Letter Sequence Response to RAI |
---|
|
|
MONTHYEARML18256A0522018-09-24024 September 2018 Plants, Units 1 and 2 - Supplemental Information Needed for Acceptance of Requested Licensing Action Risk-Informed Approach to Closure for Generic Safety Issue-191 (EPID L-2018-LLA-0222)and Project stage: Acceptance Review ML18283A0342018-10-10010 October 2018 Supplement to Final Response to Generic Letter 2004-02, Dated August 13, 2018 Project stage: Request ML18304A1392018-10-30030 October 2018 Acceptance of Requested Licensing Action Risk-Informed Approach to Closure for Generic Safety Issue-191 (EPID L-2018-LLA-0222 and EPID L-2018-LLE-0013) Project stage: Acceptance Review ML18345A1942018-12-21021 December 2018 Plants, Units 1 and 2 - Regulatory Audit Risk-Informed Approach to License Amendment Request for Closure of Generic Safety Issue-191 Project stage: Other ML19070A0192019-03-11011 March 2019 Request for Additional Information Regarding Exemption Request from 10CFR50.46(A)(1) to Support Resolution of GSI-191 Project stage: RAI ML19158A0752019-06-0707 June 2019 Revised: Final Response to Generic Letter 2004-02 Project stage: Request ML19205A2872019-07-19019 July 2019 Notification of Change in Review Schedule (Epids L-2018-LLA-0222 and L-2018-LLE-0013) Project stage: Other ML19261B2202019-09-18018 September 2019 Request for Additional Information Regarding Final Response to Generic Letter 2004-02 Project stage: RAI ML19277D1032019-10-0303 October 2019 Response to Request for Additional Information Revised - Final Response to Generic Letter 2004-02 Project stage: Response to RAI ML19294A0562019-10-21021 October 2019 Withdrawal of License Amendment Request for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 - Final Response to Generic Letter 2004-02 Project stage: Withdrawal ML19295E7142019-10-28028 October 2019 L-2018-LLA-0222 and L-2018-LLE-0013 -Withdrawal FRN 2019-10-22 Project stage: Other ML19295E7122019-10-28028 October 2019 Withdrawal of Amendment and Exemption Requests (Epids L-2018-LLA-0222 and L-2018 LLE-0013) Project stage: Withdrawal 2019-10-28
[Table View] |
|
---|
Category:Letter
MONTHYEARIR 05000317/20230042024-02-0101 February 2024 Integrated Inspection Report 05000317/2023004 and 05000318/2023004 ML24029A0102024-01-29029 January 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000317/2024010 and 05000318/2024010 ML24003A8872024-01-19019 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0033 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) 05000318/LER-2023-004, Submittal of LER 2023-004-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Submittal of Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer2024-01-16016 January 2024 Submittal of LER 2023-004-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Submittal of Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer ML24011A0732024-01-11011 January 2024 Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping 05000318/LER-2023-002, Forward LER 2023-002-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer2024-01-0808 January 2024 Forward LER 2023-002-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer 05000318/LER-2023-003, Forward LER 2023-003-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Manual Actuation of Auxiliary Feedwater System Due to 22 Steam Generator Feedwater Pump Trip2024-01-0808 January 2024 Forward LER 2023-003-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Manual Actuation of Auxiliary Feedwater System Due to 22 Steam Generator Feedwater Pump Trip ML24005A0222024-01-0505 January 2024 Revised Steam Generator Tube Inspection Reports ML23304A0642024-01-0202 January 2024 Issuance of Amendment No. 349 to Modify the Long-Term Coupon Surveillance Program RS-23-125, Request for Exemption from 10 CFR 2.109(b)2023-12-0707 December 2023 Request for Exemption from 10 CFR 2.109(b) ML23331A2992023-11-27027 November 2023 Submittal of Condition Prohibited by Technical Specifications Due to Failure to Sample Diesel Generator Fuel Oil Storage Tank IR 05000317/20230102023-11-20020 November 2023 Biennial Problem Identification and Resolution Inspection Report 05000317/2023010 and 05000318/2023010 ML23318A4722023-11-14014 November 2023 Supplement to License Amendment Request to Adopt TSTF-59-A ML23317A1032023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums ML23310A0442023-11-0707 November 2023 Project Manager Assignment IR 05000317/20230402023-11-0202 November 2023 95001 Supplemental Inspection Report 05000317/2023040 and Follow-Up Assessment Letter IR 05000317/20230032023-11-0101 November 2023 Integrated Inspection Report 05000317/2023003 and 05000318/2023003 IR 05000317/20230902023-10-26026 October 2023 Final Significance Determination of a White Finding with Assessment Follow-Up and Notice of Violation; Inspection Report 05000317/2023090 ML23289A1202023-10-16016 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 RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections ML23279A1202023-10-0606 October 2023 Response to NRC Inspection Report and Preliminary White Finding IR 05000317/20230502023-09-29029 September 2023 Special Inspection Report 05000317/2023050 and Preliminary White Finding and Apparent Violation ML23272A1032023-09-29029 September 2023 Condition Prohibited by Technical Specifications Due to Inoperable Nuclear Instrumentation at Very Low Power IR 05000317/20234012023-09-18018 September 2023 Cyber Security Inspection Report 05000317/2023401 and 05000318/2023401 ML23254A0012023-09-0505 September 2023 Registration of Use of Casks to Store Spent Fuel IR 05000317/20230052023-08-31031 August 2023 Updated Inspection Plan for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 (Report 05000317/2023005 and 05000318/2023005) ML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications ML23241A8412023-08-29029 August 2023 Response to Request for Additional Information - Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping ML23240A3872023-08-28028 August 2023 Senior Reactor and Reactor Operator Initial License Examinations ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration ML23219A1662023-08-16016 August 2023 Request for Additional Information Regarding Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping (EPID: L-2023-LLR-0006) - Non-proprietary ML23228A1002023-08-15015 August 2023 Notification of Readiness for NRC 95001 Inspection ML23188A0402023-08-0808 August 2023 Issuance of Amendment Nos. 346 and 324 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML23214A1572023-08-0707 August 2023 Correction to the Renewed Facility Operating License Page 3 in Amendment No 345 IR 05000317/20230022023-08-0303 August 2023 Integrated Inspection Report 05000317/2023002 ML23188A0512023-07-13013 July 2023 Correction to the Renewed Facility Operating License Pages in Amendment Nos. 336 and 314 ML23186A0372023-07-13013 July 2023 Correction to the Renewed Facility Operating License Pages in Amendment Nos. 340 and 318 IR 05000317/20233012023-07-12012 July 2023 Initial Operator Licensing Examination Report 05000317/2023301 and 05000318/2023301 IR 05000317/20230122023-07-10010 July 2023 Commercial Grade Dedication Report 05000317/2023012 and 05000318/2023012 ML23180A2362023-06-29029 June 2023 Correction of Errors on Technical Specification Pages RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators ML23156A6752023-06-20020 June 2023 Request for Withholding Information from Public Disclosure for Proposed Alternative to the Requirements for Repair/Replacement of Saltwater System Buried Piping 2024-02-01
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML23317A1032023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23241A8432023-08-29029 August 2023 Enclosure 3 - Response to Request for Additional Information - Non-Proprietary Version ML23241A8412023-08-29029 August 2023 Response to Request for Additional Information - Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping ML23166A1052023-06-15015 June 2023 Response to Request for Additional Information Related to the License Amendment Request to Modify the Long-Term Coupon Surveillance Program ML23155A0012023-06-0404 June 2023 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request - One-Time Extension of the Control Room Emergency Ventilation System (C RS-22-123, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator2022-12-0707 December 2022 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator RS-22-084, Response to Request for Additional Information Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator .2022-06-17017 June 2022 Response to Request for Additional Information Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator . RS-22-074, Response to Request for Additional Information - Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds .2022-05-20020 May 2022 Response to Request for Additional Information - Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds . 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 ML21334A3422021-11-30030 November 2021 Supplement to Response to Request for Additional Information Regarding the Spent Fuel Pool Cooling - Shutdown Cooling Systems Licensing Design Basis License Amendment Request ML21320A2422021-11-16016 November 2021 Stations - Response to Request for Additional Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds ML21308A5072021-11-0404 November 2021 Supplement to Response to Request for Additional Information Regarding the Spent Fuel Pool Cooling - Shutdown Cooling Systems Licensing Design Basis License Amendment Request ML21298A0432021-10-25025 October 2021 Response to Request for Additional Information Regarding the Spent Fuel Pool Cooling - Shutdown Cooling Systems Licensing Design Basis License Amendment Request 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 ML21208A0072021-07-26026 July 2021 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-567 Rev 1, Add Containment Sump TS to Address GSI-191 Issues 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 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-20-017, Response to Request for Additional Information - Proposed Alternative to Utilize Code Case N-8852021-02-0101 February 2021 Response to Request for Additional Information - Proposed Alternative to Utilize Code Case N-885 ML20317A1122020-11-12012 November 2020 Final Response and Close-out to Generic Letter 2004-02 ML20280A5132020-10-0606 October 2020 Response to Request for Additional Information - End of Interval Relief Request Associated with the Fourth Ten-Year Inservice Inspection (ISI) Interval ML20188A2642020-07-0606 July 2020 Clinton Power Station, R.E. Ginna Station, Limerick Station, Nine Mile Point Station & Peach Bottom Station - Proposed Alternative to Utilize Code Case OMN-26 - Response to Request for Additional Information ML20182A1102020-06-30030 June 2020 Response to Request for Additional Information to License Amendment Request - Proposed Changes to Technical Specification (TS) 3.8.1 Emergency Diesel Generator Surveillance Requirements Voltage ML20107F7652020-04-16016 April 2020 Response to Request for Additional Information to License Amendment Request - Revision to Technical Specification 5.5.7, Reactor Coolant Pump Flywheel Inspection Program 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 ML19282B7182019-10-0909 October 2019 Revised Response to Request for Additional Information Regarding the Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML19277D1032019-10-0303 October 2019 Response to Request for Additional Information Revised - Final Response to Generic Letter 2004-02 ML19217A3372019-08-0606 August 2019 Response to RAI #6 Regarding the Application to Adopt 10 CFR 50.69 ML19217A1432019-08-0505 August 2019 Revised Response to Request for Additional Information Regarding the Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML19200A2162019-07-19019 July 2019 Response to Request for Additional Information Regarding the Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML19183A0122019-07-0101 July 2019 Response to Request for Additional Information Regarding the Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power ... 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 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 ML18316A0342018-11-12012 November 2018 Response to Request for Additional Information: Proposed Changes to Technical Specification 3.8.1 Actions A.3 and D.3 to Extend the Offsite Circuit Inoperable Completion Times from 72 Hours to 14 ... ML18283A0342018-10-10010 October 2018 Supplement to Final Response to Generic Letter 2004-02, Dated August 13, 2018 ML18239A2602018-08-27027 August 2018 Supplement to Response to Request for Additional Information License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk .. ML18201A4062018-06-21021 June 2018 Plants, Units 1 and 2 - Exelon'S Response to NRC Questions ML18172A1452018-06-21021 June 2018 Response to Request for Additional Information License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed ... NMP1L3221, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 & 2, R. E. Ginna - Response to Request for Additional Information License Amendment Request to Adopt Emergency Action Level Schemes.2018-05-10010 May 2018 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 & 2, R. E. Ginna - Response to Request for Additional Information License Amendment Request to Adopt Emergency Action Level Schemes. 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) ML18047A1242018-02-16016 February 2018 Relief Requests Associated with Fifth Ten-Year Lnservice Testing Interval: Supplement 1 - Response to Request for Additional Information ML18025A7992018-01-25025 January 2018 Response to Request for Additional Information Regarding Generic Letter 2016-01 ML18018B3402018-01-18018 January 2018 Response to Request for Additional Information License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times. ML18011A6652018-01-11011 January 2018 Response to Request for Additional Information License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times. RS-17-053, Response to Request for Additional Information Regarding Generic Letter 2016-012017-04-27027 April 2017 Response to Request for Additional Information Regarding Generic Letter 2016-01 ML17081A3032017-03-22022 March 2017 Response to Request for Additional Information to License Amendment Request - Control Room Emergency Ventilation System 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-17-003, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal2017-01-0505 January 2017 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal ML16246A2022016-09-0101 September 2016 Response to Request for Additional Information Regarding Relief Request for Dissimilar Metal Butt Weld Examinations 2023-08-29
[Table view] |
Text
Exelon Generation © 200 Exelon Way Kennett Square. PA 19348 www.exeloncorp.com 10 CFR 50.90 October 3, 2019 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555-0001 Calvert Cliffs Nuclear Power Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-53 and DPR-69 Docket Nos. 50-317 and 50-318
Subject:
Response to Request for Additional Information Revised - Final Response to Generic Letter 2004-02
References:
- 1. Final Response to Generic Letter 2004-02, dated August 13, 2018.
- 2. Supplement to Final Response to Generic Letter 2004-02, dated October 19, 2018.
- 3. Revised - Final response to Generic letter 2004-02, dated June 7, 2019.
- 4. E-mail from Michael Marshall (NRG) to Enrique Villar (Exelon)
Calvert Cliffs Nuclear Power Plant, Units 1 and 2 - Request for Additional Information Regarding Final Response to Generic letter 2004-02 (EPID L-2018-LLE-0222}, dated September 18, 2019.
By letter dated August 13, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18226A189) as supplemented by letters dated October 10, 2018 and June 7, 2019 (ADAMS Accession Nos. ML18283A034, and ML19158A075, respectively), Exelon Generation Company, LLC (Exelon) submitted license amendment requests (LARs) for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 (Calvert Cliffs). The proposed amendments would change the Calvert Cliffs' licensing bases, including the affected portions of the Technical Specifications and Updated Final Safety Analysis Report. The methodologies in the submittal describe the use of a risk-informed approach to address safety issues discussed in Generic Safety Issue -191, "Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance" and close out generic letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors" (ADAMS Accession No. ML042360586).
Response to RAI Revised Final Response to Generic Letter 2004-02 October 3, 2019 Page 2 A request for additional information (RAI) was transmitted via e-mail on September 18, 2019 (Reference 3). to this letter contains the Nuclear Regulatory Commission (NRC) RAI followed immediately by Exelon's response.
There are no regulatory commitments contained in this letter.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 3rd day of October 2019.
If you should have any questions regarding this submittal, please contact Enrique Villar at 610-765-5736.
Respectfully, David T. Gudger Acting Director - Licensing Exelon Generation Company, LLC
Attachment:
- 1. Response to Request for Additional Information cc: NRC Regional Administrator, Region I w/attachment II NRC Senior Resident Inspector, CCNPP II NRC Project Manager, NRR, CCNPP II D. A. Tancabel, State of Maryland
ATTACHMENT 1 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION -
FINAL RESPONSE TO GENERIC LETTER 2004-02.
NRC REQUEST FOR ADDITIONAL INFORMATION
- 1. Attachment 1-2, "Deterministic (Approved Methodologies) Bases," (Page 88) of the letter dated June 7, 2019 states the largest quantity of NaAISi308 predicted from all breaks analyzed is 115.9 pounds mass (lbm) . Attachment 1-2 (page 92) states that the break that produces the largest quantity of chemical precipitates (117.21 lbm) of sodium aluminum silicate is a longitudinal break. The aluminum concentration for that break is 3.64 ppm. Attachment 1-4 (page 14), however, indicates the maximum aluminum concentration in the Calvert Cliffs sump pool for the break that produces the largest quantity of precipitate is 3.39 ppm. Please discuss which values of maximum precipitate quantity and maximum aluminum concentration are appropriate.
Exelon's Response The Attachment 1-2 values for chemical precipitate of 117.21 lbm, and aluminum concentration of 3.64 ppm are the correct values. The values listed in other attachments have been superseded.
NRC REQUEST FOR ADDITIONAL INFORMATION
- 2. The values in data columns of Table 2, "Description of Operating Margins," in Attachment 1-4, "Defense in Depth and Safety Margin," (Page 21) appear to be inconsistent.
- a. The aluminum surface area in the actual value column appears to be the value used in the analysis. However, the difference between the "actual value" column and "maximum value used in the analysis" do not sum to the value in the operating margin column. Confirm that the values for aluminum surface area shown in Attachment 1-4, Table 2 are correct. If the values are correct, explain why the maximum value used in the analyses is greater than the sum of the actual value and operating margin.
Exelon's Response The Maximum Value Used in Analysis for Aluminum of 150 ft 2 is correct, as is the Actual Value of 86.945 ft2 . The Operating Margin should be 63.055 ft 2 .
Attachment 1 Response to RAI Revised-Final Response to Generic Letter 2004-02 Page 2 of 4
- b. The fiber values in the actual value and maximum value columns do not appear to correspond to values provided elsewhere in the submittal. For example, the values used in the analysis would likely be consistent with Attachment 1-3, Table 4. Confirm that the values for fiber shown in Attachment 1-4, Table 2 are correct. If the values are correct, please explain the apparent discrepancies.
Exelon's Response Test 2 shown in Table 4 of Attachment 1-3 has a Total Fiber Fines of 403 lbm.
There is 22.5 lbm (- 23 lbm) of latent fiber included in this total (refer to Table 4 of Attachment 1-2). The Maximum amount of E-Glass Fine Fibers is therefore 403 lbm - 23 lbm = 380 lbm which is consistent with the value given in Table 2 of Attachment 1-4.
The Actual Value for E-Glass Fine Fibers are based on the amount generated by a break in a 14" Sch. 160 line, and is not provided anywhere else in the submittal.
The fiber fines values shown in Table 4 and Table 7a are based on double-ended guillotine breaks (DEGBs) of Main Loop RCS piping. As discussed previously with the NRC, since the debris loads from these DEGB breaks are predicted to result in strainer failure based on deterministic methods it is not appropriate to consider them in a table on Operating Margins.
- c. The maximum coating values correspond to values in Table 7a of attachment 1-2, but the origin of the actual values for coatings was not apparent.
Unqualified and degraded qualified coatings are assumed to fail independent of break location. Identify the sources for each value in the "actual value" and "maximum values used in the analysis" columns. How are other sources of particulate evaluated? Should particulate be evaluated including all potential sources since that is how the analysis models particulate? If the values in the table are not taken from the submittal provide the bases for the values.
Exelon's response The Actual Values for Degraded-Qualified Coatings come from a design calculation which tabulates and tracks the amount of unqualified coatings inside containment. The Maximum coating values are documented in the same design calculation and is equal to the sum of the actual values and margin that has been assigned to assure that future unqualified coating additions to containment do not invalidate the strainer design analyses.
Other sources of particulate include Never-Qualified Coatings, Qualified Coatings in the ZOI, Latent Debris particulate, and a small amount of Nuke Tape particulate.
Margin is included for Never-Qualified coatings, and Qualified Coatings in the ZOI,
Attachment 1 Response to RAI Revised-Final Response to Generic Letter 2004-02 Page 3 of 4 but is not specifically identified in Table 2 of Attachment 1-4. No margin is assigned to Latent particulate beyond the conservative method by which this value was determined.
The total particulate amount from all these sources, including any assigned margin, is obtained by summing the contribution from each source and ensuring that the total amount is less than that determined acceptable per head loss test.
- d. It relevant to the method tor establishing margin, describe how the amount of debris considered to be margin is assessed in combination with other types of debris from potential breaks. Describe the most limiting combinations of debris that could occur (including the "margin" amounts of debris).
Exelon's Response The amount of particulate debris, including margin, from each source is summed together to yield a limiting total particulate amount which is then compared to allowable amounts as determined by head loss testing.
NRC REQUEST FOR ADDITIONAL INFORMATION
- 3. Attachment 1-2, response to issues 3b1 and 3b2 (Page 9) includes a zone of influence of 4 diameters tor welded stainless steel cassettes containing mineral wool. During the regulatory audit on January 29-31, 2019, Exelon stated that some of their cassettes were modified to use rivets. Testing has identified that riveted cassettes are much less robust than welded cassettes. Discuss whether any field modifications or repairs made to the cassettes using rivets within potential zones of influence at Calvert Cliffs do or do not result in non-conservative debris generation values tor mineral wool.
Exelon's Response The stainless steel cassettes which encase the Mineral Wool are the same design tor RMI which has a ZOI of 2 diameters. A ZOI of 4 diameters tor the Mineral Wool cassettes was assigned tor conservatism.
During original installation some Mineral Wool cassettes needed to be modified in order to allow proper fit-up. These modified cassettes were typically resealed using rivets as opposed to welding. The joint that was resealed using rivets was the circumferential joint at the end of the cassette, and not the longitudinal joint that runs along the length of the cassette which was the joint of interest during ZOI testing, because it the longitudinal joint were to tail the insulation inside the cassette would become tree. It the LOCA jet were more or less along the axis of the pipe so that it could impinge the circumferential joint straight-on only a portion
Attachment 1 Response to RAI Revised-Final Response to Generic Letter 2004-02 Page 4 of 4 of the joint would be impacted because the pipe itself would shield other portions of the joint. Furthermore, this joint has an overlapping lip to prevent water from entering the gap between cassettes. This overlapping lip would act to reinforce the circumferential joint if the LOCA jet were acting to pry it apart. Finally, the contact of the end-cap held on by the circumferential joint with the adjacent cassette would prevent the piece held on by the circumferential joint from experiencing gross failure. Therefore, the cassette is not as vulnerable to having its insulation material become debris as compared to failure of the longitudinal joint.
During the 2013 and 2014 RFOs much of the Mineral Wool inside containment was replaced with RMI. The Mineral Wool that was not replaced was in high radiation areas and was covered by lead blankets so it is not known what percentage of cassettes were modified with rivets. However, overall Mineral Wool fines now account for less than 6% of the total fiber fines generated by the limiting break, and is no longer a major debris source.