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| {{#Wiki_filter:Michael P. Gallagher Exelon Generation Vice President. License Renewal Exelon Nuclear 200 Exelon Way RS-15-256 Kennett Square. PA 19348 610 765 5958 Office 610 765 5956 Fax www.exeloncorp.com michaelp.gallagher@exeloncorp.com 10 CFR 50 10 CFR 51 10 CFR 54 October 8, 2015 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 | | {{#Wiki_filter:Michael P. Gallagher Exelon Generation Vice President. |
| | License Renewal Exelon Nuclear 200 Exelon Way RS-15-256 Kennett Square. PA 19348 610 765 5958 Office 610 765 5956 Fax www.exeloncorp.com michaelp.gallagher@exeloncorp.com 10 CFR 50 10 CFR 51 10 CFR 54 October 8, 2015 U.S. Nuclear Regulatory Commission Attention: |
| | Document Control Desk Washington, DC 20555-0001 |
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| ==Subject:== | | ==Subject:== |
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| ==References:== | | ==References:== |
| LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-37 4 Response to NRC Request for Additional Information, Set 11, dated September 14, 2015 related to the LaSalle County Station, Units 1 and 2, License Renewal Application (TAC Nos. MF5347 and MF5346) 1. Letter from Michael P. Gallagher, Exelon Generation Company LLC (Exelon), to NRC Document Control Desk, dated December 9, 2014, "Application for Renewed Operating Licenses" 2. Letter from Jeffrey S. Mitchell, US NRC to Michael P. Gallagher, Exelon, dated September 14, 2015, "Requests for Additional Information for the Review of the LaSalle County Station, Units 1 and 2 License Renewal Application -Set 11 (TAC Nos. MF5347 and MF5346)" In Reference 1, Exelon Generation Company, LLC (Exelon) submitted the License Renewal Application (LRA) for the LaSalle County Station (LSCS), Units 1 and 2. In Reference 2, the NRC requested additional information to support staff review of the LRA. Enclosure A contains the response to these requests for additional information. Enclosure B contains updates to sections of the LRA affected by the response. There are no new or revised regulatory commitments contained in this letter. | | |
| October 8, 2015 U.S. Nuclear Regulatory Commission Page 2 If you have any questions, please contact Mr. John Hufnagel, Licensing Lead, LaSalle License Renewal Project, at 610-765-5829. I declare under penalty of perjury that the foregoing is true and correct. Executed on ltJ-o1-2o!S-Respectfully, Vice President -License Renewal Projects Exelon Generation Company, LLC | | LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-37 4 Response to NRC Request for Additional Information, Set 11, dated September 14, 2015 related to the LaSalle County Station, Units 1 and 2, License Renewal Application (TAC Nos. MF5347 and MF5346) 1. Letter from Michael P. Gallagher, Exelon Generation Company LLC (Exelon), |
| | to NRC Document Control Desk, dated December 9, 2014, "Application for Renewed Operating Licenses" |
| | : 2. Letter from Jeffrey S. Mitchell, US NRC to Michael P. Gallagher, Exelon, dated September 14, 2015, "Requests for Additional Information for the Review of the LaSalle County Station, Units 1 and 2 License Renewal Application |
| | -Set 11 (TAC Nos. MF5347 and MF5346)" |
| | In Reference 1, Exelon Generation |
| | : Company, LLC (Exelon) submitted the License Renewal Application (LRA) for the LaSalle County Station (LSCS), Units 1 and 2. In Reference 2, the NRC requested additional information to support staff review of the LRA. Enclosure A contains the response to these requests for additional information. |
| | Enclosure B contains updates to sections of the LRA affected by the response. |
| | There are no new or revised regulatory commitments contained in this letter. |
| | October 8, 2015 U.S. Nuclear Regulatory Commission Page 2 If you have any questions, please contact Mr. John Hufnagel, Licensing Lead, LaSalle License Renewal Project, at 610-765-5829. |
| | I declare under penalty of perjury that the foregoing is true and correct. |
| | Executed on ltJ-o1-2o!S-Respectfully, Vice President |
| | -License Renewal Projects Exelon Generation |
| | : Company, LLC |
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| ==Enclosures:== | | ==Enclosures:== |
| A: Response to Set 11 Requests for Additional Information B: LSCS License Renewal Application Updates cc: Regional Administrator-NRC Region Ill NRC Project Manager (Safety Review), NRR-DLR NRC Project Manager (Environmental Review), NRR-DLR NRC Project Manager, NRR-DORL-LaSalle County Station NRC Senior Resident Inspector, LaSalle County Station Illinois Emergency Management Agency -Division of Nuclear Safety RS-15-256 Enclosure A Page 1 of 2 Enclosure A Response to Set 11 Request for Additional Information Related to various sections of the LaSalle County Station (LSCS) License Renewal Application (LRA) RAI 4.2.7-1a RS-15-256 Enclosure A Page 2 of 2 RAI 4.2.7-1a | | |
| | A: Response to Set 11 Requests for Additional Information B: LSCS License Renewal Application Updates cc: Regional Administrator-NRC Region Ill NRC Project Manager (Safety Review), |
| | NRR-DLR NRC Project Manager (Environmental Review), |
| | NRR-DLR NRC Project Manager, NRR-DORL-LaSalle County Station NRC Senior Resident Inspector, LaSalle County Station Illinois Emergency Management Agency -Division of Nuclear Safety RS-15-256 Enclosure A Page 1 of 2 Enclosure A Response to Set 11 Request for Additional Information Related to various sections of the LaSalle County Station (LSCS) |
| | License Renewal Application (LRA) |
| | RAI 4.2.7-1a |
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| | RS-15-256 Enclosure A Page 2 of 2 RAI 4.2.7-1a |
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| ==Background:== | | ==Background:== |
| By letter dated August 6, 2015, the applicant responded to RAI 4.2.7-1 that requested sufficient information on the parameters used in the reactor vessel reflood thermal shock analysis (LRA Section 4.2.7). In its response, the applicant indicated that the maximum initial flaw depth postulated in the analysis is 5.2 percent of the reactor vessel wall thickness per ASME Code Section XI, Table IWB-3510-1. Issue: License Renewal Application (LRA) Table 4.2.7-2 and associated discussion in LRA Section 4.2.7 describe applied stress intensity factor values (KI-applied) at 52 percent of the reactor vessel wall thickness during the recirculation line break transient. The LRA also compares these KI-applied values with the adjusted fracture toughness values (KIc/1.414) of the LSCS limiting reactor vessel material during the transient. It is not clear to the staff why LRA Table 4.2.7-2 and associated discussion in Section 4.2.7 refer to the location at 52 percent of the reactor wall thickness for the fracture toughness comparison rather than 5.2 percent of the wall thickness that corresponds to the postulated initial flaw depth. In addition, the staff noted that LRA Section 4.2.7 does not provide the KI-applied value and the allowable fracture toughness value (KIc/1.414) that were evaluated in the applicant's analysis for N6 low pressure coolant injection nozzles. Request: 1. Clarify why LRA Table 4.2.7-2 and associated discussion in Section 4.2.7 assume a flaw depth of 52 percent of the wall thickness which is different from the postulated initial flaw depth per ASME Code Section XI, Table IWB-3510-1. 2. Provide the KI-applied value and the allowable fracture toughness value (KIc/1.414) that were evaluated in the applicant's analysis for N6 low pressure coolant injection nozzles. Exelon Response: 1. The correct flaw depth is 0.052T, which is 5.2 percent of the wall thickness, T. LRA Table 4.2.7-2 and the discussion in LRA Section 4.2.7 have typographical errors that have been corrected, as shown in Enclosure B. 2. At a flaw depth of 0.052T, KI-applied is approximately 35 ksiinch. This is significantly less than the allowable fracture toughness value (KIc /1.414) of 141 ksiinch. Therefore, adequate margin against non-ductile fracture has been demonstrated for the Unit 1 and Unit 2 N6 LPCI nozzles. These values are added to LRA Section 4.2.7, as shown in Enclosure B. | | By letter dated August 6, 2015, the applicant responded to RAI 4.2.7-1 that requested sufficient information on the parameters used in the reactor vessel reflood thermal shock analysis (LRA Section 4.2.7). In its response, the applicant indicated that the maximum initial flaw depth postulated in the analysis is 5.2 percent of the reactor vessel wall thickness per ASME Code Section XI, Table IWB-3510-1. Issue: License Renewal Application (LRA) Table 4.2.7-2 and associated discussion in LRA Section 4.2.7 describe applied stress intensity factor values (KI-applied) at 52 percent of the reactor vessel wall thickness during the recirculation line break transient. The LRA also compares these KI-applied values with the adjusted fracture toughness values (KIc/1.414) of the LSCS limiting reactor vessel material during the transient. It is not clear to the staff why LRA Table 4.2.7-2 and associated discussion in Section 4.2.7 refer to the location at 52 percent of the reactor wall thickness for the fracture toughness comparison rather than 5.2 percent of the wall thickness that corresponds to the postulated initial flaw depth. In addition, the staff noted that LRA Section 4.2.7 does not provide the KI-applied value and the allowable fracture toughness value (KIc/1.414) that were evaluated in the applicant's analysis for N6 low pressure coolant injection nozzles. |
| | Request: 1. Clarify why LRA Table 4.2.7-2 and associated discussion in Section 4.2.7 assume a flaw depth of 52 percent of the wall thickness which is different from the postulated initial flaw depth per ASME Code Section XI, Table IWB-3510-1. 2. Provide the KI-applied value and the allowable fracture toughness value (KIc/1.414) that were evaluated in the applicant's analysis for N6 low pressure coolant injection nozzles. |
| | Exelon Response: 1. The correct flaw depth is 0.052T, which is 5.2 percent of the wall thickness, T. LRA Table 4.2.7-2 and the discussion in LRA Section 4.2.7 have typographical errors that have been corrected, as shown in Enclosure B. 2. At a flaw depth of 0.052T, K I-applied is approximately 35 ksiinch. This is significantly less than the allowable fracture toughness value (K Ic /1.414) of 141 ksiinch. Therefore, adequate margin against non-ductile fracture has been demonstrated for the Unit 1 and Unit 2 N6 LPCI nozzles. These values are added to LRA Section 4.2.7, as shown in Enclosure B. |
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| | RS-15-256 Enclosure B Page 1 of 3 Enclosure B LSCS License Renewal Application Updates Resulting from the Response to the following RAI: |
| | RAI 4.2.7-1a Note: To facilitate understanding, portions of the LRA have been repeated in this Enclosure, with revisions indicated. Previously submitted information is shown in normal font. Changes are highlighted with bolded italics for inserted text and strikethroughs for deleted text. |
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| | RS-15-256 Enclosure B Page 2 of 3 |
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| | As a result of the response to RAI 4.2.7-1a provided in Enclosure A of this letter, the Recirculation Line Break Analysis subsection of LRA Section 4.2.7 and Table 4.2.7-2, on LRA pages 4-53 and 4-54, are revised as shown below in bolded italics to correct three typographical errors: 4.2.7 REACTOR PRESSURE VESSEL REFLOOD THERMAL SHOCK ANALYSIS Recirculation Line Break Analysis In Reference 4.8.10, the Recirculation line break LOCA was evaluated. A summary of this analysis at selected times during the transient is presented in Table 4.2.7-2, but with updated material properties at 54 EFPY. Note that K Ic is determined using crack tip temperature at the maximum allowable crack depth of 0.052T and ART is based on the limiting inside surface (0T) fluence. |
| | Table 4.2.7-2 Crack Stability Analysis for Beltline Shells During Recirculation Line Break Time During Transient (s) 0 25 84 480 1200 3000 Temperature at 0.052T 550 450 450 160 120 80 Limiting 0T 54 EFPY ART |
| | (ºF) 168 168 168 168 168 168 T-ART (ºF) 382 282 282 48 -88 KIc/1.414 (ksiin) 141 141 141 36 29 26 KI-applied at 0.52T0.052T(ksiin) 33 47 20 56 47 24 Margin 4.3 3.0 7.1 0.6 0.6 1.1 Table 4.7-2 4.2.7-2 shows that at times 0, 25, 84, and 3,000 seconds after the start of the transient, the applied stress intensity factor, K I-applied at 0.52T0.052T, is less than the available toughness, K Ic/1.414, calculated as a function of crack tip temperature and the bounding 0T fluence level. However, at 480 seconds and 1,200 seconds after the start of the transient, the applied stress intensity factor exceeds the available toughness value by 40 percent, which would indicate the initiation and propagation of a crack during that time period. However, since fluence actually attenuates as a function of distance from the inside surface, further analysis may be performed to take into account the reduced fluence as a function of crack depth. If crack initiation still occurs, the cracking must be shown to arrest prior to reaching 0.75T in order to meet the acceptance criteria. |
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| RS-15-256 Enclosure B Page 1 of 3 Enclosure B LSCS License Renewal Application Updates Resulting from the Response to the following RAI: RAI 4.2.7-1a Note: To facilitate understanding, portions of the LRA have been repeated in this Enclosure, with revisions indicated. Previously submitted information is shown in normal font. Changes are highlighted with bolded italics for inserted text and strikethroughs for deleted text. | | RS-15-256 Enclosure B Page 3 of 3 |
| RS-15-256 Enclosure B Page 2 of 3 As a result of the response to RAI 4.2.7-1a provided in Enclosure A of this letter, the Recirculation Line Break Analysis subsection of LRA Section 4.2.7 and Table 4.2.7-2, on LRA pages 4-53 and 4-54, are revised as shown below in bolded italics to correct three typographical errors: 4.2.7 REACTOR PRESSURE VESSEL REFLOOD THERMAL SHOCK ANALYSIS Recirculation Line Break Analysis In Reference 4.8.10, the Recirculation line break LOCA was evaluated. A summary of this analysis at selected times during the transient is presented in Table 4.2.7-2, but with updated material properties at 54 EFPY. Note that KIc is determined using crack tip temperature at the maximum allowable crack depth of 0.052T and ART is based on the limiting inside surface (0T) fluence. Table 4.2.7-2 Crack Stability Analysis for Beltline Shells During Recirculation Line Break Time During Transient (s) 0 25 84 480 1200 3000 Temperature at 0.052T 550 450 450 160 120 80 Limiting 0T 54 EFPY ART (ºF) 168 168 168 168 168 168 T-ART (ºF) 382 282 282 48 -88 KIc/1.414 (ksiin) 141 141 141 36 29 26 KI-applied at 0.52T0.052T(ksiin) 33 47 20 56 47 24 Margin 4.3 3.0 7.1 0.6 0.6 1.1 Table 4.7-2 4.2.7-2 shows that at times 0, 25, 84, and 3,000 seconds after the start of the transient, the applied stress intensity factor, KI-applied at 0.52T0.052T, is less than the available toughness, KIc/1.414, calculated as a function of crack tip temperature and the bounding 0T fluence level. However, at 480 seconds and 1,200 seconds after the start of the transient, the applied stress intensity factor exceeds the available toughness value by 40 percent, which would indicate the initiation and propagation of a crack during that time period. However, since fluence actually attenuates as a function of distance from the inside surface, further analysis may be performed to take into account the reduced fluence as a function of crack depth. If crack initiation still occurs, the cracking must be shown to arrest prior to reaching 0.75T in order to meet the acceptance criteria.
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| RS-15-256 Enclosure B Page 3 of 3 As a result of the response to RAI 4.2.7-1a provided in Enclosure A of this letter, the Beltline Nozzles subsection of LRA Section 4.2.7 on LRA page 4-56 is revised as shown below: Beltline Nozzles The N6 Low Pressure Coolant Injection (LPCI) nozzles are selected as the limiting beltline nozzles since the Emergency Core Coolant System (ECCS) injects coolant through this nozzle following a LOCA. Consequently, there is a severe thermal transient at this location following the design basis LOCA. The finite element analysis (FEA) results are documented in the LSCS Unit 1 and Unit 2 RPV stress analyses. The bounding temperature distribution in the LPCI Nozzle analyzed for both units is selected. A thermal stress distribution is developed from this temperature profile, which is then used to calculate a stress intensity factor. Since there is negligible pressure in the RPV following the LOCA event and since the location of the highest thermal stresses is remote from welds, there is no KI from internal pressure or weld residual stress. A flat plate KI solution for a point load acting at an arbitrary location along the crack front is selected. The point load is replaced with (x)dx then integrated over the crack depth in order to obtain the KI caused by the thermal stress distribution. The same acceptance criteria as described for the beltline shells are applied for the nozzle. The resulting KI-applied value is approximately 35 ksiinch at a flaw depth of 0.052T. This is significantly less than the allowable fracture toughness value, (KIc/1.414) of 141 ksiinch,. tTherefore, demonstrating adequate margin against non-ductile fracture has been demonstrated for the Unit 1 and Unit 2 N6 LPCI nozzles.}}
| | As a result of the response to RAI 4.2.7-1a provided in Enclosure A of this letter, the Beltline Nozzles subsection of LRA Section 4.2.7 on LRA page 4-56 is revised as shown below: |
| | Beltline Nozzles The N6 Low Pressure Coolant Injection (LPCI) nozzles are selected as the limiting beltline nozzles since the Emergency Core Coolant System (ECCS) injects coolant through this nozzle following a LOCA. Consequently, there is a severe thermal transient at this location following the design basis LOCA. The finite element analysis (FEA) results are documented in the LSCS Unit 1 and Unit 2 RPV stress analyses. The bounding temperature distribution in the LPCI Nozzle analyzed for both units is selected. A thermal stress distribution is developed from this temperature profile, which is then used to calculate a stress intensity factor. Since there is negligible pressure in the RPV following the LOCA event and since the location of the highest thermal stresses is remote from welds, there is no K I from internal pressure or weld residual stress. A flat plate K I solution for a point load acting at an arbitrary location along the crack front is selected. The point load is replaced with (x)dx then integrated over the crack depth in order to obtain the K I caused by the thermal stress distribution. The same acceptance criteria as described for the beltline shells are applied for the nozzle. The resulting K I-applied value is approximately 35 ksiinch at a flaw depth of 0.052T. This is significantly less than the allowable fracture toughness value, (KIc/1.414) of 141 ksiinch,. tTherefore, demonstrating adequate margin against non-ductile fracture has been demonstrated for the Unit 1 and Unit 2 N6 LPCI nozzles.}} |
Letter Sequence Response to RAI |
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TAC:MF5346, Control Room Habitability (Approved, Closed) TAC:MF5347, Control Room Habitability (Approved, Closed) |
Results
Other: ML15104A782, ML15196A045, ML15196A115, ML16202A033, RS-15-193, Responds to NRC Requests for Additional Information, Set 5, Dated July 7, 2015 Related to the License Renewal Application, RS-15-194, Responds to NRC Requests for Additional Information, Set 6, Dated July 7, 2015 Related to the License Renewal Application, RS-15-305, Corrections to the License Renewal Application Dated December 9, 2014, RS-15-306, Submittal of 10 CFR 54.21(b) Annual Amendment to the License Renewal Application, RS-16-033, Update to Commitment 47 Related to the License Renewal Application, RS-16-068, Comments on the Safety Evaluation Report with Open Items, Related to the License Renewal Application, RS-16-128, Second 10 CFR 54.21(b) Annual Amendment to the License Renewal Application
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MONTHYEARML15104A7822015-05-0808 May 2015 Scoping and Screening Methodology Audit Report Regarding LaSalle County Station, Units 1 and 2 Project stage: Other ML15111A1372015-05-14014 May 2015 Requests for Additional Information for the Review of the LaSalle County Station, Units 1 and 2 License Renewal Application - Set 1 (TAC Nos. MF5347 and MF5346) Project stage: RAI ML15125A1982015-05-29029 May 2015 Requests for Additional Information for the Review of the LaSalle County Station, Units 1 and 2 License Renewal Application - Set 2 (TAC Nos. MF5347 and MF5346) Project stage: RAI ML15131A4132015-06-0808 June 2015 Requests for Additional Information for the Review of the LaSalle County Station, Units 1 and 2 License Renewal Application - Set 3 (TAC Nos. MF5347 and MF5346) Project stage: RAI ML15140A1922015-06-0808 June 2015 Summary of Telephone Conference Call Held on May 13, 2015, Between the U.S. Nuclear Regulatory Commission and Exelon Generation Co., LLC, Concerning Requests for Additional Information, Set 2 Pertaining to the Lasalle County Station License Project stage: RAI ML15146A2622015-06-19019 June 2015 Requests for Additional Information for the Review of the LaSalle County Station, Units 1 and 2 License Renewal Application-Set 4 (TAC Nos. MF5347 and MF5346) Project stage: RAI RS-15-165, Response to NRC Requests for Additional Information, Set 2, Dated May 29, 2015 Related to the License Renewal Application2015-06-25025 June 2015 Response to NRC Requests for Additional Information, Set 2, Dated May 29, 2015 Related to the License Renewal Application Project stage: Response to RAI RS-15-171, Response to NRC Requests for Additional Information, Set 3, Dated June 8, 2015, Related to the License Renewal Application2015-07-0101 July 2015 Response to NRC Requests for Additional Information, Set 3, Dated June 8, 2015, Related to the License Renewal Application Project stage: Response to RAI ML15159A9002015-07-0606 July 2015 Telephone Conference Call Held on May 20, 2015, Between the U.S. Nuclear Regulatory Commission and Exelon Generation Co., LLC, Requests for Additional Information, Set 3 Pertaining to the LaSalle County Station License Renewal Application ( Project stage: RAI ML15163A0712015-07-0707 July 2015 Requests for Additional Information for the Review of the LaSalle County Station, Units 1 and 2 License Renewal Application - Set 6 (TAC Nos. MF5347 and MF5346) Project stage: RAI ML15159A2082015-07-0707 July 2015 Requests for Additional Information for the Review of the LaSalle County Station, Units 1 and 2 License Renewal Application - Set 5 (TAC Nos. MF5347 and MF5346) Project stage: RAI RS-15-180, Response to NRC Requests for Additional Information, Set 4, Dated June 19, 2015 Related to the License Renewal Application2015-07-15015 July 2015 Response to NRC Requests for Additional Information, Set 4, Dated June 19, 2015 Related to the License Renewal Application Project stage: Response to RAI RS-15-198, Request for Schedule Change Related to Advisory Committee on Reactor Safeguards (ACRS) Subcommittee Review of License Renewal Application (TAC Nos. MF5347 and MF5346)2015-07-16016 July 2015 Request for Schedule Change Related to Advisory Committee on Reactor Safeguards (ACRS) Subcommittee Review of License Renewal Application (TAC Nos. MF5347 and MF5346) Project stage: Request ML15196A5292015-07-27027 July 2015 Requests for Additional Information for the Review of the Lasalle County Station, Units 1 and 2 License Renewal Application - Set 7 (Tac Nos. MF5347 and MF5346) Project stage: RAI RS-15-194, Responds to NRC Requests for Additional Information, Set 6, Dated July 7, 2015 Related to the License Renewal Application2015-08-0606 August 2015 Responds to NRC Requests for Additional Information, Set 6, Dated July 7, 2015 Related to the License Renewal Application Project stage: Other RS-15-193, Responds to NRC Requests for Additional Information, Set 5, Dated July 7, 2015 Related to the License Renewal Application2015-08-0606 August 2015 Responds to NRC Requests for Additional Information, Set 5, Dated July 7, 2015 Related to the License Renewal Application Project stage: Other ML15204A6302015-08-18018 August 2015 Requests for Additional Information for the Review of the LaSalle County Station Units 1 & 2 License Renewal Application - Set 9 (TAC Nos. MF5347 and MF5346) Project stage: RAI RS-15-223, Response to NRC Requests for Additional Information, Set 7, Dated July 27, 2015; and a Correction to Information Associated with the Set 2 Response to RAI 8.2.1.20-2, Related to the Renewal Application2015-08-26026 August 2015 Response to NRC Requests for Additional Information, Set 7, Dated July 27, 2015; and a Correction to Information Associated with the Set 2 Response to RAI 8.2.1.20-2, Related to the Renewal Application Project stage: Response to RAI ML15229A0192015-08-27027 August 2015 Requests for Additional Information for the Review of the LaSalle County Station, Units 1 and 2 License Renewal Application - Set 10 (TAC Nos. MF5347 and MF5346) Project stage: RAI ML15217A5412015-08-28028 August 2015 June 9, 2015, Summary of Telecon Held Between the NRC and Exelon Generation Co., LLC, Concerning Request for Additional Information Set 5 Pertaining to the LaSalle County Station License Renewal Application (TAC Nos. MF5347 and MF5346) Project stage: RAI ML15217A5642015-08-28028 August 2015 June 3, 2015, Summary of Telecon Held Between the NRC and Exelon Generation Co., LLC, Concerning Request for Additional Information Set 4 Pertaining to the LaSalle County Station License Renewal Application (Tac Nos. MF5347 and MF5346) Project stage: RAI ML15217A5752015-08-28028 August 2015 June 10, 2015, Summary of Telecon Held Between the NRC and Exelon Generation Co., LLC, Concerning Request for Additional Information Set 4 Pertaining to the LaSalle County Station License Renewal Application (TAC Nos. MF5347 and MF5346) Project stage: RAI ML15219A2772015-08-28028 August 2015 June 23, 2015, Summary of Telecon Held Between the NRC and Exelon Generation Co., LLC, Concerning Request for Additional Information Set 6 Pertaining to the LaSalle County Station License Renewal Application (TAC Nos. MF5347 and MF5346) Project stage: RAI ML15222A0062015-08-28028 August 2015 August 5, 2015, Summary of Telecon Held Between the NRC and Exelon Generation Co., LLC, Concerning Request for Additional Information Set 9 Pertaining to the LaSalle County Station License Renewal Application (TAC Nos. MF5347 and MF5346) Project stage: RAI ML15195A3382015-08-28028 August 2015 Requests for Additional Information for the Review of the LaSalle County Station, Units 1 and 2 License Renewal Application-Set 8 (TAC Nos. MF5347 and MF5346) Project stage: RAI ML15222A0082015-08-28028 August 2015 July 22, 2015, Summary of Telecon Held Between the NRC and Exelon Generation Co., LLC, Concerning Request for Additional Information Set 8 Pertaining to the LaSalle County Station License Renewal Application (TAC Nos. MF5347 and MF5346) Project stage: RAI ML15222A0152015-08-28028 August 2015 July 8, 2015, Summary of Telecon Held Between the NRC and Exelon Generation Co., LLC, Concerning Request for Additional Information Set 7 Pertaining to the LaSalle County Station License Renewal Application (TAC Nos. MF5347 and MF5346) Project stage: RAI ML15224A9352015-08-28028 August 2015 August 11, 2015, Summary of Telecon Held Between the NRC and Exelon Generation Co., LLC, Concerning Request for Additional Information Set 9 Pertaining to the LaSalle County Station License Renewal Application (TAC Nos. MF5347 and MF5346) Project stage: RAI ML15244B3532015-09-14014 September 2015 RAI for the Review of the LaSalle County Station, Units 1 and 2 License Renewal Application - Set 11 (TAC Nos. MF5347 and MF5346) Project stage: RAI RS-15-232, Response to NRC Requests for Additional Information, Set 9, Dated August 18, 2015 Related to the License Renewal Application2015-09-15015 September 2015 Response to NRC Requests for Additional Information, Set 9, Dated August 18, 2015 Related to the License Renewal Application Project stage: Response to RAI RS-15-238, Response to NRC Requests for Additional Information, Set 10, Dated August 27, 2015 Related to License Renewal Application2015-09-17017 September 2015 Response to NRC Requests for Additional Information, Set 10, Dated August 27, 2015 Related to License Renewal Application Project stage: Response to RAI ML15196A1152015-09-22022 September 2015 Aging Management Programs Audit Report Regarding Lasalle County Station, Units 1 and 2, Project stage: Other ML15196A0452015-09-22022 September 2015 Aging Management Programs Audit Report Regarding Lasalle County Station, Units 1 and 2, (TAC Nos. MF5347 and MF5346). Cover Letter Project stage: Other RS-15-239, Response to NRC Requests for Additional Information, Set 8, Dated August 28, 2015 Related to the License Renewal Application2015-09-28028 September 2015 Response to NRC Requests for Additional Information, Set 8, Dated August 28, 2015 Related to the License Renewal Application Project stage: Response to RAI RS-15-256, Response to NRC Request for Additional Information, Set 11, Dated September 14, 2015 Related to the License Renewal Application2015-10-0808 October 2015 Response to NRC Request for Additional Information, Set 11, Dated September 14, 2015 Related to the License Renewal Application Project stage: Response to RAI ML15208A0522015-10-22022 October 2015 Schedule Revision for the Review of the Lasalle County Station License Renewal Application (TAC Nos. MF5347 & MF5346) Project stage: Approval ML15271A0212015-10-23023 October 2015 Requests for Additional Information for the Review of the Lasalle County Station, Units 1 and 2 License Renewal Application-Set 12 (TAC Nos. MF5347 and MF5346) Project stage: RAI RS-15-281, Response to NRC Requests for Additional Information, Set 12, Dated October 23, 2015 Related to the License Renewal Application2015-10-29029 October 2015 Response to NRC Requests for Additional Information, Set 12, Dated October 23, 2015 Related to the License Renewal Application Project stage: Response to RAI ML15300A3662015-11-0303 November 2015 Requests for Additional Information for the Review of the LaSalle County Station, Units 1 and 2 License Renewal Application - Set 13 (TAC Nos. MF5347 and MF5346) Project stage: RAI RS-15-305, Corrections to the License Renewal Application Dated December 9, 20142015-12-0202 December 2015 Corrections to the License Renewal Application Dated December 9, 2014 Project stage: Other RS-15-306, Submittal of 10 CFR 54.21(b) Annual Amendment to the License Renewal Application2015-12-0202 December 2015 Submittal of 10 CFR 54.21(b) Annual Amendment to the License Renewal Application Project stage: Other RS-15-292, Response to NRC Requests for Additional Information, Set 13, Dated November 3, 2015 Related to the License Renewal Application2015-12-10010 December 2015 Response to NRC Requests for Additional Information, Set 13, Dated November 3, 2015 Related to the License Renewal Application Project stage: Response to RAI ML15272A4002015-12-11011 December 2015 Summary of Teleconference Held on September 24, 2015, Between the NRC and Exelon Generation Co., LLC, Concerning RAI Set 10 Response Pertaining to the LaSalle County Station License Renewal Application (TAC Nos. MF5347 and MF5346) Project stage: RAI ML15301A1892015-12-14014 December 2015 Request for Additional Information for the Review of the LaSalle County Station, Units 1 & 2 License Renewal Application - Set 14 (TAC Nos. MF5347 and MF5346) Project stage: RAI RS-16-003, Responses to NRC Requests for Additional Information, Set 14, Dated December 14, 2015, and Two Additional Commitment Implementation Schedule Clarifications, Related to the License Renewal Application2016-01-0707 January 2016 Responses to NRC Requests for Additional Information, Set 14, Dated December 14, 2015, and Two Additional Commitment Implementation Schedule Clarifications, Related to the License Renewal Application Project stage: Response to RAI ML15357A2812016-01-0707 January 2016 Summary of Teleconference Held on December 22, 2015, Between the NRC and Exelon Generation Co., LLC, Concerning the LaSalle County Station License Renewal Application (Tac Nos. MF5347 and MF5346) Project stage: Meeting RS-16-007, Supplemental Information Associated with Implementation of BWRVIP-25, Core Plate Inspection and Flaw Evaluation Guidelines, Related to the License Renewal Application2016-01-14014 January 2016 Supplemental Information Associated with Implementation of BWRVIP-25, Core Plate Inspection and Flaw Evaluation Guidelines, Related to the License Renewal Application Project stage: Supplement ML16021A3252016-01-29029 January 2016 Summary of Teleconference Held on January 21, 2016, Between the NRC and Exelon Generation Co., LLC, Concerning RAI 4.2.10-1 Response Project stage: RAI RS-16-033, Update to Commitment 47 Related to the License Renewal Application2016-02-0101 February 2016 Update to Commitment 47 Related to the License Renewal Application Project stage: Other ML15344A3542016-02-16016 February 2016 Requests for Additional Information for the Review of the Lasalle County, Units 1 and 2 License Renewal Application Set 15 (TAC Nos. MF5347 and MF5346) Project stage: RAI 2015-07-16
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Category:Letter
MONTHYEARIR 05000373/20230042024-01-24024 January 2024 County Station - Integrated Inspection Report 05000373/2023004 and 05000374/2023004 ML24024A1332024-01-24024 January 2024 Confirmation of Initial License Examination IR 05000373/20230122024-01-18018 January 2024 County Station - Biennial Problem Identification and Resolution Inspection Report 05000373/2023012 and 05000374/2023012 ML23354A2902024-01-0505 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0028 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23360A6082023-12-27027 December 2023 County Station Request for Information for NRC Commercial Grade Dedication Inspection: Inspection Report 05000373/2024010 and 05000374/2024010 ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums RS-23-120, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information IR 05000373/20230032023-11-0909 November 2023 County Station Integrated Inspection Report 05000373/2023003, 05000374/2023003, and 07200070/2023001 ML23286A2602023-11-0808 November 2023 Issuance of Amendment Nos. 260 and 245 to Renewed Facility Operating Licenses Relocation of Pressure and Temperature Limit Curves to the Pressure Temperature Report IR 05000373/20234012023-11-0707 November 2023 County Station Security Baseline Inspection Report 05000373/2023401 and 05000374/2023401 RS-23-103, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans IR 05000374/20230102023-10-11011 October 2023 NRC Inspection Report 05000374/2023010 IR 05000373/20233012023-09-15015 September 2023 Errata to NRC Initial License Examination Report 05000373/2023301; 05000374/2023301 RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor ML23212A9012023-08-0303 August 2023 Regulatory Audit Report to Support the Review of the Amendments to Relocation of the Pressure Temperature Limit Curves to the Pressure and Temperature Limits Report IR 05000373/20230022023-08-0101 August 2023 County Station - Integrated Inspection Report 05000373/2023002 and 05000374/2023002 ML23208A3182023-07-27027 July 2023 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and RFI RS-23-084, Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis2023-07-24024 July 2023 Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis ML23192A5272023-07-12012 July 2023 NRC Initial License Examination Report 05000373/2023301; 05000374/2023301 ML23186A2062023-07-0606 July 2023 Information Request for a NRC Post-Approval Site Inspection for License Renewal 05000374/2023010 ML23181A1502023-06-30030 June 2023 Combined Response to Request for Additional Information and Supplemental Information in Support of LAR to Relocate Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III IR 05000373/20230112023-06-26026 June 2023 County Station - Quadrennial Fire Protection Team Inspection Report 05000373/2023011 and 05000374/2023011 RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23167A0352023-06-16016 June 2023 Registration of Use of Cask to Store Spent Fuel ML23171A9562023-06-12012 June 2023 Post Exam Ltr RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling IR 05000373/20230012023-05-10010 May 2023 County Station - Integrated Inspection Report 05000373/2023001 and 05000374/2023001 ML23123A2202023-05-0303 May 2023 Relief Request I4R-14 for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection ML23118A3472023-05-0101 May 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Correction of Amendment No. 193 Adoption of TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration EPID L-2022-LLA-0143 ML23121A1612023-05-0101 May 2023 Information Meeting (Open House) with a Question-and-Answer Session to Discuss NRC 2022 End-of-Cycle Plant Performance Assessment of LaSalle County Station, Units 1 and 2 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23081A0382023-04-25025 April 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML23107A1822023-04-18018 April 2023 Operator Licensing Examination Approval Lasalle County Station, May 2023 RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML23073A2182023-03-22022 March 2023 Issuance of Amendment No. 258 to Renewed Facility Operating Licenses Exigent Amendment to Revise Design Basis Related to Seismic Requirements RS-23-048, Exigent Amendment Request to Revise Design Basis Related to Seismic Requirements2023-03-0707 March 2023 Exigent Amendment Request to Revise Design Basis Related to Seismic Requirements ML23061A1632023-03-0303 March 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch 3 IR 05000373/20220062023-03-0101 March 2023 Annual Assessment Letter for LaSalle County Station, Units 1 and 2 (Report 05000373/2022006 and 05000374/2022006) RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023 Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203 RS-23-037, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station2023-02-22022 February 2023 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station ML23024A1372023-02-0303 February 2023 Request for Withholding Information from Public Disclosure for LaSalle County Station, Unit Nos. 1 and 2 ML23031A1972023-01-31031 January 2023 Notification of NRC Fire Protection Team Inspection Request for Information, Inspection Report Nos. 05000373/2023011 and 05000374/2023011 IR 05000373/20220042023-01-31031 January 2023 County Station - Integrated Inspection Report 05000373/2022004 and 05000374/2022004 RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023 Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 2024-01-05
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARRS-23-120, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information RS-23-084, Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis2023-07-24024 July 2023 Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis RS-22-109, Response to Request for Additional Information License Amendments Related to Fuel Storage2022-10-12012 October 2022 Response to Request for Additional Information License Amendments Related to Fuel Storage RS-22-083, Response to Request for Additional Information Related to the License Amendment Request to Change New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Proposed Changes to Technical2022-06-17017 June 2022 Response to Request for Additional Information Related to the License Amendment Request to Change New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Proposed Changes to Technical RS-22-033, Response to Request for Additional Information Regarding Relief Request I4R-13 Relief from Code Examinations for 1B33-F060A and 1B33-F060B Repairs2022-03-0303 March 2022 Response to Request for Additional Information Regarding Relief Request I4R-13 Relief from Code Examinations for 1B33-F060A and 1B33-F060B Repairs RS-22-027, Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated2022-02-23023 February 2022 Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated P NMP1L3447, Constellation Energy Generation, LLC - Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs2022-02-0202 February 2022 Constellation Energy Generation, LLC - Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs JAFP-21-0087, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-09-16016 September 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments RS-21-078, Response to Request for Additional Information for Application to Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, and TSTF-583-T, TSTF-582 Diesel2021-08-19019 August 2021 Response to Request for Additional Information for Application to Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, and TSTF-583-T, TSTF-582 Diesel RS-21-085, Response to Request for Additional Information Regarding License Amendment Request to Incorporate Licensing Topical Report NEDE-33885PA, Revision 1, GNF CRDA Application Methodology (EPID-L-2021-LLA-0016)2021-08-17017 August 2021 Response to Request for Additional Information Regarding License Amendment Request to Incorporate Licensing Topical Report NEDE-33885PA, Revision 1, GNF CRDA Application Methodology (EPID-L-2021-LLA-0016) NMP2L2773, Company - Response to Request for Additional Information2021-06-30030 June 2021 Company - Response to Request for Additional Information JAFP-21-0044, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-06-11011 June 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments RS-21-055, Response to Third Round Request for Additional Information (Rals) for LaSalle License Amendment Request to Adopt Risk Informed Completion Times TSTF- 505, Revision 2, Provide Risk-Informed Extended.2021-05-10010 May 2021 Response to Third Round Request for Additional Information (Rals) for LaSalle License Amendment Request to Adopt Risk Informed Completion Times TSTF- 505, Revision 2, Provide Risk-Informed Extended. JAFP-21-0032, Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting2021-04-20020 April 2021 Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting RS-21-050, Response to Request for Additional Information (RAI) Regarding Request for License Amendment Regarding Ultimate Heat Sink (EPID-L-2020-LLA-0165)2021-04-16016 April 2021 Response to Request for Additional Information (RAI) Regarding Request for License Amendment Regarding Ultimate Heat Sink (EPID-L-2020-LLA-0165) RS-21-045, Response to Request for Additional Information (RAI) Regarding Request for License Amendment Regarding Ultimate Heat Sink (EPID-L-2020-LLA-0165)2021-04-0707 April 2021 Response to Request for Additional Information (RAI) Regarding Request for License Amendment Regarding Ultimate Heat Sink (EPID-L-2020-LLA-0165) RS-21-040, Response to Second Round Request for Additional Information (Rais) for License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2021-03-31031 March 2021 Response to Second Round Request for Additional Information (Rais) for License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RS-21-027, Response to Request for Additional Information Regarding Request for Exemption from Pre-Access Drug and Alcohol Testing Requirements in 10 CFR 26.652021-02-21021 February 2021 Response to Request for Additional Information Regarding Request for Exemption from Pre-Access Drug and Alcohol Testing Requirements in 10 CFR 26.65 ML21022A1302021-01-22022 January 2021 Response to Request for Additional Information Regarding the License Amendment Request to Adopt 10 CFR 50.69 RS-20-136, Response to Request for Additional Information Re License Amendment Requests for Amendments to Renewed Facility OL to Adopt 10CFR50.69 & to Adopt TSTF-505, Rev. 2 (EPID L-2020-LLA-0017 and EPID-L-2020-LLA-0018)2020-10-29029 October 2020 Response to Request for Additional Information Re License Amendment Requests for Amendments to Renewed Facility OL to Adopt 10CFR50.69 & to Adopt TSTF-505, Rev. 2 (EPID L-2020-LLA-0017 and EPID-L-2020-LLA-0018) RS-20-133, Response to Request for Additional Information Re License Amendment Request to Renewed Facility Operating Licenses to Adopt 10 CFR 50.692020-10-16016 October 2020 Response to Request for Additional Information Re License Amendment Request to Renewed Facility Operating Licenses to Adopt 10 CFR 50.69 RS-20-104, Supplement to the Request for a License Amendment Technical Specification 3.7.3, Ultimate Heat Sink2020-09-11011 September 2020 Supplement to the Request for a License Amendment Technical Specification 3.7.3, Ultimate Heat Sink RS-20-112, Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-5682020-09-0303 September 2020 Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-568 NMP2L2711, Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-8792019-10-16016 October 2019 Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-879 JAFP-19-0057, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-06-0404 June 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 NMP1L3279, Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants2019-05-0101 May 2019 Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants RS-19-052, Supplement to the Response to Request for Additional Information Regarding License Amendment Request to Remove Operating Mode Restrictions for Performing Surveillance Testing of the Division 3 Battery and High ..2019-04-24024 April 2019 Supplement to the Response to Request for Additional Information Regarding License Amendment Request to Remove Operating Mode Restrictions for Performing Surveillance Testing of the Division 3 Battery and High .. RS-19-019, Response to Request for Additional Information Regarding Relief Request 13R-152019-04-0202 April 2019 Response to Request for Additional Information Regarding Relief Request 13R-15 JAFP-19-0006, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-01-0808 January 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 RS-18-143, Supplemental Information Supporting License Amendment Requests for Approval of Changes to Emergency Plan Staffing Requirements2018-11-29029 November 2018 Supplemental Information Supporting License Amendment Requests for Approval of Changes to Emergency Plan Staffing Requirements RS-18-097, Response to Request for Additional Information and Supplemental Information-License Amendment.2018-07-27027 July 2018 Response to Request for Additional Information and Supplemental Information-License Amendment. RS-18-086, Response to Request for Additional Information Regarding License Amendment Request for Temporary Extensions to Technical Specifications Supporting Maintenance on Portions of the Core Standby Cooling System2018-07-16016 July 2018 Response to Request for Additional Information Regarding License Amendment Request for Temporary Extensions to Technical Specifications Supporting Maintenance on Portions of the Core Standby Cooling System RS-18-078, Supplemental Information Related to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2018-06-18018 June 2018 Supplemental Information Related to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control RS-18-061, Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis)2018-05-0202 May 2018 Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis) RS-18-014, Supplement to Request to Revise Technical Specifications 2.1.1 for Minimum Critical Power Ratio Safety Limits2018-01-25025 January 2018 Supplement to Request to Revise Technical Specifications 2.1.1 for Minimum Critical Power Ratio Safety Limits RS-17-147, Response to Request for Additional Information Regarding LaSalle County Station Fourth Inservice Inspection Interval Relief Request 14R-012017-11-10010 November 2017 Response to Request for Additional Information Regarding LaSalle County Station Fourth Inservice Inspection Interval Relief Request 14R-01 RS-17-146, Additional Information Regarding License Amendment Request to Revise Suppression Pool Swell Design Analysis2017-10-19019 October 2017 Additional Information Regarding License Amendment Request to Revise Suppression Pool Swell Design Analysis RS-17-099, Response to Request for Additional Information Regarding LaSalle County Station License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals (PRA Branch)2017-08-0808 August 2017 Response to Request for Additional Information Regarding LaSalle County Station License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals (PRA Branch) RS-17-101, Response to Request for Additional Information Regarding License Amendment Request to Revise Suppression Pool Swell Design Analysis2017-07-28028 July 2017 Response to Request for Additional Information Regarding License Amendment Request to Revise Suppression Pool Swell Design Analysis RS-17-102, Response to Request for Supplemental Information Regarding Fourth Inservice Inspection Interval Relief Request 14R-012017-07-20020 July 2017 Response to Request for Supplemental Information Regarding Fourth Inservice Inspection Interval Relief Request 14R-01 RS-17-098, Response to Request for Additional Information Regarding License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals (Sbpb Branch)2017-07-17017 July 2017 Response to Request for Additional Information Regarding License Amendment Request for Extension of Type a and Type C Containment Leak Rate Test Intervals (Sbpb Branch) RS-17-044, Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography2017-03-13013 March 2017 Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography RS-17-010, Response to Request for Additional Information Regarding LaSalle County Station Alternative Request RV-01 for the Lnservice Testing Program Fourth 10-Year Interval2017-02-0909 February 2017 Response to Request for Additional Information Regarding LaSalle County Station Alternative Request RV-01 for the Lnservice Testing Program Fourth 10-Year Interval RS-16-244, Additional Information Regarding Request for License Amendment to Address Secondary Containment Access Openings2016-12-12012 December 2016 Additional Information Regarding Request for License Amendment to Address Secondary Containment Access Openings RS-16-176, County, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ic2016-12-0101 December 2016 County, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ich RS-16-125, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2016-08-31031 August 2016 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident RS-16-159, County, and Quad Cities - Response to Request for Additional Information Regarding License Amendment to Address Secondary Containment Access Openings2016-07-28028 July 2016 County, and Quad Cities - Response to Request for Additional Information Regarding License Amendment to Address Secondary Containment Access Openings RS-16-144, Response to Request for Additional Information on Severe Accident Mitigation Alternatives for License Renewal Environmental Review Dated July 6, 20162016-07-11011 July 2016 Response to Request for Additional Information on Severe Accident Mitigation Alternatives for License Renewal Environmental Review Dated July 6, 2016 RA-16-049, Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure2016-05-26026 May 2016 Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure RS-16-076, Response to Request for Additional Information Regarding License Amendment Request to Reduce the Reactor Steam Dome Pressure Specified in the Technical Specification 2.1.1, Reactor Core Sls.2016-04-11011 April 2016 Response to Request for Additional Information Regarding License Amendment Request to Reduce the Reactor Steam Dome Pressure Specified in the Technical Specification 2.1.1, Reactor Core Sls. 2023-07-24
[Table view] |
Text
Michael P. Gallagher Exelon Generation Vice President.
License Renewal Exelon Nuclear 200 Exelon Way RS-15-256 Kennett Square. PA 19348 610 765 5958 Office 610 765 5956 Fax www.exeloncorp.com michaelp.gallagher@exeloncorp.com 10 CFR 50 10 CFR 51 10 CFR 54 October 8, 2015 U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, DC 20555-0001
Subject:
References:
LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-37 4 Response to NRC Request for Additional Information, Set 11, dated September 14, 2015 related to the LaSalle County Station, Units 1 and 2, License Renewal Application (TAC Nos. MF5347 and MF5346) 1. Letter from Michael P. Gallagher, Exelon Generation Company LLC (Exelon),
to NRC Document Control Desk, dated December 9, 2014, "Application for Renewed Operating Licenses"
- 2. Letter from Jeffrey S. Mitchell, US NRC to Michael P. Gallagher, Exelon, dated September 14, 2015, "Requests for Additional Information for the Review of the LaSalle County Station, Units 1 and 2 License Renewal Application
-Set 11 (TAC Nos. MF5347 and MF5346)"
In Reference 1, Exelon Generation
- Company, LLC (Exelon) submitted the License Renewal Application (LRA) for the LaSalle County Station (LSCS), Units 1 and 2. In Reference 2, the NRC requested additional information to support staff review of the LRA. Enclosure A contains the response to these requests for additional information.
Enclosure B contains updates to sections of the LRA affected by the response.
There are no new or revised regulatory commitments contained in this letter.
October 8, 2015 U.S. Nuclear Regulatory Commission Page 2 If you have any questions, please contact Mr. John Hufnagel, Licensing Lead, LaSalle License Renewal Project, at 610-765-5829.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on ltJ-o1-2o!S-Respectfully, Vice President
-License Renewal Projects Exelon Generation
- Company, LLC
Enclosures:
A: Response to Set 11 Requests for Additional Information B: LSCS License Renewal Application Updates cc: Regional Administrator-NRC Region Ill NRC Project Manager (Safety Review),
NRR-DLR NRC Project Manager (Environmental Review),
NRR-DLR NRC Project Manager, NRR-DORL-LaSalle County Station NRC Senior Resident Inspector, LaSalle County Station Illinois Emergency Management Agency -Division of Nuclear Safety RS-15-256 Enclosure A Page 1 of 2 Enclosure A Response to Set 11 Request for Additional Information Related to various sections of the LaSalle County Station (LSCS)
License Renewal Application (LRA)
RAI 4.2.7-1a
RS-15-256 Enclosure A Page 2 of 2 RAI 4.2.7-1a
Background:
By letter dated August 6, 2015, the applicant responded to RAI 4.2.7-1 that requested sufficient information on the parameters used in the reactor vessel reflood thermal shock analysis (LRA Section 4.2.7). In its response, the applicant indicated that the maximum initial flaw depth postulated in the analysis is 5.2 percent of the reactor vessel wall thickness per ASME Code Section XI, Table IWB-3510-1. Issue: License Renewal Application (LRA) Table 4.2.7-2 and associated discussion in LRA Section 4.2.7 describe applied stress intensity factor values (KI-applied) at 52 percent of the reactor vessel wall thickness during the recirculation line break transient. The LRA also compares these KI-applied values with the adjusted fracture toughness values (KIc/1.414) of the LSCS limiting reactor vessel material during the transient. It is not clear to the staff why LRA Table 4.2.7-2 and associated discussion in Section 4.2.7 refer to the location at 52 percent of the reactor wall thickness for the fracture toughness comparison rather than 5.2 percent of the wall thickness that corresponds to the postulated initial flaw depth. In addition, the staff noted that LRA Section 4.2.7 does not provide the KI-applied value and the allowable fracture toughness value (KIc/1.414) that were evaluated in the applicant's analysis for N6 low pressure coolant injection nozzles.
Request: 1. Clarify why LRA Table 4.2.7-2 and associated discussion in Section 4.2.7 assume a flaw depth of 52 percent of the wall thickness which is different from the postulated initial flaw depth per ASME Code Section XI, Table IWB-3510-1. 2. Provide the KI-applied value and the allowable fracture toughness value (KIc/1.414) that were evaluated in the applicant's analysis for N6 low pressure coolant injection nozzles.
Exelon Response: 1. The correct flaw depth is 0.052T, which is 5.2 percent of the wall thickness, T. LRA Table 4.2.7-2 and the discussion in LRA Section 4.2.7 have typographical errors that have been corrected, as shown in Enclosure B. 2. At a flaw depth of 0.052T, K I-applied is approximately 35 ksiinch. This is significantly less than the allowable fracture toughness value (K Ic /1.414) of 141 ksiinch. Therefore, adequate margin against non-ductile fracture has been demonstrated for the Unit 1 and Unit 2 N6 LPCI nozzles. These values are added to LRA Section 4.2.7, as shown in Enclosure B.
RS-15-256 Enclosure B Page 1 of 3 Enclosure B LSCS License Renewal Application Updates Resulting from the Response to the following RAI:
RAI 4.2.7-1a Note: To facilitate understanding, portions of the LRA have been repeated in this Enclosure, with revisions indicated. Previously submitted information is shown in normal font. Changes are highlighted with bolded italics for inserted text and strikethroughs for deleted text.
RS-15-256 Enclosure B Page 2 of 3
As a result of the response to RAI 4.2.7-1a provided in Enclosure A of this letter, the Recirculation Line Break Analysis subsection of LRA Section 4.2.7 and Table 4.2.7-2, on LRA pages 4-53 and 4-54, are revised as shown below in bolded italics to correct three typographical errors: 4.2.7 REACTOR PRESSURE VESSEL REFLOOD THERMAL SHOCK ANALYSIS Recirculation Line Break Analysis In Reference 4.8.10, the Recirculation line break LOCA was evaluated. A summary of this analysis at selected times during the transient is presented in Table 4.2.7-2, but with updated material properties at 54 EFPY. Note that K Ic is determined using crack tip temperature at the maximum allowable crack depth of 0.052T and ART is based on the limiting inside surface (0T) fluence.
Table 4.2.7-2 Crack Stability Analysis for Beltline Shells During Recirculation Line Break Time During Transient (s) 0 25 84 480 1200 3000 Temperature at 0.052T 550 450 450 160 120 80 Limiting 0T 54 EFPY ART
(ºF) 168 168 168 168 168 168 T-ART (ºF) 382 282 282 48 -88 KIc/1.414 (ksiin) 141 141 141 36 29 26 KI-applied at 0.52T0.052T(ksiin) 33 47 20 56 47 24 Margin 4.3 3.0 7.1 0.6 0.6 1.1 Table 4.7-2 4.2.7-2 shows that at times 0, 25, 84, and 3,000 seconds after the start of the transient, the applied stress intensity factor, K I-applied at 0.52T0.052T, is less than the available toughness, K Ic/1.414, calculated as a function of crack tip temperature and the bounding 0T fluence level. However, at 480 seconds and 1,200 seconds after the start of the transient, the applied stress intensity factor exceeds the available toughness value by 40 percent, which would indicate the initiation and propagation of a crack during that time period. However, since fluence actually attenuates as a function of distance from the inside surface, further analysis may be performed to take into account the reduced fluence as a function of crack depth. If crack initiation still occurs, the cracking must be shown to arrest prior to reaching 0.75T in order to meet the acceptance criteria.
RS-15-256 Enclosure B Page 3 of 3
As a result of the response to RAI 4.2.7-1a provided in Enclosure A of this letter, the Beltline Nozzles subsection of LRA Section 4.2.7 on LRA page 4-56 is revised as shown below:
Beltline Nozzles The N6 Low Pressure Coolant Injection (LPCI) nozzles are selected as the limiting beltline nozzles since the Emergency Core Coolant System (ECCS) injects coolant through this nozzle following a LOCA. Consequently, there is a severe thermal transient at this location following the design basis LOCA. The finite element analysis (FEA) results are documented in the LSCS Unit 1 and Unit 2 RPV stress analyses. The bounding temperature distribution in the LPCI Nozzle analyzed for both units is selected. A thermal stress distribution is developed from this temperature profile, which is then used to calculate a stress intensity factor. Since there is negligible pressure in the RPV following the LOCA event and since the location of the highest thermal stresses is remote from welds, there is no K I from internal pressure or weld residual stress. A flat plate K I solution for a point load acting at an arbitrary location along the crack front is selected. The point load is replaced with (x)dx then integrated over the crack depth in order to obtain the K I caused by the thermal stress distribution. The same acceptance criteria as described for the beltline shells are applied for the nozzle. The resulting K I-applied value is approximately 35 ksiinch at a flaw depth of 0.052T. This is significantly less than the allowable fracture toughness value, (KIc/1.414) of 141 ksiinch,. tTherefore, demonstrating adequate margin against non-ductile fracture has been demonstrated for the Unit 1 and Unit 2 N6 LPCI nozzles.