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Category:Inspection Report
MONTHYEARIR 05000333/20240112024-09-19019 September 2024 Follow-up to Inspection Procedure 71153 Report 05000333/2024011 and Preliminary White Finding and Apparent Violation IR 05000333/20240052024-08-29029 August 2024 Updated Inspection Plan for James A. Fitzpatrick Nuclear Power Plant (Report 05000333/2024005) IR 05000333/20240022024-08-0707 August 2024 Integrated Inspection Report 05000333/2024002 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 IR 05000333/20240102024-07-0808 July 2024 Commercial Grade Dedication Inspection Report 05000333/2024010 IR 05000333/20240012024-05-0909 May 2024 Integrated Inspection Report 05000333/2024001 IR 05000333/20230062024-02-28028 February 2024 Annual Assessment Letter for James A. FitzPatrick Nuclear Power Plant (Report 05000333/2023006) IR 05000333/20230042024-02-0707 February 2024 Integrated Inspection Report 05000333/2023004 and Independent Spent Fuel Storage Installation Inspection Report 07200012/2023001 IR 05000333/20234012023-12-0808 December 2023 Cybersecurity Inspection Report 05000333/2023401 (Cover Letter Only) IR 05000333/20230032023-11-13013 November 2023 Integrated Inspection Report 05000333/2023003 IR 05000333/20230102023-10-26026 October 2023 Biennial Problem Identification and Resolution Inspection Report 05000333/2023010 IR 05000333/20233012023-10-19019 October 2023 Initial Operator Licensing Examination Report 05000333/2023301 IR 05000333/20230052023-08-31031 August 2023 Updated Inspection Plan for James A. FitzPatrick Nuclear Power Plant (Report 05000333/2023005) IR 05000333/20230022023-08-0707 August 2023 Integrated Inspection Report 05000333/2023002 IR 05000333/20234022023-07-26026 July 2023 Security Baseline Inspection Report 05000333/2023402 IR 05000333/20230112023-07-25025 July 2023 Post-Approval Site Inspection for License Renewal - Phase 4 Inspection Report 05000333/2023011 IR 05000333/20235012023-07-20020 July 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000333/2023501 IR 05000333/20234202023-06-26026 June 2023 Security Baseline Inspection Report 05000333 2023420 IR 05000333/20230012023-05-0303 May 2023 Integrated Inspection Report 05000333/2023001 IR 05000333/20230122023-04-13013 April 2023 Quadrennial Fire Protection Inspection Report 05000333/2023012 IR 05000333/20220042023-03-20020 March 2023 Integrated Inspection Report 05000333/2022004 IR 05000333/20220062023-03-0101 March 2023 Annual Assessment Letter for James A. FitzPatrick Nuclear Power Plant (Report 05000333/2022006) IR 05000333/20220032022-11-10010 November 2022 Integrated Inspection Report 05000333/2022003 IR 05000333/20220052022-08-31031 August 2022 Updated Inspection Plan for James A. Fitzpatrick Nuclear Power Plant (Report 05000333/2022005) IR 05000333/20220022022-08-10010 August 2022 Integrated Inspection Report 05000333/2022002 IR 05000333/20220102022-06-27027 June 2022 Reissued Design Basis Assurance Inspection (Teams) Inspection Report 05000333/2022010 ML22153A2612022-06-0202 June 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000333/2022010 IR 05000333/20210142022-05-23023 May 2022 Problem Identification and Resolution Inspection Report 05000333/2021014 IR 05000333/20220012022-05-0505 May 2022 Integrated Inspection Report 05000333/2022001 and Independent Spent Fuel Storage Installation Inspection Report 07200012/2022001 IR 05000333/20210062022-03-0202 March 2022 Annual Assessment Letter for James A. Fitzpatrick Nuclear Power Plant (Report 05000333/2021006) IR 05000333/20210042022-01-27027 January 2022 Integrated Inspection Report 05000333/2021004 IR 05000333/20210032021-11-0808 November 2021 Integrated Inspection Report 05000333/2021003 IR 05000333/20210402021-11-0808 November 2021 95001 Supplemental Inspection Report 05000333/2021040 and Assessment Follow-Up Letter IR 05000333/20213012021-10-0505 October 2021 Initial Operator Licensing Examination Report 05000333/2021301 IR 05000333/20215012021-09-29029 September 2021 Emergency Preparedness Biennial Exercise Inspection Report 05000333/2021501 IR 05000333/20210052021-09-0101 September 2021 Updated Inspection Plan for the James A. Fitzpatrick Nuclear Power Plant (Report 05000333/2021005) IR 05000333/20210132021-08-11011 August 2021 Biennial Problem Identification and Resolution Inspection Report 05000333/2021013 IR 05000333/20210022021-08-0303 August 2021 James A. Fitpatrick Nuclear Power Plant - Integrated Inspection Report 05000333/2021002 ML21176A0052021-06-25025 June 2021 Acknowledgement of Dispute of Violations Associated with White Finding - NRC Inspection Report 05000333/2021090 IR 05000333/20214022021-06-0909 June 2021 Security Baseline Inspection Report 05000333/2021402 IR 05000333/20210112021-06-0303 June 2021 Design Basis Assurance Inspection (Programs) Inspection Report 05000333/2021011 IR 05000333/20210012021-05-0505 May 2021 Integrated Inspection Report 05000333/2021001 IR 05000333/20210122021-05-0404 May 2021 Temporary Instruction 2515/194 Inspection Report 05000333/2021012 IR 05000333/20210902021-04-20020 April 2021 Final Significance Determination of a White Finding with Assessment Follow-Up and Notice of Violation: NRC Inspection Report 05000333/2021090 IR 05000333/20214012021-04-19019 April 2021 Material Control and Accounting Program Inspection Report 05000333/2021401 (Letter Only) IR 05000333/20210102021-04-0707 April 2021 Triennial Fire Protection Inspection Report 05000333/2021010 IR 05000333/20200062021-03-0303 March 2021 Annual Assessment Letter for James A. FitzPatrick Nuclear Power Plant (Report 05000333/2020006) IR 05000333/20200042021-02-11011 February 2021 Integrated Inspection Report 05000333/2020004 IR 05000333/20200122021-01-21021 January 2021 Problem Identification and Resolution Report 05000333/2020012 and Preliminary White Finding and Apparent Violation 2024-09-19
[Table view] Category:Letter
MONTHYEARML24276A1332024-10-17017 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 ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing 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 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 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 ML24165A0382024-09-0404 September 2024 Issuance of Amendment No. 356 Update Fuel Handling Accident Analysis 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 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 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 05000333/20230062024-02-28028 February 2024 Annual Assessment Letter for James A. FitzPatrick Nuclear Power Plant (Report 05000333/2023006) IR 05000333/20230042024-02-0707 February 2024 Integrated Inspection Report 05000333/2023004 and Independent Spent Fuel Storage Installation Inspection Report 07200012/2023001 2024-09-04
[Table view] |
Text
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT - NRC TRIENNIAL FIRE PROTECTION INSPECTION REPORT 0500333/2005002
Dear Mr. Sullivan:
On March 31, 2005, the NRC completed a triennial fire protection team inspection at the James A. Fitzpatrick Nuclear Power Plant. The enclosed report documents the inspection findings which were discussed at an exit meeting on March 31, 2005, with Mr. K. Mulligan and other members of your staff.
This inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions regulations and with the conditions of your license. The purpose of the inspection was to evaluate your post-fire safe shutdown capability and fire protection program. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
Based on the results of this inspection no findings of significance were identified.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/ADAMS.html (the Public Electronic Reading Room).
Sincerely,
/RA/
John F. Rogge, Chief Electrical and Fire Protection Branch Division of Reactor Safety Docket No. 50-333 License No. DPR-59
Enclosure:
Inspection Report No. 05000333/2005002
Mr. Theodore Sullivan 2
REGION I==
Docket No. 50-333 License No. DPR-59 Report No. 05000333/2005002 Licensee: Entergy Nuclear Operations, Inc.
Facility: James A. Fitzpatrick Nuclear Power Plant Location: 268 Lake Road Lycoming, New York Dates: March 14-18 and 28-31, 2005 Inspectors: R. Fuhrmeister, Sr. Reactor Engineer, Division of Reactor Safety (DRS)
J. Bobiak, Reactor Inspector, DRS D. Werkheiser, Reactor Inspector, DRS S. Lewis, Reactor Inspector, DRS Approved by: John F. Rogge, Chief Electrical and Fire Protection Branch Division of Reactor Safety Enclosure
SUMMARY OF FINDINGS
IR 05000333/2005002 on 03/14-18 and 28-31/05, Entergy Nuclear Operations, Inc., James A.
Fitzpatrick Nuclear Power Plant. Fire Protection The report covered a two-week triennial fire protection team inspection by regional specialist inspectors. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 3, dated July 2000.
NRC-Identified Findings
No findings of significance were identified.
Licensee-Identified Violations
None ii
REPORT DETAILS
Background This report presents the results of a triennial fire protection inspection conducted in accordance with the February 18, 2005, revision of NRC Inspection Procedure (IP) 71111.05T, Fire Protection. The objective of the inspection was to assess whether Entergy Nuclear Operations, Inc. (Entergy) has implemented an adequate fire protection program and that post-fire safe shutdown capabilities have been established and are being properly maintained at the James A. Fitzpatrick Nuclear Power Plant (Fitzpatrick or JAFNPP). The following target fire areas were selected for detailed review based on risk insights from the JAFNPP Individual Plant Examination (IPE) and Individual Plant Examination of External Events (IPEEE):
@ Fire Area CR-1
@ Fire Area RR-1
@ Fire Area RB-1E
@ Fire Area BR-2
@ Fire Area CT-2
REACTOR SAFETY
Cornerstones: Initiating Events, Mitigating Systems
1R05 Fire Protection
Shutdown From Outside Main Control Room
a. Inspection Scope
The inspectors reviewed AOP-43, Plant Shutdown from outside the Control Room, to determine what equipment was credited for post-fire safe shutdown (SSD) and what shutdown methodology was used. The inspectors also walked down the alternate shutdown panels in the field to evaluate accessability, habitability, and access/egress path lighting. The team evaluated selected safe shutdown components and their power and control circuits to determine whether proper alternate power sources were provided for those components and to verify whether alternate shutdown control would be affected by fire-induced circuit faults. The team reviewed the electrical isolation capability of selected equipment needed for post-fire safe shutdown to ensure that such equipment could be operated locally or from the alternate shutdown panels, if needed.
In addition, the team also reviewed the surveillance test procedure and test records of the five Remote Shutdown Panels to ensure that the functionality of the panel switch functions had been adequately demonstrated and to evaluate compliance with the JAFNPP licensing basis for fire protection.
b. Findings
No findings of significance were identified.
2. Protection of Safe Shutdown Capabilities
a. Inspection Scope
The inspectors reviewed AOP-28, Operation During Plant Fires, the JAFNPP Fire Hazards Analysis, Safe Shutdown Analysis, and FSAR to determine the strategies and equipment intended for Safe Shutdown for the target fire areas. The team evaluated selected safe shutdown components and their power and control circuits to determine whether proper separation and fire protection were provided for those components and to determine if the design requirements satisfy Section III.G of 10CFR50 Appendix R, and other JAFNPP licensing basis documents. The target fire areas were walked down by the team to verify the field configuration and status of selected cable routes and components with respect to their documented condition.
b. Findings
No findings of significance were identified.
3. Passive Fire Protection
a. Inspection Scope
The team walked down accessible portions of the target fire areas to observe material condition and the adequacy of design of fire area boundaries, fire doors, and fire dampers. The team reviewed surveillance and functional test procedures for selected items. The team also reviewed licensee submittals and NRC safety evaluation reports (SERs) associated with fire protection features. Additionally, the team reviewed the inspection history of selected barriers.
During tours of the facility, the team observed the storage of permanent and transient combustible materials and control of ignition sources. The team also reviewed the procedure that controls hot-work activities at the site. Additionally, the team reviewed a sample of hot work permits.
b. Findings
No findings of significance were identified.
4. Active Fire Protection
a. Inspection Scope
During tours of the facility, the team observed the material condition of fire protection systems and equipment. The team reviewed the adequacy of the fire detection and suppression systems in the target fire areas. This included a walkdown of the systems and review of the type of installed detectors as shown on equipment location drawings.
The team observed portable extinguishers to determine the material condition of the manual fire fighting equipment and verify locations as specified in the pre-fire plans and fire protection program documents. Additionally, the team reviewed fire detection and suppression surveillance procedures to determine the adequacy of the component testing and to ensure that the systems would function as required.
The team inspected the fire brigades protective ensembles, self-contained breathing apparatus (SCBA), and various fire brigade equipment to determine operational readiness for fire fighting. The team reviewed pre-fire plans for the target fire areas to determine if appropriate information was provided to fire brigade members and plant operators to identify safe shutdown equipment and instrumentation, and to facilitate suppression of a fire that could impact safe shutdown. The team reviewed fire brigade training course material to verify appropriate training was being conducted for the station fire fighting personnel. Additionally, the team reviewed selected fire drills and critiques to ensure that drills were being conducted in risk significant areas. The team reviewed the qualifications of several fire brigade leaders and members to ensure that they had met and maintained the requirements to be fire brigade leaders and members.
b. Findings
No findings of significance were identified.
5. Operational Implementation of Post-Fire Shutdown Capability
a. Inspection Scope
The team reviewed post-fire shutdown procedures, Simulator Exercise Guides and Job Performance Measures to verify procedure adequacy, that plant operators were provided appropriate training for post-fire shutdown activities, and that the required activities were feasible. The team compared the activities in post-fire shutdown procedures for the target areas to the fire protection safety evaluation reports to determine whether JAFNPP relied on any unapproved manual operator actions in lieu of protection of equipment.
The team performed a walkdown of the contingency actions specified in Attachment 11 to AOP-28 in order to verify feasability of the actions and that the areas would be accessible following the postulated fire. The team also verified the availability of special tools and necessary safety equipment.
The team also reviewed the surveillance test procedure and test records of the five Remote Shutdown Panels to ensure that the functionality of the panel switch functions had been adequately demonstrated.
b. Findings
No findings of significance were identified.
6. Circuit Analyses
a. Inspection Scope
The team reviewed the JAFNPP Safe Shutdown Analysis and verified that, for each target fire area, a post-fire safe shutdown analysis was performed and components required for SSD were identified. The JAFNPP analysis assessed the impact on SSD from various failures and addressed each circuit individually. Cable failure modes were reviewed for the following components:
- (1) Loop B RHR HX Bypass 10MOV-66B,
- (2) Head vent solenoid valves 02SOV-17 & 18, and
- (3) RHR inboard isolation valve 10MOV-25B.
The team reviewed cable routing for post-fire SSD components to confirm that cables subject to fire damage in the five target fire areas were identified and adequately addressed. The team also performed a walk-down of cable raceways for a sample of components required for SSD to verify that cables were routed as described in the cable routing matrices.
The team reviewed circuit breaker coordination studies to ensure equipment needed to conduct post-fire safe shutdown activities would not be impacted due to a lack of protective device coordination. The team also reviewed the JAFNPP Multiple High Impendence Fault Analysis for selected feeder buses and MCCs for components important to SSD to verify continuity of power under fire damage conditions. The team confirmed that coordination studies had addressed multiple faults due to fire.
b. Findings
No findings of significance were identified.
7. Communications
a. Inspection Scope
During the walkdown of the alternate shutdown panels and the Contingency actions specified in Attachment 11 to AOP-28, the team verified that multiple means of communication were provided for the use of operators during post-fire shutdown activities.
b. Findings
No findings of significance were identified.
8. Emergency Lighting
a. Inspection Scope
The team observed the placement and coverage area of eight-hour emergency lights throughout the target fire areas to evaluate their adequacy for illuminating access and egress pathways and any equipment requiring local operation for post-fire safe shutdown. The team also reviewed preventive maintenance procedures and completed surveillance tests, to determine if adequate surveillance testing and periodic battery replacements were in place to ensure reliable operation of the emergency lights. The team observed portions of an eight-hour discharge test.
b. Findings
No findings of significance were identified.
Cold Shutdown Repairs
a. Inspection Scope
The team reviewed post-fire shutdown procedures, and the safety evaluation reports related to fire protection to identify cold shutdown repairs. The team chose to verify cold shutdown repair activities specified in Attachment 11 to AOP-28. The team performed an inventory of the equipment, and observed a walkthrough of the repair by plant operators to verify feasability, and appropriate equipment and tools were available.
b. Findings
No findings of significance were identified.
OTHER ACTIVITIES
4OA2 Identification and Resolution of Problems
Corrective Actions for Fire Protection Deficiencies
a. Inspection Scope
The team reviewed selected condition reports for fire protection issues and the recent fire protection program system health report to evaluate the prioritization for resolving fire protection related deficiencies and the effectiveness of corrective actions. The team also reviewed a recent quality assurance audit and self-assessments of the fire protection program to determine if the licensee was identifying program deficiencies and implementing appropriate corrective actions.
b. Findings
No findings of significance were identified.
4OA6 Meetings, Including Exit
Exit Meeting Summary
The team presented their preliminary inspection results to Mr. K. Mulligan and other members of the Entergy staff at an exit meeting on March 31, 2005.
No proprietary information was included in this inspection report.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee Personnel
- K. Mulligan, General Manager of Plant Operatoins
- J. Pechacek, Manager of Design Engineering
- J. Gerety, Manager of Programs and Component Engineering
- D. Wallace, Manager of Quality Assurance
- M. Durr, Manager of System Engineering
- D. Johnson, Manager of Operations
- T. Raymond, Manager of Information Technology
- D. Koelbel, Fire Protection System Engineer
- S. Reininghouse, Training Supervisor
- R. Locy, Operations Project manager
- R. Jennings, Fire Protection Specialist
- D. Stokes, Fire Protection Engineer
- D. Spindler, Shift Manager
Constellation Generation Group, LLC
- G. Cooper, Fire Safe Shutdown Engineer
NRC
- J. Lubinski, Acting Deputy Director, Division of Reactor Safety
- J. Rogge, Chief, Electrical and Fire Protection Branch, Division of Reactor Safety
- L. Cline, Senior Resident Inspector
- D. Dempsey, Resident Inspector
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Opened
NONE Open and
Closed
NONE
Closed
NONE
Discussed
NONE
LIST OF DOCUMENTS REVIEWED