ML19094A320

Summary Report - 661st Meeting of the Advisory Committee on Reactor Safeguards - March 7-8, 2019

ML19094A320
Person / Time
Issue date:	04/02/2019
From:	Riccardella P Advisory Committee on Reactor Safeguards
To:	Kristine Svinicki NRC/Chairman
Burkhart L
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ML19100A366	List: ML19094A320
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Download: ML19094A320 (4)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, DC 20555 - 0001 April 2, 2019 The Honorable Kristine L. Svinicki Chairman U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001

SUMMARY

REPORT - 661st MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, MARCH 7-8, 2019

Dear Chairman:

During its 661st meeting, March 7-8, 2019, the Advisory Committee on Reactor Safeguards (ACRS) discussed several matters and completed the following letter and memorandum:

LETTER Letter to Margaret M. Doane, Executive Director for Operations, NRC, from Peter C.

Riccardella, Chairman, ACRS:

• Interim Letter: Chapters 13 and 18 of the NRC Staffs Safety Evaluation Report with Open Items Related to the Certification Application Review of the NuScale Small Modular Reactor, dated March 21, 2019 MEMORANDUM Memorandum to Margaret M. Doane, Executive Director for Operations, NRC, from Andrea D. Veil, Executive Director, ACRS:

• Documentation of Receipt of Applicable Official NRC Notices to the Advisory Committee on Reactor Safeguards for March 2019, dated March 19, 2019 HIGHLIGHTS OF KEY ISSUES

1. Interim Letter: Chapters 13 and 18 of the NRC Staffs Safety Evaluation Reports with Open Items Related to the Certification of the NuScale Small Modular Reactor The Committee met with representatives of the NRC staff and NuScale to review Chapter 13, Conduct of Operations, and Chapter 18, Human Factors Engineering, of the safety

2 evaluation report with open items associated with the NuScale small modular reactor design certification application.

Chapter 13 discussions at this meeting included the management and technical support organization; operating organization; reactor operator qualification and training; staffing; operational programs; administrative procedures; and emergency procedures. The staffs SER on Chapter 13 summarizes the requirements for the COL applicant in the areas of:

• The management and technical support organization,

• Description and schedule of initial personnel training and qualification,

• Design features, facilities and equipment used to support emergency response functions,

• Site-specific information for operational programs,

• Administrative and operating procedures used by the operation organization to ensure activities are conducted in a safe manner.

The DCA Chapter 13 topics on the physical security plan, cyber security plan and fitness for duty were not reviewed in this SER because they contain security-related information.

Chapter 18 describes the human factors engineering (HFE) program for the NuScale plant.

The HFE program takes advantage of state-of-the art technology and incorporates accepted HFE standards and guidelines, including the applicable staff guidance (NUREG-0711). The staff reviewed the HFE program under four general activities described in NUREG-0711:

• Planning & analysis - HFE program management, operating experience review, functional requirements and function allocation, task analysis, staffing and qualifications, and treatment of important human actions

• Designhuman-system interface design, procedure development, and training program development

• Human factors verification and validation

• Operational implementationimplementation and operation, and design implementation Committee Action The Committee issued an interim letter to the Executive Director for Operations on this matter, dated March 21, 2019, with the following conclusions and recommendations: 1) Operator training drills should include scenarios where computer displays provide misleading or incomplete information to ensure operators maintain alternate diagnostic approaches, 2) The human factors engineering program review needs to be coordinated with the review of reactor building crane design features and operations in subsequent design certification chapters in order to minimize any hazards from heavy load lifts, including module movement, and 3) We have not identified any additional major issues at this time for Chapters 13 and 18.

3 SCHEDULED TOPICS FOR THE 662nd ACRS MEETING The following topics are scheduled for the 662nd ACRS meeting, to be held April 4-6, 2019:

• NuScale Safety Evaluation Report with Open Items for Chapters 9, 10, 11, 12, and 16

• Biennial Review and Evaluation of the NRC Safety Research Program Sincerely,

/RA/

Peter C. Riccardella Chairman

4 April 2, 2019

SUMMARY

REPORT - 661st MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, MARCH 7-8, 2019 Accession No: ML19094A320 Publicly Available (Y/N): _Y___ Sensitive (Y/N): N If Sensitive, which category?

Viewing Rights: NRC Users or ACRS only or See restricted distribution OFFICE ACRS SUNSI Review ACRS ACRS NAME LBurkhart LBurkhart AVeil PRiccardella (AVeil for)

DATE 03/ 27 /19 03/ 27 /19 04/ 2 /19 04/ 2 /19 OFFICIAL RECORD COPY