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Category:Letter type:L
MONTHYEARL-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-122, Core Operating Limits Report2024-08-12012 August 2024 Core Operating Limits Report L-2024-106, Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-022024-08-12012 August 2024 Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-02 L-2024-089, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2024-07-25025 July 2024 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-112, Condition Prohibited by Technical Specifications2024-07-10010 July 2024 Condition Prohibited by Technical Specifications L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update L-2024-100, Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project2024-06-19019 June 2024 Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project L-2024-076, Reply to Notice of Violation; NOV 05000250, 05000251/2024010-052024-05-29029 May 2024 Reply to Notice of Violation; NOV 05000250, 05000251/2024010-05 L-2024-082, 2023 Annual Radiological Environmental Operating Report2024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report L-2024-060, 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report2024-05-0909 May 2024 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report L-2024-073, Cycle 34 Core Operating Limits Report2024-05-0101 May 2024 Cycle 34 Core Operating Limits Report L-2024-072, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report L-2024-048, Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision2024-04-30030 April 2024 Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision L-2024-069, Radiological Emergency Plan Revision 762024-04-22022 April 2024 Radiological Emergency Plan Revision 76 L-2024-066, Sixth 10-Year Inservice Testing Interval Relief Request No. PR-022024-04-17017 April 2024 Sixth 10-Year Inservice Testing Interval Relief Request No. PR-02 L-2024-057, 0 for Turkey Point, Unit 3 - Condition Prohibited by Technical Specifications2024-04-11011 April 2024 0 for Turkey Point, Unit 3 - Condition Prohibited by Technical Specifications L-2024-040, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2024-03-28028 March 2024 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections L-2024-047, Proposed Use of a Subsequent ASME Code Edition and Addenda2024-03-28028 March 2024 Proposed Use of a Subsequent ASME Code Edition and Addenda L-2024-013, Submittal of Periodic Reports2024-03-28028 March 2024 Submittal of Periodic Reports L-2024-044, Revised Steam Generator Tube Inspection Reports2024-03-19019 March 2024 Revised Steam Generator Tube Inspection Reports L-2024-011, and Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2024-03-13013 March 2024 and Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2024-014, 2023 Annual Radioactive Effluent Release Report2024-02-29029 February 2024 2023 Annual Radioactive Effluent Release Report L-2024-025, Notification of Improved Standard Technical Specifications (ITS) Implementation2024-02-22022 February 2024 Notification of Improved Standard Technical Specifications (ITS) Implementation L-2024-008, Supplement to License Amendment Request 278. Incorporate Advanced Fuel Products. Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles2024-02-0909 February 2024 Supplement to License Amendment Request 278. Incorporate Advanced Fuel Products. Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2024-007, Inservice Inspection Program Owners Activity Report (OAR-1)2024-01-18018 January 2024 Inservice Inspection Program Owners Activity Report (OAR-1) L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-172, Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-146, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-078, License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles2023-11-15015 November 2023 License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles L-2023-077, License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis2023-10-11011 October 2023 License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis L-2023-110, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-08-25025 August 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-115, Inservice Inspection Program Owner'S Activity Report (OAR-1)2023-08-21021 August 2023 Inservice Inspection Program Owner'S Activity Report (OAR-1) L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2023-094, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-07-27027 July 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) L-2023-086, Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation.2023-06-28028 June 2023 Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation. L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update L-2023-069, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-05-31031 May 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-072, Preparation and Scheduling of Operator Licensing Examinations2023-05-22022 May 2023 Preparation and Scheduling of Operator Licensing Examinations L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal L-2023-061, 2022 Annual Radiological Environmental Operating Report2023-05-12012 May 2023 2022 Annual Radiological Environmental Operating Report L-2023-062, Cycle 33 Core Operating Limits Report2023-04-27027 April 2023 Cycle 33 Core Operating Limits Report L-2023-060, Radiological Emergency Plan, Revision 752023-04-26026 April 2023 Radiological Emergency Plan, Revision 75 L-2023-054, Submittal of Periodic Reports2023-04-12012 April 2023 Submittal of Periodic Reports 2024-09-25
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FPL POWERING TODA February 16, 2011 EMPOWERING TOMORROW L201 1060 10 CFR 55.31 Victor M. MeCree Regional Administrator, Region II U. S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Preliminary License Re-application for Mr. Marshall W. Morris On December 2, 2010, the Nuclear Regulatory Commission (NRC) informed Mr. Marshall W.
Morris that he did not pass the Administrative Topics portion of the SRO examination taken during the week of November 10, 2010, at the Turkey Point Nuclear Plant and as a result the NRC denied his application. As stated in the NRC letter dated December 2, 2010, and in accordance with 10 CFR 55.35, Re-application, Mr. Morris is eligible to re-apply for a license two months after the date of the denial.
Additionally, since Mr. Morris has passed the Written Examination, the Systems Job Performance Measures (JPMs) and the Simulator Operating Tests, Mr. Morris is eligible to request a routine waiver from those portions of the SRO examination. Accordingly, on January 18, 2011, FPL submitted a waiver request for Mr. Morris to re-take the Administrative Topic portion of the SRO Examination.
The purpose of this letter is to provide the preliminary License Application and sufficient details on the additional training that Mr. Morris has completed to prepare for the re-take of the Administrative Topic portion of the SRO examination. provides the preliminary License Application (NRC Forms 396 and NRC Forms 398 for:
Operator: License #: Docket #:
Morris, M.W. N/A to this letter contains personal information, the disclosure of which would clearly constitute an unwarranted invasion of personal privacy. Pursuant to 10 CFR 2.390(a)(6), we request that Enclosure I of this letter be withheld from public disclosure.
FiE ii 1 ;
an FPL Group company
L-201 1-060 Page 2 The details on the additional training taken by Mr. Morris are provided in Enclosure 2.
Should there be any questions, please contact Mr. Greg Laughlin at (305) 246-6274.
Very truly yours, Michael Kiley Vice President Turkey Point Nuclear Plant SM Enclosures cc: Chief, Operations Branch, Division of Reactor Safety, Region II, USNRC (original and two copies)
Senior Resident Inspector, USNRC, Turkey Point Plant (w/o enclosures)
Document Control Desk, USNRC, Washington, D.C. (w/o enclosures)
L-201 1-060
L-201 1-060 EnclQsure2
- 1. Background and Details on the Re-application of Mr. Marshall W. Morris Mr. Marshall Morris had previously applied and taken the Senior Reactor Operator (SRO) licensing examination during the week of 10/25/2010. Mr. Morris passed all portions of the NRC SRO exam, with the exception of the Administrative JPMs. He passed two of the administrative JPMs; the requirement is to pass three. In accordance with 10 CFR 55.35, a re-application that includes a waiver of the other portions of the NRC examination has been submitted for Mr. Morris.
Mr. Morris failed three of the five required Administrative JPMs. He passed all other simulator exams, written exams and JPMs. In JPM Admin A, the measure was to Determine if shift manning, 0-ONOP-105, and fire brigade requirements are met. The candidate incorrectly assigned an ANPO to perform attachment 6 of ONOP-105. All other assignments for all other personnel were satisfactory. Mr. Morris incorrectly assumed that the ANPO was also qualified as turbine operator.
In Admin B the assignment was to identify the minimum required contingency action contained in 0-ADM-051, Outage risk assessment and Control. The candidate incorrectly applied the Required Equipment in the procedure. The candidate applied the requirement as two independently powered charging pumps vs. the correct application of two charging pumps capable of being supplied from an EDO. All other actions were properly determined.
In Admin C the requirement was to Determine any required Technical Specification actions, any required notifications, and any administrative actions. The candidate properly performed all actions with the exception of ADM-1 15 notifications.
An analysis of these three failures as a group indicates that the candidate made assumptions that were not provided in the data, or, interpreted requirements in a more conservative approach than was accounted for in the procedure. Mr. Morris did not possess sufficient administrative procedure knowledge, particularly some incidental details or knowledge gaps that come with time and practice in performing administrative activities, to properly apply the requirements to the situations presented in the JPMs.
Based on this analysis, a remediation program was designed and implemented for his improvement.
Page 1 of4
L-201 1-060 Enclosure 2.
- 2. Remediation Plan for Mr. Marshall W. Morris Re-take of the Administrative Topic Portion of the SRO Examination
- 1. Candidate to independently review and study the below listed Administrative Procedures. This review should include a determination of possible hypothetical conditions and development of JPM style scenarios. This is designed to help the candidate establish a correct mental model and interpretation requirements.
Any questions to be discussed with the class Mentor/Instructors.
- 2. Candidate to perform ten (10) practice Administrative JPMs. Each JPM should be followed by a verbal explanation of why he took each step of the JPM and why that is correct for the conditions given.
- 3. Candidate to successfully perform two (2) practice exam sets of five (5)
Administrative JPMs each.
- 4. Candidate to successfully pass an Audit Exam of five (5) Administrative JPMs.
The applicant has completed the remedial training as designed since the original exam:
- 1. Candidate independently reviewed and studied the designated Administrative Procedures. As planned, this review included a determination of possible hypothetical conditions and development ofJPM style scenarios. Questions were discussed with the class Mentor or SRO Certified Instructors.
- 2. Candidate performed ten (10) practice Administrative JPMs in accordance with the remediation plan.
- 3. Candidate successfully completed two (2) practice exam sets of five (5)
Administrative JPMs each.
- 4. Candidate successfully passed an Audit Exam of five (5) Administrative JPMs.
- 3. Remedial Assessment:
Mr. Morris has completed the above remedial plan required activities. Mr. Morris is continuing to perform practice JPMs and review of other Administrative duties in preparation for his SRO re-take examination and is showing a great improvement in his ability to understand the initial conditions, utilize the appropriate procedure and verbalize his reasoning for each step of the JPMs. We are confident in that Mr. Morris will be successful on his re-take of the Administrative portion of the NRC exam.
Page 2 of 4
L-201 1-060
-. EnclosurQ 2
- 4. List of Procedures and discussions performed during the remediation process.
Procedure Title Hypothetical Conditions 0-ONOP- 105 Staffing, Tech Control Room Evacuation Oncoming shift operator calls in Spec minimum staffing and Tech Specs sick.
NAP-402 &ADM-200 Conduct of Operations Procedure cannot be performed as written.
Reactivity management for equipment failures.
0-ADM-03 1 Independent verification Usage of IV versus CDV 0-ADM-2 12 and 212.1 In-Plant Equipment Inadequate ECO, boundary Clearance Orders modification, computer system fails.
0-ADM-1 15 Notification of Plant Events Notifications for FFD, tech spec actions due to equipment failure, RPS actuation.
%-OSP-024.2 Emergency Bus Load Failure of sequencer test and Sequencers Manual Test impact on tech specs.
%-OSP-022.4 EDG Fuel oil Transfer Test failure impact on tech Pump and Valve Test specs.
A-OSP 049.1 3 Reactor Protection System Implications of relay failures, Logic Test breaker function failures, unsat time response.
0-OSP-023.3 Equipment operability Impact of missed performance.
verification with an EDG inoperable.
0-NOP-06 1.1 4A Waste Gas Disposal System Alarm during performance, R controlled release of gas 14 OOS, permit review decay tank A.
0-NOP-06 1,11 C Controlled liquid release Alarm during performance, R from waste monitor tank A 18 OOS, permit review 0-NCOP-003 Preparation of liquid release Inaccuracies in permit Permits 0-NCOP-004 Preparation of gas release Inaccuracies in permit permits
%-OSP-028.6 RCCA Periodic Exercise Impact of dropped rod, stuck rod, slow rod, rod out of alignment during performance.
%-OSP-041.l Reactor Coolant System Use of improper sign polarity Leak Rate Calculation during calculations.
0-ADM-009 Containment entries when Failed containment door during containment integrity is containment entry at power.
established.
AD-AA-101-1004 Work Hour Controls Callout to fill position.
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L-201 1-060 Bxiclosure 2 Procedure Title Hypothetical Conditions 0-OP-028.2 Shutdown Margin Wrong curve book used and Calculation incorrect values.
0-OSP-040.4 Estimated Critical Wrong curve book, incorrect Condition time in core life used and incorrect value polarity.
%-OSP-053.4 Containment Integrity Incorrect as found position.
Penetration Alignment Verification.
0-ADM-205 Administrative control of Incorrect alignment or position.
valves, locks, and switches 0-ADM-503 Temporary System Incorrect application of process.
Alteration.
AD-AA- 100-1004 Preparation, revision, Improper application of process.
review/approval of procedures.
0-EPIP-20101 Duties of Emergency Incorrect event classification.
Coordinator 0-EPIP-201 11 Re-Entry Incorrect application of exposure limits.
0-EPIP-20 134 Offsite notifications and Incorrect or incomplete protective action notification or PARS.
recommendations.
0-ADM-600 Radiation Protection Incorrect RWP used, incorrect Manual. classification of rad area, incorrect dose rate calculation AD-AA-100-1005 Temporary changes to Improper application of process.
procedures.
Y4-OSP-204 Accident monitoring Unsat acceptance criteria instrumentation channel impact.
checks Page 4 of 4