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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] |
Text
Entergy Operations, Inc.
1448 S.R. 333 Russellville, AR 72802 Tel 479-858-3110 Jeremy G. Browning Vice President - Operations Arkansas Nuclear One 2CAN071301 July 1, 2013 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
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 Arkansas Nuclear One, Unit 2 Docket No. 50-368 License No. NPF-6
REFERENCES:
- 1. Entergy letter dated April 4, 2012, License Amendment Request -
Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-471 (2CAN041201) (ML12096A022) (TAC No. ME8348)
- 2. NRC email dated May 10, 2012, Proposed License Amendment Request to Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-471 (ML121310562)
- 3. Entergy letter dated July 9, 2012, 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 (2CAN071201) (ML12192A089) (TAC No. ME8348)
- 4. NRC email dated June 12, 2013, Request for Additional Information -
Proposed License Amendment Request to Technical Specification (TS)
Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-471 (TAC No. ME8348)
- 5. Entergy letter dated June 18, 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 (2CAN061302) (TAC No. ME8348)
2CAN071301 Page 2 of 3
Dear Sir or Madam:
With regard to Reference 1, Entergy Operations, Inc. (Entergy) submitted a request to amend the Technical Specifications (TSs) for Arkansas Nuclear One, Unit 2 (ANO-2) related to a revised fuel assembly drop analysis and adoption of NRC-approved Technical Specification Task Force (TSTF) Standard Technical Specification Change Travelers TSTF-51, TSTF-272, TSTF-286, and TSTF-471. By email dated May 10, 2012 (Reference 2), the NRC accepted the proposed amendment for review and notified Entergy of supplemental information that would be necessary for the NRC to complete the overall review of the Reference 1 submittal. Entergy submitted the requested supplemental information in letter dated July 9, 2012 (Reference 3).
By email dated June 12, 2013 (Reference 4), the NRC identified minor changes needed to complete the review process. The NRC also requested that all of Attachment 1 of the Reference 3 letter be resubmitted and all the TS pages be resubmitted, in order for this final supplement to represent a complete package. Entergy submitted the requested supplemental information in letter dated June 18, 2013 (Reference 5).
During subsequent review of Attachment 2 of the Reference 5 supplemental letter, an error was discovered on the markup of TS page 3/4 3-25 in that the markup page did not exactly match the corresponding clean (revised) TS page (Attachment 3 of the Reference 5 letter), nor did it match the corresponding discussion and illustration included on Pages 23 and 24, respectively, of Attachment 1 of the Reference 5 letter. Specifically, Table 3.3-6 Note 3.b does not contain the TSTF-51 term "recently." This term is appropriately included in the aforementioned attachments of the Reference 5 letter. Therefore, a revised markup page is provided in Attachment to this letter, which includes the missing term. Entergy requests the NRC substitute the respective TS markup page included in this letter in lieu of the corresponding TS markup page contained in Attachment 2 of the Reference 5 letter.
No change in the commitments included in Attachment 4 of the Reference 5 letter is being made. In addition, the changes incorporated by this supplemental letter have no impact on the no significant hazards consideration (NSHC) included in Attachment 1 of the Reference 5 letter.
In accordance with 10 CFR 50.91(b)(1), a copy of this application and the NSHC is being provided to the designated Arkansas state official.
If you have any questions or require additional information, please contact Stephenie Pyle at 479-858-4704.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on July 1, 2013.
Sincerely, ORIGINAL SIGNED BY JEREMY G. BROWNING JGB/dbb
Attachment:
Markup of Technical Specification Page
2CAN071301 Page 3 of 3 cc: Mr. Arthur T. Howell Regional Administrator U. S. Nuclear Regulatory Commission Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 NRC Senior Resident Inspector Arkansas Nuclear One P. O. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Kaly Kalyanam MS O-8B1 One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. Bernard R. Bevill Arkansas Department of Health Radiation Control Section 4815 West Markham Street Slot #30 Little Rock, AR 72205
Attachment to 2CAN071301 Markup of Technical Specification Page
TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICABLE ALARM/TRIP MEASUREMENT INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION
- 1. AREA MONITORS
- a. Spent Fuel Pool Area Monitor 1 Note 1 1.5 x 10-2 R/hr 10 101 R/hr 13
- b. Containment High Range 2 1, 2, 3, & 4 Not Applicable 1 - 107 R/hr 18
- 2. PROCESS MONITORS
- a. Containment Purge and 10 - 106 cpm 1 5 & 6Note 3 2 x background 16 Exhaust Isolation
- b. Control Room Ventilation 10 - 106 cpm 2 Note 2 2 x background 17,20,21 Intake Duct Monitors
- c. Main Steam Line 1/Steam Line 1, 2, 3, & 4 Not Applicable 10 104 mR/hr 19 Radiation Monitors Note 1 - With fuel in the spent fuel pool or building.
Note 2 - MODES 1, 2, 3, 4, and during movementhandling of irradiated fuel assemblies or movement of new fuel assemblies over irradiated fuel assemblies.
Note 3 - Applicable during:
- a. PURGE of the Containment Building or,
- b. Containment Building continuous ventilation operations when moving recently irradiated fuel assemblies or moving new fuel assemblies over recently irradiated fuel assemblies in the Containment Building.
ARKANSAS - UNIT 2 3/4 3-25 Amendment No. 63,130,145,206,231,255,
