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| | number = ML14216A072 | | | number = ML14216A072 |
| | issue date = 07/28/2014 | | | issue date = 07/28/2014 |
| | title = 3 and 4 Request for Additional Information - LAR 231 (TACs MF4392 and MF4393) | | | title = NRR E-mail Capture - Turkey Point 3 and 4 Request for Additional Information - LAR 231 (TACs MF4392 and MF4393) |
| | author name = Klett A | | | author name = Klett A |
| | author affiliation = NRC/NRR/DORL/LPLII-2 | | | author affiliation = NRC/NRR/DORL/LPLII-2 |
| | addressee name = Tomonto R J | | | addressee name = Tomonto R |
| | addressee affiliation = Florida Power & Light Co | | | addressee affiliation = Florida Power & Light Co |
| | docket = 05000250, 05000251 | | | docket = 05000250, 05000251 |
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| | document type = E-Mail | | | document type = E-Mail |
| | page count = 3 | | | page count = 3 |
| | | project = TAC:MF4392 |
| | | stage = RAI |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:1 NRR-PMDAPEm Resource From: Klett, Audrey Sent: Monday, July 28, 2014 3:53 PM To: Tomonto, Bob (Bob.Tomonto@fpl.com); Czaya, Paul (Paul.Czaya@fpl.com); 'Hanek, Olga' (Olga.Hanek@fpl.com) | | {{#Wiki_filter:NRR-PMDAPEm Resource From: Klett, Audrey Sent: Monday, July 28, 2014 3:53 PM To: Tomonto, Bob (Bob.Tomonto@fpl.com); Czaya, Paul (Paul.Czaya@fpl.com); 'Hanek, Olga' (Olga.Hanek@fpl.com) |
| Cc: Cross, William (WILLIAM.CROSS@fpl.com) | | Cc: Cross, William (WILLIAM.CROSS@fpl.com) |
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| ==Subject:== | | ==Subject:== |
| Turkey Point 3 and 4 Request for Additional Information - LAR 231 (TACs MF4392 and MF4393)By letter dated July 10, 2014, as supplemented by letters dated July 17, July 22, July 24, and July 26, 2014, Florida Power & Light Company (the licensee) submitted a license amendment request for the Turkey Point Nuclear Generating Unit Nos. 3 and 4 (Turkey Point). The licensee requested revisions to the Turkey Point Technical Specifications (TSs), Section 3/4.7.4, "Ultimate Heat Sink [UHS]." | | Turkey Point 3 and 4 Request for Additional Information - LAR 231 (TACs MF4392 and MF4393) |
| The U.S. Nuclear Regulatory Commission (NRC) staff re viewed the information provided by the licensee and determined that it needs additional information to complete the review. The NRC staff's request for additional information (RAI) is as follows. | | By letter dated July 10, 2014, as supplemented by letters dated July 17, July 22, July 24, and July 26, 2014, Florida Power & Light Company (the licensee) submitted a license amendment request for the Turkey Point Nuclear Generating Unit Nos. 3 and 4 (Turkey Point). The licensee requested revisions to the Turkey Point Technical Specifications (TSs), Section 3/4.7.4, Ultimate Heat Sink [UHS]. |
| SCVB RAI-4 Please describe the changes that will be included in the UFSAR related to the license amendment request (e.g., regarding maintaining the component cooling water heat exchangers so that they are ready and capable of functioning as intended during normal and accident conditions). | | The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the information provided by the licensee and determined that it needs additional information to complete the review. The NRC staffs request for additional information (RAI) is as follows. |
| | SCVB RAI-4 Please describe the changes that will be included in the UFSAR related to the license amendment request (e.g., regarding maintaining the component cooling water heat exchangers so that they are ready and capable of functioning as intended during normal and accident conditions). |
| | BOP RAI-7 The licensees response to BOP RAI-1 states that the input to HX3/HX4 is TICW in, TICW out, TCCW in, TCCW out, and intake cooling water (ICW) Flow Rate. |
| | The licensees response also states that The HX3/HX4 program equates the heat gain by the ICW system, the heat loss from CCW [component cooling water] and then determines the overall heat transfer coefficient, U, based on the surveillance heat transfer rate and logarithmic mean temperature difference. The HX3/HX4 program determines the TR [tube resistance] based on the surveillance overall heat transfer coefficient U, first principle equations and appropriate film coefficients. |
| | When doing the surveillances, Q is unknown. |
| | Equations: |
| | : 1. QICW= (MICW) (CP ICW) (TICW out - TICW in) |
| | : 2. QCCW = (MCCW) (CP CCW) (TCCW in -TCCW out) |
| | : 3. Q = U0 (A) LMTD |
| | : 4. Q= QICW = QCCW Where: |
| | QICW = Heat Gain to ICW from CCW CP ICW = ICW Specific Heat MICW = ICW Mass Flow Rate TICW out = ICW Outlet Temperature TICW in = ICW Inlet Temperature QCCW = Heat Loss from CCW to ICW MCCW = CCW Mass Flow Rate CP CCW = CCW Specific Heat TCCW in = CCW Inlet Temperature TCCW out = CCW Outlet Temperature 1 |
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| BOP RAI-7 The licensee's response to BOP RAI-1 states that the input to HX3/HX4 is TICW in, TICW out , TCCW in, TCCW out, and intake cooling water (ICW) Flow Rate.
| | U0 = Overall Heat Transfer Coefficient A = Total Tube Exterior Surface Area LMTD = log mean temperature differential Variables that are underlined are known. |
| | | Q is needed to get U0, which is needed to get TR (tube resistance), so that one can accurately enter Figure 3.5-1 of the licensees letter dated July 10, 2014, or the graphs of HX3/HX4. The unknowns are Q, CP ICW, MCCW, and U0. Considering equations 1, 2, and 3, there are 3 equations and 4 unknowns. |
| The licensee's response also states that "The HX3/HX4 program equates the heat gain by the ICW system, the heat loss from CCW [component cooling water] and then determines the overall heat transfer coefficient, 'U',
| | A. How does the licensee know the value of U0? |
| based on the surveillance heat transfer rate and logarithmic mean temperature difference. The HX3/HX4 program determines the TR [tube resistance] based on the surveillance overall heat transfer coefficient 'U', first principle equations and appropriate film coefficients."
| | B. When the licensee knows the value of U0, how does it find TR knowing that the tube side film coefficient is affected by the algae? |
| | |
| When doing the surveillances, Q is unknown.
| |
| | |
| Equations:
| |
| : 1. QICW= (MICW) (CP ICW) (TICW out - TICW in)
| |
| : 2. QCCW = (MCCW) (CP CCW) (TCCW in -TCCW out) 3. Q = U 0 (A) LMTD
| |
| : 4. Q= QICW = QCCW Where:
| |
| QICW = Heat Gain to ICW from CCW CP ICW = ICW Specific Heat MICW = ICW Mass Flow Rate TICW out = ICW Outlet Temperature TICW in = ICW Inlet Temperature QCCW = Heat Loss from CCW to ICW MCCW = CCW Mass Flow Rate CP CCW = CCW Specific Heat TCCW in = CCW Inlet Temperature TCCW out = CCW Outlet Temperature 2 U 0 = Overall Heat Transfer Coefficient A = Total Tube Exterior Surface Area LMTD = log mean temperature differential Variables that are underlined are known.
| |
| | |
| Q is needed to get U 0, which is needed to get TR (tube resistance), so that one can accurately enter Figure 3.5-1 of the licensee's letter dated July 10, 2014, or the graphs of HX3/HX4. The unknowns are Q, CP ICW, MCCW, and U0. Considering equations 1, 2, and 3, there are 3 equations and 4 unknowns. | |
| A. How does the licensee know the value of U 0? B. When the licensee knows the value of U 0, how does it find TR knowing that the tube side film coefficient is affected by the algae? | |
| C. How does the licensee know it has the correct TR when doing surveillances and thus is able to know that there is sufficient heat transfer capability for a design basis accident? | | C. How does the licensee know it has the correct TR when doing surveillances and thus is able to know that there is sufficient heat transfer capability for a design basis accident? |
| BOP RAI-8 In its response to BOP RAI-6 by letter dated July 26, 2014, the licensee stated, "The RHR [residual heat removal] Pump mechanical seals are cooled by CCW [component cooling water] through mechanical seal coolers with process fluid on the tube side and CCW water on the shell side. Per Drawing 5610-M-450-96, Sheet 1, CCW is to be available at 145ºF [degrees Fahrenheit] initially, decreasing to 125ºF in 16 hours." | | BOP RAI-8 In its response to BOP RAI-6 by letter dated July 26, 2014, the licensee stated, The RHR [residual heat removal] Pump mechanical seals are cooled by CCW [component cooling water] through mechanical seal coolers with process fluid on the tube side and CCW water on the shell side. Per Drawing 5610-M-450-96, Sheet 1, CCW is to be available at 145ºF [degrees Fahrenheit] initially, decreasing to 125ºF in 16 hours. |
| | | The licensee also stated, The CS [containment spray] Pump mechanical seal is cooled by CCW through a mechanical seal cooler. The maximum operating temperature for the Containment Spray Pump mechanical seal is 205ºF. Per the vendor data sheets for the mechanical seals on the Unit 4 CS pumps, 3 gpm [gallons per minute] of flow at 150ºF is needed for the CS pump seal coolers. |
| The licensee also stated, "The CS [containment spray] Pump mechanical seal is cooled by CCW through a mechanical seal cooler. The maximum operating temperature for the Containment Spray Pump mechanical seal is 205ºF. Per the vendor data sheets for the mechanical seals on the Unit 4 CS pumps, 3 gpm [gallons per minute] of flow at 150ºF is needed for the CS pump seal coolers." | | However, the peak CCW supply temperature to the RHR and CS pumps during a loss-of-coolant accident, double-ended pump suction (LOCA-DEPS) break approaches 160°F and stays above 150°F for several hours after the accident, according to the licensees letter dated July 24, 2014. The CCW supply temperature appears to be too high to meet the vendor-specified cooling requirements for these pumps. Discuss how the RHR and CS pumps will have adequate cooling to run continuously in order to perform their design basis function during a design basis accident. |
| | | Audrey Klett Project Manager NRR/DORL/LPLII-2 301-415-0489 2 |
| However, the peak CCW supply temperature to the RHR and CS pumps during a loss-of-coolant accident, double-ended pump suction (LOCA-DEPS) break approac hes 160°F and stays above 150°F for several hours after the accident, according to the licensee's letter dated July 24, 2014. The CCW supply temperature appears to be too high to meet the vendor-specified cooling requirements for these pumps. Discuss how the | |
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| RHR and CS pumps will have adequate cooling to run conti nuously in order to perform their design basis function during a design basis accident.
| | Hearing Identifier: NRR_PMDA Email Number: 1465 Mail Envelope Properties (Audrey.Klett@nrc.gov20140728155200) |
| | |
| Audrey Klett Project Manager NRR/DORL/LPLII-2
| |
| | |
| 301-415-0489
| |
| | |
| Hearing Identifier: NRR_PMDA Email Number: 1465 Mail Envelope Properties (Audrey.Klett@nrc.gov20140728155200) | |
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| ==Subject:== | | ==Subject:== |
| Turkey Point 3 and 4 Request for Additional Information - LAR 231 (TACs MF4392 and MF4393) Sent Date: 7/28/2014 3:52:53 PM Received Date: 7/28/2014 3:52:00 PM From: Klett, Audrey Created By: Audrey.Klett@nrc.gov Recipients: "Cross, William (WILLIAM.CROSS@fpl.com)" <WILLIAM.CROSS@fpl.com> Tracking Status: None "Tomonto, Bob (Bob.Tomonto@fpl.com)" <Bob.Tomonto@fpl.com> Tracking Status: None "Czaya, Paul (Paul.Czaya@fpl.com)" <Paul.Czaya@fpl.com> | | Turkey Point 3 and 4 Request for Additional Information - LAR 231 (TACs MF4392 and MF4393) |
| Tracking Status: None "'Hanek, Olga' (Olga.Hanek@fpl.com)" <Olga.Hanek@fpl.com> Tracking Status: None | | Sent Date: 7/28/2014 3:52:53 PM Received Date: 7/28/2014 3:52:00 PM From: Klett, Audrey Created By: Audrey.Klett@nrc.gov Recipients: |
| | | "Cross, William (WILLIAM.CROSS@fpl.com)" <WILLIAM.CROSS@fpl.com> |
| Post Office: Files Size Date & Time MESSAGE 4613 7/28/2014 3:52:00 PM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received:}} | | Tracking Status: None "Tomonto, Bob (Bob.Tomonto@fpl.com)" <Bob.Tomonto@fpl.com> |
| | Tracking Status: None "Czaya, Paul (Paul.Czaya@fpl.com)" <Paul.Czaya@fpl.com> |
| | Tracking Status: None |
| | "'Hanek, Olga' (Olga.Hanek@fpl.com)" <Olga.Hanek@fpl.com> |
| | Tracking Status: None Post Office: |
| | Files Size Date & Time MESSAGE 4613 7/28/2014 3:52:00 PM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: |
| | Recipients Received:}} |
Letter Sequence RAI |
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MONTHYEARL-2014-216, License Amendment Request No. 231, Application to Revise Technical Specifications to Revise Ultimate Heat Sink Temperature Limit2014-07-10010 July 2014 License Amendment Request No. 231, Application to Revise Technical Specifications to Revise Ultimate Heat Sink Temperature Limit Project stage: Request L-2014-226, License Amendment Request No. 231, Application to Revise Ultimate Heat Sink Temperature Limit - Request for Emergency Approval2014-07-17017 July 2014 License Amendment Request No. 231, Application to Revise Ultimate Heat Sink Temperature Limit - Request for Emergency Approval Project stage: Request ML14203A6182014-07-18018 July 2014 NRR E-mail Capture - Turkey Point 3 and 4 Request for Additional Information - LAR 231 Project stage: RAI ML15131A5752014-07-18018 July 2014 La - Turkey Point 3 and 4 Request for Additional Information - LAR 231 Project stage: RAI ML14203A6142014-07-18018 July 2014 NRR E-mail Capture - Turkey Point 3 and 4 Request for Additional Information - LAR 231 Project stage: RAI ML14203A6202014-07-21021 July 2014 NRR E-mail Capture - Turkey Point 3 and 4 Request for Additional Information - LAR 231 (TACs MF4392 and MF4393) Project stage: RAI L-2014-232, Response to Request for Additional Information Regarding License Amendment Request No. 231, Application to Revise Technical Specifications to Revise Ultimate Heat Sink Temperature Limit2014-07-22022 July 2014 Response to Request for Additional Information Regarding License Amendment Request No. 231, Application to Revise Technical Specifications to Revise Ultimate Heat Sink Temperature Limit Project stage: Response to RAI L-2014-235, License Amendment Request No. 231, Application to Revise Ultimate Heat Sink Temperature Limit - Supplement 1, and Response to Request for Additional Information2014-07-22022 July 2014 License Amendment Request No. 231, Application to Revise Ultimate Heat Sink Temperature Limit - Supplement 1, and Response to Request for Additional Information Project stage: Supplement ML14204A8142014-07-22022 July 2014 NRR E-mail Capture - Turkey Point 3 and 4 Request for Additional Information - LAR 231 (TACs MF4392 and MF4393) Project stage: RAI L-2014-236, Response to Containment and Ventilation Branch Request for Additional Information, Regarding License Amendment Request No. 231, Application to Revise Ultimate Heat Temperature Limit2014-07-24024 July 2014 Response to Containment and Ventilation Branch Request for Additional Information, Regarding License Amendment Request No. 231, Application to Revise Ultimate Heat Temperature Limit Project stage: Request ML14208A0102014-07-25025 July 2014 NRR E-mail Capture - Turkey Point 3 and 4 Request for Additional Information - LAR 231 (TACs MF4392 and MF4393) Project stage: RAI ML14208A0112014-07-26026 July 2014 NRR E-mail Capture - Turkey Point 3 and 4 Request for Additional Information - LAR 231 (TACs MF4392 and MF4393) Project stage: RAI L-2014-237, Response to Request for Additional Information Regarding License Amendment Request No. 231, Application to Revise Ultimate Heat Sink Temperature Limit2014-07-26026 July 2014 Response to Request for Additional Information Regarding License Amendment Request No. 231, Application to Revise Ultimate Heat Sink Temperature Limit Project stage: Response to RAI ML14216A0722014-07-28028 July 2014 NRR E-mail Capture - Turkey Point 3 and 4 Request for Additional Information - LAR 231 (TACs MF4392 and MF4393) Project stage: RAI ML14209A0312014-07-28028 July 2014 Environmental Assessment and Finding of No Significant Impact Related to the Ultimate Heat Sink Temperature Limit Project stage: Other NRC-2014-0181, Environmental Assessment and Finding of No Significant Impact Related to the Ultimate Heat Sink Temperature Limit (TAC Nos. MF4392 and MF4393)2014-07-28028 July 2014 Environmental Assessment and Finding of No Significant Impact Related to the Ultimate Heat Sink Temperature Limit (TAC Nos. MF4392 and MF4393) Project stage: Other ML14217A0042014-08-0303 August 2014 NRR E-mail Capture - Turkey Point 3 and 4 Request for Additional Information - LAR 231 (TACs MF4392 and MF4393) Project stage: RAI L-2014-259, Response to Containment and Ventilation Branch Request for Additional Information (RAI-5), Regarding License Amendment Request No. 231, Application to Revise Ultimate Heat Sink Temperature Limit2014-08-0404 August 2014 Response to Containment and Ventilation Branch Request for Additional Information (RAI-5), Regarding License Amendment Request No. 231, Application to Revise Ultimate Heat Sink Temperature Limit Project stage: Request 2014-07-24
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Category:E-Mail
MONTHYEARML24024A0182024-01-24024 January 2024 LTR-23-0216-1 - (E-Mail) Turkey Point Nuclear Plant, Units 3 and 4 - 10 CFR 2.206 Petition -Turkey Point and PWR RPV Embrittlement E-Mail Closure Letter to Petitioner, January 23, 2024 ML24023A0622024-01-10010 January 2024 10 CFR 2.206 Petition - LTR-23-0216-1 - Turkey Point and PWR RPV Embrittlement - E-mail Final Determination Status to Petitioner - 1-10-2024 - L-2023-CRS-0005 IR 05000250/20240102024-01-0505 January 2024 Focused Engineering Inspection 05000250/2024010 and 05000251/2024010 ML23347A0772023-12-13013 December 2023 NRR E-mail Capture - Acceptance Review - Turkey Point Nuclear Generating Unit Nos. 3 and 4 - LAR to Transition to 24-Month Fuel Cycles (L-2023-LLA-00161) ML23341A0602023-12-0707 December 2023 NRR E-mail Capture - Acceptance Review - Turkey Point Nuclear Generating Unit Nos. 3 and 4 - Exemption Request for Use of Axiom Fuel Cladding (L-2023-LLE-0036) ML23317A3752023-11-0808 November 2023 NRR E-mail Capture - Acceptance Review - Turkey Point Nuclear Generating Unit Nos. 3 and 4 - LAR to Update SFP Criticality Analysis (L-2023-LLA-0142) ML23307A2382023-11-0303 November 2023 10 CFR 2.206 Petition - LTR-23-0216-1 - Initial Assessment; Turkey Point Subsequent License Renewal with Petitioner 11/3/2023 - L-2023-CRS-0005 ML23333A0092023-10-27027 October 2023 Attachment a - NRC Extension of Comment Period-1 ML23265A2692023-09-15015 September 2023 Turkey Point,_Rp Document Request 2023-004 ML23226A0752023-08-14014 August 2023 NRR E-mail Capture - Turkey Point Nuclear Generating Unit Nos. 3 and 4 - Request for Additional Information - RCP LAR (L-2022-LLA-0128) ML23173A1522023-06-22022 June 2023 Request for Additional Information NextEra Fleet Emergency Plan Amendment Request ML23171B0532023-06-20020 June 2023 NRR E-mail Capture - Change in Estimated Review Schedule for Turkey Point Improved Standard Technical Specifications (ITS) LAR (L-2022-LLI-0002) ML23198A0592023-05-22022 May 2023 FPL to Fws, Notification of Doa Crocodile in CCS on 5/22/23 ML23138A0212023-05-17017 May 2023 Telephone Record, Call with Florida Power and Light Regarding Decommissioning Funding Plan Update Dated March 30, 2021 ML23129A8322023-05-0505 May 2023 NRR E-mail Capture - Turkey Point Nuclear Generating Unit Nos. 3 and 4 - Request for Additional Information - RCP LAR (L-2022-LLA-0128) ML23109A1862023-04-19019 April 2023 and Turkey Point Acceptance of Requested Licensing Action Proposed Alternative to Asme Section XI Authorizing Implementation of Asme Code Case N-752-1 ML23117A2712023-04-11011 April 2023 NRR E-mail Capture - (External_Sender) Updated Data for Doa Turkey Point American Crocodile at 4/10/2023 ML23067A2812023-03-0808 March 2023 NRR E-mail Capture - (External_Sender) Non-causal American Croc Doa Turkey Point ML23038A1892023-02-0303 February 2023 RP RFI April 2023 ML23006A0262023-01-0505 January 2023 NRR E-mail Capture - Audit Plan - Turkey Point Fire Protection Changes to Support RCP Seal Replacement LAR ML22311A4752022-11-0707 November 2022 NRR E-mail Capture - Turkey Point Nuclear Generating Unit Nos. 3 and 4 - Request for Additional Information - ITS ML22293B6562022-10-18018 October 2022 Request for 45 Day Extension of Comment Period of Turkey Point Subsequent License Renewal Scoping Process, Docket Id NRC-2022-0172 by Natural Resources Defense Council, Miami Waterkeeper and Counsel for Friends of the Earth ML22265A1522022-09-21021 September 2022 NRR E-mail Capture - Acceptance Review - Turkey Point Nuclear Generating Unit Nos. 3 and 4 - LAR to Revise Fire Protection Program (L-2022-LLA-0128) ML22258A1862022-09-15015 September 2022 NRR E-mail Capture - Turkey Point Unit Nos. 3 and 4 - Supplemental Information Needed for Acceptance of Requested Licensing Action License Amendment Requests to Replace Instrumentation with Digital Systems ML22181A0562022-06-30030 June 2022 NRR E-mail Capture - Request for Additional Information - Turkey Point U3 Sgtir (L-2022-LRO-0070) ML22178A1032022-06-25025 June 2022 NRR E-mail Capture - (External_Sender) Turkey Point Doa American Crocodile 6/25/22 ML22147A0672022-05-19019 May 2022 NRR E-mail Capture - (External_Sender) Turkey Point Doa Crocodile 05/19/2022 ML22095A0162022-04-0505 April 2022 NRR E-mail Capture - Verbal Authorization of Turkey Point Nuclear Plant Unit 3 - Icw Relief Request No. 10-II ML22081A0292022-03-21021 March 2022 NRR E-mail Capture - Turkey Point Nuclear Generating Unit No. 3 - Request for Additional Information - Icw Alternative ML22018A0272022-01-18018 January 2022 2022 All RFI Responses - Exercise and Program Inspections - Revl ML21302A0052021-12-23023 December 2021 Email to Nextera/Fpl Re Discussion of Availability of Human Factor Validation Information to Support the Planned Turkey Point Digital I&C License Amendment Request ML21307A2882021-11-18018 November 2021 NRC to Fws, Request to Reinitiate Endangered Species Act Section 7 Consultation for Continued Operation of Turkey Point ML21298A0572021-10-25025 October 2021 NRR E-mail Capture - Final: Tpn Request for Additional Information - Round 2 Concerning Relief Request 10 - Extension EPID: L-2021-LLR-0077 ML21291A1272021-10-14014 October 2021 NRR E-mail Capture - Request for Additional Information - Fifth Ten-Year Inservice Inspection Interval Relief Request No.10 - Extension (L-2021-LLR-0077) ML21270A1652021-09-27027 September 2021 NRR E-mail Capture - Turkey Point Request for Additional Information Concerning Full Spectrum LOCA Methodology - EPID L-2021-LLA-0070 ML21266A2602021-09-22022 September 2021 NRR E-mail Capture - (External_Sender) Partial Sea Turtle Carcass at Turkey Point ML21252A2142021-09-0101 September 2021 NRR E-mail Capture - Final: Turkey Point Units 3 and 4 - Request for Additional Information Concerning Relief Requests 8 and 9 ML21207A1212021-06-30030 June 2021 Fws to NRC, Biological Opinion Notifications to Fws Law Enforcement ML21158A2332021-06-0707 June 2021 NRR E-mail Capture - Acceptance Review: Turkey Point Units 3 and 4 Fifth Ten-Year ISI Extension of ISI RPV Welds from 10 to 20 Years (L-2021-LLR-0038) ML21154A0872021-06-0202 June 2021 NRR E-mail Capture - 06/02/2021 Print a Logbook Entry: Turkey Point Endangered Species Report Regarding Injured American Crocodiles ML21154A0862021-05-25025 May 2021 NRR E-mail Capture - Acceptance Review: Turkey Point - Update Listing of Approved LOCA Methodologies to Adopt Full Spectrum LOCA Methodology ML21140A0672021-05-13013 May 2021 NRR E-mail Capture - (External_Sender) Regarding Doa American Crocodile Report 5-13-21 ML21131A1362021-05-0404 May 2021 NRR E-mail Capture - (External_Sender) 5/4/2021 Report Regarding Doa American Crocodile ML21097A1832021-03-30030 March 2021 NRR E-mail Capture - Endangered Species Death Report from Turkey Point Regarding Incident on 03/30/2021 ML21084A1312021-03-18018 March 2021 NRR E-mail Capture - (External_Sender) Deceased American Crocodile Found Outside FPL Property Line ML21056A0002021-02-24024 February 2021 NRR E-mail Capture - Endangered Species - 2/24/2021 Logbook Entry Regarding an American Crocodile ML21029A0172021-01-25025 January 2021 NRR E-mail Capture - 1/25/2021 Logbook Entry Regarding an American Crocodile Reported in the Owner Controlled Area ML21025A4152021-01-25025 January 2021 NRR E-mail Capture - 10 CFR 2.206 Petition Dated January 10, 2021 - Open Phase Condition Implementation ML20346A1022020-12-0808 December 2020 NRR E-mail Capture - Response: September 17, 2020 Submittal to the Nuclear Regulatory Commission ML20218A5502020-08-0505 August 2020 Florida Power & Light Letter L-2020-127: FPL QAPD for 10 CFR 52 Licenses FPL-2 Revision Summary 2024-01-05
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NRR-PMDAPEm Resource From: Klett, Audrey Sent: Monday, July 28, 2014 3:53 PM To: Tomonto, Bob (Bob.Tomonto@fpl.com); Czaya, Paul (Paul.Czaya@fpl.com); 'Hanek, Olga' (Olga.Hanek@fpl.com)
Cc: Cross, William (WILLIAM.CROSS@fpl.com)
Subject:
Turkey Point 3 and 4 Request for Additional Information - LAR 231 (TACs MF4392 and MF4393)
By letter dated July 10, 2014, as supplemented by letters dated July 17, July 22, July 24, and July 26, 2014, Florida Power & Light Company (the licensee) submitted a license amendment request for the Turkey Point Nuclear Generating Unit Nos. 3 and 4 (Turkey Point). The licensee requested revisions to the Turkey Point Technical Specifications (TSs), Section 3/4.7.4, Ultimate Heat Sink [UHS].
The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the information provided by the licensee and determined that it needs additional information to complete the review. The NRC staffs request for additional information (RAI) is as follows.
SCVB RAI-4 Please describe the changes that will be included in the UFSAR related to the license amendment request (e.g., regarding maintaining the component cooling water heat exchangers so that they are ready and capable of functioning as intended during normal and accident conditions).
BOP RAI-7 The licensees response to BOP RAI-1 states that the input to HX3/HX4 is TICW in, TICW out, TCCW in, TCCW out, and intake cooling water (ICW) Flow Rate.
The licensees response also states that The HX3/HX4 program equates the heat gain by the ICW system, the heat loss from CCW [component cooling water] and then determines the overall heat transfer coefficient, U, based on the surveillance heat transfer rate and logarithmic mean temperature difference. The HX3/HX4 program determines the TR [tube resistance] based on the surveillance overall heat transfer coefficient U, first principle equations and appropriate film coefficients.
When doing the surveillances, Q is unknown.
Equations:
- 1. QICW= (MICW) (CP ICW) (TICW out - TICW in)
- 2. QCCW = (MCCW) (CP CCW) (TCCW in -TCCW out)
- 3. Q = U0 (A) LMTD
- 4. Q= QICW = QCCW Where:
QICW = Heat Gain to ICW from CCW CP ICW = ICW Specific Heat MICW = ICW Mass Flow Rate TICW out = ICW Outlet Temperature TICW in = ICW Inlet Temperature QCCW = Heat Loss from CCW to ICW MCCW = CCW Mass Flow Rate CP CCW = CCW Specific Heat TCCW in = CCW Inlet Temperature TCCW out = CCW Outlet Temperature 1
U0 = Overall Heat Transfer Coefficient A = Total Tube Exterior Surface Area LMTD = log mean temperature differential Variables that are underlined are known.
Q is needed to get U0, which is needed to get TR (tube resistance), so that one can accurately enter Figure 3.5-1 of the licensees letter dated July 10, 2014, or the graphs of HX3/HX4. The unknowns are Q, CP ICW, MCCW, and U0. Considering equations 1, 2, and 3, there are 3 equations and 4 unknowns.
A. How does the licensee know the value of U0?
B. When the licensee knows the value of U0, how does it find TR knowing that the tube side film coefficient is affected by the algae?
C. How does the licensee know it has the correct TR when doing surveillances and thus is able to know that there is sufficient heat transfer capability for a design basis accident?
BOP RAI-8 In its response to BOP RAI-6 by letter dated July 26, 2014, the licensee stated, The RHR [residual heat removal] Pump mechanical seals are cooled by CCW [component cooling water] through mechanical seal coolers with process fluid on the tube side and CCW water on the shell side. Per Drawing 5610-M-450-96, Sheet 1, CCW is to be available at 145ºF [degrees Fahrenheit] initially, decreasing to 125ºF in 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />.
The licensee also stated, The CS [containment spray] Pump mechanical seal is cooled by CCW through a mechanical seal cooler. The maximum operating temperature for the Containment Spray Pump mechanical seal is 205ºF. Per the vendor data sheets for the mechanical seals on the Unit 4 CS pumps, 3 gpm [gallons per minute] of flow at 150ºF is needed for the CS pump seal coolers.
However, the peak CCW supply temperature to the RHR and CS pumps during a loss-of-coolant accident, double-ended pump suction (LOCA-DEPS) break approaches 160°F and stays above 150°F for several hours after the accident, according to the licensees letter dated July 24, 2014. The CCW supply temperature appears to be too high to meet the vendor-specified cooling requirements for these pumps. Discuss how the RHR and CS pumps will have adequate cooling to run continuously in order to perform their design basis function during a design basis accident.
Audrey Klett Project Manager NRR/DORL/LPLII-2 301-415-0489 2
Hearing Identifier: NRR_PMDA Email Number: 1465 Mail Envelope Properties (Audrey.Klett@nrc.gov20140728155200)
Subject:
Turkey Point 3 and 4 Request for Additional Information - LAR 231 (TACs MF4392 and MF4393)
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