ML082070155

Distribution of IP3 Technical Specification Amendment 236

ML082070155
Person / Time
Site:	Indian Point
Issue date:	06/26/2008
From:	Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
IP-SMM-AD-103, Rev 0
Download: ML082070155 (40)

Text

September 27, 2007 DISTRIBUTION CONTROL LIST Document Name: IP3 ITS / BASES CC# NAME DEPARTMENT LOCATION 1 OPS PROC GP SUPERVISOR OPS PROCEDURE GROUP IP2 5 CONTROL ROOM OPERATIONS IP3 11 RES DEPARTMENT MGR RES 45-4-A 19 WALEPOLE, ROBERT LICENSING / ROOM 205 GSB-2D 20 CHEMISTRY SUPERVISOR CHEMISTRY DEPARTMENT 45-4-A 21 TSC (IP3) 53' ELEVATION IP2 22 SHIFT MANAGER OPERATIONS IP3 23 LIS LICENSING & INFO SERVICE OFFSITE 25 SIMULATOR TRAINING 48-2-A 28 RESIDENT INSPETOR US NRC 88' ELEVATION IP2 32 EOF E-PLAN EOF 47 CHAPMAN, N BECHTWL OFFSITE 50 SCOZZARO, ANTHONY WESTINGHOUSE ELECTRIC OFFSITE 61 SIMULATOR TRAINING 48-2-A 69 WALEPOLE, ROBERT LICENSING / ROOM 205 GSB/2D 99 KRAUS, KEVINV ST. EMERGENCY MGMT. OFFICE OFFSITE 106 SIM INSTRUCT AREA TRAINING #48 164 CONTROL ROOM OPERATIONS IP3 273 FAISON, CHARLENE NUCLEAR LICENSING WPO-12 319 GRANT, LEAH LRQ TRAINING #48 354 GRANT, LEAH LRQ TRAINING #48 357 GRANT, LEAH ILO TRAINING 48-2-A 424 GRANT, LEAH TRAINING #48 474 OUELLETTE P ENG, PLAN & MGMT INC OFFSITE 492 UNIT 3 FSS 53' ONE STOP SHOP IP2 493 OPERATIONS FIN TEAM 33 TURBIN DECK 45-1-A 494 AOEF / A. GROSSJEAN E-PLAN WPO/12-D 496 GRANT, LEAH LRQ TRAINING #48 497 GRANT, LEAH LRQ TRAINING #48 500 GRANT, LEAH LRQ TRAINING #48 501 GRANT, LEAH LRQ TRAINING #48 512 GRANT, LEAH LRQ TRAINING #48 513 GRANT, LEAH LRQ TRAINING #48 r518 DOC-CONTROL-DESK7--*-- NRC OFFSITE

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I IPEC SITE QUALITY RELATED IP-SMM-AD-1 03 Revision 0 MANAGEMENT ADMINISTRATIVE PROCEDURE MANUAL INFORMATIONAL USE Page 13 of 21 I a ___________

ATTACHMENT 10.1 SMM CONTROLLED DOCUMENT TRANSMITTAL FORM SITE MANAGEMENT MANUAL CONTROLLED DOCUMENT TRANSMITTAL FORM - PROCEDURES Page 1 of 1 7Entergy CONTROLLED DOCUMENT TRANSMITTAL FORM - PROCEDURES TO: DISTRIBUTION DATE: 6126108 PHONE NUMBER: 271-7057 FROM: IPEC DOCUMENT CONTROL The Document(s) identified below are forwarded for use. In accordance with IP-SMM-AD-103, please review to verify receipt, incorporate the document(s) into your controlled document file, properly disposition superseded, void, or inactive document(s). Sign and return the receipt acknowledgement below within fifteen (15) working days.

AFFECTED DOCUMENT: IP3 ITS/BASES/TRM DOC # REV # TITLE INSTRUCTIONS TECH SPEC AMENDMENT 236

• • • • • • • • • • • • • • • • FOLLOW THE ATTACHED INSTRUCTIONS****************************

• • • • • • • • • • • PLEASE NOTE EFFECTIVE DATE***********

RECEIPT OF THE ABOVE LISTED DOCUMENT(S) IS HEREBY ACKNOWLEDGED. I CERTIFY THAT ALL SUPERSEDED, VOID, OR INACTIVE COPIES OF THE ABOVE LISTED DOCUMENT(S) IN MY POSSESSION HAVE BEEN REMOVED FROM USE AND ALL UPDATES HAVE BEEN PERFORMED IN ACCORDANCE WITH EFFECTIVE DATE(S) (IF APPLICABLE) AS SHOWN ON THE DOCUMENT(S).

NAME (PRINT) SIGNATURE DATE CC# 579

-I II

Distribution of IP3 Technical Specification Amendment 236 (Approved by NRC June 9, 2008)

Pages are to be inserted into your controlled copy of the IP3 Improved Technical Specifications following the instructions listed below. The TAB notation indicates which section the pages are located.

73-.. _3-TAB - Facility Operating License FOL Page 3, Amd 235 1 FOL Page 3, Amd 236 t I TAB - List of Effective Pages Pages 1 through 3, (Amd 235) Pages 1 through 3, (Amd 236)

TAB - List of Amendments Page 14 Page 14 TAB - Table of Contents Page ii, Amd 228 Page ii, Amd 236 TAB 3.6 - Containment Systems 3.6.7-1, Amd 205 3.6.7-1, Amd 236 3.6.7-2, Amd 205 DELETED Page 1 of 1

(4) ENO pursuant to the Act and 10 CFR Parts 30, 40 and 70, Amdt. 203 to receive, possess, and use in amounts as required any 11/27/00 byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; (5) ENO pursuant to the Act and 10 CFR Parts 30 and 70, to Amdt. 203 possess, but not separate, such byproduct and special 11/27/00 nuclear materials as may be produced by the operation of the facility.

C. This amended license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level ENO is authorized to operate the facility at steady state reactor core power levels not in excess of 3216 megawatts thermal (100% of rated power).

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 236 are hereby incorporated in the License. ENO shall operate the facility in accordance with the Technical Specifications.

(3) (DELETED) Amdt. 205 2-27-01 (4) (DELETED) Amdt. 205 2-27-01 D. (DELETED) Amdt.46 2-16-83 E. (DELETED) Amdt.37 5-14-81 F. This amended license is also subject to appropriate conditions by the New York State Department of Environmental Conservation in its letter of May 2, 1975, to Consolidated Edison Company of New York, Inc., granting a Section 401 certification under the Federal Water Pollution Control Act Amendments of 1972.

Amendment No. 236

INDIAN POINT 3 TECHNICAL SPECIFICATIONS - APPENDIX A LIST OF EFFECTIVE PAGES Page 1 of 3 Section 3.0 2 I 2051 1 229 13 205 s2 226 Section 3.2.3 3229 1 1205 4 212 2 205 5 1 226 3 205 Section 3.1.1 4 205 1 1 205 Section 3.2.4 Section 3.1.2 1 205 1 205 2 205 2 205 3 205 Section 3.1.3 4 205 1 j 205 Section 3.3.1 2 205 1 205 Section 3.1.4 2 205 1 205 3 205 2 205 4 205 302

-~4 3 205 205 [6 205 205 5 205 7 205 Section 3.1.5 8 205 1 1 205 9 205 2 205 10 205 Section 3.1.6 11 205 1 205 12 205 2 205 13 225 3 205 14 205 Section 3.1.7 15 225 1 205 16 205 2 205 17 205 3 205 18 205 4 205 19 234 Section 3.1.8 20 234 1 J 205 Section 3.3.2 2 205 1 205 Section 3.2.1 2 205 1 205 3 205 2 205 4 205 3 205 5 205 Section 3.2.2 6 205

[1 2 205 7 [ 205 The, latest amendment reflected in this list is: Amendment 236

INDIAN POINT 3 TECHNICAL SPECIFICATIONS - APPENDIX A LIST OF EFFECTIVE PAGES Page 2 of 3

[5 235 Section 3.4.13 1i 2051 Section 3.4.4 j 1 233 1 [2 205 1 205 2 233 3 205 1

2 Section 3.4.5 1 205 205 j 1

2 Section 3.4.14 1 205 205 j

r4 5 [ 205 205 Section 3.6.3 3 ] 253 205 I 1 r 205 Section 3.4.6 4 205 J 2 205 1 F 20-5 5 1205 1 320 2 1205 Section 3.4.15 4 f205 3____ 205 - 1 226 5 f 205 Section 3.4.7 2 205 6 205 1 F23-5 3 205 Section 3.6.4 2 205 4 2051 3 205 Section 3.4.16 Section 3.6.5 Section 3.4.8 1 f226 1IIII 5 1252 205 Section 3.6.6 2253 2051 Section 3.4.9 4 j205 2 205 1IZI 225I Section 3.4.17 3 205 2225 1 1233 4 205 Section 3.4. 10 2 ] 233 Section 3.6.7 1 235 Section 3.5.1 23 2 205 1 222 2.KIDeleI.~ted Section 3.4.11 2 205 Section 3.6.8 1 226 3 205 1j 2 I 205 Section 3.5.2 Section 3.6.9 3205 1 F205 1 0 Seto 3.4.12 2 205220 1 235 3230 Section 3.6.10 2 [226 4 [205 1 205 3 235 Section 3.5.3 2 205 4 235 1 2263 205 5 205 2_ 205~I [4 205 6 235 Section 3.5.4 Section 3.7.1 7 235 1 205120 8 235 1 2 205220 9 235 Section 3.6.1 ~ 3 225 10 235 1 04205 121 235 2 205_______ Section3.2 1225Scin3.6.2 The latest amendment reflected in this list is: Amendment 236

INDIAN POINT 3 TECHNICAL SPECIFICATIONS - APPENDIX A LIST OF EFFECTIVE PAGES Page 3 of 3 1 205 13 F 232 2 205 4 232 3 205 5 234 4 205 6 234 Section 3.8,7 7 205 1 205 8 205 2 205 9 210 3 234 10 232 Section 3.8.8 11i 232 1 205 12 205 2 205 13 233 Section 3.8.9 14 233 205 15 233 205 16 Deleted Section 3.8.10 17 Deleted 1 205 18 Deleted 2 205 19 Deleted Section 3.9.1 20 205 1iI 20 21 224 Section 3.9.2 22 224 1 205 23 224 2I 205 24 234 Section 3.9.3 25 224 1 215 26 232 2 215 27 205 3 215 28 205 Section 3.9.4 29 205 1 205 30 '234 2 205 31 225 Section 3.9.5 32 . 227 1 205 33 227 2 205 34 225 Section 3.9.6 35 225 1 205 36 233 Section 4.0 37 232 1 205 38 232 2 205 39 232 3 205 40 232 Section 5.0 41 232 1 205 2 205 The latest amendment reflected in this list is: Amendment 236

Entergy Nuclear Operations, Inc Indian Point 3 Nuclear Power Plant License Amendments Page 14 AMENDMENT SUBJECT LETTER DATE 232 Adoption of TSTF-258, TSTF-308, and Related 12/13/2006 Administrative Control Changes Based on NUREG-1431 233 Adoption of TSTF-449 - Steam Generator Tube 02/13/2007 Integrity 234 Adoption of TSTF-485 and Miscellaneous 08/16/2007 Editorial Changes 235 Extension of the RCS pressure/temperature 10/04/2007 limits and corresponding OPS limits from 20 to 27.2 EFPY.

236 Replace Sodium Hydroxide Buffer with Sodium 06/09/2008 Tetraborate

Facility Operating License No. DPR-64 Appendix A - Technical Specifications TABLE OF CONTENTS 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits 3.4.2 RCS Minimum Temperature for Criticality 3.4.3 RCS Pressure and Temperature (P/T) Limits 3.4.4 RCS Loops-MODES 1 and 2 3.4.5 RCS Loops-MODE 3 3.4.6 RCS Loops-MODE 4 3.4.7 RCS Loops-MODE 5, Loops Filled 3.4.8 RCS Loops-MODE 5, Loops Not Filled 3.4.9 Pressurizer 3.4.10 Pressurizer Safety Valves 3.4.11 Pressurizer Power Operated Relief Valves (PORVs) 3.4.12 Low Temperature Overpressure Protection (LTOP) 3.4.13 RCS Operational LEAKAGE 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage 3.4.15 RCS Leakage Detection Instrumentation 3.4.16 RCS Specific Activity 3.4.17 Steam Generator (SG) Tube Integrity 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.1 Accumulators 3.5.2 ECCS-Operating 3.5.3 ECCS-Shutdown 3.5.4 Refueling Water Storage Tank (RWST) 3.6 CONTAINMENT SYSTEMS 3.6.1 Containment 3.6.2 Containment Air Locks 3.6.3 Containment Isolation Valves 3.6.4 Containment Pressure 3.6.5 Containment Air Temperature 3.6.6 Containment Spray System and Containment Fan Cooler System 3.6.7 Recirculation pH Control System 3.6.8 Not Used 3.6.9 Isolation Valve Seal Water (IVSW) System 3.6.10 Weld Channel and Penetration Pressurization System (WC & PPS)

(continued)

INDIAN POINT 3 ii Amendment 236

Recirculation pH Control System 3.6.7 3.6 CONTAINMENT SYSTEMS 3.6.7 Recirculation pH Control System LCO 3.6.7 The Recirculation pH Control System shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Recirculation pH A.1 Restore 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Control System Recirculation pH inoperable. Control System to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not AND met.

B.2 Be in MODE 5. 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.7.1 Perform a visual inspection of eight 24 Months sodium tetraborate storage baskets to verify each of the following:

a. Each storage basket is in place and intact; and,

b. Collectively contain > 8096 pounds (160 cubic feet) of sodium tetraborate decahydrate, or equivalent.

INDIAN POINT 3 3.6.7-1 Amendment 236

QUAITY RELATED IP-SMM-AD-10 3 Revision 0 isEnter~gy IPEC SITE MANAGEMENT ADMINISTRATIVE PROCEDURE MANUAL INFORMATIONAL USE Page 13 of 21 b a ATTACHMENT 10.1 SMM CONTROLLED DOCUMENT TRANSMITTAL FORM SITE MANAGEMENT MANUAL CONTROLLED DOCUMENT TRANSMITTAL FORM - PROCEDURES Page 1 of 1 is Entergy CONTROLLED DOCUMENT TRANSMITTAL FORM - PROCEDURES TO: DISTRIBUTION DATE: 6126108 PHONE NUMBER: 271-7057 FROM: IPEC DOCUMENT CONTROL The Document(s) identified below are forwarded for use. In accordance with IP-SMM-AD-1 03, please review to verify receipt, incorporate the document(s) into your controlled document file, properly disposition superseded, void, or inactive document(s). Sign and return the receipt acknowledgement below within fifteen (15) working days.

AFFECTED DOCUMENT: IP3 ITSIBASES/TRM DOC # REV # I TITLE INSTRUCTIONS IP3 BASES

• • • • • • • • • • • • • • • • FOLLOW THE ATTACHED INSTRUCTIONS****************************

• • • • • • • • • • • PLEASE NOTE EFFECTIVE DATE***********

RECEIPT OF THE ABOVE LISTED DOCUMENT(S) IS HEREBY ACKNOWLEDGED. I CERTIFY THAT ALL SUPERSEDED, VOID, OR INACTIVE COPIES OF THE ABOVE LISTED DOCUMENT(S) IN MY POSSESSION HAVE BEEN REMOVED FROM USE AND ALL UPDATES HAVE BEEN PERFORMED IN ACCORDANCE WITH EFFECTIVE DATE(S) (IF APPLICABLE) AS SHOWN ON THE DOCUMENT(S).

NAME (PRINT) SIGNATURE DATE CC# 57*

NDIAN POINT 3 TECHNICAL SPECIFICATION BASES For immediate distribution, regarding implementation of License Amendment 236 INSTRUCTIONS FOR UPDATE: 26-06/27/2008 Pages are to be inserted into your controlled copy of the IP3 Technical Specifications Bases following the instructions listed below. The TAB notation indicates which section the pages are located.

M~ ~~ -L -"A z!L TAB - List Of Effective Sections List of Effective Sections, Rev. 25 List of Effective Sections, Rev. 26 (6 pages) (6 pages)

TAB - Table of Contents TOC, Rev. 3 TOC, Rev. 4 (4 pages) J (4 pages)

TAB 3.6 - Containment Systems B 3.6.6; Rev 2 13 pages B 3.6.6; Rev 3 13 pages B 3.6.7; Rev 1 6 pages B 3.6.7; Rev 2 4 pages Page 1 of 1

TECHNICAL SPECIFICATION BASES LIST OF EFFECTIVE SECTIONS BASES NUMBER EFFECTIVE BASES NUMBER EFFECTIVE SECTION REV OF PAGES DATE SECTION REV OF PAGES DATE TOC 3 4 04/11/2007 B 3.5.3 1 4 08/10/2005

...B-20 SAFEl LIMITS B 3.5.4 0 9 03/19/2001 B 2.1.1 1 4 [06/03/2005 B 2.1.2 1 4 06/03/2005 B 3.6.1 0 5 03/19/2001

..B'3-0.0LCOANDSR, APPLICABILIY B 3.6.2 1 9 06/03/2005 B 3.0 3 18 11/07/2006 B 3.6.3 0 17 03/19/2001 B31REACTIVITY CONTROL B 3.6.4 0 3 03/19/2001 B 3.1.1 1 6 06/03/2005 B 3.6.5 1 5 06/20/2003 B 3.1.2 0 7 03/19/2001 B 3.6.6 3 13 0612712008 B 3.1.3 1 7 10/27/2004 B 3.6.7 2 4 0612712008 B 3.1.4 0 13 03/19/2001 B 3.6.8 1 1 08/10/2005 B 3.1.5 0 5 03/19/2001 B 3.6.9 1 8 06/03/2005 B 3.1.6 0 6 03/19/2001 B 3.6.10 2 12 09/16//2005 B 3.1.7 0 8 03/19/2001 ______ B3~ PLNTSYSTEMS B 3.1.8 0 7 03/19/2001 B 3.7.1 2 6 06/03/2005 B3.2, POWER- DISTRIBUTION, LIMITS: B 3.7.2 2 10 05/16/2007 B 3.2.1 0 7 03/19/2001 B 3.7.3 1 7 05/18/2001 B 3.2.2 1 7 06/03/2005 B 3.7.4 1 4 08/10/2005 B 3.2.3 0 9 03/19/2001 B 3.7.5 3 9 08/10/2005 B 3.2.4 0 7 03/19/2001 B 3.7.6 2 4 06/03/2005

_ 3.3 INSTRUIMENTATION.

_B  : B 3.7.7 1 4 12/17/2004 B 3.3.1 3 57 10/05/2007 B 3.7.8 1 7 06/03/2005 B 3.3.2 4 45 04/11/2005 B 3.7.9 2 9 06/03/2005 B 3.3.3 3 18 08/10/2005 B 3.7.10 1 3 06/03/2005 B 3.3.4 1 6 08/10/2005 B 3.7.11 5 7 08/10/2005 B 3.3.5 1 6 10/27/2004 B 3.7.12 1 4 04/11/2005 B 3.3.6 1 8 04/11/2005 B 3.7.13 3 7 06/03/2005 B 3.3.7 1 6 04/11/2005 B 3.7.14 1 3 04/11/2005 B 3.3.8 2 4 06/03/2005 B 3.7.15 0 5 03/19/2001 B 3.4'REACTOR COOLANT SYSTEM B 3.7.16 0 6 03/19/2001 B 3.4.1 1 6 06/03/2005 B 3.7.17 1 4 06/03/2005 B 3.4.2 0 3 03/19/2001 B3.8 ELECTRICAL POWE B 3.4.3 3 9 06/03/2005 B 3.8.1 3 30 11/04/2005 B 3.4.4 1 4 04/11/2007 B 3.8.2 1 7 10/05/2007 B 3.4.5 1 6 04/11/2007 B 3.8.3 0 13 03/19/2001 B 3.4.6 2 6 04/11/2007 B 3.8.4 1 11 01/22/2002 B 3.4.7 1 7 04/11/2007 B 3.8.5 0 4 03/19/2001 B 3.4.8 0 4 03/19/2001 B 3.8.6 0 8 03/19/2001 B 3.4.9 3 5 06/03/2005 B 3.8.7 1 8 06/20/2003 B 3.4.10 1 5 03/19/2001 B 3.8.8 1 4 06/20/2003 B 3.4.11 1 7 08/10/2005 B 3.8.9 2 14 06/20/2003 B 3.4.12 3 19 08/10/2005 B 3.8.10 -0 4 03/19/2001 B 3.4.13 4 7 04/11/2007 B'3.9gREFUELING_*OPERATIONS' B 3.4.14 0 10 03/19/2001 B 3.9.1 1 4 07/06/2006 B 3.4.15 3 7 08/10/2005 B 3.9.2 0 4 03/19/2001 B 3.4.16 2 6 08/10/2005 B 3.9.3 2 7 06/03/2005 B 3.9.4 0 4 03/19/2001 B 3.4.17 0 8 04/11/2007 B 3.9.5 0 4 03/19/2001 B 3.5 ECCS B 3.9.6 2 3 04/11/2005 B 3.5.1 1 10 10/27/2004 B 3.5.2 2 13 09/16/2005 INDIAN POINT 3 Page 1 of 6 Revision 26

TECHNICAL SPECIFICATION BASES REVISION HISTORY REVISION HISTORY FOR IP3 BASES 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'.

PA OGEf.I03190.

_._BASES&UPDATE Changes regarding containment sump flow monitor per B 3.4.13 1 03/19/01 NSE 01-3-018 LWD Rev 0.

B 3.4.15 Change issued concurrent with Rev 0.

BASES UPDATE PACN GE0E02-O51801 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

'BASESU UDTE PACKAGE- 03-11 19,01 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 97 439, 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 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.'

BASES 1PDATE- P. CGEK0,40q12202 -

B 3.3.2 2 01/22/02 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-0 PDATEPACK EO-90, 0 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.

B 3.7.9 1 09/30/02 Changes regarding SWN 1 and -2 valves per EVAL-00-3-095 SWS, Rev 0.

INDIAN POINT 3 Page 2 of 6 Revision 26

TECHNICAL SPECIFICATION BASES REVISION HISTORY AFFECTED EFFECTIVE SECTIONS REV DATE DESCRIPTION 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 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.

B 3.4.9 1 03/28/2003 Changes to reflect Tech Spec Amendment 216 regarding I_ relaxation of pressurizer level limits in MODE 3.

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 022.

B 3.8.9 2 06/20/2003 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.

____ EASS UDAT PAKAGE 11-12f004 B 3.7.7 1 12/17/2004 Addition of valves CT-1300 and CT-1302 to Surveillance SR 3.7.7.2 to verify that all city water header supply isolation valves are open. Reflects Tech Spec Amendment 218.

, BASESW., DATEPACKAG 1-01240 B 3.7.11 3 01/24/2005 Temporary allowance for use of KI/SCBA for unfiltered inleakage above limit.

INDIAN POINT 3 Page 3 of 6 Revision 26

TECHNICAL SPECIFICATION BASES REVISION HISTORY AFFECTED EFFECTIVE SECTIONS REV DATE DESCRIPTION

_BASES UPDATEýPACKAý'GEý13!-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 UPDATE PACKAGE1,4-0307O05 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 PACKAJQE.GE,1*5-0411:05 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.

BASES&UPDATEPACK'GE1,`6'-060305.-

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 B 3.7.1 2 B 3.7.2 1 B 3.7.5 2 B 3.7.6 2 B 3.7.8 1 B 3.7.9 2 B 3.7.10 1 B 3.7.13 3 B 3.7.17 1 B 3.9.3 2 INDIAN POINT 3 Page 4 of 6 Revision 26

TECHNICAL SPECIFICATION BASES REVISION HISTORY AFFECTED EFFECTIVE SECTIONS REV DATE DESCRIPTION BASES UPDATE PACKAG E ,'.17-08.ý1*0*05 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 B 3.4.15 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 BASES UPDATE PACKAGE 18gi09-1605 Q 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 PACKAGE 19-110405.

B 3.8.1 3 11/04/2005 Include operability criteria for 138 kV and 13.8 kV offsite I circuits.

BASES UPDATE-PACKAGE-20-070606- .

B 3.9.1 1 07/06/2006 Clarification on effective method for ensuring shutdown margin.

INDIAN POINT 3 Page 5 of 6 Revision 26

TECHNICAL SPECIFICATION BASES REVISION HISTORY AFFECTED EFFECTIVE SECTIONS REV DATE DESCRIPTION BASES UPDATE:PACKAGE 21-1I07206.

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 PACKAGE 22-04.l',11:2007.

TOC 3 04/11/2007 Implement TS Amendment 233 related to steam generator tube integrity.

B 3.4.4 1 B 3.4.5 1 B 3.4.6 2 B 3.4.7 1 B 3.4.13 4 B 3.4.17 0 BASES UPDATE PAC'AGE.23-.051,62007 B 3.7.2 2 05/16/2007 ý Removal of extraneous information regarding testing frequency.

BASES UPDATE PACKAGE 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 UPDATE PACKAGE 25;-11022007 Revise LTOP arming temperature and EFPY expiration date for RCS P/T curves to reflect implementation of License Amendment 235.

JPDATERPACKGE 26-06272008 Revise sections to reflect Amendment 236 changing sodium hydroxide to sodium tetraborate INDIAN POINT 3 Page 6 of 6 Revision 26

Facility Operating License No DPR-64 Appendix A - Technical Specification Bases TABLE OF CONTENTS B.2.0 SAFETY LIMITS (SLs)

B.2.1.1 Reactor Core SLs B.2.1.2 Reactor Coolant System Pressure SL B.3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY B.3.O SURVEILLANCE REQUIREMENT (SR) APPLICABILITY B.3.1 REACTIVITY CONTROL SYSTEMS B.3.1.1 SHUTDOWN MARGIN B.3.1.2 Core Reactivity B.3.1.3 Moderator Temperature Coefficient (MTC)

B.3.1.4 Rod Group Alignment Limits B.3.1.5 Shutdown Bank Insertion Limits B.3.1.6 Control Bank Insertion Limits B.3.1.7 Rod Position Indication B.3.1.8 PHYSICS TESTS Exceptions-MODE 2 B.3.2 POWER DISTRIBUTION LIMITS B.3.2.1 Heat Flux Hot Channel Factor (FQ(Z))

B.3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FNAH)

B.3.2.3 AXIAL FLUX DIFFERENCE (AFD)

B.3.2.4 QUADRANT POWER TILT RATIO (QPTR)

B.3.3 INSTRUMENTATION B.3.3.1 Reactor Protection System (RPS) Instrumentation B.3.3.2 Engineered Safety Feature Actuation System (ESFAS)

Instrumentation B.3.3.3 Post Accident Monitoring (PAM) Instrumentation B.3.3.4 Remote Shutdown B.3.3.5 Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation B.3.3.6 Containment Purge System and Pressure Relief Line Isolation Instrumentation B.3.3.7 Control Room Ventilation (CRVS) Actuation Instrumentation B.3.3.8 Fuel Storage Building Emergency Ventilation System (FSBEVS)

Actuation Instrumentation (continued)

INDIAN POINT 3 B i Revision 4

Facility Operating License No DPR-64 Appendix A - Technical Specification Bases TABLE OF CONTENTS (continued)

B.3.4 REACTOR COOLANT SYSTEM (RCS)

B.3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits B.3.4.2 RCS Minimum Temperature for Criticality B.3.4.3 RCS Pressure and Temperature (P/T) Limits B.3.4.4 RCS Loops-MODES 1 and 2 B.3.4.5 RCS Loops-MODE 3 B.3.4.6 RCS Loops-MODE 4 B.3.4.7 RCS Loops-MODE 5, Loops Filled B.3.4.8 RCS Loops-MODE 5, Loops Not Filled B.3.4.9 Pressurizer B.3.4.10 Pressurizer Safety Valves B.3.4.11 Pressurizer Power Operated Relief Valves (PORVs)

B.3.4.12 Low Temperature Overpressure Protection (LTOP)

B.3.4.13 RCS Operational LEAKAGE B.3.4.14 RCS Pressure Isolation Valve (PIV) Leakage B.3.4.15 RCS Leakage Detection Instrumentation B.3.4.16 RCS Specific Activity B.3.4.17 Steam Generator (SG) Tube Integrity B.3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)

B.3.5.1 Accumulators B.3.5.2 ECCS-Operating B.3.5.3 ECCS--Shutdown B.3.5.4 Refueling Water Storage Tank (RWST)

B.3.6 CONTAINMENT SYSTEMS B.3.6.1 Containment B.3.6.2 Containment Air Locks B.3.6.3 Containment Isolation Valves B.3.6.4 Containment Pressure B.3.6.5 Containment Air Temperature B.3.6.6 Containment Spray System and Containment Fan Cooler System B.3.6.7 Recirculation pH Control System B.3.6.8 Not Used B.3.6.9 Isolation Valve Seal Water (IVSW) System B.3.6.10 Weld Channel and Penetration Pressurization System (WC & PPS)

(continued)

INDIAN POINT 3 B ii Revision 4

Facility Operating License No DPR-64 Appendix A - Technical Specification Bases TABLE OF CONTENTS (continued)

B.3.7 PLANT SYSTEMS B.3.7.1 Main Steam Safety Valves (MSSVs)

B.3.7.2 Main Steam Isolation Valves (MSIVs) and Main Steam Check Valves (MSCVs)

B.3.7.3 Main Boiler Feedpump Discharge Valves (MBFPDVs), Main Feedwater Regulation Valves (MFRVs), Main Feedwater Inlet Isolation Valves (MFIIVs) and Main Feedwater (MF) Low Flow Bypass Valves B.3.7.4 Atmospheric Dump Valves (ADVs)

B.3.7.5 Auxiliary Feedwater (AFW) System B.3.7.6 Condensate Storage Tank (CST)

B.3.7.7 City Water (CW)

B.3.7.8 Component Cooling Water (CCW) System B.3.7.9 Service Water (SW) System B.3.7.10 Ultimate Heat Sink (UHS)

B.3.7.11 Control Room Ventilation System (CRVS)

B.3.7.12 Control Room Air Conditioning System (CRACS)

B.3.7.13 Fuel Storage Building Emergency Ventilation System (FSBEVS)

B.3.7.14 Spent Fuel Pit Water Level B.3.7.15 Spent Fuel Pit Boron Concentration B.3.7.16 Spent Fuel Assembly Storage B.3,7.17 Secondary Specific Activity B.3.8 ELECTRICAL POWER SYSTEMS B.3.8.1 AC Sources--Operating B.3.8.2 AC Sources--Shutdown B.3.8.3 Diesel Fuel Oil and Starting Air B.3.8.4 DC Sources--Operating B.3.8.5 DC Sources-Shutdown B.3.8.6 Battery Cell Parameters B. 3.8.7 Inverters--Operating B.3.8.8 Inverters--Shutdown B.3.8.9 Distribution Systems -Operating B. 3.8.10 Distribution Systems--Shutdown (continued)

INDIAN POINT 3 B iii Revision 4

Facility Operating License No DPR-64 Appendix A - Technical Specification Bases TABLE OF CONTENTS (continued)

B.3.9 REFUELING OPERATIONS B.3.9.1 Boron Concentration B.3.9.2 Nuclear Instrumentation B.3.9.3 Containment Penetrations B.3.9.4 Residual Heat Removal (RHR) and Coolant Circulation-High Water Level B.3.9.5 Residual Heat Removal (RHR) and Coolant Circulation-Low Water Level B.3.9.6 Refueling Cavity Water Level INDIAN POINT 3 B iv Revision 4

Containment Spray System and Containment Fan Cooler System B 3.6.6 B 3.6 CMYJAI*tffN SYSTEMS B 3.6.6 Contairment Spray System and Contaiment Fan Cooler System BASES B40UGJ The ContainTent Spray System and Coatainment Fan Cooler System provide contairnent atmosphere cooling to limit post accident pressure and temperature in containernt to less than the design values. Reduction of contairnent pressure and the iodine removal capability reduces the release of fission product radioactivity from cortairent to the envirorert, in the event of a Design Basis Accident (DBA), to within limits. The Contairient Spray and Containment Fan Cooler systems are designed to meet the requireTnts of 10 GFR 50, Appendix A, GDC 38, "Contairnent Heat Remival, " GDC 39, "Inspection of Contairnent Heat Removal Systems," GDC 40, "Testing of Containment Hleat Removal Systems," GDC 41, "Contaimrent Atnosphere Cleanup," G(C 42, "Inspection of Contaiment Atmosphere Cleanup Systems," and GXC 43, "Testing of Contairnent Atmosphere Cleanup Systems" (Ref. 1).

The Contairnent Spray System and Contaiment Fan Cooler System are Engineered Safety Feature (ESF) systems. They are designed to ensure that the heat removal capability required during the post accident period can be attained. The Containment Spray System and the Contairrent Fan Cooler System provide redundant methods to limit and maintain post accident conditions to less than the contairnent design values.

Contairent Spray System The Contairrent Spray System consists of two separate trains. Each train includes a ccntairnent spray pRip, piping and valves and is independently capable of delivering ore-half of the design flow needed to maintain the post-accident containment pressure below 47 psig. The spray water is injected into the containnent through spray nozzles connected to four 360 degree ring headers located in the contairnent dome area. Each train supplies two of the four ring headers. Each train is powered frcn a separate safeguards power train. The refueling wter storage tank (WST) supplies borated water to the Containment Spray System during the injection phase of operation.

(continued)

INDIAN POINT 3 B 3.6.6 - I Revision 3

Containment Spray System and Containment Fan Cooler System B 3.6.6 BASES B GOUMM After the Refueling Water Storage Tank has been exhausted, the (continued) contairment recirculation pumps or the Residual Heat Removal (R*JR) pumps are used to supply the Contairnent Spray ring headers for the long-terni containTent cooling and iodine removal during the containTent recirculation phase. In this configuration, the R-R heat exchangers provide the necessary cooling of the recirculated contaimrent spray.

The Contairnent Spray System provides a spray of cold borated water into the u*per regions of contairment to reduce the contairnent pressure and temperature.

Additionally, these systems reduce fission products frem the contairrrent atmosphere during a DBA. The W solution teoerature is an important factor in determining the heat removal capability of the Contairnent Spray System during the injection phase. In the reci rcul ation mode of operati on, heat is removed from the contairnient su*Ip or recirculation suIp water by the residual heat removal heat exchangers. Both trains of the Contairnent Spray System are needed to provide adequate spray coverage to meet the system design requirements for contairnent heat removal assuiing the Fan Cooler System is not available.

The Recirculation pH Control System functions by dissolving STB into the Containient Spray Water. The resulting alkaline pH of the spray enhances the ability of the spray to scavenge fission products from the containnent atnosphere. The STB dissolved in the spray also ensures an alkaline pH for the solution recirculated in the contairnent surp. The alkaline pH of the containrent sup water minimizes the evolution of iodine and minimizes the occurrence of chloride and caustic stress corrosion on mechanical systems and ccaxoonents exposed to the fluid.

The Contairrent Spray System is actuated either automatically by a contairnent High-High pressure signal or manually. An autimatic actuation starts the tM contairment spray pjips, opens the contairient spray puip discharge valves, and begins the injection phase. A manual actuation of the Contairnent Spray System requires the operator to actuate two separate push buttons on the main control board to begin the same sequence. The injection phase continues until the W water supply is exhausted.

After the Refueling Water Storage Tank has been exhausted, the containment recirculation puips or the (continued)

INDIAN POINT 3 B 3.6.6 - 2 Revision 3

Containment Spray System and Containment Fan Cooler System B 3.6.6 BASES residual heat removal (H*R) pulps may be used to supply the (continued) Contairment Spray ring headers for the long-tenm contairnent cooling and iodine removal during the contairment recirculation phase. In this configuration, the RfR heat exchangers provide the necessary cooling of the recirculated containment spray. The Contairment Spray function in the recirculation mode may be used to maintain an equilibriun temperature betwen the contairrent atmosphere and the recirculated SLmp water. The Contairment Spray furnction in the recirculation mode is controlled by the operator in accordance with the emergency operating procedures.

Contairnent Fan Cooler System The Contairment Fan Cooler System consists of five 20% capacity Fan Cooler Units (FCOs) located inside containment. These FCUs are used for bath normal and post accident cooling of the contaiment atmrosphere. Each FCU consists of a motor, fan. cooling coils, moisture separators, HEPA filters, carbon filters, darers, duct distribution system, instruTeatation and controls. Service water is supplied to the cooling coils to perform the heat remival function.

During normal plant operation, the moisture separators, HEPA filters and activated carbon filter assembly are isolated frcm the main air recirculation streaw. In this configuration, service water is supplied to all five FCJs and two or more FOJs fans are typically operated to limit the ambient contairment air temperature during norml umit operation to less than the limit specified in LCO 3.6.5, "Contairrent Air TeTlerature."

This temperature limitation ensures that the containmret temperature does not exceed the initial temperature conditions assumed for the DBAs.

In post accident operation following an actuation signal, the Contairment Cooling System fans are designed to start autcmatically. Additionally, the actuation signal causes the air flow (air-steam mixture) in each FCU to be split into two parts by a bypass flow control damper that fails to a pre-set position for accident operation. A mininui of 8000 cfin is directed through the FCU filtration section (moisture separators, HEPA filters, and carbon filter assembly) with the remainder of the air flow bypassing the (continued)

INDIAN POIT 3 B 3.6.6 - 3 Revision 3

Containment Spray System and Containment Fan Cooler System B 3.6.6 BA~SES filtration section. Both the filtered and unfiltered FCU flow passes S

(continued) through the cooling coils. The teraerature of the service water is an irportant factor in the heat reioval capability of the fan units. The accident analysis assuies 1400 gpm of service (cooling) water with a maxinun river water inlet teTperature of 950 F is supplied to each FU,.

Contairmient Coolinq and Iodine Removal Function The contairment cooling and iodine reioval fLuntions are provided by a cambination of the contairret spray and the containrent fan cooler systems.

Requirements for Contairment Spray Trains may be designated by the nuiber of the contairmnt. spray puip or the associated safeguards power train. Containrent Spray Train 31 is associated with Safeguards Powr Train 5A which is supported by [G 33.

Contairment Spray Train 32 is associated with Safeguards Power Train 6A which is supported by DG 32.

Requirements for the five fan cooler units are designated by grouping the 5 fan cooler units into three trains based on' the safeguards po~er train needed to support Operability. This results in the following designations:

Fan Cooler Train 5A consists of FCJ 31 and FCU 33; Fan Cooler Train 2A/3A consists of FCU 32 and FCJ 34; and Fan Cooler Train 6A consists of FCU 35.

The configuration with one contairnent spray train and tM fan cooler trains is the

-- onfi*-ratidn availablefollcwing the loss of any safeguards poer train (e.g., diesel failure).

(continued)

INDIAN POINT 3 B 3.6.6 - 4 Revision 3

Containment Spray System and Containment Fan Cooler System B 3.6.6 B4SES APPLICABLE SAFETY ANALYSES The Cotairent Spray System and Containiet Fan Cooler System limit the temperature and pressure that could be experienced following a DBA. The limiting [BAs considered are the loss of coolant accident (LOCA) and the steam line break (SLB). The LOCA and SLB are analyzed using.coiuter codes designed to predict the resultant containTelt pressure and temperature transients. No DBAs are assuied to occur simultanmusly or consecutively. The postulated DBAs are analyzed with regard to contairvent ESF systems. assuning the loss of ore safeguards poer train, which is the worst case single active failure and results in ore train of Containrient Spray and one train of Fan Coolers being rendered inoperable.

The analysis and evaluation show that under the worst case scenario, the highest peak contairnert pressure and temperature may result frcn either a LOCA or SLB, depending on the cycle specific analysis (Refs. 4 and 6). Both results meet the intent of the design basis. (See the Bases for LOD 3.6.4, "Containment Pressure," and LCO 3.6.5 for a detailed discussion.) The analyses and evaluations assume a unit specific power level of 10Z% and initial (pre-accident) containment conditions of 130 cF and 2.5 psig and a service water inlet temperature of 95 IF. The analyses also assune a response time delayed initiation to provide conservative peak calculated contaiment pressure and teTperature responses.

For certain aspects of transient accident analyses, maximizing the calculated containnent pressure is not conservative.

In particular, the effectiveness of the Emergency Core Cooling System during the core reflood phase of a LOCA analysis increases with increasing contairTent backpressure.

• For- these calculations, the contairlint backpressure -is calculated in a manner designed to conservatively minimize, rather than maximize, the calculated transient contairnent pressures in accordance with 10 CFR 50. Appendix K (Ref. 2).

(continued)

INDIAN POINT 3 B 3.6.6 - 5 Revision 3

Containment Spray System and Containment Fan Cooler System B 3.6.6 BlASES APPLICABLE SAFETY ANALYSES (continued)

The effect of an inadvertent contairm t spray activation has been analyzed. An inadvertent spray activation results in a rapid reduction of contairnEt pressure and is associated with the sudden cooling effect in the interior of a leak tight contairment. Additional docuentation is provided in the Bases for LCOD 3.6.4.

The mcdeled Contairm t Spray System actuation from the containrent analysis is based on a response time associated with exceeding the contairment High-High pressure setpoint to achieving full flow through the contairuent spray nozzles. The Contairrent Spray Systen total response time includes diesel generator (DG) startup (for loss of offsite poer), loading of equipient, contairmnnt spray pup startup, and spray line filling.

Contairnent cooling train performance for post accident conditions is given in References 3, 4 and 6. The result of the analysis is that accident analysis assurptions regarding contairment air cooling and iodine renoval are met by one contairnent spray train and any tMo fan cooler trains (i.e., at least three fan cooler units).

This configuration is the configuration available following the loss of any safeguards power train (e.g., diesel failure). S (continued)

INIAN POINT 3 B 3.6.6 - 6 Revision 3

Containment Spray System and Containment Fan Cooler System B 3.6.6 BASES APPLICABLE SAFETY ANALYSES (continued)

The mocdeled Containment Cooling System actuation frcm the containment analysis is based upon a response tiae associated with exceeding the contairient High-High pressure setpoint to achieving full Contaiment Fan Cooler System air and safety grade cooling water flow.

The Contairment Cooling System total response time includes signal delay, 0G startup (for loss of offsite poer), and service water purp startup times (Ref.4).

The Contairrment Spray System and Corntainfent Fan Cooler System satisfy Criterion 3 of 10 CFR 50.36.

LCO Accident analysis assumptions regarding contairrent air cooling and iodine removal are met by one contairment spray train and any two fan cooler trains (i.e.. at least three fan cooler units).

This configuration is the configuration available following the loss of any safeguards power train (e.g., diesel failure).

Each Contairment Spray System includes a spray pump, spray headers, nozzles, valves, piping, instruments, and controls to ensure an OPERABLE flow path capable of taking suction from the RWST upon an ESF actuation signal.

Each FCUJ consists of a mtor, fan, cooling coils, moisture separators, HEPA filters, carbon filters, _danpers, duct distribution system, instrunentation and controls necessary to maintain an OPERABLE flow path for the contairment atnosphere through both the filtration unit and cooling coils and an OPERABLE flow path for service water through the cooling coils.

(continued)

INDIAN POINT 3 8 3.6.6 - 7 Revision 3

Containment Spray System and Containment Fan Cooler System B 3.6.6 BASES APPLICABILITY In MJODES 1, 2, 3, and 4, a DBA could cause a release of radioactive material to contaiment and an increase in contairnent pressure and toTperature requiring the operation of the contaiment spray trains and contairnent cooling trains.

In MODES 5 and 6, the probability and consequences of these events are reduced due to the pressure and temperature limitations of these M]DES. Thus, the Contairnent Spray System and Containernt Fan Cooler System are not required to be OPERABLE in MIDES 5 and 6.

ACTIONS A.1 With ore contairnment spray train"inoperable, the inoperable contairent spray train must be restored to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. In this Condition, the remining OPERABLE spray and fan cooler trains are adequate to perform the iodine removal and contairnent cooling functions. The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Completion Time takes into account the redundant heat removal capability afforded by the Contairrent Spray System, reasonable time for repairs, and low probability of a [BA occurring during this period.

The 10 day portion of the Completion Time for Required Action A.1 is based upon engineering judgment. It takes into account the low probability of coincident entry into two Conditions in this Specification coupled with the low probability of an accident ocurring during this time. Refer to Section 1.3, "Completion Times," for a more detailed discussion of the purpose of the "from discovery of failure to meet the LWO" portion of the Completion Time.

B.1 and B.2 If the inoperable contaiment spray train cannot be restored to OPERABLE status within the required Coipletion Time, the plant must be brought to a MI)DE in which the LWO does not apply. To achieve this status, the plant must be brought to at least MME 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and to MNDE 5 within 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br />. The allowed Ccrpletion Time of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> is reasonable, based on operating experience, to reach MODE 3 from full power conditions in an orderly manner and without challenging plant systems.

(continued)

INDIAN PINT 3 B 3.6.6 - 8 Revision 3

Containment Spray System and Containment Fan Cooler System B 3.6.6 BASES ACTIONS B.1 and B.2 (continued)

The extended interval to reach MM4E 5 allows additional time for attempting restoration of the contairment spray train and is reasonable when considering the driving force for a release of radioactive material frcm the Reactor Coolant System is reduced in 13IE 3.

C.1 With ore of the required contaiment fan cooler trains inoperable, the inoperable required contairment fan cooler train must be restored to OPERABLE status within 7 days. The components in this degraded condition provide iodine removal capabilities and are capable of providing at least 100% of the heat removal reeds. The 7 day Copletion Time wes developed taking into accorrt the redundant heat renoval capabilities afforded by combinations of the Containment Spray Systein and Contairnient Fan Cooler Systen and the low probability of DBA occurring during this period.

The 10 day portion of the Conpletion Time for Required Action C.1 is based upon engineering judgrent. It takes into account the low probability of coincident entry into two Conditions in this Specification coupled with the low probability of an accident occurring during this time. Refer to Section 1.3 for a more detailed discussion of the purpose of the "frcm discovery of failure to meet the LCO" portion of the Completion Time.

D.1 With-two required cotainpent fan cooler trains -inoperable, ore of the required contaiment cooling trains must be restored to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. This allowable out of service time is acceptable because the minimun required contairrent cooling and iodine renoval function is maintained even though this configuration is a substantial degradation from the design capability, and may be a loss of redundancy for this function.

(continued)

INDIAN FINT, 3 B 3.6.6 - 9 Revision 3

Containment Spray System and Containment Fan Cooler System B 3.6.6 BASES ACTIONS E.1 and E.2 (continued)

If the Required Action and associated CoTpletion Time of Condition C or Dof this LOD are not et, the plantnust be brought to a M3DE in hich the LOD does rut apply. To achieve this status, the plant mist be brought to at least MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and to MJDE 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowed Caipletion Times are reasonable, based on operating experience, to reach the required plant conditions frcm full po~er conditions in an orderly manner and without challenging plant systems.

F.1 With tM contairrent spray trains or any caitination of three or more containTent spray and fan cooler trains inoperable, the unit could be in a condition outside the accident analysis. Entering this Condition represents a substantial degradation of the contairnent heat removal and iodine removal function. Therefore. LOD 3.0.3 nust be entered imTediately.

SLRVEIWAE REQUIRBE*NTS SR 3.6.6.1 Verifying the correct aligrnent for manual, power operated, and autnatic valves in the contaimet spray flow path provides assurance that the proper flow paths will exist for Containment Spray System operation. This SR does not apply to valves that are locked, sealed, or otherwise secured in position, since these wre verified to be in the correct position prior to locking, sealing, or securing. This SR does not require any testing or valve ranipulation. Rather, it involves verification, through a system walkdo , that those valves outside containrent (check valves are inside contairnmnt) and capable of patentially being mispositioned are in the correct position. Valves in contaiment with reTnte position indication may be checked using reTmte position indication.

(continued)

INDIAN POINT 3 B 3.6.6 - 10 Revision 3

Containment Spray System and Containment Fan Cooler System B 3.6.6 BASES SLRVEILLt41E REQUIREW S (continued)

SR 3.6.6.2 Operating each containnent fan cooler unit for > 15 minutes ensures that all fan cooler units are OPER4LE and that all associated controls are funtioning properly. It also ensures that blockage, fan or mrtor failure, or excessive vibration can be detected for corrective action. The 92 day Frequncy was developed considering fan coolers are operated during norml plant operation, the knovw reliability of the fan units and controls, the two train redundancy available, and the low probability of significant degradation of the contairment fan cooler units occurring between surveillarces. It has also been shom to be acceptable through operating experience.

SR 3.6.6.3 Verifying that the service water flcw rate to each fan cooler unit is > 1400 gpi provides assurance that the design flow rate assured in the safety analyses will be achieved (Ref. 3). The 92 day Frequency was developed considering the knowi reliability of the Cooling Water System, the redundancy available, and the low probability of a significant degradation of flow occurring betwAen surveillances.

SR 3.6.6.4 Verifying each contairment spray pwp's developed head at the flow test point is greater than or equal to the required developed head ensures that spray pirp performance has not degraded during the cycle. Flow and differential pressure are normal tests of centrifugal pui performance required by Section XI of the AS1E Code (Ref. 5). Since the contairment spray puips cannot be tested with flow through the spray headers, they are tested on recirculation flow. This test confirms one point on the purp design curve and is indicative of overall performance. Such inservice tests confirm coironent OPERABILITY, trend performance, and detect incipient failures by abnomal performance. The Frequency of the SR is in accordance with the Inservice Testing Program.

(continued)

INDIAN PINT 3 B 3.6.6 - 11 Revision 3

Containment Spray System and Containment Fan Cooler System B 3.6.6 BASES SLRVEILLAWE REQUIRNvENTS (continued)

SR 3.6.6.5 and SR 3.6.6.6 These SRs require verification that each automatic containment spray valve actuates to its correct position and that each contairlient spray pump starts upon receipt of an actual or simulated actuation of a contairrent High-High pressure signal. This Surveillance is not required for valves that are locked, sealed, or otherwise secured in the required position under administrative controls. The tests are perfonred with the isolation valves in the spray supply lines at the containment and the spray additive tank isolation valves blocked closed.

The 24 month Frequency is based on the need to perfom these Surveillances under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillances were performed with the reactor at power. Operating exprience has shown that these components usually pass the Surveillances Wken performed at the 24 month Frequency. Therefore, the Frequency was concluded to be acceptable fram a reliability standpoint.

SR 3.6.6.7 This SR requires verification that each containment fan cooler unit starts and darrer re-positions to the Emergency mode upon receipt of an actual or simulated safety injection signal. The 24 mnnth Frequency is based on engineering judgient and has been shmn to be acceptable through operating experience. See SR 3.6.6.5 and SR 3.6.6.6, above, for further discussion of the basis for the 24 moth Frequency.

SR 3.6.6.8 This SR verifies that the required Fan Cooler Unit testing is perforred in accordance with Specification 5.5.10, Ventilation Filter Testing Program (VFTP). The VFTP includes testing the performiance of the HEPA filter, charcoal adsorber efficiency, mininun flow rate, and (continued)

INDIAN PINT 3 B 3.6.6 - 12 Revision 3

Containment Spray System and Containment Fan Cooler System B 3.6.6 BASES SYIVEILLNCE REQUIRO`UffS SR 3.6.6.8 (continued) the physical properties of the activated charcoal. Specific test Frequeicies and additional information are discussed in detail in the VFlP.

SR 3.6.6.9 With the contairnent spray inlet valves closed and the spray header drained of any solution, low pressure air or smoke can be blown through test connections. This, SR ensures that each spray nozzle is umobstnrcted and provides assurance that spray coverage of the contair*et during an accident is not degraded. Due to the passive design of the nozzle, a test at 10 year intervals is considered adequate to detect obstruction of the nozzles.

REFORMS 1. 10 CFR 50, Appendix A.

2. 10 CFR 50, Appendix K.

3. FSAR, Sections 6.3 and 6.4.

4. FSAR, Section 14.3 Table 14.3-56.

5. AIN , Boiler and Pressure Vessel Code,Section XI.

6. WCAP - 16212P, Indian Point Nuclear Powr Generating Unit No. 3 Stretch Powr Uprate NSSS and BOP Licensing Report, June 2004.

INDIAN POINT 3 B 3.6.6 - 13 Revision 3

Recirculation pH Control System B.3.6.7 B 3.6 CONTAINMENT SYSTEMS B 3.6.7 Recirculation pH Control System BASES BACKGROUND The Recirculation pH Control System is a passive safeguard with baskets of sodium tetraborate decahydrate (STB), or equivalent, that assists in reducing the iodine fission product inventory in the containment atmosphere resulting from a Design Basis Accident (DBA).

Radioiodine in its various forms is the fission product of primary concern in the evaluation of a DBA. It is absorbed by the spray from the containment atmosphere. To enhance the iodine retention capacity of the spray during recirculation from the sump, the spray solution is adjusted to an alkaline pH that promotes iodine hydrolysis, in which iodine is converted to nonvolatile forms. The sodium tetraborate decahydrate (STB) is stored in baskets in the containment building. The initial spray, a boric acid solution from the refueling water storage tank has a pH of about 4.5. As the initial spray solution and, subsequently the recirculation solution comes in contact with the STB, the STB dissolves raising the pH of the sump solution. Reference 2 indicates that the pH should be between 7.0 and 9.5 and that the potential for increased hydrogen generation from aluminum should be addressed at pH greater than 7.5. An alkaline pH minimizes the evolution of iodine as well as the occurrence of chloride and caustic stress corrosion on mechanical systems and components.

Revision 2 INDIAN POINT 3 INDIAN POINT 3 B 3.6.7-1 B 3.6.7-1 Revision 2

Recirculation pH Control System B.3.6.7 (continued)

INDIAN POINT 3 B 3.6.7-2 Revision 2

Recirculation pH Control System B.3.6.7 BASES APPLICABLE SAFETY ANALYSES Following the assumed release of radioactive materials into containment, the containment is assumed to leak at its design value volume following the accident. The analysis assumes that 80% of containment is covered by the spray (Ref. 1).

The pH of the initial spray from the RWST is about 4.5.

The Recirculation pH Control System is a passive safeguard with the baskets of STB located in the containment. The initial spray solution and subsequently the recirculation solution come in contact with the STB in the baskets and dissolves to raise the pH. The Recirculation pH System is OPERABLE when there is sufficient STB available to guarantee a sump pH of >7.0 during the recirculation phase of a postulated LOCA. Calculation of pH was performed for STB.

The mass of STB required to provide an equilibrium sump pH solution of about 7.1 is 8,096 pounds. A 10.000 mass of STB provides a sump pH of about 7.2.

The Recirculation pH Control System satisfies Criterion 3 of 10 CFR 50.36.

LCO The Recirculation pH Control System reduces the release of radioactive material to the environment in the event of a DBA. To be considered OPERABLE, the STB baskets must be in place and intact and collectively contain >8,096 pounds (160 cubic feet) of STB or equivalent.

APPLICABILITY In MODES 1, 2, 3, and 4. a DBA could cause a release of radioactive material to containment requiring the operation of the Recirculation pH Control System. The Recirculation pH Control System assists in reducing the iodine fission product inventory prior to release to the environment.

In MODES 5 and 6. the probability and consequences of these events are reduced due to the pressure and temperature limitations in these MODES. Thus, the Recirculation pH Control System is not required to be OPERABLE in MODE 5 or 6.

INDIAN POINT 3 B 3.6.7-3 Revision 2

Recirculation pH Control System B.3.6.7 (continued)

BASES ACTIONS A.1 If the Recirculation pH Control System is inoperable, it must be restored to OPERABLE-within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The pH adjustment for corrosion protection and iodine removal enhancement is reduced in this condition. The Containment Spray System and Containment Fan Cooler System are available and would remove iodine from the containment atmosphere in the event of a DBA.

The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Completion Time takes into account the redundant flow path capabilities and the low probability of the worst case DBA occurring during this period.

B.1 and B.2 If the Recirculation pH Control System cannot be restored to OPERABLE status within the required Completion Time, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and to MODE 5 within 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br />.

The allowed Completion Time of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> is reasonable, based on operating experience, to reach MODE 3 from full power conditions in an orderly manner and without challenging plant systems. The extended interval to reach MODE 5 allows 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> for restoration of the Recirculation pH Control System in MODE 3 and 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> to reach MODE 5. This is reasonable when considering the reduced pressure and temperature conditions in MODE 3 for the release of radioactive material from the Reactor Coolant System.

SURVEILLANCE REQUIREMENTS SR 3.6.7.1 This SR provides visual verification that each of the eight storage sodium tetraborate baskets is in place and intact and collectively contain > 8,096 pounds (160 cubic feet) of sodium tetraborate decahydrate, or equivalent. This amount of STB is sufficient to ensure that the recirculation solution following a LOCA is at the correct pH level. The 24 month frequency is sufficient to ensure that the stainless steel baskets are intact and contain the appropriate amount of STB.

INDIAN POINT 3 B 3.6.7-4 Revision 2

Recirculation pH Control System B.3.6.7 (continued)

BASES REFERENCES 1. FSAR, Chapters 6 and 14.

2. NUREG-0800, "Standard Review Plan," Section 6.5.2, "Containment Spray as a Fission Product Cleanup System," Revision 4 dated March 2007 containing Branch Technical Position 6-1 "pH For Emergency Coolant Water for Pressurized Water Reactors" Revision 0 dated March 2007.

INDIAN POINT 3 B 3.6.7-5 Revision 2