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Category:Inspection Report
MONTHYEARIR 05000424/20243012024-11-19019 November 2024 Operator Licensing Examination Approval 05000424/2024301 and 05000425/2024301 ML24313A0632024-11-14014 November 2024 Integrated Inspection Report and Assessment Follow-Up Letter 05200025/2024003 and 05200026/2024003 IR 05000424/20240032024-10-30030 October 2024 – Integrated Inspection Report 05000424/2024003 and 05000425/2024003 IR 05000424/20240052024-08-26026 August 2024 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 1 and 2 - Report 05000424/2024005 and 05000425/2024005 IR 05000424/20244012024-08-15015 August 2024 4 - Security Baseline Inspection Report 05000424-2024401, 05000425-2024401, 05200025-2024402, and 05200026-2024403 - Cover Letter ML24212A1442024-08-0101 August 2024 Integrated Inspection Report 05200025/2024002 and 05200026/2024002 IR 05000424/20240022024-07-29029 July 2024 Integrated Inspection Report 05000424/2024002 and 05000425/2024002 IR 05000424/20244042024-07-26026 July 2024 Material Control and Accounting Program Inspection Report 05000424/2024404 and 05000425/2024404 (Cover Letter) ML24194A0342024-07-12012 July 2024 Review of the Refueling Outage 1R24 Steam Generator Tube Inspection Report ML24191A3792024-07-10010 July 2024 – Initial Test Program and Operational Programs Inspection Report 05200026/2024011 ML24130A2412024-05-13013 May 2024 Integrated Inspection Report 05200025/2024001 and 05200026/2024001 ML24127A2372024-05-0909 May 2024 Initial Test Program and Operational Programs Inspection Report 05200026/2024010 IR 05000424/20240012024-04-23023 April 2024 –Integrated Inspection Report 05000424/2024001 and 05000425/2024001 IR 05000424/20230062024-02-28028 February 2024 Annual Assessment Letter for Vogtle Electric Generating Plant Units 1 and 2 - NRC Inspection Report 05000424-2023006 and 05000425-2023006 IR 05000424/20240102024-02-14014 February 2024 – Fire Protection Team Inspection Report 0500424/2024010 and 05000425/2024010 IR 05000202/20300042024-02-13013 February 2024 Integrated Inspection Report 052000250/2023004 and 05200026/2023004 IR 05000424/20230042024-02-0505 February 2024 Integrated Inspection Report 05000424-2023004 and 05000425-2023004 ML24032A0252024-02-0505 February 2024 NRC Initial Test Program and Operational Programs Integrated Inspection Report 05200026-2023009 ML24031A6102024-01-31031 January 2024 Cyber Security Inspection Report 05200026/2024401 - Public IR 05000424/20244032024-01-26026 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000424/2024403; 05000425/2024403 ML23312A3502023-11-14014 November 2023 – Integrated Inspection Report 05200026/2023003 ML23318A4582023-11-14014 November 2023 Integrated Inspection Report 05200025/2023003 IR 05000424/20234022023-11-0606 November 2023 – Security Baseline Inspection Report 05000424/2023402 and 05000425/2023402 IR 05000424/20230032023-10-27027 October 2023 Integrated Inspection Report 05000424/2023003 and 05000425/2023003 ML23254A2032023-09-13013 September 2023 – Initial Test Program and Operational Programs Inspection Report 05200025/2023013 IR 05000424/20230912023-09-0505 September 2023 Plan Units 1 and 2 - NRC Investigation Report 2-2022-006 and Notice of Violation - NRC Inspection Report 05000424/2023091 and 05000425/2023091 ML23234A3002023-09-0101 September 2023 NRC Integrated Inspection Report 05200026/2023003 IR 05000424/20230052023-08-29029 August 2023 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 1 & 2 - Report 05000424/2023005 and 05000425/2023005 ML23223A0022023-08-14014 August 2023 Integrated Inspection Report 05200025/2023002 IR 05000424/20230112023-08-11011 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000424/2023011 and 05000425/2023011 ML23215A0822023-08-0404 August 2023 (Vego), Unit 3 – Initial Test Program and Operational Programs Integrated 05200025/2023011 Inspection Report IR 05000424/20234012023-07-31031 July 2023 Security Baseline Inspection Report 05000424/2023401 and 05000425/2023401 (Cover Letter) ML23212B0612023-07-31031 July 2023 Security Baseline Inspection Report 05200025/2023401 ML23216A0962023-07-26026 July 2023 Document Request for Vogtle 1 & 2 RP Inspection, Report No. 05000424/2023003 and 05000425/2023003 IR 05000424/20230022023-07-24024 July 2023 Integrated Inspection Report 05000424/2023002 and 05000425/2023002 ML23198A3802023-07-19019 July 2023 NRC Integrated Inspection Report 05200026/2023002 ML23199A0892023-07-18018 July 2023 Initial Test Program and Operational Programs Integrated Inspection Report 05200026/2023007 IR 05000424/20233012023-06-30030 June 2023 – NRC Operator License Examination Report 05000424/2023301 and 05000425/2023301 ML23128A2932023-05-11011 May 2023 NRC Integrated Inspection Report 05200026/2023001 ML23129A0222023-05-10010 May 2023 Integrated Report 05200025/2023001 ML23128A3492023-05-0909 May 2023 – Initial Test Program and Operational Programs Integrated Inspection Report 05200026/2023006 ML23121A3202023-05-0404 May 2023 NRC Initial Test Program and Operational Programs Integrated Inspection Report 05200025/2023010 IR 05000424/20040252023-04-28028 April 2023 Public Meeting Summary - Vogtle Electric Generating Plant, Units 1, 2, 3, & 4 Docket No. 5000424, 5000425, 5200025, 5200026, Meeting Number 20230375 IR 05000424/20230012023-04-26026 April 2023 Integrated Inspection Report 05000424/2023001 and 05000425/2023001 IR 05000424/20230902023-03-30030 March 2023 NRC Inspection Report 05000424/2023090 and 05000425/2023090, and Investigation Report 2-2022-006; and Apparent Violation ML23083B3702023-03-24024 March 2023 Security Baseline Inspection Report 05200026/2023401 IR 05000424/20220062023-03-0101 March 2023 Annual Assessment Letter for Vogtle Electric Generating Plant Units 1 and 2, NRC Inspection Reports 05000424/2022006 and 05000425/2022006 ML23044A3902023-02-14014 February 2023 Integrated Inspection Report05200025 2022007 ML23040A0422023-02-0909 February 2023 NRC Initial Test Program and Operational Programs Integrated Inspection Report 05200025/2022008 ML23040A3612023-02-0909 February 2023 – NRC Initial Test Program and Operational Programs Integrated Inspection Report 05200026/2022008 2024-08-26
[Table view] Category:Letter
MONTHYEARIR 05000424/20243012024-11-19019 November 2024 Operator Licensing Examination Approval 05000424/2024301 and 05000425/2024301 ML24313A0632024-11-14014 November 2024 Integrated Inspection Report and Assessment Follow-Up Letter 05200025/2024003 and 05200026/2024003 ML24305A1662024-11-0606 November 2024 Vogle Electric Generating Plant, Unit 3 - Summary of Conference Call Regarding the Fall 2024 Steam Generator Tube Inspections NL-24-0217, License Amendment Request: Source Range Neutron Flux Doubling Function Applicability2024-11-0101 November 2024 License Amendment Request: Source Range Neutron Flux Doubling Function Applicability NL-24-0385, Request for Action Matrix Deviation Due to Recent Events Impacting the Unplanned Scram with Complications Performance Indicator2024-10-31031 October 2024 Request for Action Matrix Deviation Due to Recent Events Impacting the Unplanned Scram with Complications Performance Indicator IR 05000424/20240032024-10-30030 October 2024 – Integrated Inspection Report 05000424/2024003 and 05000425/2024003 NL-24-0386, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks Response to Request for Additional Information2024-10-28028 October 2024 License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks Response to Request for Additional Information NL-24-0392, Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-0022024-10-28028 October 2024 Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-002 NL-24-0366, Core Operating Limits Report, Cycle 26, Version 12024-10-25025 October 2024 Core Operating Limits Report, Cycle 26, Version 1 ML24297A6482024-10-23023 October 2024 5 to the Updated Final Safety Analysis Report, Technical Specification Bases Changes, Technical Requirements Manual Changes, Summary Report and Revised NRC Commitments Report ML24269A2502024-09-26026 September 2024 Acknowledgement of the Withdrawal of the Requested Exemption and License Amendment Request to Remove Tier 1 and Tier 2* Requirements NL-24-0369, Withdrawal of License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2 Requirements2024-09-25025 September 2024 Withdrawal of License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2 Requirements NL-24-0350, Core Operating Limits Report, Cycle 24, Version 22024-09-25025 September 2024 Core Operating Limits Report, Cycle 24, Version 2 ML24243A0072024-09-10010 September 2024 – Correction of Amendment Nos. 223 and 206 Regarding Revision to Technical Specifications to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483 NL-24-0337, Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program2024-09-0909 September 2024 Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program ML24102A2642024-09-0909 September 2024 – Exemption Request Regarding Final Safety Analysis Report Update Schedule (EPID L-2024-LLE-0013) - Letter ML24249A2942024-09-0606 September 2024 Correction of Amendment Nos. 218 and 201 Regarding Revision to Technical Specifications to Use Online Monitoring Methodology 05200025/LER-2024-002, Manual Reactor Protection System and Automatic Safeguards Actuation Due to an Unexpected Change in Position of a Main Feedwater Pump Minimum Flow Control Valve2024-09-0505 September 2024 Manual Reactor Protection System and Automatic Safeguards Actuation Due to an Unexpected Change in Position of a Main Feedwater Pump Minimum Flow Control Valve IR 05000424/20240052024-08-26026 August 2024 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 1 and 2 - Report 05000424/2024005 and 05000425/2024005 ML24235A1952024-08-22022 August 2024 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 3 and 4 - Report 05200025/2024005 and 05200026/2024005 IR 05000424/20244012024-08-15015 August 2024 4 - Security Baseline Inspection Report 05000424-2024401, 05000425-2024401, 05200025-2024402, and 05200026-2024403 - Cover Letter NL-24-0299, Exemption Request: Final Safety Analysis Report Update Schedule, Response to Request for Additional Information2024-08-14014 August 2024 Exemption Request: Final Safety Analysis Report Update Schedule, Response to Request for Additional Information 05000425/LER-2024-001, Manual Actuation of the Reactor Protection System Due to a Rod Control Fuse Opening Causing a Misaligned Shutdown Rod2024-08-0909 August 2024 Manual Actuation of the Reactor Protection System Due to a Rod Control Fuse Opening Causing a Misaligned Shutdown Rod ML24218A1842024-08-0707 August 2024 Examination Report and Cover Letter 05200026/LER-2024-001, Manual Reactor Protection System Actuation Due to Procedure Not Optimally Sequenced to Reset the Rapid Power Reduction Signal2024-08-0606 August 2024 Manual Reactor Protection System Actuation Due to Procedure Not Optimally Sequenced to Reset the Rapid Power Reduction Signal ML24212A1442024-08-0101 August 2024 Integrated Inspection Report 05200025/2024002 and 05200026/2024002 IR 05000424/20240022024-07-29029 July 2024 Integrated Inspection Report 05000424/2024002 and 05000425/2024002 IR 05000424/20244042024-07-26026 July 2024 Material Control and Accounting Program Inspection Report 05000424/2024404 and 05000425/2024404 (Cover Letter) NL-24-0126, – Units 3 and 4, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Action a and SR 3.7.6.62024-07-25025 July 2024 – Units 3 and 4, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Action a and SR 3.7.6.6 NL-24-0282, License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2* Requirements2024-07-25025 July 2024 License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2* Requirements ML24204A0722024-07-23023 July 2024 Issuance of Amendment No. 225, Regarding LAR to Revise TS 3.7.9 for a one-time Change to Support Nuclear Service Cooling Water Transfer Pump Repairs - Emergency Circumstances NL-24-0286, Emergency Request to Revise Technical Specification 3.7.9 for a One-Time Change to Support a Unit 1 Nuclear Service Cooling Water Transfer Pump Repair2024-07-20020 July 2024 Emergency Request to Revise Technical Specification 3.7.9 for a One-Time Change to Support a Unit 1 Nuclear Service Cooling Water Transfer Pump Repair NL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 ML24191A4562024-07-19019 July 2024 Request for Relief and Alternative Requirements for Squib (Explosively Actuated) Valves First Test Interval ML24194A0342024-07-12012 July 2024 Review of the Refueling Outage 1R24 Steam Generator Tube Inspection Report ML24191A3792024-07-10010 July 2024 – Initial Test Program and Operational Programs Inspection Report 05200026/2024011 NL-24-0227, Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2024-07-0303 July 2024 Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0234, Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown2024-06-28028 June 2024 Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in NL-24-0087, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks2024-06-21021 June 2024 License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks NL-24-0201, Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2024-06-18018 June 2024 Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0243, Registration of Spent Fuel Cask Use2024-06-18018 June 2024 Registration of Spent Fuel Cask Use ML24163A0632024-06-12012 June 2024 2024 Licensed Operator Re-qualification Inspection Notification Letter Vogtle, Units 3 & 4 ML24155A1772024-06-0505 June 2024 Regulatory Audit in Support of Review of the LAR to Revise Emergency Diesel Generator Frequency and Voltage Ranges for Technical Specification 3.8.1, Surveillance Requirements NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024 SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24094A1402024-05-16016 May 2024 Staff Response to Request for Revision to NRC Staff Assessment of Updated Seismic Hazard Information and Latest Understanding of Seismic Hazards at the Vogtle Plant Site Following the NRC Process for the Ongoing Assessment of Natural Hazard ML24120A1812024-05-13013 May 2024 Request for Withholding Information from Public Disclosure Responses to NRC Request for Additional Information for Refueling Outage IR24 Steam Generator Tube Inspection Report – Enclosure 2 ML24130A2412024-05-13013 May 2024 Integrated Inspection Report 05200025/2024001 and 05200026/2024001 ML24101A2112024-05-11011 May 2024 Expedited Issuance of Amendment No. 198 Change to Technical Specification 5.5.13, Ventilation Filter Testing Program (VFTP) 2024-09-09
[Table view] |
Inspection Report - Vogtle - 2008009 |
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UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
ary 9, 2009
SUBJECT:
VOGTLE ELECTRIC GENERATING PLANT - NRC SUPPLEMENTAL INSPECTION REPORT 05000424/2008009 AND 05000425/2008009
Dear Mr. Tynan:
On December 11, 2008, the U.S. Nuclear Regulatory Commission (NRC) completed a supplemental inspection in accordance with Inspection Procedure 95001, Inspection for One or Two White Inputs in a Strategic Performance Area, at your Vogtle Electric Generating Plant, Units 1 and 2. The purpose of the inspection was to examine the circumstances surrounding the White performance indicators reported during the fourth quarter of 2007 for the Unit 1 and Unit 2 Cooling Water Mitigating Systems Performance Index. The enclosed inspection report documents the inspection results, which were discussed on December 11, 2008, with Mr. Todd Youngblood and other members of your staff.
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.
The inspector reviewed selected procedures and records and interviewed personnel. Based on the results of this inspection, no findings of significance were identified.
In accordance with the Code of Federal Regulations 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter, its enclosures, and your response (if any) will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of the 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/
Scott M. Shaeffer, Chief Reactor Projects Branch 2 Division of Reactor Projects Docket Nos.: 50-424, 50-425 License Nos.: NPF-68 and NPF-81
Enclosure:
Inspection Report 05000424/2008009 and 05000425/2008009 w/Attachment: Supplemental Information
REGION II==
Docket Nos.: 50-424, 50-425 License Nos.: NPF-68, NPF-81 Report Nos.: 05000424/2008009 and 05000425/2008009 Licensee: Southern Nuclear Operating Company, Inc.
Facility: Vogtle Electric Generating Plant, Units 1 and 2 Location: Waynesboro, GA 30830 Dates: August 20 - December 11, 2008 Inspector: G. McCoy, Senior Resident Inspector Approved by: Scott M. Shaeffer, Chief Reactor Projects Branch 2 Division of Reactor Projects Enclosure
SUMMARY OF FINDINGS
IR 05000424/2008-009, 05000425/2008-009; August 20, 2008 - December 11, 2008; Vogtle
Electric Generating Plant, Units 1 and 2; Supplemental Inspection IP 95001 for a reported White Mitigating Systems Performance Index, Cooling Water System Performance Indicator.
This inspection was conducted by a senior resident inspector. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 4, dated December 2006.
Cornerstone: Mitigating Systems
The U.S Nuclear Regulatory Commission (NRC) performed this supplemental inspection in accordance with Inspection Procedure 95001 to assess the licensees evaluation associated with a White Mitigating Systems Performance Indicator, Cooling Water Systems Performance Indicator reported during the fourth quarter of 2007 and later retracted during the first quarter of 2008. The inspector determined that the decision to retract the White performance indicator was supported by the guidance of NEI 99-02, Regulatory Assessment Performance Indicator Guideline.
NRC-Identified and Self-Revealing Findings
No significance of findings were identified.
Licensee-Identified Violations
None.
REPORT DETAILS
INSPECTION SCOPE
The U.S. Nuclear Regulatory Commission (NRC) performed this supplemental inspection to assess the licensees evaluation of a White Mitigating System Performance Index (MSPI),
Cooling Water Systems Performance Indicator (PI) for Unit 1 and Unit 2. The White PI was reported for Unit 1 for the fourth quarter 2007 and for Unit 2 for the third quarter 2007. Both PIs were re-reported Green during the first quarter 2008. This was based on the licensee re-evaluating their NSCW unavailability which caused the PIs to initially be reported as White. This inspection reviewed this re-evaluation which lead the licensee to revise the previously reported White PIs for both units.
Background On October 12, 2007, operators took manual control of the Unit 1 train A Nuclear Service Cooling Water (NSCW) tower return valves to calibrate temperature instrument 1T1668. The Shift Supervisor questioned the operability of the 1A NSCW system while the temperature instrument was being calibrated. This issue was documented in condition report (CR)2007110639. In January 2008, when the licensee was required to submit PI data for the fourth quarter 2007, the licensee conservatively determined that the train A NSCW system was inoperable without the knowledge of the operators and counted the duration the temperature instrument was being calibrated as unavailability time against the Unit 1 MSPI, Cooling Water Systems PI. The licensee reviewed the control room logs and identified that a similar condition had occurred in August 2007 on Unit 2 train B NSCW system. The licensee also counted this duration as unavailability against the Unit 2 MSPI, Cooling Water Systems PI. In conjunction with previous reported unavailability time in the NSCW system, these additional conditions caused the Unit 1 MSPI, Cooling Water Systems PI to cross the Green to White threshold in the fourth quarter of 2007. The Unit 2 MSPI, Cooling Water Systems PI was also reported as White for the fourth quarter of 2007 and retroactively for the third quarter of 2007.
During the first quarter of 2008, the licensee completed a detailed review of these two conditions and determined that in both cases the NSCW Ultimate Heat Sink and the Cooling Water design functions could be met during temperature instrument calibration. The licensee determined the NSCW system remained available in accordance with the guidance of NEI 99-02. Based on this determination, the licensee removed the previously reported unavailability from the PI data for both Unit 1 and Unit 2, reported the PIs as Green for the first quarter of 2008 and retroactively changed the previously reported White PIs to Green starting third quarter of 2007. The NRC has endorsed the guidance of NEI 99-02 for the determination of system availability for PI data reporting purposes. In accordance with this guideline, operator actions can be credited towards system availability if the function can be promptly restored by an operator in the control room, restoration actions are uncomplicated, contained in a written procedure, not require diagnosis or repair, and must be capable of being restored in time to satisfy Probability Risk Assessment (PRA) success criteria. The inspector determined that while the cooling tower was bypassed, plant operating procedure 1350-1, Nuclear Service Cooling Water System Operating Procedure, required the monitoring of NSCW return temperature in the control room and provided actions to be taken if NSCW return temperature limits were exceeded.
The operation of a single switch on the control board in main control room would return cooling to the NSCW cooling loop, even if temperature instrument 1T1668 was out of service. The inspectors determined that the NSCW system could be considered available for MSPI reporting purposes and that the licensee properly reported the PI as Green for the third and fourth quarters of 2007. The inspector noted that the licensee has modified the procedures for taking manual control of the NSCW tower return valves to make this plant condition more evident to the operators by requiring a caution tag be placed on the NSCW cooling tower return valve control switch anytime it is out of the automatic position.
In addition, the inspector reviewed the associated condition reports, reviewed the cause determinations performed, and reviewed the operability determinations. Inspector also interviewed operations and licensing personnel to understand the basis for their decisions.
During this inspection, the inspector questioned the licensees determination that the NSCW system was operable with the NSCW cooling tower return valves in manual control. The inspector noted that the NSCW system is a support system for the Ultimate Heat Sink, and without the proper operation of the NSCW cooling tower return valves the Ultimate Heat Sink would not be able to accomplish its design function during a design basis accident. The inspector also noted there is no provision in the technical specifications, the USFAR nor the safety evaluations written by the NRC for the NSCW system which evaluates the operation of the system with manual control of the tower return valves without declaring the NSCW system inoperable and entering the TS action Limiting Condition for Operability (LCO). This issue is identified as an unresolved item (URI)05000424/2008009-01, Technical Specification Operability Of The NSCW System With The Cooling Tower Return Valves In Manual Control.
EVALUATION OF INSPECTION REQUIREMENTS 02.01 Problem Identification a.
Determination of who (i.e., licensee, self-revealing, or NRC) identified the issue and under what conditions.
The potential unavailability of the NSCW system was identified by the licensee when system operability was questioned while temperature instrument 1T1668 was being calibrated.
b.
Determination of how long the issue existed, and prior opportunities for identification.
This issue existed on October 12, 2007, while temperature instrument 1T1668 was being calibrated. A previous case was identified in August 2007 when 2T1669 was being calibrated.
c.
Determination of the plant-specific risk consequences (as applicable) and compliance concerns associated with the issue.
Because of the compensatory actions (monitoring temperature, etc) taken during temperature instrument calibration, the licensee determined that the risk consequences was minimal. No compliance concerns were identified because the licensee properly reported the PI data.
02.02 Root Cause and Extent of Condition Evaluation Because the NSCW system was determined to be available while the temperature instrument was being calibrated, no cause evaluation was performed by the licensee.
The licensee determined that manual operation of NSCW tower return valves during temperature instrument calibration was consistent with other manual actions for this system where sufficient time and methods were provided to ensure the safety function of the system was maintained.
02.03 Corrective Actions No corrective actions were required or performed by the licensee because the NSCW system was determined to be available. However, the licensee modified plant procedures for taking manual control of the NSCW tower return valves to make this plant condition more evident to the operators by requiring a tag be placed on the NSCW cooling tower return valve control switch anytime it was out of the automatic position.
They also modified the plant emergency procedures to verify proper operation of the tower return valves if the control switch needed to be repositioned. These actions were considered to enhance the operators ability to maintain the NSCW system available.
The inspector determined that the licensee properly determined that the NSCW system was available during temperature instrument 1T1668 calibration. The inspector also determined the licensee properly reported the PI as Green for the third and fourth quarters of 2007.
MANAGEMENT MEETINGS
Exit Meeting Summary
The inspector presented the results of the supplemental inspection to Mr. Todd Youngblood and other members of licensee management and staff on December 11, 2008. The inspector confirmed that no proprietary information was provided or examined during the inspection.
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee Personnel
- M. Hickox, Licensing Engineer
- J. Stringfellow, Licensing Manager
- D. Vineyard, Operations Manager
- T. Youngblood, Engineering Manager
LIST OF ITEMS
OPENED AND CLOSED
Opened and Closed
- 05000424, 425/2008009-01 URI Technical Specification Operability Of The NSCW System With The Cooling Tower Return Valves In Manual Control. (Section 01)
LIST OF DOCUMENTS REVIEWED