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MONTHYEARAEP-NRC-2015-46, License Amendment Request to Adopt TSTF-425-A, Rev. 3, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force Initiative 5B2015-11-19019 November 2015 License Amendment Request to Adopt TSTF-425-A, Rev. 3, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force Initiative 5B Project stage: Request AEP-NRC-2016-17, Supplement to License Amendment Request to Adopt TSTF-425-A, Revision 3, Relocate Surveillance Frequencies to License Control - Risk Informed Technical Specification Task Force (RITSTF) Initiative 5B.2016-02-0404 February 2016 Supplement to License Amendment Request to Adopt TSTF-425-A, Revision 3, Relocate Surveillance Frequencies to License Control - Risk Informed Technical Specification Task Force (RITSTF) Initiative 5B. Project stage: Supplement ML16127A0792016-05-11011 May 2016 Request for Additional Information Regarding License Amendment Request to Relocate Surveillance Frequencies to Licensee Control Project stage: RAI ML16154A1822016-06-0909 June 2016 Request for Additional Information Regarding License Amendment Request to Relocate Surveillance Frequencies to Licensee Control (CAC Nos. MF7114 and MF7115) Project stage: RAI AEP-NRC-2016-48, Unit 2 - Response to Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-425, Relocate Surveillance Frequencies Program to Licensee-Control...2016-06-16016 June 2016 Unit 2 - Response to Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-425, Relocate Surveillance Frequencies Program to Licensee-Control... Project stage: Response to RAI ML16211A0152016-08-0101 August 2016 Follow-Up Request for Additional Information Regarding License Amendment Request to Relocate Surveillance Frequencies to Licensee Control Project stage: RAI AEP-NRC-2016-69, Follow-up Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-425, Relocate Surveillance Frequencies Program to License Control-Risk Informed Technical Specification Task Force.2016-09-0909 September 2016 Follow-up Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-425, Relocate Surveillance Frequencies Program to License Control-Risk Informed Technical Specification Task Force. Project stage: Response to RAI AEP-NRC-2016-88, Withdrawal of Emergency License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source- Operating2016-10-13013 October 2016 Withdrawal of Emergency License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source- Operating Project stage: Withdrawal ML16308A1132016-11-16016 November 2016 Summary of October 27, 2016, Public Meeting with Indiana Michigan Power Company Regarding the Donald C. Cook Nuclear Plant, Units 1 and 2 Project stage: Meeting ML17045A1502017-03-31031 March 2017 Issuance of Amendments Adopting of TSTF0425-A, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B Project stage: Approval 2016-05-11
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Category:Letter
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[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23352A3502023-12-19019 December 2023 Dc. Cook Nuclear Power Plant, Units 1 Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23310A1152023-11-0606 November 2023 Notification of the NRC Baseline Inspection and Request for Information, Inspection Report 05000316/2024002 ML22264A1112022-09-21021 September 2022 Notification of Post-Approval Site Inspection for License Renewal - Phase IV; IR 05000315/2023010; 05000316/2023010 and RFI ML22230A4362022-08-19019 August 2022 Licensed Operator Positive Fitness-For-Duty Test ML22049B4532022-02-22022 February 2022 Notification of NRC Baseline Inspection and Request for Information Report 05000315/2022002 ML21307A3352021-11-0303 November 2021 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Final RAI - License Amendment Request Regarding Containment Water Level Instrumentation ML21215A1242021-08-0303 August 2021 Information Request to Support Upcoming Temporary Instruction 2515/194 Inspection; Inspection Report 05000315/2021013; 05000316/2021013 ML21140A3052021-05-20020 May 2021 NRR E-mail Capture - Final RAI - D.C. Cook 1 & 2 - Relief Request ISIR-4-11, Impractical Examinations for the Fourth 10-Year ISI Interval ML21049A2682021-02-16016 February 2021 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit No. 2 - Final RAI - License Amendment Request for One-Time Extension Containment Type a ILRT ML21026A3472021-01-26026 January 2021 NRR E-mail Capture - Final RAI - D.C. Cook 1 & 2 - Relief Request REL-PP2 for Pump and Valve IST Fifth 10-year Interval IR 05000315/20200112020-09-17017 September 2020 Information Request to Support Upcoming Temporary Instruction 2515/194 Inspection; Inspection Report 05000315/2020011; 05000316/2020011 ML20181A4122020-06-29029 June 2020 NRR E-mail Capture - Final RAI - D.C. Cook 1 - One-Time Extension, Containment Type a ILRT Frequency ML20232B4562020-04-27027 April 2020 Request for Supporting Information for the D.C. Cook SPRA Audit Review - Fragility Questions IR 05000315/20200202020-04-10010 April 2020 Units 1 and 2 - Information Request for NRC Triennial Evaluation of Changes, Tests, and Experiments (50.59) Baseline Inspection 05000315/2020020 and 05000316/2020020 ML20232B4432020-03-25025 March 2020 Request for Supporting Information for the D.C. Cook SPRA Audit Review - Plant Response Model Questions ML19267A1362019-09-24024 September 2019 NRC Information Request (September 23, 2019) - IP 71111.08 - DC Cook U2 - Documents Selected for Onsite Review (DRS-M.Holmberg) ML19204A0962019-07-23023 July 2019 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Request for Additional Information Related to Unit 2 Leak Before Break Analysis and Deletion of Containment Humidity Monitors for Unit Nos. 1 and 2 ML19211C3032019-07-0303 July 2019 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 & 2 - Request for Additional Information Related to LAR to Address NSAL-15-1 ML19084A0002019-03-20020 March 2019 NRR E-mail Capture - Resubmitted: Draft Request for Additional Information DC Cook Unit 1 - Leak-Before-Break LAR ML19072A1432019-03-12012 March 2019 NRR E-mail Capture - Resubmitted: Draft Request for Additional Information DC Cook Unit 1 - Leak-Before-Break LAR ML19011A3512019-01-11011 January 2019 NRR E-mail Capture - Request for Additional Information DC Cook Unit 1 Leak Before Break Amendment ML18313A0802018-11-0808 November 2018 NRR E-mail Capture - D.C. Cook Units 1 and 2 - RAI for RPV Threads in Flange Alternative ML18263A1542018-09-14014 September 2018 NRR E-mail Capture - D.C. Cook Unit No. 1 - RAI for Leak-Before-Break LAR ML18204A3722018-07-19019 July 2018 NRR E-mail Capture - D.C. Cook Unit No. 1 - RAI for Leak-Before-Break LAR ML18143B6292018-05-29029 May 2018 Dtf. RAI ML18142B5312018-05-29029 May 2018 Request for Additional Information Concerning 2017 Decommissioning Funding Status Report ML18060A0212018-02-28028 February 2018 Enclosurequest for Additional Information (Request for Additional Information Regarding Indiana Michigan Power Company'S Decommissioning Funding Update for Donald C Cook Nuclear Plant Units 1 and 2 ISFSI) ML18043A0092018-02-0909 February 2018 NRR E-mail Capture - DC Cook, Unit 2 - Request for Additional Information Regarding Reactor Vessel Internals Again Management Program ML17304A0102017-11-0101 November 2017 Unit Nos.1 and 2 - Request for Additional Information Regarding Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC Nos. MF9444 and MF9445; EPID L-2016-LRC-0001) ML17249A7492017-08-28028 August 2017 E-Mail Sent August 28, 2017, Request for Information for Donald C. Cook Nuclear Power Plant, Unit 1 (Part B); Inspection Report 05000315/2017004 (Msh) ML17108A7772017-04-18018 April 2017 17 Donald C. Cook Nuclear Power Plant, Unit 1 - Notification of NRC Baseline Inspection and Request for Information (05000315/2017003; 05000316/2017003) (Msh) ML17068A0652017-03-0808 March 2017 Ltr 03/08/17 Donald C. Cook Nuclear Power Plant, Unit 2 - Information Request for an NRC Post-Approval Site Inspection for License Renewal 05000316/2017009 (Bxj) ML17027A0192017-01-26026 January 2017 NRR E-mail Capture - D.C. Cook Units 1 and 2 - RAI Regarding LAR to Revise TS 5.5.14 (MF8483 and MF8484) ML16211A0152016-08-0101 August 2016 Follow-Up Request for Additional Information Regarding License Amendment Request to Relocate Surveillance Frequencies to Licensee Control IR 05000315/20160042016-07-11011 July 2016 Donald C. Cook Nuclear Power Plant, Unit 2 - Notification of NRC Inspection and Request for Information; Inspection Report 05000315/2016004; 05000316/2016004 ML16193A6542016-07-11011 July 2016 Notification of NRC Inspection and Request for Information; Inspection Report 05000315/2016004; 05000316/2016004 ML16154A1822016-06-0909 June 2016 Request for Additional Information Regarding License Amendment Request to Relocate Surveillance Frequencies to Licensee Control (CAC Nos. MF7114 and MF7115) ML16127A0792016-05-11011 May 2016 Request for Additional Information Regarding License Amendment Request to Relocate Surveillance Frequencies to Licensee Control ML16025A0552016-01-22022 January 2016 Ltr. 01/22/16 Donald C. Cook Nuclear Power Plant, Units 1 and 2 - Request for Information for an NRC Pilot Design Bases Inspection on the Implementation of the Environmental Qualification Program Inspection Report 05000315/2016008; 05000316 ML15267A6832015-10-0505 October 2015 Second Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.1 ML15231A5542015-08-18018 August 2015 Ltr. 08/18/15 Donald C. Cook Nuclear Power Plant, Units 1 and 2 - Request for Information for an NRC Triennial Pilot Baseline Component Design Bases Inspection (Inspection Report 05000315/2015008; 05000316/2015008) (Axd) ML15225A5772015-08-13013 August 2015 Information Request to Support Upcoming Problem Identification and Resolution Inspection at D.C. Cook, Units 1 and 2 ML15163A1672015-06-15015 June 2015 Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.1 ML15149A3832015-05-28028 May 2015 Information Request to Support NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection (Mxg) ML15119A3392015-05-0505 May 2015 Follow-up Request for Additional Information Concerning the Reactor Vessel Internals Aging Management Program Submittal ML15055A5702015-02-24024 February 2015 Cyber Security RFI Temporary Instruction 2201/004 ML15022A1532015-01-21021 January 2015 Dccook ISI Request for Information ML14363A4912015-01-16016 January 2015 DC Cook Nuclear Plant, Units 1 and 2 - Supplemental Information Needed for Acceptance of Requested Licensing Action to Adopt TSTF-490, Rev.0, Deletion of E-Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Sp ML14246A4992014-08-26026 August 2014 NRR E-mail Capture - Donald C. Cook Nuclear Plant, Units 1 and 2 - Draft Requests for Additional Information (Scvb) Change to TS 5.5.14 by Adopting NEI 94-01, Revision 3-A ML14135A3202014-06-0606 June 2014 Request for Additional Information Concerning the Reactor Vessel Internals Afing Management Program Submittal 2023-12-19
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 11, 2016 Mr. Joel P. Gebbie Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, Ml 49106
SUBJECT:
DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO RELOCATE SURVEILLANCE FREQUENCIES TO LICENSEE CONTROL (CAC NOS. MF7114 AND MF7115)
Dear Mr. Gebbie:
By letter dated November 19, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15328A469), as supplemented by letter dated February 4, 2016 (ADAMS Accession No. ML16039A240), Indiana Michigan Power Company (l&M, the licensee) submitted a license amendment request (LAR) for the Donald C. Cook Nuclear Plant (CNP),
Units 1 and 2. The proposed changes are consistent with the NRG-approved Technical Specifications Task Force (TSTF) Traveler, TSTF-425, Revision 3, "Relocate Surveillance Frequencies to Licensee Control - [Risk Informed Technical Specifications Task Force] Initiative Sb." The proposed change would relocate surveillance frequencies to a licensee controlled program, the Surveillance Frequency Control Program.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the subject submittal, as supplemented, and has determined that additional information is needed to complete the review, as described in the enclosed request for additional information (RAI). The draft RAI was sent to l&M via electronic mail on April 21, 2016. The NRC staff clarified the draft RAI in a conference call conducted on May 3, 2016. A response to this RAI is expected by June 17, 2016.
J. Gebbie Please feel free to contact me at (301) 415-2846 if you have any questions or concerns.
Sincerely, Allison W. Dietrich, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316
Enclosure:
Request for Additional Information cc: Distribution via ListServ
REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO RELOCATE SURVEILLANCE FREQUENCIES TO LICENSEE CONTROL DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-315 AND 50-316 CAC NOS. MF7114 AND MF7115 RAl-PRA-1 Pre-Initiators Internal Event Probabilistic Risk Assessment (IEPRA) Facts & Observations (F&Os) associated with Supporting Requirements HR-A2, HR-A3, HR-81, HR-82, and HR-C2 find that pre-initiator events that could have an impact on the probabilistic risk assessment (PRA) were screened from the analysis. The dispositions to these F&Os explain that the impact of these findings will be addressed in accordance with Nuclear Energy Institute (NEI) 04-10, Section 4, Step 14.
NEI 04-10 allows a sensitivity study to be performed to determine the significance of modeling uncertainty "by changing the unavailability terms for PRA basic events that correspond to Structure Systems and Components (SSCs) being evaluated." It is not clear how the sensitivity study would be applied given that pre-initiator events are Human Failure Events (HFEs) rather than SSC failure events. The factor of three approximation allowed in the sensitivity study for the variance case is based on the difference in reliability between the mean and 95th percentile for typical equipment reliability distributions. It is unknown how the Donald C. Cook Nuclear Plant (CNP), Units 1 and 2, plant-specific pre-initiator distributions compare to equipment distributions.
- Given that the failure distributions for pre-initiators could be much different from equipment distributions, explain how the sensitivity study allowed for SSCs by NEI 04-10 can be properly applied to Human Error Probabilities (HEPs) associated with pre-initiators or the equipment affected by the pre-initiators.
RAl-PRA-2 Human Reliability Analysis (HRA) Incompleteness A number of F&O dispositions state that deviations from the supporting requirements (HR-D3, HR-G6, HR-11, and HR-12) were not important to the application. The F&O associated with HR-D3 finds that Performance Shaping Factors were not adequately addressed. The F&O associated with HR-G6 found the HRA consistency check insufficient. The F&Os associated with HR-11 and HR-12 found the HRA documentation inadequate to support PRA upgrades, PRA applications, and peer review. Considering the licensee's assessment of the F&Os and their disposition for this license amendment request (LAR), it does not appear that the licensee's Enclosure
HRA was complete at the time of the peer review. Two options are available for addressing this issue.
- a. Demonstrate quantitatively that the contribution to Core Damage Frequency (CDF)/large Early Release Frequency (LERF) from HRA for those basic events potentially affected by the requested changes in surveillance test intervals (STls) is negligible; or
- b. Conduct a focused-scope peer review for the HR technical element based on the enhancements made since the 2015 peer review, and adequately disposition any remaining or new F&Os.
RAl-PRA-3 HRA Inadequacies to be Addressed with a Sensitivity Study IEPRA F&Os associated with Supporting Requirements HR-E3 and HR-GS found inadequacies in the HRA that could impact PRA results due to the lack of operator interviews to confirm interpretation of procedures, and the lack of a sufficient bases for the estimation of operator response times. The dispositions to these F&Os explain that the impact of these findings will be addressed in accordance with NEI 04-10, Section 4, Step 14. NEI 04-10 allows a sensitivity study to be performed to determine the significance of modeling uncertainty "by changing the unavailability terms for PRA basic events that correspond to SSCs being evaluated." It is not clear how the sensitivity study meant for SSCs would be applied, given that the findings are associated with input to the development of HEPs. The factor of three approximation allowed in the sensitivity study for the variance case is based on the difference in reliability between the mean and 95th percentile for typical equipment reliability distributions. It is unknown how CNP plant-specific failure distribution for HFEs compares to equipment distributions.
- Given that the failure distributions for HEPs could be much different from equipment distributions, explain how the sensitivity study allowed for SSCs by NEI 04-10 can be properly applied to HFEs or equipment affected by HFEs.
RAl-PRA-4 PRA Update Commitments In the dispositions of the IEPRA, Internal Flooding PRA (IFPRA), and Fire PRA (FPRA) F&Os associated with Supporting Requirements SY-810, HR-G4, DA-C15, IFSN-A16, IFSN-A17, IFEV-A8, IFQU-A3, LE-E1, PRM-814, and PRM-815, commitments were made to perform updates to the PRA in order to resolve the F&Os prior to implementation of the risk-informed surveillance frequency control program (SFCP). It appears that these PRA updates are needed to support future STI evaluations. For the F&O associated with SY-810, the disposition states that a more detailed PRA model is needed prior to program implementation. For the F&O associated with HR-G4, the disposition indicates that the time available for operator actions will be updated based on current Modular Accident Analysis Program (MAAP) analyses and other information prior to program implementation. For the F&Os associated with IFSN-A16, IFSN-A17, IFEV-A8, and IFQU-A3, it appears that the committed updates are needed because
scenarios currently excluded will be incorporated into the PRA. For the F&O associated with DA-C15, the disposition states that credit for the cited repair will be removed. For the F&Os associated with LE-E 1, PRM-B 14, and PRM-B 15, operator actions and bypass pathways will be reviewed and incorporated into the PRA as needed and LERF documentation will be completed for the Fire PRA prior to program implementation.
In addition to the commitments made in the F&O dispositions, Section 3 of the LAR states that as part of the STI evaluations, each supporting requirement will be re-examined, and those not resolved as meeting CC-II will be evaluated in a sensitivity study using guidance from NEI 04-10, Section 4, Step 14. This statement implies that PRA updates needed to resolve F&Os may not yet be implemented at the time an STI evaluation is performed.
- a. Explain how the F&Os cited above, which have the potential to impact the application, have been resolved. Alternatively, explain why the F&Os are not important to this application.
- b. Similar to the request made in RAl-PRA-1 and RAl-PRA-3, for F&Os that will be evaluated using the sensitivity study allowed by NEI 04-10, explain how the excluded and not-yet updated PRA modeling will be evaluated for the F&Os not directly associated with an SSC (i.e., MAAP runs that are not yet updated to establish the time available for operator actions, and unconfirmed door flood loading bases for the IFPRA).
RAl-PRA-5 Use of Surveillance Data Based on the IEPRA F&O associated with Supporting Requirement DA-C10 and its disposition, it appears that surveillance tests may not have been reviewed for use in determining the demand count of plant-specific components. Considering that several component failure rates could be affected, it is not apparent how the licensee concluded that the resolution of this finding would have only a "minor or negligible" impact on the PRA.
- Explain how Supporting Requirement DA-C10 was met.
RAl-PRA-6 F&Os for LE Supporting Requirements Met at only CC-I with Inadequate Dispositions A number of the dispositions to F&Os associated with LERF supporting requirements that meet CC-I provide minimal information without sufficient detail to determine the extent and validity of the disposition (F&Os for Supporting Requirements LE-C1, LE-C2, LE-C5, LE-C10, LE-C11, LE-C12, LE-C13, and LE-E2). The dispositions to each of these F&Os state "CC-I is considered to be sufficient to support applications for this [supporting requirement]." The F&O dispositions do not explain why the PRA modeling is sufficient to support the SFCP.
- Explain how the modeling associated with each of these supporting requirements is sufficient to support the SFCP, providing sufficient detail to support the explanation.
RAl-PRA-7 Overestimation of STls because of Conservative Modeling A number of dispositions to F&Os concerning LERF explain that the modeling relevant to a supporting requirement is conservative (i.e., LE-C2, LE-C5, LE-01, LE-02, and LE-03). For many other supporting requirements, F&Os indicate that plant containment system functionality that could have been credited was not credited in the PRAs. Conservatisms in LERF related system modeling can lead to overestimation of STls, particularly for STI evaluations performed for containment systems that were excluded from the modeling.
- Explain how conservative modeling of LERF will not lead to overestimation of certain ST ls.
RAl-PRA-8 Modeling Basis for Reactor Coolant Pump (RCP) Seals Enclosure 3, Section 6.1 of the LAR states that, "[t]he current PRA model utilizes the Pressurized Water Reactor Owners Group guidance (Reference 11) for PRA modeling of the shutdown seals, supported by the Westinghouse Owners Group 2000 RCP seal failure model (Reference 12), both of which are industry consensus models." Reference 11 is the PWROG-14001-P, PRA Model forthe Generation Ill Westinghouse Shutdown Seal, Revision 1, July 2014. Reference 12 is WCAP-15603, WOG 2000 Reactor Coolant Pump Seal Leakage Model for Westinghouse Pressurized Water Reactors, Revision 1-A, June 2003. The RCP seal models in Reference 11 and Reference 12 are two different RCP seal models with major differences in the probability and magnitude of seal failure.
- a. Which RCP seals are currently installed at CNP?
- b. Which RCP seal model is in the current PRA, the model in Reference 11 or the model in Reference 12?
- c. The model in Reference 12 has been accepted by the staff, but the model in Reference 11 is still under review. The model in Reference 11 should not be used to support changes to surveillance intervals until an accepted version is available. Clarify how the RCP seal model will be used in surveillance interval-related calculations until an accepted version of Reference 11 is available.
RAl-PRA Deleted RAl-PRA-10 Peer Review of IEPRA and IFPRA Section 3 of the LAR states that a peer review of the IEPRA and IFPRA was conducted in July 2015 against ASME RA-Sa-2009 and RG 1.200, Rev. 2, and that this peer review supersedes previous peer reviews. The LAR does not describe this peer review or provide
justification for concluding that all previous peer reviews are superseded, including previously open F&Os.
- a. Explain how the peer review meets the requirements of Section 1-6 of the PRA Standard ASME RA-Sa-2009, and Section 2.2 of RG 1.200, Rev. 2, including NRC staff clarifications and qualifications.
- b. Describe the scope of the peer review and explain why it is considered to supersede all previous peer reviews.
RAl-PRA-11 External Hazards , Section 4.2 of the LAR does not explain how the risk from external hazards evaluated in the CNP Individual Plant Examination of External Events is updated to reflect new information when used in performing a qualitative or bounding analysis in support of STI extension evaluations in accordance with NEI 04-10, Section 4, Step 10.
- Discuss the process for incorporating new information into these qualitative or bounding analyses, and explain how this process is sufficient to support the SFCP and the as-built as-operated plant configuration. Specifically address high winds, including updated tornado and hurricane climatology, external flooding, and seismic events, including updated site-specific ground motion response spectra.
ML16127A079 *via memorandum OFFICE DORL/LPL3-1/PM DORL/LPL3-1/LA DE/EE EB/BC* DORL/LPL3-1/BC DORL/LPL3-1 /PM DWrona NAME ADietrich MHenderson SRosenberg ADietrich (MOrenak for)
DATE 5/9/2016 5/9/2016 4/11/2016 5/11/2016 5/11/2016