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| | issue date = 04/08/2010 | | | issue date = 04/08/2010 |
| | title = ME1819, LAR-Follow-up RAIs from Eicb | | | title = ME1819, LAR-Follow-up RAIs from Eicb |
| | author name = Vaidya B K | | | author name = Vaidya B |
| | author affiliation = NRC/NRR/DORL/LPLI-1 | | | author affiliation = NRC/NRR/DORL/LPLI-1 |
| | addressee name = Dorman E, Pechacek J | | | addressee name = Dorman E, Pechacek J |
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| | docket = 05000333 | | | docket = 05000333 |
| | license number = | | | license number = |
| | contact person = vaidya B K, NRR/Dorl/lpl1-1, 415-3308 | | | contact person = vaidya B, NRR/Dorl/lpl1-1, 415-3308 |
| | case reference number = TAC ME1819 | | | case reference number = TAC ME1819 |
| | document type = E-Mail, Request for Additional Information (RAI) | | | document type = E-Mail, Request for Additional Information (RAI) |
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| =Text= | | =Text= |
| {{#Wiki_filter:From: Vaidya, Bhalchandra Sent: Thursday, April 08, 2010 7:24 AM To: 'Dorman, Eugene'; 'Pechacek, Joseph' Cc: Salgado, Nancy; Kemper, William; Chung, Pong; Rahn, David | | {{#Wiki_filter:From: Vaidya, Bhalchandra Sent: Thursday, April 08, 2010 7:24 AM To: 'Dorman, Eugene'; 'Pechacek, Joseph' Cc: Salgado, Nancy; Kemper, William; Chung, Pong; Rahn, David |
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| ==Subject:== | | ==Subject:== |
| James A. FitzPatrick Nuclear Power Plant, ME1819, LAR-Follow-up Request for Information (RAIs) from EICB By application dated July 31, 2009, Entergy proposed license amendment to change James A Fitzpatrick Nuclear Power Plant (JAFNPP), Technical Specifications (TSs). The proposed change revises the TS and associated Bases to modify the TS Surveillance Requirements (SR) for testing of the Residual Heat Removal System Shutdown Cooling (SDC) mode Containment Isolation, Reactor Pressure - High Function by replacing the current requirement to perform TS SR 3.3.6.1.3, perform channel calibration with TS SRs 3.3.6.1.1 perform channel check, 3.3.6.1.2, perform channel functional test, 3.3.6.1.4, calibrate the trip units, and 3.3.6.1.5, perform channel calibration. This change was needed to support the plant modification to increase the reliability of SDC isolation logic by changing the source of the reactor pressure high input signal. | | James A. FitzPatrick Nuclear Power Plant, ME1819, LAR-Follow-up Request for Information (RAIs) from EICB By application dated July 31, 2009, Entergy proposed license amendment to change James A Fitzpatrick Nuclear Power Plant (JAFNPP), Technical Specifications (TSs). The proposed change revises the TS and associated Bases to modify the TS Surveillance Requirements (SR) for testing of the Residual Heat Removal System Shutdown Cooling (SDC) mode Containment Isolation, Reactor Pressure - High Function by replacing the current requirement to perform TS SR 3.3.6.1.3, perform channel calibration with TS SRs 3.3.6.1.1 perform channel check, 3.3.6.1.2, perform channel functional test, 3.3.6.1.4, calibrate the trip units, and 3.3.6.1.5, perform channel calibration. This change was needed to support the plant modification to increase the reliability of SDC isolation logic by changing the source of the reactor pressure high input signal. |
| | | The NRC Instrumentation and Controls Branch (EICB) has reviewed the supplemental submission dated March 5, 2010, responding to the previous RAIs and has determined that the following additional information is needed to complete the review. There was a tele-conference between the NRC staff and JAFNPP on April 5, 2010, and the staff's concerns regarding follow-up RAIs were discussed. |
| The NRC Instrumentation and Controls Branch (EICB) has reviewed the supplemental submission dated March 5, 2010, responding to the previous RAIs and has determined that the following additional information is needed to complete the review. There was a tele-conference between the NRC staff and JAFNPP on April 5, 2010, and the staff's concerns regarding follow-up RAIs were discussed. The follow-up RAIs are provided below: | | The follow-up RAIs are provided below: |
| JAMES A FITZPATRICK NUCLEAR POWER PLANT, REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT RELATED TO SDC SYSTEM ISOLATION, REACTOR PRESSURE - HIGH (TAC NO. ME1819) | | JAMES A FITZPATRICK NUCLEAR POWER PLANT, REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT RELATED TO SDC SYSTEM ISOLATION, REACTOR PRESSURE - HIGH (TAC NO. ME1819) |
| : 1. In attachment 1, on page 3, of the licensee's RAI response letter dated March 5, 2010 (JAFP-10-0033), it states in the first paragraph: | | : 1. In attachment 1, on page 3, of the licensee's RAI response letter dated March 5, 2010 (JAFP-10-0033), it states in the first paragraph: |
| "Following performance-to review the completed procedure to ensure acceptance criteria was satisfied and that "As-Found" and "As-left" values are within their required tolerance."
| | Following performanceto review the completed procedure to ensure acceptance criteria was satisfied and that As-Found and As-left values are within their required tolerance. |
| And in the second paragraph, it states: | | And in the second paragraph, it states: |
| "If a Condition Report documents that an instrument failed to meet Level 1 acceptance criteria and could not be restored to within tolerance, the instrument would be declared INOPERABLE and the appropriate Condition associated with the applicable Limiting Condition for Operation (LCO) would be entered."
| | If a Condition Report documents that an instrument failed to meet Level 1 acceptance criteria and could not be restored to within tolerance, the instrument would be declared INOPERABLE and the appropriate Condition associated with the applicable Limiting Condition for Operation (LCO) would be entered. |
| : a. Clarify the use of the terms and provide the values of the "acceptance criteria", the "required tolerances", and "Level 1 acceptance criteria." | | : a. Clarify the use of the terms and provide the values of the acceptance criteria, the required tolerances, and Level 1 acceptance criteria. |
| : b. Provide the detailed calculation and/or determination of "As-Found" and "As-Left" setting tolerances of the entire instrument loop. | | : b. Provide the detailed calculation and/or determination of As-Found and As-Left setting tolerances of the entire instrument loop. |
| : 2. In attachment 2, section 8.2.3, of the licensee's RAI response, it states: | | : 2. In attachment 2, section 8.2.3, of the licensee's RAI response, it states: |
| "Use of the reactor steam dome pressure measurement (ATTS) to provide the SDC isolation function will result in the utilization of an instrument loop that has a larger instrument uncertainty than originally provided by the pressure switches."
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| The licensee calculated the allowable value (section 6.5, attachment 2 of the RAI response) by applying the "method 3" of ISA-RP67.04.02-2000. The licensee also calculated the limiting trip setpoint LTS = EAL - CU (section 6.4) with a round up margin of 0.72 psig (section 6.3.1). However, the round up of AVTSMChannel from +/-14.67 psig to +/-15 psig increases the allowance for instrument channel deviation (section 6.3.1); thus is less conservative and cannot be counted as an addition margin.
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| Explain how you can ensure that the field trip setpoint is conservative with respect to the analytical value (AL) with "method 3" and with such a small margin in the LTS calculation. | | Use of the reactor steam dome pressure measurement (ATTS) to provide the SDC isolation function will result in the utilization of an instrument loop that has a larger instrument uncertainty than originally provided by the pressure switches. |
| : 3. In attachment 2, Table 1, of the licensee's RAI response, it states that the humidity, radiation, and temperature effects for the total loop uncertainty calculation of pressure transmitters and ATTS under LOCA and HELB conditions are same as those under normal condition. This statement is based on assumption 1.2.6. Assumption 1.2.6 states that "DBD-010 (Ref 4.2.11) identifies the SDC Isolation function as not having any accident mitigating functions." However, according to TS Table 3.3.6.1-1 (page 5 of 6), function 6a "SDC Isolation, Reactor Pressure - Hi" is used to initiate a primary containment isolation function. Assumption 1.2.6 seems to contradict with this TS requirement. Please provide the following: | | The licensee calculated the allowable value (section 6.5, attachment 2 of the RAI response) by applying the method 3 of ISA-RP67.04.02-2000. The licensee also calculated the limiting trip setpoint LTS = EAL - CU (section 6.4) with a round up margin of 0.72 psig (section 6.3.1). However, the round up of AVTSMChannel from +/-14.67 psig to +/-15 psig increases the allowance for instrument channel deviation (section 6.3.1); thus is less conservative and cannot be counted as an addition margin. |
| | Explain how you can ensure that the field trip setpoint is conservative with respect to the analytical value (AL) with method 3 and with such a small margin in the LTS calculation. |
| | : 3. In attachment 2, Table 1, of the licensee's RAI response, it states that the humidity, radiation, and temperature effects for the total loop uncertainty calculation of pressure transmitters and ATTS under LOCA and HELB conditions are same as those under normal condition. This statement is based on assumption 1.2.6. Assumption 1.2.6 states that DBD-010 (Ref 4.2.11) identifies the SDC Isolation function as not having any accident mitigating functions. However, according to TS Table 3.3.6.1-1 (page 5 of 6), function 6a SDC Isolation, Reactor Pressure - Hi is used to initiate a primary containment isolation function. Assumption 1.2.6 seems to contradict with this TS requirement. Please provide the following: |
| : a. Where the pressure transmitter 02-3PT-55A/D is located (inside or outside the primary containment)? | | : a. Where the pressure transmitter 02-3PT-55A/D is located (inside or outside the primary containment)? |
| : b. What are the worst-case environmental conditions at the locations for the transmitters and ATTS? | | : b. What are the worst-case environmental conditions at the locations for the transmitters and ATTS? |
| : c. What are the worst-case environmental conditions under which the SDC isolation valves are required to be actuated? | | : c. What are the worst-case environmental conditions under which the SDC isolation valves are required to be actuated? |
| : d. Provide a clarifying description regarding the conditions under which the function of this instrument channel is required when using the SDC line that resolves the apparent contradiction between assumption 1.2.6 and the TS requirement of function 6a in the TS Table 3.3.6.1-1 (page 5 of 6). | | : d. Provide a clarifying description regarding the conditions under which the function of this instrument channel is required when using the SDC line that resolves the apparent contradiction between assumption 1.2.6 and the TS requirement of function 6a in the TS Table 3.3.6.1-1 (page 5 of 6). |
| : e. Provide copies of the source documents that justify the values for seismic, radiation, humidity, and temperature values used in the calculation, JAF-CALC-NBS-02052. ========================================== | | : e. Provide copies of the source documents that justify the values for seismic, radiation, humidity, and temperature values used in the calculation, JAF-CALC-NBS-02052. |
| Please contact me, if you need additional clarification of this request. If not, provide a firm commitment for the response to this request. | | ========================================== |
| | | Please contact me, if you need additional clarification of this request. If not, provide a firm commitment for the response to this request. |
| Bhalchandra K. Vaidya Licensing Project Manager NRC/NRR/DORL/LPL1-1 (301)-415-3308 (O) bhalchandra.vaidya@nrc.gov | | Bhalchandra K. Vaidya Licensing Project Manager NRC/NRR/DORL/LPL1-1 (301)-415-3308 (O) bhalchandra.vaidya@nrc.gov |
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| E-mail Properties Mail Envelope Properties () | | E-mail Properties Mail Envelope Properties () |
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| ==Subject:== | | ==Subject:== |
| James A. FitzPatrick Nuclear Power Plant, ME1819, LAR-Follow-up Request for Information (RAIs) from EICB Sent Date: 04/07/2010 3:15:13 PM Received Date: 04/08/2010 7:23:00 AM From: Vaidya, Bhalchandra | | James A. FitzPatrick Nuclear Power Plant, ME1819, LAR-Follow-up Request for Information (RAIs) from EICB Sent Date: 04/07/2010 3:15:13 PM Received Date: 04/08/2010 7:23:00 AM From: Vaidya, Bhalchandra Created By: Bhalchandra.Vaidya@nrc.gov Recipients: |
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| Created By: Bhalchandra.Vaidya@nrc.gov | |
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| Recipients: | |
| EDorman@entergy.com ('Dorman, Eugene') | | EDorman@entergy.com ('Dorman, Eugene') |
| Tracking Status: None JPechac@entergy.com ('Pechacek, Joseph') | | Tracking Status: None JPechac@entergy.com ('Pechacek, Joseph') |
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| Tracking Status: None Pong.Chung@nrc.gov (Chung, Pong) | | Tracking Status: None Pong.Chung@nrc.gov (Chung, Pong) |
| Tracking Status: None David.Rahn@nrc.gov (Rahn, David) | | Tracking Status: None David.Rahn@nrc.gov (Rahn, David) |
| Tracking Status: None | | Tracking Status: None Post Office: |
| | | Files Size Date & Time MESSAGE 28504 04/07/2010 Options Expiration Date: |
| Post Office: | | Priority: olImportanceNormal ReplyRequested: False Return Notification: False Sensitivity: olNormal Recipients received:}} |
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| Files Size Date & Time | |
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| MESSAGE 28504 04/07/2010 | |
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| Options Expiration Date: | |
| Priority: olImportanceNormal ReplyRequested: False Return Notification: False | |
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| Sensitivity: olNormal Recipients received:}} | |
Letter Sequence RAI |
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MONTHYEARML0925305982009-09-10010 September 2009 ME1819, Acceptance of Licensing Action LAR to Modify TS Requirements for Testing of the Shutdown Cooling System Isolation, Reactor Pressure - High Function Project stage: Acceptance Review ML1003300392010-02-0202 February 2010 ME1819, RAIs from Eicb on LAR Changes to TS Requirements for Testing of the RHR (Shutdown Cooling Mode) System Containment Isolation Reactor Pressure - High Function Project stage: RAI ML1007505222010-03-0505 March 2010 James A. FitzPatrick, Response to Request for Additional Information Application for Amendment to Modify Technical Specifications Requirements for Testing of the Shutdown Cooling System Isolation, Reactor Pressure - High Function Project stage: Response to RAI JAFP-10-0033, Attachment 2 to JAFP-10-0033, Calculation JAF-CALC-NBS-02052, Revision 42010-03-0505 March 2010 Attachment 2 to JAFP-10-0033, Calculation JAF-CALC-NBS-02052, Revision 4 Project stage: Other ML1009800112010-04-0808 April 2010 ME1819, LAR-Follow-up RAIs from Eicb Project stage: RAI JAFP-10-0072, Response to Request for Additional Information Application for Amendment to Modify the Technical Specifications Requirements for Testing of the Shutdown Cooling System2010-06-17017 June 2010 Response to Request for Additional Information Application for Amendment to Modify the Technical Specifications Requirements for Testing of the Shutdown Cooling System Project stage: Response to RAI ML1018802292010-07-21021 July 2010 Issuance of License Amendment 298 Regarding Modification of the Tech Specs Requirements for Testing of the Shutdown Cooling System Isolation, Reactor Pressure-High Project stage: Approval 2010-03-05
[Table View] |
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Category:E-Mail
MONTHYEARML24024A1372024-01-24024 January 2024 NRR E-mail Capture - Final Snsb RAI Regarding FitzPatrick Amendment to Modify Safety Relief Valves Setpoint Lower Tolerance ML24017A1112024-01-17017 January 2024 NRR E-mail Capture - Acceptance of Requested Licensing Action Amendment Request to Adopt TSTF-529, Clarifyuse and Applicaion Rules, Revision 4 ML23264A7992023-09-21021 September 2023 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC Fleet Request License Amendment Request to Adopt TSTF-580, Revision 1 ML23261C3982023-09-0808 September 2023 Acceptance Review of Amendment to Update the Fuel Handling Accident Analysis ML23244A2662023-09-0101 September 2023 Acceptance of Requested Licensing Action Amendment Request to Modify Surveillance Requirement 3.4.3.1, Safety Relief Valves Setpoint Lower Tolerance ML23237B3972023-08-24024 August 2023 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of Alternative Request to Use Updated BWRVIP Guidelines ML23194A1822023-08-0303 August 2023 Acceptance Review for LAR Re SRM 3.3.1.2 ML23163A2292023-06-12012 June 2023 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of License Amendment Request to Adopt TSTF-580, Revision 1 ML22354A2622022-12-20020 December 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of Request to Use Certain Provisions of the 2019 Edition of the ASME BPV Code, Section XI NRC-2100-2022, EN 55999 Valcor Coil Shell Assemblies Final Notification (004)2022-09-12012 September 2022 EN 55999 Valcor Coil Shell Assemblies Final Notification (004) NRC 2110-2022, EN 55999 - Valcor Engineering Corporation (009)2022-07-18018 July 2022 EN 55999 - Valcor Engineering Corporation (009) ML22124A2672022-05-0404 May 2022 Request for Additional Information for James A. FitzPatrick Nuclear Power Plant TSTF-505 ML22041B5362022-02-10010 February 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541 ML22020A0642022-01-13013 January 2022 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles ML22063A4742021-11-29029 November 2021 Acceptance of Requested Licensing Action License Amendment Request to Eliminate Selected Response Time Testing ML21301A0672021-10-28028 October 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Acceptance of License Amendment Request to Adopt TSTF-541 ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21252A0482021-09-0707 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Fleet Alternative Request for Repair of Water Level Instrumentation Partial Penetration Nozzles ML21246A2112021-09-0303 September 2021 Acceptance of Requested Licensing Action License Amendment Request to Adopt TSTF-505 ML21246A2072021-09-0303 September 2021 Acceptance of Requested Licensing Action License Amendment Request to Adopt 10 CFR 50.69 ML21215A3502021-08-0303 August 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Acceptance of License Amendment Request to Adopt TSTF-554 ML21187A0522021-07-0606 July 2021 Fitz RAI Regarding FitzPatrick Amendment Request to Modify SR 3.5.1.6 ML21246A2142021-06-23023 June 2021 Acceptance of Requested Licensing Action Regarding License Amendment Request to Adopt TSTF-264 ML21154A0112021-05-28028 May 2021 NRR E-mail Capture - Extension of Comment Period for the Exelon Generation Company, LLC License Transfer Application ML21154A0142021-05-28028 May 2021 NRR E-mail Capture - Extension of Comment Period for the Exelon Generation Company, LLC License Transfer Application ML21154A0132021-05-28028 May 2021 NRR E-mail Capture - Extension of Comment Period for the Exelon Generation Company, LLC License Transfer Application ML21144A2132021-05-24024 May 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21144A1072021-05-17017 May 2021 Acceptance of Requested Licensing Action License Amendment Request to Adopt TSTF-582 ML21117A0442021-04-26026 April 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting ML21084A2532021-03-24024 March 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Acceptance of License Transfer Application ML21062A0652021-03-0101 March 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting ML21049A2572021-02-18018 February 2021 Request for Additional Information Byron/Dresden Proposed Changes to Site Emergency Plans to Support Post-Shutdown and Permanently Defueled Conditions (EPID-2020-LLA-0240 & EPID-2020-LLA-0237) ML21033A8552021-02-0202 February 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Fleet Alternative Request to Expand the Use ASME Codes Cases N-878 and N-880 ML21014A5112021-01-12012 January 2021 Acceptance of Requested Licensing Action License Amendment Request to Adopt TSTF-545 Revision 3 ML20352A2752020-12-17017 December 2020 Request for Additional Information Regarding FitzPatrick Primary Containment Isolation Valve Amendment Request ML20350B5582020-12-14014 December 2020 NRR E-mail Capture - Exelon Generation Company, LLC -Alternative Request for Documentation of Replacement of Pressure Retaining Bolting ML20294A0372020-10-19019 October 2020 Request for Additional Information Primary Containment Isolation Valve License Amendment Request ML20266G3032020-09-22022 September 2020 NRR E-mail Capture - Exelon Generation Company, LLC - Fleet Request to Use Paragraph IWA-5120 of the 2017 Edition of the ASME B&PV Code, Section XI ML20217L3882020-08-0404 August 2020 Acceptance of Requested Licensing Action License Amendment Request to Modify Primary Containment Isolation Valve TS (EPID L-2020-LLA-0145) (E-Mail) ML20204A9692020-07-22022 July 2020 Acceptance of Requested Licensing Action License Amendment Request to Adopt-TSTF-478 Revision 2 ML20122A2302020-05-0101 May 2020 NRR E-mail Capture - Exelon Generation Company, LLC - Acceptance of Fleet License Amendment Request to Adopt TSTF-566 ML20066L3682020-03-0505 March 2020 Request for Additional Information: License Amendment Request for Change to the Technical Specifications to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment ML20056E7992020-02-25025 February 2020 Request for Additional Information for LAR on Primary Containment Hydrodynamic Loads ML20035D5762020-02-0303 February 2020 Request for Additional Information: License Amendment Request for Application of the Alternative Source Term for Calculating Loss-of-Coolant Accident Dose Consequence ML20027A0672020-01-24024 January 2020 Accepted for Review - Fitzpatrick License Amendment Request to Adopt TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 ML20027A0112020-01-23023 January 2020 Request for Additional Information: License Amendment Request for Change to the Technical Specifications to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation ML19353A9452019-12-19019 December 2019 Request for Additional Information: License Amendment Request for Application of the Alternative Source Term for Calculating Loss-of-Coolant Accident Dose Consequences ML19319C3582019-11-15015 November 2019 NRR E-mail Capture - Accepted for Review - FitzPatrick License Amendment Request to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation ML19322A0062019-11-15015 November 2019 NRR E-mail Capture - Fermi 2: Request for Additional Information- Relief Request VRR-006, Proposed Alternative for Preservice Testing of Butterfly Valves ML19316A0162019-11-0404 November 2019 NRR E-mail Capture - Revised Staff Hours Estimate - FitzPatrick License Amendment Request on Proposed Changes to the Technical Specifications Related to Primary Containment Hydrodynamic Loads 2024-01-24
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24024A1372024-01-24024 January 2024 NRR E-mail Capture - Final Snsb RAI Regarding FitzPatrick Amendment to Modify Safety Relief Valves Setpoint Lower Tolerance ML24018A0012024-01-18018 January 2024 Notification of Commercial Grade Dedication Inspection (05000333/2024010) and Request for Information ML23264A7992023-09-21021 September 2023 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC Fleet Request License Amendment Request to Adopt TSTF-580, Revision 1 ML23164A0322023-06-13013 June 2023 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000333/2023010 ML22321A0102022-11-17017 November 2022 Notification of Conduct of a Fire Protection Team Inspection ML22124A2672022-05-0404 May 2022 Request for Additional Information for James A. FitzPatrick Nuclear Power Plant TSTF-505 ML22041B5362022-02-10010 February 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541 ML22020A0642022-01-13013 January 2022 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21187A0522021-07-0606 July 2021 Fitz RAI Regarding FitzPatrick Amendment Request to Modify SR 3.5.1.6 ML21144A2132021-05-24024 May 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21062A0652021-03-0101 March 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting ML21049A2572021-02-18018 February 2021 Request for Additional Information Byron/Dresden Proposed Changes to Site Emergency Plans to Support Post-Shutdown and Permanently Defueled Conditions (EPID-2020-LLA-0240 & EPID-2020-LLA-0237) ML21041A1932021-02-10010 February 2021 Request for Information for a Triennial Baseline Design-Basis Capability of Power-Operated Valves Under 10 CFR 50.55a Requirements Inspection; Inspection Report (05000333/2021011) ML20066L3682020-03-0505 March 2020 Request for Additional Information: License Amendment Request for Change to the Technical Specifications to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment ML20056E7992020-02-25025 February 2020 Request for Additional Information for LAR on Primary Containment Hydrodynamic Loads ML20035D5762020-02-0303 February 2020 Request for Additional Information: License Amendment Request for Application of the Alternative Source Term for Calculating Loss-of-Coolant Accident Dose Consequence ML20027A0112020-01-23023 January 2020 Request for Additional Information: License Amendment Request for Change to the Technical Specifications to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation ML19353A9452019-12-19019 December 2019 Request for Additional Information: License Amendment Request for Application of the Alternative Source Term for Calculating Loss-of-Coolant Accident Dose Consequences ML19322A0062019-11-15015 November 2019 NRR E-mail Capture - Fermi 2: Request for Additional Information- Relief Request VRR-006, Proposed Alternative for Preservice Testing of Butterfly Valves ML19280A0372019-10-0505 October 2019 NRR E-mail Capture - FitzPatrick Revised Request for Additional Information: Emergency Amendment to Extend Completion Time of Transformer to 21 Days ML19280A0392019-10-0505 October 2019 NRR E-mail Capture - FitzPatrick Additional Request for Additional Information: Emergency Amendment to Extend Completion Time of Transformer to 21 Days ML19280A0362019-10-0404 October 2019 NRR E-mail Capture - FitzPatrick Request for Additional Information: Emergency Amendment to Extend Completion Time of Transformer to 21 Days ML19099A2672019-04-16016 April 2019 Use of Encryption Software for Electronic Transmission of Safeguards Information ML19099A2852019-03-12012 March 2019 Draft RAI: FitzPatrick Request to Update Electronic Transmission of Safeguards Information ML19025A1202019-01-24024 January 2019 NRR E-mail Capture - Calvert Cliffs, Fitzpatrick, and Nine Mile Point - Request for Additional Information Regarding License Amendment Request to Revise Emergency Response Organization Staffing ML18353B5112018-12-20020 December 2018 Request for Additional Information Relief Request No. 14R-22, for Fourth 10-Year Inservice Inspection Interval ML18164A3652018-06-13013 June 2018 NRR E-mail Capture - FitzPatrick RAIs - LAR to Adopt EAL Schemes Pursuant to NEI 99-01, Revision 6 ML18094B0922018-04-0505 April 2018 Enclosurequest for Additional Information (Letter to B. S. Ford RAI Regarding Entergy Operations, Inc.'S Decommissioning Funding Plan Update for ISFSI Docket Nos.: 72-43, 72-51, 72-1044, 72-07, 72-12, and 72-59) ML18085A6922018-03-26026 March 2018 NRR E-mail Capture - James A. FitzPatrick Nuclear Power Plant, Unit 1 - Request for Information to Adopt Traveler TSTF-542, RPV Water Inventory Control ML18085A6912018-03-23023 March 2018 NRR E-mail Capture - Draft Request for Information (RAI) for JAFNPP Traveler TSTF-542, RPV Water Inventory Control ML18029A8422018-01-29029 January 2018 NRR E-mail Capture - Request for Additional Information: FitzPatrick License Amendment Request to Revise Technical Specifications to Address Secondary Containment Personnel Access Door Openings ML17335A1002017-11-29029 November 2017 NRR E-mail Capture - FitzPatrick - Request for Additional Information - Relief Request 15R-02 Regarding the Use of BWRVIP Guidelines Instead of ASME Code (CAC: MG0116; EPID: L-2017-LLR-0083) ML17285B1962017-10-27027 October 2017 Request for Additional Information Regarding Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools. ML17228A0052017-08-15015 August 2017 NRR E-mail Capture - Request for Additional Information - St. Lucie Relief Request #3 - Icw 30 Pipe Defect Removal (MF9288) ML16299A0192016-11-0202 November 2016 Request for Additional Information Regarding Direct License Transfer from Entergy to Exelon ML16287A6502016-10-21021 October 2016 Request for Additional Information Regarding: License Amendment Request to Revise Technical Specifications Section 5.5.6 for Extension of Type a and Type C Leak Rate Test Frequencies ML16280A5732016-10-18018 October 2016 Request for Additional Information Relief Request for Proposed Alternative for the Implementation of BWRVIP-05 ML16117A1862016-04-26026 April 2016 Entergy Fleet Relief Request EN-ISI-15-1 Request for Additional Information - 04/26/16 Email from R. Guzman to G. Davant (CAC Nos. MF7133-MF7136) ML16013A0642016-01-13013 January 2016 NRR E-mail Capture - Request for Additional Information Entergy CNRO-2015-00023 - Revision to Entergy Quality Assurance Program Manual (Fleet Submittal CAC Nos. MF7086-MF7097) ML15341A1662015-12-0707 December 2015 NRR E-mail Capture - Entergy Fleet RR-EN-15-1, Request for Additional Information (CACs MF6341-MF6349) ML14240A6122014-09-24024 September 2014 Request for Additional Information Regarding Proposed Changes to the Technical Specification Low Pressure Safety Limit ML14184A6152014-07-25025 July 2014 Request for Additional Information Regarding Proposed Safety Limit Minimum Critical Power Ratio License Amendment ML14195A0972014-07-16016 July 2014 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Hazard and Screening Report ML14164A5382014-07-0202 July 2014 Request for Additional Information Regarding 10 CFR 50.55A Alternate Request PRR-05 (Tac No. MF3680) ML14093A6772014-05-0101 May 2014 SONGS - Request for Additional Information Concerning Pre-Emption Authority ML13338A6452013-12-12012 December 2013 Interim Staff Evaluation and Request for Additional Information, Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation ML13304B4182013-11-0101 November 2013 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns ML13226A5342013-08-29029 August 2013 Request for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) ML13179A4622013-07-0505 July 2013 Entergy Nuclear Operations, Inc., Decommissioning Funding Status Report Request for Additional Information Regarding the Decommissioning Funding Status Report 2024-01-24
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From: Vaidya, Bhalchandra Sent: Thursday, April 08, 2010 7:24 AM To: 'Dorman, Eugene'; 'Pechacek, Joseph' Cc: Salgado, Nancy; Kemper, William; Chung, Pong; Rahn, David
Subject:
James A. FitzPatrick Nuclear Power Plant, ME1819, LAR-Follow-up Request for Information (RAIs) from EICB By application dated July 31, 2009, Entergy proposed license amendment to change James A Fitzpatrick Nuclear Power Plant (JAFNPP), Technical Specifications (TSs). The proposed change revises the TS and associated Bases to modify the TS Surveillance Requirements (SR) for testing of the Residual Heat Removal System Shutdown Cooling (SDC) mode Containment Isolation, Reactor Pressure - High Function by replacing the current requirement to perform TS SR 3.3.6.1.3, perform channel calibration with TS SRs 3.3.6.1.1 perform channel check, 3.3.6.1.2, perform channel functional test, 3.3.6.1.4, calibrate the trip units, and 3.3.6.1.5, perform channel calibration. This change was needed to support the plant modification to increase the reliability of SDC isolation logic by changing the source of the reactor pressure high input signal.
The NRC Instrumentation and Controls Branch (EICB) has reviewed the supplemental submission dated March 5, 2010, responding to the previous RAIs and has determined that the following additional information is needed to complete the review. There was a tele-conference between the NRC staff and JAFNPP on April 5, 2010, and the staff's concerns regarding follow-up RAIs were discussed.
The follow-up RAIs are provided below:
JAMES A FITZPATRICK NUCLEAR POWER PLANT, REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT RELATED TO SDC SYSTEM ISOLATION, REACTOR PRESSURE - HIGH (TAC NO. ME1819)
- 1. In attachment 1, on page 3, of the licensee's RAI response letter dated March 5, 2010 (JAFP-10-0033), it states in the first paragraph:
Following performanceto review the completed procedure to ensure acceptance criteria was satisfied and that As-Found and As-left values are within their required tolerance.
And in the second paragraph, it states:
If a Condition Report documents that an instrument failed to meet Level 1 acceptance criteria and could not be restored to within tolerance, the instrument would be declared INOPERABLE and the appropriate Condition associated with the applicable Limiting Condition for Operation (LCO) would be entered.
- a. Clarify the use of the terms and provide the values of the acceptance criteria, the required tolerances, and Level 1 acceptance criteria.
- b. Provide the detailed calculation and/or determination of As-Found and As-Left setting tolerances of the entire instrument loop.
- 2. In attachment 2, section 8.2.3, of the licensee's RAI response, it states:
Use of the reactor steam dome pressure measurement (ATTS) to provide the SDC isolation function will result in the utilization of an instrument loop that has a larger instrument uncertainty than originally provided by the pressure switches.
The licensee calculated the allowable value (section 6.5, attachment 2 of the RAI response) by applying the method 3 of ISA-RP67.04.02-2000. The licensee also calculated the limiting trip setpoint LTS = EAL - CU (section 6.4) with a round up margin of 0.72 psig (section 6.3.1). However, the round up of AVTSMChannel from +/-14.67 psig to +/-15 psig increases the allowance for instrument channel deviation (section 6.3.1); thus is less conservative and cannot be counted as an addition margin.
Explain how you can ensure that the field trip setpoint is conservative with respect to the analytical value (AL) with method 3 and with such a small margin in the LTS calculation.
- 3. In attachment 2, Table 1, of the licensee's RAI response, it states that the humidity, radiation, and temperature effects for the total loop uncertainty calculation of pressure transmitters and ATTS under LOCA and HELB conditions are same as those under normal condition. This statement is based on assumption 1.2.6. Assumption 1.2.6 states that DBD-010 (Ref 4.2.11) identifies the SDC Isolation function as not having any accident mitigating functions. However, according to TS Table 3.3.6.1-1 (page 5 of 6), function 6a SDC Isolation, Reactor Pressure - Hi is used to initiate a primary containment isolation function. Assumption 1.2.6 seems to contradict with this TS requirement. Please provide the following:
- a. Where the pressure transmitter 02-3PT-55A/D is located (inside or outside the primary containment)?
- b. What are the worst-case environmental conditions at the locations for the transmitters and ATTS?
- c. What are the worst-case environmental conditions under which the SDC isolation valves are required to be actuated?
- d. Provide a clarifying description regarding the conditions under which the function of this instrument channel is required when using the SDC line that resolves the apparent contradiction between assumption 1.2.6 and the TS requirement of function 6a in the TS Table 3.3.6.1-1 (page 5 of 6).
- e. Provide copies of the source documents that justify the values for seismic, radiation, humidity, and temperature values used in the calculation, JAF-CALC-NBS-02052.
==============================
Please contact me, if you need additional clarification of this request. If not, provide a firm commitment for the response to this request.
Bhalchandra K. Vaidya Licensing Project Manager NRC/NRR/DORL/LPL1-1 (301)-415-3308 (O) bhalchandra.vaidya@nrc.gov
E-mail Properties Mail Envelope Properties ()
Subject:
James A. FitzPatrick Nuclear Power Plant, ME1819, LAR-Follow-up Request for Information (RAIs) from EICB Sent Date: 04/07/2010 3:15:13 PM Received Date: 04/08/2010 7:23:00 AM From: Vaidya, Bhalchandra Created By: Bhalchandra.Vaidya@nrc.gov Recipients:
EDorman@entergy.com ('Dorman, Eugene')
Tracking Status: None JPechac@entergy.com ('Pechacek, Joseph')
Tracking Status: None Nancy.Salgado@nrc.gov (Salgado, Nancy)
Tracking Status: None William.Kemper@nrc.gov (Kemper, William)
Tracking Status: None Pong.Chung@nrc.gov (Chung, Pong)
Tracking Status: None David.Rahn@nrc.gov (Rahn, David)
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 28504 04/07/2010 Options Expiration Date:
Priority: olImportanceNormal ReplyRequested: False Return Notification: False Sensitivity: olNormal Recipients received: