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Category:Letter
MONTHYEARML24270A0742024-09-30030 September 2024 Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, & Opportunity for a Hearing (EPID L-2024-LLA-0134) - LTR ML24270A1452024-09-26026 September 2024 Notice of Enforcement Discretion for James A. Fitzpatrick Nuclear Power Plant JAFP-24-0047, License Amendment Request – Temporary Addition to TS 3.3.2.1 Condition C, Control Rod Block Instrumentation to Support Upgrade to Rod Worth Minimizer Software2024-09-25025 September 2024 License Amendment Request – Temporary Addition to TS 3.3.2.1 Condition C, Control Rod Block Instrumentation to Support Upgrade to Rod Worth Minimizer Software JAFP-24-0045, Supplemental Information for License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications2024-09-20020 September 2024 Supplemental Information for License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications IR 05000333/20240112024-09-19019 September 2024 Follow-up to Inspection Procedure 71153 Report 05000333/2024011 and Preliminary White Finding and Apparent Violation JAFP-24-0044, Core Operating Limits Report Cycle 272024-09-16016 September 2024 Core Operating Limits Report Cycle 27 JAFP-24-0043, Revision to Commitment Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues2024-09-12012 September 2024 Revision to Commitment Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues ML24165A0382024-09-0404 September 2024 Issuance of Amendment No. 356 Update Fuel Handling Accident Analysis 05000333/LER-2024-002, Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation2024-09-0404 September 2024 Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation IR 05000333/20240052024-08-29029 August 2024 Updated Inspection Plan for James A. Fitzpatrick Nuclear Power Plant (Report 05000333/2024005) 05000333/LER-2024-001, EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket2024-08-21021 August 2024 EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000333/20240022024-08-0707 August 2024 Integrated Inspection Report 05000333/2024002 JAFP-24-0034, 10 CFR 50.46 Annual Report2024-07-31031 July 2024 10 CFR 50.46 Annual Report ML24208A0492024-07-30030 July 2024 Notice of Consideration of Issuance of Amendments to Facility Operating Licenses and Proposed No Significant Hazards Consideration Determination (Letter) JAFP-24-0036, Supplement to License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2024-07-29029 July 2024 Supplement to License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-24-0033, Response to Request for Information Pertaining to a Licensed Operator Positive Fitness-For-Duty Test2024-07-23023 July 2024 Response to Request for Information Pertaining to a Licensed Operator Positive Fitness-For-Duty Test IR 05000333/20244032024-07-18018 July 2024 Biennial Problem Identification and Resolution Inspection Report 05000333/2024403 (Cover Letter Only) IR 05000333/20244012024-07-15015 July 2024 Security Baseline Inspection 05000333/2024401 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 ML24190A1932024-07-0909 July 2024 Correction Letter of Amendment No. 355 Revise Technical Specifications Section 3.4.3.1, Safety Relief Valves Setpoint Lower Tolerance IR 05000333/20240102024-07-0808 July 2024 Commercial Grade Dedication Inspection Report 05000333/2024010 ML24184A1662024-07-0303 July 2024 Senior Reactor and Reactor Operator Initial License Examinations ML24136A1162024-06-26026 June 2024 Issuance of Amendment No. 355 Revise Technical Specifications Section 3.4.3.1, Safety Relief Valves Setpoint Lower Tolerance ML24176A2412024-06-24024 June 2024 Licensed Operator Positive Fitness-for-Duty Test JAFP-24-0027, EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket2024-06-24024 June 2024 EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket 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 JAFP-24-0026, Supplement to License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (Srvs) Setpoint Lower Tolerance2024-06-12012 June 2024 Supplement to License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (Srvs) Setpoint Lower Tolerance ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 JAFP-24-0023, 2023 Annual Radiological Environmental Operating Report2024-05-0909 May 2024 2023 Annual Radiological Environmental Operating Report IR 05000333/20240012024-05-0909 May 2024 Integrated Inspection Report 05000333/2024001 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 JAFP-24-0020, 2023 Annual Radioactive Effluent Release Report2024-04-25025 April 2024 2023 Annual Radioactive Effluent Release Report JAFP-24-0019, 2023 REIRS Transmittal of NRC Form 52024-04-18018 April 2024 2023 REIRS Transmittal of NRC Form 5 ML24106A0152024-04-15015 April 2024 Request for Withholding Information from Public Disclosure Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition ML24107A6972024-04-12012 April 2024 Engine Systems, Inc Part 21 Report Re EMD Cylinder Liner Water Leak 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 ML24068A0532024-03-28028 March 2024 Issuance of Amendment No. 354 Revise Technical Specifications Section 3.3.1.2, Source Range Monitors Instrumentation JAFP-24-0014, Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2024-03-25025 March 2024 Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-24-0010, Response to Request for Additional Information for License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance2024-02-29029 February 2024 Response to Request for Additional Information for License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance IR 05000333/20230062024-02-28028 February 2024 Annual Assessment Letter for James A. FitzPatrick Nuclear Power Plant (Report 05000333/2023006) JAFP-24-0009, Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2024-02-28028 February 2024 Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis IR 05000333/20230042024-02-0707 February 2024 Integrated Inspection Report 05000333/2023004 and Independent Spent Fuel Storage Installation Inspection Report 07200012/2023001 ML24037A0102024-02-0606 February 2024 Requalification Program Inspection ML24018A0012024-01-18018 January 2024 Notification of Commercial Grade Dedication Inspection (05000333/2024010) and Request for Information ML24004A2302024-01-0808 January 2024 Project Manager Reassignment ML23356A0832024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0058 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines JAFP-23-0065, License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications2023-12-14014 December 2023 License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications 2024-09-04
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G. Ludlam UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 25, 2019 Mr. Gregg W. Ludlam, GM - Fleet Training Entergy Nuclear 1340 Echelon Parkway Jackson, MS 39213
SUBJECT:
VALIDATION OF PROPOSED REVISION TO OPERATOR INITIAL LICENSING EXAMINATION PROCESS The purpose of this letter is to request industry participation in validating a proposed revision to the operator initial licensing examination process.
The Nuclear Regulatory Commission (staff) is evaluating incorporation of current Generic Fundamentals Examination topics in the initial licensing site-specific written examination and removal of the requirement for individuals to pass a separate, generic examination developed and administered in accordance with NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Examination Standard (ES) 205, Procedure for Administering the Generic Fundamentals Examination Program.
The staff is considering incorporation of these topics into one examination to be administered after completion of the facilitys accredited systems approach to training program. This will improve flexibility for facility licensees in scheduling the training programs and will better support a level examination schedule within and between the regions. A level examination schedule will improve efficiency and reduce resource burden for both the industry and the staff. Additionally, incorporation of the test item topics for reactor theory, thermodynamics, and components into one final site-specific examination will ensure that these test items are operationally valid and applicable to the facility at which the individual is requesting a license, while maintaining alignment with regulatory requirements.
A validation of this proposed approach is warranted to evaluate the effectiveness of the proposed sample plan, the development of fundamental topic test items, impact on applicant performance, and any effect on the current accredited training program. Therefore, the staff is requesting assistance in validation of this proposal.
The staff has enclosed proposed change pages for NUREG-1021, ES-401, Preparing Initial Site-Specific Written Examinations, for use in developing these pilot test items. The proposed
Enclosures:
- 1. Proposed Replacement Pages for NUREG-1021 ES-401
- 2. Proposed Sample Plan for Option 1
- 3. Proposed Sample Plan for Option 2
G. Ludlam 2 changes include formation of a Tier 4, Theory, for testing the topics of reactor theory and thermodynamics and addition of knowledge and abilities (K/A) catalog Section 5, Components, to the list of testable K/As for reactor operator Tier 2 generic K/A questions. Two options have been considered for changes to the sample plan question distribution; both options have been enclosed with this letter.
The staff does not intend to use the proposed approach to affect any operator licensing decisions during this validation effort. Therefore, the staff recommends that these test items be developed, validated, and reviewed in accordance with NUREG-1021 using the attached change pages. The staff further recommends that these test items be administered to individuals at the same or similar timeframe as the facilitys audit examination. Although these test items should not be used to determine an individuals ability to sit for the staff-administered written examination, the staff is interested in the impact of these test items on test performance.
For this validation effort, the staff requests that an overall score for each individual be determined based on the attached sample plan, replacing audit examination test items with the proposed test items. Additionally, the proposed test items should be selected from the applicable K/A catalog using a random and systematic process, as described in NUREG-1021, ES-401. The proposed test items should include three questions testing different topics in reactor theory, three questions testing different topics in thermodynamics, and one to two questions testing component topics in the Tier 2 generic K/As. If requested, the staff can provide K/A statements for proposed test items per the attached sample plan, under examination security requirements. If requested, the staff will also provide the review of the proposed test items to ensure the test items meet the requirements of NUREG-1021 and provide feedback related to test item development for these topics. The proposed completion date for administering these test items is December 31, 2019.
The staff requests that this validation effort be performed at one boiling water reactor and one pressurized water reactor facility for each option provided. Therefore, the staff is requesting facility volunteers for at least two boiling water reactor validation efforts and two pressurized water reactor validation efforts across the industry, to best evaluate the two sample plan options provided.
The staff requests that these facility volunteers provide data and feedback on the outcomes of the proposed Generic Fundamentals Examination integration, including, but not limited to the following:
- 1. Proposed sample plan feedback - for options 1 and 2
- 2. Feedback on proposed changes to NUREG-1021 ES-401, enclosed with this letter
- 3. Pass rates - individual proposed Tier 4 and RO Tier 2 test items
- 4. Pass rates - overall if the individual was taking the audit examination based on the proposed changes and sample plans
- 5. Validator feedback - including discussion of operational validity of proposed test items
- 6. Test taker feedback - including discussion of operational validity of proposed test items
- 7. Any identified training impacts of the proposed changes.
G. Ludlam 3 The staff requests this feedback, in a format of the facilitys choosing, two months after completion of the proposed test item administration.
If you have any questions, please contact Ms. Theresa Buchanan at (301) 415-2789.
Sincerely,
/RA Gregory T. Bowman for/
Christopher G. Miller, Director Division of Inspection and Regional Support Office of Nuclear Reactor Regulation
ML19177A244 (package)
ML19177A248 ML19178A400 OFFICE NRR/DIRS/IOLB NRR/DIRS/IOLB NRR/DIRS NAME TBuchanan CCowdrey CMiller (GBowman for)
DATE 7/18/19 7/18/19 7/25/19