NL-08-163, (IP2) - Transmittal of Amendment Update to the Final Safety Analysis Report (Fsar), Revision 21

(IP2) - Transmittal of Amendment Update to the Final Safety Analysis Report (Fsar), Revision 21

ML083390108
Person / Time
Site:	Indian Point
Issue date:	10/20/2008
From:	Joseph E Pollock Entergy Nuclear Indian Point 2, Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-08-163
Download: ML083390108 (25)

Text

I Indian Point Energy Center 450 Broadway, GSB En y P.O. Box 249 Buchanan, N.Y. 10511-0249 Tel (914) 734-6700 J. Pollock.

Site Vice President Administrat~on October 20, 2008 Re: Indian Point Unit No. 2 Docket No. 50-247 NL-08-163 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station O-Pl-17 Washington, D.C. 20555-0001

Subject:

Indian Point 2 (IP2) Nuclear Power Plant Amendment Update to the Final Safety Analysis Report (FSAR), Revision 21

References:

1. NEI 98-03, "Guidelines for Updating Final Safety Analysis Reports," Revision 1, June 1999

2. NEI 99-04, "Guidelines for Managing NRC Commitments,"

Revision 2, December 1995

Dear Sir or Madam:

Entergy Nuclear Operations, Inc. (Entergy), in accordance with 10 CFR 50.71(e), hereby transmits the most recent update to the Updated Final Safety Analysis Report (UFSAR) for Indian Point Unit 2 (IP2). This submittal incorporates applicable changes made to the IP2 facility since the last UFSAR update in November 15, 2006, through the information available as of April 20, 2008, the completion of the last IP2 refueling outage. This submittal constitutes the twenty first (21) revision to the IP2 UFSAR.

As was done with previous versions of the IP2 UFSAR, this revision is being submitted on CD-ROM, and contains the entire IP2 UFSAR in Adobe Acrobat PDF format. The CD-ROM was prepared in accordance with the guidance contained in the NRC Electronic Submissions Final Rule issued October 10, 2003.

UFSAR changes to the text and tables since the last revision are indicated by gray highlighted background rather than a revision bar next to the line containing the change.

Any UFSAR figures that have been revised since the last revision contain "Rev. 21" in the figure title block.

This update to the FSAR also contains information that has been classified as "Historical" information according to the NEI 98-03 definition (Reference 1), and is no longer subject to updating. Material designated as "Historical" information in the UFSAR is indicated by a green highlighted background.

Docket No. 50-247 NL-08-163 Page 2 of 3 IP2 Technical Specification 5.5.12.d, "Technical Specification Bases Control Program,"

requires that changes to the Bases implemented without prior NRC approval be provided to the NRC on a frequency consistent with 10 CFR 50.71(e). The required information is provided in Attachment 1, "Summary of Revisions to the IP2 Technical Specification Bases". , "Revisions to IP2 Docketed Commitments," submits a summary update of all changes made to the Unit 2 docketed commitments using the NEI 99-04 guidance (Reference 2) for determination of commitments which do not have either a safety or regulatory significance, which may be changed without prior interaction with the NRC staff and which require periodic NRC staff, notification either annually or along with the FSAR updates as required by 10 CFR 50.71(e).

As specified in NEI 98-03 (Reference 1), the Technical Requirements Manual (TRM) is controlled in a manner consistent with procedures fully or partially described in the UFSAR. Under this approach, the TRM document is subject to the change control requirements of 10 CFR 50.59 and the update/reporting requirements of 10CFR50.71(e). Attachment 3 of this letter, "Summary of Revisions to the IP2 Technical Requirements Manual (TRM)," submits the summary of changes to the IP2 TRM for the same time period as the IP2 FSAR update. of this letter, "Summary Report to the NRC of Revision 21 UFSAR Changes," contains a summary with a brief description of the information changed in this revision to the IP2 UFSAR.

Entergy is making no new commitments in this letter.

Should you or your staff have any questions regarding this submittal, please contact Mr.

Robert Walpole, Manager, Licensing, Indian Point Energy Center (IPEC) at (914) 734-6710.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on O\ zt\o 9D Date Sincerely, Pollock Site Vice President Indian Point Energy Center

Docket No. 50-247 NL-08-163 Page 3 of 3

Attachment:

1. Summary of Revisions to the IP2 Technical Specification Bases

2. Revisions to IP2 Docketed Commitments

3. Summary of Revisions to the IP2 Technical Requirements Manual (TRM)

4. Summary Report of IP2 Revision 21 UFSAR Changes

Enclosure:

CD-ROM containing the IP2 UFSAR (Rev. 21) files cc w/o enclosure:

Mr. John P. Boska, Senior Project Manager, NRC NRR DORL NRC Resident Inspector's Office, Indian Point Energy Center Mr. Paul Eddy, NYS Department of Public Service

ATTACHMENT 1 TO NL-08-163

SUMMARY

OF REVISIONS TO THE IP2 TECHNICAL SPECIFICATION BASES ENTERGY NUCLEAR OPERATIONS, INC.

INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 DOCKET NO. 50-247

NL-08-163 Attachment 1 Page 1 of 7 CHANGES TO INDIAN POINT 2 TECHNICAL SPECIFICATION BASES (for period November 2007 through October 14, 2008)

AFFECTED EFFECTIVE SECTIONS REV DATE DESCRIPTION Initial issue of Bases derived from NUREG-1431, in ALL 0 11/3/2003 conjunction with Technical Specification Amendment 238 for conversion of 'Current Technical Specifications' to

'Improved Technical Specifications'.

BASES UPDATE PACKAGE 01-12102003 B 3.1.6 1 12/10/2003 Various wording clarifications based on Licensed Operator B 3.3.1 feedback during trial run of ITS.

B 3.3.2 B 3.3.4 B 3.4.15 B 3.4.16 B 3.5.2 B 3.6.3 B 3.6.6 B 3.6.10 B 3.7.7

'BASES UPDATE PACKAGE 02-03042004..

B 3.8.9 1 03/04/2004 Remove 'MCC 210' from Table B 3.8.9-1, per 50.59 screen BASES UPDATE PACKAGE 03-08092004 B 3.3.1 2 08/09/2004 Clarification of testing in bypass, per 50.59 screen.

B 3.3.5 1 08/09/2004 Clarify requirements for performing a Trip Actuating Device Operational Test (TADOT) on the 480Volt SBO, degraded grid and undervoltage relays, per 50.59 screen.

B 3.7.10 1 08/09/2004 CRVS Fan terminology correction, per 50.59 screen.

B 3.8.7 1 08/09/2004 Clarification of inverter operability with frequency out-of-range, per 50.59 screen.

B 3.8.9 2 08/09/2004 Update Table 3.8.9-1 for safeguards MCC's, per 50.59 screen.

B 3.9.4 1 08/09/2004 Installation of a roll-up door on the Containment Equipment Hatch, per 50.59 Evaluation 04-0732-MD B 3.9.5 1 08/09/2004 RE.

NL-08-163 Attachment 1 Page 2 of 7 AFFECTED EFFECTIVE SECTIONS REV DATE DESCRIPTION BASES UPDATE PACKAGE 04-10222004 B 3.4.7 1 10/22/2004 Clarification on SG coupled to remove residual heat to provide additional operating flexibility while remaining consistent with the guidance of IN 95-35, per 50.59 screen.

BASES UPDATE PACKAGE 05-11222004 B 3.3.2 2 11/22/2004 Stretch Power Uprate (3.26%) from 3114.4 MWth to B 3.4.1321611/22/2004 MWth.

B 3.4.1 1 B 3.4.9 B 3.5.4

'BASES UPDATE PACKAGE 06-12132004 B 3.1.1 1 12/13/2004 Stretch Power Uprate (3.26%) from 3114.4 MWth to B 3.2.2 3216 MWth.

B 3.3.1 3 B 3.3.2 B 3.3.6 B 3.3.7 1 B 3.4.13 B 3.4.16 2 B 3.6.1 1 B 3.6.2 B 3.6.3 2 B 3.6.4 B 3.6.7 B 3.7.3 1 B 3.7.4 B 3.7.5 B 3.7.7 2 B 3.7.8 1 Continued from previous page

NL-08-163 Attachment 1 Page 3 of 7 AFFECTED EFFECTIVE SECTIONS REV DATE DESCRIPTION B 3.7.10 12/13/2004 Stretch Power Uprate (3.26%) from 3114.4 MWth to 3216 MWth.

2 B 3.7.11 B 3.7.14 B 3.8.2 B 3.8.5 B 3.8.8 B 3.8.10 B 3.9.6 BASES UPDATE PACKAGE 07-02252005 B 3.3.1 4 02/25/2005 Clarification on the frequency of Surveillance Requirement 3.3.1.8 to perform a Channel Operational Test (COT) (CR-IP2-2004-04344).

B 3.7.5 2 Clarification on Surveillance Requirement 3.7.5.3 as it relates to plant condition/frequency of performance of Auxiliary Feedwater Pump full flow testing.

BASES UPDATE PACKAGE 08-06102005 B 3.5.2 .2 06/10/2005 Change the Hot Leg Switchover time from 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to 6.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> (as per the latest Westinghouse Power Uprate analyses).

BASES UPDATE PACKAGE 09-08102005 TOC 1 08/10/2005 TOC, B 3.3.3, B 3.6.8 - Removal of Hydrogen B 3.3.3 Recombiners from the bases as per Technical 1 Specification Amendment 243.

B 3.3.4 2 B 3.3.4 - add the circuit breaker and transfer switch B 3.4.13 2 designators to the 21 and 22 RHR pump sections.

B 3.6.8 1 B 3.4.13 - Reference correction - editorial.

B 3.7.10 - Add reference that if the primary coolant B 3.7.10 3 source of containment is in question, refer to ITS 5.5.2.

BASES UPDATE PACKAGE 10-09162005 B 3.6.2 1 09/16/2005 Clarification to reflect the approved TS 5.5.14 which states that the testing program shall be in accordance with RG 1.163.

NL-08-163 Attachment 1 Page 4 of 7 AFFECTED EFFECTIVE SECTIONS REV DATE DESCRIPTION Continued from previous page B 3.6.10 1 09/16/2005 Update LCO and Condition B to clarify required actions consistent with FSAR.

BASES UPDATE PACKAGEI1-11042005, B 3.8.1 1 11/04/2005 Include operability criteria for 138 kV and 13.8 kV offsite circuits.

'BASES UPDATE PACKAGE 12-11102005 B 3.7.3 2 11/10/2005 Assess low flow FBVs and low flow FIVs being opened while at power and the single failure of either valve for MSLB (as per 50.59 Evaluation IP2-05-026384). This supplements the SPU analysis.

BASES UPDATE PACKAGE 13-12212005 B 3.8.1 2 12/21/2005 B 3.8.1 - Allow for the performance of offsite power verifications up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to a planned equipment B 3.9.3 1 outage. Clarify the 22 EDG starting air motor redundancy limitations. Provide for establishing EDG operability on one air start motor when one of the redundant air start motors is inoperable and to provide for a staggered surveillance of operable air start motors.

B 3.9.3 - Reflect the revised fuel decay time assumption used in the updated fuel handling accident analysis performed for the IP2 Stretch Power Uprate Project.

BASES UPDATE PACKAGE 14-02272006 B 3.7.3 3 02/27/2006 Reflect the current design of main FW isolation based on cited documents and made to provide operations with clarification (EVL-IP2-05-026384, Analysis CN-CRA 20 (SPU MSLB)

NL-08-163 Attachment 1 Page 5 of 7 AFFECTED EFFECTIVE SECTIONS REV DATE DESCRIPTION BASES UPDATE PACKAGE 15-04132006 B 3.4.9 2 04/13/2006 B 3.4.9 - Relaxation of the pressurizer water level limit in 4Mode 3.

B 3.7.3 B 3.7.3 - Clarification on electronic valve closure delay assumptions, per 50.59 Evaluation EVL-IP2-05-26384, Rev. 1 BASES UPDATE PACKAGE 16-07062006 B 3.9.1 1 07/06/2006 B 3.9.1 - Clarification on effective method for ensuring 1shutdown margin.

B 3.9.2 B 3.9.2 - Editorial change to make the bases consistent with TS 3.3.1.

BASES UPDATE PACKAGE 17-08152006 B 3.3.3 2 08/15/2006 B 3.3.3 - Reflect deletion of LT-940 from the TS LCO B 3.4.15 2 3.3.3 (Amendment 249).

B 3.4.15 - Remove LT-3303 (Sump Mod - 2R17)

BASES UPDATE PACKAGE 18-11072006 B 3.0 1 11/07/2006 B 3.0 - Reflect allowing a delay time for entering a supported system TS whenifthe inoperability is due solely B 3.3.4 3 to an inoperable snubber, risk is assessed and managed. Limiting Condition of Operation 3.0.8 is added B 3.6.10 3 to provide this allowance and define the requirements and limitations of its use. (Amendment 245)

B 3.3.4 - Addition of indicators LI-459A and LI-459B to provide additional Remote Shutdown Instrumentation flexibility.

B 3.6.10 - Revise editorial error on B 3.6.10-2 to make consistent with page B 3.6.10-9.

NL-08-163 Attachment 1 Page 6 of 7 BASES UPDATE PACKAGE 19-02162007 B 3.7.12 1 02/16/2007 B 3.7.12 & B 3.7.13 - Reflect that the validity of the criticality and boron dilution analysis can be extended B. 3.7.13 1 through end of current license based upon Badger Testing in 2003 and 2006 and Racklife code projections.

B 3.8.5 2 B 3.8.5 - Clarify LCO bases regarding allowance to cross-connect DC subsystems with the plant in Modes 5 and 6 (CR-IP2-2006-02339).

BASES UPDATE PACKAGE 20-04112007 TOC 2 04/11/07 TOC, B 3.4.4, B 3.4.5, B 3.4.6, B 3.4.7, B 3.4.13, and B 3.4.17 - Implement TS Amendment 251 related to B 3.4.4 1 steam generator tube integrity.

B 3.4.5 1 B 3.7.5 - Clarify the relationship between the AFW B 3.4.6 1 system and a design basis SBLOCA.

B 3.8.3 - Revise the wording regarding EDG operating B 3.4.7 2 time capability, associated loading and unusable fuel B 3.4.13 3 volume to be consistent with UFSAR Section 8.2.3.2 B 3.4.17 0 B 3.7.5 3 B 3.8.3 1 BASES UPDATE PACKAGE 21-05162007 B 3.9.4 2 05/16/2007 Remove use of the roll-up door as a Containment closure B 3.9.5 2 device subsequent to loss of RHR cooling in Mode 6.

BASES UPDATE PACKAGE 22-08082007 B 3.3.3 3 08/08/2007 Identify the TS for functions 5 and 6 as non-conservative and to send the reader to TRM 3.3.K.

NL-08-163 Attachment 1 Page 7 of 7 BASES UPDATE PACKAGE 23-10052007 B 3.3.1 5 10/05/2007 B 3.3.1 - The TS and bases currently allow a normal B 3.8.2 shutdown without the SR testing by reducing power 2 below the modes of applicability for SR 3.3.1.8. Clarify that testing is not required if such testing was done within the prior 184 days, even if a mode of applicability was still met.

B 3.8.2 - Clarify LCO with regard to the required power sources for modes 5 and 6.

BASES UPDATE PACKAGE 24-12142007 B 3.7.10 4 12/14/2007 List CCRA1 supplying Train B and CCRA2 supplying Train A.

BASES UPDATE PACKAGE 25-04112008 B 3.6.6 2 04/11/2008 B 3.6.6 and B 3.6.7 - Replacement of the trisodium phosphate buffer by sodium tetraborate (Amendment 253)

B 3.6.7 2 BASES UPDATE PACKAGE 26-07012008 B 3.4.16 3 07/31/2008 Implement the Bases pages of TSTF 490 for dose equivalent iodine (Amendment 254)

BASES UPDATE PACKAGE 27-09162008 B 3.8.1 3 09/16/2008 Reflect installation of Appendix R Diesel and GT B 3.8.3 2 removal.

ATTACHMENT 2 TO NL-08-163 REVISIONS TO IP2 DOCKETED COMMITMENTS ENTERGY NUCLEAR OPERATIONS, INC.

INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 DOCKET NO. 50-247

NL-08-163 Attachment 2 Page 1 of 1 Revisions to IP2 Docketed Commitments May 2006 throuqh ADril 2008 COMMITMENT CURRENT CHANGED DESCRIPTION NUMBER STATUS DATE Revised text:

NOTE: There were no commitments changed over the time frame that require a report to the NRC per the NEI 99-04 guidance.

ATTACHMENT 3 TO NL-08-163

SUMMARY

OF REVISIONS TO THE IP2 TECHNICAL REQUIREMENTS MANUAL (TRM)

ENTERGY NUCLEAR OPERATIONS, INC.

INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 DOCKET NO. 50-247

NL-08-163 Attachment 3 Page 1 of 3 Unit 2 TECHNICAL REQUIREMENTS MANUAL (TRM)

REVISION HISTORY AFFECTED NEW EFFECTIVE DESCRIPTION SECTIONS REV # DATE 3.7.F 2 03/31/2004 To extend the testing frequency of the Post Accident containment venting system from 24 months to 60 months.

3.9.C 2 Revise TRO 3.9.C from "Spent fuel pit water level shall be maintained

> 23 ft above the top of irradiated fuel" to say, 'The Spent Fuel Pit water level shall be >23 ft over the top of irradiated fuel assemblies seated in the storage racks."

5.3.B 2 Revise the to be more generic in referencing the procedures(s) used for Procedure Preparation, Review, and Approval and to state that changes shall be reviewed and approved in accordance with the approved process that meets the requirements in the Quality Assurance Program Manual.

3.3.C 2 08/19/2004 Changes to Service Water Inlet 3.3.K 3 Temperature Monitoring and B3.3.K 3 Instrumentation for references to correct conditions, actions and time. Section 3.3.K changes to:

"Flowmeter (LEFM) check 2000 system" to "Flowmeters (LEFMs)".

5.0 4 08/24/2004 Change responsibility to read the Shift Manager shall be responsible for ensuring plant operations are in accordance with the TRM.

B 3.9.6 2 10/28/2004 Add clarification to TRM for the use of the roll-up door as a containment closure device.

B3.0 2 01/20/2005 Place the word NOT in paragraph on B3.0-3.

5.0 5 Replace Steam Generator procedure reference with a new I

NL-08-163 Attachment 3 Page 2 of 3 joint EN-DC-317 reference.

3.2.A 2 01/24/2005 Revise to say, "Both Quadrant B 3.2.A 2 power tilt monitors" instead of "One Quadrant power tilt monitor, and "Verify QPTR is within limit by calculation" instead of "Perform Tech Spec SR 3.2.4.1."

TOC 2 04/20/2005 Deletions due to Stretch Power 3.3.K 3 Uprate 2% uncertainty.

B.3.3.K 3 5.0 6 05/04/2005 Update of the Inservice Testing Program procedures list.

5.0 7 05/24/2005 Add requirement to provide to the NRC using an industry database (INPO's) the operating data for each calendar month that is described in GL 97-02 by the last day of the month following the end of each calendar quarter.

Complete 05/23/2005 Provide to the NRC the complete TRM to NRC TRM as of 05/23/2005 and the revision history.

5.0 8 11/30/2005 Update the procedures listed in 5.5.B "Primary Coolant Sources Outside Containment" and 5.5.F "Inservice Testing Program". The procedure list is contained in procedures ENN-DC-197 & 332.

3.9.A 2 02/02/2006 Revise the TRM to reflect the fuel B3.9.A 2 decay time assumption used in the updated fuel handling accident analysis performed for the IP2 Stretch Power Uprate project.

3.0 3 02/02/2006 Update the rules of usage sections B3.0 of TRO and TRS to reflect the 3.3.G adoption of TSTF-359; "Increased 3.9.A Flexibility in MODE Restraints".

B3.9.A B3.0 4 02/07/2006 Typo correction for TRS in place of Surveillances 3.3.G 4 03/14/2006 Correction to Rev. 2 of this section deleted step 6 from Table 3.3.G-1 PAM, however, the master copy still showed Rev. 1. Rev. 3 was made from Rev. 1 and step 6 was still included.

TOC 4 07/25/2006 Removal of subheading in section 5.4 to create Units 2 & 3 TOC the same.

2

NL-08-163 Attachment 3 Page 3 of 3 7- F 3.7.A 2 Addition of new type of snubber, LISEGA to section that may be inspected remotely.

5.0 9 Removal of required annual submittal of an Occupational Radiation Exposure Report from Tech Specs under adoption of TSTF-369 an adds a new reporting requirement to the TRM for an annual occupational exposure information.

Complete 11/17/2006 Provide to the NRC the complete TRM to NRC TRM as of 11/17/2006 and the revision history.

3.3.B 2 03/06/2007 Change to provide a TRM B.3.3.B clarification such that it is understood that there are 5 transmitters applicable to section 3.3.B RHR Flow Monitoring Instrumentation.

3.3.K 0 Containment / Recirculation Sump Level Indication addition to TRM.

3.3.L 0 09/04/2007 Containment / Recirculation Sump Level Indication addition to TRM section changed from 3.3.K to 3.3.L.

3.3.K 0 09/04/2007 Toxic Gas Monitoring Instrumentation added to TRM from UFSAR. Was previously Containment / Recir section, moved to 3.3.L.

3.3.B 0 10/05/2007 Gas Turbines section added to TRM.

3.8.C 2 10/05/2007 Provide additional detailed information on the surveillances routinely performed for the IP2 TSC diesel.

TOC 8 03/03/2008 Typo on page numbering for section 3.3.L Report of 10/20/2008 Provide to the NRC the completed TRM Changes TRM revision history changes as of to NRC 10/20/2008.

3

ATTACHMENT 4 TO NL-08-163

SUMMARY

REPORT OF IP2 REVISION 21 UFSAR CHANGES ENTERGY NUCLEAR OPERATIONS, INC.

INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 DOCKET NO. 50-247

NL-08-163 Attachment 4 Page 1 of 7 2008 Summary Report of IP2 Revision 21 UFSAR Changes May 2006 throuah October 2008 FSAR AFFECTED SOURCE of INITIATOR'S INFORMATION CHAPTER PAGES, CHANGE, NAME DESC. OF1 CHANGE I

& TABLE, or 50.59 or SCREEN PROBLEM PACKAGE FIGURES NUMBER U208 CH. 1 01-01-001 Pg. 1 NRC SER for LAR for J. Quirk Revise the UFSAR to reflect Stretch Power Uprate the correct Megawatt Thermal output of 3216 MWt and approximate electric output of 1078 MWe from the SPU changes.

01-01-002 Pg. 33 Editorial A. Stewart Update the UFSAR supplements to include Rev.

21.

01-09-001 Ch. 1 Pg. 33 EC 5000034131 M. Driscoll Reactor Core Information for Ch. 3 2R18.

CH. 2 02-02-001 Pg. 3 PAD A. Stewart Correction to the Algonquin gas pipeline information.

CH.3 CH. 4 04-02-001 T4-2-1 50.59 screen W. Wittich Revise table and appendix to App. 4C reflect actual materials of construction as documented in WCAP-15151 and 1968 Material Certification reports.

04-02-002 Pg. 40 TS Amend. #231 & F. Gumble Correct discrepancies in the T4.2-7 & 241 reported copper and nickel Ch. 14 CR-IP2-2006-06522 content of 3 Rx. Vessel base Pg.63 WCAP-15629, Rev. 1 plates. -&-

T1 4.3-52 CR-IP2-2006-06530 Tank Rupture 04-03-001 T4.3-2 NL-07-039 Error in W. Wittich Revise the table to reflect technical data from Cumulative Usage Factors vendor found during with optimized Reactor Vessel License Renewal. stud tensioning procedures as documented in Stress Report R-4147-00-1.

NL-08-163 Attachment 4 Page 2 of 7 2008 Summary Report of IP2 Revision 21 UFSAR Changes May 2006 throuah October 2008 FSAR AFFECTED SOURCE of INITIATOR'S INFORMATION CHAPTER PAGES, CHANGE, NAME DESC. OF CHANGE I

& TABLE, or 50.59 or SCREEN PROBLEM PACKAGE FIGURES NUMBER U208 CH.5 05-01-001 Pg. 42 PAD & 50.59 screen F. Gumble Remove use of the rollup door as a Containment closure device subsequent to loss of RHR cooling in MODE 6.

05-02-001 T5.2-1 CR-IP2-08-02231 K. Curley Change the normal position of PAD Containment Isolation Valves 791, 798, 796 &793 from normally open to normally closed.

CH.6 06-01-001 6.1.1 NL-07-077, F. Bauer To implement GSI-191 6.3.2 NRC SER 2/7/08 potential debris & chemical App 6A, 6C EC-5000034233 clogging of sump screens to 7.1.4 change the pH buffer from 9.2.2 STB to TSP.

14.3.6 06-02-001 6.2.3.9.2 PAD L. Cerra Clarification of the term "run-Pg. 35 LO-IP3LO-2006- out" relative to 20% margin.

00335 CA 12 & 13 06-02-002 6.2.2 Pg. 16 PAD & 50.59 screen J. Bencivenga Add note about operation of 2 EOP ES-1.3 & ES- IR pumps restriction to low 1.4 head recirculation conditions.

If high head recir exist, operator action will be taken to preclude operating 2 pumps in parallel.

06-02-003 6.2.2 Pg. 12 PAD & 50.59 screen L. Cerra Completion of sump T6.2-2 for sump mod modifications. Also includes 6.7.1 Pg. package U208 06-07-001 117 below.

Ch. 7 Pg. 2, 88

NL-08-163 Attachment 4 Page 3 of 7 2008 Summary Report of IP2 Revision 21 UFSAR Changes May 2006 through October 2008 FSAR AFFECTED SOURCE of INITIATOR'S INFORMATION CHAPTER PAGES, CHANGE, NAME DESC. OF CHANGE I

& TABLE, or 50.59 or SCREEN PROBLEM PACKAGE FIGURES NUMBER U208 06-04-001 Pg. 81 Original Typo NRC Identified Cooling coils in org. plant design are listed as tubes 0.0625" diameter & tube thickness of 0.035" both are incorrect.

06-06-001 6.6.2 Pg. 97 PAD J. Bencivenga Retire in place WC&PPS EC 7121 supply to penetration MP-O-O.

06-07-001 Pg. 117 & PAD & 50.59 Screen R. Sergi Removal of containment sump PART of Ch. 7 Pg 2, ERCN-IP2-06-28155 level transmitter LT-940.

PKG. 06- 88 ER 04-02-234 02-003 06-08-001 Pg. 138 NRC SER's for LAR's K. Kingsley Was Pkg. IP2-06 01-01-002 228 & 243 but information was missed in RA-05-022 2006 update.

CH.7 07-02-001 7.2.1.1 Pg. NRC SER G. Dahl Relocation of Toxic Gas 14 monitor LCO information from Ch. 7 & Ch. 9 into TRM.

07-02-002 F7.2-3 EC-5000034060 (ER- A. King Stator Cooling Water 10.2.3 05-2-137) PAD Reliability Upgrade.

07-02-003 7.2 pg.35 Editorial for W. Mahlmeister Cable tests rated at 600 volts clarification of IEEE for IEEE.

NL-08-163 Attachment 4 Page 4 of 7 2008 Summary Report of IP2 Revision 21 UFSAR Changes May 2006 through October 2008 FSAR AFFECTED SOURCE of INITIATOR'S INFORMATION CHAPTER PAGES, CHANGE, NAME DESC. OF CHANGE I

& TABLE, or 50.59 or SCREEN PROBLEM PACKAGE FIGURES NUMBER U208 CH. 8 08-01-001 Section 8.1 PAD &50.59 screen J. Herrera Statement that the station Pg. 7 & 8.5 1P2-2008 08-01 -001 batteries are subjected to an Pg. 29 CR-IP2-2007-00404 equalize charge on a periodic basis is not a vendor recommended practice and should be changed to an equalize charge based on voltage and specific gravity readings.

08-01-002 8.1 Pg. 3, 6 EC SBO/App R S. Prussman Revise UFSAR for placement 8.2 Pg. 9, diesel of Gas Turbine with SBO/App 10,19,22 R diesel.

8.3 Pg. 28, 29 8.5 Pg. 29, 30 Ch. 9 Pg.

17,46 08-02-001 8.2.3 Pg. 19 PAD & 50.59 screen J. Bencivenga EDG air receivers UFSAR information needs to be corrected for one automatic start during any particular power failure. This was identified during the NRC CDBI inspection, LOCR-IP2LO-06-335.

08-02-002 8.2.1 Pg. 10 CR-IP2-2006-04722 G. Dahl LCO & Surv. Req.s for Gas 8.5 Pg. 29 CA-2 Turbines removed and relocated into the TRM.

08-05-001 8.5 Pg. 29 Editorial Change A. Stewart Correction that changes to the Only Maint. Program are controlled by 10 CFR 50.64 and not CH. 9 50.59 CH.9 ____________________

NL-08-163 Attachment 4 Page 5 of 7 2008 Summary Report of IP2 Revision 21 UFSAR Changes May 2006 through October 2008 FSAR AFFECTED SOURCE of INITIATOR'S INFORMATION CHAPTER PAGES, CHANGE, NAME DESC. OF1 CHANGE I

& TABLE, or 50.59 or SCREEN PROBLEM PACKAGE FIGURES NUMBER U208 09-02-001 9.2 p. 17 E. Anderson App. R diesel 9.3 p. 45 09-03-001 46, 50 Editorial Change S. Wilkie Add Westinghouse reference Only to references for section 9.3 CR-IP2-2007-00452 and correct typo on pg. 46.

Westinghouse Calc.

CN-SEE-03-5, Rev. 0 WCAP 12312, Rev.0 09-05-001 New section 50.59 screen R. Evers Addition of the new Unit 2 Fuel 9.5.7 ER-05-2-014 Storage Building Dry Cask ER-05-2-015 Operations and crane to the UFSAR.

09-06-001 87, 88 NRC SER's for Fire S. Wilkie Removal of detail per NE198-Protection Program 03 and adding in the NRC listing of approved FP SER's.

09-06-002 85 PAD & 50.59 screen G. Bhalla Butterfly valve SWN-840 removal and the 7500 GPM flow orifice as the material upgrade to the FCU tubes.

NL-08-163 Attachment 4 Page 6 of 7 2008 Summary Report of IP2 Revision 21 UFSAR Changes May 2006 through October 2008 FSAR AFFECTED SOURCE of INITIATOR'S INFORMATION CHAPTER PAGES, CHANGE, NAME DESC. OF: CHANGE /

& TABLE, or 50.59 or SCREEN PROBLEM PACKAGE FIGURES NUMBER U208 CH. 10 10-01-001 10 PAD & 50.59 screen Y. Nembo Correct turbine differential ER-06-2-141 expansion instrumentation which does not properly correlate to the actual axial clearance.

10-01-002 F10.1-1 NRC SER for LAR# J. Bubniak SPU increased thermal and 241 electric power, this change is to correct information missed in the 2006 update for Figure 10.1-1.

CH. 11 11-02-001 40 PAD & 50.59 screen R. Deschamps Removal of detail per NEI 98-IP2-2008 11-02-001 03. Limits for removal of contamination in the controlled area should be removed and controlled through Rad Pro procedures.

CH. 12 12-01-001 Pg. 1 & 2 QAPM F. Bloise Facility staff qualifications PAD changed to reflect in the requirements ANSI N18.1-1971 to ANSI/ANS-3.1-1978.

12-06-001 Pg. 5 PAD S. Prussman Changes to the UFSAR to NRC approval of the update and correctly reflect Security Plan new NRC approved Security changes Plan changes.

CH. 13 CH. 14

NL-08-163 Attachment 4 Page 7 of 7 2008 Summary Report of IP2 Revision 21 UFSAR Changes May 2006 throunh October 2008 FSAR AFFECTED SOURCE of INITIATOR'S INFORMATION CHAPTER PAGES, CHANGE, NAME DESC. OF: CHANGE I

& TABLE, or 50.59 or SCREEN PROBLEM PACKAGE FIGURES NUMBER U208 14-02-001 69 & 70 PAD & 50.59 screen C. Tippin Based on Badger testing the IP2-2008 14-02-001 validity of the criticality and W.O. IP2-06-31214 boron dilution analysis can be extended through the end of the current license 09/30/2013.

14-02-002 Pg. 94-96, PAD & 50.59 screen A. Irani This change is to correct an 110 -112, IP2-2008 14-02-002 error in the analysis of the F1 4-2-12 RCCA ejection accident.

F14.2-15 F1 4.2-16 F1 4.2-18 CH. 15