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| | issue date = 11/07/2013 | | | issue date = 11/07/2013 |
| | title = Correction Letter to Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation | | | title = Correction Letter to Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation |
| | author name = Paige J C | | | author name = Paige J |
| | author affiliation = NRC/NRR/DORL/LPLII-1 | | | author affiliation = NRC/NRR/DORL/LPLII-1 |
| | addressee name = Capps S D | | | addressee name = Capps S |
| | addressee affiliation = Duke Energy Carolinas, LLC | | | addressee affiliation = Duke Energy Carolinas, LLC |
| | docket = 05000369, 05000370 | | | docket = 05000369, 05000370 |
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| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555*0001 November 7, 2013 Mr. Steven D. Capps Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078 MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 -CORRECTION LETTER TO INTERIM STAFF EVALUATION AND REQUEST FOR ADDITIONAL INFORMATION REGARDING THE OVERALL INTEGRATED PLAN FOR IMPLEMENTATION OF ORDER EA-12-051, RELIABLE SPENT FUEL POOL INSTRUMENTATION (TAC NOS. MF1062 AND MF1063) | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 November 7, 2013 Mr. Steven D. Capps Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078 |
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| | ==SUBJECT:== |
| | MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 - CORRECTION LETTER TO INTERIM STAFF EVALUATION AND REQUEST FOR ADDITIONAL INFORMATION REGARDING THE OVERALL INTEGRATED PLAN FOR IMPLEMENTATION OF ORDER EA-12-051, RELIABLE SPENT FUEL POOL INSTRUMENTATION (TAC NOS. MF1062 AND MF1063) |
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| ==Dear Mr. Capps:== | | ==Dear Mr. Capps:== |
| By letter dated October 28, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 13281 A791), the U.S. Nuclear Regulatory Commission issued an interim staff evaluation and requests for additional information regarding the overall integrated plan for implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation. | | |
| | By letter dated October 28, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13281A791), the U.S. Nuclear Regulatory Commission issued an interim staff evaluation and requests for additional information regarding the overall integrated plan for implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation. |
| Due to an inadvertent error, pages 15,16, and 30 were omitted from the October 28,2013, document. | | Due to an inadvertent error, pages 15,16, and 30 were omitted from the October 28,2013, document. |
| Enclose please find pages 15, 16, and 30. \ <: J ason C. Paige, Project Manager ilt Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370 | | Enclose please find pages 15, 16, and 30. |
| | ~/;, |
| | ! J |
| | \ <: |
| | ason C. Paige, Project Manager ilt Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370 |
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| ==Enclosure:== | | ==Enclosure:== |
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| As stated cc w/encl: Distribution via Listserv | | As stated cc w/encl: Distribution via Listserv |
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| | ENCLOSURE MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 INTERIM STAFF EVALUATION AND REQUEST FOR ADDITIONAL INFORMATION REGARDING THE OVERALL INTEGRATED PLAN FOR IMPLEMENTATION OF ORDER EA-12-051, RELIABLE SPENT FUEL POOL INSTRUMENTATION (TAC NOS. MF1062 AND MF1063) |
| | Pages 15, 16, and 30 |
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| | - 15 RAI #12 Please provide information indicating the maximum expected relative humidity in the room in which the associated sensor electronics will be located under BOB conditions, in which there is no ac power available to run HVAC systems, and whether the sensor electronics is capable of continuously performing its required functions under this expected humidity condition. |
| | Related to the impact of post-event radiological conditions on the primary SFP level instrumentation channel, in its letter dated July 11, 2013, the licensee stated, in part, that The area above and around the pool will be subject to large amounts of radiation in the event water level decreases near the top of the fuel racks. The only parts of the measurement channel in the pool radiation environment are the metallic waveguide and horn, which are not susceptible to the expected levels of radiation. The sensor electronics will be located in an area that does not exceed their 1x1 0 3 rad design limit for the required operating time, or the design will provide shielding as required. |
| | The NRC staff has concerns with the licensee's lack of information regarding its analysis of the maximum expected radiological conditions for the location of the sensor electronics that might be considered credible under BDB conditions. The staff is also concerned with the lack of documentation indicating how it was determined that the electronics can withstand a total integrated dose of 1X10 3 Rads. The staff has identified this request as: |
| | RAI #13 Please provide analysis of the maximum expected radiological conditions (dose rate and total integrated dose) for the location of the sensor electronics that might be considered credible under BOB conditions. Also, please provide documentation indicating how it was determined that the electronics for this equipment is capable of withstanding a total integrated dose of 1X103 Rads. Please discuss the time period over which the analyzed total integrated dose was applied. |
| | 3.6.3 Shock and Vibration NEI 12-02 states, in part, that Applicable components of the instrument channels are rated by the manufacturer (or otherwise tested) for shock and vibration at levels commensurate with those of postulated design basis event conditions in the area of instrument channel component use uSing one or more of the following methods: |
| | * instrument channel components use known operating principles, are supplied by manufacturers with commercial quality programs (such as IS09001) with shock and vibration requirements included in the purchase specification and/or instrument design, and commercial design and testing for operation in |
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| | - 16 environments where significant shock and vibration loadings are cornmon, such as for portable hand-held devices or transportation applications; |
| | * substantial history of operational reliability in environments with significant shock and vibration loading, such as transportation applications, or |
| | * use of component inherently resistant to shock and vibration loadings or are seismically reliable such as cables. |
| | In its letter dated July 11, 2013, the licensee stated, in part The VEGAPuls 62ER Through Air Radar sensor is similar in form, fit and function to the VEGAPuls 66 that was shock and vibration tested in accordance with MILS-901D and MIL-STD-167-1. This shock and vibration testing only applies to the sensor. The waveguide piping is %" diameter Schedule 40 piping and is seismically anchored to the floor. Thus the waveguide piping is not considered to be sensitive to shock or vibration. |
| | The power supply panel contains components that are part of the standard VEGA Mobile Remote Display. In addition, the readout portion of the display panel, the PLlCSCOM, was installed in the sensor during the shock and vibration testing. The Mobile Remote Display is designed for truck-mounted mobile applications subject to shock and vibration from normal handling, after transportation and setup on the job. Per NEI 12-02, designing instruments for operation in environments where significant shock and vibration loadings are common, such as for portable hand-held devices or transportation applications, is an acceptable measure for verifying that the design is adequate to withstand shock and vibration. This panel is therefore considered to have an acceptable resistance to shock and vibration. There are three components in the AREVA power control panel that are not included with the VEGA Mobile Remote Display but are similar in construction and are tested for shock and vibration and/or mounted on vibration dampeners. This panel also will be subjected to seismic tests. |
| | The main control room displaylindicator will be seismically mounted, and is seismically qualified based on similarity to other control board indicators. |
| | The NRC staff notes that the use of MI L-STD-901 D appears to be a reasonable method for shock testing. However, the staff has concerns regarding the licensee's lack of information describing the tests, applied forces, and the operability condition of the sensor after the tests were completed. The staff has identified this request as: |
| | RAI #14 Please provide information describing the evaluation of the comparative sensor design, the shock test method, test results, and forces applied to the sensor applicable to its successful tests demonstrating that the referenced previous testing provides an |
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| | - 30 RAI #24 Please provide the following: |
| | a) Further information describing the testing and calibration program the licensee will establish and implement to ensure that regular testing and calibration is performed and verified by inspection and audit to demonstrate conformance with design and system readiness requirements. Please include a description of the plans for ensuring that necessary channel checks, functional tests, periodic calibration, and maintenance will be conducted for the level measurement system and its supporting equipment. |
| | b) Information describing compensatory actions when both channels are out~of order. |
| | c) Additional information describing expedited and compensatory actions in the maintenance procedure to address when one of the instrument channels cannot be restored to functional status within 90 days. |
| | The NRC staff has concerns regarding the feasibility of the licensee's process for in-situ calibration to ensure that the design accuracy will be maintained. The staff has identified the following requests as: |
| | RAI #25 Please provide a description of the in-situ calibration process at the SFP location that will result in the channel calibration being maintained at its design accuracy. |
| | 3.15 Instrument Reliability NEI 12-02 states, in part, that A spent fuel pool level instrument channel is considered reliable when the instrument channel satisfies the design elements listed in Section 3 [Instrument Design Features] of this guidance and the plant operator has fully implemented the programmatic features listed in Section 4 [Program Features]. |
| | In its OIP, the licensee stated, in part Reliability of the level instrumentation will be assured by conformance with the guidelines of NRC JlD-ISG-2012-03 and NEI 12-02, as described below. |
| | Upon acceptable resolution of the RAls noted above, the NRC staff will be able to make a conclusion regarding the reliability of the SFP instrumentation. |
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| MCGUIRE NUCLEAR STATION, UNITS 1 AND INTERIM STAFF EVALUATION AND REQUEST FOR ADDITIONAL REGARDING THE OVERALL INTEGRATED PLAN FOR IMPLEMENTATION OF EA-12-051, RELIABLE SPENT FUEL POOL (TAC NOS. MF1062 AND Pages 15, 16, and
| | November 7, 2013 Mr. Steven D. Capps Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078 |
| -15 RAI Please provide information indicating the maximum expected relative humidity in the room in which the associated sensor electronics will be located under BOB conditions, in which there is no ac power available to run HVAC systems, and whether the sensor electronics is capable of continuously performing its required functions under this expected humidity condition.
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| Related to the impact of post-event radiological conditions on the primary SFP level instrumentation channel, in its letter dated July 11, 2013, the licensee stated, in part, that The area above and around the pool will be subject to large amounts of radiation in the event water level decreases near the top of the fuel racks. The only parts of the measurement channel in the pool radiation environment are the metallic waveguide and horn, which are not susceptible to the expected levels of radiation.
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| The sensor electronics will be located in an area that does not exceed their 1 x1 0 3 rad design limit for the required operating time, or the design will provide shielding as required.
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| The NRC staff has concerns with the licensee's lack of information regarding its analysis of the maximum expected radiological conditions for the location of the sensor electronics that might be considered credible under BDB conditions.
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| The staff is also concerned with the lack of documentation indicating how it was determined that the electronics can withstand a total integrated dose of 1X10 3 Rads. The staff has identified this request as: RAI #13 Please provide analysis of the maximum expected radiological conditions (dose rate and total integrated dose) for the location of the sensor electronics that might be considered credible under BOB conditions.
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| Also, please provide documentation indicating how it was determined that the electronics for this equipment is capable of withstanding a total integrated dose of 1X10 3 Rads. Please discuss the time period over which the analyzed total integrated dose was applied. 3.6.3 Shock and Vibration NEI 12-02 states, in part, that Applicable components of the instrument channels are rated by the manufacturer (or otherwise tested) for shock and vibration at levels commensurate with those of postulated design basis event conditions in the area of instrument channel component use uSing one or more of the following methods: instrument channel components use known operating principles, are supplied by manufacturers with commercial quality programs (such as IS09001) with shock and vibration requirements included in the purchase specification and/or instrument design, and commercial design and testing for operation in
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| -16 environments where significant shock and vibration loadings are cornmon, such as for portable hand-held devices or transportation applications; substantial history of operational reliability in environments with significant shock and vibration loading, such as transportation applications, or use of component inherently resistant to shock and vibration loadings or are seismically reliable such as cables. In its letter dated July 11, 2013, the licensee stated, in part The VEGAPuls 62ER Through Air Radar sensor is similar in form, fit and function to the VEGAPuls 66 that was shock and vibration tested in accordance with MILS-901D and MIL-STD-167-1.
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| This shock and vibration testing only applies to the sensor. The waveguide piping is %" diameter Schedule 40 piping and is seismically anchored to the floor. Thus the waveguide piping is not considered to be sensitive to shock or vibration.
| |
| The power supply panel contains components that are part of the standard VEGA Mobile Remote Display. In addition, the readout portion of the display panel, the PLlCSCOM, was installed in the sensor during the shock and vibration testing. The Mobile Remote Display is designed for truck-mounted mobile applications subject to shock and vibration from normal handling, after transportation and setup on the job. Per NEI 12-02, designing instruments for operation in environments where significant shock and vibration loadings are common, such as for portable hand-held devices or transportation applications, is an acceptable measure for verifying that the design is adequate to withstand shock and vibration.
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| This panel is therefore considered to have an acceptable resistance to shock and vibration.
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| There are three components in the AREVA power control panel that are not included with the VEGA Mobile Remote Display but are similar in construction and are tested for shock and vibration and/or mounted on vibration dampeners.
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| This panel also will be subjected to seismic tests. The main control room displaylindicator will be seismically mounted, and is seismically qualified based on similarity to other control board indicators.
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| The NRC staff notes that the use of MI L-STD-901 D appears to be a reasonable method for shock testing. However, the staff has concerns regarding the licensee's lack of information describing the tests, applied forces, and the operability condition of the sensor after the tests were completed.
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| The staff has identified this request as: RAI #14 Please provide information describing the evaluation of the comparative sensor design, the shock test method, test results, and forces applied to the sensor applicable to its successful tests demonstrating that the referenced previous testing provides an
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| -RAI #24 Please provide the following: Further information describing the testing and calibration program the licensee will establish and implement to ensure that regular testing and calibration is performed and verified by inspection and audit to demonstrate conformance with design and system readiness requirements.
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| Please include a description of the plans for ensuring that necessary channel checks, functional tests, periodic calibration, and maintenance will be conducted for the level measurement system and its supporting equipment. Information describing compensatory actions when both channels are order. Additional information describing expedited and compensatory actions in the maintenance procedure to address when one of the instrument channels cannot be restored to functional status within 90 days. The NRC staff has concerns regarding the feasibility of the licensee's process for in-situ calibration to ensure that the design accuracy will be maintained.
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| The staff has identified the following requests as: RAI #25 Please provide a description of the in-situ calibration process at the SFP location that will result in the channel calibration being maintained at its design accuracy.
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| 3.15 Instrument Reliability NEI 12-02 states, in part, that A spent fuel pool level instrument channel is considered reliable when the instrument channel satisfies the design elements listed in Section 3 [Instrument Design Features]
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| of this guidance and the plant operator has fully implemented the programmatic features listed in Section 4 [Program Features].
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| In its OIP, the licensee stated, in part Reliability of the level instrumentation will be assured by conformance with the guidelines of NRC JlD-ISG-2012-03 and NEI 12-02, as described below. Upon acceptable resolution of the RAls noted above, the NRC staff will be able to make a conclusion regarding the reliability of the SFP instrumentation.
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| Mr. Steven D. Capps Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078 November 7, 2013 | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| MCGUIRE NUCLEAR STATION, UNITS 1 AND 2-CORRECTION LETTER TO INTERIM STAFF EVALUATION AND REQUEST FOR ADDITIONAL INFORMATION REGARDING THE OVERALL INTEGRATED PLAN FOR IMPLEMENTATION OF ORDER EA-12-051, RELIABLE SPENT FUEL POOL INSTRUMENTATION (TAC NOS. MF1062 AND MF1063) | | MCGUIRE NUCLEAR STATION, UNITS 1 AND 2- CORRECTION LETTER TO INTERIM STAFF EVALUATION AND REQUEST FOR ADDITIONAL INFORMATION REGARDING THE OVERALL INTEGRATED PLAN FOR IMPLEMENTATION OF ORDER EA-12-051, RELIABLE SPENT FUEL POOL INSTRUMENTATION (TAC NOS. MF1062 AND MF1063) |
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| ==Dear Mr. Capps:== | | ==Dear Mr. Capps:== |
| By letter dated October 28, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 13281 A791 ), the U.S. Nuclear Regulatory Commission issued an interim staff evaluation and requests for additional information regarding the overall integrated plan for implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation. | | |
| | By letter dated October 28, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13281A791 ), the U.S. Nuclear Regulatory Commission issued an interim staff evaluation and requests for additional information regarding the overall integrated plan for implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation. |
| Due to an inadvertent error, pages 15, 16, and 30 were omitted from the October 28, 2013, document. | | Due to an inadvertent error, pages 15, 16, and 30 were omitted from the October 28, 2013, document. |
| Enclose please find pages 15, 16, and 30. Docket Nos. 50-369 and 50-370 | | Enclose please find pages 15, 16, and 30. |
| | Sincerely, IRA/ |
| | Jason C. Paige, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370 |
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| ==Enclosure:== | | ==Enclosure:== |
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| As stated cc w/encl: Distribution via Listserv DISTRIBUTION: | | As stated cc w/encl: Distribution via Listserv DISTRIBUTION: |
| PUBLIC LPL2-1 R/F RidsNrrDoriDpr Resource RidsNrrDorllpl2-1 Resource RidsNrrDirsltsb Resource RidsNrrLASFigueroa Resource RidsAcrsAcnw_MaiiCTR Resource RidsRgn2MaiiCenter Resource RidsNrrPMMcGuire Resource (hard copy) Correction Letter No | | PUBLIC LPL2-1 R/F RidsNrrDoriDpr Resource RidsNrrDorllpl2-1 Resource RidsNrrDirsltsb Resource RidsNrrLASFigueroa Resource RidsAcrsAcnw_MaiiCTR Resource RidsRgn2MaiiCenter Resource RidsNrrPMMcGuire Resource (hard copy) |
| * ML 13309A782
| | Correction Letter No ..* ML13309A782 *via e-mail OFFICE NRR/LPL2-1/PM NRR/LPL2-1 /LA NRR/LPL2-1/BC NRR/LPL2-1/PM NAME JPaige SFigueroa RPascarelli JPaige DATE 11/6/13 11/6/13 11/7/13 11/7/13 OFFICIAL RECORD COPY}} |
| .. OFFICE NRR/LPL2-1/PM NAME JPaige DATE 11/6/13 Sincerely, IRA/ Jason C. Paige, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation | |
| *via e-mail NRR/LPL2-1
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| /LA NRR/LPL2-1/BC NRR/LPL2-1/PM SFigueroa RPascarelli JPaige 11/6/13 11/7/13 11/7/13 OFFICIAL RECORD COPY}} | |
Letter Sequence RAI |
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MONTHYEARML13157A0972013-06-13013 June 2013 Request for Additional Information Overall Integrated Plan in Response to Order EA-12-051, Reliable Spent Fuel Pool Instrumentation Project stage: RAI ML13197A4092013-07-11011 July 2013 Response to Request for Additional Information Regarding Overall Integrated Plan in Response to Order EA-12-051, Reliable Spent Fuel Pool Instrumentation. Project stage: Response to RAI ML13242A0092013-08-26026 August 2013 Duke Energy - First Six-Month Status Reports in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) Project stage: Other ML13281A7912013-10-28028 October 2013 Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fool Instrumentation (TAC Nos. MF1062 and MF1063) Project stage: RAI ML13309A7822013-11-0707 November 2013 Correction Letter to Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation Project stage: RAI ML13353A1422013-12-20020 December 2013 Correction Letter to Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation Project stage: RAI ML14097A4262014-04-10010 April 2014 William B. McGuire Nuclear Station, Units 1 and 2 - Plan for the Onsite Audit of Areva Regarding Implementation of Reliable Spent Fuel Pool Instrumentation Related to Order EA-12-051 Project stage: Other ML14181B3212014-07-0808 July 2014 Plan for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Instrumentation Related to Orders EA-12-049 and EA-12-051 Project stage: Other ML14203A3262014-09-15015 September 2014 William B. McGuire Nuclear Station, Units 1 and 2 - Report for the Onsite Audit of Areva Regarding Implementation of Reliable Spent Fuel Pool Instrumentation Related to Order EA-12-051 Project stage: Acceptance Review 2013-07-11
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Category:Letter
MONTHYEARIR 05000369/20244042024-08-0101 August 2024 Cover Letter Security Baseline Inspection Report 05000369/2024404 and 05000370/2024404 IR 05000369/20253012024-07-29029 July 2024 Notification of Licensed Operator Initial Examination 05000369/2025301 and 05000370/2025301 IR 05000369/20240022024-07-24024 July 2024 Integrated Inspection Report 05000369/2024002 and 05000370/2024002 ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 IR 05000369/20244012024-07-0303 July 2024 – Security Baseline Inspection Report 05000369/2024401 and 05000370/2024401 ML24176A2802024-06-26026 June 2024 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000369-2024404 and 05000370-2024404) IR 05000369/20240112024-06-0404 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000369/2024011 and 05000370/2024011 ML24149A1772024-05-28028 May 2024 NRC Response to Duke Energy 2025 FOF Schedule Change Request (Catawba and McGuire) IR 05000369/20240012024-05-0808 May 2024 Integrated Inspection Report 05000369-2024001 and 05000370-2024001 and 07200038-2024001 ML24110A0382024-04-30030 April 2024 – Correction to Issuance of Amendment Nos. 330 and 309, Regarding Implementation of Technical Specifications Task Force (TSTF) Traveler TSTF 505, Revision 2, “Provide Risk-Informed Extended Completion Times - Ritstf IR 05000369/20244032024-04-10010 April 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000369/2024403; and 05000370/2024403 ML24052A3062024-04-0808 April 2024 Issuance of Amendment Nos. 331 & 310, Regarding Adoption of Title 10 of Code of Federal Regulations Section 50.69, “Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Plants ML24031A5402024-03-26026 March 2024 Issuance of Amendment Nos. 330 and 309 Regarding Implementation of TSTF 505,Rev. 2, “Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B ML24085A2402024-03-21021 March 2024 Requalification Program Inspection - McGuire Nuclear Station IR 05000369/20240102024-03-13013 March 2024 Comprehensive Engineering Team Inspection Report 05000369/2024010 and 05000370/2024010 IR 05000369/20230062024-02-28028 February 2024 Annual Assessment Letter for McGuire Nuclear Station, Units 1 and 2 - NRC Inspection Report 05000369/2023006 and 05000370/2023006 ML24024A2182024-02-0505 February 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) IR 05000369/20230042024-01-31031 January 2024 Integrated Inspection Report 05000369/2023004 and 05000370/2023004 ML24019A1392024-01-25025 January 2024 TSTF 505 and 50.69 Audit Summary ML24019A2002024-01-24024 January 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000369/20234022023-12-14014 December 2023 Material Control and Accounting Program Inspection Report 05000369/2023402 and 05000370/2023402 ML23317A2272023-11-17017 November 2023 William B. McGuire Nuclear Station, Units 1 and 2 - Transmittal of Dam Inspection Report - Non-Proprietary ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000369/20230032023-10-24024 October 2023 Integrated Inspection Report 05000369/2023003 and 05000370/2023003; and Inspection Report 07200038/2023001 IR 05000369/20230102023-10-13013 October 2023 Age Related Degradation Inspection Report 05000369/2023010 and 05000370/2023010 ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds IR 05000369/20233012023-09-20020 September 2023 William B. McGuire Nuclear Station - NRC Examination Report 05000369/2023301 and 05000370/2023301 ML23230A0652023-08-31031 August 2023 William B. McGuire Nuclear Station, Units 1 and 2 - Relief Request Use of Later Edition of ASME Code ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000369/20230052023-08-25025 August 2023 Updated Inspection Plan for McGuire Nuclear Station Units 1 and 2 (Report 05000369/2023005 and 05000370/2023005) IR 05000369/20230022023-07-28028 July 2023 Integrated Inspection Report 05000369/2023002 and 05000370/2023002 IR 05000369/20234202023-07-24024 July 2023 Security Baseline Inspection Report 050003692023420 and 050003702023420 ML23206A0092023-07-24024 July 2023 William B. McGuire Nuclear Station Operator Licensing Written Examination Approval 05000369/2023301 and 05000370/2023301 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 ML23159A2712023-06-20020 June 2023 William B. McGuire Nuclear Station, Unit 1 - Relief Request Impractical Reactor System Welds ML23237A2672023-06-13013 June 2023 June 13, 2002 - Meeting Announcement - McGuire and Catawba Nuclear Stations 50-369, 50-370 and 50-413, 50-414 ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML23115A2122023-05-0101 May 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report IR 05000369/20230012023-05-0101 May 2023 Integrated Inspection Report 05000369/2023001 and 05000370/2023001 ML23094A1832023-04-18018 April 2023 Audit Plan TSTF-505, Rev. 2, RITSTF Initiative 4B & 10 CFR 50.69, Risk-Informed Categorization & Treatment of Structures, Systems & Components for Nuclear Power Reactors (EPIDs L-2023-LLA-0021 & L-2023-LLA-0022) ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000369/20220062023-03-0101 March 2023 Annual Assessment Letter for McGuire Nuclear Station Units 1 and 2 (NRC Inspection Report 05000369/2022006 and 05000370 2022006) IR 05000369/20220042023-01-30030 January 2023 Mcguire Nuclear Station - Integrated Inspection Report 05000369/2022004 and 05000370/2022004 IR 05000369/20224202023-01-11011 January 2023 Security Baseline Inspection Report 05000369/2022420 and 05000370/2022420 ML22356A0512022-12-14014 December 2022 Curtiss-Wright Nuclear Division, Letter Regarding Potential Efect in a Configuration of the 11/2 Inch Quick Disconnect Connector Cable Assemblies Supplied to Duke Energy (See Attached Spreadsheet) for a Total of 460 of Connectors Only Suppl ML22347A1512022-12-13013 December 2022 William B. Mcguire Nuclear Station Notification of Licensed Operator Initial Examination 05000369/2023301 and 05000370/2023301 ML22340A6662022-12-0808 December 2022 Summary of November 30, 2022, Public Meeting with Duke Energy Carolinas, LLC for McGuire Nuclear Station, Units 1 & 2 Proposed LAR to Adopt TSTF-505, Rev. 2 and 10 CFR 50.69 Risk-Informed Categorization and Treatment of Structures, Systems ML22290A1012022-11-29029 November 2022 Issuance of Amendment Nos. 326 and 305, Regarding Changes to Technical Specification 3.4.3, Reactor Coolant System Pressure Temperature Limits ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations 2024-08-01
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24197A1702024-07-15015 July 2024 Request for Additional Information Two Proposed Alternatives (RA-23-0242) for the Inspection of Reactor Vessel Closure Head Penetrations ML23151A3482023-05-30030 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML23142A2732023-05-22022 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) ML23030B9032023-01-30030 January 2023 Formal Release of RAIs for McGuire Unit 1, Relief Request Impractical RPV Rx Coolant System Welds, Due March 1, 2023 (Email) ML23017A2232023-01-13013 January 2023 Request for Additional Information (RAI) Issuance for McGuire Unit 1 Steam Generator Tube Inspection Report (Email) ML22175A0162022-06-24024 June 2022 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML22115A1412022-04-25025 April 2022 NRR E-mail Capture - Duke Common EOF Relocation - Request for Addition Information ML22102A2962022-04-13013 April 2022 Request for Withholding Information from Public Disclosure Response to Request for Additional Information ML22063B1782022-03-0909 March 2022 Request for Additional Information Regarding LAR for Revision to the Conditional Exemption of the End of Cycle Moderator Temperature Coefficient Measurement Methodology (EPID L-2021-LLA-0198) NON-PROPRIETARY ML22010A0732022-01-0606 January 2022 50.59 Inspection Information Request ML21354A8612021-12-15015 December 2021 NRR E-mail Capture - Request for Additional Information - Duke Fleet Request RA-19-0352 - Alternative for RPV Closure Stud Exams (L-2020-LLR-0156) ML21267A2782021-09-23023 September 2021 50.59 Inspection Information Request ML21252A0532021-09-0808 September 2021 NRR E-mail Capture - Formal Release of Rais, 30 Day Response, Mcguire Relief Request, Ref: Later Edition Addenda ASME Code, Section XI, 50.55a(g)(4)(iv) ML21103A0542021-04-13013 April 2021 NRR E-mail Capture - Extension to Request for Additional Information AMS Topical Report AMS-TR-0720R1 ML21067A6742021-03-0505 March 2021 NRR E-mail Capture - Final Request for Additional Information AMS Topical Report AMS-TR-0720R1 ML21049A2632021-02-0404 February 2021 NRR E-mail Capture - Request for Additional Information - Duke Energy Fleet License Amendment Request to Revise Emergency Plan ML21020A0682021-01-20020 January 2021 Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000369/2021011 and 05000370/2021011) and Request for Information (RFI) ML20346A0212020-12-10010 December 2020 NRR E-mail Capture - Formal Release of RAIs - License Amendment to Change TS 3.8.1 Due Jan. 29, 2021 ML20323A4072020-11-18018 November 2020 NRR E-mail Capture - Request for Additional Information - Brunswick License Exemption Request from 10CFR73 Annual Force on Force Exercise Requirements (EPIC L-2020-LLE-0180) ML20216A3512020-08-0303 August 2020 Mcquire U-1 ISI RFI ML20101L3132020-04-10010 April 2020 Notification of Inspection and Request for Information ML20071D0962020-03-0505 March 2020 NRR E-mail Capture - Request for Additional Information - McGuire Nuclear Station Unit 1 Delay in Update of the Code of Record for in Service Inspections ML20050D3382020-02-21021 February 2020 Letter RAI 1 MAGNASTOR-Catawba and McGuire Exemptions with Enclosure ML19354B6372020-01-0707 January 2020 Exemption Request for NAC Magnastor Cask Loaded to Incorrect Helium Backfill Density Request for Additional Information ML19011A1372019-01-10010 January 2019 NRR E-mail Capture - Duke Energy Fleet RAIs - Relief Request 18-GO-001 - Proposed Alternative for Depth Sizing Qualification Examination of Welds (L-2018-LLR-0117) ML19007A3422018-12-21021 December 2018 NRR E-mail Capture - Duke Energy Fleet Draft RAIs - Relief Request 18-GO-001 - Proposed Alternative for Depth Sizing Qualification Examination of Welds (L-2018-LLR-0117) ML18352A8052018-12-18018 December 2018 NRR E-mail Capture - Request for Additional Information - McGuire Nuclear Station, Units 1 and 2 - MRP-227 Review ML18306A9372018-11-0202 November 2018 NRR E-mail Capture - Request for Additional Information - McGuire Nuclear Station, Units 1 and 2 - Esps LAR ML18285A0812018-10-11011 October 2018 NRR E-mail Capture - Request for Additional Information - McGuire Nuclear Station, Units 1 and 2 - TORMIS LAR RA-18-0011, Response to Request for Supplemental Information Regarding Duke Energy'S Response to GL 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools2018-05-30030 May 2018 Response to Request for Supplemental Information Regarding Duke Energy'S Response to GL 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools ML18138A4662018-05-18018 May 2018 NRR E-mail Capture - Request for Additional Information - McGuire Nuclear Station, Units 1 and 2 - TORMIS LAR ML18088B2822018-03-29029 March 2018 Requalification Program Inspection - McGuire Nuclear Station ML18057A2182018-02-23023 February 2018 Enclosurequest for Additional Information (Letter to A. Zaremba Request for Additional Information for Review of Duke Energy'S Decommissioning Funding Plan Update) ML17331B1492017-11-21021 November 2017 NRR E-mail Capture - Request for Additional Information - McGuire Nuclear Station, Units 1 and 2 - Nsws One-Time LAR (CACs MG0242 and MG0243, EPID L-2017-LLA-0299) ML17317B0932017-11-13013 November 2017 NRR E-mail Capture - Request for Additional Information - McGuire Nuclear Station, Units 1 and 2 - Irlt (CACs MF9020 and MF9021; EPID L-2016-LLA-0032) ML17230A1512017-08-15015 August 2017 Notification of Inspection of Inspection and Request for Information ML17192A4842017-07-11011 July 2017 NRR E-mail Capture - Duke Energy Fleet RAIs Alternative for Reactor Pressure Vessel Flange Threads Examination (MF9513 to MF9521) ML17135A0322017-05-12012 May 2017 NRR E-mail Capture - Request for Additional Information - McGuire TSTF-197 ML17114A4992017-04-17017 April 2017 Emergency Preparedness Inspection and Request for Information ML16302A1122016-11-0404 November 2016 Request for Additional Information Regarding License Amendment Request to Implement a Risk-Informed, Performance-Based Fire Protection Program (CAC Nos. MF2934 and MF2935) MNS-16-077, Responding to Request for Additional Information Related to License Amendment Request to Implement a Risk-informed Performance-Based Fire Protection Program2016-09-29029 September 2016 Responding to Request for Additional Information Related to License Amendment Request to Implement a Risk-informed Performance-Based Fire Protection Program ML16228A2612016-08-15015 August 2016 Email - McGuire Unit No. 1: Request for Additional Informati- Relief Request 16-MN-003 Alternative to Defect Removal Prior to Performing Temporary Repair Activities on Three-Inch-Diameter Nuclear Service Water System Piping. ML16194A2862016-07-12012 July 2016 E-Mail - Mcguirai Ice Condenser Door Position Alternate Verification, (ML16089A228) CAC Nos. MF7526 and MF7527 ML16175A0222016-07-12012 July 2016 Request for Additional Information Regarding License Amendment Request to Implement a Risk-Informed, Performance-Based Fire Protection Program ML16014A6882016-01-20020 January 2016 Request for Additional Information Regarding License Amendment Request to Revise Emergency Action Level Scheme ML15348A2602015-12-17017 December 2015 Request for Additional Information Regarding License Amendment Request to Use an Alternative Fission Gas Gap Release Fraction ML15320A3862015-11-19019 November 2015 RAI LAR to Adopt TSTF-523 ML15314A3592015-11-10010 November 2015 Duke Energy Draft RAIs Request to Adopt TSTF-523 (CAC Nos. MF6413-MF6422) ML15314A3562015-11-10010 November 2015 E-mail from J. Whited to A. Zaremba Duke Energy Draft RAIs License Amendment Request to Adopt TSTF-523 (CAC Nos. MF6413-MF6422) ML15289A5552015-10-26026 October 2015 Request for Additional Information Regarding License Amendment Request Nuclear Service Water System Allowed Outage Time Extension 2024-07-15
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 November 7, 2013 Mr. Steven D. Capps Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078
SUBJECT:
MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 - CORRECTION LETTER TO INTERIM STAFF EVALUATION AND REQUEST FOR ADDITIONAL INFORMATION REGARDING THE OVERALL INTEGRATED PLAN FOR IMPLEMENTATION OF ORDER EA-12-051, RELIABLE SPENT FUEL POOL INSTRUMENTATION (TAC NOS. MF1062 AND MF1063)
Dear Mr. Capps:
By letter dated October 28, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13281A791), the U.S. Nuclear Regulatory Commission issued an interim staff evaluation and requests for additional information regarding the overall integrated plan for implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation.
Due to an inadvertent error, pages 15,16, and 30 were omitted from the October 28,2013, document.
Enclose please find pages 15, 16, and 30.
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ason C. Paige, Project Manager ilt Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370
Enclosure:
As stated cc w/encl: Distribution via Listserv
ENCLOSURE MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 INTERIM STAFF EVALUATION AND REQUEST FOR ADDITIONAL INFORMATION REGARDING THE OVERALL INTEGRATED PLAN FOR IMPLEMENTATION OF ORDER EA-12-051, RELIABLE SPENT FUEL POOL INSTRUMENTATION (TAC NOS. MF1062 AND MF1063)
Pages 15, 16, and 30
- 15 RAI #12 Please provide information indicating the maximum expected relative humidity in the room in which the associated sensor electronics will be located under BOB conditions, in which there is no ac power available to run HVAC systems, and whether the sensor electronics is capable of continuously performing its required functions under this expected humidity condition.
Related to the impact of post-event radiological conditions on the primary SFP level instrumentation channel, in its letter dated July 11, 2013, the licensee stated, in part, that The area above and around the pool will be subject to large amounts of radiation in the event water level decreases near the top of the fuel racks. The only parts of the measurement channel in the pool radiation environment are the metallic waveguide and horn, which are not susceptible to the expected levels of radiation. The sensor electronics will be located in an area that does not exceed their 1x1 0 3 rad design limit for the required operating time, or the design will provide shielding as required.
The NRC staff has concerns with the licensee's lack of information regarding its analysis of the maximum expected radiological conditions for the location of the sensor electronics that might be considered credible under BDB conditions. The staff is also concerned with the lack of documentation indicating how it was determined that the electronics can withstand a total integrated dose of 1X10 3 Rads. The staff has identified this request as:
RAI #13 Please provide analysis of the maximum expected radiological conditions (dose rate and total integrated dose) for the location of the sensor electronics that might be considered credible under BOB conditions. Also, please provide documentation indicating how it was determined that the electronics for this equipment is capable of withstanding a total integrated dose of 1X103 Rads. Please discuss the time period over which the analyzed total integrated dose was applied.
3.6.3 Shock and Vibration NEI 12-02 states, in part, that Applicable components of the instrument channels are rated by the manufacturer (or otherwise tested) for shock and vibration at levels commensurate with those of postulated design basis event conditions in the area of instrument channel component use uSing one or more of the following methods:
- instrument channel components use known operating principles, are supplied by manufacturers with commercial quality programs (such as IS09001) with shock and vibration requirements included in the purchase specification and/or instrument design, and commercial design and testing for operation in
- 16 environments where significant shock and vibration loadings are cornmon, such as for portable hand-held devices or transportation applications;
- substantial history of operational reliability in environments with significant shock and vibration loading, such as transportation applications, or
- use of component inherently resistant to shock and vibration loadings or are seismically reliable such as cables.
In its letter dated July 11, 2013, the licensee stated, in part The VEGAPuls 62ER Through Air Radar sensor is similar in form, fit and function to the VEGAPuls 66 that was shock and vibration tested in accordance with MILS-901D and MIL-STD-167-1. This shock and vibration testing only applies to the sensor. The waveguide piping is %" diameter Schedule 40 piping and is seismically anchored to the floor. Thus the waveguide piping is not considered to be sensitive to shock or vibration.
The power supply panel contains components that are part of the standard VEGA Mobile Remote Display. In addition, the readout portion of the display panel, the PLlCSCOM, was installed in the sensor during the shock and vibration testing. The Mobile Remote Display is designed for truck-mounted mobile applications subject to shock and vibration from normal handling, after transportation and setup on the job. Per NEI 12-02, designing instruments for operation in environments where significant shock and vibration loadings are common, such as for portable hand-held devices or transportation applications, is an acceptable measure for verifying that the design is adequate to withstand shock and vibration. This panel is therefore considered to have an acceptable resistance to shock and vibration. There are three components in the AREVA power control panel that are not included with the VEGA Mobile Remote Display but are similar in construction and are tested for shock and vibration and/or mounted on vibration dampeners. This panel also will be subjected to seismic tests.
The main control room displaylindicator will be seismically mounted, and is seismically qualified based on similarity to other control board indicators.
The NRC staff notes that the use of MI L-STD-901 D appears to be a reasonable method for shock testing. However, the staff has concerns regarding the licensee's lack of information describing the tests, applied forces, and the operability condition of the sensor after the tests were completed. The staff has identified this request as:
RAI #14 Please provide information describing the evaluation of the comparative sensor design, the shock test method, test results, and forces applied to the sensor applicable to its successful tests demonstrating that the referenced previous testing provides an
- 30 RAI #24 Please provide the following:
a) Further information describing the testing and calibration program the licensee will establish and implement to ensure that regular testing and calibration is performed and verified by inspection and audit to demonstrate conformance with design and system readiness requirements. Please include a description of the plans for ensuring that necessary channel checks, functional tests, periodic calibration, and maintenance will be conducted for the level measurement system and its supporting equipment.
b) Information describing compensatory actions when both channels are out~of order.
c) Additional information describing expedited and compensatory actions in the maintenance procedure to address when one of the instrument channels cannot be restored to functional status within 90 days.
The NRC staff has concerns regarding the feasibility of the licensee's process for in-situ calibration to ensure that the design accuracy will be maintained. The staff has identified the following requests as:
RAI #25 Please provide a description of the in-situ calibration process at the SFP location that will result in the channel calibration being maintained at its design accuracy.
3.15 Instrument Reliability NEI 12-02 states, in part, that A spent fuel pool level instrument channel is considered reliable when the instrument channel satisfies the design elements listed in Section 3 [Instrument Design Features] of this guidance and the plant operator has fully implemented the programmatic features listed in Section 4 [Program Features].
In its OIP, the licensee stated, in part Reliability of the level instrumentation will be assured by conformance with the guidelines of NRC JlD-ISG-2012-03 and NEI 12-02, as described below.
Upon acceptable resolution of the RAls noted above, the NRC staff will be able to make a conclusion regarding the reliability of the SFP instrumentation.
November 7, 2013 Mr. Steven D. Capps Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078
SUBJECT:
MCGUIRE NUCLEAR STATION, UNITS 1 AND 2- CORRECTION LETTER TO INTERIM STAFF EVALUATION AND REQUEST FOR ADDITIONAL INFORMATION REGARDING THE OVERALL INTEGRATED PLAN FOR IMPLEMENTATION OF ORDER EA-12-051, RELIABLE SPENT FUEL POOL INSTRUMENTATION (TAC NOS. MF1062 AND MF1063)
Dear Mr. Capps:
By letter dated October 28, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13281A791 ), the U.S. Nuclear Regulatory Commission issued an interim staff evaluation and requests for additional information regarding the overall integrated plan for implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation.
Due to an inadvertent error, pages 15, 16, and 30 were omitted from the October 28, 2013, document.
Enclose please find pages 15, 16, and 30.
Sincerely, IRA/
Jason C. Paige, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370
Enclosure:
As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC LPL2-1 R/F RidsNrrDoriDpr Resource RidsNrrDorllpl2-1 Resource RidsNrrDirsltsb Resource RidsNrrLASFigueroa Resource RidsAcrsAcnw_MaiiCTR Resource RidsRgn2MaiiCenter Resource RidsNrrPMMcGuire Resource (hard copy)
Correction Letter No ..* ML13309A782 *via e-mail OFFICE NRR/LPL2-1/PM NRR/LPL2-1 /LA NRR/LPL2-1/BC NRR/LPL2-1/PM NAME JPaige SFigueroa RPascarelli JPaige DATE 11/6/13 11/6/13 11/7/13 11/7/13 OFFICIAL RECORD COPY