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| {{#Wiki_filter:June 2, 2006Duke Energy Corporation ATTN:Mr. D. M. JamilSite Vice President Catawba Site4800 Concord Road York, SC 29745-9635SUBJECT:CATAWBA NUCLEAR STATION - NRC INSPECTION REPORT 05000413/2006008 AND 05000414/2006008 | | {{#Wiki_filter:une 2, 2006 |
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| | ==SUBJECT:== |
| | CATAWBA NUCLEAR STATION - NRC INSPECTION REPORT 05000413/2006008 AND 05000414/2006008 |
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| ==Dear Mr. Jamil:== | | ==Dear Mr. Jamil:== |
| On May 19, 2006, the US Nuclear Regulatory Commission (NRC) completed an inspection atyour Catawba Nuclear Station Units 1 and 2. The enclosed inspection report documents the inspections results, which were discussed with you, and other members of your staff.The inspection examined activities conducted under your license as they relate to safety andcompliance with the Commission's rules and regulations and with the conditions of your license. | | On May 19, 2006, the US Nuclear Regulatory Commission (NRC) completed an inspection at your Catawba Nuclear Station Units 1 and 2. The enclosed inspection report documents the inspections results, which were discussed with you, and other members of your staff. |
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| | 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. |
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| | The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. |
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| 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.
| | Based on the results of this inspection no findings of significance were identified. |
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| In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and itsenclosure will be available electronically for public inspection in the NRC Public DocumentRoom or from the Publicly Available Records (PARS) component of NRC's 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).Should you have any questions concerning this letter, please contact us. | | 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 NRC's 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). |
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| | Should you have any questions concerning this letter, please contact us. |
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| Sincerely, | | Sincerely, |
| /RA/ | | /RA/ |
| Brian R. Bonser, ChiefPlant Support Branch 2 Division of Reactor SafetyDocket Nos. 50-413, 50-414License Nos. NPF-35, NPF-52 | | Brian R. Bonser, Chief Plant Support Branch 2 Division of Reactor Safety Docket Nos. 50-413, 50-414 License Nos. NPF-35, NPF-52 |
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| ===Enclosure:=== | | ===Enclosure:=== |
| (See page 2) | | (See page 2) |
| DEC 2Enclosure: NRC Inspection Report 05000413/2006008 and 05000414/2006008 w/Attachment: Supplemental Information
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| REGION IIDocket Nos.:50-413, 50-414 License Nos.:NPF-35, NPF-52 Report No: 05000413/2006008, 05000414/2006008 Licensee:Duke Energy Corporation Facility: Catawba Nuclear Station Location:4800 Concord RoadYork, SC 29745-9635Dates:May 15-19, 2006 Inspectors:L. Miller, Senior Emergency Preparedness Inspector (Section 1EP1,1EP4) | | DEC 2 Enclosure: NRC Inspection Report 05000413/2006008 and 05000414/2006008 w/Attachment: Supplemental Information |
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| | REGION II== |
| | Docket Nos.: 50-413, 50-414 License Nos.: NPF-35, NPF-52 Report No: 05000413/2006008, 05000414/2006008 Licensee: Duke Energy Corporation Facility: Catawba Nuclear Station Location: 4800 Concord Road York, SC 29745-9635 Dates: May 15-19, 2006 Inspectors: L. Miller, Senior Emergency Preparedness Inspector (Section 1EP1,1EP4) |
| J. Kreh, Emergency Preparedness Inspector (Section 1EP1, 4OA1) | | J. Kreh, Emergency Preparedness Inspector (Section 1EP1, 4OA1) |
| E. Guthrie, Senior Resident Inspector, (Section 1EP1)Approved by:Brian R. Bonser, ChiefPlant Support Branch 2 Division of Reactor Safety SUMMARY OF FINDINGS | | E. Guthrie, Senior Resident Inspector, (Section 1EP1) |
| | Approved by: Brian R. Bonser, Chief Plant Support Branch 2 Division of Reactor Safety Enclosure |
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| | SUMMARY OF FINDINGS IR 05000413/2006008, 05000414/2006008; 05/15-19/2006; Catawba Nuclear Station, Units 1 and 2; emergency preparedness The report covered an announced inspection by a team of two emergency preparedness inspectors and one resident inspector. 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. |
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| | A. NRC-Identified and Self-Revealing Findings Cornerstone: Emergency Preparedness None B. Licensee-Identified Violations. |
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| | None |
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| | 1. REACTOR SAFETY Cornerstone: Emergency Preparedness 1EP1 Exercise Evaluation a. Inspection Scope Prior to the inspection activity, the inspectors conducted an in-office review of the exercise objectives and scenario submitted to the NRC to determine if the exercise would test major elements of the emergency plan as required by 10 CFR 50.47(b)(14). |
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| | This inspection activity represents one sample on a biennial cycle. |
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| | The onsite inspection consisted of the following review and assessment: |
| | * The adequacy of the licensees performance in the biennial exercise conducted on May 16, 2006, was reviewed and assessed regarding the implementation of the Risk Significant Planning Standards (RSPSs) in 10 CFR 50.47 (b) (4), (5), (9), and (10), |
| | which are emergency classification, offsite notification, radiological assessment, and protective action recommendations, respectively. |
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| | * The overall adequacy of the licensees emergency response facilities with regard to NUREG-0696, Functional Criteria for Emergency Response Facilities and Emergency Plan commitments. The facilities assessed were the Control Room simulator, Technical Support Center (TSC), Operational Support Center (OSC) and Emergency Operations Facility (EOF). |
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| | * Other performance areas besides the RSPS, such as the emergency response organizations (ERO) recognition of abnormal plant conditions, command and control, intra- and inter-facility communications, prioritization of mitigation activities, utilization of repair and field monitoring teams, interface with offsite agencies, and the overall implementation of the emergency plan and its implementing procedures. |
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| | * Past performance issues from NRC inspection reports and Federal Emergency Management Agency (FEMA) exercise reports to determine effectiveness of corrective actions as demonstrated during this exercise to ensure compliance with 10 CFR 50.47(b)(14). |
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| | * The post-exercise critique conducted May 19, 2006, to evaluate the licensees self-assessment of its ERO performance during the exercise and to ensure compliance with 10 CFR 50 Appendix E.IV.F.2.g The inspectors reviewed various documents which are listed in the Attachment to this report. |
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| | b. Findings No findings of significance were identified. |
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| | 1EP4 Emergency Action Level (EAL) and Emergency Plan Changes a. Inspection Scope The inspectors review of revisions to the emergency plan, implementing procedures and EAL changes was performed for determining that changes had not decreased the effectiveness of the plan. The inspectors also evaluated the associated 10 CFR 50.54(q) reviews associated with non-administrative emergency plan, implementing procedures and EAL changes. The Catawba Nuclear Station Emergency Plan, revision 06-01 was reviewed. |
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| | The inspection was conducted in accordance with NRC Inspection Procedure 71114, Attachment 04, Emergency Action Level and Emergency Plan Changes. The applicable PS, 10 CFR 50.47(b)(4) and its related 10 CFR 50, Appendix E requirements were used as reference criteria. The criteria contained in NUREG-0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants, Revision 1, Regulatory Guide 1.101 were also used as references. This inspection activity represents one sample on an annual basis. |
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| | The inspectors reviewed various documents which are listed in the Attachment to this report. |
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| | b. Findings No findings of significance were identified. |
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| | 4. OTHER ACTIVITIES 4OA1 Performance Indicator (PI) Verification a. Inspection Scope The inspectors reviewed the licensees procedure for developing the data for the Emergency Preparedness PIs which are: (1) DEP; (2) ERO Drill Participation; and (3) |
| | Alert and Notification System (ANS) Reliability. The inspectors examined data reported to the NRC for the period January 1, 2005 to March 31, 2006. Procedural guidance for reporting PI information and records used by the licensee to identify potential PI occurrences were also reviewed. The inspectors verified the accuracy of the PI for ERO drill and exercise performance through review of a sample of drill and event records. |
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| | The inspectors reviewed selected training records to verify the accuracy of the PI for ERO drill participation for personnel assigned to key positions in the ERO. The inspectors verified the accuracy of the PI for alert and notification system reliability through review of a sample of the licensees records of periodic system tests. |
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| | The inspection was conducted in accordance with NRC Inspection Procedure 71151, Performance Indicator Verification. The applicable planning standard, 10 CFR 50.9 and Nuclear Energy Institute (NEI) 99-02, Revision 3, Regulatory Assessment Performance Indicator Guidelines, were used as reference criteria. This inspection activity represents three samples on an annual basis. |
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| | The inspectors reviewed various documents which are listed in the Attachment to this report. |
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| | b. Findings No findings of significance were identified. |
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| | 4OA6 Meetings, including Exit On May 19, 2006, the team lead for the Emergency Preparedness Inspection presented the inspection results to Mr. D. Jamil, Catawba Site Vice President, and other members of his staff. The inspectors confirmed that proprietary information was not provided or taken during the inspection. |
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| IR 05000413/2006008, 05000414/2006008; 05/15-19/2006; Catawba Nuclear Station, Units 1and 2; emergency preparednessThe report covered an announced inspection by a team of two emergency preparednessinspectors and one resident inspector. The NRC's program for overseeing the safe operationof commercial nuclear power reactors is described in NUREG-1649, "Reactor OversightProcess," Revision 3, dated July 2000.A.NRC-Identified and Self-Revealing FindingsCornerstone: Emergency PreparednessNoneB.Licensee-Identified Violations.
| | ATTACHMENT: SUPPLEMENTAL INFORMATION |
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| None 31.REACTOR SAFETYCornerstone: Emergency Preparedness1EP1Exercise Evaluation a.Inspection ScopePrior to the inspection activity, the inspectors conducted an in-office review of theexercise objectives and scenario submitted to the NRC to determine if the exercisewould test major elements of the emergency plan as required by 10 CFR 50.47(b)(14).
| | SUPPLEMENTAL INFORMATION KEY POINTS OF CONTACT Licensee personnel D. Jamil, Catawba Site Vice President J. Pitesa, Station Manager M. Patrick, Work Control Department Superintendent E. Beadle, Manager - Emergency Planning R. Repko, Engineering Manager G. Strickland, Regulatory Compliance (Engineer) |
| | LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED Opened None Closed None Discussed None A-1 Attachment |
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| This inspection activity represents one sample on a biennial cycle.The onsite inspection consisted of the following review and assessment:
| | LIST OF DOCUMENTS REVIEWED Section 1EP1: Exercise Evaluation Plans and Procedures RP/0/A/5000/006B, Notifications to States and Counties from the Technical Support Center, Rev. 20 RP/0/A/5000/020, Technical Support Center (TSC) Activation Procedure, Rev. 20 RP/0/A/5000/024, OSC Activation Procedure, Rev. 15 SR/0/B/2000/003, Activation of the Emergency Operations Facility, Rev. 15 SR/0/B/2000/004, Notification to States and Counties from the Emergency Operations Facility, Rev. 9 RP/0/A/5000/001, Classification of Emergency, Rev. 017 RP/0/A/5000/002, Notification of Unusual Event, Rev. 038 RP/0/A/5000/003, Alert, Rev. 041 RP/0/A/5000/004, Site Area Emergency, 043 RP/0/A/5000/005, General Emergency, 044 RP/0/A/5000/006A, Notification to States and Counties from the Control Room, Rev. 020 RP/0/A/5000/006B, Notification to States and Counties from the Technical Support Center, Rev. 021 PT/0/B/4600/006, Emergency Exercises and Drills, Rev. 011 SR/0/B/2000/003, Activation of the Emergency Operations Facility, Rev. 016 SH/0/B/2005/001, Emergency Response Offsite Dose Projections, Rev. 004 Miscellaneous Problem Investigation Process C-06-03819, Apparent mis-classification of General Emergency during graded exercise, 5/16/06 C-06-3808, Corrective Action Items for non-risk significant items from Graded Exercise 06-2, 05/16/06 C-06-03776, Required Boron concentration for end of cycle shutdown margin appear to be overly conservative on both units, 05/16/06 C-06-03807, Corrective Action Items for risk significant items from Graded Exercise 06-2, 05/16/06 Nuclear Power Plant Emergency Notification Form (Messages 1-8) for State and local agencies Section 1EP4: Emergency Action Level (EAL) and Emergency Plan Changes Plans and Changes packages Emergency Plan, Rev. 06-01 Catawba Emergency Plan Change Package 05-01 Catawba Emergency Plan Change Package 05-02 Catawba Emergency Plan Change Package 06-01 A-2 Attachment |
| *The adequacy of the licensee's performance in the biennial exercise conducted onMay 16, 2006, was reviewed and assessed regarding the implementation of the RiskSignificant Planning Standards (RSPSs) in 10 CFR 50.47 (b) (4), (5), (9), and (10),
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| which are emergency classification, offsite notification, radiological assessment, and protective action recommendations, respectively.*The overall adequacy of the licensee's emergency response facilities with regard toNUREG-0696, "Functional Criteria for Emergency Response Facilities" andEmergency Plan commitments. The facilities assessed were the Control Room simulator, Technical Support Center (TSC), Operational Support Center (OSC) and Emergency Operations Facility (EOF).*Other performance areas besides the RSPS, such as the emergency responseorganization's (ERO) recognition of abnormal plant conditions, command and control, intra- and inter-facility communications, prioritization of mitigation activities,utilization of repair and field monitoring teams, interface with offsite agencies, andthe overall implementation of the emergency plan and its implementing procedures.*Past performance issues from NRC inspection reports and Federal EmergencyManagement Agency (FEMA) exercise reports to determine effectiveness of corrective actions as demonstrated during this exercise to ensure compliance with 10 CFR 50.47(b)(14).*The post-exercise critique conducted May 19, 2006, to evaluate the licensee's self-assessment of its ERO performance during the exercise and to ensure compliance with 10 CFR 50 Appendix E.IV.F.2.gThe inspectors reviewed various documents which are listed in the Attachment to thisreport.
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| 4 b.FindingsNo findings of significance were identified.1EP4 Emergency Action Level (EAL) and Emergency Plan Changes a.Inspection ScopeThe inspectors review of revisions to the emergency plan, implementing procedures andEAL changes was performed for determining that changes had not decreased the effectiveness of the plan. The inspectors also evaluated the associated 10 CFR 50.54(q) reviews associated with non-administrative emergency plan, implementing procedures and EAL changes. The Catawba Nuclear Station Emergency Plan, revision 06-01 was reviewed.The inspection was conducted in accordance with NRC Inspection Procedure 71114,Attachment 04, "Emergency Action Level and Emergency Plan Changes." The applicable PS, 10 CFR 50.47(b)(4) and its related 10 CFR 50, Appendix E requirements were used as reference criteria. The criteria contained in NUREG-0654, "Criteria forPreparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants," Revision 1, Regulatory Guide 1.101 were also used as references. This inspection activity represents one sample on an annual basis.The inspectors reviewed various documents which are listed in the Attachment to thisreport. b.FindingsNo findings of significance were identified.4.OTHER ACTIVITIES 4OA1Performance Indicator (PI) Verification a.Inspection ScopeThe inspectors reviewed the licensee's procedure for developing the data for theEmergency Preparedness PIs which are: (1) DEP; (2) ERO Drill Participation; and (3)Alert and Notification System (ANS) Reliability. The inspectors examined data reportedto the NRC for the period January 1, 2005 to March 31, 2006. Procedural guidance forreporting PI information and records used by the licensee to identify potential PI occurrences were also reviewed. The inspectors verified the accuracy of the PI for ERO drill and exercise performance through review of a sample of dr ill and event records. The inspectors reviewed selected training records to verify the accuracy of the PI for ERO drill participation for personnel assigned to key positions in the ERO. Theinspectors verified the accuracy of the PI for alert and notification system reliabilitythrough review of a sample of the licensee's records of periodic system tests.
| | Change Package for RP/0/A/5000/006B, Notification to States and Counties from the Technical Support Center, Rev. 020 Change Package for SR/0/B/2000/004, Notification to States and Counties from the Emergency Operations Facility, Rev. 9 Section 4OA1: Performance Indicator (PI) Verification Procedures DPND-1551.00-0001, Emergency Planning Functional Area Manual: Section 3.7, NRC Regulatory Assessment Performance Indicator Guideline - Emergency Preparedness Cornerstone, Rev. 10 Records and Data Documentation (scenario, time line, event notification forms, critique report) of ERO drills on 06/21/2005, 11/22/2005 Documentation of CRS DEP evaluations in February 2005 and February 2006 Selected training records of drill/exercise participation by ERO personnel during 2004-2005 Siren system test records for January 2005-March 2006 A-3 Attachment |
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| 5The inspection was conducted in accordance with NRC Inspection Procedure 71151,"Performance Indicator Verification." The applicable planning standard, 10 CFR 50.9 and Nuclear Energy Institute (NEI) 99-02, Revision 3, "Regulatory Assessment Performance Indicator Guidelines," were used as reference criteria. This inspection activity represents three samples on an annual basis.The inspectors reviewed various documents which are listed in the Attachment to thisreport. b.FindingsNo findings of significance were identified.4OA6Meetings, including ExitOn May 19, 2006, the team lead for the Emergency Preparedness Inspection presentedthe inspection results to Mr. D. Jamil, Catawba Site Vice President, and other members of his staff. The inspectors confirmed that proprietary information was not provided or taken during the inspection.ATTACHMENT: SUPPLEMENTAL INFORMATION A-Attachment 1 SUPPLEMENTAL INFORMATIONKEY POINTS OF CONTACTLicensee personnelD. Jamil, Catawba Site Vice PresidentJ. Pitesa, Station Manager M. Patrick, Work Control Department Superintendent E. Beadle, Manager - Emergency Planning R. Repko, Engineering Manager G. Strickland, Regulatory Compliance (Engineer)LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED OpenedNoneClosedNone DiscussedNone A-Attachment 2LIST OF DOCUMENTS REVIEWEDSection 1EP1: Exercise EvaluationPlans and ProceduresRP/0/A/5000/006B, Notifications to States and Counties from the Technical Support Center, Rev. 20 RP/0/A/5000/020, Technical Support Center (TSC) Activation Procedure, Rev. 20 RP/0/A/5000/024, OSC Activation Procedure, Rev. 15 SR/0/B/2000/003, Activation of the Emergency Operations Facility, Rev. 15SR/0/B/2000/004, Notification to States and Counties from the Emergency Operations Facility, Rev. 9 RP/0/A/5000/001, Classification of Emergency, Rev. 017 RP/0/A/5000/002, Notification of Unusual Event, Rev. 038 RP/0/A/5000/003, Alert, Rev. 041 RP/0/A/5000/004, Site Area Emergency, 043 RP/0/A/5000/005, General Emergency, 044 RP/0/A/5000/006A, Notification to States and Counties from the Control Room, Rev. 020 RP/0/A/5000/006B, Notification to States and Counties from the Technical Support Center, Rev. 021 PT/0/B/4600/006, Emergency Exercises and Drills, Rev. 011SR/0/B/2000/003, Activation of the Emergency Operations Facility, Rev. 016SH/0/B/2005/001, Emergency Response Offsite Dose Projections, Rev. 004MiscellaneousProblem Investigation Process C-06-03819, Apparent mis-classification of General Emergency during graded exercise, 5/16/06C-06-3808, Corrective Action Items for non-risk significant items from Graded Exercise 06-2, 05/16/06 C-06-03776, Required Boron concentration for end of cycle shutdown margin appear to be overly conservative on both units, 05/16/06 C-06-03807, Corrective Action Items for risk significant items from Graded Exercise 06-2, 05/16/06Nuclear Power Plant Emergency Notification Form (Messages 1-8) for State and local agencies Section 1EP4: Emergency Action Level (EAL) and Emergency Plan Changes Plans and Changes packagesEmergency Plan, Rev. 06-01Catawba Emergency Plan Change Package 05-01 Catawba Emergency Plan Change Package 05-02 Catawba Emergency Plan Change Package 06-01 A-Attachment 3Change Package for RP/0/A/5000/006B, Notification to States and Counties from the Technical Support Center, Rev. 020 Change Package for SR/0/B/2000/004, Notification to States and Counties from the Emergency Operations Facility, Rev. 9Section 4OA1: Performance Indicator (PI) VerificationProceduresDPND-1551.00-0001, Emergency Planning Functional Area Manual: Section 3.7, NRCRegulatory Assessment Performance Indicator Guideline - Emergency Preparedness Cornerstone, Rev. 10Records and DataDocumentation (scenario, time line, event notification forms, critique report) of ERO drills on 06/21/2005, 11/22/2005 Documentation of CRS DEP evaluations in February 2005 and February 2006 Selected training records of drill/exercise participation by ERO personnel during 2004-2005Siren system test records for January 2005-March 2006 A-Attachment 4LIST OF ACRONYMSANSAlert and Notification System DEPDrill/Exercise Performance EALEmergency Action Level EOFEmergency Operations Facility EROEmergency Response Organization IMC Inspection Manual Chapter NEINuclear Energy Institute NRCNuclear Regulatory Commission OSCOperational Support Center PIPerformance Indicator PS Planning Standard RSPSRisk Significant Planning Standard TSCTechnical Support Center FEMAFederal Emergency Management Agency
| | LIST OF ACRONYMS ANS Alert and Notification System DEP Drill/Exercise Performance EAL Emergency Action Level EOF Emergency Operations Facility ERO Emergency Response Organization IMC Inspection Manual Chapter NEI Nuclear Energy Institute NRC Nuclear Regulatory Commission OSC Operational Support Center PI Performance Indicator PS Planning Standard RSPS Risk Significant Planning Standard TSC Technical Support Center FEMA Federal Emergency Management Agency A-4 Attachment |
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| _________________________OFFICERII:DRSRII:DRSRII:DRPRII:DRSRII:DRPSIGNATURE RARANAMELMILLERJKREH (*)EGUTHRIE (*)BBONSERCPAYNEDATE6/ /20065/23/20065/30/20066/2/20066/2/20066/ /20066/ /2006 E-MAIL COPY? YESNO YESNO YESNO YESNO YESNO YESNO YESNO
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| | OFFICE RII:DRS RII:DRS RII:DRP RII:DRS RII:DRP SIGNATURE RA RA NAME LMILLER JKREH (*) EGUTHRIE (*) BBONSER CPAYNE DATE 6/ /2006 5/23/2006 5/30/2006 6/2/2006 6/2/2006 6/ /2006 6/ /2006 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO |
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Category:Inspection Report
MONTHYEARIR 05000282/20244032024-10-25025 October 2024 – Security Baseline Inspection Report 05000282/2024403 and 05000306/2024403 IR 05000282/20243012024-09-13013 September 2024 NRC Initial License Examination Report 05000282/2024301 and 05000306/2024301 IR 05000282/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2024005 and 05000306/2024005) IR 05000282/20245012024-08-0505 August 2024 Emergency Preparedness Inspection Report 05000282/2024501 and 05000306/2024501 IR 05000282/20240022024-07-30030 July 2024 Integrated Inspection Report 05000282/2024002 and 05000306/2024002 IR 05000282/20240102024-06-28028 June 2024 Comprehensive Engineering Team Inspection Report 05000282/2024010 and 05000306/2024010 IR 05000282/20240012024-05-15015 May 2024 Integrated Inspection Report 05000282/2024001 and 05000306/2024001 IR 05000282/20244012024-04-25025 April 2024 – Security Baseline Inspection Report 05000282/2024401 and 05000306/2024401 IR 05000282/20230062024-02-28028 February 2024 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2023006 and 05000306/2023006) IR 05000282/20230042024-02-0101 February 2024 Integrated Inspection Report 05000282/2023004 and 05000306/2023004 IR 07200010/20234012023-12-20020 December 2023 Independent Spent Fuel Storage Installation Security Inspection Report 07200010/2023401 IR 05000282/20234012023-12-13013 December 2023 Security Baseline Inspection Report 05000282/2023401 and 05000306/2023401 IR 05000282/20230032023-11-0808 November 2023 Integrated Inspection Report 05000282/2023003 and 05000306/2023003 IR 05000282/20230052023-08-30030 August 2023 Updated Inspected Plan for Prairie Island Nuclear Generating Plant Report 05000282/2023005 and 05000306/2023005 IR 05000282/20230102023-08-17017 August 2023 NRC Inspection Report 05000282/2023010 and 05000306/2023010 IR 05000282/20230022023-08-0303 August 2023 Integrated Inspection Report 05000282/2023002 and 05000306/2023002 IR 05000282/20234202023-06-0101 June 2023 Security Baseline Inspection Report 05000282/2023420 and 05000306/2023420 IR 05000282/20230112023-05-16016 May 2023 Biennial Problem Identification and Resolution Inspection Report 05000282/2023011 and 05000306/2023011 IR 05000282/20230012023-05-10010 May 2023 Integrated Inspection Report 05000282/2023001 and 05000306/2023001 IR 05000282/20220062023-03-0101 March 2023 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report, Units 1 and 2 (Report 05000282/2022006 and 05000306/2022006) IR 05000282/20224042023-01-30030 January 2023 Material Control and Accounting Program Inspection Report 05000282/2022404 and 05000306/2022404 (Public) IR 05000282/20220042023-01-26026 January 2023 Integrated Inspection Report 05000282/2022004 and 05000306/2022004 IR 05000282/20224032023-01-24024 January 2023 – Security Baseline Inspection Report 05000282/2022403 and 05000306/2022403 IR 05000282/20220022022-12-0808 December 2022 RE-Issue Prairie Island Nuclear Generating Plant Integrated Inspection Report 05000282/2022002 and 05000306/2022002 IR 07200010/20222012022-11-0909 November 2022 TN-40HT, Dry Storage Cask, Inspection Report No. 07200010/2022201 IR 05000282/20220032022-11-0101 November 2022 Integrated Inspection Report 05000282/2022003 and 05000306/2022003 IR 05000282/20220112022-09-26026 September 2022 Phase 4 Post-Approval Site Inspection for License Renewal Report 05000282/2022011 and 05000306/2022011 IR 05000282/20223012022-08-31031 August 2022 NRC Initial License Examination Report 05000282/2022301; 05000306/2022301 IR 05000282/20220052022-08-29029 August 2022 Updated Inspection Plan for Prairie Island Nuclear Generating Plant (Report 05000282/2022005; 05000306/2022005) IR 05000282/20225012022-08-22022 August 2022 Emergency Preparedness Biennial Exercise Inspection Report 05000282/2022501 and 05000306/2022501 ML22227A1902022-08-16016 August 2022 Island Nuclear Generating Plant, Unit 1 - Notification of NRC Baseline Inspection and Request for Information: Inspection Report 05000282/2022004 ML22222A1732022-08-11011 August 2022 Integrated Inspection Report 05000282/2022002 and 05000306/2022002 IR 05000282/20220102022-06-24024 June 2022 Triennial Fire Protection Inspection Report 05000282/2022010 and 05000306/2022010 IR 05000282/20224022022-05-25025 May 2022 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000282/2022402 05000306/2022402 IR 05000282/20224012022-05-23023 May 2022 Security Baseline Inspection Report 05000282/2022401 and 05000306/2022401 ML22103A2522022-05-0404 May 2022 Review of the 2021 Steam Generator Tube Inspection Report IR 05000282/20220012022-05-0303 May 2022 Integrated Inspection Report 05000282/2022001, 05000306/2022001, and 07200010/2020001 IR 05000282/20210062022-03-0202 March 2022 Annual Assessment Letter (Report 05000282/2021006 and 05000306/2021006) IR 05000282/20210042022-02-11011 February 2022 Integrated Inspection Report 05000282/2021004 and 05000306/2021004 ML22017A0052022-01-17017 January 2022 (PINGP) 2021 Unit 2 180-Day Steam Generator Tube Inspection Report IR 05000282/20214032021-12-0202 December 2021 Security Baseline Inspection Report 05000282/2021403 and 05000306/2021403 IR 05000282/20210032021-11-12012 November 2021 Integrated Inspection Report 05000282/2021003 and 05000306/2021003 IR 05000282/20210122021-10-27027 October 2021 NRC Inspection Report 05000282/2021012 and 05000306/2021012 IR 05000282/20210052021-09-0101 September 2021 Updated Inspection Plan for Prairie Island Nuclear Generating Plant Units 1 and 2 (Report 05000282/2021005 and 05000306/2021005) IR 05000282/20215012021-08-25025 August 2021 Emergency Preparedness Biennial Exercise Inspection Report 05000282/2021501 and 05000306/2021501 IR 05000282/20210022021-08-0606 August 2021 Integrated Inspection Report 05000282/2021002 and 05000306/2021002 IR 05000282/20214022021-07-28028 July 2021 Security Baseline Inspection Report 05000282/2021402 and 05000306/2021402 IR 05000282/20210102021-06-22022 June 2021 Design Basis Assurance Inspection (Teams) Inspection Report 05000282/2021010 and 05000306/2021010 IR 05000282/20210112021-06-0303 June 2021 Biennial Problem Identification and Resolution Inspection Report 05000282/2021011 and 05000306/2021011 IR 05000282/20210012021-05-0606 May 2021 Integrated Inspection Report 05000282/2021001 and 05000306/2021001 2024-09-13
[Table view] Category:Letter
MONTHYEARML24298A0552024-10-30030 October 2024 Response to Alternative RR-10, Auxiliary Feedwater Valve Testing IR 05000282/20244032024-10-25025 October 2024 – Security Baseline Inspection Report 05000282/2024403 and 05000306/2024403 05000282/LER-2024-001-01, Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies2024-10-22022 October 2024 Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies L-PI-24-044, Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program2024-10-21021 October 2024 Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program ML24277A1012024-10-0303 October 2024 Closure of Interim Report of a Potential Deviation or Failure to Comply Associated with Bentley Systems Incorporated Autopipe Software ML24221A3622024-09-27027 September 2024 Issuance of Amendment Nos. 245 and 233 Revise Technical Specification 3.8.1, AC Sources-Operating, Surveillance Requirement 3.8.1.2, Note 3 ML24241A1682024-09-23023 September 2024 Transmittal Letter Amendment No. 13 to Materials License No. Special Nuclear Material-2506 for the Prairie Island Independent Spent Fuel Storage Installation 05000282/LER-2024-001, Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies2024-09-16016 September 2024 Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies IR 05000282/20243012024-09-13013 September 2024 NRC Initial License Examination Report 05000282/2024301 and 05000306/2024301 IR 05000282/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2024005 and 05000306/2024005) L-PI-24-040, Post-Submittal Package Letter2024-08-23023 August 2024 Post-Submittal Package Letter IR 05000282/20245012024-08-0505 August 2024 Emergency Preparedness Inspection Report 05000282/2024501 and 05000306/2024501 ML24213A1592024-07-31031 July 2024 Operator Licensing Examination Approval - Prairie Island Nuclear Generating Plant IR 05000282/20240022024-07-30030 July 2024 Integrated Inspection Report 05000282/2024002 and 05000306/2024002 ML24208A1502024-07-26026 July 2024 Independent Spent Fuel Storage Installation - Submittal of Quality Assurance Topical Report (NSPM-1) ML24197A2012024-07-15015 July 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2024004 IR 05000282/20240102024-06-28028 June 2024 Comprehensive Engineering Team Inspection Report 05000282/2024010 and 05000306/2024010 L-PI-24-036, – Preparation and Scheduling of Operator Licensing Examinations2024-06-28028 June 2024 – Preparation and Scheduling of Operator Licensing Examinations ML24158A5912024-06-0606 June 2024 CFR 50.46 LOCA Annual Report L-PI-24-031, Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-06-0505 June 2024 Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2) L-PI-24-014, License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption2024-06-0303 June 2024 License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption 05000306/LER-2024-001-01, Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump2024-05-31031 May 2024 Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump ML24155A1922024-05-31031 May 2024 Refueling Outage Unit 2 R33 Owners Activity Report for Class 1, 2, 3 and Mc Inservice Inspections ML24262A1992024-05-29029 May 2024 L-PI-24-018 PINGP 75 Day Letter ML24149A3712024-05-29029 May 2024 (Ping) - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection L-PI-24-030, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.12024-05-22022 May 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.1 ML24141A1292024-05-22022 May 2024 Northern States Power Company - Use of Encryption Software for Electronic Transmission of Safeguards Information ML24141A0452024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML24128A2572024-05-16016 May 2024 ISFSI A13 Acceptance Letter IR 05000282/20240012024-05-15015 May 2024 Integrated Inspection Report 05000282/2024001 and 05000306/2024001 ML24130A2362024-05-0909 May 2024 Independent Spent Fuel Storage Installation - 2023 Annual Radiological Environmental Monitoring Program Report ML24130A2392024-05-0909 May 2024 2023 Annual Radioactive Effluent Report ML24071A1162024-05-0101 May 2024 Issuance of Amendment Nos. 244 and 232 Revise TS 3.7.8, Cooling Water (Cl) System ML24128A0882024-04-30030 April 2024 Submittal of Updated Safety Analysis Report (Usar), Revision 38 05000306/LER-2024-001, Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump2024-04-29029 April 2024 Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump ML24089A2382024-04-29029 April 2024 Summary of Nuclear Property Insurance IR 05000282/20244012024-04-25025 April 2024 – Security Baseline Inspection Report 05000282/2024401 and 05000306/2024401 ML24100A8042024-04-24024 April 2024 – Alternative Request RR-09 for Safety Injection and Volume Control System Category C Check Valve Inservice Testing ML24114A0882024-04-23023 April 2024 Annual Report of Individual Monitoring for the Prairie Island Nuclear Generating Plant (PINGP) ML24113A1182024-04-12012 April 2024 NRC Letter Re NRC Office of Investigations Report No. 3-2023-004 ML24100A1212024-04-0909 April 2024 Submittal of Revised Pressure and Temperature Limits Report ML24093A2832024-04-0202 April 2024 Nuclear Material Transaction Report L-PI-24-012, Independent Spent Fuel Storage Installation - License Amendment Request: Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-04-0202 April 2024 Independent Spent Fuel Storage Installation - License Amendment Request: Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2) ML24089A2402024-03-29029 March 2024 Guarantee of Payment of Deferred Premiums ML24060A1232024-03-27027 March 2024 To Request 1-RR-5-10 and 2-RR-5-10 Regarding Reactor Pressure Vessel Welds and Nozzle Welds 05000282/LER-2023-001-01, Reactor Trip, Auxiliary Feedwater and Emergency Service Water System Actuation Due to Electrical Transient in DC Control Power Cables2024-03-21021 March 2024 Reactor Trip, Auxiliary Feedwater and Emergency Service Water System Actuation Due to Electrical Transient in DC Control Power Cables ML24262A1512024-03-15015 March 2024 L-PI-24-011 150 Day Letter 2024 PINGP ILT NRC Exam ML24010A0582024-03-0505 March 2024 Amendment No. 12 to Materials License No. Special Nuclear Material-2506 for the Prairie Island Independent Spent Fuel Storage Installation L-PI-24-004, Independent Spent Fuel Storage Installation - Annual Effluent Report, January Through December 20232024-02-29029 February 2024 Independent Spent Fuel Storage Installation - Annual Effluent Report, January Through December 2023 IR 05000282/20230062024-02-28028 February 2024 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2023006 and 05000306/2023006) 2024-09-27
[Table view] |
Inspection Report - Catawba - 2006008 |
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Text
une 2, 2006
SUBJECT:
CATAWBA NUCLEAR STATION - NRC INSPECTION REPORT 05000413/2006008 AND 05000414/2006008
Dear Mr. Jamil:
On May 19, 2006, the US Nuclear Regulatory Commission (NRC) completed an inspection at your Catawba Nuclear Station Units 1 and 2. The enclosed inspection report documents the inspections results, which were discussed with you, 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.
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 NRC's 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).
Should you have any questions concerning this letter, please contact us.
Sincerely,
/RA/
Brian R. Bonser, Chief Plant Support Branch 2 Division of Reactor Safety Docket Nos. 50-413, 50-414 License Nos. NPF-35, NPF-52
Enclosure:
(See page 2)
DEC 2 Enclosure: NRC Inspection Report 05000413/2006008 and 05000414/2006008 w/Attachment: Supplemental Information
REGION II==
Docket Nos.: 50-413, 50-414 License Nos.: NPF-35, NPF-52 Report No: 05000413/2006008, 05000414/2006008 Licensee: Duke Energy Corporation Facility: Catawba Nuclear Station Location: 4800 Concord Road York, SC 29745-9635 Dates: May 15-19, 2006 Inspectors: L. Miller, Senior Emergency Preparedness Inspector (Section 1EP1,1EP4)
J. Kreh, Emergency Preparedness Inspector (Section 1EP1, 4OA1)
E. Guthrie, Senior Resident Inspector, (Section 1EP1)
Approved by: Brian R. Bonser, Chief Plant Support Branch 2 Division of Reactor Safety Enclosure
SUMMARY OF FINDINGS IR 05000413/2006008, 05000414/2006008; 05/15-19/2006; Catawba Nuclear Station, Units 1 and 2; emergency preparedness The report covered an announced inspection by a team of two emergency preparedness inspectors and one resident inspector. 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.
A. NRC-Identified and Self-Revealing Findings Cornerstone: Emergency Preparedness None B. Licensee-Identified Violations.
None
1. REACTOR SAFETY Cornerstone: Emergency Preparedness 1EP1 Exercise Evaluation a. Inspection Scope Prior to the inspection activity, the inspectors conducted an in-office review of the exercise objectives and scenario submitted to the NRC to determine if the exercise would test major elements of the emergency plan as required by 10 CFR 50.47(b)(14).
This inspection activity represents one sample on a biennial cycle.
The onsite inspection consisted of the following review and assessment:
- The adequacy of the licensees performance in the biennial exercise conducted on May 16, 2006, was reviewed and assessed regarding the implementation of the Risk Significant Planning Standards (RSPSs) in 10 CFR 50.47 (b) (4), (5), (9), and (10),
which are emergency classification, offsite notification, radiological assessment, and protective action recommendations, respectively.
- The overall adequacy of the licensees emergency response facilities with regard to NUREG-0696, Functional Criteria for Emergency Response Facilities and Emergency Plan commitments. The facilities assessed were the Control Room simulator, Technical Support Center (TSC), Operational Support Center (OSC) and Emergency Operations Facility (EOF).
- Other performance areas besides the RSPS, such as the emergency response organizations (ERO) recognition of abnormal plant conditions, command and control, intra- and inter-facility communications, prioritization of mitigation activities, utilization of repair and field monitoring teams, interface with offsite agencies, and the overall implementation of the emergency plan and its implementing procedures.
- The post-exercise critique conducted May 19, 2006, to evaluate the licensees self-assessment of its ERO performance during the exercise and to ensure compliance with 10 CFR 50 Appendix E.IV.F.2.g The inspectors reviewed various documents which are listed in the Attachment to this report.
b. Findings No findings of significance were identified.
1EP4 Emergency Action Level (EAL) and Emergency Plan Changes a. Inspection Scope The inspectors review of revisions to the emergency plan, implementing procedures and EAL changes was performed for determining that changes had not decreased the effectiveness of the plan. The inspectors also evaluated the associated 10 CFR 50.54(q) reviews associated with non-administrative emergency plan, implementing procedures and EAL changes. The Catawba Nuclear Station Emergency Plan, revision 06-01 was reviewed.
The inspection was conducted in accordance with NRC Inspection Procedure 71114, Attachment 04, Emergency Action Level and Emergency Plan Changes. The applicable PS, 10 CFR 50.47(b)(4) and its related 10 CFR 50, Appendix E requirements were used as reference criteria. The criteria contained in NUREG-0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants, Revision 1, Regulatory Guide 1.101 were also used as references. This inspection activity represents one sample on an annual basis.
The inspectors reviewed various documents which are listed in the Attachment to this report.
b. Findings No findings of significance were identified.
4. OTHER ACTIVITIES 4OA1 Performance Indicator (PI) Verification a. Inspection Scope The inspectors reviewed the licensees procedure for developing the data for the Emergency Preparedness PIs which are: (1) DEP; (2) ERO Drill Participation; and (3)
Alert and Notification System (ANS) Reliability. The inspectors examined data reported to the NRC for the period January 1, 2005 to March 31, 2006. Procedural guidance for reporting PI information and records used by the licensee to identify potential PI occurrences were also reviewed. The inspectors verified the accuracy of the PI for ERO drill and exercise performance through review of a sample of drill and event records.
The inspectors reviewed selected training records to verify the accuracy of the PI for ERO drill participation for personnel assigned to key positions in the ERO. The inspectors verified the accuracy of the PI for alert and notification system reliability through review of a sample of the licensees records of periodic system tests.
The inspection was conducted in accordance with NRC Inspection Procedure 71151, Performance Indicator Verification. The applicable planning standard, 10 CFR 50.9 and Nuclear Energy Institute (NEI) 99-02, Revision 3, Regulatory Assessment Performance Indicator Guidelines, were used as reference criteria. This inspection activity represents three samples on an annual basis.
The inspectors reviewed various documents which are listed in the Attachment to this report.
b. Findings No findings of significance were identified.
4OA6 Meetings, including Exit On May 19, 2006, the team lead for the Emergency Preparedness Inspection presented the inspection results to Mr. D. Jamil, Catawba Site Vice President, and other members of his staff. The inspectors confirmed that proprietary information was not provided or taken during the inspection.
ATTACHMENT: SUPPLEMENTAL INFORMATION
SUPPLEMENTAL INFORMATION KEY POINTS OF CONTACT Licensee personnel D. Jamil, Catawba Site Vice President J. Pitesa, Station Manager M. Patrick, Work Control Department Superintendent E. Beadle, Manager - Emergency Planning R. Repko, Engineering Manager G. Strickland, Regulatory Compliance (Engineer)
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED Opened None Closed None Discussed None A-1 Attachment
LIST OF DOCUMENTS REVIEWED Section 1EP1: Exercise Evaluation Plans and Procedures RP/0/A/5000/006B, Notifications to States and Counties from the Technical Support Center, Rev. 20 RP/0/A/5000/020, Technical Support Center (TSC) Activation Procedure, Rev. 20 RP/0/A/5000/024, OSC Activation Procedure, Rev. 15 SR/0/B/2000/003, Activation of the Emergency Operations Facility, Rev. 15 SR/0/B/2000/004, Notification to States and Counties from the Emergency Operations Facility, Rev. 9 RP/0/A/5000/001, Classification of Emergency, Rev. 017 RP/0/A/5000/002, Notification of Unusual Event, Rev. 038 RP/0/A/5000/003, Alert, Rev. 041 RP/0/A/5000/004, Site Area Emergency, 043 RP/0/A/5000/005, General Emergency, 044 RP/0/A/5000/006A, Notification to States and Counties from the Control Room, Rev. 020 RP/0/A/5000/006B, Notification to States and Counties from the Technical Support Center, Rev. 021 PT/0/B/4600/006, Emergency Exercises and Drills, Rev. 011 SR/0/B/2000/003, Activation of the Emergency Operations Facility, Rev. 016 SH/0/B/2005/001, Emergency Response Offsite Dose Projections, Rev. 004 Miscellaneous Problem Investigation Process C-06-03819, Apparent mis-classification of General Emergency during graded exercise, 5/16/06 C-06-3808, Corrective Action Items for non-risk significant items from Graded Exercise 06-2, 05/16/06 C-06-03776, Required Boron concentration for end of cycle shutdown margin appear to be overly conservative on both units, 05/16/06 C-06-03807, Corrective Action Items for risk significant items from Graded Exercise 06-2, 05/16/06 Nuclear Power Plant Emergency Notification Form (Messages 1-8) for State and local agencies Section 1EP4: Emergency Action Level (EAL) and Emergency Plan Changes Plans and Changes packages Emergency Plan, Rev. 06-01 Catawba Emergency Plan Change Package 05-01 Catawba Emergency Plan Change Package 05-02 Catawba Emergency Plan Change Package 06-01 A-2 Attachment
Change Package for RP/0/A/5000/006B, Notification to States and Counties from the Technical Support Center, Rev. 020 Change Package for SR/0/B/2000/004, Notification to States and Counties from the Emergency Operations Facility, Rev. 9 Section 4OA1: Performance Indicator (PI) Verification Procedures DPND-1551.00-0001, Emergency Planning Functional Area Manual: Section 3.7, NRC Regulatory Assessment Performance Indicator Guideline - Emergency Preparedness Cornerstone, Rev. 10 Records and Data Documentation (scenario, time line, event notification forms, critique report) of ERO drills on 06/21/2005, 11/22/2005 Documentation of CRS DEP evaluations in February 2005 and February 2006 Selected training records of drill/exercise participation by ERO personnel during 2004-2005 Siren system test records for January 2005-March 2006 A-3 Attachment
LIST OF ACRONYMS ANS Alert and Notification System DEP Drill/Exercise Performance EAL Emergency Action Level EOF Emergency Operations Facility ERO Emergency Response Organization IMC Inspection Manual Chapter NEI Nuclear Energy Institute NRC Nuclear Regulatory Commission OSC Operational Support Center PI Performance Indicator PS Planning Standard RSPS Risk Significant Planning Standard TSC Technical Support Center FEMA Federal Emergency Management Agency A-4 Attachment
_________________________
OFFICE RII:DRS RII:DRS RII:DRP RII:DRS RII:DRP SIGNATURE RA RA NAME LMILLER JKREH (*) EGUTHRIE (*) BBONSER CPAYNE DATE 6/ /2006 5/23/2006 5/30/2006 6/2/2006 6/2/2006 6/ /2006 6/ /2006 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO