024-08-26026 August 2024 Updated Inspection Plan for Joseph M. Farley Nuclear Plant, Units 1 and 2 - Report 05000348/2024005 and 05000364/2024005 IR 05000348/20244022024-08-26026 August 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000348/2024402 and 05000364/2024402 ML24226B2112024-08-22022 August 2024 Regulatory Audit Summary in Support of License Amendment Requests to Revise Technical Specification 3.6.5, Containment Air Temperature, Actions NL-24-0321, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information2024-08-16016 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information IR 05000348/20240022024-08-12012 August 2024 – Integrated Inspection Report 05000348-2024002 and 05000364-2024002 and Exercise of Enforcement Discretion ML24215A3772024-08-0707 August 2024 2024 Farley Requal Inspection Corporate Notification Letter ML24201A2032024-08-0101 August 2024 Request for Withholding Information from Public Disclosure for Joseph M. Farley Nuclear Plant, Units 1 and 2, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions ML24200A1392024-07-25025 July 2024 Regulatory Audit in Support of Review of the License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature ML24199A2072024-07-24024 July 2024 TS 3-6-5 LAR - Individual Notice Transmittal Letter and NSHC - Rev 1 (1) - Letter NL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 NL-24-0281, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions2024-07-18018 July 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions NL-24-0227, Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2024-07-0303 July 2024 Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML24184A0452024-07-0202 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24178A3762024-07-0101 July 2024 Nonacceptance of Requested Licensing Action License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, Using Risk-Informed Process for Evaluations NL-24-0234, Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown2024-06-28028 June 2024 Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown NL-24-0230, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-3602024-06-28028 June 2024 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-360 NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in NL-24-0235, Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel2024-06-19019 June 2024 Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel NL-24-0201, Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2024-06-18018 June 2024 Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0221, Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift2024-06-17017 June 2024 Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift NL-24-0238, RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information2024-06-14014 June 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information NL-24-0229, Notice of Intent to Pursue Subsequent License Renewal2024-06-0707 June 2024 Notice of Intent to Pursue Subsequent License Renewal ML24149A0492024-06-0404 June 2024 SNC Fleet - Regulatory Audit in Support of Review of the License Amendment Request to Revise TS 1.1, Use and Application Definitions, and Add New Technical Specification 5.5.21 and 5.5.17, Online Monitoring Program, ML24143A0412024-05-28028 May 2024 Supplemental Information Needed for Using the Risk-Informed Process for Evaluation for the LAR to Change Technical Specification 3.6.5, Containment Air Temperature, Actions NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024 SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024 Annual Radiological Environmental Operating Reports for 2023 NL-24-0064, Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.52024-05-0303 May 2024 Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.5 NL-24-0188, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report NL-24-0165, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20232024-04-25025 April 2024 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2023 IR 05000348/20240012024-04-24024 April 2024 Integrated Inspection Report 05000348/2024001 and 05000364/2024001 NL-24-0137, RIPE License Amendment Request to Change Containment Air Temperature Actions2024-04-19019 April 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions IR 05000348/20240102024-04-16016 April 2024 NRC Inspection Report 05000348/2024010 and 05000364/2024010 NL-24-0123, for Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel2024-04-15015 April 2024 for Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel NL-24-0134, Renewed National Pollutant Discharge Elimination System (NPDES) Permit2024-04-12012 April 2024 Renewed National Pollutant Discharge Elimination System (NPDES) Permit IR 05000348/20240112024-04-12012 April 2024 Fire Protection Team Inspection Report 05000348/2024011 and 05000364/2024011 NL-24-0088, Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency2024-04-0505 April 2024 Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency NL-24-0115, Response to Request for Additional Information Exemption Requests for Physical.2024-04-0404 April 2024 Response to Request for Additional Information Exemption Requests for Physical. NL-24-0116, Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred.2024-03-29029 March 2024 Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred. ML24061A1692024-03-22022 March 2024 PM Reassignment Letter Farley March 2024 NL-24-0092, Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 2R292024-03-15015 March 2024 Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 2R29 2024-09-05
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION ember 18, 2008
SUBJECT:
REACTOR AND SENIOR REACTOR OPERATOR INITIAL EXAMINATIONS -
JOSEPH M. FARLEY NUCLEAR PLANT 05000348/2008301 AND 05000364/2008301
Dear Mr. Johnson:
During the period of October 27 - November 07, 2008, the Nuclear Regulatory Commission (NRC) administered operating examinations to employees of your company who had applied for licenses to operate the Farley Nuclear Plant. At the conclusion of the examination, the examiners discussed the examination questions and preliminary findings with those members of your staff identified in the enclosed report. The written examination was administered by your staff on November 10, 2008.
Eight Senior Reactor Operator (SRO) applicants and three Reactor Operator (RO) applicants passed both the written and operating examinations. One SRO applicant and one RO applicant took only the written examination and both passed. One SRO applicant and one RO applicant failed the written examination. There were two post examination comments. These comments and the NRC resolution of these comments are summarized in Enclosure 2. A Simulation Facility Report is included in this report as Enclosure 3.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter ber 18, 2008
SUBJECT:
REACTOR AND SENIOR REACTOR OPERATOR INITIAL EXAMINATIONS -
JOSEPH M. FARLEY NUCLEAR PLANT 05000348/2008301 AND 05000364/2008301
Dear Mr. Johnson:
During the period of October 27 - November 07, 2008, the Nuclear Regulatory Commission (NRC) administered operating examinations to employees of your company who had applied for licenses to operate the Farley Nuclear Plant. At the conclusion of the examination, the examiners discussed the examination questions and preliminary findings with those members of your staff identified in the enclosed report. The written examination was administered by your staff on November 10, 2008.
Eight Senior Reactor Operator (SRO) applicants and three Reactor Operator (RO) applicants passed both the written and operating examinations. One SRO applicant and one RO applicant took only the written examination and both passed. One SRO applicant and one RO applicant failed the written examination. There were two post examination comments. These comments and the NRC resolution of these comments are summarized in Enclosure 2. A Simulation Facility Report is included in this report as Enclosure 3.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS).
_________________________ XG SUNSI REVIEW COMPLETE OFFICE RII:DRS RII:DRS SIGNATURE /RA/ FEhrhardt /ra/for NAME MBates MWidmann DATE 12/18/2008 12/18/2008 12/ /2008 12/ /2008 12/ /2008 12/ /2008 12/ /2008 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO
SNC 3 cc w/encl:
Angela Thornhill Moanica Caston Managing Attorney and Compliance Officer Vice President and General Counsel Southern Nuclear Operating Company, Inc. Southern Nuclear Operating Company, Inc.
Electronic Mail Distribution Electronic Mail Distribution B. D. McKinney Dr. D. E. Williamson Licensing Services Manager State Health Officer B-031 Alabama Dept. of Public Health Southern Nuclear Operating Company, Inc. Electronic Mail Distribution Electronic Mail Distribution Mr. Mark Culver Jeffrey T. Gasser Chairman Executive Vice President Houston County Commission Southern Nuclear Operating Company, Inc. P. O. Box 6406 Electronic Mail Distribution Dothan, AL 36302 William D. Oldfield Jim Sommerville Quality Assurance Supervisor (Acting) Chief Southern Nuclear Operating Company Environmental Protection Division Electronic Mail Distribution Department of Natural Resources Electronic Mail Distribution L. Mike Stinson Vice President Senior Resident Inspector Fleet Operations Support Southern Nuclear Operating Company, Inc.
Southern Nuclear Operating Company, Inc. Joseph M. Farley Nuclear Plant Electronic Mail Distribution U.S. NRC 7388 N. State Highway 95 David H. Jones Columbia, AL 36319 Vice President Engineering Southern Nuclear Operating Company, Inc.
Southern Nuclear Operating Company, Inc. ATTN: Mr. John G. Horn, Plant Training &
Electronic Mail Distribution Emergency Preparedness Manager Farley Nuclear Plant P.O. Box 470 Ashford, AL 36312
SNC 4 Letter to J. Randy Johnson from Malcolm T. Widmann dated December 18, 2008 SUBJECT: REACTOR AND SENIOR REACTOR OPERATOR INITIAL EXAMINATIONS -
JOSEPH M. FARLEY NUCLEAR PLANT 05000348/2008301 AND 05000364/2008301 Distribution w/encl:
RIDSNRRDIRS PUBLIC R. Martin, NRR (PM: HAT, SUM)
NUCLEAR REGULATORY COMMISSION
REGION II
Docket No.: 50-348, 50-364 License No.: NPF-2, NPF-8 Report No.: 05000348/2008301, 05000364/2008301 Licensee: Southern Nuclear Operating Company, Inc.
Facility: Joseph M. Farley Nuclear Plant Location: Columbia, AL 36319 Dates: Operating Test - October 27 - November 7, 2008 Written Examination - November 10, 2008 Examiners: M. Bates, Chief Examiner, Senior Operations Engineer J. Hopkins, Reactor Technology Instructor C. Kontz, Operations Engineer Approved by: Malcolm T. Widmann, Chief Operations Branch Division of Reactor Safety Enclosure 1
SUMMARY OF FINDINGS ER 05000348/2008301, 05000364/2008301, 10/27-11/7/2008 and 11/10/2008; Farley Nuclear Plant; Licensed Operator Examinations.
The NRC examiners conducted operator licensing initial examinations in accordance with the guidance in NUREG-1021, Revision 9, Supplement 1, Operator Licensing Examination Standards for Power Reactors. This examination implemented the operator licensing requirements of 10 CFR §55.41, §55.43, and §55.45.
The NRC administered the operating tests during the period of October 27 - November 7, 2008.
Members of the Farley Nuclear Plant training staff administered the written examination on November 10, 2008. The written examinations and the operating tests were developed by the Farley Nuclear Plant training staff.
Eight Senior Reactor Operator (SRO) applicants and three Reactor Operator (RO) applicants passed both the written and operating examinations. One SRO applicant and one RO applicant took only the written examination and both passed. One SRO applicant and one RO applicant failed the written examination. Eight Senior Reactor Operator (SRO) and three Reactor Operator (RO) applicants were issued operating licenses commensurate with the level of examination administered. One SRO applicant and one RO applicant were issued letters stating that they passed both the written and operating examinations and that their licenses will not be issued until the conclusion of any pending appeals.
There were two post examination comments.
Enclosure 1
REPORT DETAILS 2. OTHER ACTIVITIES 4OA5 Operator Licensing Initial Examinations a. Inspection Scope The Farley Nuclear Plant training staff developed the operating tests and written examinations. NRC regional examiners reviewed the proposed examination material to determine whether it was developed in accordance with NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Revision 9, Supplement 1.
Examination changes agreed upon between the NRC and the licensee were made according to NUREG-1021 and incorporated into the final version of the examination materials.
The examiners reviewed the licensees examination security measures while preparing and administering the examinations to ensure examination security and integrity complied with 10 CFR 55.49, Integrity of Examinations and Tests.
The examiners evaluated 10 SRO applicants and five RO applicants who were being assessed under the guidelines specified in NUREG-1021. The examiners administered the operating tests during the period of October 27 - November 7, 2008. Members of the Farley Nuclear Plant training staff administered the written examination on November 10, 2008. The evaluations of the applicants and review of documentation were performed to determine if the applicants, who applied for licenses to operate the Farley Nuclear Plant, met requirements specified in 10 CFR Part 55, Operators Licenses.
b. Findings The initial written examination submittal was determined to be within the acceptable quality range as outlined in NUREG-1021.
The NRC determined that the details provided by the licensee for the walkthrough and simulator tests were within the range of acceptability expected for a proposed examination.
Eight Senior Reactor Operator (SRO) applicants and three Reactor Operator (RO)
applicants passed both the written and operating examinations. One SRO applicant and one RO applicant took only the written examination and both passed. One SRO applicant and one RO applicant failed the written examination.
The final RO and SRO written examinations with knowledge and abilities (K/As) question references/answers, examination references, and licensees post examination comments may be accessed in the ADAMS system (ADAMS Accession Numbers, ML083510509, and ML083510513).
Copies of all individual examination reports were sent to the facility Training Manager for evaluation and determination of appropriate remedial training.
Enclosure 1
4OA6 Meetings Exit Meeting Summary On November 7, 2008, the examination team discussed generic issues associated with the operating test with Mr. Randy Johnson, and members of the Farley Nuclear Plant staff. The examiners asked the licensee whether any materials examined during the inspection should be considered proprietary. No proprietary information was identified.
PARTIAL LIST OF PERSONS CONTACTED Licensee personnel J. Johnson, Site Vice President R. Wells, Operations Manager J. Horn, Training Manager T. Blindauer, Initial License Training Supervisor D. Christiansen, Nuclear Operations Training Supervisor C. Richter, Plant Instructor - Nuclear G. Ohmstede, Plant Instructor - Nuclear NRC personnel S. Shaeffer, Chief, Branch 2 Division of Reactor Projects E. Crowe, Senior Resident Inspector S. Sandal, Resident Inspector M. Bates, Senior Operations Engineer J. Hopkins, Reactor Technology Instructor C. Kontz, Operations Engineer Enclosure 1
NRC RESOLUTION TO THE FARLEY POST EXAMINATION COMMENT(S)
WRITTEN EXAMINATION - QUESTION 7 Licensee Comment:
(Submitted Licensee Comments May Be Located in ADAMS at ML083510513)
The stem of the question stated that the demineralizer was vented but did not specify if the demineralizer was drained. Some applicants made an assumption that the demineralizer was voided and this assumption would make the answer and one of the distractors both possible correct answers and both should be taken as correct.
Furthermore, the licensee states that the question statement did not ask for the answers to be based on the conditions provided in the stem of the question. Rather the licensee claims that the question statement was asking an open-ended question, which could apply to any incorrect method of placing the demineralizer in service.
NRC Resolution:
The licensees recommendation to accept two correct answers was not accepted.
The recommendation stated that 9 out of 15 applicants made an assumption that there was voiding of the demineralizers during the time they were vented. This is contrary to the directions given to the applicant in NUREG 1021, Revision 9, Supplement 1, Appendix E, Part B.7, which states:
When answering a question, do not make assumptions regarding conditions that are not specified in the question unless they occur as a consequence of other conditions that are stated in the question.
Based on the above guidance, it would be incorrect for the applicants to make an assumption that the demineralizers had been voided. The question did not state that the demineralizer had been voided, nor could voiding have occurred as a result of other conditions that were provided.
Also, the licensee claims that the question statement did not ask for the answers to be based on the conditions provided in the stem of the question. Rather the licensee claims that the question statement was asking an open-ended question, which could apply to any incorrect method of placing the demineralizer in service. The NRC disagrees with this argument. The conditions listed in the stem are relevant to the question being asked. This would be the only logical reason for supplying these conditions. It is true that the question statement does not contain the words, Based on the above conditions, which one of the following , but it is generally understood in the question construction that these conditions are relevant to the question that is being presented. Therefore, the applicant would have to incorrectly assume that the demineralizer had been voided, which would be contrary to the above stated NUREG-1021 instructions for taking the exam.
Enclosure 2
Lastly, the licensees request to accept two correct answers is not supported by the documentation provided. The examples, that provided similar plant conditions as given in the stem of the question, were not linked to gas binding of the charging pumps and did not cause pressure drops greater than those in the system operating procedures Precautions and Limitations. One example was linked to charging pump gas binding, but the gas binding was not due to filling a voided demineralizer, rather the voiding was due to multiple large pressure transients caused by venting of the VCT to reduce pressure. Therefore, the provided examples do not support charging pump suction voiding being a potential concern.
WRITTEN EXAMINATION - QUESTION 56 Licensee Comment:
(Submitted Licensee Comments May Be Located in ADAMS at ML083510513)
The stem of the question is not specific as to the exact step in the procedure from which the question is being asked. This ambiguity requires the applicant to make an assumption on the status of the heat exchangers. The status of the heat exchangers will determined whether CCW temperature will increase or decrease, which would then make either A or B correct, based on the assumption that the applicant was required to make. Therefore, the licensee is recommending that both answer choices A and B be considered as correct answer choices.
NRC Resolution:
The licensees recommendation to accept two correct answers was not accepted.
The NRC agrees with the licensees argument that the applicants were required to make an assumption, which ultimately would determine whether a boration or dilution was correct.
Therefore, the licensees basis for either a boration or dilution is accepted; however, these portions of answer choices A and B contain conflicting information (I.E. boration and dilution are opposite effects and therefore conflicting). NUREG 1021 Revision 9, Supplement 1, ES-403, Section D.1.c states, If, however, both answers contain conflicting information, the question will likely be deleted. Therefore, applying this guidance, this question will be deleted from the exam.
Enclosure 2
SIMULATION FACILITY REPORT Facility Licensee: Farley Nuclear Plant Facility Docket Nos.: 05000348/05000364 Operating Tests Administered on: October 27 - November 7, 2008 This form is to be used only to report observations. These observations do not constitute audit or inspection findings and, without further verification and review in accordance with IP 71111.11, are not indicative of noncompliance with 10 CFR 55.46. No licensee action is required in response to these observations.
No simulator fidelity or configuration items were identified.
Enclosure 3