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MONTHYEARML23269A0232023-09-22022 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 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 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 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 ML21071A2172021-03-10010 March 2021 NRR E-mail Capture - ANO-1 and ANO-2 - Final RAI Proposed Change to Quality Assurance Program Manual ML21022A1692021-01-22022 January 2021 NRR E-mail Capture - Entergy Fleet (ANO, Grand Gulf, River Bend, and Waterford) - Acceptance Review for RR EN-20-RR-003, Proposed Alternative to Use ASME Code Case N-711-2 ML21019A5142021-01-14014 January 2021 March 2021 Emergency Preparedness Exercise Inspection - Request for Information ML20356A1142020-12-17017 December 2020 NRR E-mail Capture - ANO Unit 2 - Acceptance of Requested Licensing Action LAR Concerning LCO 3.0.6 and Proposed Adoption of SFDP ML20350B7602020-12-14014 December 2020 NRR E-mail Capture - Arkansas Nuclear One, Unit 2 - Acceptance Review of Request to Use Alternative Examination Requirements - ANO2-ISI-022 2023-09-22
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Text
Thomas Alexion - Draft Response to RAI on ANO-1 1R1i8 SG Report _ _Page 1 From: 'BENNETT, STEVE A" <SBENNE2@entergy.com>
To: "Tom Alexion"' <twa~nrc.gov>
Date: 6/27/05 4:19PM
Subject:
Draft Response to RAI on ANO-1 1R1 8 SG Report Tom, This is the response to the two follow-up questions regarding the ANO-1 SG LBLOCA best estimate leakage values.
Steve Bennett NSA- Licensing 479-858-4626 Pager: 479-890-3323
- c:\temp)\GW)00001 .TMP Page PaQe 1 11 c:\temp\GWIOOOO1 .TMP Mail Envelope Properties (42CO5F40.50B: 0: 29963)
Subject:
Draft Response to RAI on ANO-1 IR18 SG Report Creation Date: 6/27/05 4:18PM From: "BENNETT, STEVE A" <SBENNE2@entergy.com>
Created By: SBENNE2@entergy.com Recipients nrc.gov owf4_po.0WFNDO TWA (Thomas Alexion)
Post Office Route owf4_po.0WFN_DO nrc .gov Files Size Date & Time MESSAGE 18S 06/27/05 04:1 8PPM TEXT.htm 989 IRIS OTSG ISI RAI Response (Rnd 2).doc 36864 Mime.822 53553 Options Expiration Date: None Priority: Standard Reply Requested: No Return Notification: None Concealed
Subject:
No Security: Standard
FOLLOW-UP REQUEST FOR ADDITIONAL INFORMATION SPRING 2004 ONCE-THROUGH STEAM GENERATOR TUBE INSERVICE INSPECTION REPORT ARKANSAS NUCLEAR ONE, UNIT 1 (ANO-1)
DOCKET NO. 50-313 The August 3, 2004, report (ADAMS Accession No. ML042240207) provided the results for the calculated total best-estimate large-break loss-of-coolant accident (LBLOCA) leakage during the ANO-1 eighteenth refueling outage (1R1 8). The calculated total best-estimate LBLOCA leakage for Cycle 18 was estimated to be 2.57 gallons-per-minute (gpm) for the initial two minutes and 1.49 gpm for the remaining 30 days. In Question 5 of the NRC staff's request for additional information (see e-mail at ADAMS Accession No. ML051450289), the licensee was asked to provide a summary of the flaws used in the evaluation and to discuss their individual contributions to the leak rate. In their draft response (see e-mail at ADAMS Accession No. ML051450296), the licensee discovered that there were flaws that had been classified as being in the pressure boundary during the original calculation, but were in fact outside the pressure boundary. When the licensee re-calculated the total best estimate LBLOCA leakage for Cycle 18, the estimate was revised downward. The revised best estimate LBLOCA leakage was estimated to be 1.29 gpm for the initial two minutes and 0.02 gpm for the remaining 30 days.
The staff notes that the licensee's LBLOCA leakage estimate during the previous refueling outage (1R17) considered the potential leakage of all circumferential cracks found during the inspection, including those above the re-roll repairs, because of the possibility that a leak path could exist around the roll or re-roll joints.
- 1. Discuss why the flaws in question were classified as being inside the pressure boundary for the original LBLOCA leakage estimate for Cycle 18, and discuss the basis for re-classifying the flaws as being outside of the pressure boundary. Include in your discussion the reasons why you concluded that the flaws in question should not be included in the LBLOCA leakage estimate and why the revised leakage estimate is conservative.
ANO Response:
The difference was due to a change in the way the analyst were labeling flaws in the steam generator database. The LBLOCA program takes input from the steam generator database (STMax) and develops the leakage from that. The program would see a flaw and conservatively call it inside the pressure boundary when in reality it would be outside (i.e. like a crack in a transition above the roll). The leakage should have been based on leakage past the roll instead of a crack in the pressure boundary resulting in higher leakage.
All flaws were included in the best estimate leakage determination. The methodology was consistent with the methodology used in the previous cycle (1Ri7). The revised 2-minute leakage value of 1.29 gpm is believed to be representative of the as-found flaws discovered during 1R18. However, even if the leakage value was not revised downward, the previously reported leakage value of 2.57 gpm is still well within the accident leakage of 9.0 gpm for the initial 2 minutes and 3.0 gpm for the remaining 30 days (
Reference:
Entergy'letter dated March 1, 2004, Response to NRC Request forAdditional Information
Regarding ANO-1 Steam Generator Tube Inservice Inspection Report from 1R17 (1CAN030402)). Either value still retains conservative margin to the accident analysis.
- 2. Discuss whether the LBLOCA leakage estimate methodology (i.e., not considering cracks above original rolls or re-roll repairs in the leakage estimate) has changed since the previous outage. If the LBLOCA leakage estimate methodology has changed, provide a technical basis. Include in your discussion the reasons why the leakage of flaws above the original rolls or re-roll repairs during a LBLOCA is no longer important in your assessment.
ANO Response:
As mentioned in question 1 above, the methodology is the same, therefore there is no difference. The flaws above the rolls are still included but are limited by the leakage past the roll.