NL-20-1417, Vogltle, Units 1 and 2, Response to Request for Additional Information Regarding Risk-Informed Resolution to GSI-191

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Vogltle, Units 1 and 2, Response to Request for Additional Information Regarding Risk-Informed Resolution to GSI-191
ML20352A228
Person / Time
Site: Vogtle  
Issue date: 12/17/2020
From: Gayheart C
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-20-1417
Download: ML20352A228 (12)
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U. S. Nuclear Regulatory Commission NL-20-1417 Page 2

Enclosure:

SNC Response to NRC Request for Additional Information (RAI)

Attachment:

Revised FSAR Markup Pages (for Information Only) cc:

Regional Administrator, Region ll NRR Project Manager - Vogtle 1 & 2 Senior Resident Inspector - Vogtle 1 & 2 State of Georgia Environmental Protection Division RType: CVC7000



























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Enclosure to NL-20-1417 SNC Response to NRC Request for Additional Information (RAI)

E-1 NRC RAI #1

, Section 3.2.7, of the letter dated August 17, 2020, specifies that physical or procedural modifications that affect inputs to the NARWHAL model will be updated periodically. In Section 3.2.5, and in the FSAR markup, the model is excluded specifically as a key element that is described in the FSAR. The NARWHAL model is an integral part of the analysis and replacement with a different model would be complex. Industry and the NRC expended significant resources to provide assurance that the NARWHAL model provides acceptable results. The review and development of NARWHAL included verification and validation of the software. In addition, the software is controlled under a quality assurance program intended to assure that errors in the model are tracked and corrected as necessary. Explain the reason for the statements excluding the tool or program in Section 3.2.5 and 3.2.7 and discuss whether the use of a different tool or program would constitute a change of method that could require NRC approval prior to its use. The NRC acknowledges that the licensee could perform a limited set of calculations outside of the NARWHAL model to evaluate specific scenarios. However, a full analysis may be difficult to perform without using the software.

SNC Response to NRC RAI #1 The markup to the Vogtle Final Safety Analysis Report (FSAR) is updated to clarify that NARWHAL is a key element for the risk-informed analysis. The following changes are made to the FSAR markup:

1. The use of NARWHAL software in the risk-informed analysis is now discussed in the FSAR markup on Page 6A-2 (see Attachment, Insert 1).
2. The statement This requirement applies to the methodology, but not the tool or program used is withdrawn from the response to Limitation/Condition 5 in Enclosure 2 of the LAR (NL-20-0597) and is removed from the FSAR markup on Pages 6A-2 and 6A-3 (see Attachment).
3. On Page 6A-3 of the FSAR markup, a new paragraph is added following the list of key aspects of the risk-informed evaluation to address integrated analysis using NARWHAL and performance of special evaluations (see Attachment, Insert 2).

NRC RAI #2 The list of FSAR references does not include the Vogtle Technical Report or associated NRC staff evaluation, dated September 30, 2019 (ADAMS Accession No. ML19120A469), that provides most of the technical basis for the FSAR text. Please justify not including these documents as the analysis of record in the FSAR.

SNC Response to NRC RAI #2 The Vogtle Technical Report for the July 10, 2018 submittal and the associated NRC staff evaluation are added as References 13 and 14 to the Final Safety Analysis Report (FSAR) markup on Page 6A-11 (see Attachment, Insert 3).

An introductory statement is added referring to these new references in the FSAR markup on Page 6A-1 (see Attachment, Insert 4).

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, Page A2-7, of the letter dated August 17, 2020, does not include any reference to fuel design in the Other GSI-191 Inputs. These parameters may be important when considering design modifications or operability evaluations. Sump Swapover time, Hot-Leg Switchover (HLSO) Time, Alternate Flow Path (AFP) resistance, chemical effects timing, and barrel/baffle configuration may need to be evaluated by modifications and considered in operability evaluations associated with long-term core cooling (LTCC). Please justify the omission of these parameters from consideration for operability and future modifications.

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The results of the break selection and transport analyses are not intuitive when compared to the technical report (TR, previous submittal) values. Explain why the breaks in Enclosure 2, table A3-3, of the letter dated August 17, 2020, are larger than those in table 3.b.4-2 in the TR. The small and fine fibrous debris amounts are also greater in the LAR than in the TR. Explain how smaller breaks would not be more than larger breaks if particulate debris amounts are increased and other debris source terms remain unchanged. Describe whether the breaks in TR table 3.b.4-2 still pass all acceptance criteria. Additionally, the transported values of fiber for the limiting breaks that pass all acceptance criteria are much lower in the LAR than in the TR. Table A3-5 has significantly reduced transport of fiber and sodium aluminum silicate to the RHR strainers while other particulate and chemical species are increased when compared to the TR values. Explain how the debris generation and transport values in these tables were calculated, how they relate to the limiting breaks from the TR, and how they relate to the overall analysis of risk. Describe how risk increases when the limiting breaks are larger than those that were previously identified as limiting. Based on the above, please justify the assumptions and calculations for debris generation and transport.

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