ML051320261
| ML051320261 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 04/15/2005 |
| From: | Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| IP-SMM-AD-103, Rev 0 | |
| Download: ML051320261 (14) | |
Text
Page:
91 15-APR-05 DISTRIBUTION CONTROL LIST D
Document Name:
ITS/BASES/TRM CC-NAME 1
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PLANT MANAGER'S OFFICE CONTROL ROOM & MASTER RES DEPARTMENT MANAGER STEWART ANN CHEMISTRY SUPERVISOR TSC(IP3)
SHIFT MGR.(LUB-001-GEN)
LIS SIMULATOR RESIDENT INSPECTOR EOF CHAPMAN N TADEMY L. SHARON GSB TECHNICAL LIBRARY SIMULATOR CONROY PAT BARANSKI J (ALL)
SIMULATOR INSTRUCT AREA CONTROL ROOM & MASTER TROY M FAISON CHARLENE L.GRANT (LRQ-OPS TRAIN)
L.GRANT(LRQ-OPS/TRAIN)
L.GRANT(ITS/INFO ONLY)
GRANT LEAH (9 COPIES)
OUELLETTE P SCHMITT RICHIE HANSLER ROBERT 3 CLOUGHNESSY PAT L ORLANDO TOM (MANAGER)
FSS UNIT 3 OPERATIONS FIN TEAM L AEOF/A.GROSJEAN(ALL EP'S)
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RES (UNIT 3/IPEC ONLY)
LICENSING CHEMISTRY DEPARTMENT EEC BUILDING OPS (UNIT 3/IPEC ONLY)
LICENSING & INFO SERV TRAIN(UNIT 3/IPEC ONLY)
US NRC 88' ELEVATION E-PLAN (ALL EP'S)
BECHTEL WESTINGHOUSE ELECTRIC A MCCALLION/IPEC & IP3 TRAIN(UNIT 3/IPEC ONLY)
LICENSING/ROOM 205 ST. EMERG. MGMT. OFFICE TRG/3PT-D001-D006 ONLY)
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NUCLEAR LICENSING LRQ (UNIT 3/IPEC ONLY)
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NRC/SR. PROJECT MANAGER OUTAGE PLANNING LOCATION IP2 IP2 IP3(ONLY) 45-4-A GSB-2D 45-4-A IP2 IP3 OFFSITE 48-2-A IP2 EOF OFFSITE OFFSITE GSB-3B 48-2-A GSB-2D OFFSITE
- 48 IP3(ONLY) 1A WPO-12
- 48
- 48 48-2-A
- 48 OFFSITE 45-1-A 72'UNIT 2 GSB-3B 45-3-G K-IP-I210 45-1-A WPO-12D EOF
- 48
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- 48 OFFSITE OFFSITE IP3/OSB VP'
IPEC SITE QUALITY RELATED IP-SMM-AD-103 Revision 0
- E Entergy MANAGEMENT ADMINISTRATIVE PROCEDURE MANUAL INFORMATIONAL USE Page 13 of 21 ATTACHMENT 10.1 SMM CONTROLLED DOCUMENT TRANSMITTAL FORM SITE MANAGEMENT MANUAL CONTROLLED DOCUMENT TRANSMITTAL FORM - PROCEDURES Paae I of 1 Entergy CONTROLLED DOCUMENT TRANSMITTAL FORM - PROCEDURES I
TO: DISTRIBUTION DATE:
4129105 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 belowwithin fifteen (15) working days.
AFFECTED DOCUMENT:
REV#
TITLE INSTRUCTIONS S
- 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#
57t?
Distribution of IP3 Technical Specification Amendment 227 (Approved by NRC April 14, 2005)
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.
REMOVE PAGES INSERT PAGES TAB - Facility Operating License Page 3, (Amendment 226)
Page 3, (Amendment 227)
TAB - List of Effective Pages Pages 1 through 3, (Amendment 226)
Pages 1 through 3, (Amendment 227)
TAB - List of Amendments Page 13 Page 13 TAB - Table of Contents Page i (Amendment 205)
Page ii (Amendment 205)
Page iii (Amendment 207)
Page iv (Amendment 210)
Page v (Amendment 207)
Page i (Amendment 227)
Page ii (Amendment 227)
Page iii (Amendment 227)
Page iv (Amendment 227)
TAB 5.0 - Administrative Controls Page 5.0-32 (Amendment 205)
Page 5.0-33 (Amendment 205)
Page 5.0-32 (Amendment 227)
Page 5.0-33 (Amendment 227)
Page 1 of I (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 l: 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 SDecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 227 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. 227
INDIAN POINT 3 TECHNICAL SPECIFICATIONS - APPENDIX A LIST OF EFFECTIVE PAGES Page 1 of 3 Page I Amend Table of Contents 227 ii 227 iii 227 iv 227 Section 1.1 1
205 2
205 3
224 4
205 5
225 6
205 7
205 8
205 Section 1.2 1
205 2
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205 Section 1.3 1
205 2
205 3
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205 6
205 7
205 8
205 9
205 10 205 11 205 12 205 13 205 Section 1.4 1
205 2
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205 Section 2.0 1
1 225 2
205 3
205 Section 3.2.3 1
1205 2
205 3
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_205 Section 3.2.4 1
205 2
205 3
205 4
205 Section 3.3.1 1
205 2
205 3
205 4
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205 10 205 11 205 12 205 13 225 14 205 15 225 16 205 17 205 18 205 19 225 20 225 Section 3.3.2 1
205 2
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205 8
225 9
213 10 205 11 225 12 205 13 205 Section 3.3.3 1
226 2
211 3
205 4
211 5
211 Section 3.3.4 1
1226 2
205 Section 3.3.5 1
205 2 _
205 Section 3.3.6 1
205 2
205 3
205 4
205 5
205 Section 3.3.7 1
205 2
205 3
205 Section 3.3.8 1
215 2
1205 Section 3.4.1 1
225 2
1225 Section 3.4.2 1
1 205 Section 3.4.3 1
205 2
205 3
220 4
220 The latest amendment reflected in this list is: Amendment 227
INDIAN POINT 3 TECHNICAL SPECIFICATIONS - APPENDIX A LIST OF EFFECTIVE PAGES Page 2 of 3 The latest amendment reflected in this list is: Amendment 227
INDIAN POINT 3 TECHNICAL SPECIFICATIONS - APPENDIX A LIST OF EFFECTIVE PAGES Page 3 of 3 7
8 9
10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 205 205 210 205 221 205 205 205 205 205 205 205 205 205 224 224 224 224 224 205 205 205 205 206 225 227 227 225 225 205 205 205 The latest amendment reflected in this list is: Amendment 227
Entergy Nuclear Operations, Inc Indian Point 3 Nuclear Power Plant License Amendments Page 13 AMENDMENT SUBJECT LETTER DATE 217 218 219 220 221 222 223 224 225 226 227 Use of Best-Estimate Large-Break Loss of Coolant Accident analysis methodology (WCAP 12945)
Revise City Water surveillance to reflect addition of (backflow preventer) valves Revise Ventilation Filter Testing Program to adopt ASTM D3803 charcoal filter testing requirements per GL 99-02.
Extension of the RCS pressure/temperature limits and corresponding OPS limits from 16.17 to 20 EFPY.
Extension of RCP flywheel inspection interval (from 10 years to 20 years) per TSTF 421.
Inoperable accumulator time extended from 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per TSFT-370.
Extension of the allowed outage time to support the placement of the CRVS in an alternate configuration for tracer gas testing.
Full-scope adoption of alternate source term for dose consequence analysis of DBAs.
Stretch Power Uprate (4.85%) from 3067.4 MWt to 3216 MWt, and adoption of TSTF-339.
Adopt TSTF-359; Increased Flexibility in Mode Restraints.
Remove Monthly Operating Report and Occupational Radiation Exposure Report per TSTF-369 05/06/2003 08/04/2003 10/30/2003 12/03/2003 07/02/2004 08/18/2004 01/19/2005 03/22/2005 03/24/2005 04/06/2005 04/14/2005
Facility Operating License No. DPR-64 Appendix A -
Technical Specifications TABLE OF CONTENTS 1.0 USE AND APPLICATION 1.1 Definitions 1.2 Logical Connectors 1.3 Completion Times 1.4 Frequency 2.0 SAFETY LIMITS (SLs) 2.1 Safety Limits 2.2 Safety Limit Violations 3.0 LCO AND SR APPLICABILITY 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 Shutdown Margin (SDM) 3.1.2 Core Reactivity 3.1.3 Moderator Temperature Coefficient (MTC) 3.1.4 Rod Group Alignment Limits 3.1.5 Shutdown Bank Insertion Limits 3.1.6 Control Bank Insertion Limits 3.1.7 Rod Position Indication 3.1.8 PHYSICS TESTS Exceptions-MODE 2 3.2 POWER DISTRIBUTION LIMITS 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))
3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FYH) 3.2.3 AXIAL FLUX DIFFERENCE (AFD) 3.2.4 QUADRANT POWER TILT RATIO (QPTR) 3.3 INSTRUMENTATION 3.3.1 Reactor Protection System (RPS) Instrumentation 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation 3.3.3 Post Accident Monitoring (PAM) Instrumentation 3.3.4 Remote Shutdown 3.3.5 Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation 3.3.6 Containment Purge System and Pressure Relief Line Isolation Instrumentation 3.3.7 Control Room Ventilation (CRVS) Actuation Instrumentation 3.3.8 Fuel Storage Building Emergency Ventilation System (FSBEVS)
Actuation Instrumentation (continued)
INDIAN POINT 3 i
Amendment 227
Facility Operating License No. DPR-64 Appendix A -
Technical Specifications TABLE OF CONTENTS 3.4 3.4.1 3.4.2 3.4.3 3.4.4 3.4.5 3.4.6 3.4.7 3.4.8 3.4.9 3.4.10 3.4.11 3.4.12 3.4.13 3.4.14 3.4.15 3.4.16 3.5 3.5.1 3.5.2 3.5.3 3.5.4 3.6 3.6.1 3.6.2 3.6.3 3.6.4 3.6.5 3.6.6 3.6.7 3.6.8 3.6.9 3.6.10 REACTOR COOLANT SYSTEM (RCS)
RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits RCS Minimum Temperature for Criticality RCS Pressure and Temperature (P/T) Limits RCS Loops-MODES 1 and 2 RCS Loops-MODE 3 RCS Loops-MODE 4 RCS Loops-MODE 5, Loops Filled RCS Loops-MODE 5, Loops Not Filled Pressurizer Pressurizer Safety Valves Pressurizer Power Operated Relief Valves (PORVs)
Low Temperature Overpressure Protection (LTOP)
RCS Operational LEAKAGE RCS Pressure Isolation Valve (PIY) Leakage RCS Leakage Detection Instrumentation RCS Specific Activity EMERGENCY CORE COOLING SYSTEMS (ECCS)
Accumulators ECCS-Operating ECCS-Shutdown Refueling Water Storage Tank (RWST)
CONTAINMENT SYSTEMS Containment Containment Air Locks Containment Isolation Valves Containment Pressure Containment Air Temperature Containment Spray System and Containment Fan Cooler System Spray Additive System Hydrogen Recombiners Isolation Valve Seal Water (IVSW) System Weld Channel and Penetration Pressurization System (WC & PFIS)
(continued)
INDIAN POINT 3 i i Amendment 227
Facility Operating License No. DPR-64 Appendix A -
Technical Specifications TABLE OF CONTENTS 3.7 PLANT SYSTEMS 3.7.1 Main Steam Safety Valves (MSSVs) 3.7.2 Main Steam Isolation Valves (MSIVs) and Main Steam Check Valves (MSCVs) 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 3.7.4 Atmospheric Dump Valves (ADVs) 3.7.5 Auxiliary Feedwater (AFW) System 3.7.6 Condensate Storage Tank (CST) 3.7.7 City Water (CW) 3.7.8 Component Cooling Water (CCW)
System 3.7.9 Service Water (SW) System 3.7.10 Ultimate Heat Sink (UHS) 3.7.11 Control Room Ventilation System (CRVS) 3.7.12 Control Room Air Conditioning System (CRACS) 3.7.13 Fuel Storage Building Emergency Ventilation System (FSBEVS) 3.7.14 Spent Fuel Pit Water Level 3.7.15 Spent Fuel Pit Boron Concentration 3.7.16 Spent Fuel Assembly Storage 3.7.17 Secondary Specific Activity 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources-Operating 3.8.2 AC Sources-Shutdown 3.8.3 Diesel Fuel Oil and Starting Air 3.8.4 DC Sources-Operating 3.8.5 DC Sources-Shutdown 3.8.6 Battery Cell Parameters 3.8.7 Inverters-Operating 3.8.8 Inverters -Shutdown 3.8.9 Distribution Systems-Operating 3.8.10 Distribution Systems-Shutdown 3.9 REFUELING OPERATIONS 3.9.1 Boron Concentration 3.9.2 Nuclear Instrumentation 3.9.3 Containment Penetrations 3.9.4 Residual Heat Removal (RHR) and Coolant Circulation-High Water Level 3.9.5 Residual Heat Removal (RHR) and Coolant Circulation-Low Water Level 3.9.6 Refueling Cavity Water Level (continued)
INDIAN POINT 3 iii Amendment 227
Facility Operating License No. DPR-64 Appendix A -
Technical Specifications TABLE OF CONTENTS 4.0 DESIGN FEATURES 4.1 Site Location 4.2 Reactor Core 4.3 Fuel Storage 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.2 Organization 5.3 Unit Staff Qualifications 5.4 Procedures 5.5 Programs and Manuals 5.5.1 Offsite Dose Calculation Manual (ODCM) 5.5.2 Primary Coolant Sources Outside Containment 5.5.3 NOT USED 5.5.4 Radioactive Effluent Controls Program 5.5.5 Component Cyclic or Transient Limit 5.5.6 Reactor Coolant Pump Flywheel Inspection Program 5.5.7 Inservice Testing Program 5.5.8 Steam Generator (SG) Tube Surveillance Program 5.5.9 Secondary Water Chemistry Program 5.5.10 Ventilation Filter Testing Program (VFTP) 5.5.11 Explosive Gas and Storage Tank Radioactivity Monitoring Program 5.5.12 Diesel Fuel Oil Testing Program 5.5.13 Technical Specification (TS) Bases Control Program 5.5.14 Safety Function Determination Program (SFDP) 5.5.15 Containment Leakage Rate Testing Program 5.6 Reporting Requirments 5.6.1 NOT USED 5.6.2 Annual Readiological Environmental Operating Report 5.6.3 Radioactive Effluent Release Report 5.6.4 NOT USED 5.6.5 CORE OPERATING LIMITS REPORT (COLR) 5.6.6 NOT USED 5.6.7 Post Accident Monitoring Instrumentation (PAM) Report 5.6.8 Steam Generator Tube Inspection Report 5.7 High Radiation Area INDIAN POINT 3 iv Amendment 227
Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.
5.6.1 5.6.2 Not Used Annual Radiological Environmental Operating Report
NOTE-------------------------------
A single submittal may be made for a multiple unit station.
The submittal should combine sections common to all units at the station.
The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year.
The report shall include summaries, interpretations, and analyses of trends of the results of the radiological environmental monitoring program for the reporting period.
The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM),
and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.
(continued)
INDIAN POINT 3 5.0 - 32 Amendment 227
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.2 Annual Radiological Environmental Operating Report (continued)
A full listing of the information to be contained in the Annual Radiological Environmental Operating Report is provided in the ODCM.
Radioactive Effluent Release Report 5.6.3 NOTE------------------------------
A single submittal may be made for a multiple unit station. The submittal shall combine sections common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.
The Radioactive Effluent Release Report covering the operation of the unit in the previous year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50.36a.
The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR Part 50.36a and 10 CFR 50, Appendix I, Section IV.B.1.
Not Used CORE OPERATING LIMITS REPORT (COLR) 5.6.4 5.6.5
- a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:
(continued)
INDIAN POINT 3 5.0 - 33 Amendment 227