Letter Sequence Meeting |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement
Results
Other: ML21161A299, ML21203A314, ML21211A082, ML21214A178, ML21260A161, ML22013A339, ML22019A279, ML22061A056, ML22109A175, ML22164A861, ML22167A170, ML23188A020, ML23193A938, ML23200A183, ML23243A910
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MONTHYEARML17310B2322017-11-0707 November 2017 Presentation Slides - NextEra Energy/Fpl - GSI-191 Issue Resolution, Pre-submittal Meeting, September 20, 2017 Project stage: Meeting ML17310B2062017-11-20020 November 2017 Summary of September 20, 2017, Meeting with Florida Power & Light Company and NextEra Energy Regarding Closure of NRC Generic Safety Issue 191/NRC Generic Letter 2004-02 Project stage: Meeting ML18136A9052018-05-31031 May 2018 Summary of April 25, 2017, Meeting with Florida Power & Light Company/Nextera Energy Regarding Planned Submittal of Exemption Requests to Support Closure of NRC Generic Safety Issue 191/NRC Generic Letter 2004-02 Project stage: Meeting L-20-162, Supplemental Response to NRC Generic Letter 2004-022020-11-30030 November 2020 Supplemental Response to NRC Generic Letter 2004-02 Project stage: Request 0CAN122001, Final Response to NRC Generic Letter 2004-022020-12-10010 December 2020 Final Response to NRC Generic Letter 2004-02 Project stage: Request ML21062A0642021-03-0202 March 2021 NRR E-mail Capture - Request for Additional Information for Diablo Canyon Generic Letter 2004-02 Submittal (L-2017-LRC-0000) Project stage: RAI NL-21-0020, Final Supplemental Response to NRC Generic Letter 2004-022021-03-23023 March 2021 Final Supplemental Response to NRC Generic Letter 2004-02 Project stage: Request DCL-21-034, Response to Request for Additional Information on Final Supplemental Response to Generic Letter 20042021-04-15015 April 2021 Response to Request for Additional Information on Final Supplemental Response to Generic Letter 2004 Project stage: Supplement ML21118A0072021-04-28028 April 2021 Final Response and Close-out to Generic Letter 2004-02 Project stage: Request PMNS20210610, Public Meeting Regarding Path Forward for Generic Letter 2004-02 Closure for Point Beach Nuclear Plant Units 1 and 22021-05-17017 May 2021 Public Meeting Regarding Path Forward for Generic Letter 2004-02 Closure for Point Beach Nuclear Plant Units 1 and 2 Project stage: Request ML21134A0232021-05-18018 May 2021 GL 2004-02 Resolution Update - NextEra Energy Point Beach, LLC (NextEra) Project stage: Request ML21147A1462021-05-27027 May 2021 Response to Request for Additional Information Regarding Generic Letter 2004-02 Project stage: Response to RAI ML21168A2612021-06-17017 June 2021 (Vcsns), Unit 1 - NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-water Reactors - Final Supplemental Response Project stage: Request ML21161A2992021-06-17017 June 2021 Summary of May 18, 2021 Public Webinar with Nextera Energy Point Beach, LLC Regarding Path Forward for Generic Letter 2004-02 Closure Project stage: Other ML21197A0372021-07-16016 July 2021 NRR E-mail Capture - ANO-1 and 2 - Final RAI Final Response to GL 2004-02 Project stage: RAI ML21203A3142021-07-29029 July 2021 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML21232A0402021-08-20020 August 2021 Notice of Teleconference with Entergy Operations, Inc. Concerning Final Response to Generic Letter 2004-02 at Arkansas Nuclear One, Units 1 and 2 Project stage: Meeting ML21252A3212021-08-20020 August 2021, 30 August 2021, 14 September 2021 ANO Meeting Summary for September 1, 2020 Public Meeting/Teleconference Project stage: Request ML21242A2792021-08-30030 August 2021 ANO Slides Presentation for 9-1-21 Public Meeting Project stage: Meeting ML21252A2662021-09-14014 September 2021 Summary of September 1, 2021, Teleconference Meeting with Entergy Operations, Inc. Concerning the Final Response to Generic Letter 2004-02 for Arkansas Nuclear One, Units 1 and 2 Project stage: Meeting ML21211A0822021-09-24024 September 2021 Closeout of Generic Letter 2004 02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML21260A1612021-09-24024 September 2021 Closeout of Generic Letter 2004 02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other RA-21-0230, Duke Energy - Final Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2021-09-30030 September 2021 Duke Energy - Final Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request 0CAN102101, Final Request for Additional Information Concerning Generic Letter 2004-022021-10-0404 October 2021 Final Request for Additional Information Concerning Generic Letter 2004-02 Project stage: Request ML21214A1782021-10-0808 October 2021 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Other PMNS20211455, Pre-Submittal Public Meeting Regarding License Amendment and Exemption Request for Generic Letter 2004-02 Closure for Point Beach Nuclear Plant Units 1 and 22021-12-0303 December 2021 Pre-Submittal Public Meeting Regarding License Amendment and Exemption Request for Generic Letter 2004-02 Closure for Point Beach Nuclear Plant Units 1 and 2 Project stage: Meeting ML21336A7972021-12-0909 December 2021 GL 2004-02 Resolution Update - NextEra Energy Point Beach, LLC - December 9, 2021 (Slides) Project stage: Request ML22019A2792022-01-20020 January 2022 Summary of Public Webinar with NextEra Energy Point Beach, LLC Regarding Future License Amendment and Exemption Request for Generic Letter 2004-02 Closure for Point Beach Nuclear Plant Project stage: Other ML22019A2652022-01-27027 January 2022 Us NRC Staff Review of Documentation Provided by Firstenergy Nuclear Operating Co. for Beaver Valley, Units 1&2 Concerning Resolution of Generic Letter 2004-02 - Potential Impact of Debris Blockage on Emergency Recirculation During Design B Project stage: Approval ML22013A3722022-01-27027 January 2022, 31 January 2022 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request ML22013A3392022-01-31031 January 2022 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML22053A2402022-02-22022 February 2022 Final Supplemental Response to NRC Generic Letter 2004-02 Project stage: Request ML22061A0562022-03-29029 March 2022 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML22112A1482022-04-22022 April 2022 Correction_H. B. Robinson Steam Electric Plant, Unit 2 - Request for Additional Information Regarding Supplemental Response to Generic Letter 2004-02 Project stage: RAI ML22109A1752022-04-27027 April 2022 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other RA-22-0144, Response to NRC Request for Additional Information Regarding Supplemental Response to Generic Letter 2004-022022-05-19019 May 2022 Response to NRC Request for Additional Information Regarding Supplemental Response to Generic Letter 2004-02 Project stage: Supplement ML22164A8612022-06-24024 June 2022 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML22167A1702022-07-14014 July 2022 Closeout of Generic Letter 2004 02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML22242A0452022-08-23023 August 2022 NRR E-mail Capture - Dominion GL 04-02 Response Draft RAIs (L-2017-LRC-0000) Project stage: Draft RAI ML22251A1292022-09-0909 September 2022 Request for Additional Information Related to Response to Generic Letter 2004-04 Project stage: RAI ML22312A4432022-11-0707 November 2022 NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Fleet Response to RAI Project stage: Request ML22335A4142022-12-21021 December 2022 Request for Withholding Information from Public Disclosure for Dominion Fleet Response to Request for Additional Information Regarding NRC Generic Letter 2004-02 Project stage: RAI ML23193A9382023-07-18018 July 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML23188A0202023-07-26026 July 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML23200A1832023-08-0303 August 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML23243A9102023-09-0606 September 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML24012A0492024-01-11011 January 2024 Request for Additional Information Regarding Final Response to Generic Letter 2004-02 Project stage: RAI 2021-09-14
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Category:Meeting Briefing Package/Handouts
MONTHYEARML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology Slides and Affidavit for Pre-Submittal Meeting ML23296A1002023-10-24024 October 2023 Entergy Presentation Slides for Pre-Submittal Meeting on 10/24/23, Mtc LAR ML22193A0262022-07-12012 July 2022 (ANO) RICT License Amendment Request TSTF-505 NRC Pre-Submittal Meeting Presentation - July 13, 2022 ML21351A0282021-12-16016 December 2021 Preliminary Information of ANO-1 1R17 (2002) Findings on CRDM Nozzle 56, and Presentation Slides for PT Exam of Nozzle 56 ML21348A1262021-12-14014 December 2021 RCP TS LAR Pre-Submittal Meeting Slides, December 16, 2021 ML21309A0622021-11-0909 November 2021 NRC Slides for November 9, 2021, Technology Inclusive Content of Application Project Public Meeting ML21312A0342021-11-0909 November 2021 Combined Slides for November 9, 2021, Technology Inclusive Content of Application Project Public Meeting ML21242A2792021-08-30030 August 2021 ANO Slides Presentation for 9-1-21 Public Meeting ML21200A1792021-07-31031 July 2021 Scale/Melcor Non-LWR Source Term Demonstration Project - High Temperature Gas-Cooled Reactor ML20344A0572020-12-10010 December 2020 Combined Industry and NRC Slides for the December 10, 2020, Public Meeting on Technology Inclusive Content of Application Project, Advanced Reactor Content of Application Project and Applicability of Regulations to Non-Light Water Reactors ML20315A1582020-11-17017 November 2020 Presentation Meeting Slides for the 11/17/20 Teleconference ML20269A3452020-09-28028 September 2020 Pre-submittal Meeting for Request for One-Time Exemption from 10 CFR Part 50, Appendix E, Biennial EP Exercise (Offsite) Due to COVID-19- Entergy Presentation Slides ML20255A0242020-09-11011 September 2020 (Ano), Pre-Submittal Meeting with NRC - Request to Extend Allowable Outage Time (AOT) for the Emergency Cooling Pond (ECP) ML20211L7052020-08-0404 August 2020 (ANO) Units 1 & 2, Pre-Submittal Slide Presentation for August 4, 2020 Public Meeting ML20114E2752020-04-29029 April 2020 (ANO) Carbon Fiber Reinforced Polymer (Cfrp) Relief Request Pre-Submittal Meeting with NRC - April 29, 2020 ML19136A2512019-06-13013 June 2019 Handout for the June 13, 2019 Pre-submittal Public Meeting for Planned License Amendment Request Regarding Fuel Handling Accident Analysis ML18176A1312018-06-21021 June 2018 Summary of Annual Assessment Meeting with Entergy Operations, Inc., Regarding 2017 Performance of Arkansas Nuclear One ML18107A3342018-04-10010 April 2018 Tech Spec 3.3.5.2a Change Pre-Submittal Meeting Presentation Slides ML18081A1922018-03-20020 March 2018 Presentation at the PRA Workshop ML17328A3652017-11-30030 November 2017 Workshop on Sharing Operating Experience from Rigging, Lifting and Load Handling Events - Temporary Overhead Crane Failure at Arkansas Nuclear One Presented to IAEA ML16109A3642016-04-18018 April 2016 Summary of Meeting to Discuss Supplemental Inspection Results and Annual Assessment Meeting with Entergy Operations Inc. Regarding 2015 Performance of Arkansas Nuclear One ML16015A0622016-01-20020 January 2016 Briefing Notes for 95003 Inspection at Arkansas Nuclear One ML15132A1752015-05-21021 May 2015 Summary of Annual Assessment Meeting with Entergy Operations Inc., Regarding ANO 2014 Performance ML14356A1852014-12-22022 December 2014 ANO2 Exit ML14329B2092014-11-25025 November 2014 Summary of Regulatory Conference to Discuss Safety Significance of Arkansas Nuclear One Flood Protection Deficiencies ML14259A5972014-09-16016 September 2014 Summary of Annual Performance Assessment Meeting for Arkansas Nuclear One Performance ML14169A0722014-06-19019 June 2014 Entergy Public Meeting Presentation Slides ML12332A1792012-11-26026 November 2012 Power Point Presentation by Entergy at the November 26, 2012 Meeting (TAC No. ME9706.) ML12306A2912012-11-0101 November 2012 Transmittal Email and WCAP-17128-NP, Revision 1, Flaw Evaluation of CE Design RCP Suction and Discharge Nozzle Dissimilar Metal Welds, Phase III Study, May 2010 ML12278A2552012-10-0909 October 2012 Licensee Slide Presentation, ANO-2 NFPA 805 Application, at the October 9, 2012, pre-submittal Meeting to Discuss the NFPA 805 Application ML12278A2532012-10-0909 October 2012 Licensee Handout, Design Input for Fire Risk Evaluation, at the 10/9/2012 Pre-submittal Meeting to Discuss the NFPA 805 Application ML12275A5492012-10-0101 October 2012 Summary of Meeting with Entergy Operations, Inc., to Discuss the Performance of the Subject Facilities, Recent Organizational Changes, and Current Regulatory Issues ML1218003412012-06-28028 June 2012 Handouts at the June 29, 2012 NFPA 805 Meeting at the Hq - Item #4 ML1218003192012-06-28028 June 2012 Handouts at the June 29, 2012 NFPA 805 Meeting at the Hq - Item #3 ML1218003122012-06-28028 June 2012 Handouts at the June 29, 2012 NFPA 805 Meeting at the Hq - Item #2, Table W-2 ANO-2 Fire Area Risk Summary ML1218003102012-06-28028 June 2012 Handouts at the June 29, 2012 NFPA 805 Meeting at the Hq - Item #1, Plant Modifications and Items to Be Completed ML1218003062012-06-28028 June 2012 Handouts at the June 29, 2012 NFPA 805 Meeting at the Hq - Power Point Slides ML12166A5602012-06-12012 June 2012 Licensee Presentation on June 12 & 13, 2012, Meeting License Amendment Request on NFPA 805 Adoption ML1202501112012-01-25025 January 2012 Licensee Slides Arkansas Nuclear One, Unit 1 - Steam Generators Tube to Tube Wear ML1126502692011-09-22022 September 2011 Licensee Handouts for 10/05/2011 Presubmittal Meeting ML1117906392011-06-28028 June 2011 Summary of Meeting with Entergy Operations Inc ML1110401532011-04-13013 April 2011 Licensee Slides from 4/13/11 Meeting with Entergy Operations, Inc., to Discuss Proposed National Fire Protection Programs Standards 805 License Amendment Submittal for Arkansas Nuclear One, Units 1 & 2 ML1107504262011-03-15015 March 2011 Licensee Slides from 3/15/11 Pre-Sumittal Meeting SWS Room Cooling Required Action ML1107504162011-03-15015 March 2011 Licensee Slides from 3/15/11 Meeting with Entergy Operations on Technical Specification Change - Testing of Idle RCS Cooling Loop ML1016705012010-06-17017 June 2010 Discussion of Screening Criteria - Arkansas Nuclear One (ANO) ML0935201272009-12-18018 December 2009 Nrc/Entergy Operations, Inc., Management Meeting ML0935005652009-12-15015 December 2009 NRC Handouts Current Status of Arkansas Nuclear One Unit Steam Generators, December 2009 ML0913104172009-05-11011 May 2009 Summary of Meeting with Entergy to Discuss Arkansas Nuclear One 2008 Performance ML0828000612008-10-0101 October 2008 Enclosure 3-Technical Papers 2 - Plant Application of Weld Onlay for Butt Weld Mitigation ML0828300322008-08-31031 August 2008 NRC Presentation Arkansas Nuclear One - Unit One 2023-12-14
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Text
ANO GL 200402 Final Response Requests for Additional Information 9/1/21 1
Agenda
Purpose
- The purpose of this meeting is to discuss the NRCs requests for additional information provided on July 16, 2021, for Entergys final submittal for resolution of GL 200402 which was submitted on December 10, 2020.
3
RAI 1
In Enclosure 1, on pg. 11 of 17 (PDF pg. 14), the second paragraph under test parameters appears to have one-train flow and two-train flow reversed. The velocities for one-train flow is listed as 0.008 feet per second (ft/s) (used for Test 1) and two-train as 0.004 ft/s (used for Test 2). Provide the one and two-train flow rates and state which flow rate was used for each test. State which test resulted in greater penetration.
Response
The description of the two velocities in the submittal is a typographical error. For ANO-1, the strainer approach velocity is 0.004 ft/s for one-train operation, and 0.008 ft/s for two-train. The strainer flow rate for one-train operation is 4,867 gpm, and the flow rate for two-train operation is 9,734 gpm.
The ANO fiber bypass Test 1 used the approach velocity of 0.004 ft/s, and Test 2 used the approach velocity of 0.008 ft/s. As correctly stated on Page 4 of Enclosure 1 in the submittal, Test 2 resulted in higher fiber penetration than Test 1.
4
RAI 2
Provide additional details on how the penetration models at plant scale were developed.
a) Describe how the penetration amounts determined from the testing were scaled to the plant condition for each unit.
Response
The model derived from Test 2 describes the fiber prompt and shedding penetration fractions as functions of cumulative fiber load on the test strainer. It is an important distinction to note that the plant strainer in-vessel analyses used the penetration fractions (not penetration debris quantities) calculated from the model. As stated in the submittal, the in-vessel analysis for reactor core inlet fiber load divided the recirculation phase into time steps. The fiber penetration model was used to determine the fiber prompt penetration and shedding fractions for each time step.
In the plant evaluation, the cumulative quantity of fiber on the plant strainer at the beginning of a time step was determined. This quantity was then scaled down to the test strainer surface area (i.e.,
multiplied by the ratio in surface area between the test strainer and plant strainer). The scaled fiber load was substituted into the model derived from Test 2 to calculate the fiber prompt penetration and shedding fractions for the given time step. These fractions were then applied to the plant strainer analysis to determine the fiber prompt penetration and shedding amounts for each time step, as stated in the last bullet on Page 14 and the first bullet on Page 15 of Enclosure 1 in the submittal.
5
RAI 2
Provide additional details on how the penetration models at plant scale were developed.
b) It appears that the model depicted in Figure 3.n.1-9 (PDF pg. 16) was used for both units. Provide justification that the same model is applicable to both units even though the strainer sizes and fiber amounts are significantly different between the units.
Response
The penetration model derived from Test 2 was applied for both units.
Figure 3.n.1-9 shows the results of an example application of the fiber penetration model: cumulative fiber penetration through the ANO-1 sump strainer as a function of time. The results shown in this figure are for demonstration purposes and were not directly used for the actual in-vessel analysis of either unit.
As stated in the submittal, Test 2 used a test strainer that is prototypical to the plant strainers of both units. Additionally, other testing conditions (e.g., fiber loads, approach velocity, water chemistry) were either representative of or bounded the plant strainer operating conditions of both units. The test was designed to characterize how fiber penetration varies as the quantity of fiber accumulated on the strainer increases. This was achieved by introducing debris into the test tank in five batches, allowing a gradual accumulation of fiber on the test strainer, and changing filter bags multiple times for each debris batch to collect long-term shedding penetration. The model derived from the test data describes the fiber prompt and shedding penetration fractions as functions of cumulative fiber load on the test strainer.
6
Response (contd):
As stated in the response to Part a of this RAI, in the plant strainer in-vessel analysis, the accumulated fiber load on the plant strainer was scaled down to the test strainer surface area first before being used to calculate the fiber penetration fractions from the model. These fractions were then applied to determine the fiber penetration quantities during a time step for the plant strainer. This methodology is different from the application of simply scaling up the measured total fiber penetration quantity to the plant strainer surface area to quantify the plant strainer penetration.
7
RAI 2
Provide additional details on how the penetration models at plant scale were developed.
c) Describe the relevance of the time scale on the x-axis of Figure 3.n.1-9. The NRC staff concluded that the axis implies time at a plant scale. Describe the assumptions used to develop the time scale or justify that it is not important to the calculations.
Response
The time on the x-axis of Figure 3.n.1-9 is at plant scale. As discussed above, this figure shows results of an example application, which uses similar methodology as the actual in-vessel analysis.
The prompt and shedding penetration fractions calculated from the model were used to determine the fiber penetration quantities of the plant strainer during each time step. The figure shows cumulative fiber penetration quantity over time.
Both the example application and actual in-vessel analyses assumed that the fibrous debris is uniformly distributed in the containment sump pool, consistent with the WCAP-17788 methodology.
The in-vessel analysis was terminated when the pool fiber concentration is 0.1% of the initial fiber concentration, which is more conservative than the 1% concentration termination criteria in WCAP-17788. As shown in Figure 3.n.1-9, the cumulative fiber penetration quantity plateaus well before the termination criterion is reached.
8
RAI 2
Provide additional details on how the penetration models at plant scale were developed.
d) Describe the application of Figures 3.n.1-10 and 11 to each unit (PDF pgs. 16 and 17). Explain how the difference in strainer area between units is accounted for in the analysis, considering that the ANO-2 strainer has approximately 1.8 times the area of the ANO-1 strainer.
Response
It should be clarified that the prompt penetration and shedding fractions shown in Figures 3.n.1-10 and 3.n.1-11 are not inputs to the ANO in-vessel analysis of either unit. Instead, they resulted from the example application of the model to the ANO-1 strainer as shown in Figure 3.n.1-9.
As discussed in the response to Part a of this RAI, for a given time step, the amount of fiber accumulated on the plant strainer is first scaled down to the test scale (i.e., multiplied by the ratio in surface area between the test strainer and plant strainer) before being substituted into the model to calculate the fiber penetration fractions. For example, if the same amount of fiber accumulates on the plant strainers of both units, the fiber loads scaled to the test scale will be greater for ANO-1 than ANO-2 due to much larger surface area of the ANO-2 plant strainer. As a result, when using these scaled fiber loads in the model, the calculated fiber penetration fractions for ANO-1 would be lower than those of ANO-2. In other words, the resulting fiber penetration fraction curves for ANO-2 would be different from those shown in Figures 3.n.1-10 and 3.n.1-11 for ANO-1. In summary, the penetration model derived from testing only provided fiber penetration fractions for the in-vessel analyses. Although the same model was applied to both units, the difference in plant strainer surface areas between the two units was accounted for when the model was applied.
9
RAI 3
In Enclosure 1, on pg. 15 (PDF pg. 18), the ANO-1 in-vessel fiber calculation credits one Reactor Building Spray System (RBSS) pump at minimum flow. Provide the basis for the assumption that one RBSS pump will start and continue to operate (not be shut off) during the period of interest for fiber accumulation at the core inlet. That is, confirm that the RBSS pumps start for large break scenarios and continue to run.
Response
For ANO-1, the RBSS operation is initiated by a reactor building high-high pressure signal. This occurs when the reactor building pressure exceeds 44.7 psia. This pressure is exceeded early in the event for a design basis accident, ensuring RBSS is actuated. Once actuated, the sprays remain active for the duration of the event. After spray initiation the operator is directed to throttle the RBSS flow prior to the beginning of recirculation and maintain spray flow throughout the event. With the exception of indication of sump blockage, the RBSS remains active during the recirculation phase.
As stated in the submittal, the ANO-1 in-vessel analysis conservatively used the minimum throttled RBSS flow. While the RBS operates for the entire 30-day event, the ANO-1 in-vessel analysis reached the termination criteria (as discussed in the response to RAI 2.c) approximately eight hours after initiation of the accident. Therefore, the RBSS is active during the entire period of interest for fiber accumulation at the core inlet.
10
RAI 4
In Enclosure 2, on pg. 6 (PDF pg. 27), the ANO-2 in-vessel fiber calculation credits one Containment Spray System (CSS) pump at minimum flow. Provide the basis for the assumption that one CSS pump will start and continue to operate (not be shut off) during the period of interest for fiber accumulation at the core inlet. That is, confirm that the CSS pumps start for large break scenarios and continue to run.
Response
In the ANO-2 analysis, the time when containment spray is terminated was assumed to be ten hours after the LOCA. Containment spray actuation signal is automatically initiated when the containment pressure exceeds the containment pressure high-high (CPHH) setpoint of 25.7 psia. Containment spray is terminated once the containment pressure and temperature drop below 22.5 psia and 140°F, respectively.
Since a minimum spray operating time is conservative for the in-vessel analysis, the containment pressure and temperature curves from analysis of a small-break LOCA (SBLOCA) were used to derive the spray duration. The peak containment pressure for the SBLOCA is approximately 32 psia which exceeds the containment spray actuation setpoint. The earliest time the SBLOCA containment temperature drops to 140°F is approximately 300,000 seconds, or 83 hours9.606481e-4 days <br />0.0231 hours <br />1.372354e-4 weeks <br />3.15815e-5 months <br />. The earliest time the SBLOCA containment pressure drops below 22.5 psia is at 70,000 seconds, or 19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br />. For conservatism, this value was rounded down to ten hours for the spray duration in the in-vessel analysis for ANO-2.
11
RAI 5
The NRC staff recognizes that substantial chemical effects information was provided in the licensees letter dated December 10, 2020, Final Response to NRC Generic Letter 2004-02. Please also provide the WCAP-17788, Comprehensive Analysis and Test Program for GSI-191 Closure, Test Group Number(s) that are considered representative of plant conditions for ANO-1 and ANO-2.
Response
As discussed in Enclosure 1 of the submittal, Entergy has elected to use the Box 2 path from the NRC review guidance to address in-vessel downstream effects for ANO-1, which is outfitted with a Babcock
& Wilcox (B&W) nuclear steam supply system. The minimum chemical precipitation time is not required for the Box 2 path. Therefore, comparison of the WCAP-17788 autoclave test groups with the ANO-1 plant conditions are not necessary.
For ANO-2, Entergy elected to use the Box 4 path from the NRC review guidance, and chemical precipitation was shown not to occur within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for containment sump temperatures above 135°F following the accident by using a precipitation map based on an array of representative autoclave tests from WCAP-17788, Volume 5. Additionally, WCAP-17788 autoclave Test Group 18, including Test 18-01 and Test IBOB 18-02, is considered representative of the ANO-2 post-LOCA plant conditions for the in-vessel analysis. No chemical precipitation was observed during the Test Group 18 autoclave tests down to a filtration test temperature of 160°F for the 24-hour test duration.
12
Response (contd):
The below table provides the critical projected ANO-2 post-LOCA conditions and debris loads at plant scale and test scale for comparison with the Test Group 18 parameters.
ANO-2 ANO-2 Parameter (Plant Scale) (Test Scale, 50 L)
Buffer Sodium Tetraborate Sodium Tetraborate Sump pH (Long-term) 7.2 - 8.0 7.2 - 8.0 1,765,085 L Minimum Sump Volume 50 L (384,000 gal + 82,286 gal)
Maximum Sump Pool Temperature 241.3°F 241.3°F Maximum Calcium Silicate 1,447,000 g 40.99 g Maximum E-Glass 900 g 0.0255 g Maximum Silica 0g 0g Maximum Mineral Wool 0g 0g Maximum Aluminum Silicate 25,400 g 0.720 g Maximum Concrete 49.3 g (4900 ft2) 0.00140 g (0.14 ft2)
Maximum Interam' 0g 0g Aluminum 301.0 ft2 0.00853 ft2 Galvanized Steel Not Determined Not Determined 13
Summary
- Anticipated submittal date is midSeptember, 2021.
14