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Category:Technical Specification
MONTHYEARML21091A3052022-02-28028 February 2022 Issuance of Amendment No. 272 Revision to Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device (EPID L-2020-LLA-0051) (Non-Proprietary) ML21074A0002021-04-22022 April 2021 Issuance of Amendment No. 270 Permanently Defueled Technical Specifications ML21083A0002021-04-14014 April 2021 Issuance of Amendment No. 63 Permanently Defueled Technical Specifications ML20259A2162020-09-14014 September 2020 Defueled Safety Analysis Report, Appendix a, Permanently Defueled Technical Specifications Bases NL-20-033, Technical Specifications Proposed Change - Permanently Defueled Technical Specifications2020-04-28028 April 2020 Technical Specifications Proposed Change - Permanently Defueled Technical Specifications NL-19-078, Supplement to Technical Specifications Proposed Change - Permanently Defueled Technical Specifications2019-10-22022 October 2019 Supplement to Technical Specifications Proposed Change - Permanently Defueled Technical Specifications NL-17-137, License Amendment Request (LAR) for One-Time Extension of the Containment Type a Leak Rate Testing Frequency from 15 to 16 Years2017-12-0808 December 2017 License Amendment Request (LAR) for One-Time Extension of the Containment Type a Leak Rate Testing Frequency from 15 to 16 Years NL-17-137, Indian Point Unit No. 3 - License Amendment Request (LAR) for One-Time Extension of the Containment Type a Leak Rate Testing Frequency from 15 to 16 Years2017-12-0808 December 2017 Indian Point Unit No. 3 - License Amendment Request (LAR) for One-Time Extension of the Containment Type a Leak Rate Testing Frequency from 15 to 16 Years ML16280A2292016-09-19019 September 2016 Indian Point 2 Improved Technical Specifications Bases NL-16-109, Indian Point 2 Improved Technical Specifications Bases2016-09-19019 September 2016 Indian Point 2 Improved Technical Specifications Bases NL-15-094, Proposed Changes to Technical Specifications Regarding Reactor Vessel Heatup and Cooldown Curves and Low Temperature Overpressure Protection System Requirements2015-08-11011 August 2015 Proposed Changes to Technical Specifications Regarding Reactor Vessel Heatup and Cooldown Curves and Low Temperature Overpressure Protection System Requirements NL-15-021, Proposed License Amendment Regarding a Change to Technical Specification 3.1.4 Reactivity Control Systems Indian Point Unit Number 22015-02-12012 February 2015 Proposed License Amendment Regarding a Change to Technical Specification 3.1.4 Reactivity Control Systems Indian Point Unit Number 2 NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Specification Bases List of Effective Sections2014-09-17017 September 2014 Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Specification Bases List of Effective Sections ML14287A3002014-09-17017 September 2014 Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Specification Bases List of Effective Sections NL-14-122, Indian Point, Unit 2 - Proposed License Amendment Re an Exigent Change to Technical Specification 3.8.6, Station Battery Surveillance2014-09-15015 September 2014 Indian Point, Unit 2 - Proposed License Amendment Re an Exigent Change to Technical Specification 3.8.6, Station Battery Surveillance ML14268A3532014-09-15015 September 2014 Proposed License Amendment Re an Exigent Change to Technical Specification 3.8.6, Station Battery Surveillance NL-13-145, Proposed License Amendment to Adopt TSTF-510, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection Indian Point Unit Nuclear Generating Unit Nos. 2 and 32014-04-0101 April 2014 Proposed License Amendment to Adopt TSTF-510, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection Indian Point Unit Nuclear Generating Unit Nos. 2 and 3 NL-11-119, Proposed Change to the Technical Specification Requirement for Containment Sump Level Indication2011-10-18018 October 2011 Proposed Change to the Technical Specification Requirement for Containment Sump Level Indication NL-10-133, Supplement to Proposed License Amendment to Change Technical Specifications Regarding Surveillance Requirements for AC and DC Sources2010-12-16016 December 2010 Supplement to Proposed License Amendment to Change Technical Specifications Regarding Surveillance Requirements for AC and DC Sources ML1015506572010-06-28028 June 2010 Issuance of Amendment Refueling Water Storage Tank Level Instrumentation ML0934307192009-10-13013 October 2009 2009 Amendment Update to the Final Safety Analysis Report (Fsar), Revision 03, Technical Specification Bases, November 2009, Appendix a, B.2.0 Through B.3.9.6 NL-09-062, Proposed Technical Specification Change Regarding RWST Surveillance Requirement2009-07-23023 July 2009 Proposed Technical Specification Change Regarding RWST Surveillance Requirement ENOC-09-00009, Entergy Nuclear Operations, Inc. - License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions2009-04-27027 April 2009 Entergy Nuclear Operations, Inc. - License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions NL-09-004, License Amendment Request Regarding Surveillance Requirements for ECCS Valves Required to Be in Position with Power to the Valve Operator Removed2009-03-25025 March 2009 License Amendment Request Regarding Surveillance Requirements for ECCS Valves Required to Be in Position with Power to the Valve Operator Removed NL-08-158, Additional Information Regarding Amendment Application on Control Room Envelope Habitability2008-10-28028 October 2008 Additional Information Regarding Amendment Application on Control Room Envelope Habitability NL-08-163, (IP2) - Transmittal of Amendment Update to the Final Safety Analysis Report (Fsar), Revision 212008-10-20020 October 2008 (IP2) - Transmittal of Amendment Update to the Final Safety Analysis Report (Fsar), Revision 21 NL-08-101, Proposed Changes to Technical Specifications Regarding Diesel Generator Endurance Test Surveillance2008-07-0909 July 2008 Proposed Changes to Technical Specifications Regarding Diesel Generator Endurance Test Surveillance ML0820701552008-06-26026 June 2008 Distribution of IP3 Technical Specification Amendment 236 ML0729102922007-10-0101 October 2007 Technical Specification Bases Change ML0724801632007-07-0606 July 2007 Revision 0 to IPEC Site Management Manual, IP-SMM-AD-103, IP3 Its/Bases ML0715003222007-03-29029 March 2007 IPEC Site Management Manual, Technical Specification Bases Update 23-05/16/07 ML0711402032007-03-29029 March 2007 Technical Specification Bases ML0707205372007-02-26026 February 2007 Improved Technical Specifications, Amendment 233 ML0702903522007-01-19019 January 2007 Revision 0 to IPEC Site Management Manual, IP-SMM-AD-103, IP3 Its/Bases NL-06-099, Units, 2 and 3 - Proposed Changes to Technical Specifications: Miscellaneous Editorial Changes, Including TSTF-4852006-09-25025 September 2006 Units, 2 and 3 - Proposed Changes to Technical Specifications: Miscellaneous Editorial Changes, Including TSTF-485 ML0620003692006-04-19019 April 2006 Update to IP3 Technical Specifications Bases ML0631905242006-04-19019 April 2006 Technical Specification Bases Manual, IP-SMM-AD-103 ML0604505332006-02-13013 February 2006 Tech Spec Pages for Amendments 245 and 229 Inoperability of Snubbers ML0532004452005-10-28028 October 2005 Technical Specification Bases Changes NL-05-105, Proposed Change to Technical Specifications Regarding Emergency Core Cooling System Throttle Valve Surveillance Requirements2005-10-0303 October 2005 Proposed Change to Technical Specifications Regarding Emergency Core Cooling System Throttle Valve Surveillance Requirements NL-05-107, Proposed Change to Indian Point 2 Technical Specifications Regarding LBLOCA Analysis Methodology2005-09-26026 September 2005 Proposed Change to Indian Point 2 Technical Specifications Regarding LBLOCA Analysis Methodology ML0523702312005-08-0808 August 2005 Technical Specification Bases NL-05-065, Application for a Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process (TSTF-372)2005-06-0808 June 2005 Application for a Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process (TSTF-372) NL-05-062, Proposed Change to IP2 Technical Specifications Regarding Pressurizer Water Level Requirements, Indian Point Unit No. 22005-05-25025 May 2005 Proposed Change to IP2 Technical Specifications Regarding Pressurizer Water Level Requirements, Indian Point Unit No. 2 ML0510800342005-04-14014 April 2005 Tech Spec Pages for Amendment 242 Reporting Requirements for Annual Radiological Environmental Operating Report ML0510903802005-03-31031 March 2005 Technical Specification Bases ML0509600592005-03-25025 March 2005 Distribution of IP3 Technical Specification Amendment 224 and 225 ML0508703842005-03-24024 March 2005 Technical Specification Pages Re 4.85 Percent Stretch Power Uprate & Relocation of Cycle-Specific Parameters ML0507500422005-02-0303 February 2005 Technical Specification Bases ML0506705222005-02-0303 February 2005 Technical Specification Bases 2022-02-28
[Table view] Category:Amendment
MONTHYEARML21091A3052022-02-28028 February 2022 Issuance of Amendment No. 272 Revision to Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device (EPID L-2020-LLA-0051) (Non-Proprietary) ML21074A0002021-04-22022 April 2021 Issuance of Amendment No. 270 Permanently Defueled Technical Specifications ML21083A0002021-04-14014 April 2021 Issuance of Amendment No. 63 Permanently Defueled Technical Specifications NL-19-078, Supplement to Technical Specifications Proposed Change - Permanently Defueled Technical Specifications2019-10-22022 October 2019 Supplement to Technical Specifications Proposed Change - Permanently Defueled Technical Specifications NL-17-137, Indian Point Unit No. 3 - License Amendment Request (LAR) for One-Time Extension of the Containment Type a Leak Rate Testing Frequency from 15 to 16 Years2017-12-0808 December 2017 Indian Point Unit No. 3 - License Amendment Request (LAR) for One-Time Extension of the Containment Type a Leak Rate Testing Frequency from 15 to 16 Years NL-17-137, License Amendment Request (LAR) for One-Time Extension of the Containment Type a Leak Rate Testing Frequency from 15 to 16 Years2017-12-0808 December 2017 License Amendment Request (LAR) for One-Time Extension of the Containment Type a Leak Rate Testing Frequency from 15 to 16 Years ML1015506572010-06-28028 June 2010 Issuance of Amendment Refueling Water Storage Tank Level Instrumentation ENOC-09-00009, Entergy Nuclear Operations, Inc. - License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions2009-04-27027 April 2009 Entergy Nuclear Operations, Inc. - License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions NL-09-004, License Amendment Request Regarding Surveillance Requirements for ECCS Valves Required to Be in Position with Power to the Valve Operator Removed2009-03-25025 March 2009 License Amendment Request Regarding Surveillance Requirements for ECCS Valves Required to Be in Position with Power to the Valve Operator Removed NL-08-101, Proposed Changes to Technical Specifications Regarding Diesel Generator Endurance Test Surveillance2008-07-0909 July 2008 Proposed Changes to Technical Specifications Regarding Diesel Generator Endurance Test Surveillance ML0707205372007-02-26026 February 2007 Improved Technical Specifications, Amendment 233 NL-06-099, Units, 2 and 3 - Proposed Changes to Technical Specifications: Miscellaneous Editorial Changes, Including TSTF-4852006-09-25025 September 2006 Units, 2 and 3 - Proposed Changes to Technical Specifications: Miscellaneous Editorial Changes, Including TSTF-485 ML0604505332006-02-13013 February 2006 Tech Spec Pages for Amendments 245 and 229 Inoperability of Snubbers NL-05-105, Proposed Change to Technical Specifications Regarding Emergency Core Cooling System Throttle Valve Surveillance Requirements2005-10-0303 October 2005 Proposed Change to Technical Specifications Regarding Emergency Core Cooling System Throttle Valve Surveillance Requirements NL-05-107, Proposed Change to Indian Point 2 Technical Specifications Regarding LBLOCA Analysis Methodology2005-09-26026 September 2005 Proposed Change to Indian Point 2 Technical Specifications Regarding LBLOCA Analysis Methodology NL-05-065, Application for a Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process (TSTF-372)2005-06-0808 June 2005 Application for a Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process (TSTF-372) NL-05-062, Proposed Change to IP2 Technical Specifications Regarding Pressurizer Water Level Requirements, Indian Point Unit No. 22005-05-25025 May 2005 Proposed Change to IP2 Technical Specifications Regarding Pressurizer Water Level Requirements, Indian Point Unit No. 2 ML0510800342005-04-14014 April 2005 Tech Spec Pages for Amendment 242 Reporting Requirements for Annual Radiological Environmental Operating Report ML0509600592005-03-25025 March 2005 Distribution of IP3 Technical Specification Amendment 224 and 225 ML0508703842005-03-24024 March 2005 Technical Specification Pages Re 4.85 Percent Stretch Power Uprate & Relocation of Cycle-Specific Parameters NL-04-025, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2004-03-0909 March 2004 Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process NL-04-022, Proposed Change to Technical Specifications Regarding Reactor Coolant Pump Flywheel Inspection Interval (TSTF-421)2004-03-0303 March 2004 Proposed Change to Technical Specifications Regarding Reactor Coolant Pump Flywheel Inspection Interval (TSTF-421) ML0330904272003-10-30030 October 2003 Tech Spec Page for Amendment No. 219, Revising TS 5.5.10 to Adopt the Requirements of the American Society for Testing and Materials Standard D3803-1989 ML0325213882003-08-28028 August 2003 Transmittal of IP3 Technical Specification Amendment 218 ML0311403682003-03-26026 March 2003 Transmittal of Technical Specification Amendment 216 ML0221202052002-07-30030 July 2002 Technical Specifications, Amendment Reactor Vessel Material Surveillance Program (Tac No. MB3917) NL-02-082, License Amendment Request (LAR No. 02-010) - Regarding Indian Point Energy Center, Unit No. 2 Technical Specifications Requirements for Control Rod Misalignment & Rod Position Indication2002-07-0909 July 2002 License Amendment Request (LAR No. 02-010) - Regarding Indian Point Energy Center, Unit No. 2 Technical Specifications Requirements for Control Rod Misalignment & Rod Position Indication ML0215505332002-05-29029 May 2002 List of Figures for Amendment No. 227, Indian Point, Unit 2 ML0211905422002-04-25025 April 2002 No. 2 - Technical Specifications - Changes to Technical Specifications Bases ML0210103892002-04-11011 April 2002 Correction of Technical Specification Page Issued by Amendment No. 225 (Tac No. MB2990) ML0209400142002-04-0202 April 2002 Technical Specification, Amendment Technical Specification Changes to Secondary Leakage Limits and Steam Generator Tube Inservice Surveillance Requirements (Tac No. MB0770) ML0209101122002-03-27027 March 2002 Technical Specification Pages for Amendment No. 225 ML0205004982002-02-15015 February 2002 TS, Amendment Updated Pressure-Temperature Limit Curves (Tac No. MB2419) ML0204403322002-02-12012 February 2002 Technical Specification Amendment No. 223, Re Removal of Containment Isolation Valve Lists from Technical Specifications ML0037781142000-12-12012 December 2000 Transfer of Facility Operating Licenses and Proposed License Amendments. Consolidated Edison Co. of New York, Inc, Entergy Nuclear Indian Point 2, LLC, and Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Unit Nos. 1 and 2 2022-02-28
[Table view] |
Text
LIST OF FIGURES Title Figure No.
Reactor Core Safety Limit-Four Loops In Operation 2.1-1 PORV Open Pressure 3.1.A-1 Maximum RCS Pressure: OPS Inoperable and 1 Charging Pump Capable of Injecting into the RCS 3.1 .A-2 Maximum RCS Pressure: OPS Inoperable and 2 Charging Pumps Capable of Injecting into the RCS 3.1 .A-3 Maximum RCS Pressure: OPS Inoperable and 3 Charging Pumps Capable of Injecting into the RCS 3.1.A-4 Maximum RCS Pressure: OPS Inoperable and Start of 1 RCP with SGs 40°F Hotter than RCS 3.1 .A-5 Maximum RCS Pressure: OPS Inoperable and Start of 1 RCP with SGs 100OF Hotter than RCS 3.1 ,A-6 Reactor Coolant System Heatup and Leak Test Limitations Applicable for the First 25 EFPY 3.1 ,B-1 Reactor Coolant System Cooldown Limitations Applicable for the First 25 EFPY 3.1.B-2 Spent Fuel Storage Rack Layout 3.8-1 Region 1-1 Limiting Fuel Burnup versus Initial Enrichment 3.8-2 Region 1-2 Minimum Number of IFBA Rods versus Initial Enrichment 3.8-3 Region 2-1 Limiting Fuel Burnup versus Initial Enrichment 3.8-4 Region 2-2 Limiting Fuel Burnup versus Initial Enrichment 3.8-5 Required Hot Shutdown Margin versus Reactor Coolant Boron Concentration 3.10-1 DELETED 4.3-1 Map Defining Unrestricted Areas for Radioactive Gaseous and Liquid Effluents 5.1-1 Amendment No. 227 ix
not be moved on or above El. 95' in the Fuel Storage Building. Additionally, loads in excess of the nominal weight of a fuel and control rod assembly and associated handling tool shall not be moved over spent fuel in the spent fuel pit. The weight of installed crane systems shall not be considered part of these loads.
- 2. The spent fuel storage pit water level shall be maintained at an elevation of at least 93'2". In the event the level decreases below this value, all movement of fuel assemblies in the spent fuel pool storage pit and crane operations with loads over spent fuel in the spent fuel pit shall cease and water level shall be restored to within its limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
D. The following conditions are applicable to the spent fuel pit anytime it contains fuel:
- 1. The spent fuel racks are categorized as either Region 1-1, 1-2, 2-1, or 2-2 as specified in Figure 3.8-1. Fuel assemblies to be stored in the spent fuel storage racks are qualified based on burnup. enrichment, and cooling time as specified in Figures 3.8-2 through 3.8-5.
- a. Storage of fuel in Region 1-1 is restricted to assemblies that meet the burnup criteria in Figure 3.8-2.
- b. Storage of fuel in Region 1-2 is restricted to assemblies with enrichments
< 4.5 weight percent (w/o) or < 5.0 W/o with a minimum number of Integral Fuel Burnable Absorbers (IFBA) rods as specified in Figure 3.8-3. Fuel that meets the criteria for Region 1-2 may be stored in Region 1-1 in a checkerboard (1 out of 2 cells with every other cell left vacant) loading configuration.
- c. Storage of fuel in Region 2-1 is restricted to assemblies that meet the burnup criteria in Figure 3.8-4.
- d. Storage of fuel in Region 2-2 is restricted to assemblies that meet the burnup criteria in Figure 3.8-5. Fuel that meets the criteria for Region 2-1 may be stored in Region 2-2 in "peripheral" cells. As shown in Figure 3.8-1, the peripheral cells are located along the west wall and are separated by at least 3 cells.
- 2. In the event any fuel assembly is found to be stored in a configuration other than specified, immediate action shall be initiated to:
- a. Verify the spent fuel storage pit boron concentration meets the requirements of Specification 3.8.D.3, and Amendment No. 227 3.8-4
- b. Return the stored fuel assembly to the specified configuration.
- 3. At all times the spent fuel storage pit boron concentration shall be at least 2000 ppm. With the boron concentration less than this value, all fuel movement within the spent fuel storage pit shall cease and immediate action shall be initiated to restore the boron concentration to at least the minimum specified. The required boron concentration shall be verified by chemical analysis at the frequency specified on Table 4.1-2.
- 4. During operations described in Specification 3.8.B, the spent fuel storage pit boron concentration shall be at least equal to that required in Specification 3.8.B.2. With the boron concentration less than the specified value either:
- a. Isolate the spent fuel storage pit from the refueling cavity, or
- b. Take actions required by Specification 3.8.B.12.
E. Specification 3.0.1 is not applicable to the requirements of Specification 3.8.
Basis The equipment and general procedures to be utilized during refueling are discussed in the FSAR. Detailed instructions, the above-specified precautions, and the design of the fuel-handling equipment incorporating built-in interlocks and safety features, provide assurance that no incident could occur during the refueling operations that would result in a hazard to public health and safety(1). Whenever changes are nut being made in core geometry, one flux monitor is sufficient. This permits maintenance of the instrumentation. Continuous monitoring of radiation levels and neutron flux provides immediate indication of an unsafe condition. The residual heat removal pump is used to maintain a uniform boron concentration.
The shutdown margin requirements will keep the core subcritical. During refueling, the reactor refueling cavity is filled with borated water. The minimum boron concentration of this water is the more restrictive of either 2000 ppm or else sufficient to maintain the reactor subcritical by at least 5% Ak/k in the cold shutdown condition with all rods inserted. These limitations are consistent with the initial conditions assumed for the boron dilution incident in the safety analyses. Periodic checks of refueling water boron concentration ensure the proper shutdown margin. The specifications allow the control room operator to inform the manipulator operator of any impending unsafe condition detected from the main control board indicators during fuel movement.
In addition to the above safeguards, interlocks are utilized during refueling to ensure safe handling.
An excess weight interlock is provided on the lifting hoist to prevent movement of more than one Amendment No. 227 3.8-5
fuel assembly at a time. The spent fuel transfer mechanism can accommodate only one fuel assembly at a time.
The 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> decay time following plant shutdown and the 23 feet of water above the top of the reactor vessel flanges are consistent with the assumptions used in the dose calculations for fuel-handling accidents both inside and outside of the containment. The analysis of the fuel handling accident inside and outside of the containment takes no credit for removal of radioactive iodine by charcoal filters.
The requirement for the fuel storage building charcoal filtration system to be operating when spent fuel movement is being made provides added assurance that the offsite doses will be within acceptable limits in the event of a fuel-handling accident. The additional month of spent fuel decay time will provide the same assurance that the offsite doses are within acceptable limits and therefore the charcoal filtration system would not be required to be operating.
Th* spent fuel storage pi* water level requirement in Specification 3.8.C.2 provides approximately 24 feet of water above fuel assemblies stored in the spent fuel storage racks.
The fuel enrichment and burnup limits in Specification 3.8.D.1, the partial credit taken for Boraflex panels, and the boron requirements in Specification 3.8.D.3 assure the limits assumed in the spent fuel storage safety analysis will not be exceeded. The analysis (Ref. 2) takes credit for the amount of Boraflex predicted to be available through 2006.
The requirement that at least one RHR pump and heat exchanger be in operation ensures that sufficient cooling capacity is available to maintain reactor coolant temperature below 140'F, and sufficient coolant circulation is maintained through the reactor core to minimize the effect of a boron dilution Incident and prevent boron stratification.
The requirement to have two RHR pumps and heat exchangers operable when there is less than 23 feet of water above the vessel flange ensures that a single failure will not result in a complete loss of residual heat removal capability. With the head removed and at least 23 feet of water above the flange, a large heat sink is available for core cooling, thus allowing adequate time to initiate actions to cool the core in the event of a single failure.
References (1) FSAR Section 9.5.2 (2) Northeast Technology Corporation Report NET-173-01, "Criticality Analysis for Soluble Boron and Burnup Credit in the Con Edison Indian Point Unit No. 2 Spent Fuel Storage Racks."
Amendment No. 227 3.8-6
J DF G
E DL DJ C
REGION 2-2 DC A
DE CP CF CM Ck OK CK CH C0P CF CF Cc CD '
BN BN BL BK BJ BH REGION2-2 BG BF BE BD AM BC 35 67 69 71 73 75 AK AH AF AD AB 4 40 42 44 46 48 51 55 57 59 61 6364 S PERIPHERAL CELL Figure 3.8-1 Spent Fuel Storage Rack Layout Amendment No. 227
40 L
V 30 (5
E Acceptable for Storage in Region 1-1 F
20 E
E Not Acceptable for Storage 10 - in Region 1-1 0
1 2 3 4 5 Initial Enrichment, w/o U235 Figure 3.8-2 Region 1 Limiting Burnup versus Initial Enrichment Amendment No. 227
25 20 Acceptable for Storage in Region 1-2 or Checkerboard Loading in Region 1-1 U) 0 15 0
E 10 z Not Acceptable for Storage in Region 1-2 or Checkerboard Loading in Region 1-1 5
0 4.5 4.6 4.7 4.8 4.9 5 Initial Enrichment, w/o U23 5 Figure 3.8-3 REGION 1 MINIMUM NUMBER OF IFBA RODS VERSUS INITIAL ENRICHMENT Amendment No. 227
0 Years Cooling 60 I- 5 Yr Cooling 10 Yr. Cooling 15Yr Cooling
,50 20 Yr. Cooling 50 4 Acceptable for Storage inRegion 2-1 40i I
0 30 in
-/
20 - / Not Acce ptable for
/ , Storage in Region 2-1 10 ii
[' ____,___,_
U 1 2 3 4 5 Initial Enrichment, w/o U235 Figure 3.8-4 Region 2 Limiting Burnup versus Initial Enrichment Amendment No. 227
40 0 Cooling Time 5 Years Cooling 10 Years Cooling 15 Years Cooling 30 20 Years Cooling Acceptable for V Storage in Region 2-2 20 nn F
,'// /
10 !
Not Acceptable for Storage in Region 2-2 0
1 2 3 4 5 Initial Enrichment, w/o U235 Figure 3.8-5 Region 2 Limiting Burnup versus Initial Enrichment Amendment No. 227
Table 4.1-2 Frequencies for Sampling Tests Maximum Time Check Frequency Between Tests
- 1. Reactor Coolant Samples Gross ActMty (1) 5 days/week (1) 3 days Radiochemical (2) Monthly 45 days F Determination Semi-annually (3) 30weeks Tritium Activity Weekly (1) 10 days F,CI& 02 Weekly 10 days
- 2. ReactorCodant Boron Boron Concentration Twice/week 5 days
- 3. Refueling Water Storage Boron Concentration Monthly 45 days Tank Water Sample
- 4. Boric Add Tank Boron Concenltraion Twice/week 5 days
- 5. DELETED
- 6. DELETED
- 7. Accumulator Boron Concentration Monthly 45 days
- 8. Spent Fuel Pit Boron Concentration Weekly 10 days
- 9. Secondary Coolant lodine-1 31 Weekly (4) 10 days
- 10. Containment Iodine Iodine-131 and Continuous When NAX Particulate Monitor Particulate Activity Above Cold Shutdown (5) or Gas Monitor or Gross Gaseous Activity Amendment No. 227 (Page I of 2)
5.4 FUEL STORAGE Applicability Applies to the capacity and storage arrays of new and spent fuel.
Objective To define those aspects of fuel storage relating to prevention of criticality in fuel storage areas.
Specifications
- 1. The spent fuel pit structure is designed to withstand the anticipated earthquake loadings as a Class I structure. The spent fuel pit has a stainless steel liner to ensure against loss of water.
2.A. The new fuel storage rack is designed so that it is in-possible to insert assenblies in other than an array of vertical fuel asserblies with a sufficient center-to-center distance between assemblies to assure K,, < 0.95, even if unborated water were used to fill the pit and with fuel assemblies containing a maximum enrichment of 5.0 weight percent U-235, and poisons, if necessary to meet the K-, limit.
2.B. The spent fuel storage racks are designed and their loading maintained within the limits of Technical Specification 3.8.D.1, such that K.1 < 1.0 in unborated water and K f. < 0.95 with credit for soluble boron and with the fuel asseimblies containing a maximum enrichment of 5.0 weight percent U-235 (or equivalent reactivity).
Amendment No. 2 2 7 5.4-1