Letter Sequence Acceptance Review |
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EPID:L-2017-LLA-0355, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis (Approved, Closed) |
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MONTHYEARML17181A3072017-06-23023 June 2017
NEI 17-02, Revision 0, Tornado Missile Risk Evaluator (TMRE) Industry Guidance Document
Project stage: Request
ML17235B1482017-08-23023 August 2017
U.S. Nuclear Regulatory Commission - Tornado Missile Risk Evaluator (TMRE) Methodology Topics and Methodology Feedback
Project stage: Request
HNP-17-072, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis2017-10-19019 October 2017
License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis
Project stage: Request
ML17319A5012017-11-21021 November 2017
Acceptance Review Letter, License Amendment Request to Revise Updated Final Safety Analysis Report to Incorporate Tornado Missile Risk Evaluator Methodology Into Licensing Basis
Project stage: Acceptance Review
ML17340A0612017-12-0808 December 2017
11/8/17 Summary of Teleconference with Entergy Operations, Inc., Tornado Missile Risk Evaluator with Applicability to Submittals from Duke Energy and Southern Nuclear Operating Co, Inc.
Project stage: Meeting
HNP-18-007, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Supplement Regarding De Minimis Penetrations2018-01-11011 January 2018
License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Supplement Regarding De Minimis Penetrations
Project stage: Supplement
ML18017A9382018-01-18018 January 2018
NEI 17-02 Tornado Missile Risk Evaluator (TMRE) - Resolution of NRC Staff Comments - January 18, 2018
Project stage: Request
ML18145A1812018-06-18018 June 2018
Request for Additional Information, License Amendment Request to Revise Updated Final Safety Analysis Report to Incorporate Tornado Missile Risk Evaluator Methodology Into Licensing Basis
Project stage: RAI
NL-18-0815, Tornado Missile Risk Evaluator: SNC Response to NRC Request for Additional Information2018-07-26026 July 2018
Tornado Missile Risk Evaluator: SNC Response to NRC Request for Additional Information
Project stage: Response to RAI
ML18094A2632018-08-17017 August 2018
Summary of 01/18/2018, Public Meeting with Nuclear Energy Institute, Duke Energy, Southern Nuclear Operating Co., Entergy Operations, Inc. to Discuss Development of Tornado Missile Risk Evaluator Methodology
Project stage: Meeting
NL-18-1179, Response to NRC Request for Additional Information Tornado Missile Risk Evaluator SNC Supplemental2018-09-14014 September 2018
Response to NRC Request for Additional Information Tornado Missile Risk Evaluator SNC Supplemental
Project stage: Supplement
RA-18-0106, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Supplement and Request for Additional Information Response2018-09-19019 September 2018
License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Supplement and Request for Additional Information Response
Project stage: Supplement
ML18347A3852019-03-29029 March 2019
Issuance of Amendment No. 169, Revise Updated Final Safety Analysis Report to Incorporate Tornado Missile Risk Evaluator Methodology Into Licensing Basis
Project stage: Approval
ML19120A1342019-05-0606 May 2019
3/15/19 Summary of Public Meeting with Nuclear Entergy Institute, Duke Energy, and Southern Nuclear Operating Company Post-Pilot Implementation of Tornado Missile Risk Evaluator Methodology at Vogtle, Units 1 and 2 and Shearon Harris, Unit
Project stage: Meeting
2018-01-18
[Table View] |
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Category:Acceptance Review Letter
MONTHYEARML24094A3282024-04-17017 April 2024
Acceptance of Exemption Request from Certain Requirements in 10 CFR 50.55a(h)(2)
ML23073A2282023-03-13013 March 2023
Duke Fleet- Adoption of TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements - Acceptance Review
ML23058A0562023-02-27027 February 2023
Acceptance of Amendment to Revise Surveillance Frequencies for RCS Pressure Isolation Valve Operational Leakage Testing and Reactor Trip System Instrumentation
ML23048A1512023-02-16016 February 2023
Acceptance Review - Proposed Alternative for Steam Generator Welds (L-2023-LLR-0003)
ML21006A4302021-01-0606 January 2021
Acceptance Review - Duke Fleet RA-20-0207 Request to Revise the Technical Specification for Engineered Safety Feature Actuation System (ESFAS) Instrumentation
ML20157A1062020-06-24024 June 2020
Review of the Fall 2019 Steam Generator Tube Inspections During Refueling Outage No. 22
ML20133K0722020-05-12012 May 2020
Acceptance of Requested Licensing Action Technical Specifications Related to Reducing the Minimum Required Reactor Coolant System Flow Rate and Update the List of Analytical Methods Used in the Determination of Core Operating Limits
ML19311C3412019-11-0707 November 2019
Acceptance Review: Shearon Harris License Amendment Request for TSTF-505
ML18270A1292018-10-0404 October 2018
Acceptance of Requested Licensing Action
ML17319A5012017-11-21021 November 2017
Acceptance Review Letter, License Amendment Request to Revise Updated Final Safety Analysis Report to Incorporate Tornado Missile Risk Evaluator Methodology Into Licensing Basis
ML17261A7272017-09-20020 September 2017
Shearon Harris Nuclear Power Plant, Unit 1 - Acceptance of Requested Licensing Action Regarding Spent Fuel Storage Pool Criticality Analyses (CAC No. MF9996)
ML16308A3702016-11-0707 November 2016
Results of Acceptance Review of Requested Licensing Action Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0 (CAC Nos. MF8422-MF8429)
ML16152A5962016-06-0303 June 2016
NRC Acceptance of Requested Licensing Action Amendment Request
ML15309A7282015-12-0101 December 2015
Acceptance of Requested Licensing Action Regarding Duke Energy Progress, Inc. Application to Revise Technical Specifications to Adopt Methodology Report
ML14157A0552014-06-13013 June 2014
Acceptance of Requested Relief Request I3R-14-Deferral of Reactor Vessel Inspections Inservice Inspection Program-Third 10-Year Interval
ML13329A4572013-11-25025 November 2013
Accepted for Review Shearon Harris--Acceptance Review for Relief Request I3R-13 Reactor Vessel Closure Head Nozzle 37
ML13324B0812013-11-20020 November 2013
E-mail Re. Acceptance Review for Relief Request I3R-12 Repair of Accumulator Fill Valve Piping Weld
ML11181A0162011-07-0101 July 2011
Acceptance for Review of Measurement Uncertainty Recapture Power Uprate License Amendment Request
ML1105300792011-02-18018 February 2011
E-mail, Acceptance Review of ME5410, Application for Exemption for M5 Cladding: 1/19/11
ML1018707202010-07-0909 July 2010
Acceptance Review Regarding a Relief Request for Approval of an Alternative Inservice Inspection Method for Six Pressure Retaining Dissimilar Metal Welds in the Reactor Pressure Vessel Nozzles
ML0935801382009-12-30030 December 2009
Acceptance Review Regarding Request for Exemption from the Requirements of 10 CFR Part 73, Section 73.55
ML0912705692009-05-15015 May 2009
Acceptance Review Re Amendment to Adopt Tech Spec Task Force (TSTF) Standard Tech Spec Change Traveler, TSTF-447, Elimination of Hydrogen Recombiners and Change to Hydrogen and Oxygen Monitors
ML0903603132009-02-0606 February 2009
Acceptance Review Regarding Amendment to Remove Credit for Boraflex in Boiling Water Reactor Spent Fuel Pool Storage Racks
ML0903000302009-01-30030 January 2009
Acceptance Review Regarding Amendment to Adopt National Fire Protection Association 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants, 2001 Edition
ML0902100672009-01-29029 January 2009
Acceptance Review Regarding Relief Request to Defer an ASME Code Repair of an Emergency Service Water System Weld Until the Next Refueling Outage
ML0902100112009-01-27027 January 2009
Acceptance Review Regarding Amendment to Remove Credit for Boraflex in BWR Spent Fuel Pool Storage Racks
ML0827011582008-09-26026 September 2008
Acceptance Review Regarding the License Amendment Request to Transition to NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants.
2024-04-17
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Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 21, 2017 Ms. Tanya Hamilton Site Vice President Duke Energy Progress, LLC Shearon Harris Nuclear Power Plant 5413 Shearon Harris Rd.
M/C HNP01 New Hill, NC 27562-0165
SUBJECT:
SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 - ACCEPTANCE OF PILOT APPLICATION OF TORNADO MISSILE RISK EVALUATOR METHODOLOGY (EPID L-2017-LLA-0355) (HNP-17-072)
Dear Ms. Hamilton:
By letter dated October 19, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17292B648), Duke Energy Progress, LLC (the licensee), requested a pilot license amendment request for Shearon Harris Nuclear Power Plant, Unit 1. The proposed amendment request would pilot the Nuclear Energy Institute (NEI) Technical Report NEI 17-02, Revision 1, "Tornado Missile Risk Evaluator (TMRE) Industry Guidance Document,"
September 2017 (ADAMS Accession No. ML17268A036). The proposed amendment request screens systems, structures, and components, using risk values (assessment of external hazard frequencies, system responses, and mitigating actions) to determine whether physical protection from tornado-generated missiles is warranted. The methodology would only be applicable to discovered conditions where tornado missile protection should be but is not currently provided. Future modifications to the facility requiring tornado missile protection would not be evaluated using the TMRE methodology. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
Consistent with Section 50.90 of Title 1O of the Code of Federal Regulations (1 O CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required.
This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the
T. Hamilton environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. If additional information is needed, you will be advised by separate correspondence.
The NRC staff did have a comment regarding the characterization of the compliance of the proposed change with current regulations. It is recognized that the submittal is risk-informed and outlines how the proposed change addresses the five principles of risk-informed decision making. As discussed in a public teleconference on November 8, 2017, the discussion in Section 4.1 of Enclosure 1 of the submittal indicates that the relaxation criteria is based on the risk metrics (i.e., overall plant core damage frequency or large early release frequency) in Regulatory Guide (RG) 1.174, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis." The NRC staff notes that the probabilistic criteria (i.e., the probability of damage to unprotected safety-related features) in Section 3.5.1.4 of NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition" (SRP), Revision 0, is not directly comparable to RG 1.174 acceptance guidelines. The description regarding continuing compliance with regulations needs to be enhanced by a more comprehensive discussion of the existing design bases and how it continues to meet the applicable regulations. Alternatively, the description could be enhanced to demonstrate that the relaxation, which is based on the concept that the frequency of damage to unprotected essential safety-related features, as permitted by SRP 3.5.1.4, remain applicable.
The NRC staff further notes that your submittal included application of the De Minim is screening approach. Justification for this approach is not addressed in either NEI 17-02, Revision 1, or the subject license amendment request. Although this would typically be treated as a sufficiency issue, the submittal is a pilot application, and the NRC staff has decided not to address the issue via the acceptance review in this instance. If your intent is to continue to use application of the De Minimis screening approach, a detailed justification should be provided promptly to ensure a timely review.
By letter dated July 3, 2017 (ADAMS Accession No. ML17130A761), the NRC staff approved a waiver of the fees in support of the NRC staff's review of the TMRE methodology and the amendment request related to this project. As there is an approved fee waiver, no estimate of resources will be provided. It should be noted that based on the information provided, the NRC staff expects to complete this review no later than October 2018. If there are emergent complexities or challenges in our review that would cause changes to the initial forecasted completion date, the reasons for the changes, will be communicated during the routine interactions with the assigned TMRE project manager.
The schedule is based on the NRC staff's initial review of the application and it could change, due to several factors including requests for additional information and unanticipated addition of scope to the review.
T. Hamilton If you have any questions, please contact me at (301) 415-2481 or via e-mail at Ed.Miller@nrc.gov.
Sincerely, l:fi~t:~ Manager Special Projects and Process Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-400 cc: Listserv
ML17319A501 OFFICE NRR/DORL/LSPB/PM NRR/DORL/LSPB/LAiT NRR/DORL/LSPB/LA NAME EMiller IBetts JBurkhardt DATE 11/20/17 11/17/17 11/20/17 OFFICE NRR/DORL/LSPB/BC NRR/DORL/LSPB/PM NAME DBroaddus EMiller DATE 11/20/17 11/21/17
