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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 - 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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 - 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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,