Letter Sequence Request |
---|
|
|
MONTHYEARML0734505262007-12-13013 December 2007 Request for Additional Information License Amendment Request to Revise TS 3.6.2.2, Trisodium Phosphate, to Allow Permanent Use of Sodium Tetraborate (Natb) as Containment Sump Buffering Agent Project stage: RAI ML1012506042010-05-0505 May 2010 E-mail Arkansas Nuclear One, Unit 2 - Acceptance Review Email, License Amendment Request, Technical Specification Changes and Analyses Relating to Use of Alternative Source Term Project stage: Acceptance Review ML1014502942010-05-25025 May 2010 Request for Additional Information License Amendment Request for Technical Specification Changes and Analyses Regarding Use of Alternate Source Project stage: RAI 2CAN061004, License Amendment Request Technical Specification Changes and Analyses Relating to Use of Alternative Source Term - Supplemental Information2010-06-23023 June 2010 License Amendment Request Technical Specification Changes and Analyses Relating to Use of Alternative Source Term - Supplemental Information Project stage: Supplement ML1019604922010-07-15015 July 2010 Email, Request for Additional Information License Amendment Request to Implement an Alternative Source Term Project stage: RAI ML1018102182010-07-29029 July 2010 Request for Withholding Information from Public Disclosure, 6/3/2010 Affidavit Executed by J. Gresham, Westinghouse Calculation Note CN-OA-08-15, Revision 0, TAC No. ME3678 Project stage: Withholding Request Acceptance ML1018102242010-07-29029 July 2010 Request for Withholding Information from Public Disclosure, 6/3/2010 Affidavit Executed by J. Gresham, Westinghouse Calculation Note CN-OA-08-16, Revision 0, TAC No. ME3678 Project stage: Withholding Request Acceptance ML1018102262010-07-29029 July 2010 Request for Withholding Information from Public Disclosure - 6/3/2010 Affidavit Executed by J. Gresham, Westinghouse Calculation Note CN-OA-08-17, Revision 0 Project stage: Withholding Request Acceptance ML1018102332010-07-29029 July 2010 Request for Withholding Information from Public Disclosure - 6/3/2010 Affidavit Executed by J. Gresham, Westinghouse Calculation Note CN-OA-08-57, Revision 0 Project stage: Withholding Request Acceptance ML1018103452010-07-29029 July 2010 Request for Withholding Information from Public Disclosure - 6/3/2010 Affidavit Executed by J. Gresham, Westinghouse Calculation Note CN-OA-08-18, Revision 0 Project stage: Withholding Request Acceptance ML1018103372010-07-29029 July 2010 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML1018103312010-07-29029 July 2010 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance 2CAN081001, Request for Additional Information, Technical Specification Changes and Analyses Relating to Use of Alternative Source Term2010-08-0909 August 2010 Request for Additional Information, Technical Specification Changes and Analyses Relating to Use of Alternative Source Term Project stage: Request ML1023104312010-08-19019 August 2010 Email, Request for Additional Information, Round 3, License Amendment Request for Technical Specification Changes and Analyses Regarding Use of Alternate Source Term Project stage: RAI 2CAN081007, Request for Additional Information Implementation of a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-7162010-08-24024 August 2010 Request for Additional Information Implementation of a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-716 Project stage: Request 2CAN091002, Request for Additional Information Technical Specification Changes and Analyses Relating to Use of Alternative Source Term2010-09-16016 September 2010 Request for Additional Information Technical Specification Changes and Analyses Relating to Use of Alternative Source Term Project stage: Request ML1109801972011-04-26026 April 2011 Issuance of Amendment No. 293, Technical Specification Changes and Analyses Regarding Use of Alternate Source Term Project stage: Approval ML1115108242011-05-0202 May 2011 Email Correction to the Safety Evaluation (SE) on the Alternate Source Term License Amendment Request, (SE Issued on April 26, 2011) Project stage: Request ML1115110012011-08-0909 August 2011 Correction to Safety Evaluation for Amendment No. 293 Related to Use of Alternate Source Term Project stage: Approval 2010-08-19
[Table View] |
|
---|
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
%--
mwse%
Entergy Entergy Operations, Inc.
1448 SsR. 333 Russellville, AR 72802 Tel 479-858-3110 Brad L. Berryman Acting Vice President, Operations Arkansas Nuclear One 2CAN081 001 August 9, 2010 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Request for Additional Information Technical Specification Changes and Analyses Relating to Use of Alternative Source Term
'Arkansas Nuclear One, Unit 2 Docket No. 50-368 License No. NPF-6
REFERENCES:
- 1. Entergy letter to the NRC, dated October 5, 2007, "License Amendment Request Technical Specification Change Request Associated with Replacement of Containment Sump Buffer' (2CAN 100703)
- 2. Entergy letter to the NRC, dated February 19, 2008, "License Amendment Request Replacement of Containment Sump Buffer Request for Additional Information" (2CAN020802)
- 3. NRC letter to Entergy dated March 31, 2008, "Arkansas Nuclear One, Unit No. 2 - Issuance of Amendment RE: Technical Specifications 3.6.2.2, 'Containment Sump Buffering Agent Trisodium Phosphate (TSP)'
(TAC No. MD6933)" (2CNA030809)
- 4. Entergy letter to the NRC, dated March 31, 2010, "License Amendment Request Technical Specification Changes and Analyses Relating to Use of Alternative Source Term" (2CAN031001)
- 5. Email from Kaly Kalyanam (NRC) to Robert W. Clark (Entergy), dated May 5, 2010, "Transmission of the Acceptance Review Result to Licensee and Request for Supplemental Information (TAC No. ME3678)
- 6. Email from Kaly Kalyanam (NRC) to Robert W. Clark (Entergy), dated May 25, 2010, "Request for Additional Information on the AST LAR -
ME3678" Abc)
2CAN081 001 Page 2 of 3 REFERENCES (continued):
- 7. Entergy letter to the NRC, dated June 23, 2010, "License Amendment Request Technical Specification Changes and Analyses Relating to Use of Alternative Source Term - Supplemental Information" (2CAN061004)
- 8. Entergy letter to the NRC, dated June 24, 2010, "Request For Additional Information Technical Specification Changes and Analyses Relating to Use of Alternative Source Term" (2CAN061002)
- 9. Email from Kaly Kalyanam (NRC) to David B. Bice (Entergy), dated July 15, 2010, "Request for Additional Information on the ANO-2 LAR to implement AST - ME3678"
Dear Sir or Madam:
Entergy Operations, Inc. (Entergy) submitted a request to change the Technical Specifications (TSs) for Arkansas Nuclear One, Unit 2 (ANO-2) in support of the use of alternative source terms associated with accident offsite and control room dose consequences (Reference 4).
Supplemental information was submitted to the NRC via References 7 and 8 above.
During continued review of the material provided in Reference 4, the NRC determined that further information was required to complete the Staffs evaluation of the request (Reference 9).
Attached to this submittal is the Reference .9 Request for Additional Information (RAI) along with Entergy's response.
This letter contains no new commitments.
If you have any questions or require additional information, please contact Mark Giles at 479-858-4710.
I declare under penalty of perjury that the foregoing is true and correct. Executed on August 9, 2010.
Sincerely, BLB/dbb
Attachment:
Response to Request for Additional Information Related to the Use of Alternative Source Term (AST)
2CAN081 001 Page 3 of 3 cc: Mr. Elmo E. Collins Regional Administrator U. S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 NRC Senior Resident Inspector Arkansas Nuclear One P. O. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Kaly Kalyanam MS 0-8 B1 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 2CAN081001 Response to Request for Additional Information Related to the Use of Alternative Source Term (AST)
Attachment to 2CAN081 001 Page 1 of 2 Response to Request for Additional Information Related to the Use of Alternative Source Term (AST)
- 1. Are any non-safety related systems and components credited in the alternate source term analyses?
No non-safety related electrical systems or components are credited in the Arkansas Nuclear One, Unit 2 (ANO-2) alternate source term (AST) analyses. Analyses requiring cool down to shutdown cooling (SDC) entry conditions credit the non-safety related Atmospheric Dump Valves (ADVs), which are designed to fail open upon loss of air and are located upstream of the Main Steam Isolation Valves (MSIVs). Steam release can then be controlled by safety-related motor-operated isolation valves located upstream of each ADV.
If so,
- a. Please describe the independence (electrical and physical separation) of these systems from the safety-related systems. Also, please provide a detailed discussion on how a fault on the non-Class 1E electrical circuit will not propagate to the Class I E electrical circuit.
The safety-related ADV isolation valves are located in seismic Category 1 piping, with the classification change occurring immediately downstream of the isolation valves.
Thus, physical separation of the piping and non-safety related ADVs downstream of the isolation valves is provided by this seismic boundary. No non-Class 1 E electrical circuits are credited in the ANO-2 AST analyses. Therefore, all safety-related Class 1E circuits remain electrically independent of non-Class 1 E circuits, and faults in non-Class 1 E circuits will not propagate to Class 1 E circuits.
- b. Please describe the redundancy of these systems and how these systems meet the single failure criterion.
As stated above, the ADVs fail open on loss of instrument air supply. The ADV isolation valves are capable of remote operation from the control room or associated Motor Control Center (MCC) breaker. In addition, the ADVs and ADV isolation valves are all capable of local, manual operation. Manual operation of ADVs is addressed in OP 2105.008, "Steam Dump and Bypass Control System Operations." The ANO-2 AST analyses do not credit an ADV pathway for at least 30 minutes following the initiation of an accident, providing sufficient time to take local, manual action, if required. As such, there is no credible active or passive single failure in an electrical system or active single failure in a fluid system that can prevent opening a pathway to atmosphere and allowing cool down to SDC entry conditions.
Attachment to 2CAN081 001 Page 2 of 2
- c. Please describe how the operators will be notified (e.g., control room annunciators) in the event that these systems and components become inoperable.
Although there is no credible means for the ADV pathway to become inoperable, if isolation of the pathway were to occur, the operators would be alerted by a rapid increase in the associated steam generator (SG) pressure and, if no action were taken, the eventual opening of at least one Main Steam Safety Valve (MSSV).
Discharges from the MSSVs are monitored in the control room via an acoustic monitoring panel.
- d. Describe seismic qualifications of these systems and components.
The ASME Class II piping in which the ADVs are installed has been analyzed and designed to withstand seismic loads in accordance with Section C-2 of NRC Regulatory Guide 1.29.
- 2. Are any loads being added to the Arkansas Nuclear One emergency diesel generators (EDGs)? If so, describe how the loads will impact the capability and capacity of the EDGs. Also, please describe the changes, if any, to the EDG loading sequence to support this license amendment request (LAR).
No electrical loads need to be added to the ANO-2 EDGs to support this LAR or the assumptions of the ANO-2 AST analyses.
- 3. Please provide a list and description of components being added to the Environmental Qualification Program (10 CFR 50.49) due to this LAR. Also, please confirm that these components are qualified for the environmental conditions they are expected to be exposed to.
No components need to be added to the Environmental Qualification Program (10 CFR 50.49) due to this LAR.