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Line 41: |
Line 41: |
| : 1. Entergy letter to the NRC, dated October 26, 2009, "Supplemental to Response to Request for Information Regarding Steam Generator Tube | | : 1. Entergy letter to the NRC, dated October 26, 2009, "Supplemental to Response to Request for Information Regarding Steam Generator Tube |
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| Integrity During Break in Upper Hot Leg Piping" (1CAN100903) | | Integrity During Break in Upper Hot Leg Piping" (1CAN100903) |
| : 2. NRC letter to ANO, dated November 4, 2009, "Arkansas Nuclear One, Unit No. 1 - Once-Through Steam Generator Tube Loads Under | | : 2. NRC letter to ANO, dated November 4, 2009, "Arkansas Nuclear One, Unit No. 1 - Once-Through Steam Generator Tube Loads Under |
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Letter Sequence Other |
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TAC:MD7178, Control Room Habitability (Approved, Closed) |
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MONTHYEARL-2007-087, Proposed License Amendment, Alternative Source Term and Conforming Amendment2007-07-16016 July 2007 Proposed License Amendment, Alternative Source Term and Conforming Amendment Project stage: Other 1CAN100703, License Amendment Request - Technical Specification Changes and Analyses Relating to Use of Alternate Source Term2007-10-22022 October 2007 License Amendment Request - Technical Specification Changes and Analyses Relating to Use of Alternate Source Term Project stage: Request ML0805104412008-02-27027 February 2008 Request for Additional Information Regarding Implementation of an Alternate Source Term Project stage: RAI 1CAN080801, Response to Request for Additional Information Regarding Technical Specification Changes and Analyses Relating to Use of Alternate Source Term2008-08-14014 August 2008 Response to Request for Additional Information Regarding Technical Specification Changes and Analyses Relating to Use of Alternate Source Term Project stage: Response to RAI 1CAN090802, Response to Request for Additional Information Regarding Technical Specification Changes and Analyses Relating to Use of Alternate Source Term2008-09-18018 September 2008 Response to Request for Additional Information Regarding Technical Specification Changes and Analyses Relating to Use of Alternate Source Term Project stage: Response to RAI ML0923901842009-08-27027 August 2009 Request for Additional Information Email Regarding License Amendment Request to Support the Adoption and Use of the Alternate Source Term in the ANO-1 Safety Analyses Project stage: RAI 1CAN080902, Response to Request for Information Regarding Steam Generator Tube Integrity During Break in Upper Hot Leg Piping2009-08-31031 August 2009 Response to Request for Information Regarding Steam Generator Tube Integrity During Break in Upper Hot Leg Piping Project stage: Response to RAI 1CAN080903, Updated Information Regarding Technical Specification Changes and Analyses Relating to Use of Alternate Source Term in Reference to Nrc/Pwrog Meeting Held June 25, 20092009-08-31031 August 2009 Updated Information Regarding Technical Specification Changes and Analyses Relating to Use of Alternate Source Term in Reference to Nrc/Pwrog Meeting Held June 25, 2009 Project stage: Meeting ML0927400352009-10-21021 October 2009 Issuance of Amendment No. 238, Modify Technical Specifications Related to Use of Alternate Source Term Associated with Accident Offsite/Control Room Dose Consequences Project stage: Approval 1CAN100903, Supplemental to Response to Request for Information Regarding Steam Generator Tube Integrity During Break in Upper Hot Leg Piping2009-10-26026 October 2009 Supplemental to Response to Request for Information Regarding Steam Generator Tube Integrity During Break in Upper Hot Leg Piping Project stage: Supplement ML0930104342009-11-0404 November 2009 Once-Through Steam Generator Tube Loads Under Conditions Resulting from Postulated Breaks in Reactor Coolant System Upper Hot Leg Large-Bore Piping Project stage: Other 1CAN011004, Summary of Analysis Related to ANO-1 Once-Through Steam Generator Tube Thermal Loads Due to Breaks in RCS Upper Hot Leg Large-Bore Piping2010-01-26026 January 2010 Summary of Analysis Related to ANO-1 Once-Through Steam Generator Tube Thermal Loads Due to Breaks in RCS Upper Hot Leg Large-Bore Piping Project stage: Other 2009-10-21
[Table View] |
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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
1CAN011004
January 26, 2010
U.S. Nuclear Regulatory Commission
Attn: Document Control Desk
Washington, DC 20555
SUBJECT:
Summary of Analysis Related to ANO-1 Once-Through Steam Generator Tube Thermal Loads due to Breaks in RCS Upper Hot Leg Large-Bore Piping
Arkansas Nuclear One, Unit 1
Docket No. 50-313
License No.
DPR-51
REFERENCES:
- 1. Entergy letter to the NRC, dated October 26, 2009, "Supplemental to Response to Request for Information Regarding Steam Generator Tube
Integrity During Break in Upper Hot Leg Piping" (1CAN100903)
- 2. NRC letter to ANO, dated November 4, 2009, "Arkansas Nuclear One, Unit No. 1 - Once-Through Steam Generator Tube Loads Under
Conditions Resulting from Postulated Breaks in Reactor Coolant System
Upper Hot Leg Large-Bore Piping"" (TAC No. MD 7178)
Dear Sir or Madam:
In Reference 1, Entergy Operations, Inc. (Entergy) committed to verify that the Arkansas
Nuclear One, Unit 1 (ANO-1) Steam Generators are designed to withstand the thermal loading
associated with the worst-case large break Loss of Coolant Accident (LBLOCA), specifically a
LBLOCA in the upper hot leg (candy-cane) piping, and that tube integrity will be maintained for
this LBLOCA as verified through implementation of Technical Specification (TS) 5.5.9, Steam
Generator (SG) Program. Entergy further committed to notify the NRC of the acceptability of
the ANO-1 SGs with regard to the aforementioned LBLOCA within 30 days following the
completion of the verification.
In Reference 2, the NRC acknowledged the above commitment. In addition, the NRC
presented its expectation that the ANO-1 Safety Analysis Report (SAR) would be updated as
necessary to reflect the ANO-1 SG design and management of SG tube integrity for LBLOCA loads. The SAR update would include removal of any reference to the Pressurized Water
Reactor Owners Group (PWROG) Topical Report BAW-2374, Revision 2, "Risk-Informed
Assessment of Once-Through Steam Generator Tube Thermal Loads Due to Breaks in Reactor
Coolant System Upper Hot Leg Large-Bore Piping," because this Topical Report has not been
endorsed or approved by the NRC.
Entergy Operations, Inc.
1448 S.R. 333 Russellville, AR 72802
Tel 479-858-5338 David Bice A cting Manager, Licensing A rkansas Nuclear One
1CAN011004 Page 2 of 3
Following completion of the aforementioned verification of SG tube integrity considering the
RCS upper hot leg LBLOCA, Entergy implemented necessary changes to the ANO-1 SAR. No
references to Topical Report BAW-2374 were noted. The Alternate Source Term (AST) for
ANO-1 approved by the NRC by letter dated October 29, 2009 (1CNA100901) was
implemented at the site in conjunction with the SAR update following the aforementioned
verification. The updated SAR is currently scheduled for submittal to the NRC by October 2010
in accordance with 10 CFR 50.71.
The verification of SG tube integrity with regard to the upper hot leg LBLOCA was completed by
AREVA on January 8, 2010 (AREVA-10-00083). The results are summarized in AREVA Report
51-9125139-001 "Summary Report for Qualification of EOTSG for LBLOCA Loading." This
analysis parametrically evaluated the tube-to-tubesheet weld of the SGs for the tube axial load
resulting from LBLOCA long-term differentia l thermal expansion between the tube and the SG shell (determined to be the only area of significant concern). AREVA concluded that tube
integrity is maintained with regard to the structural integrity for the tube axial load resulting from
LBLOCA long-term differential thermal expansion. The report additionally verified that the
current 40% through-wall (TW) plugging limit for SG tubes at ANO-1 as designated in TS 5.5.9
remains conservative to ensure tube integrity is maintained. AREVA Report 51-9125139-001
will be referenced in the ANO-1 Steam Generat or Inspection Program document as a bases document for the plugging limit. Based on these results, no TS changes will be required for
ANO-1.
The AREVA report is proprietary in nature, but can be reviewed by the NRC at the AREVA
office or at ANO. The report is not proposed to be docketed at this time.
The verification performed by AREVA is based on t he TS 5.5.9 SG program which implements inspection requirements that ensure SG tube integrity is assessed on a routine basis and that
degrading tubes are removed from service prior to exceeding the 40% TW limit. The program requires projected flaw growth to be determined to provide high confidence that a degraded
tube will not exceed the TS TW limit prior to the next scheduled unit shutdown.
Based on the above information, Entergy considers the Reference 1 licensee commitment to be
closed.
This letter contains no new commitments.
If you have any questions or require additional information, please contact David Bice at
479-858-5338.
Sincerely,
DBB/dbb
1CAN011004 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. Alan B. Wang
MS O-7 D1
One White Flint North
11555 Rockville Pike
Rockville, MD 20852
U. S. Nuclear Regulatory Commission
Attn: Mr. Kaly Kalyanam
MS O-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