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Category:Inspection Report
MONTHYEARIR 05000254/20240112024-11-13013 November 2024 Biennial Problem Identification and Resolution Inspection Report 05000254/2024011 and 05000265/2024011 IR 05000254/20240032024-11-12012 November 2024 Integrated Inspection Report 05000254/2024003, 05000265/2024003 and 07200053/2024001 IR 05000254/20240102024-10-28028 October 2024 Age Related Degradation Inspection Report 05000254/2024010 and 05000265/2024010 and Notice of Violation IR 05000254/20244022024-09-12012 September 2024 Material Control and Accounting Program Inspection Report 05000254/2024402 and 05000265/2024402 (Public) IR 05000254/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Quad Cities Nuclear Power Station (Report 05000254/2024005; 05000265/2024005) IR 05000254/20240022024-08-12012 August 2024 Integrated Inspection Report 05000254/2024002 and 05000265/2024002 IR 05000254/20243012024-08-0101 August 2024 NRC Initial License Examination Report 05000254/2024301; 05000265/2024301 IR 05000254/20240012024-05-14014 May 2024 Integrated Inspection Report Nos. 05000254/2024001 and 05000265/2024001 IR 05000254/20245012024-04-0505 April 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000254/2024501 and 05000265/2024501 IR 05000254/20230062024-02-28028 February 2024 Annual Assessment Letter for Quad Cities Nuclear Power Station, Units 1 and 2 (Report 05000254/2023006 and 05000265/2023006) IR 05000254/20230042024-02-0505 February 2024 Integrated Inspection Report 05000254/2023004 and 05000265/2023004 IR 05000254/20234032023-12-22022 December 2023 Public- Quad Cities Nuclear Power Station Security Baseline Inspection Report 05000254/2023403 and 05000265/2023403 IR 05000254/20230102023-12-20020 December 2023 Comprehensive Engineering Team Inspection Report 05000254/2023010 and 05000265/2023010 IR 05000254/20230032023-11-0909 November 2023 Integrated Inspection Report 05000254/2023003 and 05000265/2023003 IR 05000254/20230112023-09-20020 September 2023 Safety-Conscious Work Environment Issue of Concern Team Inspection Report 05000254/2023011 and 05000265/2023011 IR 05000254/20230052023-08-25025 August 2023 Updated Inspection Plan and Assessment Follow-Up Letter for Quad Cities Nuclear Power Station (Report 05000254/2023005; 05000265/2023005) IR 05000254/20230022023-08-0808 August 2023 Integrated Inspection Report 05000254/2023002 and 05000265/2023002 IR 05000254/20234012023-06-26026 June 2023 Cyber Security Inspection Report 05000254/2023401 and 05000265/2023401 IR 05000265/20230402023-06-22022 June 2023 Reissue Quad Cities Nuclear Power Station 95001 Supplemental Inspection Supplemental Report 05000265/2023040 and Follow Up Assessment Letter ML23167B1722023-06-16016 June 2023 95001 Supplemental Inspection Report 05000265/2023040 and Follow-Up Assessment Letter IR 05000254/20234022023-05-15015 May 2023 Security Baseline and ISFSI Inspection Reports 05000254/2023402, 05000265/2023402, 07200053/2023401 IR 05000254/20230012023-05-0808 May 2023 Integrated Report 05000254/2023001 and 05000265/2023001 ML23065A2832023-03-0707 March 2023 Request for Information for the NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000254/2023010 and 05000265/2023010 IR 05000254/20233012023-03-0707 March 2023 NRC Initial License Examination Report 05000254/2023301; 05000265/2023301 IR 05000254/20220062023-03-0101 March 2023 Annual Assessment Letter for Quad Cities Nuclear Power Station, Units 1 and 2 (Report 05000254/2022006 and 05000265/2022006) IR 05000254/20220042023-02-10010 February 2023 Integrated Inspection Report 05000254/2022004 and 05000265/2022004 IR 05000254/20220112023-01-0606 January 2023 Triennial Fire Protection Inspection Report 05000254/2022011 and 05000265/2022011 IR 05000254/20220102022-12-13013 December 2022 Phase 4 Post-Approval License Renewal Inspection Report 05000254/2022010 and 05000265/2022010 ML22313A1502022-11-29029 November 2022 EA-22-062 QC ERV Final Action IR 05000254/20224012022-11-22022 November 2022 Security Baseline Inspection Report 05000254/2022401 and 05000265/2022401 IR 05000254/20220132022-11-17017 November 2022 Biennial Problem Identification and Resolution Inspection Report 05000254/2022013 and 05000265/2022013 IR 05000254/20220032022-11-0303 November 2022 Integrated Inspection Report 05000254/2022003 and 05000265/2022003 IR 05000254/20220052022-08-22022 August 2022 Updated Inspection Plan for Quad Cities Nuclear Power Station (Report 05000254/2022005; 05000265/2022005) IR 05000254/20225012022-08-15015 August 2022 Emergency Preparedness Biennial Exercise Inspection Report 05000254/2022501 and 05000265/2022501 IR 05000254/20220022022-08-0909 August 2022 Integrated Inspection Report 05000254/2022002 and 05000265/2022002 IR 05000254/20220902022-08-0808 August 2022 NRC Inspection Report 05000254/2022090 and 05000265/2022090; Preliminary White Finding IR 05000254/20220122022-07-11011 July 2022 Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000254/2022012 and 05000265/2022012 IR 05000254/20220012022-05-11011 May 2022 Integrated Inspection Report 05000254/2022001 and 05000265/2022001 IR 05000254/20210062022-03-0202 March 2022 Annual Assessment Letter for Quad Cities Nuclear Power Station, Units 1 and 2 (Report 05000254/2021006 and 05000265/2021006) IR 05000254/20210042022-02-0202 February 2022 Integrated Inspection Report 05000254/2021004 and 05000265/2021004 ML22033A1672022-02-0202 February 2022 Notification of NRC Baseline Inspection and Request for Information Inspection Report 05000265/2022001 IR 05000254/20214022021-12-0101 December 2021 Security Baseline Inspection Report 05000254/2021402 and 05000265/2021402 IR 05000254/20210102021-11-24024 November 2021 Design Basis Assurance Inspection (Programs) Inspection Report 05000254/2021010 and 05000265/2021010 IR 05000254/20210032021-10-28028 October 2021 Integrated Inspection Report 05000254/2021003 and 05000265/2021003 IR 05000254/20214012021-09-0909 September 2021 Security Baseline Inspection Report 05000254/2021401 and 05000265/2021401 IR 05000254/20210052021-09-0101 September 2021 Updated Inspection Plan for Quad Cities Nuclear Power Station (Report 05000254/2021005 and 05000265/2021005) ML21238A3142021-08-26026 August 2021 Notification of an NRC Triennial Heat Sink Performance Inspection and Request for Information; Inspection Report 05000254/2021004; 05000265/2021004 IR 05000254/20213012021-08-23023 August 2021 NRC Initial License Examination Report 05000254/2021301; 05000265/2021301 IR 05000254/20210022021-08-0909 August 2021 Integrated Inspection Report 05000254/2021002 and 05000265/2021002 IR 05000254/20214032021-06-28028 June 2021 Quad Nuclear Power Station - Material Control and Accounting Program Inspection Report 05000254/2021403 and 05000265/2021403 2024-09-12
[Table view] Category:Letter
MONTHYEARIR 05000254/20240112024-11-13013 November 2024 Biennial Problem Identification and Resolution Inspection Report 05000254/2024011 and 05000265/2024011 IR 05000254/20240032024-11-12012 November 2024 Integrated Inspection Report 05000254/2024003, 05000265/2024003 and 07200053/2024001 ML24317A1432024-11-0404 November 2024 Constellation Energy Generation, LLC, 2024 Annual Report - Guarantees of Payment of Deferred Premiums RS-24-101, License Amendment Request for One-Time Extension of Standby Gas Treatment System Technical Specifications Completion Time to Support Piping Repair2024-11-0404 November 2024 License Amendment Request for One-Time Extension of Standby Gas Treatment System Technical Specifications Completion Time to Support Piping Repair RS-24-126, Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in Accordance with 10 CFR 2.390(b)(4)2024-10-31031 October 2024 Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in Accordance with 10 CFR 2.390(b)(4) 05000265/LER-2024-002-01, Turbine Trip and Automatic Scram Due to Digital EHC Power Supply Intermittent Failure2024-10-30030 October 2024 Turbine Trip and Automatic Scram Due to Digital EHC Power Supply Intermittent Failure SVP-24-065, Offsite Dose Calculation Manual (ODCM) Section 12.2.2 Radioactive Gaseous Effluent Monitoring Instrumentation Report Main Chimney High Range Noble Gas Monitor2024-10-29029 October 2024 Offsite Dose Calculation Manual (ODCM) Section 12.2.2 Radioactive Gaseous Effluent Monitoring Instrumentation Report Main Chimney High Range Noble Gas Monitor IR 05000254/20240102024-10-28028 October 2024 Age Related Degradation Inspection Report 05000254/2024010 and 05000265/2024010 and Notice of Violation RS-24-080, Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in .2024-10-16016 October 2024 Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in . 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 SVP-24-059, Correction to Registration of Use of Casks to Store Spent Fuel2024-10-0404 October 2024 Correction to Registration of Use of Casks to Store Spent Fuel ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24247A1642024-09-30030 September 2024 Alternative Request RP-01 IR 05000254/20244022024-09-12012 September 2024 Material Control and Accounting Program Inspection Report 05000254/2024402 and 05000265/2024402 (Public) SVP-24-054, Deviation from BWR Vessel and Internals Project (BWRVIP) Guidelines - Inspection of Top Guide Rim Welds2024-09-11011 September 2024 Deviation from BWR Vessel and Internals Project (BWRVIP) Guidelines - Inspection of Top Guide Rim Welds ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000254/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Quad Cities Nuclear Power Station (Report 05000254/2024005; 05000265/2024005) RS-24-078, Alternative Request RV-08, Revision 1, Associated with Safety Relief Valve Testing Interval2024-08-20020 August 2024 Alternative Request RV-08, Revision 1, Associated with Safety Relief Valve Testing Interval ML24183A1082024-08-0808 August 2024 – Issuance of Amendment Nos. 302 and 298 Adoption of Tstf-505, Provide Risk Informed Extended Completion Times – RITSTF Initiative 4b SVP-24-049, Owners Activity Report Submittal Sixth 10-Year Interval 2024 Refueling Outage Activities2024-08-0707 August 2024 Owners Activity Report Submittal Sixth 10-Year Interval 2024 Refueling Outage Activities IR 05000254/20243012024-08-0101 August 2024 NRC Initial License Examination Report 05000254/2024301; 05000265/2024301 SVP-24-048, Registration of Use of Casks to Store Spent Fuel2024-07-31031 July 2024 Registration of Use of Casks to Store Spent Fuel 05000265/LER-2024-002, Turbine Trip and Automatic Scram Due to Digital EHC Power Supply Intermittent Failure2024-07-22022 July 2024 Turbine Trip and Automatic Scram Due to Digital EHC Power Supply Intermittent Failure 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 SVP-24-041, Regulatory Commitment Change Summary Report2024-07-0505 July 2024 Regulatory Commitment Change Summary Report SVP-24-043, Registration of Use of Casks to Store Spent Fuel2024-07-0505 July 2024 Registration of Use of Casks to Store Spent Fuel ML24162A0982024-07-0303 July 2024 – Issuance of Amendment Nos. 301 and 297 Adoption of 10 CFR 50.69 Risk Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors SVP-24-040, Registration of Use of Casks to Store Spent Fuel2024-06-25025 June 2024 Registration of Use of Casks to Store Spent Fuel 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 SVP-24-039, Ile Post Exam Package Letter2024-06-12012 June 2024 Ile Post Exam Package Letter RS-24-053, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed2024-06-0606 June 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed ML24110A0492024-05-28028 May 2024 Audit Report Related to the TSTF-505 and 10 CFR 50.59 Amendments ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 ML24142A3352024-05-21021 May 2024 Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes ML24141A2102024-05-20020 May 2024 Operator Licensing Examination Approval - Quad Cities Nuclear Power Station, May 2024 RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report IR 05000254/20240012024-05-14014 May 2024 Integrated Inspection Report Nos. 05000254/2024001 and 05000265/2024001 05000265/LER-2024-001, Automatic Actuation of Reactor Protection System During Scram Discharge Volume Leak Rate Testing2024-05-10010 May 2024 Automatic Actuation of Reactor Protection System During Scram Discharge Volume Leak Rate Testing SVP-24-034, Annual Radiological Environmental Operating Report2024-05-10010 May 2024 Annual Radiological Environmental Operating Report RS-24-042, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion2024-05-10010 May 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion RS-24-046, 10 CFR 50.46 Annual Report2024-05-0606 May 2024 10 CFR 50.46 Annual Report ML24109A0662024-05-0202 May 2024 – Relief Request I5R-26, Revision 0 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 SVP-24-029, Radioactive Effluent Release Report for 20232024-04-26026 April 2024 Radioactive Effluent Release Report for 2023 SVP-24-028, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2024-04-26026 April 2024 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report ML24114A1712024-04-23023 April 2024 State of Illinois (IEMA-OHS) Comment Quad Cities HI-STORM Exemption Environmental Assessment SVP-24-024, Corrected Radioactive Effluent Release Report for 20222024-04-0505 April 2024 Corrected Radioactive Effluent Release Report for 2022 RS-24-032, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion2024-04-0505 April 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion IR 05000254/20245012024-04-0505 April 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000254/2024501 and 05000265/2024501 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 2024-09-04
[Table view] |
Text
ber 12, 2008
SUBJECT:
QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION 05000254/2008-008; 05000265/2008-008
Dear Mr. Pardee:
On August 8, 2008, the U. S. Nuclear Regulatory Commission (NRC) completed a routine biennial PI&R inspection at your Quad Cities Nuclear Power Station, Units 1 and 2. The enclosed report documents the inspection findings, which were discussed on August 8 with Mr. Tulon 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 inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
Based on the results of this inspection, no findings of significance were identified. The team concluded that problems were properly identified, evaluated, and resolved within the corrective action program (CAP). Assessments, the use of operating experience, and monitoring of the safety conscious work environment were also adequate. There were some minor issues identified with CAP implementation such that continued attention to the program is appropriate.
Corrective actions for certain adverse trends were not initially effective. Therefore, your staff should be attentive to the significance and difficulty certain issues represent so that the corrective actions are more appropriately aggressive.
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its enclosure will be made available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Mark A. Ring, Chief Branch 1 Division of Reactor Projects Docket Nos. 50-254; 50-265 License Nos. DPR-29; DPR-30 Enclosure: Inspection Report 05000254/2008-008; 05000265/2008-008 w/Attachment: Supplemental Information cc w/encl: Site Vice President - Quad Cities Nuclear Power Station Plant Manager - Quad Cities Nuclear Power Station Regulatory Assurance Manager -
Quad Cities Nuclear Power Station Chief Operating Officer and Senior Vice President Senior Vice President - Midwest Operations Senior Vice President - Operations Support Vice President - Licensing and Regulatory Affairs Director Licensing - Licensing and Regulatory Affairs Manager Licensing - Clinton, Dresden and Quad Cities Vice President - Law and Regulatory Affairs D. Tubbs, Manager of Nuclear Associate General Counsel Document Control Desk - Licensing Assistant Attorney General J. Klinger, State Liaison Officer, Illinois Emergency Management Agency M. Rasmusson, State Liaison Officer, State of Iowa Chairman, Illinois Commerce Commission Chief Radiological Emergency Preparedness Section, Dept. Of Homeland Security
SUMMARY OF FINDINGS
IR 05000254/2008-008; 05000265/2008-008; 07/21/2008 - 08/08/2008; Quad Cities Nuclear
Power Station, Units 1 & 2; routine biennial problem identification and resolution inspection (PI&R).
This inspection was performed by three regional inspectors and the Quad Cities 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.
Problem Identification and Resolution On the basis of the sample selected for review, the team concluded that implementation of the CAP was generally good. The licensee had a low threshold for identifying problems and entering them in the CAP. Items entered into the CAP were screened and prioritized in a timely manner using established criteria; were properly evaluated commensurate with their safety significance; and corrective actions were generally implemented in a timely manner, commensurate with the safety significance. The team noted that the licensee reviewed operating experience for applicability to station activities. Audits and self-assessments were determined to be performed at an appropriate level to identify deficiencies. On the basis of licensee self-assessments and interviews conducted during the inspection, workers at the site expressed freedom to raise safety concerns. The team observed that some significant adverse trends in human performance and equipment clearances and tagging were not initially identified and aggressively addressed for effective results. Subsequent efforts were more effective.
NRC-Identified
and Self-Revealed Findings No violations of significance were identified.
Licensee-Identified Violations
None.
REPORT DETAILS
OTHER ACTIVITIES
4OA2 Problem Identification and Resolution
Completion of sections
.1 through .4 constitutes one biennial sample of problem
identification and resolution as defined in Inspection Procedure 71152.
.1 Assessment of the CAP Effectiveness
a. Inspection Scope
The inspectors reviewed the licensees Corrective Action (CA) program implementing procedures and attended CA program meetings to assess the implementation of the CA program by site personnel.
The inspectors reviewed risk and safety significant issues in the licensees CA program since the last NRC Problem Identification and Resolution (PI&R) inspection in December 2006. The selection of issues ensured an adequate review of issues across NRC cornerstones. The inspectors used issues identified through NRC generic communications, department self-assessment, licensee audits, operating experience reports, and NRC documented findings as sources to select issues. Additionally, the inspectors reviewed issue reports generated as a result of facility personnels performance in daily plant activities. In addition, the inspectors reviewed Issue Reports (IRs) and a selection of completed investigations from the licensees various investigation methods, which included root cause, apparent cause, equipment apparent cause, and common cause investigations.
A five year review of the residual heat removal service water system was undertaken to assess the licensee staffs efforts in monitoring for system degradation due to aging aspects. The inspectors also performed partial system walkdowns of emergency AC and DC electrical systems.
During the reviews, the inspectors determined whether the licensee staffs actions were in compliance with the facilitys corrective action program and 10 CFR Part 50, Appendix B requirements. Specifically, the inspectors determined if licensee personnel were identifying plant issues at the proper threshold, entering the plant issues into the stations CA program in a timely manner, and assigning the appropriate prioritization for resolution of the issues. The inspectors also determined whether the licensee staff assigned the appropriate investigation method to ensure the proper determination of root, apparent, and contributing causes. The inspectors also evaluated the timeliness and effectiveness of corrective actions for selected issue reports, completed investigations, and NRC findings, including non-cited violations.
b. Assessment
- (1) Effectiveness of Problem Identification Overall, based on the number of IRs generated by all the plant departments, plant procedures that established a low threshold for reporting, and the types of issues in the program, the team concluded that the licensee was adequately identifying issues in the CAP. However, there were some minor issues not documented and several significant trends that were not identified in the program. Degradation of a safe shutdown makeup pump, a diesel fire pump oil leak leading to smoking insulation, and the adverse trend leading to a substantive cross-cutting issue by the NRC were issues not identified appropriately. In addition, during the inspection, the team identified that the failure of an emergency preparedness (EP) siren was not documented in the site CAP. This occurred because corporate EP staff handles siren repairs, but it prevented site staff, particularly operations staff, from being aware of a site equipment deficiency. The issue was minor in this case and an IR was initiated identifying the problem of coordination between organizations.
Findings No findings of significance were identified.
- (2) Effectiveness of Prioritization and Evaluation of Issues The team concluded that issue resolutions, established and monitored through the ownership review committee and the management review committee, were correctly assigned significance and priority in accordance with station procedures. While evaluations were generally adequate, there were three non-cited violations identified over the two year inspection period where evaluations were lacking in knowledge or thoroughness. A leak in the standby liquid control tank was not correctly evaluated for design code requirements, a risk evaluation improperly took credit for manual operation of the reactor core isolation cooling system, and pump breaker failures were inadequately evaluated. These issues were addressed through the CAP when they were identified.
Findings No findings of significance were identified.
- (3) Effectiveness of Corrective Actions Although corrective actions reviewed by the team were effective in most cases, several examples where results were less than desirable were also observed. For example, the quality of containment closeout inspections was a repeat issue identified by the resident inspectors. A packing leak from an RHRSW valve onto an RHR pump motor was inadequately addressed, and resulted in wetting the motor twice. The licensees response to two significant trends was also lacking. The NRC identified an adverse trend in human performance and an adverse trend in clearance and tagging of equipment were not recognized by the licensee early on and, in both cases, the licensees response was not aggressive enough to be effective. At the time of the inspection, corrective actions were showing positive results.
Findings No findings of significance were identified.
.2 Assessment of the Use of Operating Experience (OE)
a. Inspection Scope
The inspectors reviewed the implementation of the OE program. Specifically, the inspectors reviewed implementing operating experience program procedures, attended CA program meetings to observe the use of OE information, completed evaluations of OE issues and events, and selected monthly assessments of the OE composite performance indicators. The inspectors review was to determine whether the licensee was effectively integrating OE experience into the performance of daily activities, whether evaluations of issues were proper and conducted by qualified personnel, whether the licensees program was sufficient to prevent future occurrences of previous industry events, and whether the licensee effectively used the information in developing departmental assessments and facility audits. The inspectors also assessed if corrective actions, as a result of OE experience, were identified and effectively and timely implemented.
b. Assessment The team observed that the licensee was effectively receiving and processing operating experience reports from all sources. Operating experience was being incorporated into pre-job briefings and an initiative was underway to update and improve the way operating experience was put into work packages.
Findings No findings of significance were identified.
.3 Assessment of Self-Assessments and Audits
a. Inspection Scope
The inspectors assessed the licensee staffs ability to identify and enter issues into the CA program, prioritize and evaluate issues, and implement effective corrective actions, through efforts from departmental assessments and audits.
b. Assessment The programs for self-assessments and audits were scheduled and included a broad cross section of performance areas. Procedures for performing assessments were in place and implemented providing guidance and consistency. For the audits and assessments reviewed, observations were documented and for deficiencies that were identified, issue reports were written and corrective actions taken to address them.
Overall, self-assessment was adequately performed.
Findings No findings of significance were identified.
.4 Assessment of Safety Conscious Work Environment
a. Inspection Scope
The inspectors assessed the licensees safety conscious work environment through reviews of the facilitys employee concerns program (ECP) implementing procedures, discussions with coordinators of the employee concern program, interviews with personnel from various departments, and reviews of issue reports. The inspectors also reviewed the results from a Safety Culture Survey performed in 2007.
b. Assessment The licensee had developed an anonymous survey for plant staff. Results for 2007 indicated no significant areas of weakness in a safety conscious work environment.
Inspectors noted that the survey was returned by only approximately 45 percent of the staff and did not include contractors with a long term site presence or contract security staff. Interviews by the team and the team review of the ECP program also concluded that the licensee staff was willing to raise safety concerns. The licensee has added management tools for monitoring the worker attitudes with procedures for allegations and an Employees Issues Advisory Committee.
c. Findings
No findings of significance were identified.
4OA6 Management Meetings
Exit Meeting Summary
On August 8, 2008, the inspectors presented the inspection results to Mr. Tulon, and other members of the licensee staff. The licensee acknowledged the issues presented.
The inspectors confirmed that none of the potential report input discussed was considered proprietary.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee
Alguire, C. Engineering
Beck, W. Regulatory Affairs Manager
Cain, T. Nuclear Oversight
Colgan, J. Chemistry
Craddic, D. Maintenance Director
Darin, S. Engineering
Kronich, C. Operations/SOS
Morris, J. Corrective Action Program Manager
Peterson, T. Regulatory Assurance
Rice, M. Engineering
Scott, T. Online Work Control Manager
Tulon, T. Site Vice President
Wagner, M. Regulatory Assurance
Williams, A Radiation Protection
Illinois Emergency Management Agency (IEMA)
C. Mathews
Nuclear Regulatory Commission
B. Cushman Reactor Engineer
LIST OF ITEMS
OPENED, CLOSED AND DISCUSSED
None Attachment
LIST OF DOCUMENTS REVIEWED