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Category:Letter type:
MONTHYEAR2CAN012401, U.S. Additional Protocol2024-01-17017 January 2024 U.S. Additional Protocol 2CAN012403, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42024-01-11011 January 2024 Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 0CAN012401, Registration of Cask Use2024-01-10010 January 2024 Registration of Cask Use 1CAN122301, Responses to Request for Additional Information for Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISl-037)2023-12-14014 December 2023 Responses to Request for Additional Information for Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISl-037) 2CAN112302, Submittal of Amendment 31 to Safety Analysis Report2023-11-16016 November 2023 Submittal of Amendment 31 to Safety Analysis Report 0CAN102303, Registration of Cask Use2023-10-24024 October 2023 Registration of Cask Use 0CAN102302, (ANO) Emergency Plan Revision 49 and Emergency Plan On-Shift Staffing Analysis Revision 32023-10-11011 October 2023 (ANO) Emergency Plan Revision 49 and Emergency Plan On-Shift Staffing Analysis Revision 3 0CAN102301, Evacuation Time Estimate (ETE) Study2023-10-0404 October 2023 Evacuation Time Estimate (ETE) Study 1CAN092301, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42023-09-21021 September 2023 Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 0CAN092302, Supplement to Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002)2023-09-14014 September 2023 Supplement to Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002) 2CAN092301, Reply to a Notice of Violation2023-09-0808 September 2023 Reply to a Notice of Violation 0CAN092301, Emergency Plan Implementing Procedure Revision2023-09-0505 September 2023 Emergency Plan Implementing Procedure Revision 0CAN082301, Units 1 and 2 - Changes to the Quality Assurance Program Approval Form for Radioactive Material Package No. 03412023-08-17017 August 2023 Units 1 and 2 - Changes to the Quality Assurance Program Approval Form for Radioactive Material Package No. 0341 2CAN082301, Inservice Inspection Summary Report for the Arkansas Nuclear One, Unit 2, Twenty-Ninth Refueling Outage (2R29)2023-08-10010 August 2023 Inservice Inspection Summary Report for the Arkansas Nuclear One, Unit 2, Twenty-Ninth Refueling Outage (2R29) 0CAN072301, Registration of Cask Use2023-07-18018 July 2023 Registration of Cask Use 1CAN062304, Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation2023-06-29029 June 2023 Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation 0CAN062301, Status of Actions to Return to Compliance2023-06-26026 June 2023 Status of Actions to Return to Compliance 0CAN062302, Submittal of Revision 22 of the ANO Fire Hazards Analysis2023-06-20020 June 2023 Submittal of Revision 22 of the ANO Fire Hazards Analysis 1CAN062301, Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISI-037)2023-06-0808 June 2023 Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISI-037) 0CAN052303, Annual 10 CFR 50.46 Report for Calendar Year 20222023-05-24024 May 2023 Annual 10 CFR 50.46 Report for Calendar Year 2022 0CAN052302, Emergency Plan Rev. 482023-05-11011 May 2023 Emergency Plan Rev. 48 0CAN052301, Units 1 and 2 - Annual Radiological Environmental Operating Report for 20222023-05-0909 May 2023 Units 1 and 2 - Annual Radiological Environmental Operating Report for 2022 2CAN052301, Cycle 30 Core Operating Limits Report (COLR)2023-05-0303 May 2023 Cycle 30 Core Operating Limits Report (COLR) 0CAN042302, Annual Occupational Radiation Exposure Report for 20222023-04-27027 April 2023 Annual Occupational Radiation Exposure Report for 2022 0CAN042301, Radioactive Effluent Release Report for 20222023-04-14014 April 2023 Radioactive Effluent Release Report for 2022 2CAN042301, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42023-04-0505 April 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 1CAN032301, License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure2023-03-30030 March 2023 License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure 2CAN032303, Responses to Request for Additional Information Concerning the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-03-29029 March 2023 Responses to Request for Additional Information Concerning the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 2CAN032304, Supplement to the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-03-29029 March 2023 Supplement to the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 2CAN032305, 03 Post Examination Analysis2023-03-23023 March 2023 03 Post Examination Analysis 1CAN032302, Inspection Summary Report for the Thirtieth Refueling Outage (1R30)2023-03-20020 March 2023 Inspection Summary Report for the Thirtieth Refueling Outage (1R30) 1CAN012301, Responses to Request for Additional Information for Request for Relief ANO1-ISI-0352023-01-30030 January 2023 Responses to Request for Additional Information for Request for Relief ANO1-ISI-035 2CAN012303, U.S. Additional Protocol2023-01-23023 January 2023 U.S. Additional Protocol 2CAN012302, Relief Request ANO2-RR-23-001, Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-01-20020 January 2023 Relief Request ANO2-RR-23-001, Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 1CAN122201, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42022-12-22022 December 2022 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 0CAN122202, Registration of Cask Use2022-12-21021 December 2022 Registration of Cask Use 0CAN122201, Reply to a Notice of Violation; EA-22-0992022-12-0808 December 2022 Reply to a Notice of Violation; EA-22-099 0CAN112201, Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002)2022-11-10010 November 2022 Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002) 1CAN102202, Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation2022-10-31031 October 2022 Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation 1CAN102203, Cycle 31 Core Operating Limits Report2022-10-24024 October 2022 Cycle 31 Core Operating Limits Report 1CAN102201, Supplement to Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations2022-10-13013 October 2022 Supplement to Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations 0CAN092201, Supplement to License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements2022-09-29029 September 2022 Supplement to License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements 1CAN092201, Supplement to Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period2022-09-0808 September 2022 Supplement to Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period 0CAN082201, License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements2022-08-30030 August 2022 License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements 1CAN082201, Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period2022-08-24024 August 2022 Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period 2CAN072201, Response to Request for Additional Information Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods2022-07-20020 July 2022 Response to Request for Additional Information Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods 0CAN072201, Registration of Cask Use2022-07-14014 July 2022 Registration of Cask Use 0CAN062202, Registration of Cask Use2022-06-0909 June 2022 Registration of Cask Use 1CAN062201, Response to the Request for Additional Information Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations2022-06-0202 June 2022 Response to the Request for Additional Information Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations 1CAN052201, Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Augmented Examination Requirements ANO1-ISI-0352022-05-31031 May 2022 Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Augmented Examination Requirements ANO1-ISI-035 2024-01-17
[Table view] 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 0CAN042301, Radioactive Effluent Release Report for 20222023-04-14014 April 2023 Radioactive Effluent Release Report for 2022 ML22104A2222022-05-12012 May 2022 Issuance of Amendments Revise Technical Specifications to Adopt TSTF 554 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 ML21208A4492021-09-20020 September 2021 Issuance of Amendment No. 325 Revise Loss of Voltage Relay Allowable Values and Number of Degraded Voltage Channels ML21088A4332021-04-14014 April 2021 Issuance of Amendment No. 324 Adoption of Technical Specification Task Force Traveler, TSTF-569, Revision 2, Revise Response Time Testing Definition ML21027A4282021-03-23023 March 2021 Issuance of Amendment No. 272 Replacement of Reactor Building Spray Sodium Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent 1CAN022102, Supplement Related to License Amendment Request to Replace the Reactor Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent Sodium Tetraborate2021-02-22022 February 2021 Supplement Related to License Amendment Request to Replace the Reactor Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent Sodium Tetraborate ML20160A1472020-06-30030 June 2020 Issuance of Amendment No. 270 to Adopt TSTF 563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML20135H1412020-06-30030 June 2020 Issuance of Amendment Nos. 269 and 321 Request to Incorporate the Tornado Missile Risk Evaluator Into the Licensing Basis ML19232A3792019-09-19019 September 2019 Correction to Issuance of Amendment No. 264 Adoption of Technical Specifications Task Force Traveler TSTF-425, Revision 3 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 ML17251A2112017-10-10010 October 2017 Issuance of Amendment No. 307 Revision of Steam Generator Technical Specifications to Reflect Adoption of Technical Specifications Task Force Traveler TSTF-510 (CAC MF9654; EPID L-2017-LLA-0222) ML16165A4232017-03-10010 March 2017 Issuance of Amendment No. 257 Adoption of Technical Specifications Task Force Traveler TSTF-545, Revision 3, ML16027A1092016-02-24024 February 2016 Issuance of Amendment Nos. 255 and 303 Cyber Security Plan Implementation Schedule (CAC Nos. MF6258 and MF6259) ML15096A3812015-04-29029 April 2015 Issuance of Amendment No. 302, Revise Technical Specification Surveillance Requirement 4.1.3.1.2 Note to Eliminate Movement of Control Element Assembly 18 for Remainder of Operating Cycle 24 ML15068A3192015-03-31031 March 2015 Issuance of Amendment No. 301, Request to Adopt Technical Specification Task Force (TSTF)-422, Revision 2, Change in Technical Specifications End States (CE NPSD-1186) ML15023A1472015-03-0303 March 2015 Issuance of Amendment No. 253, Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-431, Revision 3, Change in Technical Specifications End States (BAW-2441) ML14356A2272015-02-18018 February 2015 Issuance of Amendment No. 300, Request to Adopt National Fire Protection Association Standard NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants ML15014A0712015-02-0303 February 2015 Issuance of Amendment No. 252, Request to Revise Technical Specification 5.5.16, Reactor Building Leakage Rate Testing Program, to Extend Type a Test Frequency to 15 Years ML14350B2852015-01-22022 January 2015 Issuance of Amendment No. 299, Revise Technical Specification 6.5.16, Containment Leakage Rate Testing Program, for Requirements for Containment Building Emergency Escape Air Lock Doors ML14254A1332014-11-24024 November 2014 Issuance of Amendment No. 250, Adoption of Technical Specifications Task Force (TSTF)-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360 1CAN111401, Arkansas Nuclear One, Unit 1, License Amendment Request Update the Reactor Coolant System Pressure and Temperature and the Low Temperature Overpressure Protection System Limits2014-11-21021 November 2014 Arkansas Nuclear One, Unit 1, License Amendment Request Update the Reactor Coolant System Pressure and Temperature and the Low Temperature Overpressure Protection System Limits 1CAN111401, License Amendment Request Update the Reactor Coolant System Pressure and Temperature and the Low Temperature Overpressure Protection System Limits2014-11-21021 November 2014 License Amendment Request Update the Reactor Coolant System Pressure and Temperature and the Low Temperature Overpressure Protection System Limits 1CAN101407, Clarifications to Response to Request for Additional Information Associated with Technical Specification Change to Extend the Type a Test Frequency to 15 Years2014-10-28028 October 2014 Clarifications to Response to Request for Additional Information Associated with Technical Specification Change to Extend the Type a Test Frequency to 15 Years 1CAN031401, License Amendment Request - Revised Pages Extend the Type a Test Frequency to 15 Years2014-03-11011 March 2014 License Amendment Request - Revised Pages Extend the Type a Test Frequency to 15 Years 1CAN121302, License Amendment Request Technical Specification Change to Extend the Type a Test Frequency to 15 Years2013-12-20020 December 2013 License Amendment Request Technical Specification Change to Extend the Type a Test Frequency to 15 Years 1CAN081302, Response to Request for Additional Information, Adoption of Technical Specification Task Force (TSTF)-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360.2013-08-28028 August 2013 Response to Request for Additional Information, Adoption of Technical Specification Task Force (TSTF)-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360. 2CAN061302, License Amendment Request - Supplemental Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-4712013-06-18018 June 2013 License Amendment Request - Supplemental Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-471 1CAN061301, License Amendment Request, Revision to Technical Specification 2.1.1.1 Reactor Core Safety Limits2013-06-11011 June 2013 License Amendment Request, Revision to Technical Specification 2.1.1.1 Reactor Core Safety Limits 1CAN011304, License Amendment Request - Adoption of Technical Specification Task Force (TSTF)-500, Revision 2 DC Electrical Rewrite - Update to TSTF-360.2013-01-28028 January 2013 License Amendment Request - Adoption of Technical Specification Task Force (TSTF)-500, Revision 2 DC Electrical Rewrite - Update to TSTF-360. 2CAN011301, License Amendment Request - Adoption of Technical Specification Task Force (TSTF)-500, Revision 2 DC Electrical Rewrite - Update to TSTF-3602013-01-28028 January 2013 License Amendment Request - Adoption of Technical Specification Task Force (TSTF)-500, Revision 2 DC Electrical Rewrite - Update to TSTF-360 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 1CAN061201, License Amendment Request Technical Specification Change Associated with Main Feedwater Valves2012-06-19019 June 2012 License Amendment Request Technical Specification Change Associated with Main Feedwater Valves 1CAN081001, License Amendment Request, Technical Specification Change Associated with Main Feedwater Isolation Valves2010-08-24024 August 2010 License Amendment Request, Technical Specification Change Associated with Main Feedwater Isolation Valves 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 1CAN021004, Response to Request for Additional Information, Application for Technical Specification Improvement to Adopt TSTF-490, Revision 0, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec.2010-02-28028 February 2010 Response to Request for Additional Information, Application for Technical Specification Improvement to Adopt TSTF-490, Revision 0, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec. ML0930601322009-12-23023 December 2009 License Amendment No. 240, Revised Administrative Changes to Technical Specification 5.5.8, Inservice Testing Program, to Adopt TSTF-479-A and TSTF-497-A ML0931305282009-12-23023 December 2009 License Amendment No. 241, Modified Technical Specification 3.4.9, Pressurizer, to Delete Low Pressurizer Level Limit 1CAN080901, Changes to Reflect Revision to 10 CFR 50.55a Technical Change Travelers - TSTF-479-A and TSTF-497-A2009-08-0505 August 2009 Changes to Reflect Revision to 10 CFR 50.55a Technical Change Travelers - TSTF-479-A and TSTF-497-A 2CAN030901, License Amendment Request, Technical Specification Change to Modify the Mode of Applicability for Emergency Feedwater Actuation Signal2009-03-0202 March 2009 License Amendment Request, Technical Specification Change to Modify the Mode of Applicability for Emergency Feedwater Actuation Signal 1CAN020901, License Amendment Request, Technical Specification Change to Adopt Low Pressure Air Lock Seal Test2009-02-16016 February 2009 License Amendment Request, Technical Specification Change to Adopt Low Pressure Air Lock Seal Test ML0814000372008-09-0808 September 2008 Technical Specifications for Amendment No. 282 Technical Specification Task Force TSTF-490, Rev 0, Deletion of E Bar Definition and Revision to RCS Specific Activity. ML0812203132008-08-28028 August 2008 Tech Spec Pages for Amendment No. 281 Technical Specification Task Force Change TSTF-359, Increased Flexibility in Mode Restraints. ML0823801472008-08-21021 August 2008 License Amendment Request, Technical Specification Change to Extend Integrated Leak Rate Test Interval One-Time ML0814004492008-07-23023 July 2008 Tech Spec Pages for Amendment No. 280 Reactor Coolant System Relocation to TRM (Tac MD8313) 2CAN070805, License Amendment Request Regarding Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers and Relocate TS 3.7.8 to the TRM2008-07-21021 July 2008 License Amendment Request Regarding Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers and Relocate TS 3.7.8 to the TRM 1CAN070804, License Amendment Request Regarding Technical Specification Changes Associated with Adoption of TSTF-3592008-07-21021 July 2008 License Amendment Request Regarding Technical Specification Changes Associated with Adoption of TSTF-359 1CAN070803, License Amendment Request Regarding Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers2008-07-21021 July 2008 License Amendment Request Regarding Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers ML0815402462008-07-0909 July 2008 License Page 3 & Technical Specifications for Issuance of Amendment No. 233 Containment Spray Nozzle Technical Specification Test Requirements 2023-04-14
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En terV Entergy Operations, Inc.1448S S eR. 333 Russellville, AR 72802 Tel 479-858-31 10 Timothy G. Mitchell Vice President.
Operations Arkansas Nuclear One 2CAN080701 August 30, 2007 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
REFERENCE:
License Amendment Request to Revise Technical Specification 3.1.3.4, CEA Drop Time Arkansas Nuclear One, Unit 2 Docket No. 50-368 License No. NPF-6 Entergy letter to NRC dated July 31, 2007, License Amendment Request to Revise Technical Specification 6.6.5, Core Operating Limits Report (2CAN070701)
Dear Sir or Madam:
Pursuant to 10 CFR 50.90, Entergy Operations, Inc. (Entergy) hereby requests an amendment to Arkansas Nuclear One, Unit 2 (ANO-2) Technical Specification (TS) 3.1.3.4, Control Element Assembly (CEA) Drop Time. The proposed change will revise the limit on the drop time for an individual CEA. The arithmetic average drop time or the associated delay times are not impacted by the proposed change. This change is necessary to support the implementation of Next Generation Fuel (NGF) in the next operating cycle, as described in Entergy letter dated July 31, 2007 (Reference 1).The proposed change has been evaluated in accordance with 10 CFR 50.91 (a)(1) using criteria in 10 CFR 50.92(c) and it has been determined that this change involves no significant hazards consideration.
The bases for these determinations are included in the attached submittal.
There are no new commitments contained in this letter.Entergy requests approval of the proposed amendment by February 14, 2008 in order to support the spring 2008 refueling outage. Once approved, the amendment shall be implemented prior to startup following the spring 2008 refueling outage. Although this request is neither exigent nor emergency, your prompt review is requested.
px'(ý 2CAN080701 Page 2 of 2 If you have any questions or require additional information, please contact David Bice at 479-858-5338.
I declare under penalty of perjury that the foregoing is true and correct. Executed on August 30, 2007.Sincerely,?GMdbb Attachments:
- 1. Analysis of Proposed Technical Specification Change 2. Proposed Technical Specification Changes (mark-up)cc: Dr. Bruce S. Mallett Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One P. 0. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Alan B. Wang MS 0-7 D1 Washington, DC 20555-0001 Mr. Bernard R. Bevill Director Division of Radiation Control and Emergency Management Arkansas Department of Health & Human Services P.O. Box 1437 Slot H-30 Little Rock, AR 72203-1437 Attachment I 2CAN080701 Analysis of Proposed Technical Specification Change Attachment 1 to 2CAN080701 Page 1 of 5
1.0 DESCRIPTION
This letter is a request to amend Operating License NPF-6 for Arkansas Nuclear One, Unit 2 (ANO-2).The proposed change will revise the Limiting Condition of Operations (LCOs) in ANO-2 Technical Specification (TS) 3.1.3.4, CEA Drop Time, by revising the amount of time for an individual Control Element Assembly (CEA) to travel from a fully withdrawn position until it reaches the 90% insertion position.
The current limit is 5 3.5 seconds. The proposed limit is< 3.7 seconds. The arithmetic average of the drop times for all the CEAs is unaffected by this change.
2.0 PROPOSED CHANGE
The proposed change will modify the LCO presented in TS 3.1.3.4 by changing the drop time limit for individual CEAs: The individual CEA drop time, from a fully withdrawn position, shall be < 3.7 seconds and the arithmetic average of the CEA drop times of all CEAs, from a fully withdrawn position, shall be < 3.2 seconds from when the electrical power is interrupted to the CEA drive mechanisms until the CEAs reach their 90 percent insertion positions with: a. Tavg > 525 OF, and b. All reactor coolant pumps operating.
The revised drop time limit is associated with the implementation of Combustion Engineering (CE) 16 x 16 Next Generation Fuel (NGF) as defined in "CE 16 x 16 Next Generation Fuel Core Reference Report," WCAP-16500-P (Reference 2). The applicable TS Bases will be revised and implemented in conjunction with this amendment requests in accordance with the ANO-2 TS Bases Control Program, TS 6.5.14.
3.0 BACKGROUND
CE 16 x 16 NGF as defined in WCAP-16500-P (Reference
- 2) will be implemented at ANO-2 beginning in Cycle 20 following the spring 2008 refueling outage. The ANO-2 specific application of NGF is described in Entergy letter to the NRC dated July 31, 2007 (Reference 1). The fuel design is intended to provide improved fuel reliability by reducing grid-to-rod fretting issues, improved fuel performance for high duty operation, and enhanced operating margin.The current time limits provided in the LCO for TS 3.1.3.4 were approved by the NRC in Amendment 100 to the ANO-2 Operating License. Prior to this amendment the assumption used in the safety analyses was that all CEAs drop into the core at the same time and at the same rate following a reactor trip. This amendment approved the concept that the negative reactivity insertion for any reasonable distribution of CEAs is more directly correlated to, and can be represented by, the average CEA insertion rather than by the slowest CEA.
Attachment 1 to 2CAN080701 Page 2 of 5 Based on measured CEA drop patterns at ANO-2, the CEAs do not fall at the same time and at the same rate during a reactor trip. This change associated with Amendment 100 was primarily due to the distribution of CEA extension shaft weights in ANO-2. The longer heavier extension shafts located at the core interior cause faster CEA drop times, which become progressively slower towards the core periphery where the CEA extension shafts are shorter and less heavy.In addition, the radial flux for the ANO-2 core is relatively flat or unchanging with time except near the core periphery.
On the periphery the flux is significantly lower than the average since ANO-2 employs low-leakage fuel management.
As noted previously, the few CEAs along the periphery have shorter extension shafts, thus slower drop times.In the Safety Evaluation (SE) for Amendment 100, the NRC noted that the negative reactivity added by CEAs falling in a reasonable distribution about an average position is essentially the same as the reactivity added by all CEAs falling at the same average position.
The NRC also noted that this should hold true for any reasonable family of CEA distributions similar to those measured at ANO-2. However, if the distance between the fastest and slowest CEAs becomes too large or the distribution of CEAs deviates significantly from that modeled by CE in the study, then the average CEA position may not be representative of the time dependent reactivity insertion.
Therefore, a limit was placed on the CEA drop time distribution.
This is expressed as a maximum drop time limit on the slowest CEA. This is to ensure that the safety analyses remain valid for the average CEA drop time.In the Safety Evaluation Report for Amendment 100, the NRC listed two conditions to their approval.
These conditions were: 1. Any fuel management change that significantly affects the core wide axial or radial power profiles, such as axial blankets or ultra-low leakage fuel management, may necessitate reverification of the average CEA drop time analysis.2. Changes that would significantly affect the CEA drop time distribution, such as changes to the CEDM circuits, large increases in the core flow pressure drop, changes in the total drop weight of the CEAs or changes in the location of the CEAs, may also require reverification of the average CEA drop time concept.The NRC noted in their final SE for WCAP-1 6500-P (Reference
- 3) that the ability to insert control rods within the time requirements assumed within the safety analysis is crucial. While the NGF design maintains the same interface configuration with the CEAs as the standard 16 x 16 CE assembly design, the NGF's design increased pressure drop has the potential to lengthen the time for the CEAs to insert.The location and weight of the CEAs and their associated extension shafts are not changing due to the implementation of NGF for Cycle 20. There are no changes to the CEDM circuits planned for the next refueling outage. In addition there are no fuel management changes that will significantly affect the power profiles being made for Cycle 20.
Attachment 1 to 2CAN080701 Page 3 of 5 4.0 TECHNICAL ANALYSIS Approximately half of the ANO-2 Cycle 20 reload core will be NGF and Cycle 21 will be essentially a full core of NGF. The impact on the CEA drop time due to a full core of NGF has been evaluated since it is the limiting case. This evaluation accounted for uncertainties on the increase in core pressure drop and the weight of the CEAs. The evaluation showed a maximum increase of approximately
0.2 seconds
for an individual CEA with the shortest extension shaft due to the implementation of NGF.An evaluation was performed to assess the time limit for the average of the drop times. The difference in the calculated insertion time to 90% inserted for a standard 16 x 16 CE fuel core and a NGF core was added to the worst average CEA drop time measured at ANO-2 over the last four cycles of standard 16 x 16 CE fuel and compared to the limit of 3.2 seconds. The results show there is sufficient margin to this limit with a full core of NGF. Top and bottom peaked power shapes were evaluated as well. It was determined that the fission power versus time of CEA insertions assuming a distribution of CEA drop times is the same or produced less fission power than CEA insertions assuming all CEAs dropping at the average of the distribution.
The distribution of CEA drop times is predominately a result of the different extension shaft weights and as such will continue to have the same general type of'variations from location to location.
Therefore, the general shape of the distribution of drop times should not change as a result of the introduction of NGF fuel. To quantify the magnitude of any change in the drop time distribution, the range in predicted drop times in standard and NGF cores was compared to the average drop times. The range in standard drop times represents 7.9% of the standard average drop time. The range in NGF drop times represents 8.6% of the NGF average drop time. Since the general shape of the drop time distribution is expected to be the same and the differences in the range as a percentage of the average are minimal between the standard 16 x 16 CE fuel and NGF cores, it is concluded that the implementation of NGF will not have a significant effect on the CEA drop time distribution.
Based on the above information, the only change due to NGF is to the amount of time required for the slowest CEA to drop into the core on a reactor trip. Since the average time is not changing, the safety analyses do not require a revision.While the slowest individual CEA is expected to fall up to 0.2 seconds slower and the distance between the fastest and slowest CEAs is increasing, the average CEA drop time concept has been reverified for a NGF core as required by an NRC condition listed in their SE for Amendment 100.
Attachment 1 to 2CAN080701 Page 4 of 5 5.0 REGULATORY ANALYSIS 5.1 Applicable Regulatory Requirements/Criteria The proposed change has been evaluated to determine whether applicable regulations and requirements continue to be met. Negative reactivity insertion rates relate to requirements of 10 CFR 50.36, Appendix A, General Design Criterion (GDC) 10, Reactor Design, GDC 26, Reactivity Limits, and 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors.
Entergy has determined that the proposed change does not require any exemptions or relief from regulatory requirements, other than the TS, and do not affect conformance with any GDC differently than described in the Safety Analysis Report (SAR). The proposed change is similar to that approved in ANO-2 TS Amendment 100, dated October 12, 1989.5.2 No Significant Hazards Consideration The proposed change will modify Arkansas Nuclear One, Unit 2 (ANO-2) Technical Specification (TS) 3.1.3.4 related to the drop time limit for an individual Control Element Assembly (CEA). The change in individual CEA drop time is required due to application of New Generation Fuel (NGF), as described in Entergy Operations, Inc. (Entergy) letter to NRC dated July 31, 2007, License Amendment Request to Revise Technical Specification 6.6.5, Core Operating Limits Report (2CAN070701).
Entergy has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92,"Issuance of amendment," as discussed below: 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response:
No.The proposed change to the CEA drop time requirements have been evaluated for impact on the ANO-2 accident analyses.
The change involves only an acceptance criterion for equipment performance and not physical changes. The CEA drop time acceptance criteria are used to develop trip reactivity insertion rates which are in turn used as inputs to the accident analyses.Previous analyses demonstrated that the calculated trip reactivity for a realistic distributed CEA drop pattern is the same as the trip reactivity calculated for the non-distributed pattern. The current evaluations reverified this approach.
The only difference is the maximum time limit for an individual CEA. Since the trip reactivity assumed in the accident analyses is not adversely impacted by consideration of a distributed CEA drop pattern with a larger distribution around the same average position, the proposed limits will not increase the probability or consequences of an accident previously evaluated.
Attachment 1 to 2CAN080701 Page 5 of 5 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response:
No.The proposed change does not involve any new or modified structures, systems, or components; rather, it affects only an acceptance criterion for confirming the required performance of the existing CEA hardware.
Therefore, the proposed change would not create the possibility of a new or different kind of accident from any previously evaluated.
- 3. Does the proposed change involve a significant reduction in a margin of safety?Response:
No.The margins of safety related to CEA insertion are defined by the analyzed events in the Safety Analysis Report which credit the insertion.
As demonstrated above, the proposed limits on the CEA drop time have no adverse impact on the accident analyses.
Therefore, the margins of safety reflected in the accident analysis conclusions are not reduced.Based on the above, Entergy concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.
5.3 Environmental
Considerations The proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure.
Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
6.0 REFERENCES
- 1. Entergy letter to NRC dated July 31, 2007, "License Amendment Request to Revise Technical Specification 6.6.5, Core Operating Limits Report" (2CAN070701)
- 2. Westinghouse Topical Report WCP-16500-P, "CE 16 x 16 Next Generation Fuel Core Reference Report," Revision 0 3. NRC Letter to Westinghouse dated July 30, 2007, "Final Safety Evaluation for Westinghouse Electric Company (Westinghouse)
Topical Report (TR) WCAP-16500-P, Revision 0, "CE [Combustion Engineering]
16 x 16 Next Generation Fuel [(NGF)] Core Reference Report" Attachment 2 2CAN080701 Proposed Technical Specification Changes (mark-up)
REACTIVITY CONTROL SYSTEMS CEA DROP TIME LIMITING CONDITION FOR OPERATION 3.1.3.4 The individual CEA drop time, from a fully withdrawn position, shall be 3-.53.7 seconds and the arithmetic average of the CEA drop times of all CEAs, from a fully withdrawn position, shall be < 3.2 seconds from when the electrical power is interrupted to the CEA drive mechanisms until the CEAs reach their 90 percent insertion positions with: a. Tavg > 525°F, and b. All reactor coolant pumps operating.
APPLICABILITY:
MODES 1 and 2.ACTION: a. With the CEA drop times determined to exceed either of the above limits, restore the CEA drop times to within the above limits prior to proceeding to MODE 1 or 2.b. With the CEA drop times within limits but determined at less than full reactor coolant flow, operation may proceed provided THERMAL POWER is restricted to less than or equal to the maximum THERMAL POWER level allowable for the reactor coolant pump combination operating at the time of CEA drop time determination.
SURVEILLANCE REQUIREMENTS 4.1.3.4 The CEA drop time of all CEAs shall be demonstrated through measurement prior to reactor criticality:
- a. For all CEAs following each removal of the reactor vessel head, b. For specifically affected individuals CEAs following any maintenance on or modification to the CEA drive system which could affect the drop time of those specific CEAs, and c. At least once per 18 months.ARKANSAS -UNIT 2 3/4 1-23 Amendment No. 84,94,400,-169, CorrGectie L9tt#r dated 10124!95