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June 21, 2000
MEMORANDUM TO: |
William D. Travers
Executive Director for Operations |
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/RA/ |
FROM: |
John T. Larkins, Executive Director
Advisory Committee on Reactor Safeguards |
SUBJECT: AP1000 PRE-APPLICATION REVIEW
During the 473rd meeting of the Advisory Committee on Reactor Safeguards, June 7-9, 2000, the Committee considered the proposed
AP1000 advanced reactor design pre-application and the issues that would need to be addressed as part of the staff's review of a
license application. Attached is a list of issues that the Committee decided should be addressed by the Westinghouse Electric
Company.
Attachment: ACRS Issues Related to the Review of the AP1000 Design
Reference:
Westinghouse Electric Company Slides, "AP1000 Overview," presented to the NRC staff on April 27, 2000.
cc: |
A. Vietti-Cook, SECY
J. Craig, OEDO
G. Millman, OEDO
S. Collins, NRR
D. Matthews, NRR
J. Wilson, NRR |
ACRS ISSUES RELATED TO THE REVIEW OF THE AP1000 DESIGN
1. |
The staff should ensure that the Westinghouse Electric Company's application for the AP1000
design includes the following: |
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a. |
Scope of additional analyses
needed for the Standard Safety
Analysis Report (SSAR)
Chapter 15 accidents. (Revised
codes used in the analyses may
need to be revalidated.) |
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b. |
Clear identification of the
inadequacies in the NOTRUMP
code and the steps taken to
compensate for them. (A
convincing demonstration of the
applicability of the revised
NOTRUMP code to the AP1000
design is needed.) |
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c. |
Demonstration of the scalability
and adequacy of the existing
thermal-hydraulic integral and
separate effects data. |
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d. |
Identification of additional
experiments or analyes needed
to justify crediting in-vessel core
debris retention as part of the
licensing basis. |
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e. |
An evaluation of core
performance. |
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f. |
An evaluation of the impact of
any changes in performance
ratings resulting from design
changes. |
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g. |
An evaluation of the effects of
the pool of water above the
containment on containment
structures during seismic events. |
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2. |
The staff should ensure that the Westinghouse Electric Company's probabilistic risk analysis for the
AP1000 includes the following: |
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a. |
In-containment aerosol behavior,
especially the effects of particle
charging |
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b. |
Catastrophic failure of the steel
shell containment |
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c. |
Containment bypass accident
sequences, especially sequences
involving steam generator tube
ruptures |
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d. |
Reactor coolant system
depressurization reliability |
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e. |
Efficacy and reliability of
external cooling of the
containment shell |
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f. |
Stratification and mixing in the
containment |
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