|
|
| (32 intermediate revisions by the same user not shown) |
| Line 3: |
Line 3: |
| | issue date = 09/02/2014 | | | issue date = 09/02/2014 |
| | title = Mid-Cycle Assessment Letter for Sequoyah, Units 1 and 2, Inspection Report 05000327/2014006, 05000328/2014003 | | | title = Mid-Cycle Assessment Letter for Sequoyah, Units 1 and 2, Inspection Report 05000327/2014006, 05000328/2014003 |
| | author name = Bartley J H | | | author name = Bartley J |
| | author affiliation = NRC/RGN-II/DRP/RPB6 | | | author affiliation = NRC/RGN-II/DRP/RPB6 |
| | addressee name = Shea J W | | | addressee name = Shea J |
| | 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 eptember 2, 2014 |
| [[Issue date::September 2, 2014]]
| |
|
| |
|
| Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 3D-C Chattanooga, TN 37402-2801
| | ==SUBJECT:== |
| | MID-CYCLE ASSESSMENT LETTER FOR SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2, NRC INSPECTION REPORT 05000327/2014006, 05000328/2014006 |
|
| |
|
| SUBJECT: MID-CYCLE ASSESSMENT LETTER FOR SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2, NRC INSPECTION REPORT 05000327/2014006, 05000328/2014006
| | ==Dear Shea:== |
| | On August 14, 2014, the NRC completed its mid-cycle performance review of the Sequoyah Nuclear Plant Units 1 and 2. The NRC reviewed the most recent quarterly performance indicators (PIs) in addition to inspection results and enforcement actions from July 1, 2013, through June 30, 2014. This letter informs you of the NRCs assessment of your facility during this period and its plans for future inspections at your facility. |
| | |
| | The NRC determined the performance at the Sequoyah Nuclear Plant Units 1 and 2 during the most recent quarter was within the Licensee Response Column of the NRCs Reactor Oversight Process (ROP) Action Matrix because all inspection findings had very low (i.e., green) safety significance, and all PIs indicated that your performance was within the nominal, expected range (i.e., green). Therefore, the NRC plans to conduct ROP baseline inspections at your facility. |
| | |
| | The NRC determined that the performance at Sequoyah Nuclear Plant Units 1 and 2 during the fourth quarter of 2013 was within the Degraded Cornerstone Column of the NRCs Reactor Oversight Process (ROP) Action Matrix because of one or more greater-than-green Security Cornerstone input and two White findings in the Mitigating Systems Cornerstone in the first quarter of 2013. |
| | |
| | On September 27, 2013, the NRC completed a supplemental inspection in accordance with Inspection Procedure 95001, Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area. The NRC determined that the inspection objectives of inspection procedure (IP) 95001 have been satisfied and the Greater than Green security finding is was closed. |
| | |
| | On December 13, 2013, the NRC completed a supplemental inspection in accordance with Inspection Procedure 95002, Supplemental Inspection for One Degraded Cornerstone or Any Three White Inputs in a Strategic Performance Area. Based on the results of this inspection, the NRC determined that your staff adequately addressed the causes for both White findings. |
| | |
| | Therefore, both findings were closed and Sequoyah Units 1 and 2, transitioned to the Licensee Response Column of the NRCs ROP Action Matrix on January 1, 2014. |
| | |
| | J. Shea 2 The NRC identified a cross-cutting theme in the Evaluation component of the Problem Identification and Resolution Area (P.2). Specifically, four findings with the P.2 cross-cutting aspect were identified during the assessment period. The NRC determined that a substantive cross-cutting issue (SCCI) associated with P.2 the cross-cutting aspect does not exist because the NRC does not have a concern with your staffs scope of effort and progress in addressing the cross-cutting theme. This is based on a review of the root cause conducted by your staff and consideration that the corrective action program needs a reasonable amount of time to incorporate these issues into corrective actions. The NRC will continue to monitor your staffs effort and progress in addressing the theme until the theme criteria are no longer met. |
|
| |
|
| ==Dear Shea:==
| | The enclosed inspection plan lists the inspections scheduled through December 31, 2014. |
| On August 14, 2014, the NRC completed its mid-cycle performance review of the Sequoyah Nuclear Plant Units 1 and 2. The NRC reviewed the most recent quarterly performance indicators (PIs) in addition to inspection results and enforcement actions from July 1, 2013, through June 30, 2014. This letter informs you of the NRC's assessment of your facility during this period and its plans for future inspections at your facility. The NRC determined the performance at the Sequoyah Nuclear Plant Units 1 and 2 during the most recent quarter was within the Licensee Response Column of the NRC's Reactor Oversight Process (ROP) Action Matrix because all inspection findings had very low (i.e., green) safety significance, and all PIs indicated that your performance was within the nominal, expected range (i.e., green). Therefore, the NRC plans to conduct ROP baseline inspections at your facility.
| |
|
| |
|
| The NRC determined that the performance at Sequoyah Nuclear Plant Units 1 and 2 during the fourth quarter of 2013 was within the Degraded Cornerstone Column of the NRC's Reactor Oversight Process (ROP) Action Matrix because of one or more greater-than-green Security Cornerstone input and two White findings in the Mitigating Systems Cornerstone in the first quarter of 2013. On September 27, 2013, the NRC completed a supplemental inspection in accordance with Inspection Procedure 95001, "Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area." The NRC determined that the inspection objectives of inspection procedure (IP) 95001 have been satisfied and the Greater than Green security finding is was closed. On December 13, 2013, the NRC completed a supplemental inspection in accordance with Inspection Procedure 95002, "Supplemental Inspection for One Degraded Cornerstone or Any Three White Inputs in a Strategic Performance Area." Based on the results of this inspection, the NRC determined that your staff adequately addressed the causes for both White findings. Therefore, both findings were closed and Sequoyah Units 1 and 2, transitioned to the Licensee Response Column of the NRC's ROP Action Matrix on January 1, 2014.
| | Routine inspections performed by resident inspectors are not included in the inspection plan. |
|
| |
|
| J. Shea 2 The NRC identified a cross-cutting theme in the Evaluation component of the Problem Identification and Resolution Area (P.2). Specifically, four findings with the P.2 cross-cutting aspect were identified during the assessment period. The NRC determined that a substantive cross-cutting issue (SCCI) associated with P.2 the cross-cutting aspect does not exist because the NRC does not have a concern with your staff's scope of effort and progress in addressing the cross-cutting theme. This is based on a review of the root cause conducted by your staff and consideration that the corrective action program needs a reasonable amount of time to incorporate these issues into corrective actions. The NRC will continue to monitor your staff's effort and progress in addressing the theme until the theme criteria are no longer met.
| | The inspections listed during the last nine months of the inspection plan are tentative and may be revised at the end-of-cycle performance review. The NRC provides the inspection plan to allow for the resolution of any scheduling conflicts and personnel availability issues. The NRC will contact you as soon as possible to discuss changes to the inspection plan should circumstances warrant any changes. This inspection plan does not include security related inspections, which will be sent via separate, non-publicly available correspondence. |
|
| |
|
| The enclosed inspection plan lists the inspections scheduled through December 31, 2014. Routine inspections performed by resident inspectors are not included in the inspection plan. The inspections listed during the last nine months of the inspection plan are tentative and may be revised at the end-of-cycle performance review. The NRC provides the inspection plan to allow for the resolution of any scheduling conflicts and personnel availability issues. The NRC will contact you as soon as possible to discuss changes to the inspection plan should circumstances warrant any changes. This inspection plan does not include security related inspections, which will be sent via separate, non-publicly available correspondence. In addition to the ROP baseline inspections at your facility, we also plan on conducting infrequently performed inspections which include: Problem Identification and Resolution, Modifications Inspection, Triennial Heat Sink Inspection, and IP 92702 inspection for follow-up of the December 22, 2009, Confirmatory Order. In response to the accident at Fukushima, the Commission issued Order EA-12-049, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events," which requires licensees to develop, implement, and maintain guidance and strategies to maintain or restore core cooling, containment, and spent fuel pool cooling capabilities following a beyond-design-basis external event. Additionally, the Commission issued Order EA-12-051, "Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation," which requires licensees to have a reliable means of remotely monitoring wide-range Spent Fuel Pool levels to support effective prioritization of event mitigation and recovery actions in the event of a beyond-design-basis external event. The NRC is conducting audits of licensee efforts towards compliance with these Orders. This audit includes an onsite component in order for the NRC to evaluate licensee plans for complying with the Orders, as described in site-specific submittals, and to receive and review information relative to associated open items. This onsite activity will occur in the months prior to a declaration of compliance for the first unit at each site, and will aid staff in development of an ultimate Safety Evaluation for the site. The date for the onsite component at your site is being coordinated with your staff. The onsite component at your site is scheduled to begin December 1, 2014. A site-specific audit plan for the visit will be provided in advance to allow sufficient time for preparations.
| | In addition to the ROP baseline inspections at your facility, we also plan on conducting infrequently performed inspections which include: Problem Identification and Resolution, Modifications Inspection, Triennial Heat Sink Inspection, and IP 92702 inspection for follow-up of the December 22, 2009, Confirmatory Order. |
|
| |
|
| In accordance with 10 CFR 2.390 of the NRC's Rules of Practice, a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). | | In response to the accident at Fukushima, the Commission issued Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, which requires licensees to develop, implement, and maintain guidance and strategies to maintain or restore core cooling, containment, and spent fuel pool cooling capabilities following a beyond-design-basis external event. Additionally, the Commission issued Order EA-12-051, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation, which requires licensees to have a reliable means of remotely monitoring wide-range Spent Fuel Pool levels to support effective prioritization of event mitigation and recovery actions in the event of a beyond-design-basis external event. The NRC is conducting audits of licensee efforts towards compliance with these Orders. This audit includes an onsite component in order for the NRC to evaluate licensee plans for complying with the Orders, as described in site-specific submittals, and to receive and review information relative to associated open items. This onsite activity will occur in the months prior to a declaration of compliance for the first unit at each site, and will aid staff in development of an ultimate Safety Evaluation for the site. The date for the onsite component at your site is being coordinated with your staff. |
|
| |
|
| J. Shea 3 Please contact me at 404-997-4607 with any questions you have regarding this letter.
| | The onsite component at your site is scheduled to begin December 1, 2014. A site-specific audit plan for the visit will be provided in advance to allow sufficient time for preparations. |
|
| |
|
| Sincerely,/RA/
| | In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). |
| Jonathan H. Bartley, Chief Reactor Projects Branch 6 Division of Reactor Projects Docket Nos. 50-327, 50-328 License Nos. DPR-77, DPR-79
| |
|
| |
|
| ===Enclosure:===
| | J. Shea 3 Please contact me at 404-997-4607 with any questions you have regarding this letter. |
| Sequoyah Inspection/Activity Plan (09/01/2014 - 12/31/2015)
| |
| cc distribution via ListServ J. Shea 3 Please contact me at 404-997-4607 with any questions you have regarding this letter.
| |
|
| |
|
| Sincerely,/RA/ | | Sincerely, |
| Jonathan H. Bartley, Chief Reactor Projects Branch 6 Division of Reactor Projects Docket Nos. 50-327, 50-328 License Nos. DPR-77, DPR-79 | | /RA/ |
| | Jonathan H. Bartley, Chief Reactor Projects Branch 6 Division of Reactor Projects Docket Nos. 50-327, 50-328 License Nos. DPR-77, DPR-79 Enclosure: Sequoyah Inspection/Activity Plan (09/01/2014 - 12/31/2015) |
| | cc distribution via ListServ |
|
| |
|
| ===Enclosure:===
| | _________________________ SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII:DRP RII:DR SIGNATURE JDH /RA/ JHB /RA/ |
| Sequoyah Inspection/Activity Plan (09/01/2014 - 12/31/2015)
| | NAME JHamman JBartley DATE 08/27/2014 08/26/2014 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO |
| cc distribution via ListServ
| |
|
| |
|
| PUBLICLY AVAILABLE NON-PUBLICLY AVAILABLE SENSITIVE NON-SENSITIVE ADAMS: Yes ACCESSION NUMBER:_________________________ SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII:DRP RII:DR SIGNATURE JDH /RA/ JHB /RA/ NAME JHamman JBartley DATE 08/27/2014 08/26/2014 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO OFFICIAL RECORD COPY DOCUMENT NAME: S:\DRP\PERIODIC ASSESSMENTS & REPORTS\EOC & MID-CYCLE\2014\MID-CYCLE\ADMIN WORKING FOLDER\LETTERS\SEQUOYAH 2014 MID CYCLE.DOCX J. Shea 4 Letter to Joseph W. Shea from Jonathan H. Bartley dated September 2, 2014
| | J. Shea 4 Letter to Joseph W. Shea from Jonathan H. Bartley dated September 2, 2014 SUBJECT: MID-CYCLE ASSESSMENT LETTER FOR SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2, NRC INSPECTION REPORT 05000327/2014006, 05000328/2014006 DISTRIBUTION: |
| | D. Gamberoni, RII L. Douglas, RII OE Mail RIDSNRRDIRS PUBLIC R. Pascarelli, NRR RidsNrrPMSequoyah Resource ROP Assessment ROP Reports Institute of Nuclear Power Operations (INPO) |
|
| |
|
| SUBJECT: MID-CYCLE ASSESSMENT LETTER FOR SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2, NRC INSPECTION REPORT 05000327/2014006, 05000328/2014006 DISTRIBUTION: D. Gamberoni, RII L. Douglas, RII OE Mail RIDSNRRDIRS PUBLIC R. Pascarelli, NRR RidsNrrPMSequoyah Resource ROP Assessment ROP Reports Institute of Nuclear Power Operations (INPO)
| | Page 1 of 2 Sequoyah 09/02/2014 09:42:29 Inspection / Activity Plan Report 22 09/01/2014 - 12/31/2015 Unit Planned Dates No. of Staff Number Start End Inspection Activity Title on Site EP - EP EXERCISE 3 1, 2 11/17/2014 11/21/2014 IP 7111404 Emergency Action Level and Emergency Plan Changes 1, 2 11/17/2014 11/21/2014 IP 7111407 Exercise Evaluation - Hostile Action (HA) Event 1, 2 11/17/2014 11/21/2014 IP 71151 Performance Indicator Verification OL RQ - REQUAL INSP 2 1, 2 12/01/2014 12/05/2014 IP 7111111B Licensed Operator Requalification Program RP - RP PUBLIC RAD SAFETY BASELINE 2 1, 2 01/26/2015 01/30/2015 IP 71124.06 Radioactive Gaseous and Liquid Effluent Treatment 1, 2 01/26/2015 01/30/2015 IP 71124.07 Radiological Environmental Monitoring Program 1, 2 01/26/2015 01/30/2015 IP 71151 Performance Indicator Verification OL EXAM - INITIAL LICENSE EXAM PREP 3 1 02/02/2015 02/06/2015 V23432 SEQUOYAH/MARCH 2015 INITIAL EXAM AT POWER FACILITIES OL EXAM - INITIAL LICENSE EXAM 3 1 03/02/2015 03/27/2015 V23432 SEQUOYAH/MARCH 2015 INITIAL EXAM AT POWER FACILITIES ISI - UNIT 1 IN-SERVICE INSPECTION & RVH EXAM 2 1 04/20/2015 04/24/2015 IP 7111108P Inservice Inspection Activities - PWR SGISI - UNIT 1 SG IN-SERVICE INSPECTION 1 1 04/27/2015 05/01/2015 IP 7111108P Inservice Inspection Activities - PWR PI&R - PROBLEM IDENTIFICATION AND RESOLUTION 4 1, 2 06/08/2015 06/12/2015 IP 71152B Problem Identification and Resolution 1, 2 06/22/2015 06/26/2015 IP 71152B Problem Identification and Resolution MODS - PLANT MODIFICATION INSPECTION 6 1, 2 07/13/2015 07/17/2015 IP 7111117T Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications 1, 2 07/27/2015 07/31/2015 IP 7111117T Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications HS - TRIENNIAL HEAT SINK PERFORMANCE 1 1, 2 07/20/2015 07/24/2015 IP 7111107T Heat Sink Performance EP - EP PROGRAM INSPECTION 2 1, 2 11/02/2015 11/06/2015 IP 7111402 Alert and Notification System Testing 1, 2 11/02/2015 11/06/2015 IP 7111403 Emergency Preparedness Organization Staffing and Augmentation System 1, 2 11/02/2015 11/06/2015 IP 7111404 Emergency Action Level and Emergency Plan Changes 1, 2 11/02/2015 11/06/2015 IP 7111405 Correction of Emergency Preparedness Weaknesses and Deficiencies 1, 2 11/02/2015 11/06/2015 IP 71151 Performance Indicator Verification This report does not include INPO and OUTAGE activities. Enclosure This report shows only on-site and announced inspection procedures. |
| Page 1 of 209/02/201409:42:29Report 22UnitNumberPlanned DatesStart EndInspection ActivityTitleNo. of Staffon SiteSequoyahInspection / Activity Plan09/01/2014-12/31/2015EP-EP EXERCISE31,2 IPEmergency Action Level and Emergency Plan Changes711140411/17/201411/21/20141,2 IPExercise Evaluation - Hostile Action (HA) Event711140711/17/201411/21/20141,2 IPPerformance Indicator Verification7115111/17/201411/21/2014OL RQ-REQUAL INSP21,2 IPLicensed Operator Requalification Program7111111B12/01/201412/05/2014RP-RP PUBLIC RAD SAFETY BASELINE21,2 IPRadioactive Gaseous and Liquid Effluent Treatment71124.0601/26/201501/30/20151,2 IPRadiological Environmental Monitoring Program71124.0701/26/201501/30/20151,2 IPPerformance Indicator Verification7115101/26/201501/30/2015OL EXAM-INITIAL LICENSE EXAM PREP31 SEQUOYAH/MARCH 2015 INITIAL EXAM AT POWER FACILITIESV2343202/02/201502/06/2015OL EXAM-INITIAL LICENSE EXAM31 SEQUOYAH/MARCH 2015 INITIAL EXAM AT POWER FACILITIESV2343203/02/201503/27/2015ISI-UNIT 1 IN-SERVICE INSPECTION & RVH EXAM21 IPInservice Inspection Activities - PWR7111108P04/20/201504/24/2015SGISI-UNIT 1 SG IN-SERVICE INSPECTION11 IPInservice Inspection Activities - PWR7111108P04/27/201505/01/2015PI&R-PROBLEM IDENTIFICATION AND RESOLUTION41,2 IPProblem Identification and Resolution71152B06/08/201506/12/20151,2 IPProblem Identification and Resolution71152B06/22/201506/26/2015MODS-PLANT MODIFICATION INSPECTION61,2 IPEvaluations of Changes, Tests, and Experiments and Permanent Plant Modifications7111117T07/13/201507/17/20151,2 IPEvaluations of Changes, Tests, and Experiments and Permanent Plant Modifications7111117T07/27/201507/31/2015HS-TRIENNIAL HEAT SINK PERFORMANCE11,2 IPHeat Sink Performance7111107T07/20/201507/24/2015EP-EP PROGRAM INSPECTION21,2 IPAlert and Notification System Testing711140211/02/201511/06/20151,2 IPEmergency Preparedness Organization Staffing and Augmentation System711140311/02/201511/06/20151,2 IPEmergency Action Level and Emergency Plan Changes711140411/02/201511/06/20151,2 IPCorrection of Emergency Preparedness Weaknesses and Deficiencies711140511/02/201511/06/20151,2 IPPerformance Indicator Verification7115111/02/201511/06/2015This report does not include INPO and OUTAGE activities. This report shows only on-site and announced inspection procedures. | |
|
| |
|
| Page 2 of 209/02/201409:42:29Report 22UnitNumberPlanned DatesStart EndInspection ActivityTitleNo. of Staffon SiteSequoyahInspection / Activity Plan09/01/2014-12/31/2015RP-RAD HAZARDS ANALYSIS AND TRANSPORTATION21,2 IPRadiological Hazard Assessment and Exposure Controls71124.0111/02/201511/06/20151,2 IPRadioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation71124.0811/02/201511/06/20151,2 IPPerformance Indicator Verification7115111/02/201511/06/2015ISI-UNIT 2 IN-SERVICE INSPECTION1 2 IPInservice Inspection Activities - PWR7111108P11/09/201511/13/2015SGISI-UNIT 2 SG IN-SERVICE INSPECTION1 2 IPInservice Inspection Activities - PWR7111108P11/16/201511/20/2015This report does not include INPO and OUTAGE activities. This report shows only on-site and announced inspection procedures. | | Page 2 of 2 Sequoyah 09/02/2014 09:42:29 Inspection / Activity Plan Report 22 09/01/2014 - 12/31/2015 Unit Planned Dates No. of Staff Number Start End Inspection Activity Title on Site RP - RAD HAZARDS ANALYSIS AND TRANSPORTATION 2 1, 2 11/02/2015 11/06/2015 IP 71124.01 Radiological Hazard Assessment and Exposure Controls 1, 2 11/02/2015 11/06/2015 IP 71124.08 Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation 1, 2 11/02/2015 11/06/2015 IP 71151 Performance Indicator Verification ISI - UNIT 2 IN-SERVICE INSPECTION 1 2 11/09/2015 11/13/2015 IP 7111108P Inservice Inspection Activities - PWR SGISI - UNIT 2 SG IN-SERVICE INSPECTION 1 2 11/16/2015 11/20/2015 IP 7111108P Inservice Inspection Activities - PWR This report does not include INPO and OUTAGE activities. Enclosure This report shows only on-site and announced inspection procedures. |
| }} | | }} |
|
|---|
Category:Inspection Plan
MONTHYEARML24152A1542024-05-31031 May 2024
Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2024-03
ML24059A4052024-02-28028 February 2024
Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2024-02
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 05000327/20220062023-03-0101 March 2023
Annual Assessment Letter for Sequoyah Nuclear Plant, Units 1 and 2 Report 05000327/2022006 and 05000328/2022006
ML23026A0282023-01-12012 January 2023
001 Radiation Safety Baseline Inspection Information Request
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 05000327/20210062022-03-0202 March 2022
Annual Assessment Letter for Sequoyah Nuclear Plant, Units 1 and 2 - (Report No. 05000327/2021006 and 05000328/2021006)
ML21160A0352021-06-0303 June 2021
Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2021-03
ML21092A0972021-04-0202 April 2021
Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection
ML20259A4782020-09-15015 September 2020
Emergency Preparedness Program Inspection Request for Information
IR 05000327/20200052020-08-18018 August 2020
Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2020005 and 05000328/2020005
ML20227A0082020-08-14014 August 2020
Requalification Program Inspection - Sequoyah Nuclear Plant
ML19324E9992019-11-20020 November 2019
2020 SQN - POV Inspection Information Request - Rev. 1
ML19235A1972019-08-23023 August 2019
ISI 2019004 RFI Ajb
ML19063D0842019-03-0404 March 2019
Annual Assessment Letter for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2018006 and 05000328/2018006
IR 05000327/20180062019-03-0404 March 2019
Annual Assessment Letter for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2018006 and 05000328/2018006
ML18283A6232018-09-25025 September 2018
04 RP Inspection Document Request
ML18240A3602018-08-24024 August 2018
Requalification Program Inspection
ML18172A1182018-06-21021 June 2018
Notification of Inspection and Request for Information
ML18059A1432018-02-28028 February 2018
EOC Assessment Letter
ML18058B1632018-02-27027 February 2018
Emailed U1 ISI 2018002 RFI - Bcc
IR 05000327/20170052017-08-24024 August 2017
Updated Inspection Plan for Sequoyah Updated Inspection Plant Units 1 and 2, Report 05000327/2017005 and 05000328/2017005
ML17146A1002017-05-25025 May 2017
Notification of Inspection and Request for Documents Dated May 25, 2017
ML17107A2602017-04-17017 April 2017
Notification of Inspection and Request for Information for NRC PI&R
ML17115A4452017-04-17017 April 2017
Emergency Preparedness Inspection and Request for Information
ML17067A4792017-03-0707 March 2017
Notification of Inspection and Request for Documents
IR 05000327/20160062017-03-0101 March 2017
Annual Assessment Letter for Sequoyah Nuclear Plant, Units 1 & 2 (Report 05000327/2016006 and 05000328/2016006)
ML16286A0622016-10-0606 October 2016
Notification of Inspection and Request for Information
IR 05000327/20160052016-08-31031 August 2016
Mid-Cycle Assessment Letter for Sequoyah Nuclear Plant Units 1 and 2, NRC Inspection Report 05000327/2016005, 05000328/2016005
ML16076A0612016-03-15015 March 2016
Notification of Sequoyah Nuclear Plant - Component Design Bases Inspection - NRC Inspection Report 05000327/2016007, 05000328/2016007
ML16062A2622016-03-0202 March 2016
Annual Assessment Letter
IR 05000327/20150052015-09-0101 September 2015
Mid-Cycle Assessment Letter for the Sequoyah Nuclear Plant Units 1 and 2, NRC Inspection Report 005000327/2015005, 005000328/2015005
ML15084A4022015-03-25025 March 2015
Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection
IR 05000327/20140012015-03-0404 March 2015
Annual Assessment Letter for Sequoyah Nuclear Plant Units 1 and 2, NRC Inspection Report 05000327/2014001, 05000328/2014001
IR 05000327/20140062014-09-0202 September 2014
Mid-Cycle Assessment Letter for Sequoyah, Units 1 and 2, Inspection Report 05000327/2014006, 05000328/2014003
ML14245A1212014-09-0202 September 2014
Mid-Cycle Assessment Letter for Sequoyah, Units 1 and 2, Inspection Report 05000327/2014006, 05000328/2014003
ML14072A0352014-03-10010 March 2014
Notification of Inspection and Request for Information
ML14063A2472014-03-0404 March 2014
2013 Annual Assessment Letter for Sequoyah Nuclear Plant Units 1 and 2
ML13297A0732013-10-23023 October 2013
IR 05000327-14-007 & 05000328-14-007.Sequoyah Nuclear Plant, Units 1 & 2, Notification of a Triennial Fire Protection Baseline Inspection
ML13246A1952013-09-0303 September 2013
Mid Cycle Assessment Letter
IR 05000327/20120012013-03-0404 March 2013
Annual Assessment Letter for Sequoyah Nuclear Plant Units 1 and 2 (Report 05000327/2012001 and 05000328/2012001)
ML12248A1042012-09-0404 September 2012
Mid Cycle Assessment Letter Sequoyah 2012
IR 05000327/20120062012-09-0404 September 2012
Mid Cycle Assessment Letter Sequoyah 2012
ML12065A3292012-03-0505 March 2012
RPT 22, Inspection/Activity Plan
IR 05000382/20120012012-03-0505 March 2012
Annual Assessment Letter for Waterford Steam Electric Station-Unit 3 (Report 05000382-12-001)
ML1124401842011-09-0101 September 2011
Inspection/Activity Report 22, 09/01/2011 - 12/31/2012
ML1106303542011-03-0404 March 2011
Inspection / Activity Plan, Report 22
ML1024408442010-09-0101 September 2010
Report 22 Inspection/Activity Plan 09/01/2010 - 12/31/2011
ML1006209872010-03-0303 March 2010
Inspection/Activity Plan 03/01/2010 - 06/30/2011
ML0924406512009-09-0101 September 2009
Inspection/Activity Plan 03/01/2009 - 12/31/2010
2024-05-31
[Table view]
Category:Letter
MONTHYEARML24298A1172024-10-24024 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-24-060, 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
CNL-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024
Decommitment of Flood Mode Mitigation Improvement Systems
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
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
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
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-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024
Hydrologic Engineering Center River Analysis System Project Milestone Status Update
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
IR 05000327/20240012024-04-17017 April 2024
Integrated Inspection Report 05000327/2024001 and 05000328/2024001
ML24109A0272024-04-16016 April 2024
Cycle 27 Core Operating Limits Report Revision 0
CNL-23-006, Application to Modify Technical Specifications 3.8.1, AC Sources – Operating, and 3.8.2, AC Sources – Shutdown, for Sequoyah Nuclear Plant (SQN-TSC-22-03)2024-04-15015 April 2024
Application to Modify Technical Specifications 3.8.1, AC Sources – Operating, and 3.8.2, AC Sources – Shutdown, for Sequoyah Nuclear Plant (SQN-TSC-22-03)
ML24106A0502024-04-12012 April 2024
Discharge Monitoring Report (Dmr), February 2024
ML24100A0162024-04-11011 April 2024
Request for Regulatory Conference (Tennessee Valley Authority - Sequoyah Nuclear Plant)
CNL-24-020, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements2024-04-0101 April 2024
Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements
2024-09-08
[Table view] |
Text
UNITED STATES eptember 2, 2014
SUBJECT:
MID-CYCLE ASSESSMENT LETTER FOR SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2, NRC INSPECTION REPORT 05000327/2014006, 05000328/2014006
Dear Shea:
On August 14, 2014, the NRC completed its mid-cycle performance review of the Sequoyah Nuclear Plant Units 1 and 2. The NRC reviewed the most recent quarterly performance indicators (PIs) in addition to inspection results and enforcement actions from July 1, 2013, through June 30, 2014. This letter informs you of the NRCs assessment of your facility during this period and its plans for future inspections at your facility.
The NRC determined the performance at the Sequoyah Nuclear Plant Units 1 and 2 during the most recent quarter was within the Licensee Response Column of the NRCs Reactor Oversight Process (ROP) Action Matrix because all inspection findings had very low (i.e., green) safety significance, and all PIs indicated that your performance was within the nominal, expected range (i.e., green). Therefore, the NRC plans to conduct ROP baseline inspections at your facility.
The NRC determined that the performance at Sequoyah Nuclear Plant Units 1 and 2 during the fourth quarter of 2013 was within the Degraded Cornerstone Column of the NRCs Reactor Oversight Process (ROP) Action Matrix because of one or more greater-than-green Security Cornerstone input and two White findings in the Mitigating Systems Cornerstone in the first quarter of 2013.
On September 27, 2013, the NRC completed a supplemental inspection in accordance with Inspection Procedure 95001, Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area. The NRC determined that the inspection objectives of inspection procedure (IP) 95001 have been satisfied and the Greater than Green security finding is was closed.
On December 13, 2013, the NRC completed a supplemental inspection in accordance with Inspection Procedure 95002, Supplemental Inspection for One Degraded Cornerstone or Any Three White Inputs in a Strategic Performance Area. Based on the results of this inspection, the NRC determined that your staff adequately addressed the causes for both White findings.
Therefore, both findings were closed and Sequoyah Units 1 and 2, transitioned to the Licensee Response Column of the NRCs ROP Action Matrix on January 1, 2014.
J. Shea 2 The NRC identified a cross-cutting theme in the Evaluation component of the Problem Identification and Resolution Area (P.2). Specifically, four findings with the P.2 cross-cutting aspect were identified during the assessment period. The NRC determined that a substantive cross-cutting issue (SCCI) associated with P.2 the cross-cutting aspect does not exist because the NRC does not have a concern with your staffs scope of effort and progress in addressing the cross-cutting theme. This is based on a review of the root cause conducted by your staff and consideration that the corrective action program needs a reasonable amount of time to incorporate these issues into corrective actions. The NRC will continue to monitor your staffs effort and progress in addressing the theme until the theme criteria are no longer met.
The enclosed inspection plan lists the inspections scheduled through December 31, 2014.
Routine inspections performed by resident inspectors are not included in the inspection plan.
The inspections listed during the last nine months of the inspection plan are tentative and may be revised at the end-of-cycle performance review. The NRC provides the inspection plan to allow for the resolution of any scheduling conflicts and personnel availability issues. The NRC will contact you as soon as possible to discuss changes to the inspection plan should circumstances warrant any changes. This inspection plan does not include security related inspections, which will be sent via separate, non-publicly available correspondence.
In addition to the ROP baseline inspections at your facility, we also plan on conducting infrequently performed inspections which include: Problem Identification and Resolution, Modifications Inspection, Triennial Heat Sink Inspection, and IP 92702 inspection for follow-up of the December 22, 2009, Confirmatory Order.
In response to the accident at Fukushima, the Commission issued Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, which requires licensees to develop, implement, and maintain guidance and strategies to maintain or restore core cooling, containment, and spent fuel pool cooling capabilities following a beyond-design-basis external event. Additionally, the Commission issued Order EA-12-051, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation, which requires licensees to have a reliable means of remotely monitoring wide-range Spent Fuel Pool levels to support effective prioritization of event mitigation and recovery actions in the event of a beyond-design-basis external event. The NRC is conducting audits of licensee efforts towards compliance with these Orders. This audit includes an onsite component in order for the NRC to evaluate licensee plans for complying with the Orders, as described in site-specific submittals, and to receive and review information relative to associated open items. This onsite activity will occur in the months prior to a declaration of compliance for the first unit at each site, and will aid staff in development of an ultimate Safety Evaluation for the site. The date for the onsite component at your site is being coordinated with your staff.
The onsite component at your site is scheduled to begin December 1, 2014. A site-specific audit plan for the visit will be provided in advance to allow sufficient time for preparations.
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
J. Shea 3 Please contact me at 404-997-4607 with any questions you have regarding this letter.
Sincerely,
/RA/
Jonathan H. Bartley, Chief Reactor Projects Branch 6 Division of Reactor Projects Docket Nos. 50-327, 50-328 License Nos. DPR-77, DPR-79 Enclosure: Sequoyah Inspection/Activity Plan (09/01/2014 - 12/31/2015)
cc distribution via ListServ
_________________________ SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII:DRP RII:DR SIGNATURE JDH /RA/ JHB /RA/
NAME JHamman JBartley DATE 08/27/2014 08/26/2014 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO
J. Shea 4 Letter to Joseph W. Shea from Jonathan H. Bartley dated September 2, 2014 SUBJECT: MID-CYCLE ASSESSMENT LETTER FOR SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2, NRC INSPECTION REPORT 05000327/2014006, 05000328/2014006 DISTRIBUTION:
D. Gamberoni, RII L. Douglas, RII OE Mail RIDSNRRDIRS PUBLIC R. Pascarelli, NRR RidsNrrPMSequoyah Resource ROP Assessment ROP Reports Institute of Nuclear Power Operations (INPO)
Page 1 of 2 Sequoyah 09/02/2014 09:42:29 Inspection / Activity Plan Report 22 09/01/2014 - 12/31/2015 Unit Planned Dates No. of Staff Number Start End Inspection Activity Title on Site EP - EP EXERCISE 3 1, 2 11/17/2014 11/21/2014 IP 7111404 Emergency Action Level and Emergency Plan Changes 1, 2 11/17/2014 11/21/2014 IP 7111407 Exercise Evaluation - Hostile Action (HA) Event 1, 2 11/17/2014 11/21/2014 IP 71151 Performance Indicator Verification OL RQ - REQUAL INSP 2 1, 2 12/01/2014 12/05/2014 IP 7111111B Licensed Operator Requalification Program RP - RP PUBLIC RAD SAFETY BASELINE 2 1, 2 01/26/2015 01/30/2015 IP 71124.06 Radioactive Gaseous and Liquid Effluent Treatment 1, 2 01/26/2015 01/30/2015 IP 71124.07 Radiological Environmental Monitoring Program 1, 2 01/26/2015 01/30/2015 IP 71151 Performance Indicator Verification OL EXAM - INITIAL LICENSE EXAM PREP 3 1 02/02/2015 02/06/2015 V23432 SEQUOYAH/MARCH 2015 INITIAL EXAM AT POWER FACILITIES OL EXAM - INITIAL LICENSE EXAM 3 1 03/02/2015 03/27/2015 V23432 SEQUOYAH/MARCH 2015 INITIAL EXAM AT POWER FACILITIES ISI - UNIT 1 IN-SERVICE INSPECTION & RVH EXAM 2 1 04/20/2015 04/24/2015 IP 7111108P Inservice Inspection Activities - PWR SGISI - UNIT 1 SG IN-SERVICE INSPECTION 1 1 04/27/2015 05/01/2015 IP 7111108P Inservice Inspection Activities - PWR PI&R - PROBLEM IDENTIFICATION AND RESOLUTION 4 1, 2 06/08/2015 06/12/2015 IP 71152B Problem Identification and Resolution 1, 2 06/22/2015 06/26/2015 IP 71152B Problem Identification and Resolution MODS - PLANT MODIFICATION INSPECTION 6 1, 2 07/13/2015 07/17/2015 IP 7111117T Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications 1, 2 07/27/2015 07/31/2015 IP 7111117T Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications HS - TRIENNIAL HEAT SINK PERFORMANCE 1 1, 2 07/20/2015 07/24/2015 IP 7111107T Heat Sink Performance EP - EP PROGRAM INSPECTION 2 1, 2 11/02/2015 11/06/2015 IP 7111402 Alert and Notification System Testing 1, 2 11/02/2015 11/06/2015 IP 7111403 Emergency Preparedness Organization Staffing and Augmentation System 1, 2 11/02/2015 11/06/2015 IP 7111404 Emergency Action Level and Emergency Plan Changes 1, 2 11/02/2015 11/06/2015 IP 7111405 Correction of Emergency Preparedness Weaknesses and Deficiencies 1, 2 11/02/2015 11/06/2015 IP 71151 Performance Indicator Verification This report does not include INPO and OUTAGE activities. Enclosure This report shows only on-site and announced inspection procedures.
Page 2 of 2 Sequoyah 09/02/2014 09:42:29 Inspection / Activity Plan Report 22 09/01/2014 - 12/31/2015 Unit Planned Dates No. of Staff Number Start End Inspection Activity Title on Site RP - RAD HAZARDS ANALYSIS AND TRANSPORTATION 2 1, 2 11/02/2015 11/06/2015 IP 71124.01 Radiological Hazard Assessment and Exposure Controls 1, 2 11/02/2015 11/06/2015 IP 71124.08 Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation 1, 2 11/02/2015 11/06/2015 IP 71151 Performance Indicator Verification ISI - UNIT 2 IN-SERVICE INSPECTION 1 2 11/09/2015 11/13/2015 IP 7111108P Inservice Inspection Activities - PWR SGISI - UNIT 2 SG IN-SERVICE INSPECTION 1 2 11/16/2015 11/20/2015 IP 7111108P Inservice Inspection Activities - PWR This report does not include INPO and OUTAGE activities. Enclosure This report shows only on-site and announced inspection procedures.
