NL-09-136, Indian Point 3 Nuclear Power Plant 2009 Amendment Update to the Final Safety Analysis Report (Fsar), Revision 03

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Indian Point 3 Nuclear Power Plant 2009 Amendment Update to the Final Safety Analysis Report (Fsar), Revision 03
ML093430690
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 10/13/2009
From: Pollock J E
Entergy Nuclear Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-09-136
Download: ML093430690 (21)
v • d • e


Text

Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 fBuchanan, N.Y. 10511-0249 IL---l Tel (914) 734-6700 J.E. Pollock Site Vice President Administration NL-09-136 October 13, 2009 Document Control Desk U.S. Nuclear Regulatory Commission Mail Stop O-Pl-17 Washington, D.C. 20555-0001

Subject:

Indian Point 3 Nuclear Power Plant 2009 Amendment Update to the Final Safety Analysis Report (FSAR). Revision 03 Indian Point Unit No. 3 Docket No. 50-286 License No. DPR-64

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 0, 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 3 (IP3). This submittal incorporates applicable changes made to the IP3 facility since the last UFSAR update on March 31, 2007, through the information available as of April 15, 2009, the completion of the last refueling outage.Entergy is submitting one copy of the entire IP3 UFSAR, Technical Specification Bases, and Technical Requirements Manual (TRM) in the electronic medium of Adobe PDF on CD-ROM in accordance with the guidance contained in NRC, "General (Non-Adjudicatory)

Electronic Submission Instructional Guide," June 11, 2009, Revision 4.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.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.

Any UFSAR figures that have been revised since the last revision contain "Rev. 03" in the figure title block. This revision to the IP3 UFSAR contains current 'snapshots' of the plant drawings in the form of a PDF file.1063 Docket No. 50-286 NL-09-136 Page 2 of 3 Indian Point 3 Technical Specification 5.5.13, "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 listed in Attachment 1, Revisions to the IP3 Technical Specification Bases and the entire document is provided on the enclosed CD-ROM.Attachment 2 to this letter, Revisions to IP3 Docketed Commitments, submits a summary update of all changes made to the Unit 3 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).The Technical Requirements Manual (TRM) under NEI 98-03 (Reference

1) 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 1 OCFR50.59 and the update/reporting requirements of 1 OCFR50.71 (e). Attachment 3 of this letter, submits the summary list of changes to the Unit 3 TRM for the same time period as the Unit 3 FSAR update and the entire document is provided on the enclosed CD-ROM.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 at (914) 734-6710.I declare under penalty of perjury that the forgoing is true and correct.Executed on lot I(Z6 01 Date Sincerely, JEP/as Attachments:
1) Revisions to the Indian Point 3 Technical Specification Bases 2) Revisions to Indian Point 3 Docketed Commitments
3) Revisions to the Indian Point 3 Technical Requirements Manual Docket No. 50-286 NL-09-136 Page 3 of 3 cc (w/o enclosure or attachments):

Mr. John P. Boska, NRR Senior Project Manager Mr. Samuel J. Collins, Regional Administrator, Region 1 Mr. Paul Eddy, Public service Commission Mr. Francis J. Murray, Jr., President

& CEO NYSERDA NRC Resident Inspector's Office ATTACHMENT 1 TO NL-09-136 REVISIONS TO THE INDIAN POINT 3 TECHNICAL SPECIFICATION BASES ENTERGY NUCLEAR OPERATIONS, INC INDIAN POINT UNIT 3 DOCKET NO. 50-286 DPR-64 NL-09-136 Attachment 1 Page 1 of 6 CHANGES TO INDIAN POINT 3 TECHNICAL SPECIFICATION BASES (for period March 2001 through August 2009)AFFECTED EFFECTIVE SECTIONS REV DATE DESCRIPTION Initial issue of Bases derived from NUREG-1431, in ALL 0 03/19/01 conjunction with Technical Specification Amendment 205 for conversion of 'Current Technical Specifications' to'Improved Technical Specifications'.

Changes regarding containment sump flow monitor per B 3.4.13 03/19/01 NSE 01-3-018 LWD Rev 0.B 3.4.15 Change issued concurrent with Rev 0.____ BASES UPDATE PACKAGE 02-061 801 Table of Contents 1 05/18/01 Title of Section B 3.7.3 revised per Tech Spec Amend 207 B 3.7.3 1 05/18/01 Implementation of Tech Spec Amend 207 BASES UPeDATE PAC",,Eý03411i90)i Correction to statement regarding applicability of Function B 3.3.2 1 11/19/01 5, to be consistent with the Technical Specification.

Changes to reflect reclassification of certain SG narrow B 3.3.3 1 11/19/01 range level instruments as QA Category M per NSE 97-3-439, Rev 1.Changes to reflect installation of a new control room alarm B 3.4.13 2 11/19/01 for 'VC Sump Pump Running'.

Changes per NSE 01-3-B 3.4.15

  • 018, Rev 1 and DCP 01-3-023 LWD.Clarification of allowable flowrate for CRVS in 'incident B 3.7.11 1 11/19/01 mode with outside air makeup.'____ UPDATE PACKAGE 04-01 2202 B 3.3.2 2 0.1/22/02 Clarify starting logic of 32 ABFP per EVL-01-3-078 MULTI, Rev 0.B 3.8.1 1 01/22/02 Provide additional guidance for SR 3.8.1.1 and Condition Statements A.1 and B.1 per EVL-01-3-078 MULTI, Rev 0.B 3.8.4 1 01/22/02 Revision of battery design description per plant modification and to reflect Tech Spec Amendment 209.B 3.8.9 1 01/22/02 Provide additional information regarding MCC in Table B 3.8.9-1 per EVL-01-3-078 MULTI, Rev 0.~BASES UPDATE PACKAG~E 05-093002~

B 3.0 1 09/30/02 Changes to reflect Tech Spec Amendment 212 regarding delay period for a missed surveillance.

Changes adopt TSTF 358, Rev 6.B 3.3.1 1 09/30/02 Changes regarding description of turbine runback feature per EVAL-99-3-063 NIS.B 3.3.3 2 09/30/02 Changes to reflect Tech Spec Amendment 211 regarding____ _ "CETs and other PAM instruments.

NL-09-136 Attachment 1 Page 2 of 6 AFFECTED EFFECTIVE SECTIONS REV DATE DESCRIPTION B 3.7.9 1 09/30/02 Changes regarding SWN 1 and -2 valves per____ ____ _ EVAL-00-3-095 SWS, Rev 0.- ..B 3.3.2 3 12/04/02 Changes to reflect Tech Spec Amendment 213 regarding B 3.6.6 1 1.4% power uprate.B 3.7.1 1 B 3.7.6 1_________

~I<BASES UPDATE PACKRAGE 07-031703~

B 3.3.8 1 03/17/2003 Changes to reflect Tech Spec Amendment 215 regarding B 3.7.13 1 implementation of Alternate Source Term analysis, B 3.9.3 1 methodology to the Fuel Handling Accident._______BASESUPDATE PACKAGE C(8-0O1Z8O3 B 3.4.9 1 03/28/2003

.] Changes to reflect Tech Spec Amendment 216 regarding.....relaxation of pressurizer level limits in MODE 3.________BASES UPDATE PAC KAG E6921062003~

B 3.4.9 2 06/20/2003 Changes to reflect commitment for a dedicated operator per Tech Spec Amendment 216.B 3.6.5 1 06/20/2003 Implements Corrective Action 11 from CR-IP3-2002-" 02095; 4 FCUs should be in operation to assure-representative measurement of containment air........._ temperature.

B 3.7.11 2 06/20/2003 Correction to Background description regarding system response to Firestat detector actuation per ACT 02-62887.B 3.7.13 2 06/20/2003 Revision to Background description of FSB air tempering units to reflect design change per DCP 95-3-142.B 3.8.7 1 06/20/2003 Changes to reflect replacement of Inverter 34 per DCP-B 3.8.8 1 06/20/2003 01-022.B 38.9 2 06/20/2003

____ BASES UPDATE PACKAGE 10-'10270Q4

~i B 3.1.3 1 10/27/2004--

Clarification of the surveillance requirements for TS 3.1.3 per 50.59 screen.B 3.3.5 1 10/27/2004 Clarify the requirements for performing a Trip Actuating Device Operational Test (TADOT) on the 480V degraded grid and undervoltage relays per 50.59 screen.B 3.4.3 1 10/27/2004-.

Extension of the RCS pressure/temperature limits and corresponding OPS limits from 16.17 to 20 EFPY (TS B 3.4.12 1 -Amendment 220)., B 3.5.1 1 10/27/2004 Changes to reflect Tech Spec Amendment 222 regarding_ _ extension of completion time for Accumulators.

_______ ____ BASES UPJIDATE PACKAGE 11-121~004 B 3.7.7 J 1: 12/17/2004 Addition of valves CT-1300 and CT-1i302 to Surveillance I ,SR 3.7.7.2 to verify that all city water header supply isolation valves are open. Reflects Tech Spec-_ _ _ jAmendment 218.

NL-09-1 36 Attachment 1 Page 3 of 6 AFFECTED EFFECTIVE SECTIONS REV DATE DESCRIPTION

____ ~BASES UPDATE PACKAGE 1 2-012405 B 3.7.11 3 01/24/2005 Temporary allowance for use of KI/SCBA for unfiltered

,- inleakage above limit._____________

BA~SESUPDATE PACKAGE 13-022505 B 3.7.5 1 02/25/2005 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 UPDAT[E PACKAGE 1r4-0 3 0j 7 05 B 3.9.6 1 03/07/2005 Changes to reflect that the decay time prior to fuel movement is a minimum of 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br /> per Tech Spec Amendment 215._________BASES UPDATE PACKAGE 15-041i105.B 3.3.2 4 04/11/2005 Changes to reflect AST as per Tech Spec Amendment B 3.3.6 1 224.B. 3.3.7 1 B 3.7.11 4 NOTE: In addition to the AST changes to B. 3.7.11, the B 3.7.12 1 temporary allowance for use of KI/SCBA for unfiltered B 3.7.14 1 inleakage above limit is being removed. Tracer Gas B 3.9.6 2 testing is complete.WBASES UPDATE PACKAG~E 16-060306.

B 2.1.1 .1. 06/03/2005 Changes to reflect.SPU as per Tech Spec Amendment B 2.1.2 1 225.B 3.1.1 1 B 3.2.2 1 B 3.3.1 2 .B 3.3.8 2 B 3.4.1 1 B 3.4.3 2 B 3.4.6 1 B 3.4.9 3 B 3.4.13 3 B 3.4.16 1 B 3.5.2 1 B 3.6.2 1 B 3.6.6 2 --B 3.6.7 1 B 3.6.9 1 B 3.6.10 -1 B38.7.1 .2 B3.7.2 1 B 3.7.5 2 B 3.7.6 2 B 3.7.8 1 B 3.7.9 2 NL-09-136 Attachment 1 Page 4 of 6 AFFECTED EFFECTIVE SECTIONS REV DATE DESCRIPTION B 3.7.10 1 B3.7.13 3 B 3.7.17 1 B 3.9.3 2*BASESUPDATE PACKAGE 17-081005.

TOC 2 08/10/2005 B 3.3.3, B 3.6.8 -Removal of Hydrogen Recombiners from the bases as per Technical Specification Amendment B 3.0 2 228. B 3.3.3 is also affected by Amendment 226.B 3.3.3 3 B 3.7.11 -Add reference that if the primary coolant source of containment is in question, refer to ITS 5.5.2.B 3.3.4 1 All other bases changes for this revision are associated

.-B 3.4.11 1 with Technical Specification Amendment 226 regarding increase flexibility in Mode Restraints.

B 3.4.12 2 B3.4.15 3 B 3.4.16 2 B 3.5.3 1 B 3.6.8 1 B 3.7.4 1 B 3.7.5 3 B 3.7.11 5 B 3.8.1 2 B 3.5.2 2 09/16/2005 Reflect implementation of ER-04-2-029 as part of Stretch Power Uprate (SPU) -HHSI Modification.

B 3.6.10 2 Update LCO and Condition B to clarify. required actions consistent with FSAR.-;, ::. .BASES UPDATE P ,AC.AGE 19-1 0405 B 3.8.1 3 11/04/2005 Include operability criteria for 138 kV and 13.8 kV offsite SBAE circuits.B 3.9.1 I 1 1 07/06/2006 Clarification on effective method for ensuring shutdown__ _ I margin.

NL-09-136 Attachment 1 Page 5 of 6 AFFECTEDI I EFFECTIVE 1 SECTIONS REV DATE " DESCRIPTION

____ BASES UP~DATE P'ACK~AGE 21-11 07r2006 B 3.0 3, 11/07/2006 Reflect allowing a delay time for entering a supported system TS when the inoperability is due solely to an inoperable snubber, if risk is assessed and managed..Limiting Condition of Operation 3.0.8 is added to provide, this allowance and define the requirements and limitations of its use. (Amendment 229)BASES UPDATE PACKAGEL2-04f112067 TOC 3 04/11/2007 Implement TS Amendment 233 related to steam generator tube integrity.

83.4.4 1 B 3.4.5 1 B 3.4.6 2 B3.4.7 1 B 3.4.13 4 B 3.4.17 0___,- BA8ES"UPDATE P'AC KAGE '23-051 62007-B 3.7.2 1 2 05/16/2007 1Removal of extraneous information regarding testing_ _frequency.

SBASES UPDATE P~ACKAGE 24-10052007 B 3.3.1 3 10/05/2007 B 3.3.1 -The TS and bases currently allow a normal B 3.8.2 1 shutdown without the SR testing by reducing power 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 92 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 UPIDATE-PACKAGE 25-1 1022007 ~B 3.4.3 3 11/2/2007 Revise LTOP arming temperature and EFPY expiration B 3.4.10 1 date for RCS P/T curves to reflect implementation of B 3.4.12 3 License Amendment 235.__ ........ _, ...BASES UPDATE PACKAGE 26106272008

.TOC 6/27/2008 Revise sections to reflect Amendment 236 changing B 3.6.6 3 I sodium hydroxide to sodium tetraborate.

B 3.6.7 2

  • _ _ " _ __-________ ____ BASES UPDATE PACKAGE 27-07012008 4z B 3.4.16 3 07/31/2008 Implemenit the Bases pages of TSTF 490 for lose equivalentiodine (Amendment 237).

NL-09-136 Attachment 1 Page 6 of 6____________

BASES UPDATES PACKAGE 28-08ý2?2008 B 3.3.3 B 3.7.6.B 3.4.15 4 3 4 08/22/2008 Revise sections to reflect SSFS Engineering Standard Changes to incorporate EN fleet level QA Safety Classifications.

Clarify the method that the instrument performs containment sump flow monitoring and provide arr acceptable alternative for the VC Sump Pump Running Control Room alarm.09/16/2008 Reflect installation of Unit 2 Appendix R Diesel and removal of GTs.B 3.7.11 6 01/20/2009 Implement the Bases pages of TSTF 488 for Control Room Envelope Habitability (Amendment 239).I b 6.:.1 I 3/18/2009 Correct typographical symbol error.It 3.3.3 B 3.5.2 B 3.7.5 7/28/2009 Reflect rewiring of Train B CET K03.3 4 Reflect TS Amendment 238 (Passive Failure Analysis).

Clarify SR 3.7.5.3 and 3.7.5.4 with respect to tests that deliver flow.08/21/2009 Reflect TS Amendment 231 (TADOT).B 3.5.2 4 Addition of valves SI-2165, 2166, 2168, 2170, and 2172 and deletion of valves SI-856A and 856G of the ECCS valves :to the surveillance (Amendment 230).

ATTACHMENT 2 TO NL-09-136 REVISIONS TO INDIAN POINT 3 DOCKETED COMMITMENTS ENTERGY NUCLEAR OPERATIONS, INC.INDIAN POINT UNIT 3 DOCKET NO. 50-286 DPR-64 NL-09-136 Attachment 2 Page I of 2 INDIAN POINT 3 2008 / 2009 COMMITMENT CHANGE

SUMMARY

REPORT COMMITMENT CURRENT CHANGED DESCRIPTION NUMBER STATUS DATE p-5207 Open 03/27/09 Original text: IPN-79-102 The portion of the commitment addressed herein states, "Angle of Containment IPN-80-28 pressure relief valves is limited to 40%,".COM-79-01697 Revised text: This portion of the commitment is revised to state, 'The opening angle of the Containment pressure relief valves is limited to less than or equal to 600,".Summary of justification:

The value of 40% taken from the March 7, 1980 letter is incorrect See CR-IP3,3009-00644 CA-1 response (attached to revision form). The NRC has concluded in a December 17, 1984 Safety Evaluation Report that "the information submitted demonstrated the ability of the valves to close against the buildup of containment pressure in the event of a DBNLOCA when the valves are limited to 60 degrees or less by mechanical means." p-5683 Historical 09/18/09 Original text: IPN-81-084 "These valves will be partial stroke exercised every three months. One check COM-81-02361 valve will be full flow/full stroke exercised during a refueling outage." Revised text: Delete commitment.

Summary of justification:

Prior to IP3 entering the 4th interval, the previous code required PEO of check valves when EO was not obtainable during normal operations.

The current ASME Code (2001e/2003a) that IP3 has just updated to, no longer has this requirement.

The current Code (ISTC-3522) states that, "Open and close tests need onlyibe performed at an interval when it is practicable to perform both tests." These valves are EO/EC during Outages (ROJ-1 5) under. 3PT-R077A and B.I NL-09-136 Attachment 2 Page 2 of 2 p-10108 IPN-96-118 COM-96-05814 Open 09/04/09 Original text: Commitment is to initiate'MOV periodic verification program (IPN-96-118-03).

Revised text: Make a one-time extension to initiate MOV periodic verification program (IPN-96-118-03) for SI-HCV-638 and SI-HCV-640 (31 RHR HX OUTLET FLOW CONTROL & 32 RHR HX OUTLET FLOW CONTROL).

This will also correspond to a one-time 19-month extension to the maximum interval (10 years) between static tests to allow testing in 3R16 Refueling outage.Summary of justification:

SI-HCV-638 and SI-HCV-640 are scheduled for on-line static diagnostic testing in September 2009. To diagnostically test valves SI-HCV-638 and SI-HCV-640, it is necessary to stroke the valves CLOSED. and OPEN. The normal configuration of the valves is in the THROTILED position at full power operation for containment spray during Recirculation Phase. Stroking the valves during September puts plant personnel in a high heat stress environment.

The station is moving on-line containment work into the outage because it is inefficient to send personnel into containment for preventive maintenance work. To meet this requirement, the site (IPEC) is requesting a deferral of the late date for performing the diagnostic test on valves SI-HCV-638 and SI-HCV-640 until 01/31/2010 to accommodate diagnostic testing thesevalves.

To approve this deferral requires a one-time test-interval-extension for these valves. This is acceptable because this valves have a high safety margin (for SI-HCV-638:

close positive 552%, open positive 379%, SI-HCV-640:

close, positive 542%, open positive 371 %) and the risk ranking for this valve is low (reference Probability Safety Assessment Memorandum NEA-07-039 dated 7/31/2007).

The valves have a PM tasks that monitor the condition of the assembly every 24 months and no abnormalities have been identified.

No failures of this MOV have been observed over the past 10 years and the quarterly surveillance stroke time history for the valves does not show any abnormalities.

The valves were last tested on .9/26/1999 and 9/25/1999 to meet the commitment; the valve must be tested by the 3R16 Refueling Outage. The valves will be tested during 3R16 Refueling Outage so IPEC is requesting a 19month extension beyond the 10-year commitment.

2 ATTACHMENT 3 TO NL-09-136 REVISIONS TO THE INDIAN POINT 3 TECHNICAL REQUIREMENTS MANUAL ENTERGY NUCLEAR OPERATIONS, INC.INDIAN POINT UNIT 3 DOCKET NO. 50-286 DPR-64 NL-09-136 Attachment 3 Page 1 of 5 Unit 3 TECHNICAL REQUIREMENTS MANUAL (TRM)REVISION HISTORY AFFECTED NEW EFFECTIVE DESCRIPTION SECTIONS REV # DATE ALL 0 03/19/2001 Initial-issue of TRM in conjunction Initial with Tech Spec Amendment 205*for conversion of "current Technical Specifications" to "Improved Technical Specifications".

07/0612001 3.0 1 07/06/2001 Technical Requirements for Operation Applicability

& Technical Requirements for Surveillance Applicability 3.1 .A 1 07/06/2001 Anticipated Transient Without Scram Mitigating Systems Actuation Circuitry 3.7.A.,3 1 07/06/2001 Fire Separation Devices 3.7.A.4 1 07/06/2001 Fire Separation Systems 11/30/2001 3.3.D 1 11/30/2001 Appendix R Alternate Safe Shutdown Instrumentation 12/04/2002 1.1 1 12/04/2002 Definitions 3.3.J 0 12/04/2002 Main Feedwater Leading Edge._ _ _ _ Flowmeter 03106/2003 3.1.C.1 1 03/06/2003 Boration Systems -MODES 1,2,3&4 3.1.C.2 1 03/06/2003-Boration Systems -MODES 5 & 4 04/16/2003 3.3.B 1 04/16/2003 Meteorological Monitoring

........_ _ Instrumentation 3.3.J--- 1 04/16/2003 Main Feedwater Leading Edge....__Flowmeter 5.0 1 04/16/2003 Administrative Controls 08/15/2003

"_-3.7.A.3 2 08/15/2003 Fire Separation Devices 09/03/2003 3.3.D 2 09/03/2003 Appendix R Alternate Safe Shutdown Instrumentation Update sent Above sent to NRC with to NRC UFSAR Update NL-09-136 Attachment 3 Page 2 of 5 10/27/2003 01/21/2004_

3.7.B-1 1 01/21/04 Appendix R Alternate Safe-... _" .. .Shutdown Instrumentation 5.3.1B 2 01/21/04 Procedures 02/23/2004

"_ ___1.1 2 02/23/2004 Definition of VERIFY changed terms Condition Report and CR 3.7.A 1 Definition changed terms Condition_ _Report and CR 3.7.B 1 TRO 3.7.B.10 CBL-319 louver added 5.0_.. 2 Administrative controls on....._ _ procedures -changed.08/24/2004 1 ......._"___"_"_.....___"___'_

3.7A.1 -.-08/24/2004 Changes-to all section-of 3.7.A to reflect correct ref erendes to TRM vs. T.S. Also remove name PORC.and replace with OSRC and-references to Unit 2 "property".

3.7A.2 _ _3.7A.3 " 3.7A.4 3.7A.5 3.7A,6 " 3.7AX7 3.7.B "__5.0 -Change "Shift Supervisor" to "Shift*_ _ _ _ _ _ Manager'.10/28/2004

"___ __....._"___

3.3.B 3 10/28/2004 To correct typo on page 9 01/25/2005

... ._.- _ .... ..__* * ._.3.8.C.. 2 01/25/2005 Change to read "demonstrate oil temperature'>70°F" instead of.." 'demonstrate oil temperature of>130°F" -04/05/2005 1.1 1 .04/05/2005 Definition-of amount of Rated Thermal Power from 6067 to 3216 MWt. .--3.3.J 1 Complete section regarding LEFM was deleted.-.Needed to procedure change required-for MODE 1 3.4.A_1____.__

,__.____ ______________

,__.__ , e2pwstartup.

L3.4.A 17 7 Reference

  1. 2 was replacedwta NL-09-136 Attachment 3 Page 3 of 5 reference to the new Stretch Power Uprate.05/24/2005 5.0 5 -05/24/2005 Add the requirement to provide to the NRC, using an industry database (INPO's) the operating" ' data for each calendar month that S is described in GL. 97-02 by the last~day of the month following the end.of each calendar quarter.08122/2005_

3.0 2 08/22/2005 Change to the required frequency for TRS 3.7.B.7 for visual inspection of appendix R lighting-.units, for 184 days to 366 days.3.7 3 -Update rules of usage to reflect the'new' missed surveillance rules that.. ...._ _ were established in TSTF-358.Update sent to NRC 10/04/2005 02/02/2006 3.0 3 02/02/2006 Update rules of usage sections in 3.3.B1 4 .TRM to reflect adoption of TSTF-3.3.C 1

  • 359; "Increase Flexibility in MODE 3.3.D 3 Restraints".

3.3.F 2--3.4.C ..1 3.7.A.3 6*3.7.8 B 4 3.8.B 1 02/07/2006

__...._."_____"____,..

3.0 .4 ] 02/07/2006

[Typo correction for Surveillance

__and TROs.07/25/2006..

3.7.F 0 07/25/2006 New TRM section created to capture commitments made in letter NL-04-162 and accepted in the SER (RA-05-18).

This required relocating the TS requirements and maintaining them-as necessary to meet'App lr eqguirements, 5.4 6 07/25/2006

.Add the reporting requirements regarding annual occupational exposure -information.

TS 5.6.1 required annual submittal of an Occupational Radiation Exposure__ _ _ _ _ _ _-_ _ Report; TSTF-369 provided for the NL-09-136 Attachment 3 Page 4 of 5 elimination of this requirement from Standard Tech Specs.03106/2007 3.3.F 3 03/06/2007 Revise the TRM to provide an action if Condition B is not completed.

Added Condition B to Condition C which requires 100%recirculation mode. This is the most conservative mode for toxic gas and is action taken to reflect.inability to take corrective action with one channel out and the potential for failure of the other.3.7.B 5 03/06/2007 Valve CT-46-2 function will be changed from a vent to a root isolation valve and as such, it needs to be .included in the Safe Shutdown Analysis Report for Appendix R for this valve to be closed in the event of a plant fire and LCV-1 158-1 or -2 failing to-_ _ _ _close.3.7.B 5 03/06/2007 Revise the Unit 3 TRM surveillance requirements for Appendix R emergency lights to allow for a 2 year PM replacement of light unit batteries in lieu of annual battery testing.Update sent to NRC 09/2007 3.4.A 2 11/02/2007 Implementation of Tech Spec Amend. 235 to extend the expiration date of the RPV P/T curves and corresponding LTOP arm temperature (319 F is.increased to 330 F)3.3.F 4 03/26/2008 Revise to clarify that replacement of .atoxic gas monitor with an alternate monitor can be considered either the repair of the-existing system when using another-nmhitor that meets the design requirements of the existing system or it can be an alternate model when using a monitor that does not meet all requirements but is for.- temporary use.

NL-09-136 Attachment 3 Page 5 of 5 3.1 .A 2 08/25/2008 Revise QA Safety Classifications to 3.3.A 2 match fleet rather than old Con Ed 3.8.C 3 and NYPA designations.

3.8.B 3 08/25/2008-_

Update the TRM to reflect the.addition of the Appendix R diesel and replacement of the Gas Turbines.3.7.B 6 12/01/2008 Installation of new Appendix R 8-hour rated emergency light unit was installed in the Unit 3 Control Room to provide illumination of 125 DC distribution panels DC-31 and DC-32 in the event of loss of lighting in the CCR.3.7.F 07/06/2009 -Revise TRM 3.7.F Fuel Storage Building Emergency Ventilation System (FSBEVS) and Containment Purge System (CPS)to clarify that the reference to fuel means "irradiated" fuel and not new fuel.

INDIAN POINT ENERGY CENTER (IPEC)UNIT 3. Docket No. 50-286 File Naming Table Document Title File Name Multiple File Document -Indian Point 3 UFSAR, 2009 Rev. 03 001_1.1 Introduction

&Chapter 1, Introduction and Summary Summary.pdf Chapter 1, Plant Drawings 001_1.2 Ch 1 Drawings.pdf Chapter 1, Figures 001_1.3 Ch 1 Figures.pdf Chapter 2, Site and Environment 002_2.1 Site & Environment.pdf Chapter 2, Plant Drawings 002_2.2 Ch 2 Drawings.pdf Chapter 2, Figures 002_2.3 Ch 2 Figures.pdf ,Chapter 3, Reactor 0033.1 Reactor.pdf Chapter 3, Figures 003_3.2 Ch 3 Figures.pdf Chapter 4, Reactor Coolant System 004_4.1 Reactor Coolant Sys.pdf Chapter 4, Plant Drawings 004_4.2 Ch 4 Drawings.pdf Chapter 4, Figures 004_4.3 Ch 4 Figures.pdf Chapter 5, Containment 005_5.1 Containment.pdf Chapter 5, Plant Drawings 005_5.2 Ch 5 Drawings.pdf Chapter 5, Figures 005_5.3 Ch 5 Figures.pdf Features 006_6.1 Engineered Safety Chapter 6, Engineered Safety FeFeatures.pdf jChapter 6, Plant Drawings 006_6.2 Oh 6 Drawings.pdf SChapter 6, Figures 006_6.3 Oh 6 Figures.pdf 1Chapter Instrumentation and Control 007_7.1 Instrumentation

&Control.pdf Chapter 7, Plant Drawings 007-7.2 Ch 7 Drawings.pdf Chapter 7, Figures 007_7.3 Ch 7 Figures.pdf Chapter 8, Electrical Systems 008_8.1 Electrical Systems.pdf Chapter 8, Plant Drawings 008_8.2 Ch 8 Drawings.pdf Chapter 9, Auxiliary and Emergency Systems 009_9.1 Auxiliary

& Emerg Sys.pdf Chapter 9, Plant Drawings 009_9.2 Ch 9 Drawings.pdf Chapter 9, Figures 009_9.3 Ch 9 Figures.pdf Chapter 10, Steam and Power Conversion System 010_10.1 Steam & Power Cony I Chapter 10, Plant Drawings 010_10.2 Ch 10 Drawings.pdf Chapter 10, Figures 010_10.3 Ch 10 Figures.pdf Chapter 11, Waste Disposal and Radiation 011_11.1 Waste Dis & Rad Prot Protection System Sys.pdf Chapter 11, Plant Drawings 011_11.2 Ch 11 Drawings.pdf Chapter 11, Figures 011_11.3 Ch 11 Figures.pdf Chapter 12, Conduct of Operation 012_12.1 Conduct of Operation.pdf Chapter 12, Figures 012_12.2 Ch 12 Figures.pdf Chapter 13, Initial Test and Operation 013_13.1 Initial Test & Oper.pdf Chapter 13, Figures 01313.2 Ch 13 Figures.pdf Chapter 14, Safety Analysis 014_14.1 Safety Analysis.pdf Chapter 14, Figures 014_14.2 Ch 14 Figures.pdf Chapter 15, Technical Specifications 015_15.1 TS.pdf Chapter 16, Design Criteria for Structures and 016_16.1 Design Criteria Stuct &Equipment Equip.pdf Chapter 16, Design Criteria for Structures and 016_16.2 Ch 16 Figures.pdf Equipment Chapter 17, Quality Assurance Program 017_17.1 QA Program.pdf Information Key 018_18.1 Information Key.pdf Table of Contents (TOC) 019_19.1 TOC.pdf Single File Documents Indian Point 3 Technical Requirements Manual 001_1P3 TRM.pdf (TRM)Indian Point 3 Technical Specification Bases 002_1P3 Technical Specification Bases.pdf 2

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