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{{#Wiki_filter: | {{#Wiki_filter:NRR-PMDAPEm Resource From: Jackson, Diane Sent: Friday, August 28, 2015 3:34 PM To: Shams, Mohamed Cc: DiFrancesco, Nicholas; Wyman, Stephen; Spence, Jane; Devlin-Gill, Stephanie; Roche, Kevin; Yee, On; Pettis, Robert; Gallucci, Ray; Patel, Pravin; Wang, Weijun; Graizer, Vladimir; 50.54f_Seismic Resource; RidsNroDsea Resource | ||
==Subject:== | ==Subject:== | ||
RESEND: BEAVER VALLEY NUCLEAR STATION, UNITS 1 AND 2 - TECHNICAL REVIEW CHECKLIST RELATED TO INTERIM ESEP | RESEND: BEAVER VALLEY NUCLEAR STATION, UNITS 1 AND 2 - TECHNICAL REVIEW CHECKLIST RELATED TO INTERIM ESEP SUPPORTING IMPLEMENTATION OF NTTF R2.1, SEISMIC (TAC NOS. MF5223 AND MF5224) | ||
Attachments: | Attachments: Beaver Valley R2.1 seismic ESEP NRC review.docx August 28, 2015 MEMORANDUM TO: Mohamed K. Shams, Chief Hazards Management Branch (JHMB) | ||
Beaver Valley R2.1 seismic ESEP NRC review. | |||
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 | ||
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==SUBJECT:== | ==SUBJECT:== | ||
BEAVER VALLEY NUCLEAR STATION, UNITS 1 AND 2 - 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 NOS. MF5223 AND MF5224) | BEAVER VALLEY NUCLEAR STATION, UNITS 1 AND 2 - 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 NOS. MF5223 AND MF5224) | ||
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 BEAVER VALLEY NUCLEAR STATION, UNITS 1 AND 2 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 | 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 BEAVER VALLEY NUCLEAR STATION, UNITS 1 AND 2 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 | 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. | ||
activities. | |||
This electronic memo replaces the electronic memo sent on August 10, 2015, and 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 replaces the electronic memo sent on August 10, 2015, and 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 concludes the | This concludes the NRCs efforts associated with TAC NOS. MF5223 and MF5224 for the review of the interim ESEP report for the BEAVER VALLEY NUCLEAR STATION, UNITS 1 AND 2. | ||
Docket Nos: 50-334 and 50-412 CONTACT: Stephanie Devlin-Gill Office of New Reactors 301-415-5301 Copy: Nicholas DiFrancesco, Stephen Wyman, Jane | Docket Nos: 50-334 and 50-412 CONTACT: Stephanie Devlin-Gill Office of New Reactors 301-415-5301 Copy: Nicholas DiFrancesco, Stephen Wyman, Jane Spence, Stephanie Devlin-Gill, Kevin Roche, On Yee, Weijun Wang, Ray Gallucci, Pravin Patel, Bob Pettis, Vladimir Graizer, 50.54f Seismic Resource, RidsNroDsea Resource 1 | ||
Hearing Identifier: NRR_PMDA Email Number: 2362 Mail Envelope Properties (4fbd4eaa031d44aa8f3ef7c518e84b07) | |||
==Subject:== | ==Subject:== | ||
RESEND: BEAVER VALLEY NUCLEAR STATION, UNITS 1 AND 2 - TECHNICAL REVIEW CHECKLIST RELATED TO INTERIM ESEP SUPPORTING IMPLEMENTATION OF NTTF R2.1, SEISMIC (TAC NOS. MF5223 AND MF5224) | RESEND: BEAVER VALLEY NUCLEAR STATION, UNITS 1 AND 2 - | ||
Sent Date: | TECHNICAL REVIEW CHECKLIST RELATED TO INTERIM ESEP SUPPORTING IMPLEMENTATION OF NTTF R2.1, SEISMIC (TAC NOS. MF5223 AND MF5224) | ||
Sent Date: 8/28/2015 3:34:01 PM Received Date: 8/28/2015 3:34:10 PM From: Jackson, Diane Created By: Diane.Jackson@nrc.gov Recipients: | |||
Recipients: | "DiFrancesco, Nicholas" <Nicholas.DiFrancesco@nrc.gov> | ||
Tracking Status: None | Tracking Status: None "Wyman, Stephen" <Stephen.Wyman@nrc.gov> | ||
Tracking Status: None | Tracking Status: None "Spence, Jane" <Jane.Spence@nrc.gov> | ||
Tracking Status: None Post Office: | 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 "Pettis, Robert" <Robert.Pettis@nrc.gov> | |||
Tracking Status: None "Gallucci, Ray" <Ray.Gallucci@nrc.gov> | |||
Tracking Status: None "Patel, Pravin" <Pravin.Patel@nrc.gov> | |||
Tracking Status: None "Wang, Weijun" <Weijun.Wang@nrc.gov> | |||
Tracking Status: None "Graizer, Vladimir" <Vladimir.Graizer@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 "Shams, Mohamed" <Mohamed.Shams@nrc.gov> | |||
Tracking Status: None Post Office: R4PWMSMRS03.nrc.gov Files Size Date & Time MESSAGE 3157 8/28/2015 3:34:10 PM Beaver Valley R2.1 seismic ESEP NRC review.docx 47494 Options Priority: Standard Return Notification: No Reply Requested: No | |||
Sensitivity: Normal Expiration Date: | |||
Recipients Received: | |||
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) | TECHNICAL REVIEW CHECKLIST BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO EXPEDITED SEISMIC EVALUATION PROCESS INTERIM EVALUATION IMPLEMENTING NTTF RECOMMENDATION 2.1 SEISMIC BEAVER VALLEY POWER STATION, UNITS 1 AND 2 DOCKET NOS. 50-334 AND 50-412 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, 20131, 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, 20132, 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 Beaver Valley Power Station, Units 1 and 2 By letter dated December 19, 2014,3FirstEnergy Nuclear Operating Company (FENOC) provided an Expedited Seismic Evaluation Process (ESEP) report in a response to Enclosure 1, Requested Information Item (6) of the 50.54(f) letter, for the Beaver Valley Power Station (Beaver Valley), Units 1 and 2. | |||
I. Review Level Ground Motion The licensee: | |||
* described the determination of the review level ground motion Yes (RLGM) using one of the means acceptable by the guidance | |||
* identified location of the control point and is consistent with March Yes submittal | |||
* compared the site ground motion response spectra used to select Yes the ESEP RLGM to the SSE. | |||
Beaver Valley Units 1 and 2 used a specific GMRS. | |||
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 submittal | |||
* compared the site ground motion response spectra used to select the ESEP RLGM to the SSE. | |||
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 Seismic Hazard and Screening Report (SHSR) 4 , which was found acceptable for use in Recommendation 2.1 seismic activities by the staff. | * The licensee used a new GMRS rather than its seismic hazard reevaluation GMRS documented in its March 2014 Seismic Hazard and Screening Report (SHSR)4, which was found acceptable for use in Recommendation 2.1 seismic activities by the staff. | ||
Because the new GMRS is similar to and bounds the SHSR GMRS, the staff judged that this GMRS is acceptable for this interim evaluation. | Because the new GMRS is similar to and bounds the SHSR GMRS, 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. The NRC staff concludes: | * No deviations or deficiencies were identified. | ||
* the | The NRC staff concludes: | ||
* the RLGM is reasonable for use in the interim evaluation. | * the licensees RLGM meets the intent of the guidance Yes | ||
* the RLGM is reasonable for use in the interim evaluation. Yes II. Selection of the Success Path The licensee: | |||
* described the success path | * described the success path Yes | ||
* described normal and desired state of the equipment for the success path | * described normal and desired state of the equipment for the success Yes path | ||
* ensured that the success path is consistent with the | * 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 guidance or meets the intent of the guidance | * 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 | * used installed FLEX Phase 1 equipment as part of the success path Yes | ||
* included FLEX Phase 2 and/or 3 connections | * included FLEX Phase 2 and/or 3 connections | ||
* considered installed FLEX Phase 2 and/or 3 equipment | * considered installed FLEX Phase 2 and/or 3 equipment Yes Yes Notes from the Reviewer: None Deviation(s) or Deficiency(ies), and Resolution: | ||
None | |||
* No deviations or deficiencies were identified. | * No deviations or deficiencies were identified. | ||
3 ADAMS Accession No ML14353A059 4ADAMS Accession No ML14092A203 NTTF Recommendation 2.1 Expedited Seismic Evaluation Process Technical Review Checklist for Beaver Valley Power Station, Units 1 and 2 | 3 ADAMS Accession No ML14353A059 4ADAMS Accession No ML14092A203 2 | ||
* 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. | NTTF Recommendation 2.1 Expedited Seismic Evaluation Process Technical Review Checklist for Beaver Valley Power Station, Units 1 and 2 The NRC staff concludes that: | ||
* the selected success path is reasonable for use in the interim Yes evaluation | |||
* developed and provided the ESEL by applying the ESEP | * the licensee considered installed Phase 2 and 3 connections or Yes equipment in the interim evaluation. | ||
III. Selection of the Equipment List The licensee: | |||
* developed and provided the ESEL by applying the ESEP Yes | |||
* 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 | 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: | ||
: 1. The staff verified that major components in direct flow path were identified through the use of system notebooks. | |||
: 2. Inclusion of power-operated valves not required to change state as part of FLEX mitigation strategy. | |||
Deviation(s) or Deficiency(ies), and Resolution: | Deviation(s) or Deficiency(ies), and Resolution: | ||
* No deviations or deficiencies were identified. For PWR Plants ONLY | * No deviations or deficiencies were identified. | ||
For PWR Plants ONLY The licensee included indicators / instrumentation for the following functions: | |||
The licensee included indicators / instrumentation for the following functions: | level, pressure, temperature, that would be indicative of (but not explicitly Yes identified to specific instruments): water level of the steam generator (SG), | ||
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. | pressure of SG, containment, and reactor coolant system (RCS); and temperature of the RCS. | ||
For BWR Plants ONLY The licensee considered 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. | |||
The licensee considered indicators for the following functions: | Notes from the Reviewer: None Deviation(s) or Deficiency(ies), and Resolution: | ||
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. | * No deviations or deficiencies were identified. | ||
None | Through a sampling of the ESEP key components, the NRC staff concludes that: | ||
* No deviations or deficiencies were identified. 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 Yes guidance for the interim evaluation | ||
* the | * the desired equipment state for the success path were identified Yes | ||
* the desired equipment state for the success path were identified | * the licensee considered the support equipment for the ESEL Yes | ||
* the licensee considered the support equipment for the ESEL | * both front-line and support systems appeared to be included in the Yes ESEL as evidenced by inclusion of SSCs on the success path and of support systems (e.g., batteries, motor control centers, inverters). | ||
* 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). | 3 | ||
NTTF Recommendation 2.1 Expedited Seismic Evaluation Process Technical Review Checklist for Beaver Valley Power Station, Units 1 and 2 IV. Walkdown Approach The licensee: | |||
* described the walkdown screening approach, including walkbys and walkdowns performed exclusively for the ESEP, in accordance with the guidance | * 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 action(s) to verify the present equipment condition and/or configuration (e.g., walk-bys), 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 personnel | * stated that the walkdown was performed by seismically trained Yes personnel Notes from the Reviewer: | ||
: 1. Although the licensee did not state that walkdown personnel had been trained in seismic walkdowns, other activities referenced in the ESEP report involveseismic (i.e., SQUG) training, such as NTTF Recommendation 2.3 seismic walkdowns, seismic probabilistic risk assessments. The staff finds this acceptable evidence for this interim evaluation. | |||
Deviation(s) or Deficiency(ies), and Resolution: | Deviation(s) or Deficiency(ies), and Resolution: | ||
* No deviations or deficiencies were identified. The licensee: | * No deviations or deficiencies were identified. | ||
* described, if needed, adverse material condition of the equipment (e.g., material degradation) | The licensee: | ||
* 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 | * described, if needed, adverse material condition of the equipment Yes (e.g., material degradation) | ||
* 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 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 No o piping connected to tanks (i.e., differential movement No between pipes and tanks at connections) | ||
Notes from the Reviewer: None Deviation(s) or Deficiency(ies), and Resolution: | |||
* No deviations or deficiencies were identified. | |||
The licensee reported deviations for Beaver Valley Units 1 and 2. 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. | |||
The NRC staff concludes that: | |||
* the licensee described the performed walkdown approach, including Yes any credited previous efforts (e.g., IndividualPlant Examination of External Events(IPEEE) consistent with the guidance. | |||
Yes | |||
* the licensee addressed identified deviations consistent with the guidance, if any V. Capacity Screening Approach and HCLPF Calculation Results 4 | |||
NTTF Recommendation 2.1 Expedited Seismic Evaluation Process Technical Review Checklist for Beaver Valley Power Station, Units 1 and 2 The licensee: | |||
* described the capacity screening process for the ESEL items, Yes 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 Yes report | |||
* described the development of in-structure response spectra (ISRS) N/A (see Note 1) based on scaling | |||
* described the development of ISRS based on new analysis Yes consistent with the guidance | |||
* described the method for estimating HCLPF capacity of screened-in Yes ESEL items, including both structural and functional failure modes consistent with the guidance: | |||
o use of Conservative Deterministic Failure Margin (CDFM) Yes o use of fragility analysis (FA) Yes o use of experience data or generic information N/A | |||
* credited IPEEE spectral shape for HCLPF capacity estimates is similar to or envelopes the RLGM, and anchored at the same control Yes point | |||
* presented the results of HCLPF capacities including associated failure modes for screened-in ESEL items Yes | |||
* described the capacity screening process for the ESEL items, consistent with the guidance (e.g., use of EPRI NP-6041 screening table). | * reviewed the ESEL items with the lowest HCLPF values to ensure Yes that their capacities are equal or greater than the RLGM Notes from the Reviewer: | ||
* presented the results of the screened-out ESEL items in the ESEP report | : 1. The licensee did not use a scaled ISRS. The licensee calculated a new ISRS based on a new GMRS for its upcoming seismic risk evaluation. 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. | ||
* described the development of in-structure response spectra (ISRS) based on scaling | : 2. The staff requested clarification regarding the HCLPF calculation for components mounted in or on parent components. The licensees response (ML15181A085) provided expanded description with examples, of the process used to obtain HCLPF values for components mounted in or on parent components (rule-of-the-box). This expanded description adequately addressed the staffs concern and met the intent of the guidance for this interim evaluation. | ||
* described the development of ISRS based on new analysis consistent with the guidance | : 3. The staff requested clarification regarding how variability was taken into consideration in SSI analyses. The licensees response (ML15181A085) described the method used to estimate variability for the SSI analyses. The licensee used a peak shifting approach that incorporated variability of +/- 20% in the analyses which is consistent with EPRI 6041. | ||
* described the method for estimating HCLPF capacity of screened-in ESEL items, including both structural and functional failure modes consistent with the guidance: | This adequately addressed the staffs concern and met the intent of the guidance for this interim evaluation. | ||
o use of Conservative Deterministic Failure Margin (CDFM) o use of fragility analysis (FA) o use of experience data or generic information | Deviation(s) or Deficiency(ies), and Resolution: | ||
* credited IPEEE spectral shape for HCLPF capacity estimates is similar to or envelopes the RLGM, and anchored at the same control point | * No deviations or deficiencies were identified. | ||
* presented the results of HCLPF capacities including associated failure modes for screened-in ESEL items | 5 | ||
* reviewed the ESEL items with the lowest HCLPF values to ensure that their capacities are equal or greater than the RLGM | |||
This adequately addressed the | |||
NTTF Recommendation 2.1 Expedited Seismic Evaluation Process Technical Review Checklist for Beaver Valley Power Station, Units 1 and 2 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 presented capacity screening and calculation results, as Yes appropriate, in the ESEP report | |||
* the method used to develop the ISRS is consistent with guidance for Yes use in the ESEP | |||
* for HCLPF calculations, the licensee used HCLPF calculation Yes methods as endorsed in the guidance | |||
* 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 No inaccessible items | |||
* provided Regulatory Commitment to complete walkdowns N/A Beaver Valley will provide results or complete walkdown by:__N/A_______ N/A Notes from the Reviewer: | |||
: 1. The staff requested clarification regarding the assessment of inaccessible items. The licensees response (ML15181A085) stated that the one or more methods were used to assess the inaccessible items. The methods include similarity to other components; mounting configuration from drawings; and identification of plant modifications or seismic evaluations. Those methods are based on previous walk down for more than 700 components per Unit and other IPEEE supporting documents, and the assessment process is consistent with the recommendation of EPRI 6041. This explanation adequately addressed the staffs concern and met the intent of the guidance 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 that the licensee: | |||
* | * listed inaccessible items Yes | ||
* the | * committed to provide the results (e.g., walkdowns, walk-bys, etc) of N/A the remaining inaccessible items consistent with the guidance | ||
* substitutions, if needed, were appropriately justified Yes VII. Modifications to Plant Equipment The licensee: | |||
* | * 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 | ||
* provided a schedule to implement such modifications (if any), N/A consistent with the intent of the guidance | |||
* | * provided Regulatory Commitment to complete modifications N/A | ||
* provided a schedule of the | * provided Regulatory Commitment to report completion of N/A modifications. | ||
* provided Regulatory Commitment to complete | 6 | ||
NTTF Recommendation 2.1 Expedited Seismic Evaluation Process Technical Review Checklist for Beaver Valley Power Station, Units 1 and 2 Beaver Valley Units 1 and 2 will: | |||
* complete modifications by _____N/A______________ N/A | |||
* complete modifications by _____N/A______________ | |||
* report completion of modifications by ___N/A___________ | * report completion of modifications by ___N/A___________ | ||
Notes from the Reviewer: No modifications were identified. | |||
Deviation(s) or Deficiency(ies), and Resolution: | Deviation(s) or Deficiency(ies), and Resolution: | ||
* No deviations or deficiencies were identified. The NRC staff concludes that the licensee: | * No deviations or deficiencies were identified. | ||
* identified plant modifications necessary to achieve the target seismic capacity | The NRC staff concludes that the licensee: | ||
* provided a schedule to implement the modifications (if any) consistent with the guidance | * identified plant modifications necessary to achieve the target seismic N/A capacity | ||
* provided a schedule to implement the modifications (if any) N/A consistent with the guidance VIII. | |||
== Conclusions:== | |||
Princple Contributors: | 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). In the case of Beaver Valley, the RLGM was a new site GMRS that was developed as part of the upcoming seismic risk evaluation. The licensee did not identify any necessary modification of equipment from this evaluation. The application of this staff review is limited to the ESEP interim evaluation as part of NTTF R2.1: Seismic activities. | ||
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 Beaver Valley, Units 1 and 2. | |||
Princple Contributors: Ray Gallucci, Kevin Roche, On Yee, Pravin Patel, Robert Pettis, Vladimir Graizer, Weijun Wang, Thomas Houston (NRC Consultant) 7}} |
Revision as of 07:59, 31 October 2019
ML15245A817 | |
Person / Time | |
---|---|
Site: | Beaver Valley |
Issue date: | 08/28/2015 |
From: | Diane Jackson Office of New Reactors |
To: | Mohamed Shams Japan Lessons-Learned Division |
References | |
TAC MF5223, TAC MF5224 | |
Download: ML15245A817 (10) | |
Text
NRR-PMDAPEm Resource From: Jackson, Diane Sent: Friday, August 28, 2015 3:34 PM To: Shams, Mohamed Cc: DiFrancesco, Nicholas; Wyman, Stephen; Spence, Jane; Devlin-Gill, Stephanie; Roche, Kevin; Yee, On; Pettis, Robert; Gallucci, Ray; Patel, Pravin; Wang, Weijun; Graizer, Vladimir; 50.54f_Seismic Resource; RidsNroDsea Resource
Subject:
RESEND: BEAVER VALLEY NUCLEAR STATION, UNITS 1 AND 2 - TECHNICAL REVIEW CHECKLIST RELATED TO INTERIM ESEP SUPPORTING IMPLEMENTATION OF NTTF R2.1, SEISMIC (TAC NOS. MF5223 AND MF5224)
Attachments: Beaver Valley 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:
BEAVER VALLEY NUCLEAR STATION, UNITS 1 AND 2 - 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 NOS. MF5223 AND MF5224)
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 BEAVER VALLEY NUCLEAR STATION, UNITS 1 AND 2 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 replaces the electronic memo sent on August 10, 2015, and 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 concludes the NRCs efforts associated with TAC NOS. MF5223 and MF5224 for the review of the interim ESEP report for the BEAVER VALLEY NUCLEAR STATION, UNITS 1 AND 2.
Docket Nos: 50-334 and 50-412 CONTACT: Stephanie Devlin-Gill Office of New Reactors 301-415-5301 Copy: Nicholas DiFrancesco, Stephen Wyman, Jane Spence, Stephanie Devlin-Gill, Kevin Roche, On Yee, Weijun Wang, Ray Gallucci, Pravin Patel, Bob Pettis, Vladimir Graizer, 50.54f Seismic Resource, RidsNroDsea Resource 1
Hearing Identifier: NRR_PMDA Email Number: 2362 Mail Envelope Properties (4fbd4eaa031d44aa8f3ef7c518e84b07)
Subject:
RESEND: BEAVER VALLEY NUCLEAR STATION, UNITS 1 AND 2 -
TECHNICAL REVIEW CHECKLIST RELATED TO INTERIM ESEP SUPPORTING IMPLEMENTATION OF NTTF R2.1, SEISMIC (TAC NOS. MF5223 AND MF5224)
Sent Date: 8/28/2015 3:34:01 PM Received Date: 8/28/2015 3:34:10 PM From: Jackson, Diane Created By: Diane.Jackson@nrc.gov Recipients:
"DiFrancesco, Nicholas" <Nicholas.DiFrancesco@nrc.gov>
Tracking Status: None "Wyman, Stephen" <Stephen.Wyman@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 "Pettis, Robert" <Robert.Pettis@nrc.gov>
Tracking Status: None "Gallucci, Ray" <Ray.Gallucci@nrc.gov>
Tracking Status: None "Patel, Pravin" <Pravin.Patel@nrc.gov>
Tracking Status: None "Wang, Weijun" <Weijun.Wang@nrc.gov>
Tracking Status: None "Graizer, Vladimir" <Vladimir.Graizer@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 "Shams, Mohamed" <Mohamed.Shams@nrc.gov>
Tracking Status: None Post Office: R4PWMSMRS03.nrc.gov Files Size Date & Time MESSAGE 3157 8/28/2015 3:34:10 PM Beaver Valley R2.1 seismic ESEP NRC review.docx 47494 Options Priority: Standard Return Notification: No Reply Requested: No
Sensitivity: Normal Expiration Date:
Recipients Received:
TECHNICAL REVIEW CHECKLIST BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO EXPEDITED SEISMIC EVALUATION PROCESS INTERIM EVALUATION IMPLEMENTING NTTF RECOMMENDATION 2.1 SEISMIC BEAVER VALLEY POWER STATION, UNITS 1 AND 2 DOCKET NOS. 50-334 AND 50-412 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, 20131, 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, 20132, 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 Beaver Valley Power Station, Units 1 and 2 By letter dated December 19, 2014,3FirstEnergy Nuclear Operating Company (FENOC) provided an Expedited Seismic Evaluation Process (ESEP) report in a response to Enclosure 1, Requested Information Item (6) of the 50.54(f) letter, for the Beaver Valley Power Station (Beaver Valley), Units 1 and 2.
I. Review Level Ground Motion The licensee:
- described the determination of the review level ground motion Yes (RLGM) using one of the means acceptable by the guidance
- identified location of the control point and is consistent with March Yes submittal
Beaver Valley Units 1 and 2 used a specific GMRS.
Notes from the Reviewer:
- The licensee used a new GMRS rather than its seismic hazard reevaluation GMRS documented in its March 2014 Seismic Hazard and Screening Report (SHSR)4, which was found acceptable for use in Recommendation 2.1 seismic activities by the staff.
Because the new GMRS is similar to and bounds the SHSR GMRS, 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 Yes
- the RLGM is reasonable for use in the interim evaluation. Yes II. Selection of the Success Path The licensee:
- described the success path Yes
- 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 3 equipment Yes Yes Notes from the Reviewer: None Deviation(s) or Deficiency(ies), and Resolution:
- No deviations or deficiencies were identified.
3 ADAMS Accession No ML14353A059 4ADAMS Accession No ML14092A203 2
NTTF Recommendation 2.1 Expedited Seismic Evaluation Process Technical Review Checklist for Beaver Valley Power Station, Units 1 and 2 The NRC staff concludes that:
- the selected success path is reasonable for use in the interim Yes evaluation
- the licensee considered installed Phase 2 and 3 connections or Yes equipment in the interim evaluation.
III. Selection of the Equipment List The licensee:
- identified equipment considering the following functions:
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:
- 1. The staff verified that major components in direct flow path were identified through the use of system notebooks.
- 2. Inclusion of power-operated valves not required to change state as part of FLEX mitigation strategy.
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 Yes 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 licensee considered 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.
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 Yes guidance for the interim evaluation
- the desired equipment state for the success path were identified Yes
- the licensee considered the support equipment for the ESEL Yes
- both front-line and support systems appeared to be included in the Yes ESEL as evidenced by inclusion of SSCs on the success path and of support systems (e.g., batteries, motor control centers, inverters).
3
NTTF Recommendation 2.1 Expedited Seismic Evaluation Process Technical Review Checklist for Beaver Valley Power Station, Units 1 and 2 IV. Walkdown Approach The licensee:
- 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. Although the licensee did not state that walkdown personnel had been trained in seismic walkdowns, other activities referenced in the ESEP report involveseismic (i.e., SQUG) training, such as NTTF Recommendation 2.3 seismic walkdowns, seismic probabilistic risk assessments. The staff finds this acceptable evidence for this interim evaluation.
Deviation(s) or Deficiency(ies), and Resolution:
- No deviations or deficiencies were identified.
The licensee:
- described, if needed, adverse material condition of the equipment Yes (e.g., material degradation)
- 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 The licensee:
- described the conditions of structural items considered for the interim evaluation, including:
o spatial interactions (i.e., interaction between block walls and Yes other items/components) o anchorage No o piping connected to tanks (i.e., differential movement No between pipes and tanks at connections)
Notes from the Reviewer: None Deviation(s) or Deficiency(ies), and Resolution:
- No deviations or deficiencies were identified.
The licensee reported deviations for Beaver Valley Units 1 and 2. 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.
The NRC staff concludes that:
- the licensee described the performed walkdown approach, including Yes any credited previous efforts (e.g., IndividualPlant Examination of External Events(IPEEE) consistent with the guidance.
Yes
- the licensee addressed identified deviations consistent with the guidance, if any V. Capacity Screening Approach and HCLPF Calculation Results 4
NTTF Recommendation 2.1 Expedited Seismic Evaluation Process Technical Review Checklist for Beaver Valley Power Station, Units 1 and 2 The licensee:
- described the capacity screening process for the ESEL items, Yes consistent with the guidance (e.g., use of EPRI NP-6041 screening table).
- described the development of in-structure response spectra (ISRS) N/A (see Note 1) based on scaling
- described the development of ISRS based on new analysis Yes consistent with the guidance
- described the method for estimating HCLPF capacity of screened-in Yes ESEL items, including both structural and functional failure modes consistent with the guidance:
o use of Conservative Deterministic Failure Margin (CDFM) Yes o use of fragility analysis (FA) Yes o use of experience data or generic information N/A
- credited IPEEE spectral shape for HCLPF capacity estimates is similar to or envelopes the RLGM, and anchored at the same control Yes point
- 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 Yes that their capacities are equal or greater than the RLGM Notes from the Reviewer:
- 1. The licensee did not use a scaled ISRS. The licensee calculated a new ISRS based on a new GMRS for its upcoming seismic risk evaluation. 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 staff requested clarification regarding the HCLPF calculation for components mounted in or on parent components. The licensees response (ML15181A085) provided expanded description with examples, of the process used to obtain HCLPF values for components mounted in or on parent components (rule-of-the-box). This expanded description adequately addressed the staffs concern and met the intent of the guidance for this interim evaluation.
- 3. The staff requested clarification regarding how variability was taken into consideration in SSI analyses. The licensees response (ML15181A085) described the method used to estimate variability for the SSI analyses. The licensee used a peak shifting approach that incorporated variability of +/- 20% in the analyses which is consistent with EPRI 6041.
This adequately addressed the staffs concern and met the intent of the guidance for this interim evaluation.
Deviation(s) or Deficiency(ies), and Resolution:
- No deviations or deficiencies were identified.
5
NTTF Recommendation 2.1 Expedited Seismic Evaluation Process Technical Review Checklist for Beaver Valley Power Station, Units 1 and 2 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 presented capacity screening and calculation results, as Yes appropriate, in the ESEP report
- 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 No inaccessible items
- provided Regulatory Commitment to complete walkdowns N/A Beaver Valley will provide results or complete walkdown by:__N/A_______ N/A Notes from the Reviewer:
- 1. The staff requested clarification regarding the assessment of inaccessible items. The licensees response (ML15181A085) stated that the one or more methods were used to assess the inaccessible items. The methods include similarity to other components; mounting configuration from drawings; and identification of plant modifications or seismic evaluations. Those methods are based on previous walk down for more than 700 components per Unit and other IPEEE supporting documents, and the assessment process is consistent with the recommendation of EPRI 6041. This explanation adequately addressed the staffs concern and met the intent of the guidance for this interim evaluation.
Deviation(s) or Deficiency(ies), and Resolution:
- No deviations or deficiencies were identified.
The NRC staff concludes that the licensee:
- listed inaccessible items Yes
- committed to provide the results (e.g., walkdowns, walk-bys, etc) of N/A the remaining inaccessible items consistent with the guidance
- substitutions, if needed, were appropriately justified Yes VII. Modifications to Plant Equipment The licensee:
- 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
- provided a schedule to implement such modifications (if any), N/A consistent with the intent of the guidance
- provided Regulatory Commitment to complete modifications N/A
- provided Regulatory Commitment to report completion of N/A modifications.
6
NTTF Recommendation 2.1 Expedited Seismic Evaluation Process Technical Review Checklist for Beaver Valley Power Station, Units 1 and 2 Beaver Valley Units 1 and 2 will:
- complete modifications by _____N/A______________ N/A
- report completion of modifications by ___N/A___________
Notes from the Reviewer: No modifications were identified.
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 N/A capacity
- provided a schedule to implement the modifications (if any) N/A consistent with the guidance 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). In the case of Beaver Valley, the RLGM was a new site GMRS that was developed as part of the upcoming seismic risk evaluation. The licensee did not identify any necessary modification of equipment from this evaluation. The application of this staff review is limited to the ESEP interim evaluation as part of NTTF R2.1: Seismic activities.
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 Beaver Valley, Units 1 and 2.
Princple Contributors: Ray Gallucci, Kevin Roche, On Yee, Pravin Patel, Robert Pettis, Vladimir Graizer, Weijun Wang, Thomas Houston (NRC Consultant) 7