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Category:Inspection Report
MONTHYEARIR 05000387/20230042024-02-0707 February 2024 Integrated Inspection Report 05000387/2023004 and 05000388/2023004 IR 05000387/20230102023-12-11011 December 2023 Fire Protection Team Inspection Report 05000387/2023010 and 05000388/2023010 IR 05000387/20230032023-11-0303 November 2023 Integrated Inspection Report 05000387/2023003 and 05000388/2023003 IR 05000387/20233012023-09-20020 September 2023 Initial Operator Licensing Examination Report 05000387/2023301 and 05000388/2023301 IR 05000387/20230052023-08-31031 August 2023 Updated Inspection Plan for Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2023005 and 05000388/2023005) IR 05000387/20230022023-08-0101 August 2023 Integrated Inspection Report 05000387/2023002 and 05000388/2023002 IR 05000387/20234012023-06-0707 June 2023 Security Baseline Inspection Report 05000387/2023401 and 05000388/2023401 IR 05000387/20230012023-05-12012 May 2023 Integrated Inspection Report 05000387/2023001 and 05000388/2023001 IR 05000387/20220062023-03-0101 March 2023 Annual Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2 (Reports 05000387/2022006 and 05000388/2022006) IR 05000387/20220042023-02-0808 February 2023 Integrated Inspection Report 05000387/2022004 and 05000388/2022004 IR 07200028/20220012022-12-15015 December 2022 Independent Spent Fuel Storage Installation (ISFSI) - NRC Inspection Report No. 07200028/2022001 IR 05000387/20224032022-11-29029 November 2022 Security Baseline Inspection Report 05000387/2022403 and 05000388/2022403 IR 05000387/20225012022-11-28028 November 2022 Emergency Preparedness Biennial Exercise Inspection Report 05000387/2022501 and 05000388/2022501 IR 05000387/20224042022-11-0909 November 2022 Cyber Security Inspection Report 05000387/2022404 and 05000388/2022404 (Cover Letter Only) IR 05000387/20220032022-11-0808 November 2022 Integrated Inspection Report 05000387/2022003 and 05000388/2022003 IR 05000387/20220132022-09-28028 September 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000387/2022013 and 05000388/2022013 IR 05000387/20220052022-08-31031 August 2022 Updated Inspection Plan for Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2022005 and 05000388/2022005) IR 05000387/20220102022-08-11011 August 2022 Biennial Problem Identification and Resolution Inspection Report 05000387/2022010 and 05000388/2022010 IR 05000387/20224012022-08-11011 August 2022 Material Control and Accounting Program Inspection Report 05000387/2022401 and 05000388/2022401 (Cover Letter Only) IR 05000387/20220022022-08-0404 August 2022 Integrated Inspection Report 05000387/2022002 and 05000388/2022002 IR 05000387/20220012022-05-0909 May 2022 Integrated Inspection Report 05000387/2022001 and 05000388/2022001 IR 05000387/20220112022-03-0707 March 2022 Post-Approval Site Inspection for License Renewal - Phase 2 Inspection Report 05000387/2022011 IR 05000387/20210062022-03-0202 March 2022 Annual Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2 (Reports 05000387/2021006 and 05000388/2021006) IR 05000387/20224022022-02-16016 February 2022 Security Baseline Inspection Report 05000387/2022402 and 05000388/2022402 IR 05000387/20214032022-02-11011 February 2022 Cyber Security Problem Identification and Resolution Inspection Report 05000387/2021403 and 05000388/2021403 (Cover Letter Only) IR 05000387/20210042022-02-11011 February 2022 Integrated Inspection Report 05000387/2021004 and 05000388/2021004 IR 05000387/20210102021-12-13013 December 2021 Design Basis Assurance Inspection (Programs) Inspection Report 05000387/2021010 and 05000388/2021010 IR 05000387/20210112021-11-0404 November 2021 Temporary Instruction 2515/194 Inspection Report 05000387/2021011 and 05000388/2021011 IR 05000387/20210032021-11-0303 November 2021 Integrated Inspection Report 05000387/2021003 and 05000388/2021003 IR 05000387/20214012021-10-25025 October 2021 Security Baseline Inspection Report 05000387/2021401 and 05000388/2021401 IR 05000387/20214022021-09-23023 September 2021 Security Baseline Inspection Report 05000387/2021402 and 05000388/2021402 IR 05000387/20213012021-09-17017 September 2021 Initial Operator Licensing Examination Report 05000387/2021301 and 05000388/2021301 IR 05000387/20210052021-09-0101 September 2021 Updated Inspection Plan for the Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2021005 and 05000388/2021005) ML21224A2402021-08-24024 August 2021 Security Baseline Inspection Report Cover Letter 2021 FOF IR 05000387/20210022021-08-0404 August 2021 Integrated Inspection Report 05000387/2021002 and 05000388/2021002 IR 05000387/20210012021-05-0505 May 2021 Integrated Inspection Report 05000387/2021001 and 05000388/2021001 IR 05000388/20210122021-03-0404 March 2021 EA-20-131: Susquehanna Steam Electric Station, Unit 2 - NRC Investigation Report No. 1-2020-001 and NRC Inspection Report No. 05000388/2021012 IR 05000387/20200062021-03-0303 March 2021 Annual Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2 (Reports 05000387/2020006 and 05000388/2020006) IR 05000387/20204032021-02-10010 February 2021 Cyber Security Problem Identification and Resolution Inspection Report 05000387/2020403 and 05000388/2020403 (Cover Letter Only) IR 05000387/20200042021-02-0808 February 2021 Integrated Inspection Report 05000387/2020004 and 05000388/2020004 IR 05000387/20205012020-11-18018 November 2020 Emergency Preparedness Biennial Exercise Inspection Report 05000387/2020501 and 05000388/2020501 IR 05000387/20200032020-11-0505 November 2020 Integrated Inspection Report 05000387/2020003 and 05000388/2020003 IR 05000387/20200122020-10-27027 October 2020 Triennial Fire Protection Inspection Report 05000387/2020012 and 05000388/2020012 IR 05000387/20200052020-08-31031 August 2020 Updated Inspection Plan (Inspection Reports 05000387/2020005 and 05000388/2020005) IR 05000387/20200112020-08-18018 August 2020 Biennial Problem Identification and Resolution Inspection Report 05000387/2020011 and 05000388/2020011 IR 05000387/20200022020-08-11011 August 2020 Integrated Inspection Report 05000387/2020002 and 05000388/2020002 IR 05000387/20204012020-07-0202 July 2020 Security Baseline Inspection Report 05000387/2020401 and 05000388/2020401 IR 05000387/20200012020-05-0505 May 2020 Integrated Inspection Report 05000387/2020001 and 05000388/2020001 IR 05000387/20190062020-03-0303 March 2020 Annual Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2019006 and 05000388/2019006) IR 05000387/20200102020-02-21021 February 2020 Temporary Instruction 2515/194 Inspection Report 05000387/2020010 and 05000388/2020010 2024-02-07
[Table view] Category:Letter
MONTHYEARIR 05000387/20230042024-02-0707 February 2024 Integrated Inspection Report 05000387/2023004 and 05000388/2023004 PLA-8096, Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval2024-01-0404 January 2024 Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval PLA-8077, Emergency Plan Revision 67 (PLA-8077)2023-12-27027 December 2023 Emergency Plan Revision 67 (PLA-8077) IR 05000387/20230102023-12-11011 December 2023 Fire Protection Team Inspection Report 05000387/2023010 and 05000388/2023010 PLA-8089, Submittal of Revision to Inservice Testing Program Plan2023-12-0505 December 2023 Submittal of Revision to Inservice Testing Program Plan PLA-8084, Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.22023-11-29029 November 2023 Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.2 ML23345A0682023-11-28028 November 2023 Technical Specification Bases, Manual PLA-8091, Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inseervice Inspection Interval (PLA-8091)2023-11-0808 November 2023 Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inseervice Inspection Interval (PLA-8091) IR 05000387/20230032023-11-0303 November 2023 Integrated Inspection Report 05000387/2023003 and 05000388/2023003 PLA-8082, Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2023-11-0202 November 2023 Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML23291A1132023-10-12012 October 2023 Submittal of Revision 71 to Updated Final Safety Analysis Report and Revision 25 to Fire Protection Review Report ML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23277A0412023-10-0505 October 2023 Notification of Commercial Grade Dedication Inspection (05000387/2024011 and 05000388/2024011) and Request for Information IR 05000387/20233012023-09-20020 September 2023 Initial Operator Licensing Examination Report 05000387/2023301 and 05000388/2023301 ML23254A0242023-09-0606 September 2023 Paragon Energy Solutions LLC, Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) IR 05000387/20230052023-08-31031 August 2023 Updated Inspection Plan for Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2023005 and 05000388/2023005) ML23228A1952023-08-21021 August 2023 Summary of August 10, 2023, Public Observation Meeting Re. Proposed Alternative PLA-8080, Proposed Relief for Valve 251130 (PLA-8080)2023-08-14014 August 2023 Proposed Relief for Valve 251130 (PLA-8080) PLA-8074, Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval2023-08-0303 August 2023 Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval IR 05000387/20230022023-08-0101 August 2023 Integrated Inspection Report 05000387/2023002 and 05000388/2023002 ML23195A1852023-07-27027 July 2023 Correction to Technical Specifications Page 3.3-73 in Amendment No. 265 PLA-8076, Unit 2 - 21st Refueling Outage Owner'S Activity Report (PLA-8076)2023-07-20020 July 2023 Unit 2 - 21st Refueling Outage Owner'S Activity Report (PLA-8076) ML23201A0152023-07-20020 July 2023 Operator Licensing Examination Approval ML23200A1012023-07-19019 July 2023 Notification of Conduct of a Fire Protection Team Inspection ML23193A0062023-07-12012 July 2023 Requalification Program Inspection PLA-8078, Submittal of Unit 2 Cycle 22 Core Operating Limits Report, Revision 1, PLA-80782023-07-0505 July 2023 Submittal of Unit 2 Cycle 22 Core Operating Limits Report, Revision 1, PLA-8078 ML23163A1012023-06-12012 June 2023 10 CFR 50.46 Annual Report (Pla 8065) PLA-8054, Proposed Amendment to Licenses NPF-14 and NPF-22: Remove Control Rod Operability Separation Criteria and Replace Reference to Banked Position Withdrawal Sequence with the Analyzed Rod Position Sequence2023-06-0808 June 2023 Proposed Amendment to Licenses NPF-14 and NPF-22: Remove Control Rod Operability Separation Criteria and Replace Reference to Banked Position Withdrawal Sequence with the Analyzed Rod Position Sequence IR 05000387/20234012023-06-0707 June 2023 Security Baseline Inspection Report 05000387/2023401 and 05000388/2023401 PLA-8073, Proposed Relief Request for the Fifth 10-Year Inservice Inspection Interval2023-06-0101 June 2023 Proposed Relief Request for the Fifth 10-Year Inservice Inspection Interval PLA-8064, Response to NRC Regulatory Issue Summary 2023-01 (PLA-8064)2023-05-17017 May 2023 Response to NRC Regulatory Issue Summary 2023-01 (PLA-8064) ML23132A3212023-05-17017 May 2023 Associated Independent Spent Fuel Storage Installation - Issuance of Amendment Nos. 285 and 269 Related to Order Approving Transfer of Licenses PLA-8067, Notification of Completion of Emergence from Bankruptcy (PLA-8067)2023-05-17017 May 2023 Notification of Completion of Emergence from Bankruptcy (PLA-8067) IR 05000387/20230012023-05-12012 May 2023 Integrated Inspection Report 05000387/2023001 and 05000388/2023001 PLA-8066, Notification of Planned Closing Date and Information Identified in March 30, 2023 Order, PLA-80662023-05-0808 May 2023 Notification of Planned Closing Date and Information Identified in March 30, 2023 Order, PLA-8066 PLA-8053, Radiation Exposure Information and Reporting System2023-04-27027 April 2023 Radiation Exposure Information and Reporting System PLA-8058, Annual Radiological Environmental Operating Report (PLA-8058)2023-04-26026 April 2023 Annual Radiological Environmental Operating Report (PLA-8058) PLA-8041, Radioactive Effluent Release Report and Offsite Dose Calculation Manual (PLA-8041)2023-04-25025 April 2023 Radioactive Effluent Release Report and Offsite Dose Calculation Manual (PLA-8041) PLA-8047, 2022 Annual Environmental Operating Report (Nonradiological), PLA-80472023-04-19019 April 2023 2022 Annual Environmental Operating Report (Nonradiological), PLA-8047 PLA-8062, Supplement to Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 252F007B, PLA-80622023-04-11011 April 2023 Supplement to Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 252F007B, PLA-8062 PLA-8061, Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 25F007B, PLA-80612023-04-10010 April 2023 Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 25F007B, PLA-8061 ML23090A2302023-03-31031 March 2023 NRC Decommissioning Funding Status Report PLA-8049 PLA-8060, Submittal of Unit 2 Cycle 22 Core Operating Limits Report (PLA-8060)2023-03-30030 March 2023 Submittal of Unit 2 Cycle 22 Core Operating Limits Report (PLA-8060) ML23095A0572023-03-29029 March 2023 NRC Decommissioning Funding Status Report December 31, 2022 PLA-8057, Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments- Supplemental Information, PLA-80572023-03-15015 March 2023 Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments- Supplemental Information, PLA-8057 ML23065A1962023-03-0202 March 2023 EN 56387 Paragon - Part 21 Report Re Defect Identified in Automatic Transfer Switch Pn: NLI-ATS480A400X1 IR 05000387/20220062023-03-0101 March 2023 Annual Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2 (Reports 05000387/2022006 and 05000388/2022006) PLA-8052, (Sses), Proof of Financial Protection and Guarantee of Payment of Deferred Premiums2023-02-13013 February 2023 (Sses), Proof of Financial Protection and Guarantee of Payment of Deferred Premiums IR 05000387/20220042023-02-0808 February 2023 Integrated Inspection Report 05000387/2022004 and 05000388/2022004 ML23010A0882023-01-15015 January 2023 Summary of Regulatory Audit in Support of License Amendment Request to Revise Control Rod Technical Specifications 2024-02-07
[Table view] |
Text
ust 4, 2005
SUBJECT:
SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 -
SAFETY SYSTEM DESIGN AND PERFORMANCE CAPABILITY INSPECTION REPORT NOS. 05000387/2005007 AND 05000388/2005007
Dear Mr. McKinney:
On June 24, 2005, the U.S. Nuclear Regulatory Commission (NRC) completed a Safety System Design and Performance Capability team inspection at the Susquehanna Steam Electric Station. The enclosed inspection report documents the inspection results which were discussed on June 24, 2005, with you and members of your staff.
The inspection examined activities conducted under your license related to safety and compliance with the Commissions rules and regulations, and with the conditions of your license. The inspection involved field walkdowns, examination of selected procedures, calculations and records, and interviews with station 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/
Lawrence T. Doerflein, Chief Engineering Branch 2 Division of Reactor Safety Docket Nos. 50-387,05-388 License Nos. NPF-14, NPF-22 Enclosure: Inspection Report Nos. 05000387/2005007 and 05000388/2005007
Mr. Britt
SUMMARY OF FINDINGS
IR 05000387/2005007, 05000388/2005007; June 6-10 and June 20-24, 2005; Susquehanna
Steam Electric Station Units 1 and 2; Engineering Team Inspection.
The inspection was conducted by five regional inspectors and an NRC contractor. No findings of significance were identified during the inspection. The NRC's 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 and Self-Revealing Findings
None
Licensee-Identified Violations
None ii
REPORT DETAILS
REACTOR SAFETY
Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity
1R21 Safety System Design and Performance Capability (IP 71111.21)
a. Inspection Scope
In selecting systems and components for review, the team focused on risk significance and considered the risk information contained in the NRCs Risk Informed Inspection Notebook for Susquehanna Steam Electric Station (SSES) Units 1 & 2. Using risk insights, the team selected the automatic depressurization system (ADS) and the high pressure coolant injection (HPCI) system and their respective components for review.
The review of the automatic depressurization system included the six automatically controlled safety-relief valves installed on the main steam lines inside primary containment. The team reviewed the automatic function, by action of an electric-pneumatic control system, of these dual purpose valves. The relief by normal mechanical action is intended to prevent over pressurization of the reactor vessel. The depressurization by automatic action of the control system was reviewed because it reduces reactor vessel pressure during small and medium size Loss-of-Coolant Accident (LOCA) scenarios in which the high pressure coolant injection system is not available.
The team specifically reviewed the design capability of major risk significant components of the automatic depressurization system including the ADS valves, ADS solenoids and the ADS nitrogen supply system. This review was performed to determine if the design basis was in conformance with the licensing commitments, regulatory requirements and design output documents. Operational procedures were reviewed to determine if the procedure could be implemented given the current system configuration. These procedures were compared against lesson plans, training, and simulator use to assure the plant configuration matched to training configuration.
Regarding the high coolant pressure injection system, the team focused on the steam turbine driven constant-flow pump assembly, associated system piping, valves, controls, and instrumentation located in the reactor building. The team inspected the HPCI suction piping from both the condensate storage tank and the suppression pool. The team also reviewed the HPCI injection line into the reactor feedwater line. In addition, the team inspected the HPCI system controls, such as the remote controls for valve and turbine operation.
Since the HPCI system is provided to ensure that the reactor core is adequately cooled in the event of a small break in the reactor coolant pressure boundary which does not result in rapid depressurization of the reactor vessel, a number of high risk sequences, such as station blackout, were considered during the inspection. In addition, since the HPCI system is designed to pump water into the reactor vessel for a wide range of pressures, the team evaluated HPCI performance capability for various backpressures.
The team reviewed the design and operation of the ADS and HPCI system. Specifically, the team reviewed the design basis documents, the Technical Specifications (TS), the Updated Final Safety Analysis Report (USFAR), and the ADS valve vendor manual.
The design output documents reviewed included piping and instrument drawings. The team performed this review to determine whether the system and component functional requirements during normal, abnormal and accident conditions were met and to ensure consistency with various design documents, design specifications and control diagrams.
For both systems, the team reviewed selected mechanical calculations and analyses to verify the appropriate input assumptions were used and that the assumptions applied to the current system and plant configuration. The team verified that adequate engineering methods were utilized and the technical bases supported the conclusions.
The team also selected some design and electrical calculations, and performed independent calculations to evaluate their adequacy.
The team evaluated system environmental conditions, including the effect of various design basis accidents, to verify plant conditions were bounded by the equipment qualification assumptions. A sample of preventive maintenance activities were reviewed to verify that maintenance was performed as scheduled and that environmental qualification was being maintained. The team evaluated a sample of surveillance and pre-operational test results to verify system capability. In addition, the team chose the intermittent steam-trap alarm to focus on the two-phase flow and flow accelerated corrosion in the steam-trap drain.
The team reviewed the control wiring diagrams of ADS and HPCI to verify, for example, that pump operation, including automatic initiation, conforms with the system operation described in the updated final safety analysis report. The review included control of valves critical to the correct operation of the systems. The team reviewed both alternating and direct current power distribution to ensure that a single failure of an electrical component or source did not impair the ability of the systems to perform their safety function. The review confirmed that sufficient instrumentation was provided to initiate automatic functions and to monitor the operation of the systems during a loss-of-offsite power (LOOP).
The team reviewed the Class 1E battery load calculation to verify that required loads had been correctly identified and to ensure that the batteries were capable of meeting the load requirements under worst-case duty cycles. Since station black out is a risk significant accident scenario for both ADS and HPCI, the calculations were reviewed specifically against the Susquehanna coping scheme. The team also reviewed the direct current voltage drop calculation and sampled recent battery performance tests to verify that adequate voltage was provided to the safety-related loads during worst-case loading. The team reviewed environmental qualification of motors and valves to verify that the motors and valves would be capable of performing their required safety function.
b. Findings
No findings of significance were identified.
4OA2 Identification and Resolution of Problems
a. Inspection Scope
The inspectors reviewed a sample of corrective action reports, as identified in the Documents Reviewed section, to verify that Susquehanna Steam Station personnel were identifying issues at an appropriate threshold, entering them in the corrective action program, and taking appropriate corrective actions. Also, the inspectors evaluated corrective actions to confirm that repairs and/or modifications to components had no adverse impact on the system design basis.
b. Findings
No findings of significance were identified.
4OA5 Other
(Closed) URI 05000387;05000388/2001004-03; Inclusion of SLC Design Modifications for ATWS Rule in the Design Bases of the Plant During the March 2001 safety system design and performance capability team inspection, NRC staff identified that the Standby Liquid Control (SLC) system would not obtain the assumed flow-rate specified under the Anticipated Transient Without Scram (ATWS) Rule as defined in 10 CFR50.62. The specific postulated scenario of concern was an ATWS with Loss-of-Offsite Power (LOOP) event. Non-cited violation 05000387;05000388/2001004-02 was subsequently issued. PPL took corrective actions by implementing physical hardware changes to correct the nonconforming condition. The NRC staff also opened an Unresolved Item (URI) in order to later review PPLs conclusion regarding the functional requirement of the SLC system with respect to the ATWS rule, the applicability of TS section 3.1.7 to the ATWS Rule in this case, and PPLs decision not to report the failure to meet the requirements of the ATWS rule.
The inspectors reviewed PPLs corrective actions responding to the URI. The team reviewed condition report (CR) numbers 316309, 316780, 321640, and 548025. The team found PPLs evaluation, including their completed and proposed corrective actions to be acceptable. These included licensing bases changes, enhancements to training regarding the interpretation of the ATWS requirements with respect to design bases, and hardware and procedure changes which fully addressed the concerns of the issue.
Based on the review of the above, the inspectors considered this unresolved item closed. No violations of NRC requirements were identified.
4OA6 Meetings, including Exit
On June 24, 2005, at the completion of the inspection, the team presented the inspection results to Mr. McKinney and other members of his staff. The team verified that the inspection report does not contain proprietary information. Any proprietary information that was provided or examined during the inspection was returned to the licensee upon completion of the inspection.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee Personnel
- M. Adelizzi, Senior Engineer - Plant Analysis
- P. Brady, Supervisor - Electrical and I&C Design
- D. Brophy, Senior Engineer - Nuclear Regulatory Affairs
- R. Centenaro, Mechanical Design Engineering
- D. Gladey, Senior Electrical Engineer
- S. Kartchner, Senior Engineer - Station Engineering / ADS System Engineer
- J. Krais, Manager - Nuclear Design Engineering
- B. McKinney, Senior Vice President and Chief Nuclear Officer
- E. Miller, Senior Engineer - Nuclear Regulatory Affairs
- J. Petrilla, Unit Supervisor - Operations
- J. Vandenberg, Senior Engineer - Station Engineering / HPCI System Engineer
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Opened
None
Closed
- 05000387;
- 05000388/200104-03 URI Inclusion of SLC Design Modifications for ATWS Rule in the Design Bases of the Plant
DOCUMENTS REVIEWED