ML15245A816: Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:NRR-PMDAPEm Resource From:                     Jackson, Diane Sent:                     Friday, August 28, 2015 3:28 PM To:                       Shams, Mohamed Cc:                       DiFrancesco, Nicholas; Spence, Jane; Devlin-Gill, Stephanie; Roche, Kevin; Yee, On; 50.54f_Seismic Resource; RidsNroDsea Resource; Wyman, Stephen; Rivera-Lugo, Richard; Patterson, Malcolm; Hoang, Dan; Le, Tuan; Heeszel, David
{{#Wiki_filter:1 NRR-PMDAPEm Resource From:
Jackson, Diane Sent:
Friday, August 28, 2015 3:28 PM To:
Shams, Mohamed Cc:
DiFrancesco, Nicholas; Spence, Jane; Devlin-Gill, Stephanie; Roche, Kevin; Yee, On; 50.54f_Seismic Resource; RidsNroDsea Resource; Wyman, Stephen; Rivera-Lugo, Richard; Patterson, Malcolm; Hoang, Dan; Le, Tuan; Heeszel, David


==Subject:==
==Subject:==
DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1 - TECHNICAL REVIEW CHECKLIST RELATED TO INTERIM ESEP SUPPORTING IMPLEMENTATION OF NTTF R2.1, SEISMIC (TAC NO. MF5238)
DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1 - TECHNICAL REVIEW CHECKLIST RELATED TO INTERIM ESEP SUPPORTING IMPLEMENTATION OF NTTF R2.1, SEISMIC (TAC NO. MF5238)
Attachments:               Davis Besse R2.1 Seismic ESEP NRC Review.docx August 28, 2015 MEMORANDUM TO: Mohamed K. Shams, Chief Hazards Management Branch (JHMB)
Attachments:
Davis Besse R2.1 Seismic ESEP NRC Review.docx August 28, 2015 MEMORANDUM TO: Mohamed K. Shams, Chief Hazards Management Branch (JHMB)
Japan Lessons-Learned Division Office of Nuclear Reactor Regulation FROM: Diane T. Jackson, Chief Geosciences and Geotechnical Engineering Branch 2 (RGS2)
Japan Lessons-Learned Division Office of Nuclear Reactor Regulation FROM: Diane T. Jackson, Chief Geosciences and Geotechnical Engineering Branch 2 (RGS2)
Division of Site Safety and Environmental Analysis Office of New Reactors
Division of Site Safety and Environmental Analysis Office of New Reactors  


==SUBJECT:==
==SUBJECT:==
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Seismic, of the 50.54(f) letter. Attached is a file containing the technical review checklist to prepare a response letter to the licensee.
Seismic, of the 50.54(f) letter. Attached is a file containing the technical review checklist to prepare a response letter to the licensee.
The NRC staff reviewed the information provided and, as documented in the enclosed staff checklist, determined that sufficient information was provided to be responsive to this portion of the Enclosure 1 of the 50.54(f) letter. The application of this staff review is limited to the interim ESEP as part of NTTF R2.1: Seismic activities.
The NRC staff reviewed the information provided and, as documented in the enclosed staff checklist, determined that sufficient information was provided to be responsive to this portion of the Enclosure 1 of the 50.54(f) letter. The application of this staff review is limited to the interim ESEP as part of NTTF R2.1: Seismic activities.
This electronic memo constitutes the DSEA concurrence provided that only editorial changes are made to the staff assessment that would not affect the technical conclusions or technical context of the assessment.
This electronic memo constitutes the DSEA concurrence provided that only editorial changes are made to the staff assessment that would not affect the technical conclusions or technical context of the assessment.  
1


This concludes the NRCs efforts associated with TAC NO. MF5238 for the review of the interim ESEP report for the DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1.
2 This concludes the NRCs efforts associated with TAC NO. MF5238 for the review of the interim ESEP report for the DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1.
Docket No: 50-346 CONTACT: Stephanie Devlin-Gill Office of New Reactors 301-415-5301 Copy: Nicholas DiFrancesco, Steve Wyman, Jane Spence, Stephanie Devlin-Gill, Kevin Roche, On Yee, Richie Rivera-Lugo, Malcolm Patterson, Dan Hoang, Tuan Li, David Heeszel, 50.54(f) Seismic Resource; RidsNroDsea Resource 2
Docket No: 50-346 CONTACT: Stephanie Devlin-Gill Office of New Reactors 301-415-5301 Copy: Nicholas DiFrancesco, Steve Wyman, Jane Spence, Stephanie Devlin-Gill, Kevin Roche, On Yee, Richie Rivera-Lugo, Malcolm Patterson, Dan Hoang, Tuan Li, David Heeszel, 50.54(f) Seismic Resource; RidsNroDsea Resource  


Hearing Identifier:     NRR_PMDA Email Number:           2361 Mail Envelope Properties     (d50dda2ec0d541269ced2c6404ae6b91)
Hearing Identifier:
NRR_PMDA Email Number:
2361 Mail Envelope Properties (d50dda2ec0d541269ced2c6404ae6b91)  


==Subject:==
==Subject:==
DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1 - TECHNICAL REVIEW CHECKLIST RELATED TO INTERIM ESEP SUPPORTING IMPLEMENTATION OF NTTF R2.1, SEISMIC (TAC NO. MF5238)
DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1 - TECHNICAL REVIEW CHECKLIST RELATED TO INTERIM ESEP SUPPORTING IMPLEMENTATION OF NTTF R2.1, SEISMIC (TAC NO. MF5238)
Sent Date:               8/28/2015 3:28:16 PM Received Date:           8/28/2015 3:28:33 PM From:                   Jackson, Diane Created By:             Diane.Jackson@nrc.gov Recipients:
Sent Date:
8/28/2015 3:28:16 PM Received Date:
8/28/2015 3:28:33 PM From:
Jackson, Diane Created By:
Diane.Jackson@nrc.gov Recipients:  
"DiFrancesco, Nicholas" <Nicholas.DiFrancesco@nrc.gov>
"DiFrancesco, Nicholas" <Nicholas.DiFrancesco@nrc.gov>
Tracking Status: None "Spence, Jane" <Jane.Spence@nrc.gov>
Tracking Status: None "Spence, Jane" <Jane.Spence@nrc.gov>
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Tracking Status: None "Heeszel, David" <David.Heeszel@nrc.gov>
Tracking Status: None "Heeszel, David" <David.Heeszel@nrc.gov>
Tracking Status: None "Shams, Mohamed" <Mohamed.Shams@nrc.gov>
Tracking Status: None "Shams, Mohamed" <Mohamed.Shams@nrc.gov>
Tracking Status: None Post Office:             R4PWMSMRS03.nrc.gov Files                           Size                     Date & Time MESSAGE                         3170                     8/28/2015 3:28:33 PM Davis Besse R2.1 Seismic ESEP NRC Review.docx                         53210 Options Priority:                       Standard Return Notification:           No Reply Requested:               No
Tracking Status: None Post Office:
R4PWMSMRS03.nrc.gov Files Size Date & Time MESSAGE 3170 8/28/2015 3:28:33 PM Davis Besse R2.1 Seismic ESEP NRC Review.docx 53210 Options Priority:
Standard Return Notification:
No Reply Requested:
No  


Sensitivity:         Normal Expiration Date:
Sensitivity:
Recipients Received:
Normal Expiration Date:
Recipients Received:  


TECHNICAL REVIEW CHECKLIST BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO EXPEDITED SEISMIC EVALUATION PROCESSINTERIM EVALUATION IMPLEMENTING NTTF RECOMMENDATION 2.1 SEISMIC DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1 DOCKET NO.50-346 By letter dated March 12, 2012 (USNRC, 2012a), 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 (10 CFR), Section 50.54(f) Conditions of License (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 with the reevaluated seismic hazards. Requested Information Item (6) in Enclosure 1 to the 50.54(f) letter requests addressees to provide an interim evaluation and actions taken or planned to address a higher seismic hazard relative to the design basis, as appropriate, prior to completion and submission of the seismic risk evaluation.
TECHNICAL REVIEW CHECKLIST BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO EXPEDITED SEISMIC EVALUATION PROCESSINTERIM EVALUATION IMPLEMENTING NTTF RECOMMENDATION 2.1 SEISMIC DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1 DOCKET NO.50-346 By {{letter dated|date=March 12, 2012|text=letter dated March 12, 2012}} (USNRC, 2012a), 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 (10 CFR), Section 50.54(f) Conditions of License (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 with the reevaluated seismic hazards. Requested Information Item (6) in Enclosure 1 to the 50.54(f) letter requests addressees to provide an interim evaluation and actions taken or planned to address a higher seismic hazard relative to the design basis, as appropriate, prior to completion and submission of the seismic risk evaluation.
Additionally, by letter dated April 12, 2013,1 the Electric Power Research Institute (EPRI) staff submitted EPRI TR 3002000704 Seismic Evaluation Guidance: Augmented Approach for the Resolution of Fukushima Near-Term Task Force (NTTF) Recommendation 2.1: Seismic (hereafter referred to as the guidance). The Augmented Approach proposed that licensees would use an Expedited Seismic Evaluation Process (ESEP) to address the interim actions as requested by Information Item (6) in the 50.54(f) letter. The ESEP is a simplified seismic capacity evaluation with a focused scope of certain key installed Mitigating Strategies equipment that is used for core cooling and containment functions to cope with scenarios that involve a loss of all AC power and loss of access to the ultimate heat sink to withstand the Review Level Ground Motion, which is up to two times the safe shutdown earthquake (SSE).
Additionally, by {{letter dated|date=April 12, 2013|text=letter dated April 12, 2013}},1 the Electric Power Research Institute (EPRI) staff submitted EPRI TR 3002000704 Seismic Evaluation Guidance: Augmented Approach for the Resolution of Fukushima Near-Term Task Force (NTTF) Recommendation 2.1: Seismic (hereafter referred to as the guidance). The Augmented Approach proposed that licensees would use an Expedited Seismic Evaluation Process (ESEP) to address the interim actions as requested by Information Item (6) in the 50.54(f) letter. The ESEP is a simplified seismic capacity evaluation with a focused scope of certain key installed Mitigating Strategies equipment that is used for core cooling and containment functions to cope with scenarios that involve a loss of all AC power and loss of access to the ultimate heat sink to withstand the Review Level Ground Motion, which is up to two times the safe shutdown earthquake (SSE).
Due to the expedited and interim nature of the ESEP, the assessment does not include many considerations that are part of a normal risk evaluation.These deferred items, include but are not limited to, structures, piping, non-seismic failures, and operator actions, as well scenarios such as addressing loss of coolant accidents. By letter dated May 7, 2013,2 the NRC staff endorsed the guidance. Central and eastern United States licensees with a reevaluated seismic hazard exceeding the SSE submitted an ESEP interim evaluation in December 2014.
Due to the expedited and interim nature of the ESEP, the assessment does not include many considerations that are part of a normal risk evaluation.These deferred items, include but are not limited to, structures, piping, non-seismic failures, and operator actions, as well scenarios such as addressing loss of coolant accidents. By {{letter dated|date=May 7, 2013|text=letter dated May 7, 2013}},2 the NRC staff endorsed the guidance. Central and eastern United States licensees with a reevaluated seismic hazard exceeding the SSE submitted an ESEP interim evaluation in December 2014.
Consistent with the interim nature of this activity, the staff performed the review of the licensees submittal to assess whether the intent of the guidance was implemented. A multi-disciplined team checked whether the identified methods were consistent with the guidance. A senior expert panel reviewed the teams questions, if any, and checklist for consistency and scope.
Consistent with the interim nature of this activity, the staff performed the review of the licensees submittal to assess whether the intent of the guidance was implemented. A multi-disciplined team checked whether the identified methods were consistent with the guidance. A senior expert panel reviewed the teams questions, if any, and checklist for consistency and scope.
New or updated parameters (e.g., In-Structure Response Spectra, High Confidence of Low Probability of Failure calculations) presented by the licensees were assessed only based on licensee statements for acceptability for the Item (6) response. The application of this staff review is limited to the ESEP interim evaluation as part of NTTF R2.1: Seismic activities.
New or updated parameters (e.g., In-Structure Response Spectra, High Confidence of Low Probability of Failure calculations) presented by the licensees were assessed only based on licensee statements for acceptability for the Item (6) response. The application of this staff review is limited to the ESEP interim evaluation as part of NTTF R2.1: Seismic activities.
1 ADAMS Accession No. ML13102A142 2 ADAMS Accession No. ML13106A331
1 ADAMS Accession No. ML13102A142 2 ADAMS Accession No. ML13106A331  


NTTF Recommendation 2.1 Expedited Seismic Evaluation Process Technical Review Checklist for Davis-Besse Nuclear Power Station, Unit 1 By letter dated December 19, 2014,3FirstEnergy Nuclear Operating Company (FENOC or the licensee) provided an Expedited Seismic Evaluation Process (ESEP) report in a response to , Requested Information Item (6) of the 50.54(f) letter, for the Davis-Besse Nuclear Power Station, Unit 1 (Davis-Besse).
NTTF Recommendation 2.1 Expedited Seismic Evaluation Process Technical Review Checklist for Davis-Besse Nuclear Power Station, Unit 1 2
I.       Review Level Ground Motion The licensee:
By {{letter dated|date=December 19, 2014|text=letter dated December 19, 2014}},3FirstEnergy Nuclear Operating Company (FENOC or the licensee) provided an Expedited Seismic Evaluation Process (ESEP) report in a response to, Requested Information Item (6) of the 50.54(f) letter, for the Davis-Besse Nuclear Power Station, Unit 1 (Davis-Besse).
* described the determination of the review level ground motion                   Yes (RLGM) using one of the means acceptable by the guidance
I.
* identified location of the control point and is consistent with March           Yes 4
Review Level Ground Motion The licensee:
2014 seismic hazard and screening report (SHSR) submittal
described the determination of the review level ground motion (RLGM) using one of the means acceptable by the guidance identified location of the control point and is consistent with March 2014 seismic hazard and screening report (SHSR)4 submittal compared the site ground motion response spectra used to select the ESEP RLGM to the SSE.
* compared the site ground motion response spectra used to select                 Yes the ESEP RLGM to the SSE.
Yes Yes Yes Davis-Besse used the GMRS developed for use in the SPRA.
Davis-Besse used the GMRS developed for use in the SPRA.
Notes from the Reviewer:
Notes from the Reviewer:
* The licensee used a new GMRS rather than its seismic hazard reevaluation GMRS documented in its March 2014 SHSR, which was found acceptable for use in Recommendation 2.1 seismic activities by the staff. The licensee used the same velocity models as in the hazard report but reduced the damping values in the interval between 100 and 500 ft below the control point. The staff notes that the GMRS is less than the SSE over some ranges. Because the new GMRS is similar to and bounds the SHSR GMRS at frequencies above ~3 Hz, the staff judged that this GMRS is acceptable for this interim evaluation.
The licensee used a new GMRS rather than its seismic hazard reevaluation GMRS documented in its March 2014 SHSR, which was found acceptable for use in Recommendation 2.1 seismic activities by the staff. The licensee used the same velocity models as in the hazard report but reduced the damping values in the interval between 100 and 500 ft below the control point. The staff notes that the GMRS is less than the SSE over some ranges. Because the new GMRS is similar to and bounds the SHSR GMRS at frequencies above ~3 Hz, the staff judged that this GMRS is acceptable for this interim evaluation.
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 licensees RLGM meets the intent of the guidance                           Yes
the licensees RLGM meets the intent of the guidance the RLGM is reasonable for use in the interim evaluation Yes Yes II.
* the RLGM is reasonable for use in the interim evaluation                       Yes II.     Selection of the Success Path The licensee:
Selection of the Success Path The licensee:
* described the success path                                                       Yes
described the success path described normal and desired state of the equipment for the success path ensured that the success path is consistent with the plants overall mitigating strategies approach or provided a justification for an alternate path stated that the selection process was in accordance with the guidance or meets the intent of the guidance used installed FLEX Phase 1 equipment as part of the success path included FLEX Phase 2 and/or 3 connections considered installed FLEX Phase 2 and/or 3equipment Yes Yes Yes Yes Yes Yes Yes 3ADAMS Accession No. ML14253A058 4ADAMS Accession No ML14092A203  
* described normal and desired state of the equipment for the success             Yes path
* ensured that the success path is consistent with the plants overall             Yes mitigating strategies approach or provided a justification for an alternate path
* stated that the selection process was in accordance with the                     Yes guidance or meets the intent of the guidance
* used installed FLEX Phase 1 equipment as part of the success path               Yes
* included FLEX Phase 2 and/or 3 connections
* considered installed FLEX Phase 2 and/or 3equipment Yes Yes 3ADAMS Accession No. ML14253A058 4ADAMS Accession No ML14092A203 2


NTTF Recommendation 2.1 Expedited Seismic Evaluation Process Technical Review Checklist for Davis-Besse Nuclear Power Station, Unit 1 Notes from the Reviewer:
NTTF Recommendation 2.1 Expedited Seismic Evaluation Process Technical Review Checklist for Davis-Besse Nuclear Power Station, Unit 1 3
Notes from the Reviewer:
: 1. This licensee relies on a diesel-driven emergency feedwater (EFW) pump for Phase 1, and it appears the licensee included a diesel fuel oil day tank and storage tank on the ESEL.
: 1. This licensee relies on a diesel-driven emergency feedwater (EFW) pump for Phase 1, and it appears the licensee included a diesel fuel oil day tank and storage tank on the ESEL.
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 that:
The NRC staff concludes that:
* the selected success path is reasonable for use in the interim                     Yes evaluation
the selected success path is reasonable for use in the interim evaluation the licensee considered installed Phase 2 and 3 connections or equipment in the interim evaluation.
* the licensee considered installed Phase 2 and 3 connections or                     Yes equipment in the interim evaluation.
Yes Yes III.
III. Selection of the Equipment List The licensee:
Selection of the Equipment List The licensee:
* developed and provided the ESEL by applying the ESEP                             Yes
developed and provided the ESEL by applying the ESEP identified equipment considering the following functions:
* identified equipment considering the following functions:
o Core cooling (with focus on Mode 1) function o Available, sustainable water source o Containment function and integrity Yes Yes Yes Yes Notes from the Reviewer:None Deviation(s) or Deficiency(ies), and Resolution:
o Core cooling (with focus on Mode 1) function                           Yes o Available, sustainable water source                                   Yes o Containment function and integrity                                     Yes Notes from the Reviewer:None Deviation(s) or Deficiency(ies), and Resolution:
No deviations or deficiencies were identified.
For PWR Plants ONLY The licensee included indicators / instrumentation for the following functions: level, pressure, temperature, that would be indicative of (but not          Yes explicitly identified to specific instruments): water level of the steam generator (SG), pressure of SG, containment, and reactor coolant system (RCS); and temperature of the RCS.
For BWR Plants ONLY The licenseeconsidered indicators for the following functions:
level, pressure, temperature that would be indicative of (but not explicitly          N/A identified to specific instruments): Temperature of suppression pool, RCS, containment); Pressure of suppression pool, RCS, and drywell; water level of the suppression pool.
Notes from the Reviewer:None Deviation(s) or Deficiency(ies), and Resolution:
No deviations or deficiencies were identified.
No deviations or deficiencies were identified.
3
For PWR Plants ONLY The licensee included indicators / instrumentation for the following functions: level, pressure, temperature, that would be indicative of (but not explicitly identified to specific instruments): water level of the steam generator (SG), pressure of SG, containment, and reactor coolant system (RCS); and temperature of the RCS.
Yes For BWR Plants ONLY The licenseeconsidered indicators for the following functions:
level, pressure, temperature that would be indicative of (but not explicitly identified to specific instruments): Temperature of suppression pool, RCS, containment); Pressure of suppression pool, RCS, and drywell; water level of the suppression pool.
N/A Notes from the Reviewer:None Deviation(s) or Deficiency(ies), and Resolution:
No deviations or deficiencies were identified.


NTTF Recommendation 2.1 Expedited Seismic Evaluation Process Technical Review Checklist for Davis-Besse Nuclear Power Station, Unit 1 Through a sampling of the ESEP key components, the NRC staff concludes that:
NTTF Recommendation 2.1 Expedited Seismic Evaluation Process Technical Review Checklist for Davis-Besse Nuclear Power Station, Unit 1 4
* the licensees process to develop the ESEL meets the intent of the             Yes guidance for the interim evaluation
Through a sampling of the ESEP key components, the NRC staff concludes that:
* the desired equipment state for the success path were identified               Yes
the licensees process to develop the ESEL meets the intent of the guidance for the interim evaluation the desired equipment state for the success path were identified the licensee considered the support equipment for the ESEL both front-line and support systems appeared to be included in the ESEL as evidenced by inclusion of SSCs on the success path and of support systems (e.g., batteries, motor control centers, inverters).
* the licensee considered the support equipment for the ESEL                     Yes
Yes Yes Yes Yes IV.
* both front-line and support systems appeared to be included in the ESEL as evidenced by inclusion of SSCs on the success path and of support systems (e.g., batteries, motor control centers,                 Yes inverters).
Walkdown Approach The licensee:
IV.     Walkdown Approach The licensee:
described the walkdown screening approach, including walkbys and walkdowns performed exclusively for the ESEP, in accordance with the guidance credited previous walkdown results, including a description of current action(s) to verify the present equipment condition and/or configuration (e.g., walk-bys), in accordance with the guidance stated that the walkdown was performed by seismically trained personnel Yes Yes Yes Notes from the Reviewer:
* described the walkdown screening approach, including walkbys and                   Yes walkdowns performed exclusively for the ESEP, in accordance with the guidance
* credited previous walkdown results, including a description of current             Yes action(s) to verify the present equipment condition and/or configuration (e.g., walk-bys), in accordance with the guidance
* stated that the walkdown was performed by seismically trained                     Yes personnel Notes from the Reviewer:
: 1. The staffrequested clarifcationregarding the trainingof the walkdown engineers. In their response from July 14, 2015 (ML15212A713), the licensee provided additional information on all individuals who performed the plant walkdowns have successfully completed the SQUG Walkdown Screening and Seismic Evaluation Training Course or equivalent training. This adequately responded to the staffs concern and the licensee demonstrated that it met the intent of the guidance.
: 1. The staffrequested clarifcationregarding the trainingof the walkdown engineers. In their response from July 14, 2015 (ML15212A713), the licensee provided additional information on all individuals who performed the plant walkdowns have successfully completed the SQUG Walkdown Screening and Seismic Evaluation Training Course or equivalent training. This adequately responded to the staffs concern and the licensee demonstrated that it met the intent of the guidance.
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 licensee:
The licensee:
* described, as needed,adverse material condition of the equipment                   Yes (e.g., material degradation)
described, as needed,adverse material condition of the equipment (e.g., material degradation) credited previous walkdown results, included a description of current action(s) to verify the present equipment condition (e.g., walk-bys),
* credited previous walkdown results, included a description of current             Yes action(s) to verify the present equipment condition (e.g., walk-bys),
meeting the intent of the guidance Yes Yes The licensee:
meeting the intent of the guidance The licensee:
described the conditions of structural items considered for the interim evaluation, including:
* described the conditions of structural items considered for the interim evaluation, including:
o spatial interactions (i.e., interaction between block walls and other items/components) o anchorage o piping connected to tanks (i.e., differential movement between pipes and tanks at connections)
o spatial interactions (i.e., interaction between block walls and           Yes other items/components) o anchorage                                                                 Yes o piping connected to tanks (i.e., differential movement                   Yes between pipes and tanks at connections)
Yes Yes Yes Notes from the Reviewer:None Deviation(s) or Deficiency(ies), and Resolution:
Notes from the Reviewer:None Deviation(s) or Deficiency(ies), and Resolution:
No deviations or deficiencies were identified.  
No deviations or deficiencies were identified.
4


NTTF Recommendation 2.1 Expedited Seismic Evaluation Process Technical Review Checklist for Davis-Besse Nuclear Power Station, Unit 1 The licensee reported deviations for Davis-Besse.                                         No If deviations were identified, there is a discussion of how the deficiencies             N/A were or will be addressed in the ESEP submittal report.
NTTF Recommendation 2.1 Expedited Seismic Evaluation Process Technical Review Checklist for Davis-Besse Nuclear Power Station, Unit 1 5
The NRC staff concludes that:
The licensee reported deviations for Davis-Besse.
* the licensee described the performed walkdown approach, including                   Yes any credited previous efforts (e.g.,Individual Plant Examination of External Events(IPEEE)) consistent with the guidance Yes
If deviations were identified, there is a discussion of how the deficiencies were or will be addressed in the ESEP submittal report.
* the licensee addressed identified deviations consistent with the guidance, if any V.       Capacity Screening Approach and HCLPF Calculation Results The licensee:
No N/A The NRC staff concludes that:
* described the capacity screening process for the ESEL items,                       Yes consistent with the guidance (e.g., use of EPRI NP-6041 screening table).
the licensee described the performed walkdown approach, including any credited previous efforts (e.g.,Individual Plant Examination of External Events(IPEEE)) consistent with the guidance the licensee addressed identified deviations consistent with the guidance, if any Yes Yes V.
* presented the results of the screened-out ESEL items in the ESEP                   Yes report
Capacity Screening Approach and HCLPF Calculation Results The licensee:
* described the development of in-structure response spectra (ISRS)                   N/A based on scaling                                                                 Yes
described the capacity screening process for the ESEL items, consistent with the guidance (e.g., use of EPRI NP-6041 screening table).
* described the development of ISRS based on new analysis consistent with the guidance                                                     Yes
presented the results of the screened-out ESEL items in the ESEP report described the development of in-structure response spectra (ISRS) based on scaling described the development of ISRS based on new analysis consistent with the guidance described the method for estimating HCLPF capacity of screened-in ESEL items, including both structural and functional failure modes consistent with the guidance:
* described the method for estimating HCLPF capacity of screened-in ESEL items, including both structural and functional failure modes consistent with the guidance:                                                     Yes o use of Conservative Deterministic Failure Margin (CDFM)                     No o use of fragility analysis (FA)                                             Yes o use of experience data or generic information                             N/A
o use of Conservative Deterministic Failure Margin (CDFM) o use of fragility analysis (FA) o use of experience data or generic information credited IPEEE spectral shape for HCLPF capacity estimates is similar to or envelopes the RLGM, and anchored at the same control point presented the results of HCLPF capacities including associated failure modes for screened-in ESEL items reviewed the ESEL items with the lowest HCLPF values to ensure that their capacities are equal or greater than the RLGM Yes Yes N/A Yes Yes Yes No Yes N/A Yes Yes Notes from the Reviewer:
* credited IPEEE spectral shape for HCLPF capacity estimates is similar to or envelopes the RLGM, and anchored at the same control point                                                                             Yes
* presented the results of HCLPF capacities including associated failure modes for screened-in ESEL items                                         Yes
* reviewed the ESEL items with the lowest HCLPF values to ensure that their capacities are equal or greater than the RLGM Notes from the Reviewer:
: 1. As allowed by guidance, the licensee did not use a scaled ISRS. The licensee calculated an ISRS based on a new GMRS for its upcoming seismic risk evaluation,as noted in Section I of this checklist. The ISRS is judged by the staff to be acceptable for this interim evaluation only based on the staffs review of ESEP submittal and because the new GMRS is similar to and bounds the SHSR GMRS.
: 1. As allowed by guidance, the licensee did not use a scaled ISRS. The licensee calculated an ISRS based on a new GMRS for its upcoming seismic risk evaluation,as noted in Section I of this checklist. The ISRS is judged by the staff to be acceptable for this interim evaluation only based on the staffs review of ESEP submittal and because the new GMRS is similar to and bounds the SHSR GMRS.
: 2. The staffrequested confirmation that the HCLPF table included in the report as Attachment B represents those items from Attachment A that were screened in, and to also provide a roadmap between both attachment tables. In their response from July 14, 2015 (ML15212A713), the licensee confirmed this information and provided an updated version of Attachment B that identifies the ESEL item number to serve as a roadmap to Attachment A in the ESEP report. This response satisfies the staffs request for the purposes of this interim evaluation.
: 2. The staffrequested confirmation that the HCLPF table included in the report as Attachment B represents those items from Attachment A that were screened in, and to also provide a roadmap between both attachment tables. In their response from July 14, 2015 (ML15212A713), the licensee confirmed this information and provided an updated version of Attachment B that identifies the ESEL item number to serve as a roadmap to Attachment A in the ESEP report. This response satisfies the staffs request for the purposes of this interim evaluation.
: 3. The staffrequested clarfication of the approach(es) applied to evaluate the seismic 5
: 3. The staffrequested clarfication of the approach(es) applied to evaluate the seismic  


NTTF Recommendation 2.1 Expedited Seismic Evaluation Process Technical Review Checklist for Davis-Besse Nuclear Power Station, Unit 1 capacity of components physically located on panels and/or cabinets, known as rule-of-the-box. In their response from July 14, 2015 (ML15212A713), the licenseeexplained that indicators and recorders are listed on the ESEL as distinct items, but their seismic evaluation is based on the evaluation of the parent component (ESEP Section 3.1.5),
NTTF Recommendation 2.1 Expedited Seismic Evaluation Process Technical Review Checklist for Davis-Besse Nuclear Power Station, Unit 1 6
capacity of components physically located on panels and/or cabinets, known as rule-of-the-box. In their response from July 14, 2015 (ML15212A713), the licenseeexplained that indicators and recorders are listed on the ESEL as distinct items, but their seismic evaluation is based on the evaluation of the parent component (ESEP Section 3.1.5),
and that when an ESEL item is identified to be mounted on a parent component, the HCLPF of the parent component is assigned to the item. The licensee also stated that all HCLPF calculations are based on the guidance provided in EPRI TR-1002988 and TR-1019200. The staffjudgedthe response from the licensee to be acceptable for the purposes of this interim evaluation.
and that when an ESEL item is identified to be mounted on a parent component, the HCLPF of the parent component is assigned to the item. The licensee also stated that all HCLPF calculations are based on the guidance provided in EPRI TR-1002988 and TR-1019200. The staffjudgedthe response from the licensee to be acceptable for the purposes of this interim evaluation.
: 4. The staff requested clarification regarding the soil-structure-interaction (SSI) analysis. In the response dated July 14, 2015 (ML15212A713), the licensee described their use of the peak shifting approach recommended guidelines from EPRI 1019200 and NP-6041.
: 4. The staff requested clarification regarding the soil-structure-interaction (SSI) analysis. In the response dated July 14, 2015 (ML15212A713), the licensee described their use of the peak shifting approach recommended guidelines from EPRI 1019200 and NP-6041.
Line 156: Line 156:
No deviations or deficiencies were identified.
No deviations or deficiencies were identified.
The NRC staff concludes that:
The NRC staff concludes that:
* the licensee described the implementation of the capacity screening                   Yes process consistent with the intent of the guidance
the licensee described the implementation of the capacity screening process consistent with the intent of the guidance the licensee presented capacity screening and calculation results, as appropriate, in the ESEP report the method used to develop the ISRS is consistent with guidance for use in the ESEP for HCLPF calculations, the licensee used HCLPF calculation methods as endorsed in the guidance no anomalies were noted in the reported HCLPF Yes Yes Yes Yes Yes VI.
* the licensee presented capacity screening and calculation results, as                 Yes appropriate, in the ESEP report
Inaccessible Items The licensee:
* the method used to develop the ISRS is consistent with guidance for                   Yes use in the ESEP
provided a list of inaccessible items provided a schedule of the planned walkdown and evaluation for all inaccessible items provided Regulatory Commitment to complete walkdowns.
* for HCLPF calculations, the licensee used HCLPF calculation                           Yes methods as endorsed in the guidance
Yes N/A N/A Davis-Besse will provide results or complete walkdown by: N/A N/A Notes from the Reviewer:
* no anomalies were noted in the reported HCLPF                                         Yes VI.     Inaccessible Items The licensee:
* provided a list of inaccessible items                                               Yes
* provided a schedule of the planned walkdown and evaluation for all                 N/A inaccessible items
* provided Regulatory Commitment to complete walkdowns.                               N/A Davis-Besse will provide results or complete walkdown by: N/A                           N/A Notes from the Reviewer:
: 1. The licensee identified a total of 14 inaccessible items from the ESEL (ESEP report Table 7-1), identified the reason for the inaccessibility of each item, and the criteria used to confirm the installed condition and its fragility. Methods such as photographs from the recent flooding walkdowns, review of plant drawings, and equivalency with other accessible equipment were used to determine the seismic fragility of these items. This to be acceptable for the purposes of this interim evaluation.
: 1. The licensee identified a total of 14 inaccessible items from the ESEL (ESEP report Table 7-1), identified the reason for the inaccessibility of each item, and the criteria used to confirm the installed condition and its fragility. Methods such as photographs from the recent flooding walkdowns, review of plant drawings, and equivalency with other accessible equipment were used to determine the seismic fragility of these items. This to be acceptable for the purposes of this interim evaluation.
Deviation(s) or Deficiency(ies), and Resolution:
Deviation(s) or Deficiency(ies), and Resolution:  
6


NTTF Recommendation 2.1 Expedited Seismic Evaluation Process Technical Review Checklist for Davis-Besse Nuclear Power Station, Unit 1 No deviations or deficiencies were identified.
NTTF Recommendation 2.1 Expedited Seismic Evaluation Process Technical Review Checklist for Davis-Besse Nuclear Power Station, Unit 1 7
No deviations or deficiencies were identified.
The NRC staff concludes that the licensee:
The NRC staff concludes that the licensee:
* listed inaccessible items                                                         Yes
listed inaccessible items committed to provide the results (e.g. walkdowns, walkbys, etc.) of the remaining inaccessible items consistent with the guidance substitutions, if needed, were appropriately justified Yes N/A Yes VII.
* committed to provide the results (e.g. walkdowns, walkbys, etc.) of               N/A the remaining inaccessible items consistent with the guidance
Modifications to Plant Equipment The licensee:
* substitutions, if needed, were appropriately justified                             Yes VII. Modifications to Plant Equipment The licensee:
identified modifications for ESEL items necessary to achieve HCLPF values that bound the RLGM (excluding mitigative strategies equipment (FLEX)), as specified in the guidance provided a schedule to implement such modifications (if any),
* identified modifications for ESEL items necessary to achieve HCLPF                 N/A values that bound the RLGM (excluding mitigative strategies equipment (FLEX)), as specified in the guidance
consistent with the intent of the guidance provided Regulatory Commitment to complete modifications provided Regulatory Commitment to report completion of modifications.
* provided a schedule to implement such modifications (if any),                       N/A consistent with the intent of the guidance
N/A N/A N/A N/A Davis-Besse will:
* provided Regulatory Commitment to complete modifications                           N/A
complete modifications by:N/A report completion of modifications by:N/A Notes from the Reviewer:
* provided Regulatory Commitment to report completion of                             N/A modifications.
Davis-Besse will:
* complete modifications by:N/A
* report completion of modifications by:N/A Notes from the Reviewer:
: 1. The licensee does not plan to perform any modifications since all the components in the ESEL have a HCLPF greater than the RLGM (0.20g).
: 1. The licensee does not plan to perform any modifications since all the components in the ESEL have a HCLPF greater than the RLGM (0.20g).
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 that the licensee:
The NRC staff concludes that the licensee:
* identified plant modifications necessary to achieve the target seismic capacity                                                                         N/A
identified plant modifications necessary to achieve the target seismic capacity provided a schedule to implement the modifications (if any) consistent with the guidance N/A N/A VIII.  
* provided a schedule to implement the modifications (if any) consistent with the guidance                                                     N/A VIII.  
 
== Conclusions:==


The NRC staff assessed the licensees implementation of the ESEP guidance. Due to the interim applicability of the ESEP evaluations, use of the information for another application would require a separate NRC review and approval. Based on its review, the NRC staff concludes that the licensees implementation of the interim evaluation meets the intent of the guidance. The staff concludes that, through the implementation of the ESEP guidance, the licensee identified and evaluated the seismic capacity of certain key installed Mitigating Strategies equipment that is used for core cooling and containment functions to cope with scenarios that involve a loss of all AC power and loss of access to the ultimate heat sink to withstand a seismic event up to the Review Level Ground Motion (RLGM)and thus, provides additional assurance while the plant seismic risk evaluation is being conducted. In the case of Davis-Besse, in accordance as an option within the guidance and noted above, a GMRS was used as the RLGM, which is less than the SSE in some ranges. The application of this staff review is limited to the ESEP interim evaluation as part of NTTF R2.1: Seismic activities. As noted in the review checklist, the staff did not identify deviations or exceptions were taken from the guidance. The licensee did not identify any modifications of equipment was required from the ESEP.
==
7
Conclusions:==
The NRC staff assessed the licensees implementation of the ESEP guidance. Due to the interim applicability of the ESEP evaluations, use of the information for another application would require a separate NRC review and approval. Based on its review, the NRC staff concludes that the licensees implementation of the interim evaluation meets the intent of the guidance. The staff concludes that, through the implementation of the ESEP guidance, the licensee identified and evaluated the seismic capacity of certain key installed Mitigating Strategies equipment that is used for core cooling and containment functions to cope with scenarios that involve a loss of all AC power and loss of access to the ultimate heat sink to withstand a seismic event up to the Review Level Ground Motion (RLGM)and thus, provides additional assurance while the plant seismic risk evaluation is being conducted. In the case of Davis-Besse, in accordance as an option within the guidance and noted above, a GMRS was used as the RLGM, which is less than the SSE in some ranges. The application of this staff review is limited to the ESEP interim evaluation as part of NTTF R2.1: Seismic activities. As noted in the review checklist, the staff did not identify deviations or exceptions were taken from the guidance. The licensee did not identify any modifications of equipment was required from the ESEP.  


NTTF Recommendation 2.1 Expedited Seismic Evaluation Process Technical Review Checklist for Davis-Besse Nuclear Power Station, Unit 1 In summary, the licensee, by implementing the ESEP interim evaluation, has demonstrated additional assurance which supports continued plant safety while the longer-term seismic evaluation is completed to support regulatory decision making. The NRC staff concludes that the licensee responded appropriately to Enclosure 1, Item (6) of the 50.54(f) letter, dated March 12, 2012, for Davis-Besse Nuclear Power Station, Unit 1.
NTTF Recommendation 2.1 Expedited Seismic Evaluation Process Technical Review Checklist for Davis-Besse Nuclear Power Station, Unit 1 8
Principal Contributors: Malcolm Patterson, Dan Hoang, Tuan Le, David Heeszel, On Yee, Richard Rivera-Lugo, Richard Morante, (NRC Consultant) 8}}
In summary, the licensee, by implementing the ESEP interim evaluation, has demonstrated additional assurance which supports continued plant safety while the longer-term seismic evaluation is completed to support regulatory decision making. The NRC staff concludes that the licensee responded appropriately to Enclosure 1, Item (6) of the 50.54(f) letter, dated March 12, 2012, for Davis-Besse Nuclear Power Station, Unit 1.
Principal Contributors: Malcolm Patterson, Dan Hoang, Tuan Le, David Heeszel, On Yee, Richard Rivera-Lugo, Richard Morante, (NRC Consultant)}}

Latest revision as of 08:44, 10 January 2025

NRR E-mail Capture - DAVIS-BESSE Nuclear Power Station, Unit 1 - Technical Review Checklist Related to Interim ESEP Supporting Implementation of NTTF R2.1, Seismic
ML15245A816
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 08/28/2015
From: Diane Jackson
Office of New Reactors
To: Mohamed Shams
Japan Lessons-Learned Division
References
TAC MF5238
Download: ML15245A816 (12)


Text

1 NRR-PMDAPEm Resource From:

Jackson, Diane Sent:

Friday, August 28, 2015 3:28 PM To:

Shams, Mohamed Cc:

DiFrancesco, Nicholas; Spence, Jane; Devlin-Gill, Stephanie; Roche, Kevin; Yee, On; 50.54f_Seismic Resource; RidsNroDsea Resource; Wyman, Stephen; Rivera-Lugo, Richard; Patterson, Malcolm; Hoang, Dan; Le, Tuan; Heeszel, David

Subject:

DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1 - TECHNICAL REVIEW CHECKLIST RELATED TO INTERIM ESEP SUPPORTING IMPLEMENTATION OF NTTF R2.1, SEISMIC (TAC NO. MF5238)

Attachments:

Davis Besse R2.1 Seismic ESEP NRC Review.docx August 28, 2015 MEMORANDUM TO: Mohamed K. Shams, Chief Hazards Management Branch (JHMB)

Japan Lessons-Learned Division Office of Nuclear Reactor Regulation FROM: Diane T. Jackson, Chief Geosciences and Geotechnical Engineering Branch 2 (RGS2)

Division of Site Safety and Environmental Analysis Office of New Reactors

SUBJECT:

DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1 - TECHNICAL REVIEW CHECKLIST RELATED TO INTERIM EXPEDITED SEISMIC EVALUATION PROCESS SUPPORTING IMPLEMENTATION OF NTTF RECOMMENDATION 2.1, SEISMIC, RELATED TO THE FUKUSHIMA DAI-ICHI NUCLEAR POWER PLANT ACCIDENT (TAC NO. MF5238)

The NRC technical staff working through the Geosciences and Geotechnical Engineering Branches 1 and 2 (RGS1 and RGS2) completed the Technical Review Checklist of the DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1 response to Enclosure 1, Item (6) of the March 12, 2012, request for information letter issued per Title 10 of the Code of Federal Regulations, Subpart 50.54(f), to power reactor licensees and holders of construction permits requesting addressees to provide further information to support the NRC staffs evaluation of regulatory actions to be taken in response to Fukushima Near-Term Task Force (NTTF)

Recommendation 2.1: Seismic which implements lessons learned from Japans March 11, 2011, Great Thoku Earthquake and subsequent tsunami. This addresses the staff review of the interim Expedited Seismic Evaluation Process (ESEP) report in response to Requested Item (6) of Enclosure 1, Recommendation 2.1:

Seismic, of the 50.54(f) letter. Attached is a file containing the technical review checklist to prepare a response letter to the licensee.

The NRC staff reviewed the information provided and, as documented in the enclosed staff checklist, determined that sufficient information was provided to be responsive to this portion of the Enclosure 1 of the 50.54(f) letter. The application of this staff review is limited to the interim ESEP as part of NTTF R2.1: Seismic activities.

This electronic memo constitutes the DSEA concurrence provided that only editorial changes are made to the staff assessment that would not affect the technical conclusions or technical context of the assessment.

2 This concludes the NRCs efforts associated with TAC NO. MF5238 for the review of the interim ESEP report for the DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1.

Docket No: 50-346 CONTACT: Stephanie Devlin-Gill Office of New Reactors 301-415-5301 Copy: Nicholas DiFrancesco, Steve Wyman, Jane Spence, Stephanie Devlin-Gill, Kevin Roche, On Yee, Richie Rivera-Lugo, Malcolm Patterson, Dan Hoang, Tuan Li, David Heeszel, 50.54(f) Seismic Resource; RidsNroDsea Resource

Hearing Identifier:

NRR_PMDA Email Number:

2361 Mail Envelope Properties (d50dda2ec0d541269ced2c6404ae6b91)

Subject:

DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1 - TECHNICAL REVIEW CHECKLIST RELATED TO INTERIM ESEP SUPPORTING IMPLEMENTATION OF NTTF R2.1, SEISMIC (TAC NO. MF5238)

Sent Date:

8/28/2015 3:28:16 PM Received Date:

8/28/2015 3:28:33 PM From:

Jackson, Diane Created By:

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"DiFrancesco, Nicholas" <Nicholas.DiFrancesco@nrc.gov>

Tracking Status: None "Spence, Jane" <Jane.Spence@nrc.gov>

Tracking Status: None "Devlin-Gill, Stephanie" <Stephanie.Devlin-Gill@nrc.gov>

Tracking Status: None "Roche, Kevin" <Kevin.Roche@nrc.gov>

Tracking Status: None "Yee, On" <On.Yee@nrc.gov>

Tracking Status: None "50.54f_Seismic Resource" <50.54f_Seismic.Resource@nrc.gov>

Tracking Status: None "RidsNroDsea Resource" <RidsNroDsea.Resource@nrc.gov>

Tracking Status: None "Wyman, Stephen" <Stephen.Wyman@nrc.gov>

Tracking Status: None "Rivera-Lugo, Richard" <Richard.Rivera-Lugo@nrc.gov>

Tracking Status: None "Patterson, Malcolm" <Malcolm.Patterson@nrc.gov>

Tracking Status: None "Hoang, Dan" <Dan.Hoang@nrc.gov>

Tracking Status: None "Le, Tuan" <Tuan.Le@nrc.gov>

Tracking Status: None "Heeszel, David" <David.Heeszel@nrc.gov>

Tracking Status: None "Shams, Mohamed" <Mohamed.Shams@nrc.gov>

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R4PWMSMRS03.nrc.gov Files Size Date & Time MESSAGE 3170 8/28/2015 3:28:33 PM Davis Besse R2.1 Seismic ESEP NRC Review.docx 53210 Options Priority:

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TECHNICAL REVIEW CHECKLIST BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO EXPEDITED SEISMIC EVALUATION PROCESSINTERIM EVALUATION IMPLEMENTING NTTF RECOMMENDATION 2.1 SEISMIC DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1 DOCKET NO.50-346 By letter dated March 12, 2012 (USNRC, 2012a), 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 (10 CFR), Section 50.54(f) Conditions of License (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 with the reevaluated seismic hazards. Requested Information Item (6) in Enclosure 1 to the 50.54(f) letter requests addressees to provide an interim evaluation and actions taken or planned to address a higher seismic hazard relative to the design basis, as appropriate, prior to completion and submission of the seismic risk evaluation.

Additionally, by letter dated April 12, 2013,1 the Electric Power Research Institute (EPRI) staff submitted EPRI TR 3002000704 Seismic Evaluation Guidance: Augmented Approach for the Resolution of Fukushima Near-Term Task Force (NTTF) Recommendation 2.1: Seismic (hereafter referred to as the guidance). The Augmented Approach proposed that licensees would use an Expedited Seismic Evaluation Process (ESEP) to address the interim actions as requested by Information Item (6) in the 50.54(f) letter. The ESEP is a simplified seismic capacity evaluation with a focused scope of certain key installed Mitigating Strategies equipment that is used for core cooling and containment functions to cope with scenarios that involve a loss of all AC power and loss of access to the ultimate heat sink to withstand the Review Level Ground Motion, which is up to two times the safe shutdown earthquake (SSE).

Due to the expedited and interim nature of the ESEP, the assessment does not include many considerations that are part of a normal risk evaluation.These deferred items, include but are not limited to, structures, piping, non-seismic failures, and operator actions, as well scenarios such as addressing loss of coolant accidents. By letter dated May 7, 2013,2 the NRC staff endorsed the guidance. Central and eastern United States licensees with a reevaluated seismic hazard exceeding the SSE submitted an ESEP interim evaluation in December 2014.

Consistent with the interim nature of this activity, the staff performed the review of the licensees submittal to assess whether the intent of the guidance was implemented. A multi-disciplined team checked whether the identified methods were consistent with the guidance. A senior expert panel reviewed the teams questions, if any, and checklist for consistency and scope.

New or updated parameters (e.g., In-Structure Response Spectra, High Confidence of Low Probability of Failure calculations) presented by the licensees were assessed only based on licensee statements for acceptability for the Item (6) response. The application of this staff review is limited to the ESEP interim evaluation as part of NTTF R2.1: Seismic activities.

1 ADAMS Accession No. ML13102A142 2 ADAMS Accession No. ML13106A331

NTTF Recommendation 2.1 Expedited Seismic Evaluation Process Technical Review Checklist for Davis-Besse Nuclear Power Station, Unit 1 2

By letter dated December 19, 2014,3FirstEnergy Nuclear Operating Company (FENOC or the licensee) provided an Expedited Seismic Evaluation Process (ESEP) report in a response to, Requested Information Item (6) of the 50.54(f) letter, for the Davis-Besse Nuclear Power Station, Unit 1 (Davis-Besse).

I.

Review Level Ground Motion The licensee:

described the determination of the review level ground motion (RLGM) using one of the means acceptable by the guidance identified location of the control point and is consistent with March 2014 seismic hazard and screening report (SHSR)4 submittal compared the site ground motion response spectra used to select the ESEP RLGM to the SSE.

Yes Yes Yes Davis-Besse used the GMRS developed for use in the SPRA.

Notes from the Reviewer:

The licensee used a new GMRS rather than its seismic hazard reevaluation GMRS documented in its March 2014 SHSR, which was found acceptable for use in Recommendation 2.1 seismic activities by the staff. The licensee used the same velocity models as in the hazard report but reduced the damping values in the interval between 100 and 500 ft below the control point. The staff notes that the GMRS is less than the SSE over some ranges. Because the new GMRS is similar to and bounds the SHSR GMRS at frequencies above ~3 Hz, the staff judged that this GMRS is acceptable for this interim evaluation.

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

No deviations or deficiencies were identified.

The NRC staff concludes:

the licensees RLGM meets the intent of the guidance the RLGM is reasonable for use in the interim evaluation Yes Yes II.

Selection of the Success Path The licensee:

described the success path described normal and desired state of the equipment for the success path ensured that the success path is consistent with the plants overall mitigating strategies approach or provided a justification for an alternate path stated that the selection process was in accordance with the guidance or meets the intent of the guidance used installed FLEX Phase 1 equipment as part of the success path included FLEX Phase 2 and/or 3 connections considered installed FLEX Phase 2 and/or 3equipment Yes Yes Yes Yes Yes Yes Yes 3ADAMS Accession No. ML14253A058 4ADAMS Accession No ML14092A203

NTTF Recommendation 2.1 Expedited Seismic Evaluation Process Technical Review Checklist for Davis-Besse Nuclear Power Station, Unit 1 3

Notes from the Reviewer:

1. This licensee relies on a diesel-driven emergency feedwater (EFW) pump for Phase 1, and it appears the licensee included a diesel fuel oil day tank and storage tank on the ESEL.

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

No deviations or deficiencies were identified.

The NRC staff concludes that:

the selected success path is reasonable for use in the interim evaluation the licensee considered installed Phase 2 and 3 connections or equipment in the interim evaluation.

Yes Yes III.

Selection of the Equipment List The licensee:

developed and provided the ESEL by applying the ESEP identified equipment considering the following functions:

o Core cooling (with focus on Mode 1) function o Available, sustainable water source o Containment function and integrity Yes Yes Yes Yes Notes from the Reviewer:None Deviation(s) or Deficiency(ies), and Resolution:

No deviations or deficiencies were identified.

For PWR Plants ONLY The licensee included indicators / instrumentation for the following functions: level, pressure, temperature, that would be indicative of (but not explicitly identified to specific instruments): water level of the steam generator (SG), pressure of SG, containment, and reactor coolant system (RCS); and temperature of the RCS.

Yes For BWR Plants ONLY The licenseeconsidered indicators for the following functions:

level, pressure, temperature that would be indicative of (but not explicitly identified to specific instruments): Temperature of suppression pool, RCS, containment); Pressure of suppression pool, RCS, and drywell; water level of the suppression pool.

N/A Notes from the Reviewer:None Deviation(s) or Deficiency(ies), and Resolution:

No deviations or deficiencies were identified.

NTTF Recommendation 2.1 Expedited Seismic Evaluation Process Technical Review Checklist for Davis-Besse Nuclear Power Station, Unit 1 4

Through a sampling of the ESEP key components, the NRC staff concludes that:

the licensees process to develop the ESEL meets the intent of the guidance for the interim evaluation the desired equipment state for the success path were identified the licensee considered the support equipment for the ESEL both front-line and support systems appeared to be included in the ESEL as evidenced by inclusion of SSCs on the success path and of support systems (e.g., batteries, motor control centers, inverters).

Yes Yes Yes Yes IV.

Walkdown Approach The licensee:

described the walkdown screening approach, including walkbys and walkdowns performed exclusively for the ESEP, in accordance with the guidance credited previous walkdown results, including a description of current action(s) to verify the present equipment condition and/or configuration (e.g., walk-bys), in accordance with the guidance stated that the walkdown was performed by seismically trained personnel Yes Yes Yes Notes from the Reviewer:

1. The staffrequested clarifcationregarding the trainingof the walkdown engineers. In their response from July 14, 2015 (ML15212A713), the licensee provided additional information on all individuals who performed the plant walkdowns have successfully completed the SQUG Walkdown Screening and Seismic Evaluation Training Course or equivalent training. This adequately responded to the staffs concern and the licensee demonstrated that it met the intent of the guidance.

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

No deviations or deficiencies were identified.

The licensee:

described, as needed,adverse material condition of the equipment (e.g., material degradation) credited previous walkdown results, included a description of current action(s) to verify the present equipment condition (e.g., walk-bys),

meeting the intent of the guidance Yes Yes The licensee:

described the conditions of structural items considered for the interim evaluation, including:

o spatial interactions (i.e., interaction between block walls and other items/components) o anchorage o piping connected to tanks (i.e., differential movement between pipes and tanks at connections)

Yes Yes Yes Notes from the Reviewer:None Deviation(s) or Deficiency(ies), and Resolution:

No deviations or deficiencies were identified.

NTTF Recommendation 2.1 Expedited Seismic Evaluation Process Technical Review Checklist for Davis-Besse Nuclear Power Station, Unit 1 5

The licensee reported deviations for Davis-Besse.

If deviations were identified, there is a discussion of how the deficiencies were or will be addressed in the ESEP submittal report.

No N/A The NRC staff concludes that:

the licensee described the performed walkdown approach, including any credited previous efforts (e.g.,Individual Plant Examination of External Events(IPEEE)) consistent with the guidance the licensee addressed identified deviations consistent with the guidance, if any Yes Yes V.

Capacity Screening Approach and HCLPF Calculation Results The licensee:

described the capacity screening process for the ESEL items, consistent with the guidance (e.g., use of EPRI NP-6041 screening table).

presented the results of the screened-out ESEL items in the ESEP report described the development of in-structure response spectra (ISRS) based on scaling described the development of ISRS based on new analysis consistent with the guidance described the method for estimating HCLPF capacity of screened-in ESEL items, including both structural and functional failure modes consistent with the guidance:

o use of Conservative Deterministic Failure Margin (CDFM) o use of fragility analysis (FA) o use of experience data or generic information credited IPEEE spectral shape for HCLPF capacity estimates is similar to or envelopes the RLGM, and anchored at the same control point presented the results of HCLPF capacities including associated failure modes for screened-in ESEL items reviewed the ESEL items with the lowest HCLPF values to ensure that their capacities are equal or greater than the RLGM Yes Yes N/A Yes Yes Yes No Yes N/A Yes Yes Notes from the Reviewer:

1. As allowed by guidance, the licensee did not use a scaled ISRS. The licensee calculated an ISRS based on a new GMRS for its upcoming seismic risk evaluation,as noted in Section I of this checklist. The ISRS is judged by the staff to be acceptable for this interim evaluation only based on the staffs review of ESEP submittal and because the new GMRS is similar to and bounds the SHSR GMRS.
2. The staffrequested confirmation that the HCLPF table included in the report as Attachment B represents those items from Attachment A that were screened in, and to also provide a roadmap between both attachment tables. In their response from July 14, 2015 (ML15212A713), the licensee confirmed this information and provided an updated version of Attachment B that identifies the ESEL item number to serve as a roadmap to Attachment A in the ESEP report. This response satisfies the staffs request for the purposes of this interim evaluation.
3. The staffrequested clarfication of the approach(es) applied to evaluate the seismic

NTTF Recommendation 2.1 Expedited Seismic Evaluation Process Technical Review Checklist for Davis-Besse Nuclear Power Station, Unit 1 6

capacity of components physically located on panels and/or cabinets, known as rule-of-the-box. In their response from July 14, 2015 (ML15212A713), the licenseeexplained that indicators and recorders are listed on the ESEL as distinct items, but their seismic evaluation is based on the evaluation of the parent component (ESEP Section 3.1.5),

and that when an ESEL item is identified to be mounted on a parent component, the HCLPF of the parent component is assigned to the item. The licensee also stated that all HCLPF calculations are based on the guidance provided in EPRI TR-1002988 and TR-1019200. The staffjudgedthe response from the licensee to be acceptable for the purposes of this interim evaluation.

4. The staff requested clarification regarding the soil-structure-interaction (SSI) analysis. In the response dated July 14, 2015 (ML15212A713), the licensee described their use of the peak shifting approach recommended guidelines from EPRI 1019200 and NP-6041.

The response adequately addressed the staffs concern and met the intent of the guindance for this interim evaluation.

5. In response to a staff clarification request, the licensee clarified in their response dated July 14, 2015 (ML15212A713) that the CDFM methodology was the only method used for all calculations, as stated in Section 6.4 of the ESEP report. The term fragility only refers to use of the hybrid approach to fragilities (described in Section 6.4.1 of EPRI 1025287) and does not imply that an alternative to CDFM was used in calculations.

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

No deviations or deficiencies were identified.

The NRC staff concludes that:

the licensee described the implementation of the capacity screening process consistent with the intent of the guidance the licensee presented capacity screening and calculation results, as appropriate, in the ESEP report the method used to develop the ISRS is consistent with guidance for use in the ESEP for HCLPF calculations, the licensee used HCLPF calculation methods as endorsed in the guidance no anomalies were noted in the reported HCLPF Yes Yes Yes Yes Yes VI.

Inaccessible Items The licensee:

provided a list of inaccessible items provided a schedule of the planned walkdown and evaluation for all inaccessible items provided Regulatory Commitment to complete walkdowns.

Yes N/A N/A Davis-Besse will provide results or complete walkdown by: N/A N/A Notes from the Reviewer:

1. The licensee identified a total of 14 inaccessible items from the ESEL (ESEP report Table 7-1), identified the reason for the inaccessibility of each item, and the criteria used to confirm the installed condition and its fragility. Methods such as photographs from the recent flooding walkdowns, review of plant drawings, and equivalency with other accessible equipment were used to determine the seismic fragility of these items. This to be acceptable for the purposes of this interim evaluation.

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

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No deviations or deficiencies were identified.

The NRC staff concludes that the licensee:

listed inaccessible items committed to provide the results (e.g. walkdowns, walkbys, etc.) of the remaining inaccessible items consistent with the guidance substitutions, if needed, were appropriately justified Yes N/A Yes VII.

Modifications to Plant Equipment The licensee:

identified modifications for ESEL items necessary to achieve HCLPF values that bound the RLGM (excluding mitigative strategies equipment (FLEX)), as specified in the guidance provided a schedule to implement such modifications (if any),

consistent with the intent of the guidance provided Regulatory Commitment to complete modifications provided Regulatory Commitment to report completion of modifications.

N/A N/A N/A N/A Davis-Besse will:

complete modifications by:N/A report completion of modifications by:N/A Notes from the Reviewer:

1. The licensee does not plan to perform any modifications since all the components in the ESEL have a HCLPF greater than the RLGM (0.20g).

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

No deviations or deficiencies were identified.

The NRC staff concludes that the licensee:

identified plant modifications necessary to achieve the target seismic capacity provided a schedule to implement the modifications (if any) consistent with the guidance N/A N/A VIII.

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Conclusions:==

The NRC staff assessed the licensees implementation of the ESEP guidance. Due to the interim applicability of the ESEP evaluations, use of the information for another application would require a separate NRC review and approval. Based on its review, the NRC staff concludes that the licensees implementation of the interim evaluation meets the intent of the guidance. The staff concludes that, through the implementation of the ESEP guidance, the licensee identified and evaluated the seismic capacity of certain key installed Mitigating Strategies equipment that is used for core cooling and containment functions to cope with scenarios that involve a loss of all AC power and loss of access to the ultimate heat sink to withstand a seismic event up to the Review Level Ground Motion (RLGM)and thus, provides additional assurance while the plant seismic risk evaluation is being conducted. In the case of Davis-Besse, in accordance as an option within the guidance and noted above, a GMRS was used as the RLGM, which is less than the SSE in some ranges. The application of this staff review is limited to the ESEP interim evaluation as part of NTTF R2.1: Seismic activities. As noted in the review checklist, the staff did not identify deviations or exceptions were taken from the guidance. The licensee did not identify any modifications of equipment was required from the ESEP.

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In summary, the licensee, by implementing the ESEP interim evaluation, has demonstrated additional assurance which supports continued plant safety while the longer-term seismic evaluation is completed to support regulatory decision making. The NRC staff concludes that the licensee responded appropriately to Enclosure 1, Item (6) of the 50.54(f) letter, dated March 12, 2012, for Davis-Besse Nuclear Power Station, Unit 1.

Principal Contributors: Malcolm Patterson, Dan Hoang, Tuan Le, David Heeszel, On Yee, Richard Rivera-Lugo, Richard Morante, (NRC Consultant)