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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
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION November 21, 2008
[[Issue date::November 21, 2008]]


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


==Dear Mr. Campbell,==
==Dear Mr. Campbell,==
Jr.:  
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.
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 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.


The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
Line 38: Line 35:
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).


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


===Enclosure:===
===Enclosure:===
Inspection Report 05000327/2008501 and 05000328/2008501  
Inspection Report 05000327/2008501 and 05000328/2008501 w/Attachment:
 
Supplemental Information (
===w/Attachment:===
Supplemental Information  
 
(cc w/encl - See page 2)
 
_________________________ 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
 
Ludwig E. Thibault General Manager Nuclear Oversight & Assistance Tennessee Valley Authority Electronic Mail Distribution
 
Tom Coutu Vice President Nuclear Support Tennessee Valley Authority Electronic Mail Distribution
 
William R. Campbell, Jr.
 
Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
 
Christopher R. Church Plant Manager Sequoyah Nuclear Plant Tennessee Valley Authority Electronic Mail Distribution
 
(Vacant)
Vice President Nuclear Support Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
 
Michael J. Lorek Interim Vice President Nuclear Engineering & Projects Tennessee Valley Authority Electronic Mail Distribution
 
(cc: w/encl - See Page 3)
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
 
General Counsel Tennessee Valley Authority Electronic Mail Distribution
 
Beth A. Wetzel Manager Corporate Licensing Tennessee Valley Authority Electronic Mail Distribution


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
 
Michael A. Purcell Senior Licensing Manager Nuclear Power Group Tennessee Valley Authority Electronic Mail Distribution
 
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
 
James H. Bassham Director Tennessee Emergency Management Agency Electronic Mail Distribution Ann Harris 341 Swing Loop Rockwood, TN 37854
 
TVA 4 Letter to William R. Campbell, Jr. from Brian Bonser dated November 21, 2008
 
SUBJECT: SEQUOYAH NUCLEAR PLANT - NRC EMERGENCY PREPAREDNESS INSPECTION REPORT 05000327/2008501 AND 05000328/2008501 Distribution w/encl:
RIDSNRRDIRS PUBLIC R. Pascarelli, NRR ((Regulatory Conferences Only)) B. Moroney, NRR (PM: SEQ)
 
Attachment U.S. NUCLEAR REGULATORY COMMISSION 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=
=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


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.


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===


===A. NRC-Identified and Self-Revealing Findings===
No findings of significance were identified.


No findings of significance were identified.
===Licensee-Identified Violations===
.
None.


===B. Licensee-Identified Violations===
Attachment
. None.


=REPORT DETAILS=
=REPORT DETAILS=
Line 127: Line 65:
==REACTOR SAFETY==
==REACTOR SAFETY==


===Cornerstone:===
===Cornerstone: Emergency Preparedness===
Emergency Preparedness 1EP1 Exercise Evaluation
 
1EP1 Exercise Evaluation


====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).
 
This inspection activity represents one sample on a biennial cycle.


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.


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.
Line 144: Line 85:
====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


====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.
 
The inspection was conducted in accordance with NRC Inspection Procedure 71114, Attachment 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 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.
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.
Line 164: Line 103:


====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.
 
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 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.


Line 176: Line 116:
====b. Findings====
====b. Findings====
No findings of significance were identified.
No findings of significance were identified.
{{a|4OA5}}
==4OA5 Other Activities==


{{a|4OA5}}
===.1 (Closed) NRC Temporary Instruction (TI) 2525/175, Emergency Response Organization,===
==4OA5 Other Activities==


===.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.


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.
{{a|4OA6}}
{{a|4OA6}}
==4OA6 Meetings, including Exit==
==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.
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:  
ATTACHMENT:  
Line 195: Line 137:


===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


==LIST OF DOCUMENTS REVIEWED==
==LIST OF DOCUMENTS REVIEWED==
1EP1 Exercise Evaluation
===Procedures===
: EPIP-1, Emergency Plan Classification Matrix, Rev.40
: EPIP-3, Alert, Rev. 30
: EPIP-4, Site Area Emergency, Rev. 30
: EPIP-5, General Emergency, Rev. 37 CECC
: EPIP-1, Central Emergency Control Center (CECC) Operations, Rev. 47 CECC
: EPIP-6, CECC Plant Assessment Staff Procedure for Alert, Site Area Emergency, and General Emergency, Rev. 30 CECC
: EPIP-9, Emergency Environmental Radiological Monitoring, Rev. 36
: OPDP-1, Conduct of Operations, Rev. 10 
: Records and Data Documentation packages completed in the Control Room, Technical Support Center, Operations Support Center, Combined Emergency Control Center, Joint Information Center.
: The packages included, but not limited to the following: logs, event notification forms, Protective Action Recommendations, Media releases, Radiological Dose Assessments, Core Damage calculations.
: Corrective Action - Problem Evaluation Report (PER)
: PER 154730
: PER 154738
: PER 154749
: PER 154762
: PER 154766
: PER 154804
: PER 154852
: PER 154855
: PER 154856
: PER 154859
: PER 154860
: PER 154862
: PER 154864
: PER 154865
: PER 154869
: PER 154878
: PER 154879
: PER 154881
: PER 154883
: PER 154888
: PER 154889
: PER 154891
: PER 154892
: PER 154894
: PER 154895
: PER 154898
: PER 154906
: PER 154908
: PER 154909
: PER 154910
: PER 154912
: PER 154914
: PER 154938
: PER 154939 
: 1EP4 Emergency Action Level and Emergency Plan Changes
===Procedures===
: Tennessee Valley Authority Nuclear Radiological Emergency Plan, Rev. 87 and 88
: EPIL-1, Emergency Preparedness Instruction Letter - Procedures, Maps, and Drawings, Rev.
: Plans and Changes packages
: EPIP-6, Activation and Operation of the Technical Support Center, Rev. 43
: EPIP-8, Personnel Accountability and Evacuation, Rev. 17
: EPIP-12, Emergency Equipment and Supplies, Rev. 7
: EPIP-13, Dose Assessment, Rev. 12 and 13
: 4OA1 Performance Indicator Verification
===Procedures===
: EPIL-15, Emergency Preparedness Performance Indicators, Rev. 12
: Records and Data
: ANS data from 3
rd Quarter 2007 to 2
nd Quarter 2008 ERO data from 3
rd Quarter 2007 to 2
nd Quarter 2008 DEP data from 3
rd Quarter 2007 to 2
nd Quarter 2008
==LIST OF ACRONYMS==
: [[ANS]] [[Alert and Notification System]]
: [[CECC]] [[Central Emergency Control Center]]
: [[DEP]] [[Drill/Exercise Performance]]
: [[DHS]] [[Department of Homeland Security]]
: [[ERO]] [[Emergency Response Organization]]
: [[FEMA]] [[Federal Emergency Management Agency]]
: [[NEI]] [[Nuclear Energy Institute]]
: [[OSC]] [[Operations Support Center]]
: [[PI]] [[Performance Indicator]]
: [[PS]] [[Planning Standard]]
: [[RSPS]] [[Risk Significant Planning Standards]]
: [[TI]] [[Temporary Instruction]]
: [[TSC]] [[Technical Support Center]]
: [[STAND]] [[-ALONE INSPECTION]]
: [[REPORT]] [[(]]
: [[NOTE]] [[: E-MAIL]]
: [[COPY]] [[]]
: [[OF]] [[]]
: [[REPORT]] [[]]
: [[WITH]] [[]]
: [[THIS]] [[]]
: [[FORM]] [[)]]
: [[IP]] [[Used Sample Size Completion Status** (for]]
: [[IP]] [[use]]
: [[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]]
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
s conditions require") Complete (by reference) - one or more samples was completed during a different inspection such as
: [[SGRP]] [[or a]]
TI Incomplete - The minimum number of samples was not inspected
**Provide brief explanation if the minimum number of samples were not inspected.
Branch Chief Approval:  Brian Bonser      Date: 11/20/2008


Emailed By:    Karen Hunter        Date: 11/21/2008
}}
}}

Latest revision as of 01:47, 22 December 2019

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
ML083260004
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 11/21/2008
From: Brian Bonser
NRC/RGN-II/DRS/PSB1
To: Campbell W
Tennessee Valley Authority
References
IR-08-501
Download: ML083260004 (13)


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

.1 (Closed) NRC Temporary Instruction (TI) 2525/175, Emergency Response Organization,

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