ML18078B073

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US-APWR RAI - RAI Letter 1099
ML18078B073
Person / Time
Site: 05200021
Issue date: 03/19/2018
From:
NRC
To:
Mitsubishi Heavy Industries, Ltd
References
Download: ML18078B073 (3)


Text

1 US-APWRRAIsPEm Resource From:

Hughes, Brian Sent:

Monday, March 19, 2018 3:28 PM To:

US-APWRRAIsPEm Resource

Subject:

RAI Letter 1099 Attachments:

RAI_9448.docx Brian Hughes Senior Project Manager NRO/DNRL/LB4/LB2 US NRC 301-415-6582

Hearing Identifier:

Mitsubishi_USAPWR_DCD_eRAI_Public Email Number:

170 Mail Envelope Properties (BY1PR09MB0934A76141A14FD4F4E4067E89D40)

Subject:

RAI Letter 1099 Sent Date:

3/19/2018 3:27:33 PM Received Date:

3/19/2018 3:27:37 PM From:

Hughes, Brian Created By:

Brian.Hughes@nrc.gov Recipients:

"US-APWRRAIsPEm Resource" <US-APWRRAIsPEm.Resource@nrc.gov>

Tracking Status: None Post Office:

BY1PR09MB0934.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 106 3/19/2018 3:27:37 PM RAI_9448.docx 27617 Options Priority:

Standard Return Notification:

No Reply Requested:

No Sensitivity:

Normal Expiration Date:

Recipients Received:

Request for Additional Information 1099 Issue Date: 03/19/2018 Application

Title:

US-APWR Design Certification - Docket Number 52-021 Operating Company: Mitsubishi Heavy Industries Docket No.52-021 Review Section: TR MHI Advanced Accumulator, Rev. 6 Application Section:

QUESTIONS TR MHI Advanced Accumulator, Rev. 6-2 General Design Criterion (GDC) 35, Emergency Core Cooling, requires, in part, that a system that would provide abundant emergency core cooling to satisfy the ECCS safety function of transferring heat from the reactor core following any loss of reactor coolant at a rate such that (1) fuel and clad damage that could interfere with continued effective core cooling is prevented and (2) clad metal-water reaction is limited to negligible amounts.

10 CFR 50.46, Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors, requires, in part, that ECCS must be designed so that its calculated cooling performance following postulated loss-of-coolant accidents conforms to the criteria set forth in paragraph (b) of 10 CFR 50.46. 10 CFR 50.46 also requires that for the realistic analysis of the ECCS cooling performance, the uncertainties in the analysis method and input must be identified and assessed so that the uncertainty in the calculated results can be estimated and accounted for.

In order to make a safety finding on the APWR advanced accumulators (ACCs) Topical Report, Revision 6 submittal (part of the US-APWR ECCS design) to meet GDC 35 and 50.46, the staff needs the following additional information.

1. In Section 5.1.2 of the topical report, it is stated: The total error of a measured value was evaluated according to GUM ISO/IEC Guide 98-3 (Ref. 5-3) This approach and reference is introduced in Revision 6 of the TR and no explanation and justification is provided for the change from the Revision 5 approach where ANSI/ASME PTC19.1-1985 is used. Explain the difference and the reason for the change. In addition, discuss the overall impact of the full scale test on the estimation of uncertainty of the characteristics equations of flow rates.
2. For random errors, your presentation of the dispersion data in Rev 6, Table 5.1-1 is different from Rev 5 of the topical report. Explain the difference in approach and the resulting dispersion data.
3. For instrument uncertainties, your presentation of the results in Rev 6, Table 5.1-2 is different from Rev 5 of the topical report. Explain the difference in approach and the resulting instrument uncertainty associated with flow rate coefficient.