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Category:Letter
MONTHYEARML24339B7292024-12-18018 December 2024 Amd - Constellation - Adoption of TSTF-591 JAFP-24-0065, Inservice Inspection Summary Report Cycle 262024-12-0909 December 2024 Inservice Inspection Summary Report Cycle 26 JAFP-24-0053, License Amendment Request to Eliminate Remaining Main Steam Line Radiation Monitor Initiated Isolation Functions2024-11-26026 November 2024 License Amendment Request to Eliminate Remaining Main Steam Line Radiation Monitor Initiated Isolation Functions JAFP-24-0063, Interim Report of a Deviation or Failure to Comply Associated with General Electric Thermal Overload Relay, Model CR124G011, Part Number DD317A7861P0032024-11-25025 November 2024 Interim Report of a Deviation or Failure to Comply Associated with General Electric Thermal Overload Relay, Model CR124G011, Part Number DD317A7861P003 05000333/LER-2024-003, Turbine Trip and Scram Due to Automatic Voltage Regulator Protective Device During a Grid Transient2024-11-22022 November 2024 Turbine Trip and Scram Due to Automatic Voltage Regulator Protective Device During a Grid Transient IR 05000333/20240032024-11-12012 November 2024 Integrated Inspection Report 05000333/2024003 ML24317A1432024-11-0404 November 2024 Constellation Energy Generation, LLC, 2024 Annual Report - Guarantees of Payment of Deferred Premiums JAFP-24-0055, Response to Request for Additional Information for License Amendment Request to Add Temporary Change to TS 3.3.2.1, Condition C, Control Rod Block Instrumentation2024-10-29029 October 2024 Response to Request for Additional Information for License Amendment Request to Add Temporary Change to TS 3.3.2.1, Condition C, Control Rod Block Instrumentation IR 05000333/20240902024-10-29029 October 2024 Final Significance Determination of a White Finding with Assessment Follow-Up and Notice of Violation; Inspection Report 05000333/2024090 IR 05000333/20244022024-10-28028 October 2024 Material Control and Accounting Program Inspection Report 05000333/2024402 (Cover Letter Only) ML24267A0562024-10-23023 October 2024 Exemption Issuance Letter ML24276A1332024-10-17017 October 2024 Issuance of Amendment No. 357 Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision-4, and Administrative Changes ML24282B0302024-10-11011 October 2024 Project Manager Assignment RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - 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 ML24207A0192024-10-0909 October 2024 SE Addendum Related to the License Amendment No. 338 for Implementation of the Alternative Source Term (DPO-2021-001) JAFP-24-0051, Reply to Preliminary White Finding and Apparent Violation in NRC Inspection Report 05000333/2024011; EA-24-0882024-10-0303 October 2024 Reply to Preliminary White Finding and Apparent Violation in NRC Inspection Report 05000333/2024011; EA-24-088 ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24270A0742024-09-30030 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-24-0046, Request for Enforcement Discretion for Technical Specification (TS) 3.3.2.1 Control Rod Block Instrumentation2024-09-25025 September 2024 Request for Enforcement Discretion for Technical Specification (TS) 3.3.2.1 Control Rod Block Instrumentation 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-2024-001-01, 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 05000333/LER-2024-002-01, Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation2024-07-0808 July 2024 Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation 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 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 05000333/LER-2024-001, 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 ML24176A2412024-06-24024 June 2024 Licensed Operator Positive Fitness-for-Duty Test 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 IR 05000333/20240012024-05-0909 May 2024 Integrated Inspection Report 05000333/2024001 2024-09-04
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Official Use Only-Security-Related InformationOfficial Use Only-Security-Related Information April 23, 2007 Mr. Pete Dietrich Site Vice President
Entergy Nuclear Northeast James A. FitzPatrick Nuclear Power Plant
Post Office Box 110
Lycoming, NY 13093
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT - NRC MATERIAL CONTROL AND ACCOUNTING PROGRAM INSPECTION - REPORT
05000333/2007201 Dear Mr. Dietrick
On March 22, 2007, the U.S. Nuclear Regulatory Commission (NRC) completed a material control and accounting (MC&A) safeguards program inspection at the James A. FitzPatrick
Nuclear Power Plant. The enclosed inspection report documents the inspection findings, which
were discussed with you and other members of y our staff during an exit meeting on that date .
The inspection examined activities conducted under your license as they relate to safety, security and compliance with the Commission's rules and regulations and with the conditions of
your license. The inspectors reviewed selected procedures and records, observed storage of
special nuclear material in the spent fuel pool, and interviewed personnel. Areas examined
during the inspection included physical inventory and accounting records.
Based on the results of this inspection, no findings of significance were identified. However, a licensee-identified violation, which was determined to be of very low safety significance is
discussed in the report. The NRC is treating this violation as a non-cited violation (NCV)
consistent with Section VI.A.1 of the Enforcement Policy because of the very low safety
significance of the violation and because it was corrected prior to this inspection. If you contest
this non-cited violation you should provide a response within 30 days of the date of this report, with the basis for your denial, to the Nuclear Regulatory Commission, ATTN: Document Control
Desk, Washington DC 20555-0001; with copies to the Regional Administrator, Region I; Office
of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; and the
NRC Resident Inspector at FitzPatrick.
When separated from the Enclosure, this document is DECONTROLLED.
Official Use Only-Security-Related InformationOfficial Use Only-Security-Related Information In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, will be available electronically for public inspection in the NRC Public Document Room or from the Public Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html (the Public
Electronic Reading Room). However, because of the security-related concerns contained in the
enclosure, and in accordance with 10 CFR 2.390, this letter's enclosure will not be available for
public inspection.
In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response, if any. This practice will ensure that your response will not be made available electronically for public inspection in the NRC Public Document Room or from NRCs document system ADAMS. If Safeguards information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21. Otherwise, mark your entire
response "Security-Related Information-Withhold Under 10 CFR 2.390" and follow the
instructions for withholding in 10 CFR 2.390(b)(1).
Should you have any questions concerning this report, please contact Martha Williams at (301) 415-7878 or Dori Votolato at (301) 415-7633.
Sincerely,
/RA/
Ralph Costello, Acting Chief Reactor Oversight Branch
Division of Security Operations
Office of Nuclear Security and Incident Response Docket No. 50-333 License No. DPR-59
Enclosure:
MC&A Inspection Report 05000333/2007201 w/
Attachment:
Supplemental Information cc w/enclosure: Attached list Official Use Only-Security-Related InformationOfficial Use Only-Security-Related Information In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, will be available electronically for public inspection in the NRC Public Document Room or from the Public Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html (the Public
Electronic Reading Room). However, because of the security-related concerns contained in the
enclosure, and in accordance with 10 CFR 2.390, this letter's enclosure will not be available for
public inspection.
In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response, if any. This practice will ensure that your response will not be made available electronically for public inspection in the NRC Public Document Room or from NRCs document system ADAMS. If Safeguards information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21. Otherwise, mark your entire
response "Security-Related Information-Withhold Under 10 CFR 2.390" and follow the
instructions for withholding in 10 CFR 2.390(b)(1).
Should you have any questions concerning this report, please contact Martha Williams at (301) 415-7878 or Dori Votolato at (301) 415-7633.
Sincerely,
/RA/
Ralph Costello, Acting Chief Reactor Oversight Branch
Division of Security Operations
Office of Nuclear Security and Incident Response Docket No. 50-333 License No. DPR-59
Enclosure:
MC&A Inspection Report 05000333/2007201 w/
Attachment:
Supplemental Information cc w/enclosure: Attached list Distribution w/encl
- DRiffle, NSIRJWilliams, NSIR TShedlosky, NSIR JRobinson, NRR JBoska, NRRECobey, RIGHunegs,RIDDempsey,RI CAdkinson, NSIRAMcLeod, NSIR
Enclosure:
ML070950330 Log-In #OFFICEDSO/RSOBEDSO/RSOBERIDSO/RSOBNAMEDVotolatoMWilliamsJWhiteby phone RCostelloDATE04/23/0704/23/0704/23/0704/23/07INDICATE IN BOX: "C"=COPY W/O ATTACHMENT/ENCLOSURE, "E"=COPY W/ATT/ENCL, "N"=NO COPY OFFICIAL RECORD COPYP. Dietrich Official Use Only-Security-Related InformationOfficial Use Only-Security-Related Information cc w/enclosure:
Peter Smith, President New York State Energy Research & Development Authority
17 Columbia Circle
Albany, NY 12203-6399 cc w/o enclosure:
G. Taylor, CEO, Entergy Operations, Inc.
M. Kansler, President, Entergy Nuclear Operations, Inc (ENO)
J. Herron, Sr, VP and Chief Operating Officer, (ENO)
C. Schwarz, VP, Operations Support (ENO)
K. Mulligan, General Manager, Plant Operations (ENO)
O. Limpias, VP, Engineering (ENO)
J. McCann, Director, Licensing (ENO)
C. Faison, Manager, Licensing (ENO)
M. Colomb, Director of Oversight (ENO)
D. Wallace, Director, Nuclear Safety Assurance (ENO)
J. Costedio, Manager, Regulatory Compliance (ENO)
T. McCullough, Assistant General Counsel (ENO)