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| | issue date = 08/18/2016 | | | issue date = 08/18/2016 |
| | title = Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident | | | title = Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident |
| | author name = Capps S D | | | author name = Capps S |
| | author affiliation = Duke Energy Carolinas, LLC | | | author affiliation = Duke Energy Carolinas, LLC |
| | addressee name = | | | addressee name = |
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| =Text= | | =Text= |
| {{#Wiki_filter:el_-. DUKE | | {{#Wiki_filter:Steven D. Capps el_-. DUKE |
| * August 18, 2016 MNS-16-060 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission | | * Vice President McGuire Nuclear Station |
| * Washington, DC 20555 Duke Energy Carolinas, LLC (Duke Energy) McGuire Nuclear Station (MNS), Units 1 and 2 Docket Nos. 50-369 and 50-370 Renewed License Nos, NPF-9 and NPF:-17 Steven D. Capps Vice President McGuire Nuclear Station Duke Energy MGOIVP 1*12700 Hagers Ferry Road Huntersville, NC 28078 o: 980.875.4805 f: 980.875.4809 Steven.Capps@duke-energy.com 10 CFR 50.4 10 CFR 50.54(f) | | *~;ENERGY Duke Energy MGOIVP 1*12700 Hagers Ferry Road Huntersville, NC 28078 o: 980.875.4805 f: 980.875.4809 Steven.Capps@duke-energy.com 10 CFR 50.4 10 CFR 50.54(f) |
| | August 18, 2016 MNS-16-060 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission |
| | * Washington, DC 20555 Duke Energy Carolinas, LLC (Duke Energy) |
| | McGuire Nuclear Station (MNS), Units 1 and 2 Docket Nos. 50-369 and 50-370 Renewed License Nos, NPF-9 and NPF:-17 |
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| ==Subject:== | | ==Subject:== |
| Spent Fuei Pool Evaluation Supplemental Report, Response to NRC Request for Information Pl.irs1,1ant to 1 O CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident | | Spent Fuei Pool Evaluation Supplemental Report, Response to NRC Request for Information Pl.irs1,1ant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident |
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| ==References:== | | ==References:== |
| : 1. NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated | | : 1. NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated |
| * March 12-, 2012, ADAMS Accession Number ML 12053A340. | | * March 12-, 2012, ADAMS Accession Number ML12053A340. |
| : 2. NRC Letter; Final Determination of Licensee Seismic Probabilistic Risk Assessments. | | : 2. NRC Letter; Final Determination of Licensee Seismic Probabilistic Risk Assessments. |
| * Under the Request for Information Pursuant to Title 1 O of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 "Seismic" of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated October 27, 2015, ADAMS Accession Number ML 15194A015. | | * Under the Request for Information Pursuant to Title 1Oof the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 "Seismic" of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated October 27, 2015, ADAMS Accession Number ML15194A015. |
| : 3. NEI Letter, transmits EPRI 3002007148 for NRC endorsement, dated February 2016, ADAMS Accession Number ML 16055A017. | | : 3. NEI Letter, transmits EPRI 3002007148 for NRC endorsement, dated February 2~, 2016, ADAMS Accession Number ML16055A017. |
| : 4. EPRI 3002007148", Seismic Evaluation Guidance SpE3nt Fuel Pool Integrity Evaluation, dated,* February 2016, ADAMS Accession Number ML 16055A021. | | : 4. EPRI 3002007148", Seismic Evaluation Guidance SpE3nt Fuel Pool Integrity Evaluation, dated,* February 2016, ADAMS Accession Number ML16055A021. |
| : 5. NRC Letter, provides endorsement of EPRI 3002007148,.dated March 17,. 2016, ADAMS Accession Number ML 15350A 158. ; 6. Duke Energy Letter, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC 1 O CFR 50.54(f) Request for Information Pursuant to Title 1 O of the Co.de of Federal Regulations 50.54(f) regarding Recommendations 2 .. 1, 2.3 and 9.3 of the Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated March 20, 2014, ADAMS Accession Number ML 14098A421. | | : 5. NRC Letter, provides endorsement of EPRI 3002007148,.dated March 17,. 2016, ADAMS Accession Number ML15350A158. |
| ft DID U.S. Nuclear Regulatory Commission August 18, 2016 Page2 / 7. NRC Letter, McGuire Nuclear Station, Units 1 and 2 -Staff Assessment of Information provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima DAl-ICHI Accident, dated July 20, 2015, ADAMS Accession Number ML 15182A067. | | : 6. Duke Energy Letter, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 1O of the Co.de of Federal Regulations 50.54(f) regarding Recommendations 2 .. 1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated March 20, 2014, ADAMS Accession Number ML14098A421. |
| ' 8. EPRI 1025287, Seismic Evaluation Guidance, Screening, Prioritization and Implementation Details [SPID] for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic, dated February 15, 2013, Accession Number ML 12319A074.
| | ft DID |
| On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued a Request for Information per 10 CFR 50.54(f) (Reference
| | ~.(Lf- |
| : 1) to all power reactor Enclosure 1, Item (9) of the 50.54(f) letter requested addressees to provide limited scope spent fuel pool (SFP) evaluations.
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| By letter dated Octob.er 27, 2015 (Reference 2), the NRC transmitted final seismic information request tables which identified that Duke Energy's McGuire Nuclear Station is to conduct a limited scope SFP Evaluation.
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| By Reference 3, Nuclear Energy Institute (NEI) submitted an Electric Power Research Institute (EPRI) report entitled, Seismic Evaluation Guidance Spent Fuel Pool Integrity Evaluation (EPRI .30020071A8) (Reference
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| : 4) for NRC review arid endorsement.
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| NRC endorsement was provided by Reference
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| : 5. EPRI 3002007148 provides criteria for evaluating the seismic adequacy of a SFP to the reevaluated ground motion response spectrum (GMRS) hazard levels. This report supplements the guidance in the SPID (Reference 8), for plants where the GMRS peak spectral acceleration . is less than or equal to 0.8g. Section 3.3 of EPRI 3002007148 lists the parameters to be verified to confirm that the results of the report are applicable to Duke Energy's McGuire Nuclear Station, and that the. McGuire Nuclear Station SFP is seismically adequate in accordance with NTTF 2.1 Seismic evaluation criteria.
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| The attachment to this letter provides the data for McGuire Nuclear Station that confirms applicability of the EPRI 3002007148 criteria, confirms that the SFP is seismically adequate, and provides the requested information in response to Item (9) of the 50.54(f) letter associated with NTTF Recommendation
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| ===2.1 Seismic===
| | U.S. Nuclear Regulatory Commission August 18, 2016 Page2 |
| evaluation criteria. | | / |
| This letter contains no new Regulatory Commitments and no revision to existing Regulatory Commitments . . Should you have any questions regarding this submittal, please contact George Murphy at 980-875-5715. | | : 7. NRC Letter, McGuire Nuclear Station, Units 1 and 2 - Staff Assessment of Information provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima DAl-ICHI Accident, dated July 20, 2015, ADAMS Accession Number ML15182A067. ' |
| * I declare under penalty of perjury that the foregoing is true and correct. Executed on August 18, 2016. Sincerely, Steven D. Capps | | : 8. EPRI 1025287, Seismic Evaluation Guidance, Screening, Prioritization and Implementation Details [SPID] for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic, dated February 15, 2013, ADAM~ Accession Number ML12319A074. |
| | On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued a Request for Information per 10 CFR 50.54(f) (Reference 1) to all power reactor licensees~ Enclosure 1, Item (9) of the 50.54(f) letter requested addressees to provide limited scope spent fuel pool (SFP) evaluations. By letter dated Octob.er 27, 2015 (Reference 2), the NRC transmitted final seismic information request tables which identified that Duke Energy's McGuire Nuclear Station is to conduct a limited scope SFP Evaluation. By Reference 3, Nuclear Energy Institute (NEI) submitted an Electric Power Research Institute (EPRI) report entitled, Seismic Evaluation Guidance Spent Fuel Pool Integrity Evaluation (EPRI .30020071A8) (Reference 4) for NRC review arid endorsement. NRC endorsement was provided by Reference 5. |
| | EPRI 3002007148 provides criteria for evaluating the seismic adequacy of a SFP to the reevaluated ground motion response spectrum (GMRS) hazard levels. This report supplements the guidance in the SPID (Reference 8), for plants where the GMRS peak spectral acceleration . |
| | is less than or equal to 0.8g. Section 3.3 of EPRI 3002007148 lists the parameters to be verified to confirm that the results of the report are applicable to Duke Energy's McGuire Nuclear Station, and that the. McGuire Nuclear Station SFP is seismically adequate in accordance with NTTF 2.1 Seismic evaluation criteria. |
| | The attachment to this letter provides the data for McGuire Nuclear Station that confirms applicability of the EPRI 3002007148 criteria, confirms that the SFP is seismically adequate, and provides the requested information in response to Item (9) of the 50.54(f) letter associated with NTTF Recommendation 2.1 Seismic evaluation criteria. |
| | This letter contains no new Regulatory Commitments and no revision to existing Regulatory Commitments . |
| | .Should you have any questions regarding this submittal, please contact George Murphy at 980-875-5715. |
| | * I declare under penalty of perjury that the foregoing is true and correct. Executed on August 18, 2016. |
| | Sincerely, Steven D. Capps |
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| ==Attachment:== | | ==Attachment:== |
| | Site~Specific Spent Fuel Pool Criteria for McGuire Nuclear Station |
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| Spent Fuel Pool Criteria for McGuire Nuclear Station U. S. Nuclear Regulatory Commission August 18, 2016 Page 3 xc: C. Haney, Region II Administrator U.S. Nuclear Regulatory Commission Marquis One _Tower 245 Peachtree Center Avenue NE, Suite 1200 Atlanta, Georgia 30303-1257 J.P. Beska, Project Manager John.Boska@nrc.gov
| | U. S. Nuclear Regulatory Commission August 18, 2016 Page 3 xc: |
| * G.E. Miller, Project Manager Ed.Miller@nrc.gov V. Screenivas, Interim Project Manager V.Screenivas@nrc.gov A. Hutto NRC Senior Resident Inspector McGuire Nuclear Station Justin Folkwein American Nuclear Insurers . 95 Glastonbury, CT. 06033-4453 ATTACHMENT Duke Energy McGuire Nuclear Station (MNS), Units 1 arid 2 Docket Nos. 50-369 and 50-370 Renewed License Nos. NPF-9 and NPF-17 Site-Specific Spent Fuel Pool Criteria for McGuire Nuclear Station Site-Specific Spent Fuel Pool Criteria for McGuire Nuclear Station Page 2 of 5 The 50.54(f) letter requested that, in conjunction with the response to NTTF Recommendation 2.1, a seismic evaluation be made of the SFP. More specifically, plants were asked to consider "all seismically induced failures that can lead to draining of the SFP." Such an evaluation would be needed for any plant in which the ground motion response spectrum (GMRS) exceeds the safe shutdown earthquake (SSE) in the 1 to 1 frequency range. The staff confirmed through References 2 and 7 that the GMRS exceeds the SSE and concluded that a SFP evaluation is merited for Duke Energy's McGuire Nuclear Station. By letter dated March 17, 2016, . [Reference 5], the staff determined that EPRI 3002007148 was an acceptable approach for performing SFP evaluations for plants where the peak spectral acceleration is less than or equal to 0.8g. The table below Hsts the criteria from Section 3.3 of EPRI 3002007148 along with d?ta* for McGuire Nuclear Station that confirms applicability of the EPRI 3002007148 criteria and confirms that the SFP is seismically adequate and can retain adequate water inventory for 72 hours in accordance with NTTF 2.1 Seismic evaluation criteria. | | C. Haney, Region II Administrator U.S. Nuclear Regulatory Commission Marquis One _Tower 245 Peachtree Center Avenue NE, Suite 1200 Atlanta, Georgia 30303-1257 J.P. Beska, Project Manager John.Boska@nrc.gov |
| ,*
| | * G.E. Miller, Project Manager Ed.Miller@nrc.gov V. Screenivas, Interim Project Manager V.Screenivas@nrc.gov A. Hutto NRC Senior Resident Inspector McGuire Nuclear Station Justin Folkwein American Nuclear Insurers . |
| .. ;J
| | 95 Glastonbury, CT. 06033-4453 |
| .; .*. -;,',,.; .,.: <Z*:. -. .. * ,: -. .. ,,,'.::-: *<< : Site Parameters
| |
| : 1. The site-specific GMRS peak The GMRS peak spectral acceleration in Reference spectral acceleration at any 6 as accepted by the NRC in Reference 7 is 0.676g, frequency should be less than or which is :::;; 0.8g; therefore, this criterion is met. equal to 0.8g. Structural Parameters l 2. The structure housing the SFP . The SFP is housed in the Fuel Building (part of the should be designed using an SSE . Auxiliary Building structure), which is seismically with peak ground acceleration (PGA) designed to the site SSE with a PGA of 0.15g [Ref. of at least 0.1g. McGuire UFSAR Section 3.1 and Reference 12]. The McGuire Nuclear Station PGA is greater than 0.1 g; therefore, this criterion is met. 3. The structural load_path to the SFP The structural load path from the foundation to the should consist of some combination SFP consists of four foot thick concrete shear walls of reinforced concrete shear wall and with an integrated concrete frame [Ref. UFSAR elements, reinforced concrete frame Section 3.8.4.1.1, UFSAR Figures 3-104 through 3-elements, post-tensioned concrete 107, and References 9 and 1 O]; therefore, this elements and/or structural steel criterion is met for McGuire Nuclear Station. frame elements.
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| : 4. The SFP structure should be The SFP structure is included in the McGuire Nuclear included in the Civil Inspection Station Civil Inspection Program in accordance with P,rogram performed in accordance 10 CFR 50.65, which monitors the performance or with Maintenance Rule. condition of structures, systems, or components (SSCs) in a manner sufficient to provide reasonable assurance that these SSCs are capable of fulfilling their intended functions
| |
| [Ref. UFSAR Section 18.2.17, UFSAR Table 18-1, and Reference 13]. Therefore, this criterion is met for McGuire Nuclear Station.
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| . / Site-Specific Spent Fuel Pool Criteria for McGuire Nuclear Station Page 3 of 5 Non-Structural Parameters
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| : 5. To confirm applicability of the piping \ evaluation in Section 3.2 of EPRI 3002007148, piping attached *to the SFP up to the first valve should have been evaluated for the SSE. 6. Anti-siphoning devices should be installed on any piping that could lead to siphoning water from the SFP. In addition, for any cases _where active anti-siphoning devices are attached to 2-inch or smaller piping and have extremely large extended operators, the valves should be walked down to confirm adequate lateral support. 7. To confirm applicability of the sloshing evaluation in Section 3.2 of EPRI 3002007148, the maximum SFP horizontal dimension (length or width) should be less than 125 ft, the SFP depth should be greater than 36 ft, and the GMRS peak Sa should be <0.1 g at frequencies equal to or less than 0.3 Hz. Piping attached to the SFP is evaluated to the SSE in accordance with McGuire's UFSAR Section 3.1 -Discussion for Generic Design Criteria 61, which assures "the spent fuel pool is designed such that no postulated accident could cause excessive loss of coolant inventory''
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| as well as McGuire UFSAR Section 3.7 and Table 3-4 [See References
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| ===7.5 through===
| | ATTACHMENT Duke Energy McGuire Nuclear Station (MNS), Units 1 arid 2 Docket Nos. 50-369 and 50-370 Renewed License Nos. NPF-9 and NPF-17 Site-Specific Spent Fuel Pool Criteria for McGuire Nuclear Station |
| 7.8 of MCC-1612.00-00-0001 for a complete list of relevant piping drawings which contain QA conditions of the piping sections], therefore, this criterion is met for McGuire Nuclear StatiOI").
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| The McGuire Unit 1 and 2 SFP relies on passive design features to limit the amount of inventory which .could be inadvertently drained [Ref. UFSAR Sections 9.1.3.1.3 and 9.1.3.3.2].
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| In general, the mechanical piping interfaces below the SFP normal water level are either equipped with siphon breakers, and/or the pipe elevation does not extend more than 2-4' below normal SFP water level. The potential for rapid drawdown on SFP inventory due to attached piping was examined in depth in McGuire calculation MCC-1612.00-00-0001, which was in response to the 1 O CFR 50.54(f) request for information regarding the Fukushima Near-Term Task Force (NTTF) Recommendation 2.3 for Seismic Walkdowns
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| [See References
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| ===7.5 through===
| | Site-Specific Spent Fuel Pool Criteria for McGuire Nuclear Station Page 2 of 5 The 50.54(f) letter requested that, in conjunction with the response to NTTF Recommendation 2.1, a seismic evaluation be made of the SFP. More specifically, plants were asked to consider "all seismically induced failures that can lead to draining of the SFP." Such an evaluation would be needed for any plant in which the ground motion response spectrum (GMRS) exceeds the safe shutdown earthquake (SSE) in the 1 to 1o~Hz frequency range. The staff confirmed through References 2 and 7 that the GMRS exceeds the SSE and concluded that a SFP evaluation is merited for Duke Energy's McGuire Nuclear Station. By letter dated March 17, 2016, |
| 7.8 of MCC-1612.00 0001 for a complete list of relevant piping drawings]. | | . [Reference 5], the staff determined that EPRI 3002007148 was an acceptable approach for performing SFP evaluations for plants where the peak spectral acceleration is less than or equal to 0.8g. |
| As described, anti-siphoning devices are installed on all SFP piping that could lead to siphoning; therefore, this criterion is met for McGuire Nuclear Station. As described above, there are no anti-siphoning devices attached to 2-inch or smaller piping with extremely large extended operators. | | The table below Hsts the criteria from Section 3.3 of EPRI 3002007148 along with d?ta* for McGuire Nuclear Station that confirms applicability of the EPRI 3002007148 criteria and confirms that the SFP is seismically adequate and can retain adequate water inventory for 72 hours in accordance with NTTF 2.1 Seismic evaluation criteria. |
| Therefore, this criterion is met for McGuire Nuclear Station. The McGuire Nuclear Station SFP has a length of 67 ft., a width of 21.5 ft. and a depth of 40 ft. based on McGuire's UFSAR Section 3.8.4.1.1 and References 9 and 1 O; therefore, this criterion is met. The McGuire Nuclear Station GMRS maximum spectral acceleration in the frequency range less than 0.3 Hz is 0.0326g from Reference 6, which is less than 0.1 g; therefore, this criterion is met. | | ,* SFJ?.,Cri~~ri.'! Jr~~ ',E.~Rl'.;~,~*02<!9-!1'~~ .. ;J Si\~.'."Sp:ec:if~.~ D~ta .; .*. -;,',,.; ~:; .,.: <Z*:. -. ,~..*,: .. -. -~, |
| Site-Specific Spent Fuel Pool Criteria for McGuire Nuclear Station. 8. To confirm applicability of the evaporation loss evaluation in Section 3.2 of EPRI 3002007148, the SFP surface area should be greater than 500 ft2 and the licensed reactor core thermal power should be less than 4,000 MWt per unit. | | ,,,'.::- : ~: *<< ~ : |
| | Site Parameters |
| | : 1. The site-specific GMRS peak The GMRS peak spectral acceleration in Reference spectral acceleration at any 6 as accepted by the NRC in Reference 7 is 0.676g, frequency should be less than or which is :::;; 0.8g; therefore, this criterion is met. |
| | equal to 0.8g. |
| | Structural Parameters l |
| | : 2. The structure housing the SFP . The SFP is housed in the Fuel Building (part of the should be designed using an SSE . Auxiliary Building structure), which is seismically with peak ground acceleration (PGA) designed to the site SSE with a PGA of 0.15g [Ref. |
| | of at least 0.1g. McGuire UFSAR Section 3.1 and Reference 12]. |
| | The McGuire Nuclear Station PGA is greater than 0.1 g; therefore, this criterion is met. |
| | : 3. The structural load_path to the SFP The structural load path from the foundation to the should consist of some combination SFP consists of four foot thick concrete shear walls of reinforced concrete shear wall and with an integrated concrete frame [Ref. UFSAR elements, reinforced concrete frame Section 3.8.4.1.1, UFSAR Figures 3-104 through 3-elements, post-tensioned concrete 107, and References 9 and 1O]; therefore, this elements and/or structural steel criterion is met for McGuire Nuclear Station. |
| | frame elements. |
| | : 4. The SFP structure should be The SFP structure is included in the McGuire Nuclear included in the Civil Inspection Station Civil Inspection Program in accordance with P,rogram performed in accordance 10 CFR 50.65, which monitors the performance or with Maintenance Rule. condition of structures, systems, or components (SSCs) in a manner sufficient to provide reasonable assurance that these SSCs are capable of fulfilling their intended functions [Ref. UFSAR Section 18.2.17, UFSAR Table 18-1, and Reference 13]. |
| | Therefore, this criterion is met for McGuire Nuclear Station. |
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| | . / |
| | Site-Specific Spent Fuel Pool Criteria for McGuire Nuclear Station Page 3 of 5 Non-Structural Parameters |
| | : 5. To confirm applicability of the piping \ Piping attached to the SFP is evaluated to the SSE in evaluation in Section 3.2 of EPRI accordance with McGuire's UFSAR Section 3.1 - |
| | 3002007148, piping attached *to the Discussion for Generic Design Criteria 61, which SFP up to the first valve should have assures "the spent fuel pool is designed such that no been evaluated for the SSE. postulated accident could cause excessive loss of coolant inventory'' as well as McGuire UFSAR Section 3.7 and Table 3-4 [See References 7.5 through 7.8 of MCC-1612.00-00-0001 for a complete list of relevant piping drawings which contain QA conditions of the piping sections], therefore, this criterion is met for McGuire Nuclear StatiOI"). |
| | : 6. Anti-siphoning devices should be The McGuire Unit 1 and 2 SFP relies on passive installed on any piping that could design features to limit the amount of inventory which lead to siphoning water from the .could be inadvertently drained [Ref. UFSAR Sections SFP. In addition, for any cases 9.1.3.1.3 and 9.1.3.3.2]. In general, the mechanical |
| | _where active anti-siphoning devices piping interfaces below the SFP normal water level are attached to 2-inch or smaller are either equipped with siphon breakers, and/or the piping and have extremely large pipe elevation does not extend more than 2-4' below extended operators, the valves normal SFP water level. The potential for rapid should be walked down to confirm drawdown on SFP inventory due to attached piping adequate lateral support. was examined in depth in McGuire calculation MCC-1612.00-00-0001, which was in response to the 10 CFR 50.54(f) request for information regarding the Fukushima Near-Term Task Force (NTTF) |
| | Recommendation 2.3 for Seismic Walkdowns [See References 7.5 through 7.8 of MCC-1612.00 a 0001 for complete list of relevant piping drawings]. |
| | As described, anti-siphoning devices are installed on all SFP piping that could lead to siphoning; therefore, this criterion is met for McGuire Nuclear Station. |
| | As described above, there are no anti-siphoning devices attached to 2-inch or smaller piping with extremely large extended operators. Therefore, this criterion is met for McGuire Nuclear Station. |
| | : 7. To confirm applicability of the The McGuire Nuclear Station SFP has a length of 67 sloshing evaluation in Section 3.2 of ft., a width of 21.5 ft. and a depth of 40 ft. based on EPRI 3002007148, the maximum McGuire's UFSAR Section 3.8.4.1.1 and References SFP horizontal dimension (length or 9 and 1O; therefore, this criterion is met. |
| | width) should be less than 125 ft, the The McGuire Nuclear Station GMRS maximum SFP depth should be greater than spectral acceleration in the frequency range less 36 ft, and the GMRS peak Sa should than 0.3 Hz is 0.0326g from Reference 6, which is be <0.1 g at frequencies equal to or less than 0.1 g; therefore, this criterion is met. |
| | less than 0.3 Hz. |
| | |
| | Site-Specific Spent Fuel Pool Criteria for McGuire Nuclear Station. |
| | Page 4 of 5 |
| | : 8. To confirm applicability of the The surface area of the McGuire Nuclear Station evaporation loss evaluation in SFP is 1087.6 ft2 [Calculated based on References 9 Section 3.2 of EPRI 3002007148, and 1O], whicr is greater than 500 ft 2* Licensed the SFP surface area should be reactor thermal power for McGuire Nuclear Station is greater than 500 ft2 and the licensed 3469 MWt per unit [Ref. UFSAR Section 1.1], which reactor core thermal power should is less than 4,000 MWt per unit; therefore, these be less than 4,000 MWt per unit. criteria are met. |
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| ==References:== | | ==References:== |
| | : 1. NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated |
| | * March 12, 2012, ADAMS Accession Number ML12053A340. |
| | : 2. NRC Letter, Final Determination of Licensee Seismic Probabilistic Risk Assessments Under the Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 "Seismic" of the Near-Term Task Force Review of Insights from ~he Fukushima Dai-ichi Accident, dated October 27, 2015, ADAMS Accession Number ML15194A015. * |
| | : 3. NEI Letter, transmits EPRI 3002007148 for NRC endorsement, dated February 23, 2016, ADAMS Accession Number ML16055A017. |
| | : 4. EPRI 3002007148, Seismic Evaluation Guidance Spent Fuel Pool Integrity Evaluation, February 2016, ADAMS Accession Number ML16055A021. |
| | : 5. NRC Letter, .provides endorsement of EPRI 3002007148, dated March 17, 2016, ADAMS Accession Number ML15350A158. |
| | : 6. Duke Energy Letter, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated March 20, 2014, ADAMS Acces$ion Number ML14098A421. |
| | : 7. NRC Letter, McGuire Nuclear Station, Units 1 and 2 - Staff Assessment of Information provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima DAl-ICHI Accident, dated July 20, 2015, ADAMS Accession Number ML15182A067. |
| | : 8. EPRI 1025287, Seismic Evaluation Guidance, Screening, Prioritization and Implementation Details [SPID] for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic, February 15, 2013, ADAMS Accession Number ML12319A074. |
| | : 9. McGuire Drawings MC-1230-01.00 through MC-1230-09.00; Unit 1 Spent Fuel Pool Concrete and Reinforcing Drawings |
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| Page 4 of 5 -, The surface area of the McGuire Nuclear Station SFP is 1087.6 ft2 [Calculated based on References 9 and 1 O], whicr is greater than 500 ft 2* Licensed reactor thermal power for McGuire Nuclear Station is 3469 MWt per unit [Ref. UFSAR Section 1.1], which is less than 4,000 MWt per unit; therefore, these criteria are met. 1. NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated
| | Site-Specific Spent Fuel Pool Criteria for McGuire Nuclear Station Page 5 of 5 |
| * March 12, 2012, ADAMS Accession Number ML 12053A340.
| | : 10. McGuire Drawings MC-1230-12.00 through MC-1230-20.00; Unit 2 Spent Fuel Pool Concrete and Reinforcing Drawings |
| : 2. NRC Letter, Final Determination of Licensee Seismic Probabilistic Risk Assessments Under the Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 "Seismic" of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident, dated October 27, 2015, ADAMS Accession Number ML 15194A015.
| | : 11. McGuire Calculation MCC-1612.00-00-0001, Rev. 2; "10CFR50.54(f) Recommendation 2.;3 Fukushima Near-Terni Task Force (NTTF) Seismic W,alkdown Inspections" |
| * 3. NEI Letter, transmits EPRI 3002007148 for NRC endorsement, dated February 23, 2016, ADAMS Accession Number ML 16055A017.
| | : 12. McGuire Specification MCS-1108.00-00-0002, Rev. 9; "Specification for the Response Spectra and Seismic Displacements for Category I Structures" |
| : 4. EPRI 3002007148, Seismic Evaluation Guidance Spent Fuel Pool Integrity Evaluation, February 2016, ADAMS Accession Number ML 16055A021.
| | : 13. EDM-410, Rev. 17; "Inspection Program for Civil Engineering Structures and Components"}} |
| : 5. NRC Letter, .provides endorsement of EPRI 3002007148, dated March 17, 2016, ADAMS Accession Number ML 15350A 158. 6. Duke Energy Letter, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) regarding Recommendations 2.1, 2.3 and 9.3 of the Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated March 20, 2014, ADAMS Acces$ion Number ML 14098A421.
| |
| : 7. NRC Letter, McGuire Nuclear Station, Units 1 and 2 -Staff Assessment of Information provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima DAl-ICHI Accident, dated July 20, 2015, ADAMS Accession Number ML 15182A067.
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| : 8. EPRI 1025287, Seismic Evaluation Guidance, Screening, Prioritization and Implementation Details [SPID] for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic, February 15, 2013, ADAMS Accession Number ML 12319A074.
| |
| : 9. McGuire Drawings MC-1230-01.00 through MC-1230-09.00; Unit 1 Spent Fuel Pool Concrete and Reinforcing Drawings Site-Specific Spent Fuel Pool Criteria for McGuire Nuclear Station Page 5 of 5 10. McGuire Drawings MC-1230-12.00 through MC-1230-20.00; Unit 2 Spent Fuel Pool Concrete and Reinforcing Drawings 11. McGuire Calculation MCC-1612.00-00-0001, Rev. 2; "10CFR50.54(f)
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| Recommendation 2.;3 Fukushima Near-Terni Task Force (NTTF) Seismic W,alkdown Inspections" 12. McGuire Specification MCS-1108.00-00-0002, Rev. 9; "Specification for the Response Spectra and Seismic Displacements for Category I Structures" 13. EDM-410, Rev. 17; "Inspection Program for Civil Engineering Structures and Components"}} | |
Letter Sequence Request |
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MONTHYEARONS-2014-164, Revision to Tornado/Helb Mitigation Strategies and Regulatory Commitment 17T2014-12-19019 December 2014 Revision to Tornado/Helb Mitigation Strategies and Regulatory Commitment 17T Project stage: Request ONS-2015-052, Response to Request for Additional Information Dated March 27, 2015, Related to the Oconee Expedited Seismic Evaluation Process (ESEP) Report2015-04-24024 April 2015 Response to Request for Additional Information Dated March 27, 2015, Related to the Oconee Expedited Seismic Evaluation Process (ESEP) Report Project stage: Response to RAI ML15344A1832016-01-0505 January 2016 Report for the Audit of Duke Energy Carolinas, LLC Interim Evaluations Associated with Reevaluated Seismic Hazard Implementing Near-Term Task Force Recommendation Project stage: Other MNS-16-060, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2016-08-18018 August 2016 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident Project stage: Request ML16237A3542016-08-31031 August 2016 Staff Review of Spent Fuel Pool Evaluation Associated with Reevaluated Seismic Hazard Implementing Near-Term Task Force Recommendation 2.1 Project stage: Approval 2016-01-05
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Category:Letter type:MNS
MONTHYEARMNS-18-044, Independent Spent Fuel Storage Installation (Isfsi), Submittal of 10 CFR 72.48 Summary Report from September 15, 2016 to July 26, 2018, No Changes, Tests, or Experiments2018-07-26026 July 2018 Independent Spent Fuel Storage Installation (Isfsi), Submittal of 10 CFR 72.48 Summary Report from September 15, 2016 to July 26, 2018, No Changes, Tests, or Experiments MNS-18-036, Redacted Response to the Request for Additional Information Regarding the License Amendment Request to Revise the Licensing Bases for Protection from Tornado Generated Missiles2018-07-0303 July 2018 Redacted Response to the Request for Additional Information Regarding the License Amendment Request to Revise the Licensing Bases for Protection from Tornado Generated Missiles MNS-18-042, Independent Spent Fuel Storage Installation (ISFSI)2018-06-28028 June 2018 Independent Spent Fuel Storage Installation (ISFSI) MNS-18-040, Submittal of Information Related to Pressurizer Surge and Spray Nozzle Thermal Sleeves Attachment Welds for License Renewal2018-06-26026 June 2018 Submittal of Information Related to Pressurizer Surge and Spray Nozzle Thermal Sleeves Attachment Welds for License Renewal MNS-18-039, Independent Spent Fuel Storage Installation (ISFSI)2018-06-19019 June 2018 Independent Spent Fuel Storage Installation (ISFSI) MNS-18-001, Application to Revise Technical Specifications to Adopt TSTF-234-A Revision 1, Add Action for More than One Dpri Inoperable2018-05-31031 May 2018 Application to Revise Technical Specifications to Adopt TSTF-234-A Revision 1, Add Action for More than One Dpri Inoperable MNS-18-030, 2017 Annual Radiological Environmental Operating Report2018-05-15015 May 2018 2017 Annual Radiological Environmental Operating Report MNS-18-029, Resolution of Commitments Related to Review Request for the Aging Management Program and Inspection Plan for the McGuire Nuclear Station Units 1 and 2 Reactor Vessel Internals to Implement MRP-227-A2018-05-0909 May 2018 Resolution of Commitments Related to Review Request for the Aging Management Program and Inspection Plan for the McGuire Nuclear Station Units 1 and 2 Reactor Vessel Internals to Implement MRP-227-A MNS-18-029, McGuire Nuclear Station, Units 1 and 2 - Resolution of Commitments Related to Review Request for the Aging Management Program and Inspection Plan for the McGuire Nuclear Station Units 1 and 2 Reactor Vessel Internals to Implement MRP-227-2018-05-0909 May 2018 McGuire Nuclear Station, Units 1 and 2 - Resolution of Commitments Related to Review Request for the Aging Management Program and Inspection Plan for the McGuire Nuclear Station Units 1 and 2 Reactor Vessel Internals to Implement MRP-227-A MNS-18-028, Annual Radioactive Effluent Release Report2018-04-25025 April 2018 Annual Radioactive Effluent Release Report MNS-18-017, Non-Voluntary License Amendment Request (LAR) to Correct Non-Conservative Technical Specification 3.4.11 - PORVs2018-02-26026 February 2018 Non-Voluntary License Amendment Request (LAR) to Correct Non-Conservative Technical Specification 3.4.11 - PORVs MNS-18-018, McGuire, Units 1 & 2, Submittal of Emergency Plan Implementing Procedure Changes2018-02-22022 February 2018 McGuire, Units 1 & 2, Submittal of Emergency Plan Implementing Procedure Changes MNS-18-009, McGuire Nuclear Station, Units 1 and 2, Submittal of Emergency Plan, Revision 18-12018-01-31031 January 2018 McGuire Nuclear Station, Units 1 and 2, Submittal of Emergency Plan, Revision 18-1 MNS-18-003, End of Cycle 25 In-service and Steam Generator In-service Inspection Summary Reports2018-01-11011 January 2018 End of Cycle 25 In-service and Steam Generator In-service Inspection Summary Reports MNS-17-050, Review Request for the Aging Management Program and Inspection Plan for the Reactor Vessel Internals to Implement MRP-227-A2017-12-13013 December 2017 Review Request for the Aging Management Program and Inspection Plan for the Reactor Vessel Internals to Implement MRP-227-A MNS-17-048, Response to Request for Additional Information License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies2017-12-12012 December 2017 Response to Request for Additional Information License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies MNS-17-026, Submittal of License Amendment Request Proposing to Revise the Bases for Protection from Tornado-Generated Missiles2017-12-0808 December 2017 Submittal of License Amendment Request Proposing to Revise the Bases for Protection from Tornado-Generated Missiles MNS-17-042, McGuire Nuclear Station, Unit 1, Submittal of Cycle 26, Revision 0, Core Operating Limits Report2017-10-0909 October 2017 McGuire Nuclear Station, Unit 1, Submittal of Cycle 26, Revision 0, Core Operating Limits Report MNS-17-040, (Mns), Units 1 and 2 - Supplement to the High Frequency Supplement to Seismic Hazard Screening Report, Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force ..2017-09-27027 September 2017 (Mns), Units 1 and 2 - Supplement to the High Frequency Supplement to Seismic Hazard Screening Report, Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force .. MNS-17-038, Startup Ascension Summary Report Measurement Uncertainty Recapture Power Uprate2017-09-25025 September 2017 Startup Ascension Summary Report Measurement Uncertainty Recapture Power Uprate MNS-17-039, McGuire Nuclear Station, Units 1 and 2, Submittal of Emergency Plan, Revision 17-12017-09-19019 September 2017 McGuire Nuclear Station, Units 1 and 2, Submittal of Emergency Plan, Revision 17-1 MNS-17-031, License Amendment Request for Temporary Changes to Technical Specifications to Address an 'A' Train Nuclear Service Water System (Nsws) Non-Conforming Condition2017-09-14014 September 2017 License Amendment Request for Temporary Changes to Technical Specifications to Address an 'A' Train Nuclear Service Water System (Nsws) Non-Conforming Condition MNS-17-037, Submittal of Summary Report of Evaluations Performed Pursuant to 10 CFR 50.59 Changes, Tests, and Experiments During the Period from January 1, 2016 to March 31, 20172017-08-10010 August 2017 Submittal of Summary Report of Evaluations Performed Pursuant to 10 CFR 50.59 Changes, Tests, and Experiments During the Period from January 1, 2016 to March 31, 2017 MNS-17-033, Snubber Program Plan for the Fourth Ten-Year Lnservice Testing (IST) Interval2017-08-0202 August 2017 Snubber Program Plan for the Fourth Ten-Year Lnservice Testing (IST) Interval MNS-17-034, 16C4435-RPT-002, Rev. 1, 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation for McGuire Nuclear Station.2017-07-24024 July 2017 16C4435-RPT-002, Rev. 1, 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation for McGuire Nuclear Station. MNS-17-030, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal2017-06-28028 June 2017 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal MNS-17-023, Response to Request for Additional Information to License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies2017-05-25025 May 2017 Response to Request for Additional Information to License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies MNS-17-016, Nuclear Regulatory Commission (NRC) Annual Commitment Change Report2017-05-18018 May 2017 Nuclear Regulatory Commission (NRC) Annual Commitment Change Report MNS-17-020, Transmittal of McGuire, Units 1 and 2, 2016 Annual Radiological Environmental Operating Report2017-05-0505 May 2017 Transmittal of McGuire, Units 1 and 2, 2016 Annual Radiological Environmental Operating Report MNS-17-019, McGuire Nuclear Station, Units 1 and 2 - Submittal of Annual Radioactive Effluent Release Report2017-04-28028 April 2017 McGuire Nuclear Station, Units 1 and 2 - Submittal of Annual Radioactive Effluent Release Report MNS-17-008, Letter of Intent to Submit Plant-Specific Reactor Vessel Internals Inspection Plans2017-02-23023 February 2017 Letter of Intent to Submit Plant-Specific Reactor Vessel Internals Inspection Plans MNS-16-092, License Amendment Request to Revise Technical Specifications Section 5.5.2, Containment Leakage Rate Testing Program for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2016-12-19019 December 2016 License Amendment Request to Revise Technical Specifications Section 5.5.2, Containment Leakage Rate Testing Program for Permanent Extension of Type a and Type C Leak Rate Test Frequencies MNS-16-091, License Amendment Request for Technical Specification 3.6.14, Divider Barrier Integrity.2016-12-0808 December 2016 License Amendment Request for Technical Specification 3.6.14, Divider Barrier Integrity. MNS-16-086, Emergency Plan, Revision 16-42016-12-0707 December 2016 Emergency Plan, Revision 16-4 MNS-16-078, Written Notification Joslyn Clark Overload Heater Element Part No. 24552016-10-19019 October 2016 Written Notification Joslyn Clark Overload Heater Element Part No. 2455 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 MNS-16-070, Response to Request for Additional Information to Relief Request 16-MN-0032016-08-18018 August 2016 Response to Request for Additional Information to Relief Request 16-MN-003 MNS-16-060, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2016-08-18018 August 2016 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident MNS-16-062, Relief Request 16-MN-003 Alternative to Defect Removal Prior to Performing Temporary Repair Activities on Three-Inch-Diameter Nuclear Service Water System Piping2016-08-10010 August 2016 Relief Request 16-MN-003 Alternative to Defect Removal Prior to Performing Temporary Repair Activities on Three-Inch-Diameter Nuclear Service Water System Piping MNS-16-046, License Amendment Request for Technical Specification 3.6.14, Divider Barrier Integrity2016-06-30030 June 2016 License Amendment Request for Technical Specification 3.6.14, Divider Barrier Integrity MNS-16-056, License Amendment Request, One-Time Extension of Appendix J Type a Integrated Leakage Rate Test Interval, Response to Request for Additional Information2016-06-30030 June 2016 License Amendment Request, One-Time Extension of Appendix J Type a Integrated Leakage Rate Test Interval, Response to Request for Additional Information MNS-16-053, Relief Request 16-MN-002, Alternative to Defect Removal Prior to Performing Repair Activities on Nuclear Service Water System Piping2016-06-23023 June 2016 Relief Request 16-MN-002, Alternative to Defect Removal Prior to Performing Repair Activities on Nuclear Service Water System Piping MNS-16-052, Supplement to License Amendment Request for the Removal of Superseded Technical Specification Requirements, Dated May 5, 2016, TAC Nos. MF7682 and MF76832016-06-16016 June 2016 Supplement to License Amendment Request for the Removal of Superseded Technical Specification Requirements, Dated May 5, 2016, TAC Nos. MF7682 and MF7683 MNS-16-042, Withdrawal of Relief Request Serial No. 15-MN-0022016-05-17017 May 2016 Withdrawal of Relief Request Serial No. 15-MN-002 MNS-16-020, License Amendment Request Removal of Superseded Technical Specification Requirements2016-05-0505 May 2016 License Amendment Request Removal of Superseded Technical Specification Requirements MNS-16-041, Supplement to Final Notification of Full Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events and with Order EA-12-051..2016-05-0505 May 2016 Supplement to Final Notification of Full Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events and with Order EA-12-051.. MNS-16-036, Relief Request 16-MN-001, Limited Weld Examinations2016-04-28028 April 2016 Relief Request 16-MN-001, Limited Weld Examinations MNS-16-039, Submittal Revising Attachment s of License Amendment Request to Implement a Risk-Informed Performance-Based Fire Protection Program2016-04-26026 April 2016 Submittal Revising Attachment s of License Amendment Request to Implement a Risk-Informed Performance-Based Fire Protection Program MNS-16-026, Transmittal of Updated Final Safety Analysis Report, Revision 192016-04-0505 April 2016 Transmittal of Updated Final Safety Analysis Report, Revision 19 MNS-15-068, License Amendment Request to Technical Specification (TS) 3.6.13, Ice Condenser Doors.2016-03-24024 March 2016 License Amendment Request to Technical Specification (TS) 3.6.13, Ice Condenser Doors. 2018-07-03
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARRA-23-0154, Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2023-07-20020 July 2023 Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) RA-23-0136, Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2023-07-20020 July 2023 Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) RA-23-0142, Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require2023-07-0707 July 2023 Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require RA-23-0076, Supplement to Response to Request for Additional Information (RAI) Regarding McGuire Nuclear Station Unit 1 Spring, 2022 Outage Steam Generator Tube Inspection Report2023-03-16016 March 2023 Supplement to Response to Request for Additional Information (RAI) Regarding McGuire Nuclear Station Unit 1 Spring, 2022 Outage Steam Generator Tube Inspection Report RA-23-0024, Response to Request for Additional Information (RAI) for Relief Request for RPV Reactor Coolant System Welds2023-02-28028 February 2023 Response to Request for Additional Information (RAI) for Relief Request for RPV Reactor Coolant System Welds RA-23-0025, End of Cycle 28 (M1R28) Steam Generator Tube Inspection Report Response to Request for Additional Information (RAI)2023-02-15015 February 2023 End of Cycle 28 (M1R28) Steam Generator Tube Inspection Report Response to Request for Additional Information (RAI) RA-22-0147, Duke Energy Carolinas, LLC, and Duke Energy Progress, LLC, Response to Request for Additional Information (RAI) Regarding License Amendment Request for Relocating the Duke Energy Emergency Operations Facility2022-05-13013 May 2022 Duke Energy Carolinas, LLC, and Duke Energy Progress, LLC, Response to Request for Additional Information (RAI) Regarding License Amendment Request for Relocating the Duke Energy Emergency Operations Facility RA-22-0102, Response to Request for Additional Information (RAI) Regarding Revision 1 of DPC-NE-1007-P, Conditional Exemption of the EOC Mtc Measurement Methodology2022-04-0707 April 2022 Response to Request for Additional Information (RAI) Regarding Revision 1 of DPC-NE-1007-P, Conditional Exemption of the EOC Mtc Measurement Methodology RA-22-0003, Response to Requests for Additional Information for Reactor Vessel Closure Stud Exam Extension Alternative2022-01-31031 January 2022 Response to Requests for Additional Information for Reactor Vessel Closure Stud Exam Extension Alternative RA-21-0259, Response to Request for Additional Information for Request to Use Provisions of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI for Repair/ Replacement Activities in Accordance with 10 CFR 50.55a(g)(42021-10-0404 October 2021 Response to Request for Additional Information for Request to Use Provisions of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI for Repair/ Replacement Activities in Accordance with 10 CFR 50.55a(g)(4 RA-21-0063, 1, 2; Catawba Nuclear Station 1, 2; H. B. Robinson Steam Electric Plant 2; Mcgguire Nuclear Station 1, 2; Oconee Nuclear Station 1, 2, 3; Shearon Harris Nuclear Power Plant 1 - Response to RAI Re Amend for Emergency Plan2021-03-11011 March 2021 1, 2; Catawba Nuclear Station 1, 2; H. B. Robinson Steam Electric Plant 2; Mcgguire Nuclear Station 1, 2; Oconee Nuclear Station 1, 2, 3; Shearon Harris Nuclear Power Plant 1 - Response to RAI Re Amend for Emergency Plan RA-21-0032, Duke Energy - Response to Requests for Additional Info for Request to Use a Provision of Later Edition & Addenda of the ASME Boiler & Pressure Vessel Code, Section XI for Repair/Replacement Activities in Accordance with 10 CFR 50.55a(g)(42021-02-11011 February 2021 Duke Energy - Response to Requests for Additional Info for Request to Use a Provision of Later Edition & Addenda of the ASME Boiler & Pressure Vessel Code, Section XI for Repair/Replacement Activities in Accordance with 10 CFR 50.55a(g)(4)( RA-21-0017, Response to Request for Additional Information Re License Amendment Request to Revise Tech Spec 3.8.1 to Reduce Emergency Diesel Generator Maximum Steady State Voltage2021-01-29029 January 2021 Response to Request for Additional Information Re License Amendment Request to Revise Tech Spec 3.8.1 to Reduce Emergency Diesel Generator Maximum Steady State Voltage RA-20-0087, Response to Request for Additional Information Regarding Request for Alternative in Accordance with 10CFR 50.55a(z)(1) to Delay the Update of the ASME Code of Record for the First Inspection Period2020-04-0202 April 2020 Response to Request for Additional Information Regarding Request for Alternative in Accordance with 10CFR 50.55a(z)(1) to Delay the Update of the ASME Code of Record for the First Inspection Period RA-19-0189, Supplement to Response for Request for Additional Information Regarding License Amendment Request Proposing Changes to the Technical Specifications 3.8.12019-04-0808 April 2019 Supplement to Response for Request for Additional Information Regarding License Amendment Request Proposing Changes to the Technical Specifications 3.8.1 RA-19-0004, Response to NRC for Additional Information (RAI) Regarding License Amendment Request Proposing Changes to the Technical Specifications 3.8.1 for Catawba Nuclear Station, Units 1 and 22019-03-0707 March 2019 Response to NRC for Additional Information (RAI) Regarding License Amendment Request Proposing Changes to the Technical Specifications 3.8.1 for Catawba Nuclear Station, Units 1 and 2 RA-19-0026, Response to Request for Additional Information (RAI) Regarding Proposed Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 and 10 (18-GO-001)2019-02-11011 February 2019 Response to Request for Additional Information (RAI) Regarding Proposed Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 and 10 (18-GO-001) RA-19-0005, Response to NRC Request for Additional Information Regarding Review Request of the Aging Management Program and Inspection Plan for the Reactor Vessel Internals to Implement MRP-227-A2019-01-30030 January 2019 Response to NRC Request for Additional Information Regarding Review Request of the Aging Management Program and Inspection Plan for the Reactor Vessel Internals to Implement MRP-227-A RA-18-0229, Response to NRC Request for Additional Information Regarding License Amendment Request Proposing Changes to the Technical Specification 3.8.12018-12-0303 December 2018 Response to NRC Request for Additional Information Regarding License Amendment Request Proposing Changes to the Technical Specification 3.8.1 RA-18-0213, Response to the Second Request for Additional Information Regarding the License Amendment Request to Revise the Licensing Bases for Protection from Tornado-Generated Missiles2018-11-0101 November 2018 Response to the Second Request for Additional Information Regarding the License Amendment Request to Revise the Licensing Bases for Protection from Tornado-Generated Missiles ML18191A5642018-07-10010 July 2018 Attachment 3 - Response to NRC Request for Additional Information MNS-18-036, Redacted Response to the Request for Additional Information Regarding the License Amendment Request to Revise the Licensing Bases for Protection from Tornado Generated Missiles2018-07-0303 July 2018 Redacted Response to the Request for Additional Information Regarding the License Amendment Request to Revise the Licensing Bases for Protection from Tornado Generated Missiles ML20052D9362018-07-0303 July 2018 Response to Nrg Request for Additional Information (RAI) Regarding NAC Magnastor Cask Loaded to Incorrect Helium Backfill Density MNS-17-048, Response to Request for Additional Information License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies2017-12-12012 December 2017 Response to Request for Additional Information License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML17349A1572017-12-12012 December 2017 Response to Request for Additional Information Regarding License Amendment Request for Temporary Changes to Technical Specifications to Address the 'A' Train Nuclear Service Water System Non-Conforming Condition RA-17-0039, Response to Request for Additional Information (RAI) Regarding 10 CFR 50.55a(z)(1)Proposed Alternative to ASME Section XI Threads in Flange Examination (17-GO-001)2017-08-0909 August 2017 Response to Request for Additional Information (RAI) Regarding 10 CFR 50.55a(z)(1)Proposed Alternative to ASME Section XI Threads in Flange Examination (17-GO-001) RA-17-0035, Supplement to License Amendment Request Proposing Changes to Technical Specification 3.5.1, AC Sources - Operating.2017-07-20020 July 2017 Supplement to License Amendment Request Proposing Changes to Technical Specification 3.5.1, AC Sources - Operating. MNS-17-030, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal2017-06-28028 June 2017 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal RA-17-0030, Response to Request for Additional Information Regarding Application to Reverse Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers2017-06-0808 June 2017 Response to Request for Additional Information Regarding Application to Reverse Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers MNS-17-023, Response to Request for Additional Information to License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies2017-05-25025 May 2017 Response to Request for Additional Information to License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies CNS-16-066, Stations - Supplemental Information Regarding Reevaluated Seismic Hazard Screening and Prioritization Results - Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task..2016-10-20020 October 2016 Stations - Supplemental Information Regarding Reevaluated Seismic Hazard Screening and Prioritization Results - Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task.. ML16294A2542016-10-13013 October 2016 Response to Request for Additional Information Regarding Relief Request 16-MN-002, Alternative to Defect Removal Prior to Performing Repair Activities on Nuclear Service Water System Piping RA-16-0035, Response to Request for Additional Information (RAI) Regarding Application for Emergency Operations Facility (EOF) Consolidation2016-10-0303 October 2016 Response to Request for Additional Information (RAI) Regarding Application for Emergency Operations Facility (EOF) Consolidation ML16244A0602016-08-18018 August 2016 Response to Request for Addition Information to RR 16-MN-003 MNS-16-070, Response to Request for Additional Information to Relief Request 16-MN-0032016-08-18018 August 2016 Response to Request for Additional Information to Relief Request 16-MN-003 MNS-16-060, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2016-08-18018 August 2016 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML16230A0062016-08-11011 August 2016 Response to Request for Additional Information Regarding License Amendment Request to Technical Specification 3.6.13, Ice Condenser Doors RA-16-0027, Response to NRC Regulatory Issue Summary 2016-09 Preparation and Scheduling of Operator Licensing Examinations2016-07-14014 July 2016 Response to NRC Regulatory Issue Summary 2016-09 Preparation and Scheduling of Operator Licensing Examinations MNS-16-056, License Amendment Request, One-Time Extension of Appendix J Type a Integrated Leakage Rate Test Interval, Response to Request for Additional Information2016-06-30030 June 2016 License Amendment Request, One-Time Extension of Appendix J Type a Integrated Leakage Rate Test Interval, Response to Request for Additional Information MNS-16-023, Response to Request for Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding License Amendment Request for Control Room Chilled Water System Technical Specifications2016-03-16016 March 2016 Response to Request for Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding License Amendment Request for Control Room Chilled Water System Technical Specifications ML16056A2422016-02-18018 February 2016 Response to Request for Additional Information Regarding the License Amendment Request (LAR) to Change the Emergency Plan to Upgrade Emergency Action Levels Based on NEI 99-01, Revision 6 MNS-16-005, Response to Request for Additional Information (RAI) During January 12, 2016, NRC Teleconference Pertaining to License Amendment Request for Nuclear Service Water System Allowed Outage Time Extension2016-02-10010 February 2016 Response to Request for Additional Information (RAI) During January 12, 2016, NRC Teleconference Pertaining to License Amendment Request for Nuclear Service Water System Allowed Outage Time Extension MNS-16-008, Expedited Seismic Evaluation Process (ESEP) Closeout, Response to NRC Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima..2016-02-0404 February 2016 Expedited Seismic Evaluation Process (ESEP) Closeout, Response to NRC Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.. MNS-16-009, Response to NRC Letter Dated December 9, 2015, Request for Additional Information Regarding Request for Exemption from Title 10 of the Code of Federal Regulations (10 CFR) Part 74.19(c)2016-02-0404 February 2016 Response to NRC Letter Dated December 9, 2015, Request for Additional Information Regarding Request for Exemption from Title 10 of the Code of Federal Regulations (10 CFR) Part 74.19(c) RA-16-0006, Response to NRC Request for Additional Information (RAI) Regarding Application to Use Alternate Fission Gas Gap Release Fractions2016-02-0101 February 2016 Response to NRC Request for Additional Information (RAI) Regarding Application to Use Alternate Fission Gas Gap Release Fractions MNS-16-003, Response to Request for Additional Information (RAI) Regarding License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation2016-01-0707 January 2016 Response to Request for Additional Information (RAI) Regarding License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation ML15343A0122015-12-0707 December 2015 Response to NRC Letter Dated 10/26/2015, Request for Additional Information Regarding License Amendment Request, Nuclear Service Water System Allowed Outage Time Extension. MNS-15-093, Response to Request for Additional Information Regarding License Amendment Request Regarding Residual Heat Removal System2015-11-13013 November 2015 Response to Request for Additional Information Regarding License Amendment Request Regarding Residual Heat Removal System MNS-15-078, Response to NRC Letter Dated September 14, 2015, Request for Additional Information Regarding License Amendment Request, Nuclear Service Water System Allowed Outage Time Extension2015-10-0808 October 2015 Response to NRC Letter Dated September 14, 2015, Request for Additional Information Regarding License Amendment Request, Nuclear Service Water System Allowed Outage Time Extension MNS-15-077, Expedited Seismic Evaluation Process (ESEP) Report (CEUS Sites), Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima..2015-10-0808 October 2015 Expedited Seismic Evaluation Process (ESEP) Report (CEUS Sites), Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.. 2023-07-07
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Text
Steven D. Capps el_-. DUKE
- Vice President McGuire Nuclear Station
- ~;ENERGY Duke Energy MGOIVP 1*12700 Hagers Ferry Road Huntersville, NC 28078 o: 980.875.4805 f: 980.875.4809 Steven.Capps@duke-energy.com 10 CFR 50.4 10 CFR 50.54(f)
August 18, 2016 MNS-16-060 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission
McGuire Nuclear Station (MNS), Units 1 and 2 Docket Nos. 50-369 and 50-370 Renewed License Nos, NPF-9 and NPF:-17
Subject:
Spent Fuei Pool Evaluation Supplemental Report, Response to NRC Request for Information Pl.irs1,1ant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
References:
- 1. NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated
- 2. NRC Letter; Final Determination of Licensee Seismic Probabilistic Risk Assessments.
- Under the Request for Information Pursuant to Title 1Oof the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 "Seismic" of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated October 27, 2015, ADAMS Accession Number ML15194A015.
- 3. NEI Letter, transmits EPRI 3002007148 for NRC endorsement, dated February 2~, 2016, ADAMS Accession Number ML16055A017.
- 4. EPRI 3002007148", Seismic Evaluation Guidance SpE3nt Fuel Pool Integrity Evaluation, dated,* February 2016, ADAMS Accession Number ML16055A021.
- 5. NRC Letter, provides endorsement of EPRI 3002007148,.dated March 17,. 2016, ADAMS Accession Number ML15350A158.
- 6. Duke Energy Letter, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 1O of the Co.de of Federal Regulations 50.54(f) regarding Recommendations 2 .. 1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated March 20, 2014, ADAMS Accession Number ML14098A421.
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U.S. Nuclear Regulatory Commission August 18, 2016 Page2
/
- 7. NRC Letter, McGuire Nuclear Station, Units 1 and 2 - Staff Assessment of Information provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima DAl-ICHI Accident, dated July 20, 2015, ADAMS Accession Number ML15182A067. '
- 8. EPRI 1025287, Seismic Evaluation Guidance, Screening, Prioritization and Implementation Details [SPID] for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic, dated February 15, 2013, ADAM~ Accession Number ML12319A074.
On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued a Request for Information per 10 CFR 50.54(f) (Reference 1) to all power reactor licensees~ Enclosure 1, Item (9) of the 50.54(f) letter requested addressees to provide limited scope spent fuel pool (SFP) evaluations. By letter dated Octob.er 27, 2015 (Reference 2), the NRC transmitted final seismic information request tables which identified that Duke Energy's McGuire Nuclear Station is to conduct a limited scope SFP Evaluation. By Reference 3, Nuclear Energy Institute (NEI) submitted an Electric Power Research Institute (EPRI) report entitled, Seismic Evaluation Guidance Spent Fuel Pool Integrity Evaluation (EPRI .30020071A8) (Reference 4) for NRC review arid endorsement. NRC endorsement was provided by Reference 5.
EPRI 3002007148 provides criteria for evaluating the seismic adequacy of a SFP to the reevaluated ground motion response spectrum (GMRS) hazard levels. This report supplements the guidance in the SPID (Reference 8), for plants where the GMRS peak spectral acceleration .
is less than or equal to 0.8g. Section 3.3 of EPRI 3002007148 lists the parameters to be verified to confirm that the results of the report are applicable to Duke Energy's McGuire Nuclear Station, and that the. McGuire Nuclear Station SFP is seismically adequate in accordance with NTTF 2.1 Seismic evaluation criteria.
The attachment to this letter provides the data for McGuire Nuclear Station that confirms applicability of the EPRI 3002007148 criteria, confirms that the SFP is seismically adequate, and provides the requested information in response to Item (9) of the 50.54(f) letter associated with NTTF Recommendation 2.1 Seismic evaluation criteria.
This letter contains no new Regulatory Commitments and no revision to existing Regulatory Commitments .
.Should you have any questions regarding this submittal, please contact George Murphy at 980-875-5715.
- I declare under penalty of perjury that the foregoing is true and correct. Executed on August 18, 2016.
Sincerely, Steven D. Capps
Attachment:
Site~Specific Spent Fuel Pool Criteria for McGuire Nuclear Station
U. S. Nuclear Regulatory Commission August 18, 2016 Page 3 xc:
C. Haney, Region II Administrator U.S. Nuclear Regulatory Commission Marquis One _Tower 245 Peachtree Center Avenue NE, Suite 1200 Atlanta, Georgia 30303-1257 J.P. Beska, Project Manager John.Boska@nrc.gov
- G.E. Miller, Project Manager Ed.Miller@nrc.gov V. Screenivas, Interim Project Manager V.Screenivas@nrc.gov A. Hutto NRC Senior Resident Inspector McGuire Nuclear Station Justin Folkwein American Nuclear Insurers .
95 Glastonbury, CT. 06033-4453
ATTACHMENT Duke Energy McGuire Nuclear Station (MNS), Units 1 arid 2 Docket Nos. 50-369 and 50-370 Renewed License Nos. NPF-9 and NPF-17 Site-Specific Spent Fuel Pool Criteria for McGuire Nuclear Station
Site-Specific Spent Fuel Pool Criteria for McGuire Nuclear Station Page 2 of 5 The 50.54(f) letter requested that, in conjunction with the response to NTTF Recommendation 2.1, a seismic evaluation be made of the SFP. More specifically, plants were asked to consider "all seismically induced failures that can lead to draining of the SFP." Such an evaluation would be needed for any plant in which the ground motion response spectrum (GMRS) exceeds the safe shutdown earthquake (SSE) in the 1 to 1o~Hz frequency range. The staff confirmed through References 2 and 7 that the GMRS exceeds the SSE and concluded that a SFP evaluation is merited for Duke Energy's McGuire Nuclear Station. By letter dated March 17, 2016,
. [Reference 5], the staff determined that EPRI 3002007148 was an acceptable approach for performing SFP evaluations for plants where the peak spectral acceleration is less than or equal to 0.8g.
The table below Hsts the criteria from Section 3.3 of EPRI 3002007148 along with d?ta* for McGuire Nuclear Station that confirms applicability of the EPRI 3002007148 criteria and confirms that the SFP is seismically adequate and can retain adequate water inventory for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in accordance with NTTF 2.1 Seismic evaluation criteria.
,* SFJ?.,Cri~~ri.'! Jr~~ ',E.~Rl'.;~,~*02<!9-!1'~~ .. ;J Si\~.'."Sp:ec:if~.~ D~ta .; .*. -;,',,.; ~:; .,.: <Z*:. -. ,~..*,: .. -. -~,
,,,'.::- : ~: *<< ~ :
Site Parameters
- 1. The site-specific GMRS peak The GMRS peak spectral acceleration in Reference spectral acceleration at any 6 as accepted by the NRC in Reference 7 is 0.676g, frequency should be less than or which is :::;; 0.8g; therefore, this criterion is met.
equal to 0.8g.
Structural Parameters l
- 2. The structure housing the SFP . The SFP is housed in the Fuel Building (part of the should be designed using an SSE . Auxiliary Building structure), which is seismically with peak ground acceleration (PGA) designed to the site SSE with a PGA of 0.15g [Ref.
of at least 0.1g. McGuire UFSAR Section 3.1 and Reference 12].
The McGuire Nuclear Station PGA is greater than 0.1 g; therefore, this criterion is met.
- 3. The structural load_path to the SFP The structural load path from the foundation to the should consist of some combination SFP consists of four foot thick concrete shear walls of reinforced concrete shear wall and with an integrated concrete frame [Ref. UFSAR elements, reinforced concrete frame Section 3.8.4.1.1, UFSAR Figures 3-104 through 3-elements, post-tensioned concrete 107, and References 9 and 1O]; therefore, this elements and/or structural steel criterion is met for McGuire Nuclear Station.
frame elements.
- 4. The SFP structure should be The SFP structure is included in the McGuire Nuclear included in the Civil Inspection Station Civil Inspection Program in accordance with P,rogram performed in accordance 10 CFR 50.65, which monitors the performance or with Maintenance Rule. condition of structures, systems, or components (SSCs) in a manner sufficient to provide reasonable assurance that these SSCs are capable of fulfilling their intended functions [Ref. UFSAR Section 18.2.17, UFSAR Table 18-1, and Reference 13].
Therefore, this criterion is met for McGuire Nuclear Station.
. /
Site-Specific Spent Fuel Pool Criteria for McGuire Nuclear Station Page 3 of 5 Non-Structural Parameters
- 5. To confirm applicability of the piping \ Piping attached to the SFP is evaluated to the SSE in evaluation in Section 3.2 of EPRI accordance with McGuire's UFSAR Section 3.1 -
3002007148, piping attached *to the Discussion for Generic Design Criteria 61, which SFP up to the first valve should have assures "the spent fuel pool is designed such that no been evaluated for the SSE. postulated accident could cause excessive loss of coolant inventory as well as McGuire UFSAR Section 3.7 and Table 3-4 [See References 7.5 through 7.8 of MCC-1612.00-00-0001 for a complete list of relevant piping drawings which contain QA conditions of the piping sections], therefore, this criterion is met for McGuire Nuclear StatiOI").
- 6. Anti-siphoning devices should be The McGuire Unit 1 and 2 SFP relies on passive installed on any piping that could design features to limit the amount of inventory which lead to siphoning water from the .could be inadvertently drained [Ref. UFSAR Sections SFP. In addition, for any cases 9.1.3.1.3 and 9.1.3.3.2]. In general, the mechanical
_where active anti-siphoning devices piping interfaces below the SFP normal water level are attached to 2-inch or smaller are either equipped with siphon breakers, and/or the piping and have extremely large pipe elevation does not extend more than 2-4' below extended operators, the valves normal SFP water level. The potential for rapid should be walked down to confirm drawdown on SFP inventory due to attached piping adequate lateral support. was examined in depth in McGuire calculation MCC-1612.00-00-0001, which was in response to the 10 CFR 50.54(f) request for information regarding the Fukushima Near-Term Task Force (NTTF)
Recommendation 2.3 for Seismic Walkdowns [See References 7.5 through 7.8 of MCC-1612.00 a 0001 for complete list of relevant piping drawings].
As described, anti-siphoning devices are installed on all SFP piping that could lead to siphoning; therefore, this criterion is met for McGuire Nuclear Station.
As described above, there are no anti-siphoning devices attached to 2-inch or smaller piping with extremely large extended operators. Therefore, this criterion is met for McGuire Nuclear Station.
- 7. To confirm applicability of the The McGuire Nuclear Station SFP has a length of 67 sloshing evaluation in Section 3.2 of ft., a width of 21.5 ft. and a depth of 40 ft. based on EPRI 3002007148, the maximum McGuire's UFSAR Section 3.8.4.1.1 and References SFP horizontal dimension (length or 9 and 1O; therefore, this criterion is met.
width) should be less than 125 ft, the The McGuire Nuclear Station GMRS maximum SFP depth should be greater than spectral acceleration in the frequency range less 36 ft, and the GMRS peak Sa should than 0.3 Hz is 0.0326g from Reference 6, which is be <0.1 g at frequencies equal to or less than 0.1 g; therefore, this criterion is met.
less than 0.3 Hz.
Site-Specific Spent Fuel Pool Criteria for McGuire Nuclear Station.
Page 4 of 5
- 8. To confirm applicability of the The surface area of the McGuire Nuclear Station evaporation loss evaluation in SFP is 1087.6 ft2 [Calculated based on References 9 Section 3.2 of EPRI 3002007148, and 1O], whicr is greater than 500 ft 2* Licensed the SFP surface area should be reactor thermal power for McGuire Nuclear Station is greater than 500 ft2 and the licensed 3469 MWt per unit [Ref. UFSAR Section 1.1], which reactor core thermal power should is less than 4,000 MWt per unit; therefore, these be less than 4,000 MWt per unit. criteria are met.
References:
- 1. NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated
- 2. NRC Letter, Final Determination of Licensee Seismic Probabilistic Risk Assessments Under the Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 "Seismic" of the Near-Term Task Force Review of Insights from ~he Fukushima Dai-ichi Accident, dated October 27, 2015, ADAMS Accession Number ML15194A015. *
- 3. NEI Letter, transmits EPRI 3002007148 for NRC endorsement, dated February 23, 2016, ADAMS Accession Number ML16055A017.
- 4. EPRI 3002007148, Seismic Evaluation Guidance Spent Fuel Pool Integrity Evaluation, February 2016, ADAMS Accession Number ML16055A021.
- 5. NRC Letter, .provides endorsement of EPRI 3002007148, dated March 17, 2016, ADAMS Accession Number ML15350A158.
- 6. Duke Energy Letter, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated March 20, 2014, ADAMS Acces$ion Number ML14098A421.
- 7. NRC Letter, McGuire Nuclear Station, Units 1 and 2 - Staff Assessment of Information provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima DAl-ICHI Accident, dated July 20, 2015, ADAMS Accession Number ML15182A067.
- 8. EPRI 1025287, Seismic Evaluation Guidance, Screening, Prioritization and Implementation Details [SPID] for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic, February 15, 2013, ADAMS Accession Number ML12319A074.
- 9. McGuire Drawings MC-1230-01.00 through MC-1230-09.00; Unit 1 Spent Fuel Pool Concrete and Reinforcing Drawings
Site-Specific Spent Fuel Pool Criteria for McGuire Nuclear Station Page 5 of 5
- 10. McGuire Drawings MC-1230-12.00 through MC-1230-20.00; Unit 2 Spent Fuel Pool Concrete and Reinforcing Drawings
- 11. McGuire Calculation MCC-1612.00-00-0001, Rev. 2; "10CFR50.54(f) Recommendation 2.;3 Fukushima Near-Terni Task Force (NTTF) Seismic W,alkdown Inspections"
- 12. McGuire Specification MCS-1108.00-00-0002, Rev. 9; "Specification for the Response Spectra and Seismic Displacements for Category I Structures"
- 13. EDM-410, Rev. 17; "Inspection Program for Civil Engineering Structures and Components"