ML102500617

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2008/10/31-NRC000005-NRC Inspection Manual, Inspection Procedure 71003, Post-Approval Site Inspection for License Renewal
ML102500617
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 10/31/2008
From:
Division of License Renewal
To:
Atomic Safety and Licensing Board Panel
SECY RAS
Shared Package
ML102500610 List:
References
50-282-LR, 50-306-LR, ASLBP 08-871-01-LR-BD01, RAS 18571
Download: ML102500617 (18)
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Text

Issue Date: 10/31/08 71003 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. a. The post-renewal inspections (PRI) verify, on a sampling basis, that:

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: 10/31/08 71003 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 a commitment
  • 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 Issue Date: 10/31/08 71003
  • 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 ensurethat 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 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,"

Issue Date: 10/31/08 71003 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

§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:
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: 10/31/08 71003 Att1-1ATTACHMENT 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: 10/31/08 71003 Att1-2Attachment 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/

12/15 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 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 Seabrook Station 03/15/30

Issue Date: 10/31/08 71003 Att1-3Attachment 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 08/06/22 McGuire Nuclear Station, Unit 2 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: 10/31/08 71003 Att1-4Attachment 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 Duane Arnold Energy Center 02/21/14 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 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: 10/31/08 71003 Att1-5Attachment 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 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 Diablo Canyon Power Plant, Unit 1 11/02/24 Waterford Steam Electric Station, Unit 3 12/18/24 Wolf Creek Generating Station 03/11/25 Palo Verde Nuclear Station, Unit 1 06/01/25 Diablo Canyon Power Plant, Unit 2 08/26/25 River Bend Station 08/29/25 Palo Verde Nuclear Station, Unit 2 04/24/26 South Texas Project Electric Generating Station, Unit 1 08/20/27 Palo Verde Nuclear Station, Unit 3 11/25/27 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: 10/31/08 71003 Att2-1ATTACHMENT 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. Time-limited 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 body 1

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: 10/31/08 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: 10/31/08 71003 Att2-3Table 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: 10/31/08 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: 10/31/08 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: 10/31/08 71003 Att2-6Peach Bottom Unit 2 08/08/2013 NUREG-1769 Issued 03/2003 (Appendix D) ML030300673 02-0902-1002-12 Unit 3 07/02/2014 NUREG-1769 Issued 03/2003 (Appendix D) ML030300673 02-0902-1002-12Point 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 05-0505-15Quad 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 04-0304-06Robinson Unit 2 07/31/2010 NUREG-1785 Issued 03/2004 ML040200981 03-0803-0903-11St. 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 02-0703-03Summer 08/06/2022 NUREG-1787 Issued 03/2004 ML040300170 03-07 03-0803-09Surry 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: 10/31/08 71003 Att2-7Turkey Point Unit 3 07/19/2012 NUREG-1759 Issued 04/2002 NUREG-1759, Supp. 1, Issued 05/2002 ML021280496, ML021280532, ML021560094 01-0901-11 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: 10/31/08 71003 Att3-1ATTACHMENT 3 Revision History For 71003 Commitment Tracking Number Issue Date Description of Change Training Needed Training Completion Date Comment Resolution

Accession Number 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 N/A N/A 10/31/08 CN 08-031 Attachment1- Expiration Dates of Original Licenses has been revised to address incorrect dates for the following plants: Indian Point Nuclear Generating Unit 3, Seabrook Station, Virgil C. Summer Nuclear Station, McGuire Nuclear Station Unit 2, Duane Arnold Energy Center, Diablo Canyon Power Plant Units 1 and 2, Palo Verde Nuclear Station Units 1, 2 and 3. N/A N/A N/A

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