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| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 7, 2015 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 7, 2015 Mr. Michael P. Gallagher Vice President, License Renewal Projects Exelon Generation Company, LLC 200 Exelon Way Kennett Square, PA 19348 |
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| Mr. Michael P. Gallagher Vice President, License Renewal Projects Exelon Generation Company, LLC | |
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| 200 Exelon Way | |
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| Kennett Square, PA 19348 | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| 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) | | 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) |
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| ==Dear Mr. Gallagher:== | | ==Dear Mr. Gallagher:== |
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| By letter dated December 9, 2014, Exelon Gene ration Company, LLC (Exelon) submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54, to renew the operating licenses NPF-11 and NPF-18 for LaSalle County Station (LSCS), Units 1 and 2, respectively. The staff of the U.S. Nuclear Regulatory Commission (NRC or the staff) is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review. | | By letter dated December 9, 2014, Exelon Generation Company, LLC (Exelon) submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54, to renew the operating licenses NPF-11 and NPF-18 for LaSalle County Station (LSCS), Units 1 and 2, respectively. The staff of the U.S. Nuclear Regulatory Commission (NRC or the staff) is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review. |
| | | These requests for additional information were discussed with Mr. John Hufnagel, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-3019 or by e-mail at Jeffrey.Mitchell2@nrc.gov. |
| These requests for additional information were discussed with Mr. John Hufnagel, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-3019 or by e-mail at Jeffrey.Mitchell2@nrc.gov. Sincerely, | | Sincerely, |
| | | /RA/ |
| /RA/ Jeffrey S. Mitchell, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation | | Jeffrey S. Mitchell, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374 |
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| Docket Nos. 50-373 and 50-374 | |
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| ==Enclosure:== | | ==Enclosure:== |
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| As stated cc: Listserv July 7, 2015 | | As stated cc: Listserv |
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| Mr. Michael P. Gallagher Vice President, License Renewal Projects Exelon Generation Company, LLC | | July 7, 2015 Mr. Michael P. Gallagher Vice President, License Renewal Projects Exelon Generation Company, LLC 200 Exelon Way Kennett Square, PA 19348 |
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| 200 Exelon Way | |
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| Kennett Square, PA 19348 | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| 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) | | 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) |
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| ==Dear Mr. Gallagher:== | | ==Dear Mr. Gallagher:== |
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| By letter dated December 9, 2014, Exelon Gene ration Company, LLC (Exelon) submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54, to renew the operating licenses NPF-11 and NPF-18 for LaSalle County Station (LSCS), Units 1 and 2, respectively. The staff of the U.S. Nuclear Regulatory Commission (NRC or the staff) is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review. | | By letter dated December 9, 2014, Exelon Generation Company, LLC (Exelon) submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54, to renew the operating licenses NPF-11 and NPF-18 for LaSalle County Station (LSCS), Units 1 and 2, respectively. The staff of the U.S. Nuclear Regulatory Commission (NRC or the staff) is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review. |
| | | These requests for additional information were discussed with Mr. John Hufnagel, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-3019 or by e-mail at Jeffrey.Mitchell2@nrc.gov. |
| These requests for additional information were discussed with Mr. John Hufnagel, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-3019 or by e-mail at Jeffrey.Mitchell2@nrc.gov. Sincerely, | | Sincerely, |
| | | /RA/ |
| /RA/ Jeffrey S. Mitchell, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374
| | Jeffrey S. Mitchell, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374 |
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| ==Enclosure:== | | ==Enclosure:== |
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| As stated | | As stated cc: Listserv DISTRIBUTION: See next page ADAMS Accession Number: ML15163A071 *Concurred via e-mail OFFICE LA:DLR* PM:RPB1:DLR PM:RPB1:DLR BC:RPB1:DLR PM:RPB1:DLR NAME YEdmonds JMitchell RPlasse YDiaz-Sanabria JMitchell DATE 6/24/15 6/24/15 6/29/15 7/7/15 7/7/15 OFFICIAL RECORD COPY |
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| cc: Listserv
| | Letter to Michael Gallagher from Jeffrey S. Mitchell dated July 7, 2015 |
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| DISTRIBUTION: See next page | | ==SUBJECT:== |
| | 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) |
| | DISTRIBUTION: |
| | E-MAIL: |
| | PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRerb Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsNrrDlrRsrg Resource RidsNrrPMLaSalle Resource |
| | --------------- |
| | J. Mitchell R. Plasse D. Drucker B. Wittick J. Wachutka, OGC D. McIntyre, OPA M. Kunowski, RIII V. Mitlyng, RIII P. Chandrathil, RIII H. Logaras, RIII C. Lipa, RIII S. Sheldon, RIII R. Ruiz, RIII J. Robbins, RIII |
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| ADAMS Accession Number: ML15163A071
| | LASALLE COUNTY STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION REQUESTS FOR ADDITIONAL INFORMATION - SET 6 (TAC NOS. MF5347 AND MF5346) |
| *Concurred via e-mail OFFICE LA:DLR* PM:RPB1:DLR PM:RPB1:DLR BC:RPB1:DLR PM:RPB1:DLR NAME YEdmonds JMitchell RPlasse YDiaz-Sanabria JMitchell DATE 6/24/15 6/24/15 6/29/15 7/7/15 7/7/15 OFFICIAL RECORD COPY Letter to Michael Gallagher from Jeffrey S. Mitchell dated July 7, 2015
| | RAI B.2.1.24-1 |
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| ==SUBJECT:== | | ==Background:== |
| 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)
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| DISTRIBUTION
| | Generic Aging Lessons Learned (GALL) Report aging management program (AMP) XI.M36, External Surfaces Monitoring of Mechanical Components, as modified by License Renewal Interim Staff Guidance (LR-ISG) LR-ISG-2012-02, Aging Management of Internal Surfaces, Fire Water Systems, Atmospheric Storage Tanks, and Corrosion Under Insulation, program element 4, detection of aging effects, recommends that [t]ightly adhering insulation is considered to be a separate population from the remainder of insulation installed on in-scope components. The entire population of in-scope piping that has tightly adhering insulation is visually inspected for damage to the moisture barrier with the same frequency as for other types of insulation inspections. |
| : E-MAIL: PUBLIC RidsNrrDlr Resource | | License renewal application (LRA) Section B.1.24 states in the Program Description section that the program does not require removal of tightly-adhering insulation that is impermeable to moisture unless there is evidence of damage to the moisture barrier. Instead, the program includes visual inspection of the entire accessible population of piping and components during each 10-year period of the period of extended operation. |
| | Issue: |
| | The staff has identified a difference between the GALL Report AMP and the applicants program. The applicants program states that it will inspect the entire accessible population of the tightly-adhering insulation components, instead of the entire population as stated in the GALL Report AMP. It is not clear to the staff what criteria were used to identify components as accessible and the basis for the acceptability of not inspecting inaccessible insulation. In addition, the staff lacks sufficient information to complete its review of this issue because it does not know the material type and environment (e.g., radiation) of the tightly adhering insulation in inaccessible locations. |
| | Request: |
| | Explain the criteria used in establishing categories of the accessible population and justify program adequacy if only the accessible population is inspected. In addition, state the insulation material type and environment for the inaccessible insulation. |
| | RAI B.2.1.24-2 |
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| RidsNrrDlrRpb1 Resource
| | ==Background:== |
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| RidsNrrDlrRpb2 Resource
| | GALL Report AMP XI.M36, as modified by LR-ISG-2012-02, program element 4, detection of aging effects, recommends that [f]or all outdoor components (except tanks) and any indoor ENCLOSURE |
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| RidsNrrDlrRerb Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource
| | components exposed to condensation (because the in-scope component is operated below the dew point), inspections are conducted of each material type (e.g., steel, stainless steel, copper alloy, aluminum) and environment (e.g., air-outdoor, moist air, air accompanied by leakage) where condensation or moisture on the surfaces of the component could occur routinely or seasonally. |
| | LRA Section B.1.24 states in the Program Description section that [i]nspections are conducted for each external environment where condensation or moisture on the surfaces of the component could occur routinely or seasonally. |
| | Issue: |
| | It is not clear to the staff that each external environment will include each material type and environment as provided in the GALL Report AMP. |
| | Request: |
| | Explain what each external environment refers to. Justify and provide a basis if any material/environment combination will be exempted. |
| | RAI 3.2.2.1.1-1 |
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| RidsNrrDlrRsrg Resource RidsNrrPMLaSalle Resource
| | ==Background:== |
| ---------------
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| J. Mitchell R. Plasse
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| D. Drucker
| | LRA Section B.2.1.11, Bolting Integrity, states that submerged bolting will be visually inspected for loss of material and loss of preload as enhancements to the program. Examples of submerged bolting are in the emergency core cooling system (ECCS) suction strainers, diesel fire pump suction screens, and Lake Screen House traveling screens. |
| | The parameters monitored or inspected of AMP XI.M18, Bolting Integrity, are based on inspecting bolted connections for leakage on a frequency of at least once per refueling cycle. |
| | LRA Section B.2.1.11 states that the inspection frequencies for submerged bolting are as follows: |
| | * ECCS and reactor core isolation cooling (RCIC) suction strainers in the suppression pool - during each inservice inspection (ISI) interval |
| | * Service water diver safety barriers and diesel fire pump suction screens - during maintenance activities |
| | * Lake Screen House traveling screens framework - during each refuel cycle Issue: |
| | It is unclear to the staff whether visual inspections for submerged bolting will consist of inspecting the bolt head only, or if a representative sample of bolts will be removed and the shank inspected. If visual inspections are only performed on the head of the bolt, loss of material in the shank region or loss of preload of the bolt might not be recognized. |
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| B. Wittick J. Wachutka, OGC D. McIntyre, OPA M. Kunowski, RIII V. Mitlyng, RIII P. Chandrathil, RIII | | The staff also noted that the inspection frequency coupled to ISI intervals for the ECCS and RCIC suction strainers is not consistent with that of the inspection frequency for AMP XI.M18. |
| | LRA Section B.2.1.11 does not provide a defined inspection frequency for the service water diver safety barrier and diesel fire pump suction strainer bolting. |
| | It is unclear to the staff that loss of material and loss of preload for submerged bolting will be adequately managed so that the intended function(s) will be maintained consistent with the current licensing basis during the period of extended operation, as required by Title 10 of the Code of Federal Regulations, Part 54.21(a)(3). |
| | Request: |
| | : 1. Justify the inspection parameters, such as removal of the bolt to permit inspections of the shank portion of the bolting, for the visual inspections of submerged bolting, and whether a representative sample will be removed and inspected. |
| | : 2. Justify the inspection frequency in the LRA for visual inspections of submerged bolting, other than that associated with the lake screen house traveling screen framework. |
| | RAI 3.1.2.2.1-1 |
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| H. Logaras, RIII
| | ==Background:== |
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| C. Lipa, RIII S. Sheldon, RIII R. Ruiz, RIII J. Robbins, RIII ENCLOSURE LASALLE COUNTY STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION REQUESTS FOR ADDITIONAL INFORMATION - SET 6 (TAC NOS. MF5347 AND MF5346) RAI B.2.1.24-1
| | LRA Table 3.1.2-3 provides the applicants summary of the aging management review for the reactor vessel internals system. LRA Table 4.3.4-1 provides the bounding cumulative usage factor (CUF) values for the reactor vessel internal components that have been analyzed for fatigue. |
| | Issue: |
| | LRA Table 4.3.4-1 provides the CUF values for the access hole cover and the core differential pressure and liquid control line, implying that these components are subject to cumulative fatigue damage. These two components are also included in LRA Table 3.1.2-3. However, LRA Table 3.1.2-3 does not include cumulative fatigue damage as an aging effect requiring management for either of these components. |
| | Request: |
| | Justify why cumulative fatigue damage is not included as an aging effect requiring management in LRA Table 3.1.2-3 for the access hole cover and the core differential pressure and liquid control line components, or revise LRA Table 3.1.2-3 to include this effect for these components. |
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| ===Background===
| | RAI 4.2.7-1 |
| : Generic Aging Lessons Learned (GALL) Report aging management program (AMP) XI.M36, "External Surfaces Monitoring of Mechanical Components," as modified by License Renewal Interim Staff Guidance (LR-ISG) LR-ISG-2012-02, "Aging Management of Internal Surfaces, Fire Water Systems, Atmospheric Storage Tanks, and Corrosion Under Insulation," program element 4, "detection of aging effects," recommends that "[t]ightly adhering insulation is considered to be a separate population from the remainder of insulation installed on in-scope components. The entire population of in-scope piping that has tightly adhering insulation is visually inspected for damage to the moisture barrier with the same frequency as for other types of insulation inspections." License renewal application (LRA) Section B.1.24 states in the Program Description section that "the program does not require removal of tightly-adhering insulation that is impermeable to moisture unless there is evidence of damage to the moisture barrier. Instead, the program includes visual inspection of the entire accessible population of piping and components during each 10-year period of the period of extended operation."
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| Issue: The staff has identified a difference between the GALL Report AMP and the applicant's program. The applicant's program states that it will inspect the "entire accessible population" of the "tightly-adhering insulation" components, instead of the "entire population" as stated in the GALL Report AMP. It is not clear to the staff what criteria were used to identify components as "accessible" and the basis for the acceptability of not inspecting inaccessible insulation. In addition, the staff lacks sufficient information to complete its review of this issue because it does not know the material type and environment (e.g., radiation) of the tightly adhering insulation in inaccessible locations.
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| Request: Explain the criteria used in establishing categories of the "accessible" population and justify program adequacy if only the "accessible" population is inspected. In addition, state the insulation material type and environment for the inaccessible insulation. RAI B.2.1.24-2
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| ===Background===
| | ==Background:== |
| : GALL Report AMP XI.M36, as modified by LR-ISG
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| -2012-02, program element 4, "detection of aging effects," recommends that "[f]or all outdoor components (except tanks) and any indoor components exposed to condensation (because the in-scope component is operated below the dew point), inspections are conducted of each material type (e.g., steel, stainless steel, copper alloy, aluminum) and environment (e.g., air-outdoor, moist air, air accompanied by leakage) where condensation or moisture on the surfaces of the component could occur routinely or seasonally." LRA Section B.1.24 states in the Program Description section that "[i]nspections are conducted for each external environment where condensation or moisture on the surfaces of the component could occur routinely or seasonally."
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| Issue: It is not clear to the staff that "each external environment" will include each material type and environment as provided in the GALL Report AMP.
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| Request: Explain what "each external environment" refers to. Justify and provide a basis if any material/environment combination will be exempted.
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| RAI 3.2.2.1.1-1
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| ===Background===
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| : LRA Section B.2.1.11, "Bolting Integrity," states that submerged bolting will be visually inspected for loss of material and loss of preload as enhancements to the program. Examples of submerged bolting are in the emergency core cooling system (ECCS) suction strainers, diesel fire pump suction screens, and Lake Screen House traveling screens. The parameters monitored or inspected of AMP XI.M18, "Bolting Integrity," are based on inspecting bolted connections for leakage on a frequency of at least once per refueling cycle.
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| LRA Section B.2.1.11 states that the inspection frequencies for submerged bolting are as follows:
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| * ECCS and reactor core isolation cooling (RCIC) suction strainers in the suppression pool - during each inservice inspection (ISI) interval
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| * Service water diver safety barriers and diesel fire pump suction screens - during maintenance activities
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| * Lake Screen House traveling screens framework - during each refuel cycle Issue: It is unclear to the staff whether visual inspections for submerged bolting will consist of inspecting the bolt head only, or if a representative sample of bolts will be removed and the shank inspected. If visual inspections are only performed on the head of the bolt, loss of material in the shank region or loss of preload of the bolt might not be recognized. The staff also noted that the inspection frequency coupled to ISI intervals for the ECCS and RCIC suction strainers is not consistent with that of the inspection frequency for AMP XI.M18. LRA Section B.2.1.11 does not provide a defined inspection frequency for the service water diver safety barrier and diesel fire pump suction strainer bolting. It is unclear to the staff that loss of material and loss of preload for submerged bolting will be adequately managed so that the intended function(s) will be maintained consistent with the current licensing basis during the period of extended operation, as required by Title 10 of the Code of Federal Regulations , Part 54.21(a)(3).
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| Request: 1. Justify the inspection parameters, such as removal of the bolt to permit inspections of the shank portion of the bolting, for the visual inspections of submerged bolting, and whether a representative sample will be removed and inspected. 2. Justify the inspection frequency in the LRA for visual inspections of submerged bolting, other than that associated with the lake screen house traveling screen framework.
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| RAI 3.1.2.2.1-1
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| ===Background===
| | LRA Section 4.2.7 addresses a time-limited aging analysis (TLAA) on reactor pressure vessel reflood thermal shock analysis. |
| : LRA Table 3.1.2-3 provides the applicant's summary of the aging management review for the reactor vessel internals system. LRA Table 4.3.4-1 provides the bounding cumulative usage factor (CUF) values for the reactor vessel internal components that have been analyzed for fatigue. Issue: LRA Table 4.3.4-1 provides the CUF values for the access hole cover and the core differential pressure and liquid control line, implying that these components are subject to cumulative fatigue damage. These two components are also included in LRA Table 3.1.2-3. However, LRA Table 3.1.2-3 does not include cumulative fatigue damage as an aging effect requiring management for either of these components.
| | Issue: |
| Request: Justify why cumulative fatigue damage is not included as an aging effect requiring management in LRA Table 3.1.2-3 for the access hole cover and the core differential pressure and liquid control line components, or revise LRA Table 3.1.2-3 to include this effect for these
| | LRA Section 4.2.7 does not clearly address all parameters used in the applicants analysis. The staff needs additional information to clarify the adequacy of the applicants analysis. |
| | Request: |
| | As discussed above, provide the following information: |
| | : 1. Orientation, shape, and maximum size of the bounding flaw which is postulated for the limiting locations of reactor vessel and nozzle. |
| | : 2. Structural factor used for Service Level C (Emergency) conditions if Service Level C conditions are applicable as a bounding condition for the analysis. |
| | : 3. Method used to calculate neutron fluence attenuation through reactor vessel component thickness if neutron fluence attenuation is considered. |
| | RAI 4.3.2-1 |
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| components. RAI 4.2.7-1
| | ==Background:== |
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| ===Background===
| | LRA Section 4.3.2 describes two categories of license renewal systems that were designed in accordance with American Society of Mechanical Engineers (ASME) Section III, Class 2 or 3 or American National Standards Institute (ANSI) B31.1 requirements: |
| : LRA Section 4.2.7 addresses a time-limited aging analysis (TLAA) on reactor pressure vessel reflood thermal shock analysis.
| | : 1. systems that are attached to ASME Section III, Class 1 piping and are affected by the same thermal and pressure transients as the Class 1 systems |
| Issue: LRA Section 4.2.7 does not clearly address all parameters used in the applicant's analysis. The staff needs additional information to clarify the adequacy of the applicant's analysis.
| | : 2. systems that are affected by different thermal and pressure cycles related to their specific operations The first category includes the portions of the following systems: Residual Heat Removal, High Pressure Core Spray, Low Pressure Core Spray, Reactor Core Isolation Cooling, Reactor Water Cleanup, Control Rod Drive, Main Steam, Feedwater, and Condenser and Air Removal. The systems in the second category include portions of the Reactor Core Isolation Cooling, Fire Protection, and Diesel Generator and Auxiliary systems. |
| Request: As discussed above, provide the following information: 1. Orientation, shape, and maximum size of the bounding flaw which is postulated for the limiting locations of reactor vessel and nozzle. 2. Structural factor used for Service Level C (Emergency) conditions if Service Level C conditions are applicable as a bounding condition for the analysis. 3. Method used to calculate neutron fluence attenuation through reactor vessel component thickness if neutron fluence attenuation is considered.
| | For both groups of non-Class 1 piping, the applicant states that the 60-year projections for the transients will not exceed 7,000 cycles, and therefore, the stress range factors originally selected for the components within these systems remain applicable for the period of extended operation. These allowable stress calculations meet the requirements for a TLAA, and the applicant dispositioned them in accordance with 10 CFR 54.21(c)(1)(i). |
| RAI 4.3.2-1
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| ===Background===
| | Issue: |
| : LRA Section 4.3.2 describes two categories of license renewal systems that were designed in accordance with American Society of Mechanical Engineers (ASME) Section III, Class 2 or 3 or American National Standards Institute (ANSI) B31.1 requirements: 1. systems that are attached to ASME Section III, Class 1 piping and are affected by the same thermal and pressure transients as the Class 1 systems 2. systems that are affected by different thermal and pressure cycles related to their specific operations The first category includes the portions of the following systems: Residual Heat Removal, High Pressure Core Spray, Low Pressure Core Spray, Reactor Core Isolation Cooling, Reactor Water Cleanup, Control Rod Drive, Main Steam, Feedwater, and Condenser and Air Removal. The
| | LRA Tables 4.3.1-1 and 4.3.1-2 provide the 60-year cycle projections for the transients associated with the Class 2 and 3 and ANSI B31.1 piping in the Reactor Coolant System and Auxiliary Systems. The applicant stated that the systems in the first category experience the same thermal and pressure transients included in these tables. However, the applicant did not provide the applicable transient information for the second category of systems. The staff requires additional clarification on the transients and 60-year projections for these systems to verify that the cycle limits and the original allowable stress calculations will remain valid for the period of extended operation. |
| | Request: |
| | : 1. Identify the ASME Section III, Class 2 or 3 or ANSI B31.1 systems that are affected by different thermal and pressure cycles than the ones included in LRA Tables 4.3.1-1 and 4.3.1-2, including the Reactor Core Isolation Cooling, Fire Protection, and Diesel Generator and Auxiliary systems. |
| | : 2. For each of the identified systems: |
| | a) provide the transients used in the allowable stress calculations, b) provide the projected 60 year cycle count for each of these transients, and c) justify that the TLAA remains valid for the period of extended operation in accordance with 10 CFR 54.21(c)(1)(i). |
| | RAI 4.3.3-1 |
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| systems in the second category include portions of the Reactor Core Isolation Cooling, Fire Protection, and Diesel Generator and Auxiliary systems. For both groups of non-Class 1 piping, the applicant states that the 60-year projections for the transients will not exceed 7,000 cycles, and therefore, the stress range factors originally selected for the components within these systems remain applicable for the period of extended operation. These allowable stress calculations meet the requirements for a TLAA, and the applicant dispositioned them in accordance with 10 CFR 54.21(c)(1)(i). Issue: LRA Tables 4.3.1-1 and 4.3.1-2 provide the 60-year cycle projections for the transients associated with the Class 2 and 3 and ANSI B31.1 piping in the Reactor Coolant System and Auxiliary Systems. The applicant stated that the systems in the first category experience the same thermal and pressure transients included in these tables. However, the applicant did not provide the applicable transient information for the second category of systems. The staff requires additional clarification on the transients and 60-year projections for these systems to verify that the cycle limits and the original allowable stress calculations will remain valid for the period of extended operation.
| | ==Background:== |
| Request: 1. Identify the ASME Section III, Class 2 or 3 or ANSI B31.1 systems that are affected by different thermal and pressure cycles than the ones included in LRA Tables 4.3.1-1 and 4.3.1-2, including the Reactor Core Isolation Cooling, Fire Protection, and Diesel Generator and Auxiliary systems. 2. For each of the identified systems: a) provide the transients used in the allowable stress calculations, b) provide the projected 60 year cycle count for each of these transients, and c) justify that the TLAA remains valid for the period of extended operation in accordance with 10 CFR 54.21(c)(1)(i).
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| RAI 4.3.3-1
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| ===Background===
| | LRA Section 4.3.3 states that for each Class 1 piping system or subsystem in the environmental fatigue evaluation, the applicant determined the most limiting location for each wetted material type based on the location with the highest ASME Code CUF value. The LRA further states that, in some cases, one Class 1 piping location was evaluated because the analysis represents another piping location that is bounded. The applicant defined the criteria for determining a bounded location as: a) must be affected by the same transients as the analyzed location, b) must have a lower ASME Code CUF than the analyzed location, and c) must be made from the same material or, if of a different material, the bounded material must have a lower Fen value than the bounding material. |
| : LRA Section 4.3.3 states that for each Class 1 piping system or subsystem in the environmental fatigue evaluation, the applicant determined the most limiting location for each wetted material type based on the location with the highest ASME Code CUF value. The LRA further states that, in some cases, one Class 1 piping location was evaluated because the analysis represents another piping location that is bounded. The applicant defined the criteria for determining a bounded location as: a) must be affected by the same transients as the analyzed location, b) must have a lower ASME Code CUF than the analyzed location, and c) must be made from the same material or, if of a different material, the bounded material must have a lower F en value than the bounding material. LRA Table 4.3.3-3, Note 12 states that stainless steel location 376IJ in the N7 head spray nozzle bounds the carbon steel location 10A in the reactor core isolation cooling piping system
| | LRA Table 4.3.3-3, Note 12 states that stainless steel location 376IJ in the N7 head spray nozzle bounds the carbon steel location 10A in the reactor core isolation cooling piping system for Unit 1. |
| | Issue: |
| | The staff noted that in order to have a meaningful comparison of CUF values to determine the most limiting component (or leading location) by using the highest CUF value, it is important that the CUFs were assessed similarly (e.g., amount of rigor in calculating CUF) and used the same |
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| for Unit 1.
| | fatigue curves in ASME Code, Section III, Appendix I. The staff noted that through the course of plant operation it is possible that CUF values for specific components were possibly re-evaluated as part of power uprates, generic letters, bulletins, etc. to different editions of ASME Code, Section III and with varying levels of rigor when compared to the fatigue evaluations performed for the plants original design. |
| Issue: The staff noted that in order to have a meaningful comparison of CUF values to determine the most limiting component (or leading location) by using the highest CUF value, it is important that the CUFs were assessed similarly (e.g., amount of rigor in calculating CUF) and used the same fatigue curves in ASME Code, Section III, Appendix I. The staff noted that through the course of plant operation it is possible that CUF values for specific components were possibly re-evaluated as part of power uprates, generic letters, bulletins, etc. to different editions of ASME Code, Section III and with varying levels of rigor when compared to the fatigue evaluations performed for the plant's original design. The staff also noted that LRA Table 4.3.3-3, Note 12 states that environmental fatigue analysis for the stainless steel location 376IJ is provided in LRA Table 4.3.3-1. The staff noted that location 376IJ is provided in LRA Table 4.3.3-2, which provides the environmental fatigue analysis results for Unit 2. The staff is unclear on either: a) which component in LRA Table 4.3.3-1 the note is referencing, or b) how a component in Unit 2 can bound a piping component in Unit 1 for consideration of environmentally-assisted fatigue.
| | The staff also noted that LRA Table 4.3.3-3, Note 12 states that environmental fatigue analysis for the stainless steel location 376IJ is provided in LRA Table 4.3.3-1. The staff noted that location 376IJ is provided in LRA Table 4.3.3-2, which provides the environmental fatigue analysis results for Unit 2. The staff is unclear on either: a) which component in LRA Table 4.3.3-1 the note is referencing, or b) how a component in Unit 2 can bound a piping component in Unit 1 for consideration of environmentally-assisted fatigue. |
| Request: 1. Confirm that the CUFs that were compared with each other in a system to identify the location with the highest CUF value were assessed similarly (e.g., amount of rigor in calculating CUF) and used the same fatigue curves in ASME Code, Section III, Appendix I to provide a meaningful comparison. If not, provide the basis for ranking or comparing the CUFs to one another to provide an appropriate method for screening and determining a leading/limiting location. 2. Clarify which reactor pressure vessel component bounds the carbon steel location 10A from LRA Table 4.3.3-3. If the bounding component is a component in Unit 2, justify how a component or piping component can be used to bound components in different units for consideration for environmentally-assisted fatigue. 3. Identify any additional locations where a different material type was bounded by the limiting location(s) within a system and provide the system, locations, and materials that have been compared and bounded. For the carbon steel location 10A in LRA Table 4.3.3-3 and any additional locations, justify that this comparison of environmentally-adjusted CUF values between different materials within a reactor pressure vessel component or piping system for the consideration of environmentally-assisted fatigue is appropriate or valid.}} | | Request: |
| | : 1. Confirm that the CUFs that were compared with each other in a system to identify the location with the highest CUF value were assessed similarly (e.g., amount of rigor in calculating CUF) and used the same fatigue curves in ASME Code, Section III, Appendix I to provide a meaningful comparison. If not, provide the basis for ranking or comparing the CUFs to one another to provide an appropriate method for screening and determining a leading/limiting location. |
| | : 2. Clarify which reactor pressure vessel component bounds the carbon steel location 10A from LRA Table 4.3.3-3. If the bounding component is a component in Unit 2, justify how a component or piping component can be used to bound components in different units for consideration for environmentally-assisted fatigue. |
| | : 3. Identify any additional locations where a different material type was bounded by the limiting location(s) within a system and provide the system, locations, and materials that have been compared and bounded. For the carbon steel location 10A in LRA Table 4.3.3-3 and any additional locations, justify that this comparison of environmentally-adjusted CUF values between different materials within a reactor pressure vessel component or piping system for the consideration of environmentally-assisted fatigue is appropriate or valid.}} |
Letter Sequence 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
[Table View] |
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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:Request for Additional Information (RAI)
MONTHYEARML23360A6082023-12-27027 December 2023 County Station Request for Information for NRC Commercial Grade Dedication Inspection: Inspection Report 05000373/2024010 and 05000374/2024010 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 ML23208A3182023-07-27027 July 2023 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and RFI ML23153A1562023-06-0202 June 2023 NRR E-mail Capture - RAI LaSalle pressure-temperature Limits Report (PTLR) Amendment Request ML23150A2482023-05-25025 May 2023 NRR E-mail Capture - RAI Re LaSalle Downcomer Analysis Amendment Request ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML22361A0792022-12-27027 December 2022 Notification of NRC Baseline Inspection and Request for Information (05000374/2023001) ML22256A0112022-09-12012 September 2022 NRR E-mail Capture - Request for Additional Information LaSalle County Station, Units 1 and 2 and Quad Cities Nuclear Power Station, Units 1 and 2 License Amendments Related to Fuel Storage ML22138A4112022-05-18018 May 2022 NRR E-mail Capture - Lasalle 1 and 2 - (RAI) License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Changes to TS Sections 4.3.1 and 5.6.5 (EPID-L-2021-LLA-0124) ML22126A0392022-05-0606 May 2022 NRR E-mail Capture - Lasalle 1 and 2 Draft (RAI) License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Proposed Changes to TS Sections 4.3.1 and 5.6.5 ML22097A0832022-04-0707 April 2022 County Station Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000373/2022403 and 05000374/2022403 ML22062B0232022-03-0303 March 2022 NRR E-mail Capture - EPID-L-2022-LLR-0028, LaSalle Unit 1, Request for Additional Information (Rai), LaSalle Unit 1, Relief Request I4R-13 Relief from Code Examinations for 1B33-F060A and 1B33-F060B Repairs 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 ML21292A1782021-10-19019 October 2021 Information Request for a NRC Post-Approval Site Inspection for License Renewal 05000373/2022010 ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21207A0072021-07-26026 July 2021 NRR E-mail Capture - La Salle Units 1 and 2 - Request for Additional Information (RAI) License Amendment Request to Incorporate Licensing Topical Report NEDE-33885P-A, Revision 1, GNF CRDA Application Methodology(EPID-L-2021-LLA-0016) ML21190A0192021-07-0808 July 2021 NRR E-mail Capture - Exelon Fleet - Request for Additional Information Regarding Adoption of TSTF-582 and TSTF-583-T ML21187A2972021-07-0707 July 2021 Information Request for an NRC Triennial 10 CFR 50.59 (Evaluation of Changes, Tests, and Experiments) Baseline Inspection ML21144A2132021-05-24024 May 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21117A0342021-05-0505 May 2021 Request for Additional Information Regarding Proposed Alternative to Use ASME Code Case N-893 ML21119A2282021-04-29029 April 2021 NRR E-mail Capture - Request for Additional Information (RAI) - LaSalle, EPID-L-2020-LLA-0018, License Amendment Request (LAR) TSTF-505 ML21077A1902021-03-18018 March 2021 NRR E-mail Capture - Lasalle Units 1 and 2 - Request for Additional Information (RAI) Request for License Amendment Regarding Ultimate Heat Sink, (EPID-L-2020-LLA-0165) ML21068A2762021-03-0909 March 2021 NRR E-mail Capture - La Salle Units 1 and 2 - Request for Additional Information (RAI) Relief Request I4R-12 Relief from Code Surface Examinations for 2B33-F060B Valve Repair (EPID-L-2020-LLA-0016) ML21067A6752021-03-0808 March 2021 NRR E-mail Capture - La Salle Units 1 and 2 - Request for Additional Information (RAI) UHS Amendment Request (EPID-L-2020-LLA-0165) ML21060B4352021-03-0101 March 2021 NRR E-mail Capture - Second Round - Request for Additional Information (Rais) EPID-L-2020-LLA-0018, LaSalle License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2 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 ML21053A0252021-02-20020 February 2021 NRR E-mail Capture - Request for Additional Information (Rais) - LaSalle Request for Exemption from Pre-Access Drug and Alcohol Testing 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) ML21048A0432021-02-16016 February 2021 County Station - Notification of NRC Design Bases Assurance Inspection (Programs) and Initial Request for Information - Inspection Report 05000373/2021011 and 05000374/2021011 ML20364A2452020-12-29029 December 2020 Notification of an NRC Triennial Heat Sink Performance Inspection and Request for Information; Inspection Report 05000373/2021002; 05000374/2021002 ML20346A1042020-12-11011 December 2020 NRR E-mail Capture - LaSalle County Station, Units 1 and 2 - Request for Additional Information Regarding the License Amendment Request to Adopt 10 CFR 50.69 ML20330A1892020-11-25025 November 2020 Request for Information for an NRC Post-Approval Site Inspection for License Renewal; Inspection Report 05000374/2021010 ML20321A0852020-11-16016 November 2020 Notification of NRC Baseline Inspection and Request for Information (05000374/2021001) ML20247J4082020-09-29029 September 2020 Apla Request for Additional Information LAR 50.69 and TSTF-505 (Epids L-2020-LLA-0017) and ML20253A3422020-09-17017 September 2020 Correction to Request for Additional Information Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (EPID-2020-LLA-0017) ML20253A2272020-09-16016 September 2020 Correction to Request for Additional Information Application to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML20240A2182020-09-0303 September 2020 Request for Additional Information Regarding Amendment Request for Amendments to Renewed Facility Operating Licenses to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Co ML20239A7262020-08-27027 August 2020 Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding Request for a License Amendment to Technical Specification 3.7.3, Ultimate Heat Sink ML20239A7982020-08-25025 August 2020 NRR E-mail Capture - Exelon Generation Company, LLC - Fleet License Amendment Request to Adopt TSTF-568, Revision 2 ML19275H1362019-10-0202 October 2019 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Request to Use ASME Code Case N-879 ML19179A0612019-07-19019 July 2019 Three Mile Point 1 - Supplemental Information Needed to Proposed Alternative to Use ASME Code Case N-879 ML19120A2302019-04-29029 April 2019 Ltr. 04/29/19 LaSalle County Station, Units 1 and 2 - Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team); Inspection Report 05000373/2019012; 05000374/2019012 (DRS-M.Jones) ML19087A2682019-03-28028 March 2019 NRR E-mail Capture - Request for Additional Information (RAI) - LaSalle 1 and 2, EPID-L-2018-LLA-0162, LAR Removal of Operating Mode Restrictions for Performing Surveillance Testing of the Div 3 Battery and HPCS DG ML19065A0902019-03-0505 March 2019 NRR E-mail Capture - LaSalle 1 and 2, EPID-L-2018-LLR-0162, LAR Removal of Operating Mode Restrictions for Performing Surveillance Testing of the Div 3 Battery and HPCS DG, Additional Draft Request for Additional Information (RAI) ML19058A2392019-02-27027 February 2019 Information Request to Support Upcoming Problem Identification and Resolution Inspection at LaSalle County Station, Units 1 and 2 ML19036A6562019-02-0505 February 2019 NRR E-mail Capture - LaSalle 1 and 2, EPID-L-2018-LLR-0123, Relief Request I3R-15, Third Inservice Inspection Interval, Request for Additional Information (RAI) ML19022A2552019-01-22022 January 2019 NRR E-mail Capture - LaSalle Units 1 and 2, EPID-L-2018-LLA-0035, Amendment Request to Adopt TSTF-334-A, Status of Revised Draft RAIs Sent to You on December 13, 2018 ML19050A0042019-01-22022 January 2019 NRR E-mail Capture - LaSalle 1 and 2, EPID-L-2018-LLR-0162, LAR Removal of Operating Mode Restrictions for Performing Surveillance Testing of the Div 3 Battery and HPCS DG, Draft Request for Additional Information (RAI) ML19022A0292018-12-13013 December 2018 NRR E-mail Capture - Draft Request for Additional Information for LaSalle License Amendment Request to Adopt TSTF-334-A, Revision 2 2023-09-21
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 7, 2015 Mr. Michael P. Gallagher Vice President, License Renewal Projects Exelon Generation Company, LLC 200 Exelon Way Kennett Square, PA 19348
SUBJECT:
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)
Dear Mr. Gallagher:
By letter dated December 9, 2014, Exelon Generation Company, LLC (Exelon) submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54, to renew the operating licenses NPF-11 and NPF-18 for LaSalle County Station (LSCS), Units 1 and 2, respectively. The staff of the U.S. Nuclear Regulatory Commission (NRC or the staff) is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review.
These requests for additional information were discussed with Mr. John Hufnagel, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-3019 or by e-mail at Jeffrey.Mitchell2@nrc.gov.
Sincerely,
/RA/
Jeffrey S. Mitchell, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374
Enclosure:
As stated cc: Listserv
July 7, 2015 Mr. Michael P. Gallagher Vice President, License Renewal Projects Exelon Generation Company, LLC 200 Exelon Way Kennett Square, PA 19348
SUBJECT:
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)
Dear Mr. Gallagher:
By letter dated December 9, 2014, Exelon Generation Company, LLC (Exelon) submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54, to renew the operating licenses NPF-11 and NPF-18 for LaSalle County Station (LSCS), Units 1 and 2, respectively. The staff of the U.S. Nuclear Regulatory Commission (NRC or the staff) is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review.
These requests for additional information were discussed with Mr. John Hufnagel, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-3019 or by e-mail at Jeffrey.Mitchell2@nrc.gov.
Sincerely,
/RA/
Jeffrey S. Mitchell, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374
Enclosure:
As stated cc: Listserv DISTRIBUTION: See next page ADAMS Accession Number: ML15163A071 *Concurred via e-mail OFFICE LA:DLR* PM:RPB1:DLR PM:RPB1:DLR BC:RPB1:DLR PM:RPB1:DLR NAME YEdmonds JMitchell RPlasse YDiaz-Sanabria JMitchell DATE 6/24/15 6/24/15 6/29/15 7/7/15 7/7/15 OFFICIAL RECORD COPY
Letter to Michael Gallagher from Jeffrey S. Mitchell dated July 7, 2015
SUBJECT:
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)
DISTRIBUTION:
E-MAIL:
PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRerb Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsNrrDlrRsrg Resource RidsNrrPMLaSalle Resource
J. Mitchell R. Plasse D. Drucker B. Wittick J. Wachutka, OGC D. McIntyre, OPA M. Kunowski, RIII V. Mitlyng, RIII P. Chandrathil, RIII H. Logaras, RIII C. Lipa, RIII S. Sheldon, RIII R. Ruiz, RIII J. Robbins, RIII
LASALLE COUNTY STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION REQUESTS FOR ADDITIONAL INFORMATION - SET 6 (TAC NOS. MF5347 AND MF5346)
RAI B.2.1.24-1
Background:
Generic Aging Lessons Learned (GALL) Report aging management program (AMP) XI.M36, External Surfaces Monitoring of Mechanical Components, as modified by License Renewal Interim Staff Guidance (LR-ISG) LR-ISG-2012-02, Aging Management of Internal Surfaces, Fire Water Systems, Atmospheric Storage Tanks, and Corrosion Under Insulation, program element 4, detection of aging effects, recommends that [t]ightly adhering insulation is considered to be a separate population from the remainder of insulation installed on in-scope components. The entire population of in-scope piping that has tightly adhering insulation is visually inspected for damage to the moisture barrier with the same frequency as for other types of insulation inspections.
License renewal application (LRA) Section B.1.24 states in the Program Description section that the program does not require removal of tightly-adhering insulation that is impermeable to moisture unless there is evidence of damage to the moisture barrier. Instead, the program includes visual inspection of the entire accessible population of piping and components during each 10-year period of the period of extended operation.
Issue:
The staff has identified a difference between the GALL Report AMP and the applicants program. The applicants program states that it will inspect the entire accessible population of the tightly-adhering insulation components, instead of the entire population as stated in the GALL Report AMP. It is not clear to the staff what criteria were used to identify components as accessible and the basis for the acceptability of not inspecting inaccessible insulation. In addition, the staff lacks sufficient information to complete its review of this issue because it does not know the material type and environment (e.g., radiation) of the tightly adhering insulation in inaccessible locations.
Request:
Explain the criteria used in establishing categories of the accessible population and justify program adequacy if only the accessible population is inspected. In addition, state the insulation material type and environment for the inaccessible insulation.
RAI B.2.1.24-2
Background:
GALL Report AMP XI.M36, as modified by LR-ISG-2012-02, program element 4, detection of aging effects, recommends that [f]or all outdoor components (except tanks) and any indoor ENCLOSURE
components exposed to condensation (because the in-scope component is operated below the dew point), inspections are conducted of each material type (e.g., steel, stainless steel, copper alloy, aluminum) and environment (e.g., air-outdoor, moist air, air accompanied by leakage) where condensation or moisture on the surfaces of the component could occur routinely or seasonally.
LRA Section B.1.24 states in the Program Description section that [i]nspections are conducted for each external environment where condensation or moisture on the surfaces of the component could occur routinely or seasonally.
Issue:
It is not clear to the staff that each external environment will include each material type and environment as provided in the GALL Report AMP.
Request:
Explain what each external environment refers to. Justify and provide a basis if any material/environment combination will be exempted.
RAI 3.2.2.1.1-1
Background:
LRA Section B.2.1.11, Bolting Integrity, states that submerged bolting will be visually inspected for loss of material and loss of preload as enhancements to the program. Examples of submerged bolting are in the emergency core cooling system (ECCS) suction strainers, diesel fire pump suction screens, and Lake Screen House traveling screens.
The parameters monitored or inspected of AMP XI.M18, Bolting Integrity, are based on inspecting bolted connections for leakage on a frequency of at least once per refueling cycle.
LRA Section B.2.1.11 states that the inspection frequencies for submerged bolting are as follows:
- Service water diver safety barriers and diesel fire pump suction screens - during maintenance activities
- Lake Screen House traveling screens framework - during each refuel cycle Issue:
It is unclear to the staff whether visual inspections for submerged bolting will consist of inspecting the bolt head only, or if a representative sample of bolts will be removed and the shank inspected. If visual inspections are only performed on the head of the bolt, loss of material in the shank region or loss of preload of the bolt might not be recognized.
The staff also noted that the inspection frequency coupled to ISI intervals for the ECCS and RCIC suction strainers is not consistent with that of the inspection frequency for AMP XI.M18.
LRA Section B.2.1.11 does not provide a defined inspection frequency for the service water diver safety barrier and diesel fire pump suction strainer bolting.
It is unclear to the staff that loss of material and loss of preload for submerged bolting will be adequately managed so that the intended function(s) will be maintained consistent with the current licensing basis during the period of extended operation, as required by Title 10 of the Code of Federal Regulations, Part 54.21(a)(3).
Request:
- 1. Justify the inspection parameters, such as removal of the bolt to permit inspections of the shank portion of the bolting, for the visual inspections of submerged bolting, and whether a representative sample will be removed and inspected.
- 2. Justify the inspection frequency in the LRA for visual inspections of submerged bolting, other than that associated with the lake screen house traveling screen framework.
RAI 3.1.2.2.1-1
Background:
LRA Table 3.1.2-3 provides the applicants summary of the aging management review for the reactor vessel internals system. LRA Table 4.3.4-1 provides the bounding cumulative usage factor (CUF) values for the reactor vessel internal components that have been analyzed for fatigue.
Issue:
LRA Table 4.3.4-1 provides the CUF values for the access hole cover and the core differential pressure and liquid control line, implying that these components are subject to cumulative fatigue damage. These two components are also included in LRA Table 3.1.2-3. However, LRA Table 3.1.2-3 does not include cumulative fatigue damage as an aging effect requiring management for either of these components.
Request:
Justify why cumulative fatigue damage is not included as an aging effect requiring management in LRA Table 3.1.2-3 for the access hole cover and the core differential pressure and liquid control line components, or revise LRA Table 3.1.2-3 to include this effect for these components.
RAI 4.2.7-1
Background:
LRA Section 4.2.7 addresses a time-limited aging analysis (TLAA) on reactor pressure vessel reflood thermal shock analysis.
Issue:
LRA Section 4.2.7 does not clearly address all parameters used in the applicants analysis. The staff needs additional information to clarify the adequacy of the applicants analysis.
Request:
As discussed above, provide the following information:
- 1. Orientation, shape, and maximum size of the bounding flaw which is postulated for the limiting locations of reactor vessel and nozzle.
- 2. Structural factor used for Service Level C (Emergency) conditions if Service Level C conditions are applicable as a bounding condition for the analysis.
- 3. Method used to calculate neutron fluence attenuation through reactor vessel component thickness if neutron fluence attenuation is considered.
RAI 4.3.2-1
Background:
LRA Section 4.3.2 describes two categories of license renewal systems that were designed in accordance with American Society of Mechanical Engineers (ASME)Section III, Class 2 or 3 or American National Standards Institute (ANSI) B31.1 requirements:
- 1. systems that are attached to ASME Section III, Class 1 piping and are affected by the same thermal and pressure transients as the Class 1 systems
- 2. systems that are affected by different thermal and pressure cycles related to their specific operations The first category includes the portions of the following systems: Residual Heat Removal, High Pressure Core Spray, Low Pressure Core Spray, Reactor Core Isolation Cooling, Reactor Water Cleanup, Control Rod Drive, Main Steam, Feedwater, and Condenser and Air Removal. The systems in the second category include portions of the Reactor Core Isolation Cooling, Fire Protection, and Diesel Generator and Auxiliary systems.
For both groups of non-Class 1 piping, the applicant states that the 60-year projections for the transients will not exceed 7,000 cycles, and therefore, the stress range factors originally selected for the components within these systems remain applicable for the period of extended operation. These allowable stress calculations meet the requirements for a TLAA, and the applicant dispositioned them in accordance with 10 CFR 54.21(c)(1)(i).
Issue:
LRA Tables 4.3.1-1 and 4.3.1-2 provide the 60-year cycle projections for the transients associated with the Class 2 and 3 and ANSI B31.1 piping in the Reactor Coolant System and Auxiliary Systems. The applicant stated that the systems in the first category experience the same thermal and pressure transients included in these tables. However, the applicant did not provide the applicable transient information for the second category of systems. The staff requires additional clarification on the transients and 60-year projections for these systems to verify that the cycle limits and the original allowable stress calculations will remain valid for the period of extended operation.
Request:
- 1. Identify the ASME Section III, Class 2 or 3 or ANSI B31.1 systems that are affected by different thermal and pressure cycles than the ones included in LRA Tables 4.3.1-1 and 4.3.1-2, including the Reactor Core Isolation Cooling, Fire Protection, and Diesel Generator and Auxiliary systems.
- 2. For each of the identified systems:
a) provide the transients used in the allowable stress calculations, b) provide the projected 60 year cycle count for each of these transients, and c) justify that the TLAA remains valid for the period of extended operation in accordance with 10 CFR 54.21(c)(1)(i).
RAI 4.3.3-1
Background:
LRA Section 4.3.3 states that for each Class 1 piping system or subsystem in the environmental fatigue evaluation, the applicant determined the most limiting location for each wetted material type based on the location with the highest ASME Code CUF value. The LRA further states that, in some cases, one Class 1 piping location was evaluated because the analysis represents another piping location that is bounded. The applicant defined the criteria for determining a bounded location as: a) must be affected by the same transients as the analyzed location, b) must have a lower ASME Code CUF than the analyzed location, and c) must be made from the same material or, if of a different material, the bounded material must have a lower Fen value than the bounding material.
LRA Table 4.3.3-3, Note 12 states that stainless steel location 376IJ in the N7 head spray nozzle bounds the carbon steel location 10A in the reactor core isolation cooling piping system for Unit 1.
Issue:
The staff noted that in order to have a meaningful comparison of CUF values to determine the most limiting component (or leading location) by using the highest CUF value, it is important that the CUFs were assessed similarly (e.g., amount of rigor in calculating CUF) and used the same
fatigue curves in ASME Code,Section III, Appendix I. The staff noted that through the course of plant operation it is possible that CUF values for specific components were possibly re-evaluated as part of power uprates, generic letters, bulletins, etc. to different editions of ASME Code,Section III and with varying levels of rigor when compared to the fatigue evaluations performed for the plants original design.
The staff also noted that LRA Table 4.3.3-3, Note 12 states that environmental fatigue analysis for the stainless steel location 376IJ is provided in LRA Table 4.3.3-1. The staff noted that location 376IJ is provided in LRA Table 4.3.3-2, which provides the environmental fatigue analysis results for Unit 2. The staff is unclear on either: a) which component in LRA Table 4.3.3-1 the note is referencing, or b) how a component in Unit 2 can bound a piping component in Unit 1 for consideration of environmentally-assisted fatigue.
Request:
- 1. Confirm that the CUFs that were compared with each other in a system to identify the location with the highest CUF value were assessed similarly (e.g., amount of rigor in calculating CUF) and used the same fatigue curves in ASME Code,Section III, Appendix I to provide a meaningful comparison. If not, provide the basis for ranking or comparing the CUFs to one another to provide an appropriate method for screening and determining a leading/limiting location.
- 2. Clarify which reactor pressure vessel component bounds the carbon steel location 10A from LRA Table 4.3.3-3. If the bounding component is a component in Unit 2, justify how a component or piping component can be used to bound components in different units for consideration for environmentally-assisted fatigue.
- 3. Identify any additional locations where a different material type was bounded by the limiting location(s) within a system and provide the system, locations, and materials that have been compared and bounded. For the carbon steel location 10A in LRA Table 4.3.3-3 and any additional locations, justify that this comparison of environmentally-adjusted CUF values between different materials within a reactor pressure vessel component or piping system for the consideration of environmentally-assisted fatigue is appropriate or valid.