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| number = ML17031A001
| number = ML17031A001
| issue date = 02/02/2017
| issue date = 02/02/2017
| title = Brunswick Steam Electric Plant, Units 1 and 2 - Staff Review of Spent Fuel Pool Evaluation Associated with Reevaluated Seismic Hazard Implementing Near-Term Task Force Recommendation 2.1 (CAC Nos. MF3824 and MF3825)
| title = Staff Review of Spent Fuel Pool Evaluation Associated with Reevaluated Seismic Hazard Implementing Near-Term Task Force Recommendation 2.1
| author name = Vega F G
| author name = Vega F
| author affiliation = NRC/NRR/JLD
| author affiliation = NRC/NRR/JLD
| addressee name = Gideon W R
| addressee name = Gideon W
| addressee affiliation = Duke Energy Progress, LLC
| addressee affiliation = Duke Energy Progress, LLC
| docket = 05000324, 05000325
| docket = 05000324, 05000325
| license number =  
| license number =  
| contact person = Vega F G, NRR/JLD 415-1617
| contact person = Vega F, NRR/JLD 415-1617
| case reference number = CAC MF3824, CAC MF3825
| case reference number = CAC MF3824, CAC MF3825
| document type = Letter
| document type = Letter
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. William R. Gideon Site Vice President Brunswick Steam Electric Plant Brunswick Steam Electric Plant 8470 River Rd. SE (M/C BNP001) Southport , NC 28461 February 2 , 2017
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 2, 2017 Mr. William R. Gideon Site Vice President Brunswick Steam Electric Plant Brunswick Steam Electric Plant 8470 River Rd. SE (M/C BNP001)
Southport, NC 28461


==SUBJECT:==
==SUBJECT:==
BRUNSWICK STEAM ELECTRIC PLANT , UNITS 1AND2 -STAFF REVIEW OF SPENT FUEL POOL EVALUATION ASSOCIATED WITH REEVALUATED SEISMIC HAZARD IMPLEMENTING NEAR-TERM TASK FORCE RECOMMENDATION 2.1 (CAC NOS. MF3824 AND MF3825)  
BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1AND2 - STAFF REVIEW OF SPENT FUEL POOL EVALUATION ASSOCIATED WITH REEVALUATED SEISMIC HAZARD IMPLEMENTING NEAR-TERM TASK FORCE RECOMMENDATION 2.1 (CAC NOS. MF3824 AND MF3825)


==Dear Mr. Gideon:==
==Dear Mr. Gideon:==
The purpose of this letter is to inform Duke Energy Progress , LLC (Duke , the licensee) of the results of the U.S. Nuclear Regulatory Commission (NRC) staff's review of the spent fuel pool (SFP) evaluation for Brunswick Steam Electric Plant , Units 1 and 2 (Brunswick), which was submitted in response to Item 9 of Enclosure 1 of the NRC's March 12 , 2012 , request for information (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 12053A340) issued under Title 1 O of the Code of Federal Regulations Part 50 , Section 50.54(f) (hereafter referred to as the 50.54(f) letter). The NRC staff concludes that the licensee's assessment was performed consistent with the NRG-endorsed SFP Evaluation Guidance Report and that the licensee has provided sufficient information to complete the response to Item 9 of the 50.54(f) letter. BACKGROUND On March 12 , 2012 , the NRC issued a 50.54(f) letter as part of implementing lessons learned from the accident at the Fukushima Dai-ichi nuclear power plant. Enclosure 1 to the 50.54(f) letter requested that licensees reevaluate seismic hazards at their sites using present-day methodologies and guidance.
 
Enclosure 1 , Item 4 , of the 50.54(f) letter requested that licensees perform a comparison of the ground motion response spectrum (GMRS) and the safe shutdown earthquake (SSE). The staff's assessment of the information provided in response to Items 1-3 and 5-7 of the 50.54(f) letter is provided by letter dated March 1 , 2016 (ADAMS Accession No. ML 16041 A435). Enclosure 1 , Item 9 , of the 50.54(f) letter requested that , when the GMRS exceeds the SSE in the 1 to 1 O Hertz frequency range , 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."
The purpose of this letter is to inform Duke Energy Progress, LLC (Duke , the licensee) of the results of the U.S. Nuclear Regulatory Commission (NRC) staff's review of the spent fuel pool (SFP) evaluation for Brunswick Steam Electric Plant, Units 1 and 2 (Brunswick), which was submitted in response to Item 9 of Enclosure 1 of the NRC's March 12, 2012, request for information (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12053A340) issued under Title 1O of the Code of Federal Regulations Part 50, Section 50.54(f) (hereafter referred to as the 50.54(f) letter). The NRC staff concludes that the licensee's assessment was performed consistent with the NRG-endorsed SFP Evaluation Guidance Report and that the licensee has provided sufficient information to complete the response to Item 9 of the 50.54(f) letter.
W. Gideon By letter dated February 23 , 2016 (ADAMS Accession No. ML 16055A021
BACKGROUND On March 12, 2012, the NRC issued a 50.54(f) letter as part of implementing lessons learned from the accident at the Fukushima Dai-ichi nuclear power plant. Enclosure 1 to the 50.54(f) letter requested that licensees reevaluate seismic hazards at their sites using present-day methodologies and guidance. Enclosure 1, Item 4, of the 50.54(f) letter requested that licensees perform a comparison of the ground motion response spectrum (GMRS) and the safe shutdown earthquake (SSE). The staff's assessment of the information provided in response to Items 1-3 and 5-7 of the 50.54(f) letter is provided by letter dated March 1, 2016 (ADAMS Accession No. ML16041A435) . Enclosure 1, Item 9, of the 50.54(f) letter requested that, when the GMRS exceeds the SSE in the 1 to 1O Hertz frequency range, 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."
), the Nuclear Energy Institute (NEI) staff submitted Electric Power Research Institute (EPRI) Report No. 3002007148 entitled , " Seismic Evaluation Gu i dance: Spent Fuel Pool Integrity Evaluation" (SFP Evaluation Guidance Report). The SFP Evaluation Guidance Report provides criteria for evaluating th.e se i smic adequacy of an SFP to the reevaluated GMRS hazard levels. This report supplements the gu i dance in EPRI Report 1025287 , " Seismic Evaluation Guidance: Screening , Prioritization and Implementation Details (SPID)" (ADAMS Accession No. ML 12333A 170), for plants where the GMRS peak spectral acceleration is less than or equal to 0.8g (low GMRS sites). The NRC endorsed the SFP Evaluat i on Guidance Report by letter dated March 17 , 2016 (ADAMS Accession No. ML 15350A 158), as an acceptable method for licensees to use when responding to Item 9 in Enclosure 1 of the 50.54(f) letter. By letter dated October 27 , 2015 (ADAMS Accession No. ML 15194A015), the NRC staff stated that SFP evaluation submittals for low GMRS sites are expected by December 31 , 2016. REVIEW OF LICENSEE SPENT FUEL POOL EVALUATION By letter dated December 15 , 2016 (ADAMS Accession No. ML 16365A025), the licensee submitted its SFP evaluation for Brunswick for NRC review. The NRC staff assessed the licensee's implementation of the SFP Evaluation Guidance Report through the completion of a reviewer checklist , which is included as an enclosure to this letter. TECHNICAL EVALUATION Section 3.0 of the SFP Evaluation Guidance Report develops SFP evaluation criteria for plants with GMRS peak spectral acceleration less than or equal to 0.8g. These criteria address SFP structural elements (e.g., floors , walls, and supports); non-structural elements (e.g., penetrations)
 
; seismically-induced SFP sloshing; and water losses due to heat-up and boil-off. Section 3.0 also provides applicability criteria , which will enable licensees to determine if their site-specific conditions are within the bounds considered in developing the evaluat i on criteria for this report. The staff's review consists of confirming that these SFP site-specific conditions are within the bounds considered for the evaluation criteria specified in the SFP Evaluation Guidance Report. 1.1 Spent Fuel Pool Structural Evaluation Section 3.1 of the SFP Evaluation Guidance Report provides a SFP structural evaluation approach used to demonstrate that the SFP structure is sufficiently robust against the reevaluated seismic hazard. This approach supplements the guidance in Section 7 of the SPID and followed acceptable methods used to assess the seismic capacity of structures , systems , and components (SSCs) for nuclear power plants as documented in EPRI NP-6041 , " A Methodology for Assessment of Nuclear Plant Seismic Margin , Revision 1." Table 3-2 of the SFP Evaluation Guidance Report (reproduced from Table 2.3 of EPRI NP-6041) provides the structural screening criteria to assess the SFPs and their supporting structures. The licensee stated that it followed the SFP structural evaluation approach presented in the SFP Evaluation Guidance Report and provided site-specific data to confirm its applicability.
W. Gideon                                         By letter dated February 23, 2016 (ADAMS Accession No. ML16055A021 ), the Nuclear Energy Institute (NEI) staff submitted Electric Power Research Institute (EPRI) Report No. 3002007148 entitled, "Seismic Evaluation Guidance: Spent Fuel Pool Integrity Evaluation" (SFP Evaluation Guidance Report) . The SFP Evaluation Guidance Report provides criteria for evaluating th.e seismic adequacy of an SFP to the reevaluated GMRS hazard levels. This report supplements the guidance in EPRI Report 1025287, "Seismic Evaluation Guidance: Screening, Prioritization and Implementation Details (SPID)" (ADAMS Accession No. ML12333A170), for plants where the GMRS peak spectral acceleration is less than or equal to 0.8g (low GMRS sites). The NRC endorsed the SFP Evaluation Guidance Report by letter dated March 17, 2016 (ADAMS Accession No. ML15350A158), as an acceptable method for licensees to use when responding to Item 9 in Enclosure 1 of the 50.54(f) letter.
W. Gideon The NRC staff reviewed the structural information provided, which included the requested specific data in Section 3.3 of the SFP Evaluation Guidance Report, and confirmed that the evaluation criteria are applicable to the Brunswick site. The staff concludes that SFP SSCs were appropriately evaluated and screened based on the seismic capacity criteria in EPRI NP-6041 , and that the licensee has demonstrated that the SFP structure is sufficiently robust and can withstand ground motions with peak spectral acceleration less than or equal to O.Bg. 1.2 Spent Fuel Pool Non-Structural Evaluation Section 3.2 of the SFP Evaluation Guidance Report provides criteria for evaluating the structural aspects of the SFP , such as piping connections , fuel gates , and anti-siphoning devices, as well as SFP sloshing and heat up and boil-off of SFP water inventory.
By letter dated October 27, 2015 (ADAMS Accession No. ML15194A015), the NRC staff stated that SFP evaluation submittals for low GMRS sites are expected by December 31 , 2016.
Specifically, Table 3-4 of the SFP Evaluation Guidance Report provides a summary of the SFP structural evaluation criteria derived in Section 3.2, along with applicability criteria to demonstrate that site-specific conditions are suitable for applying the evaluation criteria. The licensee stated that it followed the SFP non-structural evaluation approach presented in the guidance report and provided site-specific data to confirm its applicability.
REVIEW OF LICENSEE SPENT FUEL POOL EVALUATION By letter dated December 15, 2016 (ADAMS Accession No. ML16365A025), the licensee submitted its SFP evaluation for Brunswick for NRC review. The NRC staff assessed the licensee's implementation of the SFP Evaluation Guidance Report through the completion of a reviewer checklist, which is included as an enclosure to this letter.
The staff reviewed the non-structural information provided, which included the requested site-specific data in Table 3-4 of the SFP Evaluation Guidance Report, and confirmed that the evaluation criteria are applicable to the Brunswick site. Therefore, the staff concludes that the licensee adequately evaluated the non-structural considerations for SSCs whose failure could lead to potential down of the SFP due to a seismic event. CONCLUSION The NRC staff reviewed the licensee's SFP evaluation report. Based on its review, the NRC staff concludes that the licensee's implementation of the SFP integrity evaluation met the criteria of the SFP Evaluation Guidance Report for Brunswick and therefore , the licensee responded appropriately to Item 9 in Enclosure 1 of the NRC's 50.54(f) letter.
TECHNICAL EVALUATION Section 3.0 of the SFP Evaluation Guidance Report develops SFP evaluation criteria for plants with GMRS peak spectral acceleration less than or equal to 0.8g. These criteria address SFP structural elements (e.g ., floors, walls, and supports); non-structural elements (e.g.,
W. Gideon If you have any questions, please contact me at (301) 415-1617 or via e-mail at Frankie.Vega@nrc.gov.
penetrations) ; seismically-induced SFP sloshing; and water losses due to heat-up and boil-off.
Docket Nos. 50-325 and 50-324  
Section 3.0 also provides applicability criteria, which will enable licensees to determine if their site-specific conditions are within the bounds considered in developing the evaluation criteria for this report. The staff's review consists of confirming that these SFP site-specific conditions are within the bounds considered for the evaluation criteria specified in the SFP Evaluation Guidance Report.
1.1 Spent Fuel Pool Structural Evaluation Section 3.1 of the SFP Evaluation Guidance Report provides a SFP structural evaluation approach used to demonstrate that the SFP structure is sufficiently robust against the reevaluated seismic hazard. This approach supplements the guidance in Section 7 of the SPID and followed acceptable methods used to assess the seismic capacity of structures, systems, and components (SSCs) for nuclear power plants as documented in EPRI NP-6041 , "A Methodology for Assessment of Nuclear Plant Seismic Margin , Revision 1." Table 3-2 of the SFP Evaluation Guidance Report (reproduced from Table 2.3 of EPRI NP-6041) provides the structural screening criteria to assess the SFPs and their supporting structures.
The licensee stated that it followed the SFP structural evaluation approach presented in the SFP Evaluation Guidance Report and provided site-specific data to confirm its applicability.
 
W. Gideon                                       The NRC staff reviewed the structural information provided, which included the requested site-specific data in Section 3.3 of the SFP Evaluation Guidance Report, and confirmed that the evaluation criteria are applicable to the Brunswick site. The staff concludes that SFP SSCs were appropriately evaluated and screened based on the seismic capacity criteria in EPRI NP-6041 , and that the licensee has demonstrated that the SFP structure is sufficiently robust and can withstand ground motions with peak spectral acceleration less than or equal to O.Bg.
1.2 Spent Fuel Pool Non-Structural Evaluation Section 3.2 of the SFP Evaluation Guidance Report provides criteria for evaluating the non-structural aspects of the SFP, such as piping connections, fuel gates, and anti-siphoning devices, as well as SFP sloshing and heat up and boil-off of SFP water inventory. Specifically, Table 3-4 of the SFP Evaluation Guidance Report provides a summary of the SFP non-structural evaluation criteria derived in Section 3.2, along with applicability criteria to demonstrate that site-specific conditions are suitable for applying the evaluation criteria.
The licensee stated that it followed the SFP non-structural evaluation approach presented in the guidance report and provided site-specific data to confirm its applicability. The staff reviewed the non-structural information provided, which included the requested site-specific data in Table 3-4 of the SFP Evaluation Guidance Report, and confirmed that the evaluation criteria are applicable to the Brunswick site. Therefore, the staff concludes that the licensee adequately evaluated the non-structural considerations for SSCs whose failure could lead to potential drain-down of the SFP due to a seismic event.
CONCLUSION The NRC staff reviewed the licensee's SFP evaluation report. Based on its review, the NRC staff concludes that the licensee's implementation of the SFP integrity evaluation met the criteria of the SFP Evaluation Guidance Report for Brunswick and therefore, the licensee responded appropriately to Item 9 in Enclosure 1 of the NRC's 50.54(f) letter.
 
W. Gideon                                   If you have any questions, please contact me at (301) 415-1617 or via e-mail at Frankie.Vega@nrc.gov.
Sincerely, Frankie Vega, Project Manager Hazards Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket Nos. 50-325 and 50-324


==Enclosure:==
==Enclosure:==
Technical Review Checklist cc w/encl: Distribution via Listserv Sincerely , Frankie Vega , Project Manager Hazards Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation TECHNICAL REVIEW CHECKLIST BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO SPENT FUEL POOL EVALUATIONS FOR LOW GROUND MOTION RESPONSE SPECTRUM SITES IMPLEMENTING NEAR-TERM TASK FORCE RECOMMENDATION


===2.1 SEISMIC===
Technical Review Checklist cc w/encl : Distribution via Listserv
BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 DOCKET NOS. 50-325 AND 50-324 BACKGROUND By letter dated March 12, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 12053A340), the U.S. Nuclear Regulatory Commission (NRC) issued a request for information to all power reactor licensees and holders of construction permits in active or deferred status, pursuant to Title 10 of the Code of Federal Regulations (1 O CFR), Section 50.54(f) (hereafter referred to as the "50.54(f) letter'').
 
Enclosure 1 of the 50.54(f) letter requests addressees to reevaluate the seismic hazard at their site using day methods and guidance for licensing new nuclear power plants, and identify actions to address or modify, as necessary, plant components affected by the reevaluated seismic hazards. Enclosure 1, Item 4, of the 50.54(f) letter requested that licensees perform a comparison of the ground motion response spectrum (GMRS) with the safe shutdown earthquake (SSE). Enclosure 1, Item 9, requests that, when the GMRS exceeds the SSE in the 1 to 10 Hertz (Hz) frequency range , a seismic evaluation be made of the spent fuel pool (SFP). More specifically, plants were asked to consider" ... all seismically induced failures that can lead to draining of the SFP." Additionally, by letter dated February 23, 2016 (ADAMS Accession No. ML 16055A021
TECHNICAL REVIEW CHECKLIST BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO SPENT FUEL POOL EVALUATIONS FOR LOW GROUND MOTION RESPONSE SPECTRUM SITES IMPLEMENTING NEAR-TERM TASK FORCE RECOMMENDATION 2.1 SEISMIC BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 DOCKET NOS. 50-325 AND 50-324 BACKGROUND By letter dated March 12, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12053A340), the U.S. Nuclear Regulatory Commission (NRC) issued a request for information to all power reactor licensees and holders of construction permits in active or deferred status, pursuant to Title 10 of the Code of Federal Regulations (1 O CFR), Section 50.54(f) (hereafter referred to as the "50.54(f) letter''). Enclosure 1 of the 50.54(f) letter requests addressees to reevaluate the seismic hazard at their site using present-day methods and guidance for licensing new nuclear power plants, and identify actions to address or modify, as necessary, plant components affected by the reevaluated seismic hazards. Enclosure 1, Item 4, of the 50.54(f) letter requested that licensees perform a comparison of the ground motion response spectrum (GMRS) with the safe shutdown earthquake (SSE). Enclosure 1, Item 9, requests that, when the GMRS exceeds the SSE in the 1 to 10 Hertz (Hz) frequency range, a seismic evaluation be made of the spent fuel pool (SFP).
), the Nuclear Energy Institute (NEI) submitted Electric Power Research Institute (EPRI) Report No. 3002007148 entitled, "Seismic Evaluation Guidance:
More specifically, plants were asked to consider" ... all seismically induced failures that can lead to draining of the SFP."
Spent Fuel Pool Integrity Evaluation" (SFP Evaluation Guidance Report). The SFP Evaluation Guidance Report supports the completion of SFP evaluations for sites with reevaluated seismic hazard exceedance in the 1 to 1 O Hz frequency range. Specifically, the SFP Evaluation Guidance Report addressed those sites where the GMRS peak spectral acceleration (Sa) is less than or equal to 0.8g (low GMRS sites). The NRC endorsed the SFP Evaluation Guidance Report by letter dated March 17, 2016 (ADAMS Accession No. ML 15350A 158), as an acceptable method for licensees to use when responding to Item 9 in Enclosure 1 of the 50.54(f) letter. Licensee deviations from the SFP Evaluation Guidance should be discussed in their SFP evaluation submittal.
Additionally, by letter dated February 23, 2016 (ADAMS Accession No. ML16055A021 ), the Nuclear Energy Institute (NEI) submitted Electric Power Research Institute (EPRI) Report No. 3002007148 entitled, "Seismic Evaluation Guidance: Spent Fuel Pool Integrity Evaluation" (SFP Evaluation Guidance Report). The SFP Evaluation Guidance Report supports the completion of SFP evaluations for sites with reevaluated seismic hazard exceedance in the 1 to 1O Hz frequency range. Specifically, the SFP Evaluation Guidance Report addressed those sites where the GMRS peak spectral acceleration (Sa) is less than or equal to 0.8g (low GMRS sites). The NRC endorsed the SFP Evaluation Guidance Report by letter dated March 17, 2016 (ADAMS Accession No. ML15350A158), as an acceptable method for licensees to use when responding to Item 9 in Enclosure 1 of the 50.54(f) letter. Licensee deviations from the SFP Evaluation Guidance should be discussed in their SFP evaluation submittal.
By letter dated December 15, 2016 (ADAMS Accession No. ML 16365A025), Duke Energy Progress , LLC (Duke, the licensee), provided a SFP report in a response to Enclosure 1, Item 9 , of the 50.54(f) letter for Brunswick Steam Electric Plant , Units 1 and 2 (Brunswick).
By letter dated December 15, 2016 (ADAMS Accession No. ML16365A025), Duke Energy Progress, LLC (Duke, the licensee), provided a SFP report in a response to Enclosure 1, Item 9, of the 50.54(f) letter for Brunswick Steam Electric Plant, Units 1 and 2 (Brunswick). The NRC staff performed its review of the licensee's submittal to assess whether the licensee responded appropriately to Item 9 in Enclosure 1 of the 50.54(f) letter. The NRC staff checked whether the site-specific parameters are within the bounds of the criteria considered in the SFP Evaluation Guidance Report, verified the SFP's seismic adequacy to withstand the reevaluated GMRS hazard levels, and confirmed that the requested information in response to Item 9 of the 50.54(f) letter was provided.
The NRC staff performed its review of the licensee's submittal to assess whether the licensee responded appropriately to Item 9 in Enclosure 1 of the 50.54(f) letter. The NRC staff checked whether the site-specific parameters are within the bounds of the criteria considered in the SFP Evaluation Guidance Report, verified the SFP's seismic adequacy to withstand the reevaluated GMRS hazard levels, and confirmed that the requested information in response to Item 9 of th e 50.54(f) letter was provided.
Enclosure
Enclosure   A review checklist was used for consistency and scope. The application of this staff review is limited to the SFP evaluation as part of the seismic review of low GMRS sites as part of the Near-Term Task Force (NTTF) Recommendation 2.1.
 
NTTF Recommendation
A review checklist was used for consistency and scope. The application of this staff review is limited to the SFP evaluation as part of the seismic review of low GMRS sites as part of the Near-Term Task Force (NTTF) Recommendation 2.1.


===2.1 Spent===
NTTF Recommendation 2.1 Spent Fuel Pool Evaluations Technical Review Checklist for Brunswick Steam Electric P_            lant, Units 1 and 2 Site Parameters:
Fuel Pool Evaluations Technical Review Checklist for Brunswick Steam Electric P_lant, Units 1 and 2 Site Parameters:
I.       Site-Specific GMRS The licensee:
I. Site-Specific GMRS The licensee:
* Provided the site-specific GMRS consistent with the information             Yes provided in the Seismic Hazard and Screening Report (SHSR), or its update, and evaluated by the staff in its staff assessment.
* Provided the site-specific GMRS consistent with the information Yes provided in the Seismic Hazard and Screening Report (SHSR), or its update , and evaluated by the staff in its staff assessment.
* Stated that the GMRS peak Sa is less than or equal to 0.8g for any         Yes frequency.
* Stated that the GMRS peak S a is less than or equal to 0.8g for any Yes frequency. Notes from the reviewer:  
Notes from the reviewer:
: 1. The NRC staff confirmed that the site-specific peak S a= 0.563g (SHSR -ADAMS Accession No. ML 14106A461
: 1. The NRC staff confirmed that the site-specific peak Sa = 0.563g (SHSR - ADAMS Accession No. ML14106A461 ).
). Deviation(s) or Deficiency(ies), and Resolution
Deviation(s) or Deficiency(ies), and Resolution:
: No deviations or deficiencies were identified.
No deviations or deficiencies were identified.
The NRC staff concludes:
The NRC staff concludes:
* The site-specific GMRS peak S a at any frequency i s less than 0.8g .
* The site-specific GMRS peak Sa at any frequency is less than 0.8g .         Yes
* The licensee's GMRS used in this evaluation is consistent with the information provided in the SHSR. Structural Parameters:
* The licensee's GMRS used in this evaluation is consistent with the         Yes information provided in the SHSR.
II. Seismic Design of the SFP Structure The licensee:
Structural Parameters:
* Specified the building housing the SFP.
II.       Seismic Design of the SFP Structure The licensee:
* Specified the plant's peak ground acceleration (PGA).
* Specified the building housing the SFP.                                     Yes
* Stated th a t the building housing the SFP w a s designed u s ing a n SSE with a PGA of at least 0.1 g. Yes Yes Yes Y e s Y e s Notes from the reviewer:  
* Specified the plant's peak ground acceleration (PGA).                       Yes
: 1. The NRC staff confirmed that the SFP is housed in the reactor building which is seismically designed to the site SSE with a PGA of 0.16g (SHSR Section 3.1 and Updated Final Safety Analysis Report (UFSAR , Section 3.2.1 and 3.8) Deviation(s) or Deficiency(ies), and Resolution:
* Stated that the building housing the SFP was designed using an              Yes SSE with a PGA of at least 0.1g.
Notes from the reviewer:
: 1. The NRC staff confirmed that the SFP is housed in the reactor building which is seismically designed to the site SSE with a PGA of 0.16g (SHSR Section 3.1 and Updated Final Safety Analysis Report (UFSAR, Section 3.2.1 and 3.8)
Deviation(s) or Deficiency(ies), and Resolution:
No deviations or deficiencies were identified.
No deviations or deficiencies were identified.
The NRC staff concludes that:
The NRC staff concludes that:
* The structure housing the SFP was designed using an SSE w i th a Yes PGA of at least 0.1 g. Ill. Structural Load Path to the SFP The licensee:
* The structure housing the SFP was designed using an SSE with a               Yes PGA of at least 0.1 g.
* Provided a description of the structural load path from the Y e s foundation to the SFP.
Ill. Structural Load Path to the SFP The licensee:
* Performed screening based on EPRI NP-6041 Table 2-3 screening Yes criteria. Notes from the reviewer:  
* Provided a description of the structural load path from the                   Yes foundation to the SFP.
: 1. The staff verified the structural load path to the SFP. The staff confirmed that the structural load path from the reactor building foundation to the SFP consists of a combination of reinforced concrete shear wall elements , reinforced concrete frame elements , post-tensioned concrete elements , and/or structural steel frame elements (UFSAR Section 3.8.4). Deviation(s) or Deficiency(ies), and Resolution:
* Performed screening based on EPRI NP-6041 Table 2-3 screening                 Yes criteria.
Notes from the reviewer:
: 1. The staff verified the structural load path to the SFP. The staff confirmed that the structural load path from the reactor building foundation to the SFP consists of a combination of reinforced concrete shear wall elements, reinforced concrete frame elements, post-tensioned concrete elements, and/or structural steel frame elements (UFSAR Section 3.8.4).
Deviation(s) or Deficiency(ies), and Resolution:
No deviations or deficiencies were identified.
No deviations or deficiencies were identified.
The NRC staff concludes that:
The NRC staff concludes that:
* Licen see a ppropriately de sc ribed the stru c tur a l l o a d p a th to th e SFP.
* Licensee appropriately described the structural load path to the              Yes SFP.
* Structures were appropriately screened based on the screen i ng criteria in EPRI NP-6041. Y es Yes IV. SFP Structure Included in the Civil Inspection Program Performed in Accordance with Maintenance Rule The licensee:
* Structures were appropriately screened based on the screening                  Yes criteria in EPRI NP-6041.
* Stated that the SFP structure is included in the Civil Inspection Yes Program performed in accordance with Maintenance Rule (1 O CFR 50.65). Notes from the reviewer:
IV. SFP Structure Included in the Civil Inspection Program Performed in Accordance with Maintenance Rule The licensee:
* Stated that the SFP structure is included in the Civil Inspection           Yes Program performed in accordance with Maintenance Rule (1 O CFR 50.65).
Notes from the reviewer:
None Deviation(s) or Deficiency(ies), and Resolution:
None Deviation(s) or Deficiency(ies), and Resolution:
No deviations or deficiencies were identified. The NRC staff concludes that:
No deviations or deficiencies were identified.
* The SFP structure is included in the Civil Inspection Program Yes performed in accordance with Maintenance Rule (1 O CFR 50.65). Non-Structural Parameters:
The NRC staff concludes that:
* The SFP structure is included in the Civil Inspection Program               Yes performed in accordance with Maintenance Rule (1 O CFR 50.65) .
Non-Structural Parameters:
V. Applicability of Piping Evaluation The licensee:
V. Applicability of Piping Evaluation The licensee:
* Stated that piping attached to the SFP is evaluated to the SSE . Yes Notes from the reviewer:  
* Stated that piping attached to the SFP is evaluated to the SSE .           Yes Notes from the reviewer:
: 1. T h e licen s ee stated th a t piping a tt a ched to th e S F P is Cl a s s 1 p i ping ev a lu a t e d to th e SSE (UFSAR Section 3.2.1.6). Deviation(s) or Deficiency(ies), and Resolution:
: 1. The licensee stated that piping attached to the SFP is Class 1 piping evaluated to the SSE (UFSAR Section 3.2.1 .6).
No devi a tions or deficienci es w e re i dentified.
Deviation(s) or Deficiency(ies), and Resolution:
No deviations or deficiencies were identified.
The NRC staff concludes that:
The NRC staff concludes that:
* The piping attached to the SFP is evaluated to the SSE . Yes
* The piping attached to the SFP is evaluated to the SSE .                   Yes
* Applicability cr i teria specified in Table 3-4 of SFP evaluation Yes guid a nce h a v e been m e t.
* Applicability criteria specified in Table 3-4 of SFP evaluation             Yes guidance have been met.
VI. Siphoning Evaluation The licensee:
VI. Siphoning Evaluation The licensee:
* Stated that anti-siphoning devices are installed on piping systems Yes that could lead to siphoning inventory from the SFP.
* Stated that anti-siphoning devices are installed on piping systems           Yes that could lead to siphoning inventory from the SFP.
* In cases where anti-siphoning devices were not included on the N/A applicable piping, a description documenting the evaluation performed to determine the seismic adequacy of the piping is provided.
* In cases where anti-siphoning devices were not included on the               N/A applicable piping, a description documenting the evaluation performed to determine the seismic adequacy of the piping is provided.
* Stated that the piping of the SFP cooling system cannot lead fo rapid No drain down due to siphoning.
* Stated that the piping of the SFP cooling system cannot lead fo rapid         No drain down due to siphoning.
* Stated that no anti-siphoning devices are attached to 2" or smaller piping with extremely large extended operators. Yes
* Stated that no anti-siphoning devices are attached to 2" or smaller Yes piping with extremely large extended operators.
* Provided a seismic adequacy evaluation, in accordance with NP-6041, for cases where active siphoning devices are attached to 2" or N/A smaller piping with extremely large extended operators.
* Provided a seismic adequacy evaluation, in accordance with NP-N/A 6041, for cases where active siphoning devices are attached to 2" or smaller piping with extremely large extended operators.
Notes from the reviewer:  
Notes from the reviewer:
: 1. The licensee stated that anti-siphoning devices are installed on all SFP piping that could lead to siphoning (UFSAR Section 9.1.3.2).  
: 1. The licensee stated that anti-siphoning devices are installed on all SFP piping that could lead to siphoning (UFSAR Section 9.1.3.2).
: 2. Piping of the SFP cooling system is not likely to lead to rapid draindown due to siphoning.
: 2. Piping of the SFP cooling system is not likely to lead to rapid draindown due to siphoning.
Deviation(s) or Deficiency(ies), and Resolution:
Deviation(s) or Deficiency(ies), and Resolution:
No deviations or deficiencies were identified. The NRC staff concludes:
No deviations or deficiencies were identified.
* Anti-siphoning devices exist in applicable piping systems that could Yes lead to siphoning water from the SFP.
The NRC staff concludes:
* Piping of the SFP cooling system is not likely to lead to rapid Yes draindown due to siphoning.
* Anti-siphoning devices exist in applicable piping systems that could         Yes lead to siphoning water from the SFP.
* No active anti-siphoning devices are attached to 2" or smaller piping Yes with extremely large extended operators.
* Piping of the SFP cooling system is not likely to lead to rapid               Yes draindown due to siphoning.
* Applicability criteria specified in Table 3-4 of SFP evaluation Yes guidance have been met.
* No active anti-siphoning devices are attached to 2" or smaller piping         Yes with extremely large extended operators.
Yes
* Applicability criteria specified in Table 3-4 of SFP evaluation guidance have been met.
VII. Sloshing Evaluation The licensee:
VII. Sloshing Evaluation The licensee:
* Specified the SFP dimensions (length, width, and depth). Yes
* Specified the SFP dimensions (length, width, and depth) .               Yes
* Specified that the SFP dimensions are bounded by the dimensions Yes specified in the report (i.e., SFP length and width <125ft.; SFP depth >36ft.).
* Specified that the SFP dimensions are bounded by the dimensions         Yes specified in the report (i .e., SFP length and width <125ft.; SFP depth >36ft.) .
* Stated that the peak Sa in the frequency range less than 0.3 Hz is Yes less than 0.1 g. Notes from the reviewer:  
* Stated that the peak Sa in the frequency range less than 0.3 Hz is       Yes less than 0.1g.
: 1. Unit 1 -SFP dimensions (UFSAR Section 9.1.2.2.1)  
Notes from the reviewer:
-SFP Length -46 ft. -SFP Width -28 ft. -SFP Depth -38. 75 ft. 2. The staff confirmed in the SHSR that the peak Sa in the frequency range less than 0.3 Hz is less than 0.1 g (SHSR). Deviation(s) or Deficiency(ies), and Resolution:
: 1. Unit 1 - SFP dimensions (UFSAR Section 9.1.2.2.1)
        - SFP Length - 46 ft.
        - SFP Width - 28 ft.
        - SFP Depth - 38. 75 ft.
: 2. The staff confirmed in the SHSR that the peak Sa in the frequency range less than 0.3 Hz is less than 0.1 g (SHSR).
Deviation(s) or Deficiency(ies), and Resolution:
No deviations or deficiencies were identified.
The NRC staff concludes:
* SFP dimensions are bounded by the dimensions specified in the            Yes report (i.e ., SFP length and width <125ft. ; SFP depth >36ft.).
* The peak Sa in the frequency range less than 0.3 Hz is less than        Yes 0.1g.
* Applicability criteria specified in Table 3-4 of SFP evaluation          Yes guidance have been met.
VIII. Evaporation Evaluation The licensee:
* Provided the surface area of the plant's SFP .                          Yes
* Stated that the surface area of the plant's SFP is greater than        Yes 500 ft 2 .
* Provided the licensed reactor core thermal power .                      Yes
* Stated that the reactor core thermal power is less than 4,000          Yes megawatt thermal (MW1) per unit.
Notes from the reviewer:
: 1. Surface area of pool = 1,288 ft2
: 2. Reactor thermal power= 2,923 MW1(UFSAR Section 1.1)
Deviation(s) or Deficiency(ies), and Resolution:
No deviations or deficiencies were identified.
No deviations or deficiencies were identified.
The NRC staff concludes:
The NRC staff concludes:
* SFP dimensions are bounded by the dimensions specified in the report (i.e., SFP length and width <125ft.; SFP depth >36ft.).
* The surface area of the plant's SFP is greater than 500 ft2 .               Yes
* The peak Sa in the frequency range less than 0.3 Hz is less than 0.1g.
* The reactor core thermal power is less than 4,000 MW1per unit.             Yes
* Applicability criteria specified in Table 3-4 of SFP evaluation guidance have been met. VIII. Evaporation Evaluation The licensee:
* Applicability criteria specified in Table 3-4 of SFP evaluation             Yes guidance have been met.
* Provided the surface area of the plant's SFP .
* Stated that the surface area of the plant's SFP is greater than 500 ft 2.
* Provided the licensed reactor core thermal power .
* Stated that the reactor core thermal power is less than 4,000 megawatt thermal (MW1) per unit. Yes Yes Yes Yes Yes Yes Yes Notes from the reviewer:
: 1. Surface area of pool = 1 , 288 ft 2 2. Reactor thermal power= 2 , 923 MW 1 (UFSAR Section 1.1) Deviation(s) or Deficiency(ies), and Resolution:
No deviations or deficiencies were identified. The NRC staff concludes:
* The surface area of the plant's SFP is greater than 500 ft 2. Yes
* The reactor core thermal power is less than 4 , 000 MW 1 per unit. Yes
* Applicability criteria specified in Table 3-4 of SFP evaluation Yes guidance have been met.


== Conclusions:==
==
Conclusions:==


The NRC staff reviewed the licensee's SFP evaluation report. Based on its r eview , the NRC staff concludes that the licensee's implementation of the SFP integrity evaluation met the criteri a of the SFP Evaluation Guidance Report for Brunswick and therefore the licensee responded appropriately to Item 9 in Enclosure 1 of the 50.54(f) letter.
The NRC staff reviewed the licensee's SFP evaluation report. Based on its review, the NRC staff concludes that the licensee's implementation of the SFP integrity evaluation met the criteria of the SFP Evaluation Guidance Report for Brunswick and therefore the licensee responded appropriately to Item 9 in Enclosure 1 of the 50.54(f) letter.
W. Gideon BRUNSWICK STEAM ELECTRIC PLANT , UNITS 1 AND 2 -STAFF REVIEW OF SPENT FUEL POOL EVALUATION ASSOCIATED WITH REEVALUATED SEISMIC HAZARD IMPLEMENTING NEAR-TERM TASK FORCE RECOMMENDATION


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Latest revision as of 21:37, 18 March 2020

Staff Review of Spent Fuel Pool Evaluation Associated with Reevaluated Seismic Hazard Implementing Near-Term Task Force Recommendation 2.1
ML17031A001
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 02/02/2017
From: Frankie Vega
Japan Lessons-Learned Division
To: William Gideon
Duke Energy Progress
Vega F, NRR/JLD 415-1617
References
CAC MF3824, CAC MF3825
Download: ML17031A001 (13)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 2, 2017 Mr. William R. Gideon Site Vice President Brunswick Steam Electric Plant Brunswick Steam Electric Plant 8470 River Rd. SE (M/C BNP001)

Southport, NC 28461

SUBJECT:

BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1AND2 - STAFF REVIEW OF SPENT FUEL POOL EVALUATION ASSOCIATED WITH REEVALUATED SEISMIC HAZARD IMPLEMENTING NEAR-TERM TASK FORCE RECOMMENDATION 2.1 (CAC NOS. MF3824 AND MF3825)

Dear Mr. Gideon:

The purpose of this letter is to inform Duke Energy Progress, LLC (Duke , the licensee) of the results of the U.S. Nuclear Regulatory Commission (NRC) staff's review of the spent fuel pool (SFP) evaluation for Brunswick Steam Electric Plant, Units 1 and 2 (Brunswick), which was submitted in response to Item 9 of Enclosure 1 of the NRC's March 12, 2012, request for information (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12053A340) issued under Title 1O of the Code of Federal Regulations Part 50, Section 50.54(f) (hereafter referred to as the 50.54(f) letter). The NRC staff concludes that the licensee's assessment was performed consistent with the NRG-endorsed SFP Evaluation Guidance Report and that the licensee has provided sufficient information to complete the response to Item 9 of the 50.54(f) letter.

BACKGROUND On March 12, 2012, the NRC issued a 50.54(f) letter as part of implementing lessons learned from the accident at the Fukushima Dai-ichi nuclear power plant. Enclosure 1 to the 50.54(f) letter requested that licensees reevaluate seismic hazards at their sites using present-day methodologies and guidance. Enclosure 1, Item 4, of the 50.54(f) letter requested that licensees perform a comparison of the ground motion response spectrum (GMRS) and the safe shutdown earthquake (SSE). The staff's assessment of the information provided in response to Items 1-3 and 5-7 of the 50.54(f) letter is provided by letter dated March 1, 2016 (ADAMS Accession No. ML16041A435) . Enclosure 1, Item 9, of the 50.54(f) letter requested that, when the GMRS exceeds the SSE in the 1 to 1O Hertz frequency range, 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."

W. Gideon By letter dated February 23, 2016 (ADAMS Accession No. ML16055A021 ), the Nuclear Energy Institute (NEI) staff submitted Electric Power Research Institute (EPRI) Report No. 3002007148 entitled, "Seismic Evaluation Guidance: Spent Fuel Pool Integrity Evaluation" (SFP Evaluation Guidance Report) . The SFP Evaluation Guidance Report provides criteria for evaluating th.e seismic adequacy of an SFP to the reevaluated GMRS hazard levels. This report supplements the guidance in EPRI Report 1025287, "Seismic Evaluation Guidance: Screening, Prioritization and Implementation Details (SPID)" (ADAMS Accession No. ML12333A170), for plants where the GMRS peak spectral acceleration is less than or equal to 0.8g (low GMRS sites). The NRC endorsed the SFP Evaluation Guidance Report by letter dated March 17, 2016 (ADAMS Accession No. ML15350A158), as an acceptable method for licensees to use when responding to Item 9 in Enclosure 1 of the 50.54(f) letter.

By letter dated October 27, 2015 (ADAMS Accession No. ML15194A015), the NRC staff stated that SFP evaluation submittals for low GMRS sites are expected by December 31 , 2016.

REVIEW OF LICENSEE SPENT FUEL POOL EVALUATION By letter dated December 15, 2016 (ADAMS Accession No. ML16365A025), the licensee submitted its SFP evaluation for Brunswick for NRC review. The NRC staff assessed the licensee's implementation of the SFP Evaluation Guidance Report through the completion of a reviewer checklist, which is included as an enclosure to this letter.

TECHNICAL EVALUATION Section 3.0 of the SFP Evaluation Guidance Report develops SFP evaluation criteria for plants with GMRS peak spectral acceleration less than or equal to 0.8g. These criteria address SFP structural elements (e.g ., floors, walls, and supports); non-structural elements (e.g.,

penetrations) ; seismically-induced SFP sloshing; and water losses due to heat-up and boil-off.

Section 3.0 also provides applicability criteria, which will enable licensees to determine if their site-specific conditions are within the bounds considered in developing the evaluation criteria for this report. The staff's review consists of confirming that these SFP site-specific conditions are within the bounds considered for the evaluation criteria specified in the SFP Evaluation Guidance Report.

1.1 Spent Fuel Pool Structural Evaluation Section 3.1 of the SFP Evaluation Guidance Report provides a SFP structural evaluation approach used to demonstrate that the SFP structure is sufficiently robust against the reevaluated seismic hazard. This approach supplements the guidance in Section 7 of the SPID and followed acceptable methods used to assess the seismic capacity of structures, systems, and components (SSCs) for nuclear power plants as documented in EPRI NP-6041 , "A Methodology for Assessment of Nuclear Plant Seismic Margin , Revision 1." Table 3-2 of the SFP Evaluation Guidance Report (reproduced from Table 2.3 of EPRI NP-6041) provides the structural screening criteria to assess the SFPs and their supporting structures.

The licensee stated that it followed the SFP structural evaluation approach presented in the SFP Evaluation Guidance Report and provided site-specific data to confirm its applicability.

W. Gideon The NRC staff reviewed the structural information provided, which included the requested site-specific data in Section 3.3 of the SFP Evaluation Guidance Report, and confirmed that the evaluation criteria are applicable to the Brunswick site. The staff concludes that SFP SSCs were appropriately evaluated and screened based on the seismic capacity criteria in EPRI NP-6041 , and that the licensee has demonstrated that the SFP structure is sufficiently robust and can withstand ground motions with peak spectral acceleration less than or equal to O.Bg.

1.2 Spent Fuel Pool Non-Structural Evaluation Section 3.2 of the SFP Evaluation Guidance Report provides criteria for evaluating the non-structural aspects of the SFP, such as piping connections, fuel gates, and anti-siphoning devices, as well as SFP sloshing and heat up and boil-off of SFP water inventory. Specifically, Table 3-4 of the SFP Evaluation Guidance Report provides a summary of the SFP non-structural evaluation criteria derived in Section 3.2, along with applicability criteria to demonstrate that site-specific conditions are suitable for applying the evaluation criteria.

The licensee stated that it followed the SFP non-structural evaluation approach presented in the guidance report and provided site-specific data to confirm its applicability. The staff reviewed the non-structural information provided, which included the requested site-specific data in Table 3-4 of the SFP Evaluation Guidance Report, and confirmed that the evaluation criteria are applicable to the Brunswick site. Therefore, the staff concludes that the licensee adequately evaluated the non-structural considerations for SSCs whose failure could lead to potential drain-down of the SFP due to a seismic event.

CONCLUSION The NRC staff reviewed the licensee's SFP evaluation report. Based on its review, the NRC staff concludes that the licensee's implementation of the SFP integrity evaluation met the criteria of the SFP Evaluation Guidance Report for Brunswick and therefore, the licensee responded appropriately to Item 9 in Enclosure 1 of the NRC's 50.54(f) letter.

W. Gideon If you have any questions, please contact me at (301) 415-1617 or via e-mail at Frankie.Vega@nrc.gov.

Sincerely, Frankie Vega, Project Manager Hazards Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket Nos. 50-325 and 50-324

Enclosure:

Technical Review Checklist cc w/encl : Distribution via Listserv

TECHNICAL REVIEW CHECKLIST BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO SPENT FUEL POOL EVALUATIONS FOR LOW GROUND MOTION RESPONSE SPECTRUM SITES IMPLEMENTING NEAR-TERM TASK FORCE RECOMMENDATION 2.1 SEISMIC BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 DOCKET NOS. 50-325 AND 50-324 BACKGROUND By letter dated March 12, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12053A340), the U.S. Nuclear Regulatory Commission (NRC) issued a request for information to all power reactor licensees and holders of construction permits in active or deferred status, pursuant to Title 10 of the Code of Federal Regulations (1 O CFR), Section 50.54(f) (hereafter referred to as the "50.54(f) letter). Enclosure 1 of the 50.54(f) letter requests addressees to reevaluate the seismic hazard at their site using present-day methods and guidance for licensing new nuclear power plants, and identify actions to address or modify, as necessary, plant components affected by the reevaluated seismic hazards. Enclosure 1, Item 4, of the 50.54(f) letter requested that licensees perform a comparison of the ground motion response spectrum (GMRS) with the safe shutdown earthquake (SSE). Enclosure 1, Item 9, requests that, when the GMRS exceeds the SSE in the 1 to 10 Hertz (Hz) frequency range, a seismic evaluation be made of the spent fuel pool (SFP).

More specifically, plants were asked to consider" ... all seismically induced failures that can lead to draining of the SFP."

Additionally, by letter dated February 23, 2016 (ADAMS Accession No. ML16055A021 ), the Nuclear Energy Institute (NEI) submitted Electric Power Research Institute (EPRI) Report No. 3002007148 entitled, "Seismic Evaluation Guidance: Spent Fuel Pool Integrity Evaluation" (SFP Evaluation Guidance Report). The SFP Evaluation Guidance Report supports the completion of SFP evaluations for sites with reevaluated seismic hazard exceedance in the 1 to 1O Hz frequency range. Specifically, the SFP Evaluation Guidance Report addressed those sites where the GMRS peak spectral acceleration (Sa) is less than or equal to 0.8g (low GMRS sites). The NRC endorsed the SFP Evaluation Guidance Report by letter dated March 17, 2016 (ADAMS Accession No. ML15350A158), as an acceptable method for licensees to use when responding to Item 9 in Enclosure 1 of the 50.54(f) letter. Licensee deviations from the SFP Evaluation Guidance should be discussed in their SFP evaluation submittal.

By letter dated December 15, 2016 (ADAMS Accession No. ML16365A025), Duke Energy Progress, LLC (Duke, the licensee), provided a SFP report in a response to Enclosure 1, Item 9, of the 50.54(f) letter for Brunswick Steam Electric Plant, Units 1 and 2 (Brunswick). The NRC staff performed its review of the licensee's submittal to assess whether the licensee responded appropriately to Item 9 in Enclosure 1 of the 50.54(f) letter. The NRC staff checked whether the site-specific parameters are within the bounds of the criteria considered in the SFP Evaluation Guidance Report, verified the SFP's seismic adequacy to withstand the reevaluated GMRS hazard levels, and confirmed that the requested information in response to Item 9 of the 50.54(f) letter was provided.

Enclosure

A review checklist was used for consistency and scope. The application of this staff review is limited to the SFP evaluation as part of the seismic review of low GMRS sites as part of the Near-Term Task Force (NTTF) Recommendation 2.1.

NTTF Recommendation 2.1 Spent Fuel Pool Evaluations Technical Review Checklist for Brunswick Steam Electric P_ lant, Units 1 and 2 Site Parameters:

I. Site-Specific GMRS The licensee:

  • Provided the site-specific GMRS consistent with the information Yes provided in the Seismic Hazard and Screening Report (SHSR), or its update, and evaluated by the staff in its staff assessment.
  • Stated that the GMRS peak Sa is less than or equal to 0.8g for any Yes frequency.

Notes from the reviewer:

1. The NRC staff confirmed that the site-specific peak Sa = 0.563g (SHSR - ADAMS Accession No. ML14106A461 ).

Deviation(s) or Deficiency(ies), and Resolution:

No deviations or deficiencies were identified.

The NRC staff concludes:

  • The site-specific GMRS peak Sa at any frequency is less than 0.8g . Yes
  • The licensee's GMRS used in this evaluation is consistent with the Yes information provided in the SHSR.

Structural Parameters:

II. Seismic Design of the SFP Structure The licensee:

  • Specified the building housing the SFP. Yes
  • Specified the plant's peak ground acceleration (PGA). Yes
  • Stated that the building housing the SFP was designed using an Yes SSE with a PGA of at least 0.1g.

Notes from the reviewer:

1. The NRC staff confirmed that the SFP is housed in the reactor building which is seismically designed to the site SSE with a PGA of 0.16g (SHSR Section 3.1 and Updated Final Safety Analysis Report (UFSAR, Section 3.2.1 and 3.8)

Deviation(s) or Deficiency(ies), and Resolution:

No deviations or deficiencies were identified.

The NRC staff concludes that:

  • The structure housing the SFP was designed using an SSE with a Yes PGA of at least 0.1 g.

Ill. Structural Load Path to the SFP The licensee:

  • Provided a description of the structural load path from the Yes foundation to the SFP.
  • Performed screening based on EPRI NP-6041 Table 2-3 screening Yes criteria.

Notes from the reviewer:

1. The staff verified the structural load path to the SFP. The staff confirmed that the structural load path from the reactor building foundation to the SFP consists of a combination of reinforced concrete shear wall elements, reinforced concrete frame elements, post-tensioned concrete elements, and/or structural steel frame elements (UFSAR Section 3.8.4).

Deviation(s) or Deficiency(ies), and Resolution:

No deviations or deficiencies were identified.

The NRC staff concludes that:

  • Licensee appropriately described the structural load path to the Yes SFP.
  • Structures were appropriately screened based on the screening Yes criteria in EPRI NP-6041.

IV. SFP Structure Included in the Civil Inspection Program Performed in Accordance with Maintenance Rule The licensee:

  • Stated that the SFP structure is included in the Civil Inspection Yes Program performed in accordance with Maintenance Rule (1 O CFR 50.65).

Notes from the reviewer:

None Deviation(s) or Deficiency(ies), and Resolution:

No deviations or deficiencies were identified.

The NRC staff concludes that:

  • The SFP structure is included in the Civil Inspection Program Yes performed in accordance with Maintenance Rule (1 O CFR 50.65) .

Non-Structural Parameters:

V. Applicability of Piping Evaluation The licensee:

  • Stated that piping attached to the SFP is evaluated to the SSE . Yes Notes from the reviewer:
1. The licensee stated that piping attached to the SFP is Class 1 piping evaluated to the SSE (UFSAR Section 3.2.1 .6).

Deviation(s) or Deficiency(ies), and Resolution:

No deviations or deficiencies were identified.

The NRC staff concludes that:

  • The piping attached to the SFP is evaluated to the SSE . Yes
  • Applicability criteria specified in Table 3-4 of SFP evaluation Yes guidance have been met.

VI. Siphoning Evaluation The licensee:

  • Stated that anti-siphoning devices are installed on piping systems Yes that could lead to siphoning inventory from the SFP.
  • In cases where anti-siphoning devices were not included on the N/A applicable piping, a description documenting the evaluation performed to determine the seismic adequacy of the piping is provided.
  • Stated that the piping of the SFP cooling system cannot lead fo rapid No drain down due to siphoning.
  • Stated that no anti-siphoning devices are attached to 2" or smaller Yes piping with extremely large extended operators.
  • Provided a seismic adequacy evaluation, in accordance with NP-N/A 6041, for cases where active siphoning devices are attached to 2" or smaller piping with extremely large extended operators.

Notes from the reviewer:

1. The licensee stated that anti-siphoning devices are installed on all SFP piping that could lead to siphoning (UFSAR Section 9.1.3.2).
2. Piping of the SFP cooling system is not likely to lead to rapid draindown due to siphoning.

Deviation(s) or Deficiency(ies), and Resolution:

No deviations or deficiencies were identified.

The NRC staff concludes:

  • Anti-siphoning devices exist in applicable piping systems that could Yes lead to siphoning water from the SFP.
  • Piping of the SFP cooling system is not likely to lead to rapid Yes draindown due to siphoning.
  • No active anti-siphoning devices are attached to 2" or smaller piping Yes with extremely large extended operators.

Yes

  • Applicability criteria specified in Table 3-4 of SFP evaluation guidance have been met.

VII. Sloshing Evaluation The licensee:

  • Specified the SFP dimensions (length, width, and depth) . Yes
  • Specified that the SFP dimensions are bounded by the dimensions Yes specified in the report (i .e., SFP length and width <125ft.; SFP depth >36ft.) .
  • Stated that the peak Sa in the frequency range less than 0.3 Hz is Yes less than 0.1g.

Notes from the reviewer:

1. Unit 1 - SFP dimensions (UFSAR Section 9.1.2.2.1)

- SFP Length - 46 ft.

- SFP Width - 28 ft.

- SFP Depth - 38. 75 ft.

2. The staff confirmed in the SHSR that the peak Sa in the frequency range less than 0.3 Hz is less than 0.1 g (SHSR).

Deviation(s) or Deficiency(ies), and Resolution:

No deviations or deficiencies were identified.

The NRC staff concludes:

  • SFP dimensions are bounded by the dimensions specified in the Yes report (i.e ., SFP length and width <125ft. ; SFP depth >36ft.).
  • The peak Sa in the frequency range less than 0.3 Hz is less than Yes 0.1g.
  • Applicability criteria specified in Table 3-4 of SFP evaluation Yes guidance have been met.

VIII. Evaporation Evaluation The licensee:

  • Provided the surface area of the plant's SFP . Yes
  • Stated that the surface area of the plant's SFP is greater than Yes 500 ft 2 .
  • Provided the licensed reactor core thermal power . Yes
  • Stated that the reactor core thermal power is less than 4,000 Yes megawatt thermal (MW1) per unit.

Notes from the reviewer:

1. Surface area of pool = 1,288 ft2
2. Reactor thermal power= 2,923 MW1(UFSAR Section 1.1)

Deviation(s) or Deficiency(ies), and Resolution:

No deviations or deficiencies were identified.

The NRC staff concludes:

  • The surface area of the plant's SFP is greater than 500 ft2 . Yes
  • The reactor core thermal power is less than 4,000 MW1per unit. Yes
  • Applicability criteria specified in Table 3-4 of SFP evaluation Yes guidance have been met.

==

Conclusions:==

The NRC staff reviewed the licensee's SFP evaluation report. Based on its review, the NRC staff concludes that the licensee's implementation of the SFP integrity evaluation met the criteria of the SFP Evaluation Guidance Report for Brunswick and therefore the licensee responded appropriately to Item 9 in Enclosure 1 of the 50.54(f) letter.

ML17031A001

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