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| | issue date = 11/21/2008 | | | issue date = 11/21/2008 |
| | title = IR 05000327-08-501 & 05000328-08-501; Tennessee Valley Authority; on 10/13/2008 - 10/17/2008; Sequoyah Nuclear Plant Units 1 and 2, NRC Emergency Preparedness Inspection Report | | | title = IR 05000327-08-501 & 05000328-08-501; Tennessee Valley Authority; on 10/13/2008 - 10/17/2008; Sequoyah Nuclear Plant Units 1 and 2, NRC Emergency Preparedness Inspection Report |
| | author name = Bonser B R | | | author name = Bonser B |
| | author affiliation = NRC/RGN-II/DRS/PSB1 | | | author affiliation = NRC/RGN-II/DRS/PSB1 |
| | addressee name = Campbell W R | | | addressee name = Campbell W |
| | addressee affiliation = Tennessee Valley Authority | | | addressee affiliation = Tennessee Valley Authority |
| | docket = 05000327, 05000328 | | | docket = 05000327, 05000328 |
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| =Text= | | =Text= |
| {{#Wiki_filter: | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION November 21, 2008 |
| [[Issue date::November 21, 2008]]
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| Mr. William R. Campbell, Jr. Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
| | ==SUBJECT:== |
| | | SEQUOYAH NUCLEAR PLANT - NRC EMERGENCY PREPAREDNESS INSPECTION REPORT 05000327/2008501 AND 05000328/2008501 |
| SUBJECT: SEQUOYAH NUCLEAR PLANT - NRC EMERGENCY PREPAREDNESS INSPECTION REPORT 05000327/2008501 AND 05000328/2008501 | |
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| ==Dear Mr. Campbell,== | | ==Dear Mr. Campbell,== |
| Jr.: | | Jr.: |
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| On October 17, 2008, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Sequoyah Nuclear Plant, Units 1 and 2. The enclosed inspection report documents the inspection results, which were discussed on October 16, 2008, with Mr. T. Cleary and other members of his staff. | | On October 17, 2008, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Sequoyah Nuclear Plant, Units 1 and 2. The enclosed inspection report documents the inspection results, which were discussed on October 16, 2008, with Mr. T. Cleary and other members of his staff. |
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| The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license. | | 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. | | The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. |
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| In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response, if any, will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). | | In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response, if any, will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). |
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| Sincerely,/RA/ Brian Bonser, Chief Plant Support Branch 1 Division of Reactor Safety Docket No.: 50-327, 50-328 License No.: DPR-77, DPR-79 | | Sincerely, |
| | /RA/ |
| | Brian Bonser, Chief Plant Support Branch 1 Division of Reactor Safety Docket No.: 50-327, 50-328 License No.: DPR-77, DPR-79 |
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| ===Enclosure:=== | | ===Enclosure:=== |
| Inspection Report 05000327/2008501 and 05000328/2008501 | | Inspection Report 05000327/2008501 and 05000328/2008501 w/Attachment: |
| | | Supplemental Information ( |
| ===w/Attachment:===
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| Supplemental Information | |
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| (cc w/encl - See page 2)
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| _________________________ X G SUNSI REVIEW COMPLETE TVA 2 cc w/encl: Ashok S. Bhatnagar Senior Vice President Nuclear Generation Development and Construction Tennessee Valley Authority Electronic Mail Distribution
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| Ludwig E. Thibault General Manager Nuclear Oversight & Assistance Tennessee Valley Authority Electronic Mail Distribution
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| Tom Coutu Vice President Nuclear Support Tennessee Valley Authority Electronic Mail Distribution
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| William R. Campbell, Jr.
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| Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
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| Christopher R. Church Plant Manager Sequoyah Nuclear Plant Tennessee Valley Authority Electronic Mail Distribution
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| (Vacant) | |
| Vice President Nuclear Support Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
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| Michael J. Lorek Interim Vice President Nuclear Engineering & Projects Tennessee Valley Authority Electronic Mail Distribution
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| (cc: w/encl - See Page 3)
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| Timothy P. Cleary Site Vice President Sequoyah Nuclear Plant Tennessee Valley Authority Electronic Mail Distribution John C. Fornicola General Manager Nuclear Assurance Tennessee Valley Authority Electronic Mail Distribution
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| General Counsel Tennessee Valley Authority Electronic Mail Distribution
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| Beth A. Wetzel Manager Corporate Licensing Tennessee Valley Authority Electronic Mail Distribution
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| James D. Smith Manager, Licensing and Industry Affairs Sequoyah Nuclear Plant Tennessee Valley Authority Electronic Mail Distribution
| | REGION II== |
| | | Docket Nos.: 05000327, 05000328 License Nos.: DPR-77, DPR-79 Report No.: 05000327/2008501 and 05000328/2008501 Licensee: Tennessee Valley Authority Facility: Sequoyah Nuclear Plant, Units 1 and 2 Location: Soddy-Daisy, TN Dates: October 13, 2008 through October 17, 2008 Inspectors: Lee Miller, Senior Emergency Preparedness Inspector Bob Holbrook, Emergency Preparedness Inspector Rick Baldwin, Senior Operations Engineer Approved by: Brian Bonser, Chief Plant Support Branch 1 Division of Reactor Safety Attachment |
| Larry E. Nicholson General Manager Licensing & Performance Improvement Tennessee Valley Authority Electronic Mail Distribution
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| Michael A. Purcell Senior Licensing Manager Nuclear Power Group Tennessee Valley Authority Electronic Mail Distribution
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| Senior Resident Inspector U.S. Nuclear Regulatory Commission Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy Daisy, TN 37379-3624 TVA 3 cc: w/encl Lawrence Edward Nanney Director Division of Radiological Health TN Dept. of Environment & Conservation Electronic Mail Distribution County Mayor Hamilton County Hamilton County Courthouse Hamilton County Courthouse Chattanooga, TN 37402-2801
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| James H. Bassham Director Tennessee Emergency Management Agency Electronic Mail Distribution Ann Harris 341 Swing Loop Rockwood, TN 37854
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| TVA 4 Letter to William R. Campbell, Jr. from Brian Bonser dated November 21, 2008
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| SUBJECT: SEQUOYAH NUCLEAR PLANT - NRC EMERGENCY PREPAREDNESS INSPECTION REPORT 05000327/2008501 AND 05000328/2008501 Distribution w/encl:
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| RIDSNRRDIRS PUBLIC R. Pascarelli, NRR ((Regulatory Conferences Only)) B. Moroney, NRR (PM: SEQ)
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| Attachment U.S. NUCLEAR REGULATORY COMMISSION REGION II
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| Docket Nos.: 05000327, 05000328 | |
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| License Nos.: DPR-77, DPR-79 | |
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| Report No.: 05000327/2008501 and 05000328/2008501 | |
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| Licensee: Tennessee Valley Authority | |
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| Facility: Sequoyah Nuclear Plant, Units 1 and 2 | |
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| Location: Soddy-Daisy, TN | |
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| Dates: October 13, 2008 through October 17, 2008 | |
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| Inspectors: Lee Miller, Senior Emergency Preparedness Inspector Bob Holbrook, Emergency Preparedness Inspector Rick Baldwin, Senior Operations Engineer | |
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| Approved by: Brian Bonser, Chief Plant Support Branch 1 Division of Reactor Safety | |
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| Attachment | |
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| =SUMMARY OF FINDINGS= | | =SUMMARY OF FINDINGS= |
| IR 05000327/2008-501 and 05000328/2008-501; 10/13/2008 - 10/17/2008; Sequoyah Nuclear | | IR 05000327/2008-501 and 05000328/2008-501; 10/13/2008 - 10/17/2008; Sequoyah Nuclear |
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| Plant, Units 1 and 2; Emergency Preparedness Baseline Inspection | | Plant, Units 1 and 2; Emergency Preparedness Baseline Inspection The report covered an announced inspection by two regional emergency preparedness inspectors and an operations engineer. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, AReactor Oversight Process,@ Revision 3, dated July 2000. |
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| The report covered an announced inspection by two regional emergency preparedness inspectors and an operations engineer. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, AReactor Oversight Process,@ Revision 3, dated July 2000.
| | ===NRC-Identified and Self-Revealing Findings=== |
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| ===A. NRC-Identified and Self-Revealing Findings===
| | No findings of significance were identified. |
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| No findings of significance were identified.
| | ===Licensee-Identified Violations=== |
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| | None. |
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| ===B. Licensee-Identified Violations===
| | Attachment |
| . None.
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| =REPORT DETAILS= | | =REPORT DETAILS= |
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| ==REACTOR SAFETY== | | ==REACTOR SAFETY== |
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| ===Cornerstone:=== | | ===Cornerstone: Emergency Preparedness=== |
| Emergency Preparedness 1EP1 Exercise Evaluation
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| | 1EP1 Exercise Evaluation |
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| ====a. Inspection Scope==== | | ====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. | | 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 onsite inspection consisted of the following review and assessment: |
| * The adequacy of the licensee's performance in the biennial exercise conducted on October 15, 2008, 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 address emergency classification, offsite notification, radiological assessment, and protective action recommendations, respectively. | | * The adequacy of the licensees performance in the biennial exercise conducted on October 15, 2008, 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 address emergency classification, offsite notification, radiological assessment, and protective action recommendations, respectively. |
| * The overall adequacy of the licensee's 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), Operations Support Center (OSC) and Central Emergency Control Center (CECC). | | * 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), Operations Support Center (OSC) and Central Emergency Control Center (CECC). |
| * Other performance areas besides the RSPS, such as the emergency response organization'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, and the overall implementation of the emergency plan and its implementing procedures. | | * 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. |
| * Past performance issues from NRC inspection reports and Federal Emergency Management Agency (FEMA)/Department of Homeland Security (DHS) exercise reports to determine effectiveness of corrective actions as demonstrated during this exercise to ensure compliance with 10 CFR 50.47(b)(14). | | * Past performance issues from NRC inspection reports and Federal Emergency Management Agency (FEMA)/Department of Homeland Security (DHS) 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 process and the presentation to the licensee's senior management conducted on October 16, 2008, 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.g. | | * The post-exercise critique process and the presentation to the licensee's senior management conducted on October 16, 2008, 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. |
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| The inspectors reviewed various documents which are listed in the Attachment to this report. | | The inspectors reviewed various documents which are listed in the Attachment to this report. |
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| ====b. Findings==== | | ====b. Findings==== |
| No findings of significance were identified. | | No findings of significance were identified. |
| | | 1EP4 Emergency Action Level and Emergency Plan Changes |
| 1EP4 Emergency Action Level and Emergency Plan Changes | |
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| ====a. Inspection Scope==== | | ====a. Inspection Scope==== |
| Since the last NRC inspection of this program area, Revisions 87 and 88 of Tennessee Valley Authority Nuclear Radiological Emergency Plan were implemented based on the licensee's determination, in accordance with 10 CFR 50.54(q), that the changes resulted in no decrease in the effectiveness of the Plan, and that the revised Plan continued to meet the requirements of 10 CFR 50.47(b) and Appendix E to 10 CFR Part 50. The inspectors conducted a sampling review of the Plan changes and implementing procedure changes made between June 1, 2007 and September 30, 2008 to evaluate for potential decreases in effectiveness of the Plan. However, this review was not documented in a Safety Evaluation Report and does not constitute formal NRC approval of the changes. Therefore, these changes remain subject to future NRC inspection in their entirety. | | Since the last NRC inspection of this program area, Revisions 87 and 88 of Tennessee Valley Authority Nuclear Radiological Emergency Plan were implemented based on the licensees determination, in accordance with 10 CFR 50.54(q), that the changes resulted in no decrease in the effectiveness of the Plan, and that the revised Plan continued to meet the requirements of 10 CFR 50.47(b) and Appendix E to 10 CFR Part 50. The inspectors conducted a sampling review of the Plan changes and implementing procedure changes made between June 1, 2007 and September 30, 2008 to evaluate for potential decreases in effectiveness of the Plan. However, this review was not documented in a Safety Evaluation Report and does not constitute formal NRC approval of the changes. Therefore, these changes remain subject to future NRC inspection in their entirety. |
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| The inspection was conducted in accordance with NRC Inspection Procedure 71114, Attachment 04, AEmergency Action Level and Emergency Plan Changes.
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| @ The applicable planning standard (PS), 10 CFR 50.47(b) (4) and its related 10 CFR 50, Appendix E requirements were used as reference criteria. | | The inspection was conducted in accordance with NRC Inspection Procedure 71114, 04, AEmergency Action Level and Emergency Plan Changes.@ The applicable planning standard (PS), 10 CFR 50.47(b) |
| | : (4) and its related 10 CFR 50, Appendix E requirements were used as reference criteria. |
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| The inspectors reviewed various documents which are listed in the Attachment to this report. This inspection activity satisfied one inspection sample for the emergency action level and emergency plan changes on an annual basis. | | The inspectors reviewed various documents which are listed in the Attachment to this report. This inspection activity satisfied one inspection sample for the emergency action level and emergency plan changes on an annual basis. |
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| ====a. Inspection Scope==== | | ====a. Inspection Scope==== |
| ===Cornerstone:=== | | ===Cornerstone: Emergency Preparedness=== |
| Emergency Preparedness The inspectors sampled licensee submittals for three Performance Indicators (PI) listed below. For each of the submittals reviewed, the inspectors reviewed the period from April 1, 2007 through June 30, 2008. To verify the accuracy of the PI data reported during that period, PI definitions and guidance contained in Nuclear Energy Institute (NEI) 99-02, ARegulatory Assessment Indicator Guideline,@ Revision 5, were used to verify the basis in reporting for each data element.
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| | The inspectors sampled licensee submittals for three Performance Indicators (PI) listed below. For each of the submittals reviewed, the inspectors reviewed the period from April 1, 2007 through June 30, 2008. To verify the accuracy of the PI data reported during that period, PI definitions and guidance contained in Nuclear Energy Institute (NEI) 99-02, ARegulatory Assessment Indicator Guideline,@ Revision 5, were used to verify the basis in reporting for each data element. |
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| $ Emergency Response Organization Drill/Exercise Performance (DEP) | | $ Emergency Response Organization Drill/Exercise Performance (DEP) |
| $ Emergency Response Organization Readiness (ERO) | | $ Emergency Response Organization Readiness (ERO) |
| $ Alert and Notification System Reliability (ANS) | | $ Alert and Notification System Reliability (ANS) |
| The inspectors reviewed portions of the raw PI data developed from monthly performance indicator reports and discussed the methods for compiling and reporting the PIs with cognizant emergency preparedness personnel. The inspectors also independently screened drill and exercise opportunity evaluations, drill participation reports, and drill evaluations. Selected reported values were calculated to verify their accuracy. The inspectors compared graphical representations from the most recent PI report to the raw data to verify that the data was correctly reflected in the report. | | The inspectors reviewed portions of the raw PI data developed from monthly performance indicator reports and discussed the methods for compiling and reporting the PIs with cognizant emergency preparedness personnel. The inspectors also independently screened drill and exercise opportunity evaluations, drill participation reports, and drill evaluations. Selected reported values were calculated to verify their accuracy. The inspectors compared graphical representations from the most recent PI report to the raw data to verify that the data was correctly reflected in the report. |
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| ====b. Findings==== | | ====b. Findings==== |
| No findings of significance were identified. | | No findings of significance were identified. |
| | {{a|4OA5}} |
| | ==4OA5 Other Activities== |
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| {{a|4OA5}}
| | ===.1 (Closed) NRC Temporary Instruction (TI) 2525/175, Emergency Response Organization,=== |
| ==4OA5 Other Activities== | |
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| ===.1 (Closed) NRC Temporary Instruction (TI) 2525/175, Emergency Response Organization, Drill/Exercise Performance Indicator, Program Review===
| | Drill/Exercise Performance Indicator, Program Review The inspectors completed Temporary Instruction TI 2515/175, Emergency Response Organization, Drill/Exercise Performance Indicator, Program Review. Appropriate documentation of the results was provided to NRC, HQ, as required by the TI. This completes the Region II inspection requirements for this TI for Sequoyah Nuclear Power Plant. |
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| The inspectors completed Temporary Instruction TI 2515/175, Emergency Response Organization, Drill/Exercise Performance Indicator, Program Review. Appropriate documentation of the results was provided to NRC, HQ, as required by the TI. This completes the Region II inspection requirements for this TI for Sequoyah Nuclear Power Plant.
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| {{a|4OA6}} | | {{a|4OA6}} |
| ==4OA6 Meetings, including Exit== | | ==4OA6 Meetings, including Exit== |
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| On October 16, 2008, the lead inspector presented the inspection results to Mr. T. Cleary and other members of your staff. The inspectors confirmed that proprietary information was not provided during the inspection. | | On October 16, 2008, the lead inspector presented the inspection results to Mr. T. |
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| | Cleary and other members of your staff. The inspectors confirmed that proprietary information was not provided during the inspection. |
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| ATTACHMENT: | | ATTACHMENT: |
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| ===Licensee personnel=== | | ===Licensee personnel=== |
| : [[contact::T. Cleary]], Site Vice President | | : [[contact::T. Cleary]], Site Vice President |
| : [[contact::C. Church]], Plant Manager | | : [[contact::C. Church]], Plant Manager |
| : [[contact::B. Marks]], Corporate Emergency Preparedness Manager | | : [[contact::B. Marks]], Corporate Emergency Preparedness Manager |
| : [[contact::R. Thompson]], Emergency Preparedness Manager | | : [[contact::R. Thompson]], Emergency Preparedness Manager |
| : [[contact::R. Proffitt]], Licensing Engineer | | : [[contact::R. Proffitt]], Licensing Engineer |
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| ==LIST OF DOCUMENTS REVIEWED== | | ==LIST OF DOCUMENTS REVIEWED== |
| 1EP1 Exercise Evaluation
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| ===Procedures===
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| : EPIP-1, Emergency Plan Classification Matrix, Rev.40
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| : EPIP-3, Alert, Rev. 30
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| : EPIP-4, Site Area Emergency, Rev. 30
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| : EPIP-5, General Emergency, Rev. 37 CECC
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| : EPIP-1, Central Emergency Control Center (CECC) Operations, Rev. 47 CECC
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| : EPIP-6, CECC Plant Assessment Staff Procedure for Alert, Site Area Emergency, and General Emergency, Rev. 30 CECC
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| : EPIP-9, Emergency Environmental Radiological Monitoring, Rev. 36
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| : OPDP-1, Conduct of Operations, Rev. 10
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| : Records and Data Documentation packages completed in the Control Room, Technical Support Center, Operations Support Center, Combined Emergency Control Center, Joint Information Center.
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| : The packages included, but not limited to the following: logs, event notification forms, Protective Action Recommendations, Media releases, Radiological Dose Assessments, Core Damage calculations.
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| : Corrective Action - Problem Evaluation Report (PER)
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| : PER 154730
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| : PER 154738
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| : PER 154749
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| : PER 154762
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| : PER 154766
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| : PER 154804
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| : PER 154852
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| : PER 154855
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| : PER 154856
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| : PER 154859
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| : PER 154860
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| : PER 154862
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| : PER 154864
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| : PER 154865
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| : PER 154869
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| : PER 154878
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| : PER 154879
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| : PER 154881
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| : PER 154883
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| : PER 154888
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| : PER 154889
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| : PER 154891
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| : PER 154892
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| : PER 154894
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| : PER 154895
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| : PER 154898
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| : PER 154906
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| : PER 154908
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| : PER 154909
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| : PER 154910
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| : PER 154912
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| : PER 154914
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| : PER 154938
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| : PER 154939
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| : 1EP4 Emergency Action Level and Emergency Plan Changes
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| ===Procedures===
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| : Tennessee Valley Authority Nuclear Radiological Emergency Plan, Rev. 87 and 88
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| : EPIL-1, Emergency Preparedness Instruction Letter - Procedures, Maps, and Drawings, Rev.
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| : Plans and Changes packages
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| : EPIP-6, Activation and Operation of the Technical Support Center, Rev. 43
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| : EPIP-8, Personnel Accountability and Evacuation, Rev. 17
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| : EPIP-12, Emergency Equipment and Supplies, Rev. 7
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| : EPIP-13, Dose Assessment, Rev. 12 and 13
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| : 4OA1 Performance Indicator Verification
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| ===Procedures===
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| : EPIL-15, Emergency Preparedness Performance Indicators, Rev. 12
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| : Records and Data
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| : ANS data from 3
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| rd Quarter 2007 to 2
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| nd Quarter 2008 ERO data from 3
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| rd Quarter 2007 to 2
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| nd Quarter 2008 DEP data from 3
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| rd Quarter 2007 to 2
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| nd Quarter 2008
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| ==LIST OF ACRONYMS==
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| : [[ANS]] [[Alert and Notification System]]
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| : [[CECC]] [[Central Emergency Control Center]]
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| : [[DEP]] [[Drill/Exercise Performance]]
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| : [[DHS]] [[Department of Homeland Security]]
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| : [[ERO]] [[Emergency Response Organization]]
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| : [[FEMA]] [[Federal Emergency Management Agency]]
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| : [[NEI]] [[Nuclear Energy Institute]]
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| : [[OSC]] [[Operations Support Center]]
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| : [[PI]] [[Performance Indicator]]
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| : [[PS]] [[Planning Standard]]
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| : [[RSPS]] [[Risk Significant Planning Standards]]
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| : [[TI]] [[Temporary Instruction]]
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| : [[TSC]] [[Technical Support Center]]
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| : [[STAND]] [[-ALONE INSPECTION]]
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| : [[REPORT]] [[(]]
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| : [[NOTE]] [[: E-MAIL]]
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| : [[COPY]] [[]]
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| : [[OF]] [[]]
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| : [[REPORT]] [[]]
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| : [[WITH]] [[]]
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| : [[THIS]] [[]]
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| : [[FORM]] [[)]]
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| : [[IP]] [[Used Sample Size Completion Status** (for]]
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| : [[IP]] [[use]]
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| : [[MC]] [[306 status; for Its use 'Closed' or 'More to Follow') 71114.01 1 Complete - Minimum number inspected 71114.04 1 Complete - Minimum number inspected 71151 3 Complete - Minimum number inspected]]
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| TI 2515/175 Closed (by reference) Completion Status Definitions (MC 0306): Complete - The minimum number of samples were inspected Complete (minimum sample not available during the inspection cycle) - licensee did not perform minimum number of activities Complete (opportunity to apply procedure not available during the inspection cycle - used for inspections that are scheduled "a
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| s conditions require") Complete (by reference) - one or more samples was completed during a different inspection such as
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| : [[SGRP]] [[or a]]
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| TI Incomplete - The minimum number of samples was not inspected
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| **Provide brief explanation if the minimum number of samples were not inspected.
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| Branch Chief Approval: Brian Bonser Date: 11/20/2008
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| Emailed By: Karen Hunter Date: 11/21/2008
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| }} | | }} |
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Category:Inspection Report
MONTHYEARIR 05000327/20240032024-11-0606 November 2024 Integrated Inspection Report 05000327/2024003 and 05000328/2024003 IR 05000327/20250102024-10-29029 October 2024 Notification of Sequoyah, Units 1 and 2 - Comprehensive Engineering Team Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000327/2025010 and 05000328/2025010 IR 05000327/20240052024-08-26026 August 2024 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2024005 and 05000328/2024005 IR 05000327/20240022024-07-31031 July 2024 Integrated Inspection Report 05000327/2024002 and 05000328/2024002 ML24145A0852024-05-30030 May 2024 1B-B Diesel Generator Failure - Final Significance Determination Letter IR 05000327/20240012024-04-17017 April 2024 Integrated Inspection Report 05000327/2024001 and 05000328/2024001 IR 05000327/20240902024-03-19019 March 2024 NRC Inspection Report 05000327-2024090 and 05000328-2024090 and Preliminary Greater than Green Finding and Apparent Violation IR 05000327/20244012024-03-12012 March 2024 – Security Baseline Inspection Report 05000327/2024401 and 05000328/2024401 IR 05000259/20230062024-02-28028 February 2024 Annual Assessment Letter for Sequoyah Nuclear Plant, Units 1, 2 - Report 05000259/2023006, 05000260/2023006 and 05000296/2023006 IR 05000327/20230042024-02-12012 February 2024 Integrated Inspection Report 05000327/2023004 and 05000328/2023004 and Apparent Violation IR 05000327/20234422024-01-11011 January 2024 95001 Supplemental Inspection Report 05000327/2023442 and 05000328/2023442 and Follow-Up Assessment Letter IR 05000327/20234202023-11-28028 November 2023 Security Baseline Inspection Report 05000327/2023420 and 05000328/2023420 IR 05000327/20230032023-11-0303 November 2023 – Integrated Inspection Report 05000327/2023003 and 05000328/2023003 IR 05000327/20230112023-10-16016 October 2023 Triennial Fire Protection Inspection Report 05000327/2023011 and 05000328/2023011 IR 05000327/20234032023-09-14014 September 2023 Cyber Security Inspection Report 05000327/2023403 and 05000328/2023403 (Cover Letter) IR 05000327/20230052023-08-29029 August 2023 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2023005 and 05000328/2023005 IR 05000327/20230022023-07-31031 July 2023 Integrated Inspection Report 05000327/2023002 and 05000328/2023002 IR 05000327/20230102023-07-20020 July 2023 – Biennial Problem Identification and Resolution Inspection Report 05000327/2023010 and 05000328/2023010 ML23163A0392023-06-13013 June 2023 – Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000327/2023011, 05000328/2023011) and Request for Information (RFI) IR 05000327/20233012023-05-15015 May 2023 – NRC Operator License Examination Report 05000327/2023301 and 05000328/2023301 IR 05000327/20230012023-05-0202 May 2023 Integrated Inspection Report 05000327/2023001 and 05000328/2023001 and Exercise of Enforcement Discretion IR 05000327/20234412023-04-20020 April 2023 Final Significance Determination for a Security-Related Greater than Green Finding, Nov & Assessment Followup Letter, 05000327/2023441 & 05000328/2023441 IR 05000327/20234022023-04-13013 April 2023 Security Baseline Inspection Report 05000327/2023402 and 05000328/2023402 IR 05000327/20220062023-03-0101 March 2023 Annual Assessment Letter for Sequoyah Nuclear Plant, Units 1 and 2 Report 05000327/2022006 and 05000328/2022006 IR 05000327/20234402023-02-13013 February 2023 – NRC Inspection Report 05000327/2023440 and 05000328/2023440; Preliminary Greater than Green and Apparent Violation Cover Letter IR 05000327/20220042023-02-10010 February 2023 Integrated Inspection Report 05000327/2022004 and 05000328/2022004 IR 05000327/20234012023-02-0606 February 2023 – Security Baseline Inspection Report 05000327/2023401 and 05000328/2023401 IR 05000327/20224402023-01-17017 January 2023 – Special Inspection Report 05000327/2022440 and 05000328/2022440 and Apparent Violation - Cover IR 05000327/20220032022-11-0707 November 2022 – Integrated Inspection Report 05000327/2022003 and 05000328/2022003 IR 05000327/20224012022-10-18018 October 2022 Material Control and Accounting Program Inspection Report 05000327/2022401 and 05000328/2022401 IR 05000327/20220052022-08-30030 August 2022 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327 2022005 and 05000328 2022005 - Final IR 05000327/20220022022-08-0101 August 2022 Integrated Inspection Report 05000327 2022002 and 05000328 2022002 IR 05000327/20220012022-05-11011 May 2022 Integrated Inspection Report 05000327/2022001, 05000328/2022001 and 07200034/2010002 IR 05000327/20223012022-05-10010 May 2022 NRC Operator Licensing Examination Approval 05000327/2022301 and 05000328/2022301 IR 05000327/20224022022-03-28028 March 2022 Security Baseline Inspection Report 05000327/2022402 and 05000328/2022402 IR 05000327/20210062022-03-0202 March 2022 Annual Assessment Letter for Sequoyah Nuclear Plant, Units 1 and 2 - (Report No. 05000327/2021006 and 05000328/2021006) IR 05000327/20210042022-02-0707 February 2022 Integrated Inspection Report 05000327/2021004 and 05000328/2021004 IR 05000327/20220102021-12-15015 December 2021 Notification of Sequoyah Nuclear Plant - Design Bases Assurance Inspection (Teams) - U.S. Nuclear Regulatory Commission Inspection Report 05000327/2022010 and 05000328/2022010 IR 05000327/20210032021-11-10010 November 2021 Integrated Inspection Report 05000327/2021003 and 05000328/2021003 and Apparent Violation and Exercise of Enforcement Discretion IR 05000327/20210052021-08-18018 August 2021 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 Report 05000327/2021005 and 05000328/2021005 IR 05000327/20210022021-07-27027 July 2021 Integrated Inspection Report 05000327/2021002 and 05000328/2021002 IR 05000327/20210112021-07-19019 July 2021 Biennial Problem Identification and Resolution Inspection Report 05000327/2021011 and 05000328/2021011 IR 05000327/20210012021-04-27027 April 2021 Integrated Inspection Report 05000327/2021001 and 05000328/2021001 IR 05000327/20210102021-04-21021 April 2021 NRC Inspection Report 05000327/2021010 and 05000328/2021010 IR 05000327/20214012021-04-21021 April 2021 NRC Inspection Report 05000327/2021401 and 05000328/2021401 (U) IR 05000327/20200062021-03-0303 March 2021 Annual Assessment Letter for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2020006 and 05000328/2020006 IR 05000327/20200042021-01-29029 January 2021 Integrated Inspection Report 05000327/2020004 and 05000328/2020004 IR 05000327/20204202020-11-20020 November 2020 Security Inspection Report 05000327/2020420 and 05000328/2020420 ML20321A2102020-11-20020 November 2020 Security Inspection Report 05000327/2020420 and 05000328/2020420 - Cover Letter IR 05000327/20200032020-11-10010 November 2020 Integrated Inspection Report 05000327/2020003, 05000328/2020003 and 07200034/2020002 2024-08-26
[Table view] Category:Letter
MONTHYEARCNL-24-021, Application to Revise Technical Specification Limiting Condition of Operation 3.5.2, ECCS – Operating, Note 1 to Include Residual Heat Removal Pump Flow Paths (SQN-TS-23-04 and WBN-TS-23-020)2024-11-12012 November 2024 Application to Revise Technical Specification Limiting Condition of Operation 3.5.2, ECCS – Operating, Note 1 to Include Residual Heat Removal Pump Flow Paths (SQN-TS-23-04 and WBN-TS-23-020) ML24312A1552024-11-0606 November 2024 Cycle 27 Core Operating Limits Report, Revision 1 IR 05000327/20240032024-11-0606 November 2024 Integrated Inspection Report 05000327/2024003 and 05000328/2024003 CNL-24-014, License Amendment Request to Revise the Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications to Use Online Monitoring Methodology (SQN-TS-24-02 and WBN-TS-23-22)2024-11-0404 November 2024 License Amendment Request to Revise the Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications to Use Online Monitoring Methodology (SQN-TS-24-02 and WBN-TS-23-22) ML24304A8492024-10-31031 October 2024 December 2024 Requalification Inspection Notification Letter IR 05000327/20250102024-10-29029 October 2024 Notification of Sequoyah, Units 1 and 2 - Comprehensive Engineering Team Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000327/2025010 and 05000328/2025010 ML24298A1172024-10-24024 October 2024 Cycle 26, 180-Day Steam Generator Tube Inspection Report CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 05000327/LER-2024-001, Reactor Trip Due to a Turbine Trip2024-10-17017 October 2024 Reactor Trip Due to a Turbine Trip ML24282B0412024-10-15015 October 2024 Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 ML24260A1682024-10-0404 October 2024 Regulatory Audit Summary Related to Request to Add and Revise Notes Related to Technical Specification Table 3.3.2-1, Function 5 ML24284A1072024-09-26026 September 2024 Affidavit for Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2 05000328/LER-2024-001, Reactor Trip Due to an Electrical Trouble Turbine Trip2024-09-25025 September 2024 Reactor Trip Due to an Electrical Trouble Turbine Trip CNL-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024 Decommitment of Flood Mode Mitigation Improvement Systems CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan ML24267A0402024-09-19019 September 2024 Cycle 27 Core Operating Limits Report Revision 0 CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24185A1742024-09-18018 September 2024 Cover Letter - Issuance of Exemption Related to Non-Destructive Examination Compliance Regarding Sequoyah Nuclear Plant Independent Spent Fuel Storage Installation ML24253A0152024-09-0808 September 2024 Emergency Plan Implementing Procedure Revisions ML24247A2212024-08-29029 August 2024 Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Letter OG-21-160, NEI 03-08 Needed Guidance: PWR Lower Radial Support Clevis Insert X-750 Bolt Inspection Requirements, September 1, 2021 ML24247A1802024-08-28028 August 2024 Application to Revise the Fuel Handling Accident Analysis, to Delete Technical Specification 3.9.4, Containment Penetrations, and to Modify Technical Specification 3.3.6, Containment Ventilation Isolation Instrumentation for Sequoyah Nuclea IR 05000327/20240052024-08-26026 August 2024 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2024005 and 05000328/2024005 ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 CNL-24-061, Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),2024-08-19019 August 2024 Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08), IR 05000327/20240022024-07-31031 July 2024 Integrated Inspection Report 05000327/2024002 and 05000328/2024002 ML24211A0572024-07-29029 July 2024 Submittal of Emergency Plan Implementing Procedure Revision ML24211A0542024-07-29029 July 2024 Operator License Examination Report ML24211A0412024-07-26026 July 2024 Unit 1 Cycle 26 Refueling Outage - 90-Day Inservice Inspection Summary Report ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter ML24191A4652024-07-0909 July 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24177A0282024-06-25025 June 2024 Emergency Plan Implementing Procedure Revisions ML24176A0222024-06-24024 June 2024 Retraction of Interim Report of a Deviation or Failure to Comply – Transducer Model 8005N ML24089A1152024-06-21021 June 2024 Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) ML24145A0852024-05-30030 May 2024 1B-B Diesel Generator Failure - Final Significance Determination Letter ML24145A1052024-05-29029 May 2024 301 Exam Approval Letter ML24134A1762024-05-13013 May 2024 Submittal of 2023 Annual Radiological Environmental Operating Report CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24128A0352024-05-0707 May 2024 Providing Supplemental Information to Apparent Violation ML24120A0582024-04-26026 April 2024 10 CFR 50.46 Annual Report for Sequoyah Nuclear Plant Units 1 and 2 ML24116A2612024-04-25025 April 2024 Interim Report of a Deviation or Failure to Comply - Transducer Model 8005N ML24114A0482024-04-23023 April 2024 Annual Radioactive Effluent Release Report for 2023 Monitoring Period CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 ML24144A2322024-04-20020 April 2024 Tennessee Multi-Sector Permit (Tmsp), 2024 Annual Discharge Monitoring Report for Outfalls SW-3, SW-3, and SW-9 ML24144A2362024-04-20020 April 2024 Discharge Monitoring Report (Dmr), March 2024 ML24089A0882024-04-18018 April 2024 – Exemption from Select Requirements of 10 CFR Part 73; Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24102A1212024-04-18018 April 2024 Summary of Conference Call with Tennessee Valley Authority Regarding Sequoyah Nuclear Plant, Unit 1 Spring 2024 Steam Generator Tube Inspections CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 2024-09-08
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION November 21, 2008
SUBJECT:
SEQUOYAH NUCLEAR PLANT - NRC EMERGENCY PREPAREDNESS INSPECTION REPORT 05000327/2008501 AND 05000328/2008501
Dear Mr. Campbell,
Jr.:
On October 17, 2008, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Sequoyah Nuclear Plant, Units 1 and 2. The enclosed inspection report documents the inspection results, which were discussed on October 16, 2008, with Mr. T. Cleary and other members of his 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, its enclosure, and your response, if any, will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Brian Bonser, Chief Plant Support Branch 1 Division of Reactor Safety Docket No.: 50-327, 50-328 License No.: DPR-77, DPR-79
Enclosure:
Inspection Report 05000327/2008501 and 05000328/2008501 w/Attachment:
Supplemental Information (
REGION II==
Docket Nos.: 05000327, 05000328 License Nos.: DPR-77, DPR-79 Report No.: 05000327/2008501 and 05000328/2008501 Licensee: Tennessee Valley Authority Facility: Sequoyah Nuclear Plant, Units 1 and 2 Location: Soddy-Daisy, TN Dates: October 13, 2008 through October 17, 2008 Inspectors: Lee Miller, Senior Emergency Preparedness Inspector Bob Holbrook, Emergency Preparedness Inspector Rick Baldwin, Senior Operations Engineer Approved by: Brian Bonser, Chief Plant Support Branch 1 Division of Reactor Safety Attachment
SUMMARY OF FINDINGS
IR 05000327/2008-501 and 05000328/2008-501; 10/13/2008 - 10/17/2008; Sequoyah Nuclear
Plant, Units 1 and 2; Emergency Preparedness Baseline Inspection The report covered an announced inspection by two regional emergency preparedness inspectors and an operations engineer. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, AReactor Oversight Process,@ Revision 3, dated July 2000.
NRC-Identified and Self-Revealing Findings
No findings of significance were identified.
Licensee-Identified Violations
.
None.
Attachment
REPORT DETAILS
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 October 15, 2008, 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 address 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), Operations Support Center (OSC) and Central Emergency Control Center (CECC).
- 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 process and the presentation to the licensee's senior management conducted on October 16, 2008, 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 and Emergency Plan Changes
a. Inspection Scope
Since the last NRC inspection of this program area, Revisions 87 and 88 of Tennessee Valley Authority Nuclear Radiological Emergency Plan were implemented based on the licensees determination, in accordance with 10 CFR 50.54(q), that the changes resulted in no decrease in the effectiveness of the Plan, and that the revised Plan continued to meet the requirements of 10 CFR 50.47(b) and Appendix E to 10 CFR Part 50. The inspectors conducted a sampling review of the Plan changes and implementing procedure changes made between June 1, 2007 and September 30, 2008 to evaluate for potential decreases in effectiveness of the Plan. However, this review was not documented in a Safety Evaluation Report and does not constitute formal NRC approval of the changes. Therefore, these changes remain subject to future NRC inspection in their entirety.
The inspection was conducted in accordance with NRC Inspection Procedure 71114, 04, AEmergency Action Level and Emergency Plan Changes.@ The applicable planning standard (PS), 10 CFR 50.47(b)
- (4) and its related 10 CFR 50, Appendix E requirements were used as reference criteria.
The inspectors reviewed various documents which are listed in the Attachment to this report. This inspection activity satisfied one inspection sample for the emergency action level and emergency plan changes on an annual basis.
b. Findings
No findings of significance were identified.
OTHER ACTIVITIES
4OA1 Performance Indicator Verification
a. Inspection Scope
Cornerstone: Emergency Preparedness
The inspectors sampled licensee submittals for three Performance Indicators (PI) listed below. For each of the submittals reviewed, the inspectors reviewed the period from April 1, 2007 through June 30, 2008. To verify the accuracy of the PI data reported during that period, PI definitions and guidance contained in Nuclear Energy Institute (NEI) 99-02, ARegulatory Assessment Indicator Guideline,@ Revision 5, were used to verify the basis in reporting for each data element.
$ Emergency Response Organization Drill/Exercise Performance (DEP)
$ Emergency Response Organization Readiness (ERO)
$ Alert and Notification System Reliability (ANS)
The inspectors reviewed portions of the raw PI data developed from monthly performance indicator reports and discussed the methods for compiling and reporting the PIs with cognizant emergency preparedness personnel. The inspectors also independently screened drill and exercise opportunity evaluations, drill participation reports, and drill evaluations. Selected reported values were calculated to verify their accuracy. The inspectors compared graphical representations from the most recent PI report to the raw data to verify that the data was correctly reflected in the report.
Reviewed documents are listed in the Attachment to this report.
b. Findings
No findings of significance were identified.
4OA5 Other Activities
Drill/Exercise Performance Indicator, Program Review The inspectors completed Temporary Instruction TI 2515/175, Emergency Response Organization, Drill/Exercise Performance Indicator, Program Review. Appropriate documentation of the results was provided to NRC, HQ, as required by the TI. This completes the Region II inspection requirements for this TI for Sequoyah Nuclear Power Plant.
4OA6 Meetings, including Exit
On October 16, 2008, the lead inspector presented the inspection results to Mr. T.
Cleary and other members of your staff. The inspectors confirmed that proprietary information was not provided during the inspection.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee personnel
- T. Cleary, Site Vice President
- C. Church, Plant Manager
- B. Marks, Corporate Emergency Preparedness Manager
- R. Thompson, Emergency Preparedness Manager
- R. Proffitt, Licensing Engineer
LIST OF DOCUMENTS REVIEWED