Issue Date: 02/15/08 71003 - 1 -

NRC INSPECTION MANUAL DLR

INSPECTION PROCEDURE 71003 

POST-APPROVAL SITE INSPECTION FOR LICENSE RENEWAL 

PROGRAM APPLICABILITY: IMC 2515 

71003-01 INSPECTION OBJECTIVES 

01.01 To verify that license conditions added as part of the renewed license, license 

renewal commitments, selected aging management programs, and license renewal 

commitments revised after the renewed license was granted, are implemented in 

accordance with Title 10 of the Code of Federal Regulations (CFR) Part 54, 

“Requirements for the Renewal of Operating Licenses for Nuclear Power Plants.” 

01.02 To verify that “newly identified” systems, structures, and components (SSCs), 

pursuant to 10 CFR 54.37(b), and Regulatory Issue Summary RIS-2007-16, are 

implemented in accordance with 10 CFR Part 54. 

01.03 To verify, on a sample basis, that the description of the aging management 

programs and related activities covered in §01.01 are, or will be, contained in the 

updated final safety analysis report (UFSAR) and that the description of the programs is 

consistent with the programs implemented by the licensee. 

71003-02 INSPECTION REQUIREMENTS 

General Inspection Requirements. The post-renewal inspections (PRI) verify, on a 

sampling basis, that: 

 a. (1) The licensee has completed the necessary actions to comply with the license 

conditions that are a part of the renewed operating license, and has 

implemented the aging management programs and time-limited aging analyses 

(TLAA) included in the staff’s license renewal safety evaluation report (SER). 

(2) The licensee followed the guidance in NEI 99-04 for the license renewal 

commitment change process, including the elimination of commitments, and 

properly evaluated, and reported where necessary, changes to license renewal 

commitments listed in the UFSAR in accordance with 10 CFR 50.59. 
Issue Date: 02/15/08 71003 - 2 -

(3) The licensee has identified, evaluated, and incorporated “newly identified” 

SSCs into the renewed license in accordance with 10 CFR 54.37(b). 

 b. The UFSAR supplement describes the aging management programs and TLAA, 

approved by the NRC in the SER issued with the renewed license. This 

inspection will also verify that the UFSAR description matches the aging 

management program or TLAA being implemented and that changes, caused by 

the inclusion of “newly identified” SSCs, were included in the UFSAR. If the 

licensee has not submitted a UFSAR update since implementing the program or 

TLAA, review the planned UFSAR changes and verify that they are included in 

the an appropriate tracking system. 

71003-03 INSPECTION GUIDANCE 

03.01 General Guidance

 a. The inspection is intended to sample the licensee’s implementation of the 

following license renewal-related activities covered in §01 in the following 

manner: 

 1. Inspectors should familiarize themselves with the requirements and 

guidance relating to license renewal in general. The inspectors should 

familiarize themselves with the specific license renewal application and 

associated SER for the plant being inspected. License renewal 

requirements and guidance documents that should be reviewed prior to an 

inspection include: 

 • 10 CFR Part 54, “Requirements for Renewal of Operating Licenses 

for Nuclear Power Plants” 

 • The statement of consideration published with the revision to 

10 CFR Part 54 in the Federal Register, Vol. 60, No. 88, Monday, 

May 8, 1995, pages 22461 to 22495 

 • The plant-specific renewed license and license conditions 

 • The SERs for the plant(s) to be inspected 

 • Appendix A of the SER 

 2. In selecting samples, consideration should be given to attributes such as: 

 • the risk significance of the commitments, using insights gained from 

sources such as the NRC’s “SDP Risk Informed Inspection 

Notebooks”, Revision 2 

 • the extent of previous license renewal audits and inspections of 

aging management programs 

 • the extent of a commitment 
Issue Date: 02/15/08 71003 - 3 -

 • the extent that baseline inspection programs will inspect an SSC or 

commodity group 

 • the amount of time since the renewed license was granted and 

beginning of the period of extended operation 

 • the results of the one time inspection (e.g., selective leaching 

inspection), to ensure that either there is no aging effect or aging 

effects detected were properly evaluated 

 b. The lead inspector will determine the number and nature of license conditions 

and commitments to be reviewed prior to performing these inspections. The 

sample should include all conditions placed on the license as part of license 

renewal, and as many commitments, which were identified by the staff during 

the course of the application review, as inspection resources will allow. The 

inspection will also include those commitments made by the applicant, which 

were either modified/enhanced or agreed upon by the staff, and selected in 

accordance with the risk guidance given in the above Section 03.01.a. 

The population of license conditions and commitments will be inspected to the 

extent necessary to determine that the license conditions and commitments were 

implemented as described in the SER, that any modification of commitments was 

done in accordance with 10 CFR 50.59 and established commitment 

management guidance, and that prior NRC approval was obtained for changes to 

license conditions. The inspection team should determine there is reasonable 

assurance the commitment tracking program is effective. 

 

Any “newly identified” SSCs will be inspected to the extent necessary to ensure 

that the licensee adequately evaluated and included applicable SSCs into its 

aging management programs or TLAAs, as required under 10 CFR 54.37(b). 

 1. Inspection of outstanding commitments should include a review of 

supporting documentation to determine if the licensee has taken the 

appropriate actions, including corrective action, to satisfy a particular 

license condition or commitment. Appropriate technical expertise should 

be sought if needed. 

 2. The PRI may require visual inspection of structures and components 

during the resolution of a particular commitment. Therefore, portions of the 

inspection may have to be performed during a unit outage to allow visual 

observation of those structures and components which are not accessible 

during power operation, e.g., inside containment, and normal high radiation 

areas. The inspectors should request assistance from NRR technical staff 

if the visual observations require intricate knowledge of aging effects to a 

specific structure or component. 

 3. Commitments that are not implemented by the licensee, except those the 

NRC previously agreed could be delayed, deferred, or eliminated, after the 
Issue Date: 02/15/08 71003 - 4 -

extended period of operation commences will be evaluated for NRC 

enforcement action using Inspection Manual Chapter (IMC) 0308 “Reactor 

Oversight Process Basis Document”, IMC 609 “Significance Determination 

Process”, in keeping with the NRC’s "General Statement of Policy and 

Procedure for NRC Enforcement Actions - Enforcement Policy," 

 c. The inspectors should verify the UFSAR supplement describes the aging 

management programs and TLAAs as approved by the NRC in the SER issued 

with the renewed license, or as subsequently amended. The inspectors should 

determine the basis for the removal or addition of SSCs or commodity groups 

from/to an aging management program and whether the basis was justified. 

 d. The PRI program will be implemented before commencement of the extended 

period of operation, which should be clearly stated in the inspection plan. This 

plan will also state the appropriate time and duration of the program. Portions of 

the inspection program may be performed before the period of extended 

operation and/or during the unit outage preceding the extended operation date. 

Subsequent inspection(s) may be necessary, if outstanding commitments and/or 

issues remain after the completion of the initial PRI. 

71003-04 RESOURCE ESTIMATES 

It has been estimated that the post-renewal inspections will require approximately two 

weeks of inspection time onsite involving a team of four inspectors and an inspection 

lead. An additional week will be allocated each to inspection preparation, in-office 

review between two onsite weeks, and for documentation of the inspection results. The 

team leader will require an additional week of preparation and an additional two weeks 

in order to finalize the inspection report. Based on these estimates, each PRI will 

require about 28 inspection weeks. It is estimated that each unit at each site will require 

an inspection; however, later inspections at multi-unit sites may not require the same 

level of effort as the first unit PRI inspection. The level of remaining effort will be 

determined by the Regional Administrator, or his designee, following completion of the 

first inspection at a particular site. 

Note to the Lead Inspector Regarding the Identification of Newly Identified SSCs. 

Licensees may identify new SSCs that should be within the scope of its license renewal 

program at any time. These SSCs are “newly identified” pursuant to 10 CFR 54.37(b), 

which has been further clarified in Regulatory Issue Summary RIS-2007-16 as part of 

NRC generic communications. The NRC may also specify additional newly identified 

SSCs that one or more holders of renewed licenses must evaluate and include as 

applicable in its next FSAR update in accordance with §54.37(b). 

Contact NRR/DLR staff for (1) information on generic communications that were issued 

naming newly identified SSCs, or (2) technical assistance in the review of new aging 

management programs that have been developed by the licensee. The intent of 
Issue Date: 02/15/08 71003 - 5 -

§54.37(b) is to capture those SSCs that, if they had been identified at the time of the 

license renewal application, would have been subject to an AMR or evaluation as a 

TLAA. Newly identified SSCs are those SSCs that meet one of the two following 

conditions: 

 a. There is a change to the current licensing basis (CLB) that: 

• Impacts SSCs that were not in scope for license renewal when the license 

renewal application was approved, and 

• The SSCs would have been in the scope of license renewal based on the 

CLB change if §54.4(a) were applied to the SSCs; 

 b. SSCs were installed in the plant at the time of the license renewal review that in 

accordance with its CLB at the time, should have been in the scope of license 

renewal per §54.4(a) but were not identified as in scope until after the renewed 

license was issued. 

SSCs that are plant additions or modifications installed after the renewed license 

Is issued are not subject to the provision of §54.37(b) as per staff 

communication with the industry when RIS-2007-16 was issued. 

END 
Issue Date: 02/15/08 71003 Att1-1

ATTACHMENT 1 

EXPIRATION DATES OF ORIGINAL LICENSES 

The following pages provide a convenient compilation of operating license expiration 

dates for inspection planning purposes. Plants are listed on an individual unit basis, by 

region and the date when their [original] operating license expires. Inclusion on this list 

does not mean that the plant has come in with an application to operate beyond the 

original operating license nor does it mean that NRC has granted a renewed operating 

license. Prior to scheduling this inspection, it is incumbent upon the Region to 

determine that a renewed operating license has been granted and that the conditions 

for performing the inspection have been met. 
Issue Date: 02/15/08 71003 Att1-2

Attachment 1.1 

Region I Plants — Original Operating License Expiration Dates 

Plant Name Expiration Date

Oyster Creek Generating Station 04/09/09 

Nine Mile Point Nuclear Station, Unit 1 08/22/09 

Ginna Nuclear Power Plant 09/18/09 

Vermont Yankee Nuclear Power Station 03/21/12 

Pilgrim Nuclear Power Station 06/08/12 

Peach Bottom Atomic Power Station, Unit 2 08/08/13 

Indian Point Nuclear Generating, Unit 2 09/28/13 

Three Mile Island Station, Unit 1 04/19/14 

Peach Bottom Atomic Power Station, Unit 3 07/02/14 

Calvert Cliffs Nuclear Power Plant, Unit 1 07/31/14 

James A. FitzPatrick Nuclear Power Plant 10/17/14 

Millstone Power Station, Unit 2 07/31/15 

Indian Point Nuclear Generating, Unit 3 12/15/15 

Beaver Valley Power Station, Unit 1 01/29/16 

Calvert Cliffs Nuclear Power Plant, Unit 2 08/13/16 

Salem Nuclear Generating Station, Unit 1 08/13/16 

Salem Nuclear Generating Station, Unit 2 04/18/20 

Susquehanna Steam Electric Station, Unit 1 07/17/22 

Susquehanna Steam Electric Station, Unit 2 03/23/24 

Limerick Generating Station, Unit 1 10/26/24 

Millstone Power Station, Unit 3 11/25/25 

Hope Creek Nuclear Generating Station 04/11/26 

Seabrook Station 10/17/26 

Nine Mile Point Nuclear Station, Unit 2 10/31/26 

Beaver Valley Power Station, Unit 2 05/27/27 

Limerick Generating Station, Unit 2 06/22/29 
Issue Date: 02/15/08 71003 Att1-3

Attachment 1.2 

Region II Plants — Original Operating License Expiration Dates 

Plant Name Expiration Date

H. B. Robinson Steam Electric Plant 07/31/10 

Surry Power Station, Unit 1 05/25/12 

Turkey Point Nuclear Plant, Unit 3 07/19/12 

Surry Power Station, Unit 2 01/29/13 

Oconee Nuclear Station, Unit 1 02/06/13 

Turkey Point Nuclear Plant, Unit 4 04/10/13 

Oconee Nuclear Station, Unit 2 10/06/13 

Browns Ferry Nuclear Plant, Unit 1 12/20/13 

Browns Ferry Nuclear Plant, Unit 2 06/28/14 

Oconee Nuclear Station, Unit 3 07/19/14 

Edwin I. Hatch Nuclear Plant, Unit 1 08/06/14 

Brunswick Steam Electric Plant, Unit 2 12/27/14 

St. Lucie Nuclear Plant, Unit 1 03/01/16 

Browns Ferry Nuclear Plant, Unit 3 07/02/16 

Brunswick Steam Electric Plant, Unit 1 09/08/16 

Crystal River, Unit 3 12/03/16 

Joseph M. Farley Nuclear Plant, Unit 1 06/25/17 

North Anna Power Station, Unit 1 04/01/18 

Edwin I. Hatch Nuclear Plant, Unit 2 06/13/18 

North Anna Power Station, Unit 2 08/21/20 

Sequoyah Nuclear Plant, Unit 1 09/17/20 

Joseph M. Farley Nuclear Plant, Unit 2 03/31/21 

McGuire Nuclear Station, Unit 1 06/12/21 

Sequoyah Nuclear Plant, Unit 2 09/15/21 

Virgil C. Summer Nuclear Station 03/03/23 

St. Lucie Nuclear Plant, Unit 2 04/06/23 

Catawba Nuclear Station, Unit 1 12/06/24 

Catawba Nuclear Station, Unit 2 02/24/26 

Shearon Harris Nuclear Power Plant 10/24/26 

Vogtle Electric Generating Station, Unit 1 01/16/27 

Vogtle Electric Generating Station, Unit 2 02/09/29 

Watts Bar Nuclear Plant 11/09/35 
Issue Date: 02/15/08 71003 Att1-4

Attachment 1.3 

Region III Plants — Original Operating License Expiration Dates 

Plant Name Expiration Date

Dresden Nuclear Power Station, Unit 2 12/22/09 

Monticello Nuclear Generating Plant 09/08/10 

Point Beach Nuclear Plant, Unit 1 10/05/10 

Dresden Nuclear Power Station, Unit 3 01/12/11 

Palisades Nuclear Power Plant 03/24/11 

Quad Cities Nuclear Power Station, Unit 1 12/14/12 

Quad Cities Nuclear Power Station, Unit 2 12/14/12 

Point Beach Nuclear Plant, Unit 2 03/08/13 

Prairie Island Nuclear Generating Plant, Unit 1 08/09/13 

Kewaunee Power Station 12/21/13 

D. C. Cook Nuclear Power Plant, Unit 1 10/25/14 

Prairie Island Nuclear Generating Plant, Unit 2 10/29/14 

Davis-Besse Nuclear Power Station 04/22/17 

D. C. Cook Nuclear Power Plant, Unit 2 12/23/17 

LaSalle County Station, Unit 1 04/17/22 

LaSalle County Station, Unit 2 12/16/23 

Duane Arnold Energy Center 02/21/24 

Byron Station, Unit 1 10/31/24 

Fermi Power Plant, Unit 2 03/20/25 

Perry Nuclear Power Plant 03/18/26 

Clinton Power Station 09/29/26 

Braidwood Nuclear Power Plant, Unit 1 10/17/26 

Byron Station, Unit 2 11/06/26 

Braidwood Nuclear Power Plant, Unit 2 12/18/27 
Issue Date: 02/15/08 71003 Att1-5

Attachment 1.4 

Region IV Plants — Original Operating License Expiration Dates 

Plant Name Expiration Date

Fort Calhoun Station 08/09/13 

Cooper Nuclear Station 01/18/14 

Arkansas Nuclear One, Unit 1 05/20/14 

Arkansas Nuclear One, Unit 2 07/17/18 

Diablo Canyon Power Plant, Unit 1 09/22/21 

San Onofre Nuclear Generating Station, Unit 2 02/16/22 

San Onofre Nuclear Generating Station, Unit 3 11/15/22 

Columbia Generating Station 12/20/23 

Callaway Plant 10/18/24 

Grand Gulf Nuclear Station 11/01/24 

Waterford Steam Electric Station, Unit 3 12/18/24 

Palo Verde Nuclear Station, Unit 1 12/31/24 

Wolf Creek Generating Station 03/11/25 

Diablo Canyon Power Plant, Unit 2 04/26/25 

River Bend Station 08/29/25 

Palo Verde Nuclear Station, Unit 2 12/09/25 

Palo Verde Nuclear Station, Unit 3 03/25/27 

South Texas Project Electric Generating Station, Unit 1 08/20/27 

South Texas Project Electric Generating Station, Unit 2 12/15/28 

Comanche Peak Steam Electric Station, Unit 1 02/08/30 

Comanche Peak Steam Electric Station, Unit 2 02/02/33 
Issue Date: 02/15/08 71003 Att2-1

ATTACHMENT 2 

LICENSE CONDITIONS, COMMITMENTS, AND TLAAs 

FOR POST-RENEWAL INSPECTIONS 

The license conditions can be found in the Introduction and General Discussion section 

of the Safety Evaluation Report (SER). The license renewal commitments can be found 

appended to the SER, with the exception of four plants as described below. Timelimited aging analyses are those described in Section 4.0 of the SER and are those 

licensee calculations and analyses that, in part, involve conclusions or provide the basis 

for conclusions related to the capability of SSCs to perform its intended functions as 

delineated in 10 CFR 54.21 54.4(b). 

(1) License Conditions – License conditions are normally listed at the end of Section 1, 

Introduction and General Discussion, of the SER. There are two generic conditions: 

 a. The licensee is required to include the UFSAR supplements required by 

10 CFR 54.21(d) in the next UFSAR 10 CFR 50.71(e) update following the 

issuance of the renewed license. 

 b. The activities identified in the UFSAR supplements are required to be completed 

in accordance with the schedule as appended to the safety evaluation report as 

discussed below. 

In addition to the above two conditions, there are others that might be required, 

depending upon the plant specific’s material aging, degradation, and/or operating issues 

that were evaluated at the time of the staff review. 

(2) Commitments – The list of commitments can be found in the following locations: 

 Arkansas Nuclear One; Edwin I. Hatch Nuclear Power Plant; SER NUREG 

 Oconee Nuclear Station and Turkey Point Nuclear Plant body1

 Calvert Cliffs Nuclear Power Plant SER NUREG 

 Appendix E 

 Catawba, McGuire, North Anna, Peach Bottom, St. Lucie, SER NUREG 

 Surry Appendix D 

 Fort Calhoun Station and all renewed licenses since SER NUREG 

 January 2004 Appendix A 

 

1 The commitments for these four plants have been compiled and can be found in ADAMS ML070640041
Issue Date: 02/15/08 71003 Att2-2

(3) Approved Renewed Operating License (ROL)` – The following table provides a list of 

those nuclear power plants which have had renewed operating licenses approved. 

This table will be revised, as necessary, but may not be current. Future approved 

ROL plants and related SER NUREG information can be found on ADAMS 

Accession No. ML070850037, or the NRC external website at the following link: 

http://www.nrc.gov/reactors/operating/licensing/renewal/applications.html. 

 The List of Approved Renewed Operating Licenses (ML070850037) will be 

 updated annually by NRR/DLR. 
Issue Date: 02/15/08 71003 Att2-3

Table 2-1 

List of Plants With Approved Renewed Operating Licenses (AROLs) 

(See ML070850037 for later list of AROLs) 

Site With Approved

Renewed OLs

Unit Line 1 Expiration of Initial License

Line 2 ROL SER/NUREG Issued Date

Line 3 And Related ADAMS ML# Nos

71002 

IR#

Arkansas Nuclear One Unit 1 05/20/2014 

NUREG-1743 Issued 04/2001 

ML011640099, ML011640177, 

ML011640217

00-17 

01-03 

01-02

Unit 2 07/17/2018 

NUREG-1828 Issued 06/2005 

ML051730233

04-06 

04-07 

05-12

Browns Ferry Unit 1 12/20/2013 

NUREG-1843 Issued 01/2006, 04/2006 

(Supp) 

ML060120453, ML061220272(Supp)

04-12 

05-03 

05-13

Unit 2 06/28/2014 

NUREG-1843 Issued 01/2006, 04/2006 

(Supp) 

ML060120453, ML061220272(Supp)

04-12 

05-03 

05-13

Unit 3 07/02/2016 

NUREG-1843 Issued 01/2006, 04/2006 

(Supp) 

ML060120453, ML061220272(Supp)

04-12 

05-03 

05-13

Brunswick Unit 1 09/08/2016 

NUREG-1856 Issued 06/2006 

ML061730123, ML061730129

05-08

Unit 2 12/27/2014 

NUREG-1856 Issued 06/2006 

ML061730123, ML061730129

05-08

Calvert Cliffs Unit 1 07/31/2014 

NUREG-1705 Issued 12/1999 

ML063620322

99-02 

99-04 

99-12

Unit 2 08/13/2016 

NUREG-1705 Issued 12/1999 

ML063620322

99-02 

99-04 

99-12

Catawba Unit 1 12/06/2024 

NUREG-1772 Issued 03/2003 (Appendix D) 

ML030850251

02-05 

02-06
Issue Date: 02/15/08 71003 Att2-4

Unit 2 02/24/2026 

NUREG-1772 Issued 03/2003 (Appendix D) 

ML030850251

02-05 

02-06

D. C. Cook Unit 1 10/25/2014 

NUREG-1831 Issued 05/2005 

ML052230442

04-03 

04-13

Unit 2 12/23/2017 

NUREG-1831 Issued 05/2005 

ML052230442

04-03 

04-13

Dresden Unit 2 12/22/2009 

NUREG-1796 Issued 10/2004 

ML042050507

03-04 

03-10 

04-05 

04-07

Unit 3 01/12/2011 

NUREG-1796 Issued 10/2004 

ML042050507

03-04 

03-10 

04-05 

04-07

Fort Calhoun 08/09/2013 

NUREG-1782 Issued 07/2003 

ML032481209

02-07 

03-03

Ginna 09/18/2009 

NUREG-1786 Issued 05/2004 

ML040640687

03-08 

03-10

Hatch Unit 1 08/06/2014 

NUREG-1803 Issued 10/2001 

ML012820121

00-09 

00-10

Unit 2 06/13/2018 

NUREG-1803 Issued 10/2001 

ML012820121

00-09 

00-10

Joseph M. Farley Unit 1 06/25/2017 

NUREG-1825 Issued 03/2005 

ML050630571

04-09 

05-11

Unit 2 03/21/2021 

NUREG-1825 Issued 03/2005 

ML050630571

04-09 

05-11

McGuire Unit 1 06/12/2021 

NUREG-1772 Issued 03/2003 (Appendix D) 

ML030850251

02-05 

02-06
Issue Date: 02/15/08 71003 Att2-5

Unit 2 03/03/2023 

NUREG-1772 Issued 03/2003 (Appendix D) 

ML030850251

02-05 

02-06

Millstone Unit 2 07/31/2015 

NUREG-1838 Issued 08/2005 

ML053270483 (Vol. 1), ML053290180 (Vol. 

2)

04-09 

04-10

Unit 3 11/25/2025 

NUREG-1838 Issued 08/2005 

ML053270483 (Vol. 1), ML053290180 (Vol. 

2)

04-09 

04-10

Monticello 09/08/2010 

NUREG-1865 Issued 10/2006 

ML063050414

06-06

Nine Mile Point Unit 1 08/22/2009 

NUREG-1900 Issued 09/2006 

ML061460313

05-11

Unit 2 10/31/2026 

NUREG-1900 Issued 09/2006 

ML061460313

05-11

North Anna Unit 1 04/01/2018 

NUREG-1766 Issued 12/2002 (Appendix D) 

ML030160853, ML030160804, 

ML030160825, ML030160848

02-06 

02-09

Unit 2 08/21/2020 

NUREG-1766 Issued 12/2002 (Appendix D) 

ML030160853, ML030160804, 

ML030160825, ML030160848

02-06 

02-09

Oconee Unit 1 02/06/2013 

NUREG-1723 Issued 03/2000 

ML003695154

99-11 

99-12 

00-03

Unit 2 10/06/2013 

NUREG-1723 Issued 03/2000 

ML003695154

99-11 

99-12 

00-03

Unit 3 07/19/2014 

NUREG-1723 Issued 03/2000 

ML003695154

99-11 

99-12 

00-03

Palisades (Note 5) 03/24/2011 

NUREG-1871 Issued 01/2007 

ML070600578

05-09
Issue Date: 02/15/08 71003 Att2-6

Peach Bottom Unit 2 08/08/2013 

NUREG-1769 Issued 03/2003 (Appendix D) 

ML030300673

02-09

02-10

02-12

Unit 3 07/02/2014 

NUREG-1769 Issued 03/2003 (Appendix D) 

ML030300673

02-09

02-10

02-12

Point Beach Unit 1 10/05/2010 

NUREG-1839 Issued 12/2005 

ML053420134, ML053420137

05-05

05-15

Unit 2 03/08/2013 

NUREG-1839 Issued 12/2005 

ML053420134, ML053420137

05-05

05-15

Quad Cities Unit 1 12/14/2012 

NUREG-1796 Issued 10/2004 

ML042050507

03-04

03-14

04-03

04-06

Unit 2 12/14/2012 

NUREG-1796 Issued 10/2004 

ML042050507

03-04

03-14

04-03

04-06

Robinson Unit 2 07/31/2010 

NUREG-1785 Issued 03/2004 

ML040200981

03-08

03-09

03-11

St. Lucie Unit 1 03/01/2016 

NUREG-1779 Issued 07/2003 (Appendix D) 

ML031890043

02-07

03-03

Unit 2 04/06/2023 

NUREG-1779 Issued 07/2003 (Appendix D) 

ML031890043

02-07

03-03

Summer 08/06/2022 

NUREG-1787 Issued 03/2004 

ML040300170

03-07

03-08

03-09

Surry Unit 1 05/25/2012 

NUREG-1766 Issued 12/2002 (Appendix D) 

ML030160853

02-06

02-09

Unit 2 01/29/2013 

NUREG-1766 Issued 12/2002 (Appendix D) 

ML030160853

02-06

02-09
Issue Date: 02/15/08 71003 Att2-7

Turkey Point Unit 3 07/19/2012 

NUREG-1759 Issued 04/2002 

NUREG-1759, Supp. 1, Issued 05/2002 

ML021280496, ML021280532, 

ML021560094

01-09

01-11

Unit 4 04/10/2013 

NUREG-1759 Issued 04/2002 

NUREG-1759, Supp. 1, Issued 05/2002 

ML021280496, ML021280532, 

ML021560094

01-09

01-11
Issue Date: 02/15/08 

Att3-1

ATTACHMENT 3 

Revision History For 71003 

Commitment Tracking Number 

Issue Date Description of Change Training 

Needed 

Training CompletDate 

N/A 02/15/08 

08-008 

Revision history reviewed for the last four years. IP 71003 has been revised to address the concern that the previous IP as written was too broad and that it did not focus on the needed inspection activities. 

N/A N/A