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{{Adams | |||
| number = ML14245A121 | |||
| issue date = 09/02/2014 | |||
| title = Mid-Cycle Assessment Letter for Sequoyah, Units 1 and 2, Inspection Report 05000327/2014006, 05000328/2014003 | |||
| author name = Bartley J | |||
| author affiliation = NRC/RGN-II/DRP/RPB6 | |||
| addressee name = Shea J | |||
| addressee affiliation = Tennessee Valley Authority | |||
| docket = 05000327, 05000328 | |||
| license number = DPR-077, DPR-079 | |||
| contact person = | |||
| case reference number = IR-2014-003 | |||
| document type = Inspection Plan, Letter | |||
| page count = 7 | |||
}} | |||
See also: [[see also::IR 05000328/2014003]] | |||
=Text= | |||
{{#Wiki_filter:UNITED STATES | |||
NUCLEAR REGULATORY COMMISSION | |||
REGION II | |||
245 PEACHTREE CENTER AVENUE NE, SUITE 1200 | |||
ATLANTA, GEORGIA 30303-1257 | |||
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 | |||
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. | |||
}} |
Revision as of 17:18, 9 March 2020
ML14245A121 | |
Person / Time | |
---|---|
Site: | Sequoyah |
Issue date: | 09/02/2014 |
From: | Bartley J Reactor Projects Region 2 Branch 6 |
To: | James Shea Tennessee Valley Authority |
References | |
IR-2014-003 | |
Download: ML14245A121 (7) | |
See also: IR 05000328/2014003
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
245 PEACHTREE CENTER AVENUE NE, SUITE 1200
ATLANTA, GEORGIA 30303-1257
September 2, 2014
Mr. Joseph W. Shea
Vice President, Nuclear Licensing
Tennessee Valley Authority
Chattanooga, TN 37402-2801
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
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
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
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
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.