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Category:Letter
MONTHYEARNMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024 Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations ML23354A0012024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (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 NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023 Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 NMP1L3564, Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements ML23291A4642023-12-0707 December 2023 Issuance of Amendment No. 251 Regarding the Adoption of Title 10 the Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of SSC for Nuclear Power Plants ML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b NMP1L3563, Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-12-0404 December 2023 Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) IR 05000220/20234022023-11-28028 November 2023 Security Baseline Inspection Report 05000220/2023402 and 05000410/2023402 NMP1L3557, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000220/20234202023-11-0101 November 2023 Security Baseline Inspection Report 05000220/2023420 and 05000410/2023420 ML23305A0052023-11-0101 November 2023 Operator Licensing Examination Approval IR 05000220/20230032023-10-25025 October 2023 Integrated Inspection Report 05000220/2023003 and 05000410/2023003 IR 05000220/20235012023-10-17017 October 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000220/2023501 and 05000410/2023501 IR 05000220/20230112023-10-16016 October 2023 Comprehensive Engineering Team Inspection Report 05000220/2023011 and 05000410/2023011 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans NMP1L3554, Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases2023-10-0606 October 2023 Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases C IR 05000220/20233032023-09-20020 September 2023 Retake Operator Licensing Examination Report 05000220/2023303 ML23250A0822023-09-19019 September 2023 Regulatory Audit Summary Regarding LARs to Adopt TSTF-505, Rev. 2, and 10 CFR 50.69 ML23257A1732023-09-14014 September 2023 Requalification Program Inspection IR 05000220/20230052023-08-31031 August 2023 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2023005 and 05000410/2023005) RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs NMP2L2851, Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations2023-08-25025 August 2023 Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration NMP1L3534, License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2023-08-18018 August 2023 License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation ML23220A0262023-08-0808 August 2023 Licensed Operator Positive Fitness-for-Duty Test IR 05000220/20234012023-08-0808 August 2023 Cyber Security Inspection Report 05000220/2023401 and 05000410/2023401 (Cover Letter Only) NMP1L3545, Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .2023-08-0404 August 2023 Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems . RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor IR 05000220/20230022023-08-0101 August 2023 Integrated Inspection Report 05000220/2023002 and 05000410/2023002 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 NMP1L3544, Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations2023-07-14014 July 2023 Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations ML23186A1642023-07-0606 July 2023 Operator Licensing Retake Examination Approval NMP2L2846, Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications2023-07-0505 July 2023 Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications ML23192A0622023-06-30030 June 2023 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance, Report No. 10CFR21-0136, Rev. 0 IR 05000220/20230102023-06-29029 June 2023 Biennial Problem Identification and Resolution Inspection Report 05000220/2023010 and 05000410/2023010 ML23131A4242023-06-23023 June 2023 Issuance of Amendment No. 249 Regarding the Revision to Technical Specification 3.3.1 to Adopt Technical Specifications Task Force Traveler TSTF-568 RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3539, Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-06-0909 June 2023 Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling IR 05000410/20233022023-05-15015 May 2023 Initial Operator Licensing Examination Report 05000410/2023302 2024-02-01
[Table view] Category:Licensee Response to Notice of Violation
MONTHYEARNMP1L3001, Response to Apparent Violations in Inspection Report No. 05000220 & 05000410/2014005; EA-14-1922015-03-0505 March 2015 Response to Apparent Violations in Inspection Report No. 05000220 & 05000410/2014005; EA-14-192 ML0911903062009-04-15015 April 2009 Reply to a Notice of Violation ML0710703792007-04-0909 April 2007 NRC Inspection Report No. 50-220/2006-011, Reply to a Notice of Violation: EA-07-001 ML0318800152003-06-23023 June 2003 Reply to Notice of Violation - NRC Inspection Report 50-220/03-003 ML17037C2111974-05-14014 May 1974 Response to Atomic Energy Commission Letter Dated April 5, 1994 Regarding Inspection No. 50-220/74-02 ML17037C2141973-11-14014 November 1973 Letter Responding to the September 13, 1973 Informing the Commission of the Action Taken to Correct the Items of Noncompliance Following the Recent Inspection and Advising That the Action Will Be Verified During the Next .. ML17037C2151973-10-25025 October 1973 Letter Responding to the September 10, 1973 Letter Informing the Commission of the Action Taken to Correct the Item of Noncompliance Brought to Attention Following the Recent Inspection and Advising That Corrective Action .. 2015-03-05
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Keith J. Poison P.O. Box 63 Vice President-Nine Mile Point Lycoming, New York 13093 315.349.5200 315.349.1321 Fax Constellation Energy-Nine Mile Point Nuclear Station April 15, 2009 U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 ATTENTION: Document Control Desk
SUBJECT:
Nine Mile Point Nuclear Station Unit No. 1; Docket No. 50-220 NRC Investigation Report No. 1-2008-018 Reply to a Notice of Violation: EA-09-005
REFERENCE:
Letter from Mr. D. C. Lew (NRC) to Mr. K. J. Poison (NMPNS) dated March 16, 2009, Notice of Violation - NRC Investigation Report No. 1-2008-018 This letter provides the Nine Mile Point Nuclear Station, LLC (NMPNS) response to the referenced letter, which identified a Notice of Violation associated with the reactor overpower event of January 5, 2008.
This violation involved misconduct by two licensed operators in making reactivity changes without proper approval and oversight, and a subsequent delay in reporting the event to control room supervision.
NMPNS agrees with the violation and has taken corrective steps to prevent further violations.
The attachment to this letter provides the NMPNS detailed response to the violation. In accordance with 10 CFR 2.201, this response describes the reason for the violation, the corrective steps that have been taken and results achieved, the corrective steps that will be taken to avoid further violations, and the date when full compliance was achieved.
Should you have any questions regarding this matter, please contact T. F. Syrell, Licensing Director, at (315) 349-5219.
Very truly yours, XA I(VIA L500.04 KJP/JJD
Attachment:
Reply to a Notice of Violation: EA-09-005, NRC Investigation Report No. 1-2008-018
Document Control Desk April 15, 2009 Page 2 cc: NRC Regional Administrator, Region I NRC Resident Inspector NRR Project Manager
ATTACHMENT REPLY TO A NOTICE OF VIOLATION:
EA-09-005 NRC INVESTIGATION REPORT NO. 1-2008-018 Nine Mile Point Nuclear Station, LLC April 15, 2009
ATTACHMENT REPLY TO A NOTICE OF VIOLATION: EA-09-005 NRC INVESTIGATION REPORT NO. 1-2008-018 NOTICE OF VIOLATION Technical Specification 6.4.1(a) requires that written procedures and administrative policies shall be established, implemented and maintained that meet or exceed the requirements and recommendations of Sections 5.1 and 5.3 of ANSI N18. 7-19 72 and cover the describedactivities in Regulatory Guide 1.33, Appendix A, November 3, 1972 (Safety Guide 33). Safety Guide 33, Appendix A, PartA.2, requiresproceduresfor authoritiesand responsibilitiesfor safe operation and shutdown.
Nine Mile Point Operations Administrative Procedure S-ODP-OPS-0001, Revision 06, "Conduct of Operations," states in section 3.1.6.a, that planned reactivity and power changes are only performed with Shift Manager (SM)permission and shall be supervised by a Senior Reactor Operator (SRO).
Constellation Nuclear Generation Fleet Administrative Procedure CNG-OP-3.01-1000, "Reactivity Management," Revision 00100, states in Attachment 4, Section 1.d, that control room operators shall take conservative action when any unexpected situation occurs with respect to core reactivity and shall notify Operations management and ReactorEngineeringas soon as possible.
Contrary to the above, on January 5, 2008: (1) a Reactor Operator (RO) increased power without SM permission or supervision by an SRO, and, after power exceeded the megawatt-thermal license limit, a CRO and the RO decreased power without SM permission or supervision by an SRO; and, (2) the CRO and the RO failed to notify Operations management and Reactor Engineering as soon as possible after the unexpected situation occurred with respect to core reactivity. Specifically, control room management was not notified until the following day that the over-power and down-power events had occurred.
II. REASON FOR THE VIOLATION As listed above, an NRC Notice of Violation was issued to Nine Mile Point Nuclear Station, LLC (NMPNS) for the failure of two licensed operators to follow administrative procedures concerning roles and responsibilities of control room personnel. Specifically, on January 5, 2008:
(1) licensed operators increased and decreased reactor power without SM permission and senior reactor operator oversight; and (2) the licensed operators did not notify Operations management as soon as possible after the unexpected situation occurred with respect to core reactivity. The root cause investigation conducted to address this event identified the following causes:
- Operations management did not ensure that high standards and expectations of performance were being implemented on shift. This resulted from a flawed mental model associated with compliance with standards and inadequate monitoring.
- Less than clear standards, expectations, and practices for maintaining power at or below the licensed core thermal power limit existed at the time of the event.
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A-ATTACHMENT REPLY TO A NOTICE OF VIOLATION: EA-09-005 NRC INVESTIGATION REPORT NO. 1-2008-018 III. CORRECTIVE STEPS THAT HAVE BEEN TAKEN AND THE RESULTS ACHIEVED Immediate and compensatory actions taken included:
- 1. A stand down was conducted with operations management to share lessons learned.
- 2. Shift Managers briefed each operating crew on the event.
- 3. The expectations/requirements for the function of the operator at the controls were clarified.
- 4. Interim reactor power maintenance guidelines were established to ensure that power is maintained at or below rated core thermal power.
In addition, the following corrective actions were taken as a result of the investigation:
- 1. A case study of the event was developed and presented to plant operators, initial license candidates, Training department SRO instructors, and Operations management. The case study discussed how erosion of the following standards led to the event: formal communications protocol during day-to-day activities, the control room command function, reactivity maneuvers/adjustments and SRO oversight expectations, and roles and responsibilities of control room personnel.
- 2. Dynamic learning activities were developed and completed for Operations management, SMs, and licensed operators for reinforcing and evaluating operator fundamentals associated with typical at power, steady state operational activities, including power maintenance, that focused on operational standards such as formal communications protocol, the control room command function, reactivity maneuvers/adjustments and SRO oversight expectations, roles and responsibilities of control room personnel, and critical parameter monitoring.
- 3. Operating procedures were revised with clear written standards for conduct of power maintenance including initiation and approval of verbal requests to conduct power maintenance, parameter monitoring and verification of intended response, and SRO oversight.
- 4. An operating band, designed to stay below the licensed thermal power limit, was developed and placed in appropriate procedures and communicated to operating crews via briefings.
- 5. The NMP steady-state power maintenance guidelines were revised to provide guidance in the event power exceeds the licensed thermal power limit, including making notifications as required by administrative procedures.
- 6. Disciplinary action was taken against the two operators described in the violation. Neither operator is currently employed by NMPNS.
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ATTACHMENT REPLY TO A NOTICE OF VIOLATION: EA-09-005 NRC INVESTIGATION REPORT NO. 1-2008-018 IV. CORRECTIVE STEPS THAT WILL BE TAKEN TO AVOID FURTHER VIOLATIONS NMPNS is confident that the actions described above provide reasonable assurance that future similar events Will not occur.
V. DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED Full compliance was achieved on August 29, 2008, when the last of the corrective actions described above was completed.
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