Letter Sequence RAI |
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Initiation
- Request, 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, ML23290A009, ML24067A103, ML24101A194
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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 ML21252A3212021-08-20020 August 2021, 30 August 2021, 14 September 2021 ANO Meeting Summary for September 1, 2020 Public Meeting/Teleconference Project stage: Request 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 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 L-04-002, Stations - NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Fleet Response to Request for Additional Information2023-05-0808 May 2023 Stations - NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Fleet Response to Request for Additional Information Project stage: Response to RAI L-2023-075, Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-022023-06-0909 June 2023 Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-02 Project stage: Response to 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 ML23290A0092023-10-17017 October 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 2021-09-24
[Table View] |
Text
From:
Lee, Samson Sent:
Tuesday, March 2, 2021 4:47 PM To:
Richardson, Michael
Subject:
Request for additional information for Diablo Canyon Generic Letter 2004-02 Submittal (L-2017-LRC-0000)
By letter dated April 30, 2020 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML20121A095), Pacific Gas and Electric Company (PG&E or the licensee) submitted a final response to close Generic Letter (GL) 2004-02, dated September 13, 2004 (ADAMS Accession No. ML042360586), Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, for the Diablo Canyon Power Plant, Units 1 and 2 (Diablo Canyon). 10 CFR 50.46 requires that plants are able to maintain adequate long-term core cooling (LTCC) to ensure that the fuel in the core can be cooled and maintained in a safe and stable configuration following a postulated accident. GL 2004-02 requested that licensees provide information confirming that their plants are in compliance with the regulation. During its review of the licensees submittal, the NRC staff identified that it required additional information to confirm the licensees evaluation.
The staff sent the draft request for additional information (RAI) to the PG&E staff, who determined that no clarification call was necessary. The PG&E staff requested, and NRC agreed, to a RAI response by April 15, 2021. The NRC staff considers that timely responses to RAIs contribute toward the NRCs goal of efficient and effective use of staff resources. If circumstances result in the need to revise the agreed upon response date, please contact me at (301) 415-3168 or via e-mail Samson.Lee@nrc.gov.
Please provide the following information:
- 1) Table 3.b.1-1 of the April 30, 2020 submittal states that WCAP-17561 was used to determine the zone of influence (ZOI) for Temp-Mat. The ZOI credited is 3.7D. The NRC staff reviewed WCAP-17561 and found that the methods and results in the WCAP were generally acceptable.
However, the NRC staff determined that some of the test geometries for the Temp-Mat tests may not have been representative or conservative with respect to those installed in plants. The text in Section 3.b.1 states that the amount of debris included in the testing exceeded the debris quantity that would result if a ZOI of 11.7D (NRC generically approved ZOI for Temp-Mat) were applied. As used in the current debris generation and head loss analysis, this is a conservative assumption and is acceptable. This issue regarding the test geometry for the WCAP-17561 testing is not relevant to Diablo Canyons current submittal but could be relevant to future modifications or operability determinations. If future actions assume the reduced ZOI based on WCAP-17561, and the use of this ZOI is not appropriate for the plant specific geometry, the amount of fibrous debris generated could exceed that included in the plant specific testing.
Please justify that the WCAP-17561 ZOI is representative of the plant geometry or explain how the potential discrepancy will be managed.
- 2) Provide an overview of the analysis method for the Temp-Mat ZOI length for the hot and cold-leg nozzle breaks. Also, describe how the break geometries and sizes were determined and how these geometries relate to the assigned ZOI volumes.
- 3) Please provide additional details regarding the submergence of the strainer for the Small Break Loss-of-Coolant Accident (SBLOCA) scenario. Section 3.f.11 of the submittal states that the submerged height of the strainer is 1.01 ft. for the front and 1.79 ft. for the rear sections. It also
states that the headloss is 0.758 ft. This is less than half of the rear section submergence, but greater than half of the front section submergence. Considering Regulatory Guide 1.82 guidance, please explain why this condition is acceptable? Also, please provide details of the timing of additional submergence for this case. For example, how long does it take the height of the pool to increase such that the strainer is fully submerged? If this occurs relatively quickly, it may be demonstrated that headloss will not increase quickly enough to cause partially submerged strainer failure.
- 4) Related to question 3 above, Section 3.g.5 of the submittal states that the Containment Spray (CS) pumps may not be actuated. Table 3.g.12-1 implies that the volume injected from the Refueling Water Storage Tank (RWST) for the SBLOCA assumes CS flow. Please describe how the status of CS affects strainer submergence for the SBLOCA case. The submittal demonstrates that there is adequate margin to account for the sump level reduction that may occur due to reduced injection from the RWST. Please confirm that future changes to net positive suction head (NPSH) calculations will account for the actual minimum sump level that may occur. The potential for a reduction in sump level of 1.3 ft. may be evaluated against increased NPSH available from other sources. For example, if CS does not actuate, there is additional inventory available because CS piping is not filled. In addition, debris headloss is very low at start of recirculation. Other aspects of the scenario may be considered.
- 5) In Section 3.f.14 of the submittal, it was determined that the maximum amount of entrained gases that can reach the pump suction is 0.17 percent. Was the NPSH required value used in the NPSH margin calculation adjusted per the guidance in Regulatory Guide 1.82, Appendix A-3, to account for the entrained gases? If not, please describe how the effect of entrained gases on pump performance was evaluated.
- 6) For the in-vessel evaluation, please provide the WCAP-17788 chemical effects test group number that was applied to the Diablo Canyon in-vessel analysis and confirm it is representative of projected post-LOCA plant conditions.
Docket Nos. 50-275 and 50-323
Hearing Identifier:
NRR_DRMA Email Number:
1049 Mail Envelope Properties (DM8PR09MB61835219CF1EDF151A6784649A999)
Subject:
Request for additional information for Diablo Canyon Generic Letter 2004-02 Submittal (L-2017-LRC-0000)
Sent Date:
3/2/2021 4:47:26 PM Received Date:
3/2/2021 4:47:26 PM From:
Lee, Samson Created By:
Samson.Lee@nrc.gov Recipients:
"Richardson, Michael" <MJRm@pge.com>
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