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MONTHYEARW3F1-2007-0037, License Amendment Request NPF-38-271 to Support Next Generation Fuel2007-08-0202 August 2007 License Amendment Request NPF-38-271 to Support Next Generation Fuel Project stage: Request W3F1-2007-0038, Emergency Core Cooling System Performance Analysis2007-08-0909 August 2007 Emergency Core Cooling System Performance Analysis Project stage: Request W3F1-2007-0045, Supplement to the ECCS Performance Analysis Submittal in Support of Next Generation Fuel - 1999 EM Optional Steam Cooling Model Justification2007-10-0404 October 2007 Supplement to the ECCS Performance Analysis Submittal in Support of Next Generation Fuel - 1999 EM Optional Steam Cooling Model Justification Project stage: Request W3F1-2008-0004, Supplement to Amendment Request NPF-38-271 to Support Next Generation Fuel2008-01-17017 January 2008 Supplement to Amendment Request NPF-38-271 to Support Next Generation Fuel Project stage: Supplement ML0801802842008-01-22022 January 2008 Request for Additional Information on the Revised Emergency Core Cooling System Performance Analysis Supporting the Next Generation Fuel Project stage: RAI ML0801600592008-02-0707 February 2008 Request for Additional Information Regarding Review of Supplemental Information to ECCS Performance Analysis in Support of Next Generation Fuel, Optional Spacer Grid Steam Cooling Transfer Model Project stage: RAI ML0803804332008-02-12012 February 2008 Request for Additional Information License Amendment Request to Modify TS 6.9.1.11.1, Core Operating Limits, TS 3.5.1, Safety Injection Tanks, & TS 3.6.1.5, Containment Air Temperature to Support Next Generation Fuel Project stage: RAI W3F1-2008-0021, Supplement 2 RAI Response to Amendment Request NPF-38-271 to Support Next Generation Fuel2008-03-10010 March 2008 Supplement 2 RAI Response to Amendment Request NPF-38-271 to Support Next Generation Fuel Project stage: Supplement ML0808404842008-03-24024 March 2008 E-mail from Ronald L. Williams, Entergy, to N. Kalyanam, NRC, RAI Response to On-Going Processes to Support Next Generation Fuel. Project stage: Other ML0810003322008-04-0303 April 2008 Drawing Lr 1-30-1, Rev. 5, River Water System. Project stage: Other L-08-123, Drawing Lr 1-46-2, Rev. 5, Post DBA Hydrogen Analyzer System.2008-04-0303 April 2008 Drawing Lr 1-46-2, Rev. 5, Post DBA Hydrogen Analyzer System. Project stage: Other ML0808800142008-04-15015 April 2008 License Amendment 214, Request to Support Next Generation Fuel; Review and Approval of ECCS Performance Analysis; and Review and Approval of Supplement to ECCS Performance Analysis Project stage: Approval ML0808800152008-04-15015 April 2008 Tech Spec Pages for Amendment 214, Request to Support Next Generation Fuel; Review and Approval of ECCS Performance Analysis; and Review and Approval of Supplement to ECCS Performance Analysis Project stage: Other ML0812700362008-05-0909 May 2008 Tech Spec Page for Correction to Amendment 214 Request to Support Next Generation Fuel; Review & Approval of Revised ECCS Performance Analysis; & Review & Approval of Supplement to ECCS Performance Analysis Project stage: Other ML0812605352008-05-0909 May 2008 Correction to Amendment 214 Request to Support Next Generation Fuel; Review & Approval of Revised ECCS Performance Analysis; & Review & Approval of Supplement to ECCS Performance Analysis (Tac Nos. MD6299, MD6363, & MD6954) Project stage: Other ML21148A0522021-06-0808 June 2021 Correction to License Amendment 214 Request to Support Next Generation Fuel; Review and Approval of Revised ECCS Performance Analysis; and Review and Approval of Supplement to the ECCS Performance Analysis Project stage: Approval 2008-02-07
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Category:Technical Specifications
MONTHYEARML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology Slides and Affidavit for Pre-Submittal Meeting W3F1-2023-0035, Application for Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program2023-07-26026 July 2023 Application for Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program ML22104A2222022-05-12012 May 2022 Issuance of Amendments Revise Technical Specifications to Adopt TSTF 554 ML22075A1022022-04-29029 April 2022 Issuance of Amendment No. 264 to Relocate Chemical Detection System Technical Specifications to Technical Requirements Manual ML21279A2312021-10-0606 October 2021 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements Using the Consolidated Line-Item Improvement ML21148A0522021-06-0808 June 2021 Correction to License Amendment 214 Request to Support Next Generation Fuel; Review and Approval of Revised ECCS Performance Analysis; and Review and Approval of Supplement to the ECCS Performance Analysis ML21116A1432021-04-26026 April 2021 (Waterford 3) - Revision to License Amendment Request to Relocate Boration Systems Technical Specifications to the Technical Requirements Manual ML20148M1062020-06-22022 June 2020 Corrections to Technical Specifications Issued in Amendments Nos. 102 and 225 and with the Renewed License ML20113E8362020-04-23023 April 2020 Summary of March 19, 2020, Category 1 Public Meeting with Entergy Operations Inc. a Planned LAR to Install Digital Systems in Accordance with Di&C ISG-06 Revision 2, Licensing Processes at Waterford Steam Electric Station ML19175A0422019-09-11011 September 2019 Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules ML19022A3372019-02-13013 February 2019 Issuance of Amendment No. 253 to Revise Section 15.4.3.1 of the Updated Final Safety Analysis Report to Account for Fuel Misload ML17192A0072017-07-27027 July 2017 Issuance of Amendment No. 250 Adoption of Technical Specifications Task Force Traveler TSTF 545, Revision 3 ML16077A2702016-05-10010 May 2016 Issuance of Amendment No. 247 Regarding Cyber Security Plan Milestone 8 Full Implementation Schedule W3F1-2016-0010, Responses to Request for Additional Information Regarding the Risk-Informed Surveillance Requirements License Amendment Request (LAR)2016-03-0303 March 2016 Responses to Request for Additional Information Regarding the Risk-Informed Surveillance Requirements License Amendment Request (LAR) ML15289A1432015-11-13013 November 2015 Redacted - Issuance of Amendment No. 246 Changes to Technical Specification 3.1.3.4 Regarding Control Element Assembly Drop Times ML15244B3862015-09-0303 September 2015 Correction to Issuance of Amendment Extension of the Integrated Leak Rate Testing to 15 Years ML15139A4832015-08-31031 August 2015 Issuance of Amendment No. 245 Change to Updated Final Safety Analysis Report Clarifying Pressurizer Heaters Function for Natural Circulation at the Onset of a Loss of Offsite Power ML15217A1432015-08-24024 August 2015 Issuance of Amendment No. 244 Extension of the Integrated Leak Rate Testing to 15 Years ML15138A4402015-08-14014 August 2015 Orders Approving Transfer of Facility Operating Licenses and Indirect Transfer, Draft Conforming Amendment, and Safety Evaluation W3F1-2015-0061, Provides Supplement to Revise Control Element Assembly Drop Times Associated with Technical Specification 3.1.3.42015-08-14014 August 2015 Provides Supplement to Revise Control Element Assembly Drop Times Associated with Technical Specification 3.1.3.4 ML15174A2272015-07-29029 July 2015 Issuance of Amendment of Technical Specifications s 3.9.6 and 3.9.7 to the Technical Requirements Manual ML14321A7132014-12-10010 December 2014 Issuance of Amendment No. 241, Revise Operating License Condition for Change to Cyber Security Plan Milestone 8 Full Implementation Date W3F1-2014-0052, License Amendment Request Technical Specification Change to Extend the Type a Test Frequency to 15 Years2014-08-28028 August 2014 License Amendment Request Technical Specification Change to Extend the Type a Test Frequency to 15 Years CNRO-2012-00009, Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications2012-11-20020 November 2012 Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications W3F1-2012-0084, Technical Specification Change for Dry Cooling Tower Fans Out of Service for Ultimate Heat Sink2012-10-0808 October 2012 Technical Specification Change for Dry Cooling Tower Fans Out of Service for Ultimate Heat Sink W3F1-2012-0028, Supplement 2 of License Amendment Request to Revise Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train2012-05-22022 May 2012 Supplement 2 of License Amendment Request to Revise Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train W3F1-2011-0067, License Amendment Request, Proposed Change to Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train.2011-10-13013 October 2011 License Amendment Request, Proposed Change to Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train. ML1125103192011-09-20020 September 2011 Correction of an Error in Amendment No. 226, Administrative Changes to Technical Specifications 6.9.1.11 and 6.9.1.11.1 Relating to Core Operating Limits Report ML1109501232011-04-0404 April 2011 Attachment 2 to W3F1-2011-0021, Proposed Operating License Change (Mark-up) and Attachment 3, Revised Operating License Page ML1021001582010-09-13013 September 2010 Issuance of Amendment No. 228, Modify Technical Specification Tables 2.2-1 and 3.3-1 to Clarify Notes and Actions ML1021504662010-09-13013 September 2010 Issuance of Amendment No. 227, Modify Technical Specification 3/4.9.7, Crane Travel - Fuel Handling Building to Permit Certain Operations Needed for Dry Cask Storage of Spent Nuclear Fuel W3F1-2010-0065, Response to Request for Additional Information Associated with Technical Specification Table 3.4-1 Isolation Valve Addition2010-08-12012 August 2010 Response to Request for Additional Information Associated with Technical Specification Table 3.4-1 Isolation Valve Addition W3F1-2010-0047, License Amendment Request for Proposed Change to Technical Specification 3.7.1.2, Emergency Feedwater System.2010-07-20020 July 2010 License Amendment Request for Proposed Change to Technical Specification 3.7.1.2, Emergency Feedwater System. 2CAN051001, Response to Request for Additional Information Associated with Core Operating Limits Report References2010-05-17017 May 2010 Response to Request for Additional Information Associated with Core Operating Limits Report References ML1011100352010-04-22022 April 2010 Correction to Technical Specification Page 3/4 3-10 Issued with Amendment No. 225 Technical Specification Change to Relocate Steam Generator Level - High Trip Function W3F1-2010-0011, License Amendment Request, Technical Specification Change Regarding Steam Generator Program2010-02-22022 February 2010 License Amendment Request, Technical Specification Change Regarding Steam Generator Program ML1005504632010-02-22022 February 2010 Request for Amendment to Technical Specification Table 3.4-1 Isolation Valve Addition W3F1-2009-0045, License Amendment Request to Modify Technical Specification Information for Table 2.2-1 and Table 3.3-12009-10-22022 October 2009 License Amendment Request to Modify Technical Specification Information for Table 2.2-1 and Table 3.3-1 W3F1-2009-0021, License Amendment Request to Revise the Departure from Nucleate Boiling Ratio (DNBR) Safety Limit2009-06-0303 June 2009 License Amendment Request to Revise the Departure from Nucleate Boiling Ratio (DNBR) Safety Limit W3F1-2008-0051, Entergy'S Response to Nrc'S Request for Additional Information Regarding License Amendment Request to Modify Requirements Regarding Control Room Envelope Habitability, Waterford Unit 32009-01-0808 January 2009 Entergy'S Response to Nrc'S Request for Additional Information Regarding License Amendment Request to Modify Requirements Regarding Control Room Envelope Habitability, Waterford Unit 3 ML0819904722008-07-30030 July 2008 License and Technical Specification Pages, Issuance of Amendment No. 216, Modify Diesel Generator Fuel Oil Testing Surveillance Requirements ML0812700362008-05-0909 May 2008 Tech Spec Page for Correction to Amendment 214 Request to Support Next Generation Fuel; Review & Approval of Revised ECCS Performance Analysis; & Review & Approval of Supplement to ECCS Performance Analysis ML0803800062008-04-16016 April 2008 License Page 4 and Technical Specification Page 5-5, Issuance of Amendment No. 215 Use of Optimized ZIRLO-TM Fuel Rod Cladding ML0808800152008-04-15015 April 2008 Tech Spec Pages for Amendment 214, Request to Support Next Generation Fuel; Review and Approval of ECCS Performance Analysis; and Review and Approval of Supplement to ECCS Performance Analysis ML0804401272008-02-12012 February 2008 2/12/2008 E-mail from Licensee Enclosing Markup of Technical Specification Page 5-5, Supplement to 4/24/2007 License Amendment Request Use of Optimized ZIRLO-TM Fuel Rod Cladding W3F1-2008-0001, License Amendment Request NPF-38-275, Containment Isolation Valves.2008-01-0202 January 2008 License Amendment Request NPF-38-275, Containment Isolation Valves. W3F1-2007-0033, License Amendment Request NPF-38-273 to Modify Requirements Regarding Control Room Envelope Habitability2007-08-16016 August 2007 License Amendment Request NPF-38-273 to Modify Requirements Regarding Control Room Envelope Habitability ML0711603482007-04-24024 April 2007 License Amendment Request to Allow the Use of Optimized Zirlo Fuel Rod Cladding ML0706803372007-03-19019 March 2007 Tech Spec Pages for Amendment 212 Reactor Coolant System Leakage Detection Instrumentation ML0703704312007-02-0606 February 2007 Technical Specifications, Issuance of Amendment No. 211 to Facility Operating License Removal of Vendor Recommended Diesel Generator Surveillance Requirement 2023-07-26
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Text
or indirectly any control over (i) the facility, (ii) power or energy produced by the facility, or (iii) the licensees of the facility. Further, any rights acquired under this authorization may be exercised only
in compliance with and subject to the requirements and restrictions
of this operating license, the Atomic Energy Act of 1954, as
amended, and the NRC's regulations. For purposes of this
condition, the limitations of 10 CFR 50.81, as now in effect and as
they may be subsequently amended, are fully applicable to the
equity investors and any successors in interest to the equity
investors, as long as the license for the facility remains in effect. (b) Entergy Louisiana, LLC (or its designee) to notify the NRC in writing prior to any change in (i) the terms or conditions of any lease
agreements executed as part of the above authorized financial
transactions, (ii) any facility operating agreement involving a
licensee that is in effect now or will be in effect in the future, or (iii) the existing property insurance coverages for the facility, that
would materially alter the representations and conditions, set forth
in the staff's Safety Evaluation enclosed to the NRC letter dated
September 18, 1989. In addition, Entergy Louisiana, LLC or its
designee is required to notify the NRC of any action by equity
investors or successors in interest to Entergy Louisiana, LLC that
may have an effect on the operation of the facility. C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I 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 EOI is authorized to operate the facility at reactor core power levels not in excess of 3716 megawatts thermal (100% power) in accordance with the
conditions specified herein. 2. Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. , and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. EOI shall operate the
facility in accordance with the Technical Specifications and the
Environmental Protection Plan.
Amendment No.
214 214 WATERFORD - UNIT 33/4 5-1AMENDMENT NO. 121, 129, 147, 155, 199 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 SAFETY INJECTION TANKS LIMITING CONDITION FOR OPERATION 3.5.1 Each Reactor Coolant System safety injection tank shall be OPERABLE with:a.The isolation valve open, b.A contained borated water volume of between 40% and 72.8% level,c.Between 2050 and 2900 ppm of boron, and d.A nitrogen cover-pressure of between 600 and 670 psig.
APPLICABILITY
- MODES 1, 2, 3*, and 4*.
ACTION: MODES 1, 2, 3 and 4 with pressurizer pressure greater than or equal to 1750 psia.a.With one of the required safety injection tanks inoperable due to boron concentration not within limits, restore the boron concentration to within limits within
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce
pressurizer pressure to less than 1750 psia within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.a.With one of the required safety injection tanks inoperable due to inability to verify level or pressure, restore the tank to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or be in at
least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce pressurizer pressure to
less than 1750 psia within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.c. With one of the required safety injection tanks inoperable for reasons other than ACTION a or b, restore the tank to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or be in
HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce pressurizer pressure to less
than 1750 psia within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
- With pressurizer pressure greater than or equal to 1750 psia. When pressurizer pressure is less than 1750 psia, at least three safety injection tanks must be OPERABLE, each with a
minimum pressure of 235 psig and a maximum pressure of 670 psig, and a contained borated
water volume of between 61% and 72.8% level. With all four safety injection tanks OPERABLE, each tank shall have a minimum pressure of 235 psig and a
maximum pressure of 670 psig, a boron concentration of between 2050 and 2900 ppm boron, and a contained borated water volume of between 39% and 72.8% level. In MODE 4 with pressurizer pressure less than 392 psia (700 psia for remote shutdown from
LCP-43), the safety injection tanks may be isolated.
214 WATERFORD - UNIT 33/4 6-13AMENDMENT NO. 199
, CONTAINMENT SYSTEMS AIR TEMPERATURE LIMITING CONDITION FOR OPERATION 3.6.1.5 Primary containment average air temperature shall be >
95°F* and < 120 °F.APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:a.If the minimum containment average air temperature is less than 95°F* but greater than or equal to 90°F*, then within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> either restore containment air temperature to greater
than 95°F or reduce the peak linear heat generation rate in accordance with the COLR.
Otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD
SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.b.If maximum containment average air temperature is greater than allowable limit, then restore containment air temperature to within the limit within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least HOT
STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30
hours.SURVEILLANCE REQUIREMENTS 4.6.1.5 The primary containment average air temperature shall be the arithmetical average of the temperatures at any three of the following locations
and shall be determined at least once per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:
Location a. Containment Fan Cooler No. 1A Air Intake
- b. Containment Fan Cooler No. 1B Air Intake
- c. Containment Fan Cooler No. 1C Air Intake
- d. Containment Fan Cooler No. 1D Air Intake
____________
- The minimum containment average air temperature limit is only applicable at greater than 70%
RATED THERMAL POWER.
214 AMENDMENT NO. 102, 146, 158, 182, 188, 191, 199, 200, 210
,WATERFORD - UNIT 36-20a ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT COLR (Continued)
- 6) "CESEC - Digital Simulation for a Combustion Engineering Nuclear Steam Supply System,"(CE letter LD-82-001 and NRC SE to CE dated April 3, 1984). (Methodology for
Specification 3.1.1.1 and 3.1.1.2 for Shutdown Margins, 3.1.1.3 for MTC, 3.1.3.1 for
Movable Control Assemblies - CEA Position, 3.1.3.6 for Regulating and group P CEA
Insertion Limits, and 3.2.3 for Azimuthal Power Tilt).
- 7) "Qualification of Reactor Physics Methods for the Pressurized Water Reactors of the Entergy System," ENEAD-01-P. (Methodology for Specifications 3.1.1.1 and 3.1.1.2 for
Shutdown Margins, 3.1.1.3 for MTC, 3.1.3.6 for Regulating and group P CEA Insertion
Limits, 3.1.2.9 Boron Dilution (Calculation of CBC & IBW), and 3.9.1 Boron
Concentration).
- 8) Fuel Rod Maximum Allowable Gas Pressure, CEN-372-P-A. (Methodology for Specification 3.2.1, Linear Heat Rate).
- 9) Technical Description Manual for the CENTS Code, WCAP-15996-P-A. (Methodology for Specification 3.1.1.1 and 3.1.1.2 for Shutdown Margins, 3.1.1.3 for
MTC, 3.1.3.1 for Movable Control Assemblies - CEA Position, 3.1.3.6 for Regulating and
group P CEA Insertion Limits, and 3.2.3 for Azimuthal Power Tilt).
- 10) Calculative Methods for the CE Nuclear Power Large Break LOCA Evaluation Model, CENPD-132, Supplement 4-P-A. (Methodology for Specification 3.1.1.3 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt and 3.2.7 for ASI).
- 11) Implementation of ZIRLO Material Cladding in CE Nuclear Power Fuel Assembly Designs, CENPD-404-P-A (Methodology for Specification 3.1.1.3 for MTC, 3.2.1 for
Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for ASI).12) Qualification of the PHOENIX-P/ANC Nuclear Design System For Pressurized Water Reactor Cores, WCAP-11596-P-A; ANC: A Westinghouse Advanced Nodal Computer
Code, WCAP-10965-P-A; and ANC: A Westinghouse Advanced Nodal Computer Code:
Enhancements to ANC Rod Power Recovery, WCAP-10965-P-A Addendum 1.
(Methodology for Specifications 3.1.1.1 and 3.1.1.2 for Shutdown Margins, 3.1.1.3 for
MTC, 3.1.3.6 for Regulating and group P CEA Insertion Limits, 3.1.2.9 Boron Dilution (Calculation of CBC & IBW), and 3.9.1 Boron Concentration).
- 13) Qualification of the Two-Dimensional Transport Code PARAGON, WCAP-16045-P-A (Methodology for Specifications 3.1.1.1 and 3.1.1.2 for Shutdown Margins, 3.1.1.3 for
MTC, 3.1.3.6 for Regulating and group P CEA Insertion Limits, 3.1.2.9 Boron Dilution (Calculation of CBC & IBW), and 3.9.1 Boron Concentration).
- 14) Implementation of Zirconium Diboride Burnable Absorber Coatings in CE Nuclear Power Fuel Assembly Designs, WCAP-16072-P-A (Methodology for Specification 3.1.1.3
for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for ASI).
- 15) CE 16 x 16 Next Generation Fuel Core Reference Report, WCAP-16500-P and Final Safety Evaluation for Westinghouse Electric Company (Westinghouse) Topical Report (TR) WCAP-16500-P, Revision 0, CE [Combustion Engineering] 16x16 Next Generation
Fuel [(NGF)] Core Reference Report, (Methodology for Specification 3.1.1.3 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, 3.2.4.b, 3.2.4.c, and 3.2.4.d for
DNBR Margin, and 3.2.7 for ASI).
214 WATERFORD - UNIT 36-20bAMENDMENT NO. 200
, ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT COLR (Continued)
- 16) Optimized ZIRLO TM , WCAP-12610-P-A and CENPD-404-P-A Addendum 1-A, (Methodology for Specification 3.1.1.3 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for
Azimuthal Power Tilt, and 3.2.7 for ASI).
- 17) Westinghouse Correlations WSSV and WSSV-T for Predicting Critical Heat Flux in Rod Bundles with Side-Supported Mixing Vanes, WCAP-16523-P-A and Final Safety
Evaluation for Westinghouse Electric Company (Westinghouse) Topical Report (TR),
WCAP-16523-P, Westinghouse Correlations WSSV and WSSV-T for Predicting Critical
Heat Flux in Rod Bundles with Side-Supported Mixing Vanes, (Methodology for
Specification 3.2.4.b, 3.2.4.c, and 3.2.4.d for DNBR Margin).
- 18) ABB Critical Heat Flux Correlations for PWR Fuel, CENPD-387-P-A (Methodology for Specification 3.2.4.b, 3.2.4.c, and 3.2.4.d for DNBR Margin and 3.2.7 for ASI).
- 19) Calculative Methods for the CE Nuclear Power Large Break LOCA Evaluation Model -
Improvement to 1999 Large Break LOCA EM Steam Cooling Model for Less Than 1 in/sec
Core Reflood CENPD-132, Supplement 4-P-A, Addendum 1-P and Final Safety Evaluation
for Westinghouse Electric Company (Westinghouse) Topical Report (TR) CENPD-132
Supplement 4-P-A, Addendum 1-P, Calculative Methods for the CE [Combustion
Engineering] Nuclear Power Large Break LOCA Evaluation Model - Improvement to 1999
Large Break LOCA EM Steam Cooling Model for Less Than 1 in/sec Core Reflood (Methodology for Specification 3.1.1.3 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for
Azimuthal Power Tilt, and 3.2.7 for ASI).
6.9.1.11.2 The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown
margin, and transient and accident analysis limits) of the safety analysis are met.
6.9.1.11.3 The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC SPECIAL REPORTS 6.9.2 Special reports shall be submitted in accordance with 10 CFR 50.4 within the time period specified for each report.
6.10 Not Used 214