Letter Sequence Supplement |
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EPID:L-2017-LLR-0076, Relief Requests Associated with Fifth Ten-Year Inservice Testing Interval (Open) |
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MONTHYEARML17215A0072017-08-0202 August 2017 Relief Requests Associated with Fifth Ten-Year Inservice Testing Interval Project stage: Request ML17345A0912018-01-19019 January 2018 Plants, Units 1 and 2 - Request for Additional Information Regarding Alternative Request SI-RR-01, Rev. 0 (CAC Nos. MG0068 and MG0069; EPID L-2017-LLR-0078) Project stage: RAI ML18047A1242018-02-16016 February 2018 Relief Requests Associated with Fifth Ten-Year Lnservice Testing Interval: Supplement 1 - Response to Request for Additional Information Project stage: Supplement ML18117A2642018-05-10010 May 2018 Plants, Units 1 and 2 - Relief Requests for the Fifth 10-Year Interval Inservice Testing Program for Pumps and Valves Project stage: Acceptance Review ML18138A4042018-05-25025 May 2018 Plants, Units 1 and 2 - Correction to Relief Requests for the Fifth 10-Year Interval Inservice Testing Program for Pumps and Valves (EPID L-2017-LLR-0076, EPID L-2017-LLR-0077; EPID L-2017-LLR-0078) Project stage: Other 2018-02-16
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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
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Exelon Generation@
200 Exelon Way Kennett Square. PA 19348 www.exeloncorp.com 10 CFR 50.55a February 16, 2018 U.S. Nuclear Regulatory Commission ATTN: 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 NRC Docket Nos. 50-317 and 50-318
Subject:
Relief Requests Associated with Fifth Ten-Year lnservice Testing Interval -
Supplement 1 - Response to Request for Additional Information
References:
- 1. Exelon letter to the NRC, "Relief Requests Associated with Fifth Ten-Year lnservice Testing Interval," dated August 2, 2017 (ADAMS Accession No. ML17215A007)
- 2. Letter from M. Marshall (USNRC) to D. Neff (Exelon), "Calvert Cliffs Nuclear Power Plant, Units 1 and 2 - Request for Additional Information Regarding Alternative Request Sl-RR-01, Rev. O (CAC Nos. MG0068 and MG0069; EPID L-2017-LLR-0078," dated January 19, 2018 (ADAMS Accession No. ML17345A091)
In accordance with 10 CFR 50.55a, Exelon Generation Company, LLC (Exelon) requested relief requests associated with the fifth ten-year lnservice Testing (IST) interval for Calvert Cliffs Nuclear Power Plan (CCNPP), Units 1 and 2. The fifth interval of the CCNPP, Units 1 and 2 IST program complies with the ASME OM Code, 2012 Edition. The fifth ten-year interval for CCNPP, Units 1 and 2 begins on July 1, 2018, and will conclude on June 30, 2028.
During their technical review of the application, the NRC Staff identified the need for additional information. Reference 2 provided the Requests for Additional Information (RAls) and included a request for a response within 30 days of January 19, 2018. The Attachment to this letter provides the responses to the RAls.
There are no regulatory commitments contained within this letter.
lnservice Testing Relief Requests - Supplement 1 Response to Request for Additional Information Docket Nos. 50-317 and 50-318 February 16, 2018 Page 2 If you have any questions concerning this letter, please contact Mr. David Neff at (267) 533-1132.
Sincerely, David T. Gudger Manager - Licensing & Regulatory Affairs Exelon Generation Company, LLC
Attachment:
lnservice Testing Relief Requests- Supplement 1 cc: USNRC Region I, Regional Administrator USNRC Project Manager, CCNPP USNRC Senior Resident Inspector, CCNPP S. T. Gray, Maryland Department of Natural Resources
ATTACHMENT Calvert Cliffs Nuclear Power Plant, Units 1 and 2 NRC Docket Nos. 50-317 and 50-318 lnservice Testing Relief Requests - Supplement 1 Response to Request for Additional Information
lnservice Testing Relief Requests- Supplement 1 Attachment Response to Request for Additional Information Page 1 of 3 Responses to NRC Staff's Request for Additional Information By submittal dated August 2, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17215A007), Exelon Generation Company, LLC (Exelon) requested relief requests associated with the fifth ten-year lnservice Testing (IST) interval for Calvert Cliffs Nuclear Power Plan (CCNPP), Units 1 and 2. The fifth interval of the CCNPP, Units 1 and 2 IST program complies with the ASME OM Code, 2012 Edition. The fifth ten-year interval for CCNPP, Units 1 and 2 begins on July 1, 2018, and will conclude on June 30, 2028.
During their technical review of the application, the NRC Staff identified the need for additional information. In letter dated January 19, 2018, from the NRC (Michael Marshall) to Exelon (David Neff) (ADAMS Accession No. ML17345A091 ), the NRC provided Requests for Additional Information (RAls) seeking clarification of certain issues related to those relief requests. In a phone call on January 17, 2018, Mr. Neff stated that Exelon would provide a response to the RAI questions within 30 days of issuance of the NRC RAls.
In Section 4 of the alternative request, it states:
Additionally, in Generic Letter (GL) 89-04, Position 9, the NRG determined that, in cases where pump flow can only be established through a non-instrumented, minimum-flow path during quarterly pump testing, and a path exists at cold shutdown or refueling outages to perform a test of the pump under full or substantial flow conditions, the increased interval is an acceptable alternative to the Code requirements. Therefore, the proposed alternative testing of [Low Pressure Safety Injection] (LPSI) pumps as Group B during Modes 1-4 and as Group A during Modes 5-6 is consistent with GL 89-04, Position 9.
Provide an explanation describing how the proposed alternative is consistent with Generic Letter 89-04, Position 9 when the minimum recirculation flow common header used for quarterly testing is instrumented with an ultrasonic flow meter.
RESPONSE
Within GL 89-04, Position 9, discusses limitations on pump testing based on the system configuration. Specifically, the position discusses a system configuration that is designed such that the minimum-flow return line is the only flow path that can be used for quarterly pump testing. In this configuration, the pump is operating on a flat portion of the curve and the ability to detect and monitor for component degradation is limited.
However, the pump can be tested at full or substantial flow conditions during cold shutdowns or refueling outages. As stated in GL 89-04, minimum flow lines are not designed for pump testing purposes and few have installed flow measuring devices.
In the specific case for Calvert Cliffs, Unit 1 and Unit 2, the LPSI pumps have a recirculation line that is limited to providing only minimum flow protection and cannot be
lnservice Testing Relief Requests- Supplement 1 Attachment Response to Request for Additional Information Page 2 of 3 used for full flow testing. Additionally, the LPSI system piping configuration is such that it is feasible to install temporary flow measurement equipment on the recirculation line and monitor the minimum flow rate quarterly. However, the limitations for the quarterly test (i.e., can only be tested using the minimum recirculation line) are the same as discussed in the GL.
Full flow testing of the LPSI pumps can only be performed during plant shutdown conditions using the normal system flow path. All Code parameters (i.e., pump flow, differential pressure, and vibration) are monitored during the full flow test run during cold shutdowns or refueling outages.
In Section 4, it is stated that:
The low pressure safety injection (LPSI) pumps are tested at a substantial flow rate (approximately 3000 gallons per minute (gpm))
during every refueling outage, as well as during planned and unplanned cold shutdown periods when plant conditions and circumstances permit.
It is also stated that:
The quarterly tests are performed at approximately 55 - 65 gpm, which is between approximately 1.3% - 1.6% the LPSI pumps' Best Efficiency Flow rate.
There are large differences in the substantial flow rate, the best efficiency flow rate, and the low quarterly test flow rate.
- a. Are the LPSI pumps operated below the manufacturer's minimum continuous stable flow?
- b. Provide the manufacturer's recommended minimum flow and maximum run time at the minimum flow for the LPSI pumps and compare that to the flow rate and maximum run time for the LPSI pumps for the quarterly test.
- c. Explain any differences between manufacturer's recommended minimum flow and maximum run time at the minimum flow and the flow rate and maximum run time for the LPSI pumps for the quarterly test.
RESPONSE
- a. For the LPSI pumps, the manufacturer did not provide a minimum continuous stable flow but did provide the minimum pump flowrate of 40 gpm to provide thermal pump protection during low pump flows. During LPSI pump operation, the minimum flow rate is maintained between 55-65 gpm by a
lnservice Testing Relief Requests- Supplement 1 Attachment Response to Request for Additional Information Page 3 of 3 permanently installed flow orifice in the minimum recirculation line and is above the manufacturer's recommended minimum flow rate.
- b. For the LPSI pumps, the manufacturer's recommended minimum flow rate is 40 gpm but a maximum run time at the minimum flow rate was not provided by the manufacturer.
During pump operation, including the quarterly surveillance tests, the minimum flow rate is maintained between 55-65 gpm by a permanently installed flow orifice in the minimum recirculation line and is above the manufacturer's recommended minimum flow rate. This flow rate is measured by temporarily installed ultrasonic flowmeters. While no maximum run time for the LPSI pumps was provided, there are several factors employed to minimize the potential for degradation of the LPSI pumps due to low pump flows . These factors are discussed below.
- c. For the minimum pump flowrates, the LPSI pump quarterly surveillance testing is in conformance with the manufacturer's recommended minimum flow rate and there is no further explanation necessary.
For the maximum run time consideration, design, vibration monitoring and operating factors are employed instead to minimize the potential for pump degradation due to low pump flows. These factors include a stainless-steel pump impeller design, pump vibration monitoring during testing, vibration trending and augmented pump internal inspections. These factors were included in the NRC accepted response to NRC Bulletin 88-04, "Potential Safety-Related Pump Loss," for CCNPP, Units 1 and 2, dated July 5, 1988.
This response stated the LPSI pumps have adequate flow (Item 1) and the minimum flow bypass line was determined to be adequate provided vibration monitoring was employed and acceptable stable vibration levels were observed at the minimum flow conditions (Item 3.8). Augmented pump inspections would be necessary if pump vibration levels do not remain unchanged (Item 3.B).
Furthermore, in Section 4 of the alternative request, several operational factors are requested that will continue to minimize the cumulative run-time for each LPSI pump under low-flow conditions. These factors include elimination of the two-minute minimum pump run-time for quarterly tests and combining the IST pump test into the engineering safety features actuation logic test for each pump when the testing is scheduled in the same quarter.
These factors have been in place in accordance with the same alternative request approved for the previous IST intervals. Testing and Maintenance history has shown that the LPSI pumps' vibration levels have remained stable and internal pump inspections have shown no abnormal pump degradation and indicates no adverse impact from low-flow conditions.