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Category:E-Mail
MONTHYEARML24227A0072024-08-13013 August 2024 NRR E-mail Capture - LIC-109 Acceptance - ANO 2 - Proposed Alternative for Implementation of Extended Reactor Vessel In-Service Inspection Interval (ANO2-ISI-24-02) - EPID L-2024-LLR-0048 ML24218A0652024-08-0202 August 2024 NRR E-mail Capture - LIC-109 Acceptance Review - Arkansas Nuclear One, Unit 1 - License Amendment Request - Request for Review and Approval Changes to SAR and to a Confirmatory Order - Pzr Htr Emergency Power Supply - EPID L-2024-LLA-0092 ML24180A0022024-06-26026 June 2024 NRR E-mail Capture - LIC-109 Acceptance - ANO 1 and 2 - Proposed Alternatives for Examinations of SG Pressure Retaining Welds and Full Penetrations Nozzles - EPID L-2024-LLR-0038 ML24117A0262024-04-26026 April 2024 NRR E-mail Capture - ANO Unit 2 - Acceptance of Requested Licensing Action License Amendment Request to Revise Typographical Errors in Technical Specifications ML24088A0082024-03-27027 March 2024 NRR E-mail Capture - ANO-2 -- TSTF-505 Post-Audit Final RAI (L-2023-LLA-0052) ML23269A0232023-09-22022 September 2023 NRR E-mail Capture - Arkansas Nuclear One, Unit 2 - TSTF-505 Audit Questions ML23240A3412023-08-28028 August 2023 NRR E-mail Capture - ANO-2, Grand Gulf, and River Bend - Acceptance Review of LAR Revising TSs to Adopt TSTF-205, Revision of Channel Calibration, Channel Functional Test, and Related Definitions ML23194A1752023-07-13013 July 2023 NRR E-mail Capture - ANO-1 - Acceptance Review of Alternative Request ANO1-ISI-037 ML23187A0432023-07-0303 July 2023 NRR E-mail Capture - Arkansas Nuclear One, Unit 1 - TSTF-505 Audit Agenda ML23166A0132023-06-14014 June 2023 NRR E-mail Capture - Arkansas Nuclear One, Unit 1 - TSTF-505 Audit Questions ML23130A2752023-05-10010 May 2023 NRR E-mail Capture - ANO Unit 2- Acceptance of Requested Licensing Action LAR to Adopt TSTF-505 Revision 2 ML23118A0692023-04-28028 April 2023 NRR E-mail Capture - ANO Unit 1 - Acceptance of Requested Licensing Action LAR to Modify ANO-1 TS 3.3.1, Reactor Protection System Instrumentation (L-2023-LLA-0048) ML23104A1052023-03-10010 March 2023 NRR E-mail Capture - ANO-2 Final RAI Alternative Request for Life-of-Repair of RVCH Pen. 46 ML23072A3672023-03-0909 March 2023 NRR E-mail Capture - Entergy Fleet - Acceptance Review of Quality Assurance Program Manual Reduction in Commitment ML23039A0872023-02-0808 February 2023 NRR E-mail Capture - Arkansas Nuclear One, Unit 2 - Acceptance Review of Relief Request ANO2-RR-23-001, Half-Nozzle Repair of RVCH Penetration 46 (L-2023-LLR-0000) ML23026A1322023-01-26026 January 2023 NRR E-mail Capture - ANO Unit 1 - Acceptance of Requested Licensing Action LAR to Adopt TSTF-505 Revision 2 ML22354A0122022-12-19019 December 2022 NRR E-mail Capture - ANO-1 and ANO-2 - Acceptance Review of Request for Alternative ANO-CISI-002 Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (L-2022-LLR-0080) ML22349A0112022-12-14014 December 2022 NRR E-mail Capture - Final RAI Relief Request ANO1-ISI-035 ML22341A1202022-12-0707 December 2022 NRR E-mail Capture - ANO Unit 1 - Acceptance of Requested Licensing Action LAR to to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation (L-2022-LLA-0161) ML22273A0982022-09-30030 September 2022 NRR E-mail Capture - ANO Units 1 and 2 - Acceptance of Requested Licensing Action Emergency Plan Staffing Requirements ML22265A2012022-09-22022 September 2022 NRR E-mail Capture - ANO-1 - Acceptance Review of Relief Request ANO1-ISI-036 ML22188A1782022-07-0707 July 2022 NRR E-mail Capture - ANO-1 - Acceptance Review of Relief Request ANO1-ISI-035 ML22174A1362022-06-23023 June 2022 NRR E-mail Capture - ANO-2 Final RAI Relief Requests ANO2-ISI-023 Through -028 (EPIDs L-2022-LLR-0022 Through -0027) ML22151A3262022-05-31031 May 2022 August 2022 Emergency Preparedness Exercise Inspection - Request for Information ML22124A2452022-05-0404 May 2022 NRR E-mail Capture - ANO-1 and ANO-2 - Final RAI 2 License Amendment Requests to Implement Provisions of 10 CFR 50.69 (L-2021-LLA-0105/-0106) ML22108A1642022-04-18018 April 2022 NRR E-mail Capture - ANO-1: Final RAI License Amendment Request Concerning TS Changes Due to Revised Dose Calculations (L-2021-LLA-0181) ML22081A3902022-03-22022 March 2022 NRR E-mail Capture - ANO-2 - Acceptance Review of Relief Requests ANO2-ISI-023, -024, -025, -026, -027, and -028 (Epids: L-2022-LLR-022, -023, -024, -025, -026, and -027) ML22034A5482022-02-0303 February 2022 NRR E-mail Capture - Final RAI License Amendment Requests to Implement Provisions of 10 CFR 50.69 (L-2021-LLA-0105/-0106) ML22020A0822022-01-19019 January 2022 NRR E-mail Capture - ANO-1 and 2 - Final RAI 2 License Amendment Requests to Allow the ECP to Remain Operable on a One-Time Basis for Up to 65 Days to Perform Piping Upgrade (L-2021-LLA-0015) ML22020A0742022-01-13013 January 2022 NRR E-mail Capture - ANO Unit 2 - Acceptance of Requested Licensing Action Alternative ANO2-PT-003 ML21314A1212021-11-0909 November 2021 Verbal Authorization of Relief Request ANO2-RR-21-002 ML21312A4792021-11-0505 November 2021 Email: NRC Staff Preliminary Questions Regarding X Energy LLC Xe-100 Topical Report: Risk-Informed Performance-Based Licensing Basis Development ML21312A0382021-11-0505 November 2021 NRR E-mail Capture - ANO-2 RAI Relief Request ANO2-RR-21-002 ML21308A5602021-11-0404 November 2021 NRR E-mail Capture - Arkansas Nuclear One, Units 1 and 2, Grand Gulf, River Bend, and Waterford, Unit 3 - Acceptance Review of LAR to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements ML21292A0112021-10-18018 October 2021 NRR E-mail Capture - ANO, 1 and 2, Grand Gulf, River Bend, Waterford, 3 - Acceptance Review of LAR to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML21287A1692021-10-13013 October 2021 Record of 10-13-21 Verbal Authorization of ANO2-R&R-012 (L-2021-LLR-0082) ML21298A1562021-10-11011 October 2021 NRR E-mail Capture - ANO-2 Final RAI Relief Request ANO2-R&R-012 Concerning Rv Closure Head Penetration 46 ML21273A0672021-09-29029 September 2021 NRR E-mail Capture - ANO-2 Final RAI 2 License Amendment Request to Adopt a Safety Function Determination Program ML21238A3742021-08-23023 August 2021 RFI Email - Cyber PI&R Inspection (ANO) ML21252A0052021-08-20020 August 2021 NRR E-mail Capture - ANO-1 and 2 Final RAI License Amendment Request to Allow the ECP to Remain Operable on a One-Time Basis for Up to 65 Days to Perform Piping Upgrade (L-2021-LLA-0015) ML21217A3302021-08-0505 August 2021 (ANO) Problem Identification and Resolution (PIR) Request for Information Combined ML21202A1662021-07-20020 July 2021 NRR E-mail Capture - ANO Unit 2 - Acceptance of Requested Licensing Action Alternative ANO2-PT-003 ML21201A0062021-07-19019 July 2021 NRR E-mail Capture - Arkansas Nuclear One, Units 1 and 2, and Waterford, Unit 3 - Acceptance Review of LAR to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML21197A0372021-07-16016 July 2021 NRR E-mail Capture - ANO-1 and 2 - Final RAI Final Response to GL 2004-02 ML21179A0042021-06-25025 June 2021 NRR E-mail Capture - ANO Unit 1 - Acceptance of Requested Licensing Action License Amendment Request to Adopt 10 CFR 50.69 ML21179A0052021-06-25025 June 2021 NRR E-mail Capture - ANO Unit 2 - Acceptance of Requested Licensing Action License Amendment Request to Adopt 10 CFR 50.69 ML21174A0342021-06-22022 June 2021 NRR E-mail Capture - Entergy Fleet (ANO, Ggulf, Rbend, & Waterford) - Acceptance Review for Relief Request to Use a Provision of a Later Edition of the ASME Code, Section XI for Periodic System Pressure Tests Exemptions ML21116A1092021-04-26026 April 2021 NRR E-mail Capture - ANO-1 and ANO-2: Final Supplemental RAI Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of ECP Supply Piping ML21105A0122021-04-0909 April 2021 NRR E-mail Capture - ANO-2 Final RAI License Amendment Request to Adopt a Safety Function Determination Program ML21074A2552021-03-15015 March 2021 NRR E-mail Capture - ANO-1 and ANO-2 - Acceptance of Requested Licensing Action LAR for One-Time Change to Support Upgrade of the ECP Supply Piping 2024-08-02
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24143A0632024-05-22022 May 2024 Notification of Inspection (NRC Inspection Report 05000368/2024003) and Request for Information ML24107A0282024-04-17017 April 2024 Notification of Comprehensive Engineering Team Inspection (05000313/2024011 and 05000368/2024011) and Request for Information ML24088A0082024-03-27027 March 2024 NRR E-mail Capture - ANO-2 -- TSTF-505 Post-Audit Final RAI (L-2023-LLA-0052) ML23130A2972023-05-17017 May 2023 Notification of Inspection (NRC Inspection Report 05000313/2023003) and Request for Information ML23104A1052023-03-10010 March 2023 NRR E-mail Capture - ANO-2 Final RAI Alternative Request for Life-of-Repair of RVCH Pen. 46 ML23019A0672023-01-19019 January 2023 Inservice Inspection Request for Information ML22349A0112022-12-14014 December 2022 NRR E-mail Capture - Final RAI Relief Request ANO1-ISI-035 ML22213A1662022-08-0101 August 2022 Information Request, Security IR 2022401 ML22208A0542022-07-26026 July 2022 Request for Information ML22174A1362022-06-23023 June 2022 NRR E-mail Capture - ANO-2 Final RAI Relief Requests ANO2-ISI-023 Through -028 (EPIDs L-2022-LLR-0022 Through -0027) ML22159A3242022-06-0909 June 2022 Notification of NRC Triennial Heat Exchanger/Sink Performance Inspection (05000313/2022003 and 05000368/2022003) and Request for Information ML22151A3262022-05-31031 May 2022 August 2022 Emergency Preparedness Exercise Inspection - Request for Information ML22124A2452022-05-0404 May 2022 NRR E-mail Capture - ANO-1 and ANO-2 - Final RAI 2 License Amendment Requests to Implement Provisions of 10 CFR 50.69 (L-2021-LLA-0105/-0106) ML22122A2952022-05-0404 May 2022 Notification of Inspection NRC Inspection Report 05000368/2022003 and Request for Information ML22108A1642022-04-18018 April 2022 NRR E-mail Capture - ANO-1: Final RAI License Amendment Request Concerning TS Changes Due to Revised Dose Calculations (L-2021-LLA-0181) ML22034A5482022-02-0303 February 2022 NRR E-mail Capture - Final RAI License Amendment Requests to Implement Provisions of 10 CFR 50.69 (L-2021-LLA-0105/-0106) ML22020A0822022-01-19019 January 2022 NRR E-mail Capture - ANO-1 and 2 - Final RAI 2 License Amendment Requests to Allow the ECP to Remain Operable on a One-Time Basis for Up to 65 Days to Perform Piping Upgrade (L-2021-LLA-0015) ML21312A0382021-11-0505 November 2021 NRR E-mail Capture - ANO-2 RAI Relief Request ANO2-RR-21-002 ML21286A7132021-10-15015 October 2021 ANO2022010 Tfp RFI Stg, Arkansas Nuclear One, Units 1 and 2 - Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000313/2022010 and 05000368/2022010) and Request for Information ML21273A0672021-09-29029 September 2021 NRR E-mail Capture - ANO-2 Final RAI 2 License Amendment Request to Adopt a Safety Function Determination Program ML21236A3222021-09-19019 September 2021 Request for Information ML21252A0052021-08-20020 August 2021 NRR E-mail Capture - ANO-1 and 2 Final RAI License Amendment Request to Allow the ECP to Remain Operable on a One-Time Basis for Up to 65 Days to Perform Piping Upgrade (L-2021-LLA-0015) ML21217A3302021-08-0505 August 2021 (ANO) Problem Identification and Resolution (PIR) Request for Information Combined ML21204A0842021-07-28028 July 2021 ANO Phase 4 2021013 RFI Gap ML21197A0372021-07-16016 July 2021 NRR E-mail Capture - ANO-1 and 2 - Final RAI Final Response to GL 2004-02 0CAN042105, Supplement to Response to Request for Additional Information Reduction of Commitment to the Entergy Operation'S Quality Assurance Program Manual Description2021-04-30030 April 2021 Supplement to Response to Request for Additional Information Reduction of Commitment to the Entergy Operation'S Quality Assurance Program Manual Description ML21116A1092021-04-26026 April 2021 NRR E-mail Capture - ANO-1 and ANO-2: Final Supplemental RAI Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of ECP Supply Piping ML21105A0122021-04-0909 April 2021 NRR E-mail Capture - ANO-2 Final RAI License Amendment Request to Adopt a Safety Function Determination Program ML21071A2172021-03-10010 March 2021 NRR E-mail Capture - ANO-1 and ANO-2 - Final RAI Proposed Change to Quality Assurance Program Manual ML21026A2682021-01-26026 January 2021 Request for Information ML21022A0842021-01-22022 January 2021 Request for Additional Information - Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency Cooling Pond Supply Piping - Arkansas Nuclear One,Units 1 and 2 -Entergy Operations, Inc. NON-PROPRIETARY Redacted ML21019A5142021-01-14014 January 2021 March 2021 Emergency Preparedness Exercise Inspection - Request for Information ML20324A6412020-11-19019 November 2020 NRR E-mail Capture - ANO-1 - Final RAI Relief Request ANO1-ISI-034 ML20316A0102020-11-0202 November 2020 NRR E-mail Capture - ANO-1 and ANO-2 - Final RAI Concerning Relief Request EN-20-RR-01 ML20262H0752020-09-17017 September 2020 NRR E-mail Capture - ANO-2 Final RAI 2 License Amendment Request Concerning Proposed Technical Specification Additions, Deletions, and Relocations ML20260H4762020-09-0909 September 2020 NRR E-mail Capture - ANO-1 Final RAI License Amendment Request to Revise Lov Relay Allowable Values ML20154K7622020-06-0101 June 2020 NRR E-mail Capture - ANO-2 Final RAI License Amendment Request Concerning Proposed Technical Specification Additions, Deletions, and Relocations ML20119A0982020-04-28028 April 2020 Notification of Inspection (NRC Inspection Report 05000368/2020003 and Request for Information ML20106E8522020-04-13013 April 2020 Information Request, NRC Inspection Report 05000313/2020410 and 05000368/2020410 ML20065H7992020-03-0606 March 2020 Supplemental Information Needed for Acceptance of Requested Licensing Action License Amendment Request to Revise Loss of Voltage Relay Allowable Values ML20055E9092020-02-24024 February 2020 NRR E-mail Capture - ANO-2 Final RAI License Amendment Request to Revise Control Element Assembly Drop Time ML20036D3092020-02-0505 February 2020 NRR E-mail Capture - ANO-2 - Final RAI Alternative Request VRR-ANO2-2019-1 ML20013C7472020-01-10010 January 2020 NRR E-mail Capture - ANO-1 and 2 -- Final RAI #2 LAR to Incorporate Tornado Missile Risk Evaluator (TMRE) Into Licensing Basis ML19316A0242019-11-0707 November 2019 NRR E-mail Capture - ANO-1 - - Final RAI Concerning Relief Request ANO1-ISI-033 (L-2019-LLR-0100) ML19280A0402019-10-0707 October 2019 NRR E-mail Capture - ANO-1 and 2 - Final RAI #1 License Amendment Request to Incorporate Tornado Missile Risk Evaluator (TMRE) Into Licensing Basis ML19339F5902019-09-23023 September 2019 Request for Information: Arkansas Nuclear One, IR 05000313/2019-004 Occupational Radiation Safety Inspection ML19281E0032019-08-0505 August 2019 ANO 2019 PIR Request for Information ML19203A0122019-07-16016 July 2019 Request for Information - Inservice Inspection Activities (NRC Inspection Report 05000313/2019004) ML19106A4322019-04-16016 April 2019 NRR E-mail Capture - ANO-2 Final RAI Re LAR to Add TS Actions to Address Inoperability of the Containment Building Sump ML19058A8332019-02-27027 February 2019 NRR E-mail Capture - ANO-1 - Final RAI Relief Request ANO1-ISI-032 2024-05-22
[Table view] |
Text
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From: Thomas Alexion To: DAVANT, GUY H Date: 3/29/04 2:14PM
Subject:
REVISED RAI FOR R&R-005&006 Guy, See the attached.
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Subject:
REVISED RAI FOR R&R-005&006 Creation Date: 3/29/04 2:14PM From: Thomas Alexion Created By: TWA@nrc.gov Recipients Action Date & Time entergy.com Transferred 03/29/04 02:14PM GDAVANT (DAVANT, GUY H)
Post Office Delivered Route entergy.com Files Size Date & Time R&R005&6.wpd 13691 03/29/04 01:35PM MESSAGE 655 03/29/04 02: 14PM Options Auto Delete: No Expiration Date: None Notify Recipients: Yes Priority: Standard Reply Requested: No Return Notification: None Concealed
Subject:
No Security: Standard To Be Delivered: Immediate Status Tracking: Delivered & Opened
REQUEST FOR ADDITIONAL INFORMATION (REVISED 03/29/04)
RELIEF REQUEST-005 & 006 ARKANSAS NUCLEAR ONE. UNIT 1 By letters dated June 6, 2003, and February 23, 2004, Entergy submitted proposed relief request ANO1 -R&R-005 and ANO1 -R&R-006 for use at ANO-1. The technical basis for Request No. ANO1 -R&R-006 is documented in ANO Calculations 86-E-0074-156, -160, -161, and -164 which were submitted on November 26, 2002, to support Request No. ANO1 -R&R-004. Non-proprietary versions of Calculations 86-E-0074-156 and -161 were submitted on December 16, 2002. (Calculations 86-E-0074-160 and -164 were submitted as entirely non-proprietary.)
AN01-R&R-006 By letter dated March 4, 2004, Entergy submitted its technical basis as documented in Engineering Report M-EP-2004-002 to support its decision not to perform water jet conditioning treatment on the repaired region of the CRDM nozzles.
- 1. Entergy indicated in the cover letter of the March 4, 2004, submittal that it has two concerns regarding ANO Calculation 86-E-0074-156. Entergy has committed to submit a revised fracture mechanics analysis by June 1, 2004. In light of pending revision, Entergy needs to clarify as to the status of ANO calculation 86-E-0074-156 with respect to the proposed Relief Request, R&R-005 and R& R-006.
Questions on CNRO-2004-00014, Enclosure 1. dated March 4. 2004
- 2. Page 4. Describe the flaw model in the revised fracture mechanics calculations:
- a. Describe the location of the initial and final flaw.
- b. Specify the length and depth of the initial flaw.
- c. Describe the path of crack propagation.
- d. Clarify whether the final crack be 100% through wall of the J-groove and butter weld.
- e. Clarify whether the flaw selected is a worse-case scenario flaw.
- 3. Page 4, fourth paragraph. It is stated that the outmost nozzle penetration will be used in the analysis because it would give the bounding values. Explain this statement in terms of stress distributions.
- 4. Page 5, first Paragraph. (A) Entergy stated that . ..Relaxing the residual stresses due to cracking will not be utilized since the analysis will use a liner elastic formulation..."
Clarify whether this approach will provide conservative results. (B) Entergy also stated that "...The stresses obtained from the residual stress analysis will be entered as crack face pressure. Reactor vessel internal pressure on the crack face will be added to the pressure distribution obtained from the residual stress analysis..." Clarify whether this approach will provide conservative results. (C) Describe, step by step, the fracture mechanics analysis.
1
- 5. Page 5, second paragraph. It is stated that the stress intensity factor will be maximized for use in fatigue evaluation. Describe the fatigue evaluation.
- 6. The staff understands that the fracture mechanics analysis will be based on the finite element analysis. Describe whether the results from the revised analysis would be consistent with the calculations performed using either Raju-Newman's solution or Anderson's solution. These two methods are also based on finite element analysis results.
- 7. Stresses along the crack length vary. It has been shown that stress intensity factors are higher when the stress in the crack center, instead of in the crack tip, is used in the flaw evaluation. Describe how the stresses along the crack length are modeled in the revised analysis.
- 8. Once the draft fracture mechanics analysis is completed, Entergy needs to submit for staff review the following: preliminary results of the analysis with sufficient explanation, supporting technical basis, and the draft fracture mechanics analysis on docket.
Questions on CNRO-2004-00014/Engineering Report M-EP-2004-002 in the March 4. 2004.
Submittal
- 9. Page 15. The staff needs clarification on the postulated flaw model. In Figure 1 of ANO Calculation 86-E-0074-161 in the November 26, 2002, submittal, Entergy assumed a certain flaw size due to lack of fusion to occur at the intersection of the repaired temper bead weld, nozzle, and vessel base metal. Explain why this flaw was not included in the M-EP-2004-002 Calculation in addition to the surface flaw as discussed above.
- 10. Page 23. Entergy stated that "... For the initial crack location the stress distribution at the fusion line, the crack tip on the ID surface and the mid-height of the crack are averaged to produce an average stress field that is applied to the crack..." Clarify why the maximum stress field was not applied to the crack.
- 11. Page 23. There is a considerable discussion of residual stresses in the flaw evaluation.
Discuss whether other applied stresses (e.g., thermal fatigue and pressure) were considered in the stress distribution.
- 12. Page 27. Specify the allowable length of an acceptable flaw as presented in Figure 15 on page 27.
- 13. It seems that Entergy's flaw evaluation did not address flaw growth due to fatigue.
Explain.
Questions on Appendix D. Evaluation of FTI Repair on a Weld Overlay Repaired Nozzle in the March 4. 2004. Submittal
- 14. It seems that Entergy has not provided sufficient technical basis to demonstrate the structural adequacy of installing a FTI weld repair on a weld overlay repaired nozzle.
Entergy compared only the hoop stresses of an as-built nozzle configuration to the hoop 2
stresses of a J-groove overlay weld configuration. Entergy should have compared the hoop stresses of a FTI weld repair on an overlay repaired nozzle to the hoop stresses of a FTI weld repair on an as-built nozzle. If the hoop stresses are comparable between two models, then Entergy can conclude that the FTI weld repair is acceptable to be installed on an overlay repaired nozzle, assuming other analytical parameters between the two models are comparable. Entergy needs to clarify its technical basis.
Questions on ANO Calculation 86-E-0074-161 in the November 26. 2002. Submittal
- 15. Page 23. It is stated that the postulated flaw in the temper bead weld repair was evaluated using residual stresses and fatigue stresses. Discuss whether other stresses such as thermal and pressure stresses were also applied in the flaw evaluation.
ANOI-R&R-005 Questions on CNRO-2004-00006/Februarv 23. 2004, Resubmittal of ANO1-R&R-005
- 16. Page 7. Entergy indicated in its letter dated February 23, 2004, that its repair method leaves a strip of low alloy steel exposed to the primary coolant and that the general corrosion of the low alloy base material is insignificant and is estimated to be 0.0032 inch/year. Entergy also indicates that repair of all 69 RPV head nozzles would present a 16.9% increase in annual release of Fe into the reactor coolant system. Based on the six repaired nozzles from the last outage, has the licensee seen an increase in the release of Fe into the reactor coolant system and if so, is the increase commensurate with the number of nozzles that were repaired based on calculations of general corrosion?
- 17. Page 7. Entergy discusses an ANSYS analysis performed by Framatome-ANP and calculated stresses that were then compared to ASME Code,Section III, NB-3000 criteria. Please provide analysis and calculations or provide a reference if material has been submitted previously.
ANO1-R&R-005 AND R&R-006
- 18. Entergy needs to provide for staff review inspection results of the six repaired CRDM nozzles as soon as the results are available.
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