|
---|
Category:Letter
MONTHYEARML23180A1512023-06-29029 June 2023 LLC, Request for Exemption to the Reporting Requirements of 10 CFR 50.46(a)(3) ML21102A3072021-04-15015 April 2021 OEDO-21-00155 - Lessons-Learned from the Design Certification Review of the NuScale Power, LLC, Small Modular Reactor ML21050A4312021-02-19019 February 2021 LLC - Lessons-Learned from the Design Certification Review of the NuScale Power, LLC Small Modular Reactor ML20247J5642020-09-11011 September 2020 Standard Design Approval for the NuScale Power Plant Based on the NuScale 600 Standard Plant Design Certification Application ML20231A8042020-08-28028 August 2020 Final Safety Evaluation Report for the NuScale Standard Plant Design ML20224A4602020-08-25025 August 2020 OEDO-20-00292-Response to the Advisory Committee on Reactor Safeguards Letter on NuScale Power, LLC, Report on the Safety Aspects of the NuScale Small Modular Reactor ML20231A5982020-08-25025 August 2020 OEDO-20-00285_NuScale Area of Focus - Boron Redistribution ML20210M8902020-07-29029 July 2020 Area of Focus - Boron Redistribution ML20195A5872020-07-13013 July 2020 LLC - Submittal of Draft Operator Licensing and Examination Standard for NuScale Small Modular Reactors ML20195C7662020-07-13013 July 2020 LLC Request for Standard Design Approval Based on the NuScale Standard Plant Design Certification Application ML20192A3262020-07-10010 July 2020 LLC, Submittal of Environmental Report: Revision Status ML20198M3932020-07-0202 July 2020 LLC Submittal of Revised Packing Slip for Submittal of the NuScale Standard Plant Design Certification Application, Revision 4.1, Dated June 19, 2020 ML20174A3472020-07-0101 July 2020 OEDO-20-00220 - Area of Focus - Probabilistic Risk Assessment and Emergency Core Cooling System Valve Performance ML20184A2872020-07-0101 July 2020 LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topic - Boron Redistribution and General Design Criterion 33, PM-0720-70785, Revision 0 ML20181A4322020-06-22022 June 2020 Final SER for NuScale TR-0516-49416 NON-Loss-of-Coolant Analysis Model, Rev 3 (Letter) ML20181A2702020-06-22022 June 2020 Final SER for NuScale TR-0516-49422 Loss-of-Coolant Analysis Model, Rev 2 (Letter) ML20198M3922020-06-19019 June 2020 LLC - Submittal of the NuScale Standard Plant Design Certification Application, Revision 4.1 ML20171A7312020-06-19019 June 2020 LLC, Submittal of Riser Flow Hole Methodology and Associated Changes to Final Safety Analysis Report Incorporating Its Use ML20157A2232020-06-0303 June 2020 Letter to NuScale Requesting -A for TR-0716-50350 ML20150C5172020-05-29029 May 2020 LLC Submittal of Presentation Materials Entitled NRC Public Meeting Presentation: Boron Redistribution and Associated Design and DCA Changes, PM-0620-70336, Revision 0 ML20150E1772020-05-29029 May 2020 LLC - Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topic - Extended Dhrs Operation and RCS Boron Redistribution (Closed Session), PM-0620-70243, Revision 0 ML20150C8812020-05-29029 May 2020 LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topic - Boron Redistribution and Associated Design and DCA Changes, PM-0620-70244, Revision 0 ML20149M1192020-05-28028 May 2020 LLC Summary of Impacts to Erai 8930 Response and Discussion on the Exemption from General Design Criterion 33 ML20141L8082020-05-20020 May 2020 LLC Submittal of Containment Response Analysis Methodology Technical Report, TR-0516-49084, Revision 3 ML20141N0122020-05-20020 May 2020 LLC Submittal of Changes to Final Safety Analysis Report, Section 6.2, Containment Systems, Section 6.3, Emergency Core Cooling System, and Technical Report TR-0516-49084, Containment Response Analysis Methodology Technical Report ML20141M7642020-05-20020 May 2020 LLC Submittal of Nuclear Steam Supply System Advanced Sensor Technical Report, TR-0316-22048, Revision 3 ML20141L7872020-05-20020 May 2020 LLC, Submittal of Second Updates to Standard Plant Design Certification Application, Revision 4 ML20141L8162020-05-20020 May 2020 LLC, Submittal of Long-Term Cooling Methodology, TR-0916-51299, Revision 3 ML20141M1142020-05-20020 May 2020 LLC Submittal of NuScale Instrument Setpoint Methodology Technical Report, TR-0616-49121, Revision 3 ML20141L8042020-05-20020 May 2020 LLC Submittal of Technical Specifications Regulatory Conformance and Development, TR-1116-52011, Revision 4 ML20128J3162020-05-18018 May 2020 OEDO-20-00167 - Response to the ACRS Letter on Combustible Gas Monitoring ML20133K0882020-05-12012 May 2020 LLC, Submittal of Presentation Materials Entitled Public Meeting Presentation: Topic - Emergency Core Cooling System (ECCS) Boron Distribution (Closed Session), PM-0420-69512, Revision 0 ML20133J9142020-05-11011 May 2020 LLC Submittal of Presentation Materials Entitled Public Meeting Presentation: Topic - Emergency Core Cooling System (ECCS) Boron Distribution, PM-0420-69511, Revision 0 ML20112F4552020-05-0101 May 2020 LLC, Design Certification Application Phases 5 and 6 Review Status ML20107F8492020-05-0101 May 2020 OEDO-2000140 - NuScale Area of Focus - Helical Tube Steam Generator Design ML20104A0792020-04-27027 April 2020 OEDO-20-00115 - Safety Evaluation Report for Topical Report TR-0516-49416, Revision 2, Non-Loss-of-Coolant Accident Analysis Methodology ML20099H0802020-04-0808 April 2020 LLC - Submittal of Presentation Materials Entitled NRC Public Meeting: Revisions to Nuscale'S EPZ Sizing Methodology Topical Report, PM-0420-69598, Revision 0 ML20098G2372020-04-0707 April 2020 Nuscale Power, LLC Submittal of Remaining Closure Items for the Emergency Core Cooling System Valve Failure Mode Effects Analysis Audit Items ML20097F1922020-04-0606 April 2020 Nuscale Power, LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: Nuscale Topic - Hydrogen/Oxygen Monitoring, PM-0420-69518, Revision 0 ML20094H6742020-04-0303 April 2020 LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation NuScale Topic-Probabilistic Risk Assessment with a Focus on Emergency Core Cooling System Analysis PM-0420-69559, Revision 0 ML20092L8992020-04-0101 April 2020 LLC - Submittal of Updates to Standard Plant Design Certification Application, Revision 4 ML20072M6682020-03-30030 March 2020 Response to NuScale Letter Dated February 24, 2020, on Planned SDA Application Content ML20072H3332020-03-0909 March 2020 LLC - Submittal of Presentation Materials Entitled Public Meeting Presentation: Topic - Emergency Core Cooling System (ECCS) Boron Distribution, PM-0320-69218, Revision 0 ML20057D9002020-03-0606 March 2020 Submittal of Errata to Final SE for NuScale Power, LLC TR-1010-859-NP-A, Quality Assurance Program Description for the NuScale Power Plant ML20062F7262020-03-0505 March 2020 Request for Withholding Information from Public Disclosure for Nuscale Power, LLC Letter Public ML20069A1572020-03-0404 March 2020 LLC - Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topical Report-Rod Ejection Accident Methodology, PM-0320-69146, Revision 0 ML20069A1772020-03-0404 March 2020 LLC - Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topical Report-Non-Loss-of-Coolant Accident, PM-0320-69141, Revision 0 ML20069A9632020-03-0404 March 2020 LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topical Report, Loss-of-Coolant Accident Evaluation Model, PM-0320-69138, Revision 0 ML20066G2802020-03-0303 March 2020 LLC, Submittal of Presentation Materials Entitled ACRS Subcommittee Presentation: NuScale Topic - Hydrogen Monitoring, PM-0220-69071, Revision 0 ML20066G2882020-02-28028 February 2020 LLC Submittal of Presentation Materials Titled ACRS Full Committee Presentation: NuScale - Steam Generator Design (Closed Session), PM-0220-69053, Revision 0 2023-06-29
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARRAIO-0420-69855, LLC, Submittal of Corrected Response to NRC Request for Additional Information No. 284 (Erai No. 9225) on the NuScale Design Certification2020-04-30030 April 2020 LLC, Submittal of Corrected Response to NRC Request for Additional Information No. 284 (Erai No. 9225) on the NuScale Design Certification ML19332A1202019-11-27027 November 2019 LLC Supplemental Response to NRC Request for Additional Information No. 484 (Erai No. 8930) on the NuScale Design Certification Application ML19304B4712019-10-31031 October 2019 LLC Supplemental Response to NRC Request for Additional Information No. 466 (Erai No. 9482) on the NuScale Design Certification Application ML19296D8052019-10-23023 October 2019 LLC Response to NRC Request for Additional Information No. 526 (Erai No. 9719) on the NuScale Design Certification Application ML19283E5302019-10-10010 October 2019 LLC Supplemental Response to NRC Request for Additional Information No. 522 (Erai No. 9681) on the NuScale Design Certification Application ML19260G7352019-10-0707 October 2019 Summary of Public Meeting with NuScale to Discuss Response to RAI 9681 ML19266A5872019-09-23023 September 2019 LLC Supplemental Response to NRC Request for Additional Information No. 518 (Erai No. 9659) on the NuScale Design Certification Application ML19262G9742019-09-19019 September 2019 LLC - Submittal of Changes to Final Safety Analysis Report, Tier 1, Section 3.11, Reactor Building and Section 3.13, Control Building, and Tier 2, Section 3.8.4, Design of Category I Structure and Section 14.3, Certified ... ML19262G5762019-09-19019 September 2019 LLC - Submittal of Changes to Final Safety Analysis Report, Section 14.2, Initial Plant Test Program, Table 14.2-2, Pool Cleanup Systems Test #2, and Table 14.2-50, Module Assembly Equipment Test #50 ML19259B8102019-09-16016 September 2019 LLC Supplemental Response to NRC Request for Additional Information No. 205 (Erai No. 9044) on the NuScale Design Certification Application ML19259A0922019-09-16016 September 2019 LLC Response to NRC Request for Additional Information No. 525 (Erai No. 9705) on the NuScale Design Certification Application ML19238A3722019-08-26026 August 2019 LLC Supplemental Response to NRC Request for Additional Information No. 197 (Erai No. 9051) on the NuScale Design Certification Application ML19238A3662019-08-23023 August 2019 LLC - Response to NRC Request for Additional Information No. 523 (Erai No. 9682) on the NuScale Design Certification Application ML19215A0032019-08-0202 August 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 202 (Erai No. 8911) on the NuScale Design Certification Application ML19215A0062019-08-0202 August 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 441 (Erai No. 9485) on the NuScale Design Certification Application ML19212A7622019-07-31031 July 2019 LLC Response to NRC Request for Additional Information No. 523 (Erai No. 9682) on the NuScale Design Certification Application ML19212A3752019-07-31031 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 483 (Erai No. 9516) on the NuScale Design Certification Application ML19212A7992019-07-31031 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 427 (Erai No. 9408) on the NuScale Design Certification Application ML19212A6892019-07-31031 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 205 (Erai No. 9044) on the NuScale Design Certification Application ML19210D1592019-07-29029 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 401 (Erai No. 9447) on the NuScale Design Certification Application ML19210D7342019-07-29029 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 520 (Erai No. 9642) on the NuScale Design Certification Application ML19210E1462019-07-29029 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 197 (Erai No. 9051) on the NuScale Design Certification Application ML19207B3812019-07-26026 July 2019 LLC - Response to NRC Request for Additional Information No. 427 (Erai No. 9408) on the NuScale Design Certification Application ML19207A5342019-07-26026 July 2019 LLC - Response to NRC Request for Additional Information No. 523 (Erai No. 9682) on the NuScale Design Certification Application ML19207B8522019-07-25025 July 2019 LLC Response to NRC Request for Additional Information No. 194 (Erai No. 8884) on the NuScale Design Certification Application ML19203A3152019-07-22022 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 325 (Erai No. 9268) on the NuScale Design Certification Application ML19203A3212019-07-22022 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 333 (Erai No. 9282) on the NuScale Design Certification Application ML19203A3092019-07-22022 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 54 (Erai No. 8837) on the NuScale Design Certification Application ML19203A3422019-07-22022 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 154 (Erai No. 8938) on the NuScale Design Certification Application ML19200A2482019-07-19019 July 2019 LLC Response to NRC Request for Additional Information No. 522 (Erai No. 9681) on the NuScale Design Certification Application ML19200A2082019-07-19019 July 2019 LLC - Response to NRC Request for Additional Information No. 524 (Erai No. 9691) on the NuScale Design Certification Application ML19199A1172019-07-18018 July 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 484 (Erai No. 8930) on the NuScale Design Certification Application ML19198A3252019-07-17017 July 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 249 (Erai No. 9135) on the NuScale Design Certification Application ML19196A3682019-07-15015 July 2019 LLC Response to NRC Request for Additional Information No. 516 (Erai No. 9647) on the NuScale Design Certification Application ML19191A2202019-07-10010 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 197 (Erai No. 9051) on the NuScale Design Certification Application ML19184A6152019-07-0303 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 386 (Erai No. 9316) on the NuScale Design Certification Application ML19176A5802019-06-25025 June 2019 LLC Supplemental Response to NRC Request for Additional Information No. 232 (Erai No. 9113) on the NuScale Design Certification Application ML19170A3702019-06-19019 June 2019 LLC Supplemental Response to NRC Request for Additional Information No. 232 (Erai No. 9113) on the NuScale Design Certification Application ML19168A2442019-06-17017 June 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 325 (Erai No. 9268) on the NuScale Design Certification Application ML19164A1452019-06-13013 June 2019 LLC - Submittal of Containment Response Analysis Methodology Technical Report, TR-0516 -49 08 4, Revision 1 ML19157A3262019-06-0606 June 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 232 (Erai No. 9113) on the NuScale Design Certification Application ML19154A6222019-06-0303 June 2019 LLC Supplemental Response to NRC Request for Additional Information No. 202 (Erai No. 8911) on the NuScale Design Certification Application ML19154A6052019-06-0303 June 2019 LLC Response to NRC Request for Additional Information No. 514 (Erai No. 9645) on the NuScale Design Certification Application ML19151A8372019-05-31031 May 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 377 (Erai No. 9380) on the NuScale Design Certification Application ML19140A4592019-05-20020 May 2019 LLC Supplemental Response to NRC Request for Additional Information No. 401 (Erai No. 9447) on the NuScale Design Certification Application ML19137A2902019-05-17017 May 2019 LLC Supplemental Response to NRC Request for Additional Information No. 156 (Erai No. 9031) on the NuScale Design Certification Application ML19137A2872019-05-15015 May 2019 LLC Response to NRC Request for Additional Information No. 519 (Erai No. 9656) on the NuScale Design Certification Application ML19126A2942019-05-0606 May 2019 LLC Supplemental Response to NRC Request for Additional Information No. 26 (Erai No. 8840) on the NuScale Design Certification Application ML19122A5092019-05-0202 May 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 494 (Erai No. 9548)on the Design Certification Application ML19121A6002019-05-0101 May 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 202 (Erai No. 8911) on Design Certification Application 2020-04-30
[Table view] |
Text
RAIO-0118-57981 January 02, 2018 Docket No.52-048 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738
SUBJECT:
NuScale Power, LLC Response to NRC Request for Additional Information No.
278 (eRAI No. 9123) on the NuScale Design Certification Application
REFERENCE:
U.S. Nuclear Regulatory Commission, "Request for Additional Information No.
278 (eRAI No. 9123)," dated November 03, 2017 The purpose of this letter is to provide the NuScale Power, LLC (NuScale) response to the referenced NRC Request for Additional Information (RAI).
The Enclosure to this letter contains NuScale's response to the following RAI Question from NRC eRAI No. 9123:
18-12 This letter and the enclosed response make no new regulatory commitments and no revisions to any existing regulatory commitments.
If you have any questions on this response, please contact Steven Mirsky at 240-833-3001 or at smirsky@nuscalepower.com.
Sincerely, Zackary W. Rad Di Director, R l Regulatory Aff i Affairs NuScale Power, LLC Distribution: Gregory Cranston, NRC, OWFN-8G9A Samuel Lee, NRC, OWFN-8G9A Demetrius Murray, NRC, OWFN-8G9A : NuScale Response to NRC Request for Additional Information eRAI No. 9123 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvalis, Oregon 97330, Office: 541.360.0500, Fax: 541.207.3928 www.nuscalepower.com
RAIO-0118-57981 :
NuScale Response to NRC Request for Additional Information eRAI No. 9123 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvalis, Oregon 97330, Office: 541.360.0500, Fax: 541.207.3928 www.nuscalepower.com
Response to Request for Additional Information Docket No.52-048 eRAI No.: 9123 Date of RAI Issue: 11/03/2017 NRC Question No.: 18-12 REGULATORY BASIS Title 10 of the Code of Federal Regulations (10 CFR) Section 52.47(a)(8) requires an applicant for a design certification to provide a final safety analysis report (FSAR) that must include the information necessary to demonstrate compliance with any technically relevant portions of the Three Mile Island requirements set forth in 10 CFR 50.34(f), except paragraphs (f)(1)(xii),
(f)(2)(ix), and (f)(3)(v). Specifically, 10 CFR 50.34, in part, requires that applicants design the main control room representing state-of-the-art human factors principles.
Chapter 18, Human Factors Engineering, of NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, identifies NUREG-0711, "Human Factors Engineering Program Review Model as the source of acceptance criteria the staff uses to evaluate whether an applicant meets the regulation.
BACKGROUND INFORMATION HUMAN FACTORS REGULATORY GUIDANCE IN NUREG-0711 NUREG-0711 provides acceptance criteria for 12 human factors program elements that the NRC considers to be part of an acceptable human factors program. The various analyses described in NUREG-0711 help to form a systematic and scientific basis for different design and evaluation assumptions used in the NUREG-0711 process. For instance Section 11.4.3.3, Validation Testbeds, Criterion 1 states, The applicants testbed represent completely the integrated system, and it should include human- system interfaces (HSI) and procedures not specifically required by the test scenarios. The results of analytical processes described in NUREG-0711 such as operating experience review (OER), functional requirements analysis &
function allocation (FRA/FA), task analysis (TA), and treatment of important human actions (TIHA) are inputs to the design of HSI and procedures. Therefore, these activities need to be complete prior to conducting ISV activities in order to ensure adequate test fidelity.
NUREG-0711 PRODUCT SUBMITTALS Each NUREG-0711 program element contains descriptions of appropriate applicant products and submittals. There are two types of submittals described in NUREG-0711: implementation NuScale Nonproprietary
plans and results summary reports (RSRs). The process allows for applicants to submit implementation plans for work that is not yet complete at the time of the design certification application. Implementation plans describe detailed methods that the applicant intends to follow while conducting human factors analysis, design, and evaluation work.
Implementation plans are to be followed by an RSR when the design work is ultimately finished.
Alternatively, an applicant can submit an RSR at the time of the design certification application.
RSRs describe the results of the human factors analyses and design activities along with a summary of the methods used to generate these results.
The NRC expectation for an RSR is that the work associated with a particular NUREG-0711 element should be complete at the time of submittal. NUREG-0711 uses language to specifically call out those areas that must be complete in an RSR using terminology like:
complete, results should be enumerated (which implies that a complete list of results should be provided for review), or use other similar language. For instance, Section 3.3 of NUREG-0711 indicates that an applicant submitting a results summary report should include an enumeration of open issues still being tracked in the HFE issues-tracking system. An understanding of unresolved issues is critical to both the designer and to the regulator while considering design assumptions, human performance evaluation techniques, and other human factors considerations.
DESCRIPTION OF PROBLEM In a letter dated, April 8, 2016, NuScale described a proposed approach to submitting the Chapter 18 portion of the design certification application (DCA). This letter describes the contents of RSRs that were proposed to be submitted as part of the DCA. The letter states, Unless otherwise noted, the contents of the RSRs will be in accordance with the applicable guidance of NUREG-0711 (see ADAMS Accession No. ML16099A270). The letter indicated that RSRs would be provided for most NUREG- 0711 elements at the time of the DCA with exception of the RSR for the human factors verification and validation element which would be submitted prior to the NRC phase 4 review. NRC has accepted this as an acceptable strategy.
NuScale submitted a series of RSRs summarizing the work that has been done to support NUREG-0711 human factors design efforts as part of the DCA. The staff found that some samples of results were provided in the DCA. The staff requested an audit to independently select samples of the results to determine whether the results conformed to the guidance in NUREG-0711.
On May 9-10, 2017, NRC staff conducted an audit of the results of several human factors analyses (OER, FRA/FA, TA, and TIHA) used in support of the Chapter 18 submittal (ADAMS Accession No.ML17181A415). Staff reviewed the contents of several NuScale databases in an attempt to confirm that the sample of results provided in the RSRs were truly representative of a full set of analytical results. Staff identified multiple areas where human factors analyses are not yet complete. Therefore, staff could not yet conclude that the results described in the RSRs are representative of the full set of results (which do not yet exist).
NRC staff discussed the issue with NuScale staff during the audit as well as during a NuScale Nonproprietary
clarification call on June 20, 2017. A schedule to complete all analyses was discussed.
POTENTIAL IMPACT ON PROJECT & NRC REVIEW SCHEDULE Based on the schedule discussion described above, the applicants schedule appears to support the applicants human factors verification and validation activities. This schedule, if adhered to, should ensure that the analyses are complete prior to the integrated system validation (as is expected based on NUREG-0711). It appears as if the applicants project schedule is suitable to meet their needs. However, this strategy poses new potential schedule threats to the NRC review.
- 1. The NRC expected to complete confirmation that the analytical human factors work (OER, FRA/FA, TA, & TIHA) was complete and consistent with NUREG-0711 during the May 2017 audit. Staff were unable to complete this process, therefore a follow-up audit will need to be scheduled when the analyses are complete.
- 2. NRC staff have the option to use open items in the Phase 2 safety evaluation report. As a result of the incomplete human analyses, the staff will need to track many of these as open items into the phase 2 of the review. Open items do not necessarily pose a problem for the review, however many open items that need to be closed late in the review process may require NRC staff to do significant review late in the review process (Phase 4 safety evaluation). Significant issues that arise late in the review may threaten project review schedules.
- 3. The audit (described in point 1) and the closing of open items (described in point 2) will now need to occur within a small window of time just before the Phase 4 technical review due date. NRC resources were already allocated to support verification and validation activities during this time of the review, consistent with the April 8, 2016 letter. Additional NRC resources may be needed to support this increase in workload and/or adjustments to the schedule may need to be made if at some point NuScale can no longer support this schedule due to unforeseen issues.
HOW TO RESOLVE THE ISSUE Conducting an additional audit and using open items in the staff safety evaluation report may provide an acceptable path to success within the scope of the NRC review process. However, additional information is necessary to help the NRC allocate resources to support the unexpected issues with the review.
Specifically:
- 1. The scope of the remaining work should be identified. Provide a list all specific human factors analyses that are not yet completely entered into the corresponding OER, FRA/FA, and TA databases. These analyses should support the assumptions and design decisions used in creating the final MCR design, procedures, and training that will ultimately be used in the ISV. (See figure 1-1 from NUREG-0711 illustrates how the human factors analyses are intended to support the design process.)
- 2. Provide a schedule for the completion of outstanding analysis work which includes all of the items identified in item 1 above. Include expected dates for completion of each NuScale Nonproprietary
NUREG-0711 program element.
- 3. Propose approximate dates for future regulatory interactions which will be conducted by the NRC.
NRC audit(s) of the complete OER, FRA/FA, TA, & TIHA analyses NRC audit of the human factors verification and validation process (staff may also consider HSI design, Staffing and Qualifications, Procedures, and Training at this time)
Potential HED Resolution Audit -staff may need to review the resolutions to issues identified during the ISV Please provide additional information addressing the points listed above.
Please provide additional information addressing the points listed above.
NuScale Response:
Part 1 of the RAI Response The Planning and Analysis portion of the HFE program, as described in NUREG-0711, Figure 1-1, Elements of the HFE programs review model, includes:
HFE Program Management Operating Experience Review (OER)
Functional Requirements Analysis and Function Allocation (FRA/FA)
Task Analysis (TA)
Staffing and Qualification (S&Q)
Treatment of Important Human Actions (TIHA)
All of the analyses related to the elements listed above and in support of licensed operators in the main control room during normal, abnormal, and emergency operating conditions are complete, with the exception of 15 OER items.
The OER database contains a broad scope of events that were evaluated with respect to the NuScale design. Entries that are considered in-scope for this RAI question are those entries that are deemed applicable to the NuScale design and whose evaluation indicates resolution through a physical plant or HSI design solution. For example, an OE item that is addressed by the functionality of the computer-based procedure HSI would be considered in-scope, whereas an OE item that is addressed by training or procedural content would not be considered in-scope since Training Program Development and Procedure Development are COL action items per FSAR Sections 13.2 and 13.5, respectively. Therefore, there may be open items in the OER or HFEITS databases with resolution assigned to the COL applicant, but those entries are not considered in this response.
NuScale Nonproprietary
Part 2 of the RAI Response All required human factors analyses associated with the Planning and Analysis portion of the HFE program are complete, with the exception of 15 OER items. The open OER items will be closed by June 4, 2018.
The following HFE program elements are complete:
HFE Program Management Functional Requirements Analysis and Function Allocation (FRA/FA)
Task Analysis (TA)
Staffing and Qualification (S&Q)
Treatment of Important Human Actions (TIHA)
Human-System Interface Design (HSI Design)
The Human Factors Verification and Validation (HF V&V) element is the final HFE element for which NuScale will submit an RSR. This element is scheduled for completion before 8/28/2019, the beginning of the DCA review Phase 4, with the submittal of the HF V&V RSR.
Part 3 of the RAI Response The following dates are proposed for follow-up audit activities:
NRC audit(s) of the complete OER, FRA/FA, TA, & TIHA analysis - March 5, 2018 NRC audit of the human factors verification and validation process (staff may also consider HSI design, Staffing and Qualifications, Procedures, and Training at this time) -
June 4, 2018 Potential HED Resolution Audit - staff may need to review the resolutions to issues identified during the ISV - October 22, 2018 Impact on DCA:
There are no impacts to the DCA as a result of this response.
NuScale Nonproprietary