ML20236U783

Informs That Certain Info in AP600 Ssar,If Proposed for Change That Refs AP600 Std Design,Will Require Prior NRC Approval Before Proposed Change Can Be Implemented.Tier 2* Info for AP600 Design & Staff Decision Encl

ML20236U783
Person / Time
Site:	05200003
Issue date:	07/29/1998
From:	Joshua Wilson NRC (Affiliation Not Assigned)
To:	Mcintyre B WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
References
NUDOCS 9807310060
Download: ML20236U783 (5)

Text

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t, July 29, 1998  ;

(' .Mr. Brian A. McIntyre, Manager l Advanced Plant Safety and Licensing l Energy Systems Business Unit l' Westinghouse Electric Company l P.O. Box 355 l Pittsburgh, PA 15230-0355 l

SUBJECT:

TIER 2* INFORMATION FOR THE AP600 DESIGN

Dear Mr. McIntyre:

.The U. S. Nuclear Regulatory Commission (NRC) staff has determined that certain information l (i.e., design commitments)in the AP600 Standard Safety Analysis Report (SSAR), if proposed h

for a change by an applicant orlicensee that references the AP600 standard design, will require prior NRC approval before the proposed change can be implemented. This information will be

. referred to as Tier 2* in the proposed design certification rule for the AP600 design and must be

' explicitly identified with italicized text or brackets and an asterisk (or comparable designations) in l the AP600 design control document (DCD). An index for this information should be provided in

! Tier 2 (Chanter 1) of the DCD. The staff has also determined that the Tier 2* designation should L expire for some of this information after a plant that references the AP600 design achieves full power for the first time ~. The Tier 2* information for the AP600 design and the staff's decision on whether it should expire at first full power is listed in Enclosure 1 to this letter. If you have any questions en this matter, you may contact me at 301-415-3145.

Sincerely, original signed by:

Jerry N. Wilson, Senior Policy Analyst

! Standardization Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation l~ <

Docket No.52-003 -

Enclosure:

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Mr. B. A. McIntyre Docket No.52-003 Westinghouse Electric Company AP600 cc: Mr. H. A. Sepp Mr. Russ Bell Advanced Plant Safety & Licensing Senior Project Manager, Programs I Westinghouse Electric Corporation Nuclear Energy Institute Energy Systems Business Unit 1776 i Street, NW P.O. Box 355 Suite 300 l Pittsburgh, PA 15230 Washington, DC 20006-3706 j i Ms. Susan Fanto Ms. Lynn Cunnor l'

Advanced Plant Safety & Licensing Doc-Search Associates Westinghouse Electric Corporation Post Office Box 34 ,

Energy Systems Business Unit Cabin John, MD 20818 i P.O. Box 355

Pittsburgh, PA 15230 Dr. Craig D. Sawyer, Manager Advanced Reactor Programs  ;

! Mr. Sterling Franks GE Nuclear Energy I U.S. Department of Energy 175 Curtner Avenue, MC-754 l

NE-50 San Jose, CA 95125 19901 Germantown Road l Germantown, MD 20874 Mr. Robert H. Buchholz GE Nuclear Energy Mr. Frank A. Ross 175 Curtner Avenue, MC-781 U.S. Department of Energy, NE-42 San Jose, CA 95125 Office of LWR Safety and Technology '

19901 Germantown Road Barton Z. Cowan, Esq.

l . Germantown, MD 20874 Eckert Seamans Cherin & Mellott 600 Grant Street 42nd Floor l Mr. Charles Thompson, Nuclear Engineer Pittsburgh, PA 15219 i AP600 Certification l NE 50 -

M- Ed Rodwell, Manager 19901 Germantown Road P'vR Design Certification Germantown, MD 20874 E..ctric Power Research Institute 3412 Hillview Avenue Mr. Robert Maiers, P.E. Palo Alto, CA 94303 l Pennsylvania Department of i Environmental Protection l Bureau of Radiation Protection l Rachel Carson State Office Building P.O. Box S469 Harrisburg, PA 17105 8469

I =

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• l SSAR location Subiect Expiration Figure 3.7.1-16 Dimensions for Nuclear Island Structures Yes Figure 3.7.2-12 Nuclear Island Key Structural Dimensions Yes 3.8.2.2 ASME Code, Section Ill, Edition etc. Yes 3.8.2.5 + 3G ASME Code Case N-284 Yes 3.8.3.5.8 Design Summary of Critical Sections Yes 3.8.4.4.1 ACI 318-95 Yes l

l 3.8.4.5.1 ACI 349-90 Yes 3.8.4.5.2 ANSI /AISC N690 Yes 3.8.4.5.4 + 3H Design Summary of Critical Sections Yes 3.8.5.4.5 Design Summary of Critical Sections Yes 3.8.5.5 ACI 349-90 and ACI 318-95 Yes 3.10.1.1 Seismic Qualification Standards Yes 3.10.2 Methods and Procedures for Qualifying Electrical Equipment, Yes Instrumentation, and Mechanical Components j 4 + Table 1.6-1 WCAP-12488-A, " Fuel Criteria Evaluation Process" No 4.1 Maximum Fuel Rod Average Bumup No 4.1.1 Principal Design Requirements No Table 4.3-1 Reactor Core Description (First Cycle) Yes Table 4.3-2 Nuclear Design Parameters (First Cycle) Yes Table 4.3-3 Reactivity Requirements for Rod Cluster Control Assemblies Yes 5.*c.1.1 ASME Code, Section 111, Edition and Addenda Yes 5.4.8.1.2 MOV Design and Qualification Yes 5.4.8.1.3 POV Design and Qualification Yes 5.4.8.5.2 Motor- Operated Valves Yes 1

5.4.8.5.3 Power - Operated Valv6s Yes j i

Enclosure 1

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, I l

SSAR location Subiect Expiration 7 + Table 1.6-1 WCAP-13383, "AP600 Instrumentation and Control Hardware & Yes Software Design, Verification, & Validation Process Report," Rev.1 7 + Table 1.6-1 WCAP-14605, " Westinghouse Setpoint Methodology Yes for Protection Systems, AP600," Rev. 0 7,1.2.15 Verification & Validation Yes 7.1.4.1.8 Conformance with industry Standards Yes Figure 9A-1 NuclearIsland Fire Areas Yes Figure 9A-2 Turbine Building Fire Areas Yes Figure 9A-3 Annex I & ll Building Fire Areas Yes Figure 9A-4 Radwaste Building Fire Areas Yes Figure 9A-5 Diesel Generator Building Fire Areas Yes 18 + Table 1.6-1 WCAP-14396,

• Man-in-The-Loop Test Plan Description," Rev. 2 No 18 + Table 1.6-1 WCAP-14401, " Programmatic Level Description of the AP600 No Human Factors Verification and Validation Plan," Rev. 3 18 + Table 1.6-1 WCAP-14651, " integration of Human Reliability Analysis with No Human Factors Engineering Design Implementation Plan," Rev. 2 18 + Table 1.6-1 WCAP-14695, " Description of the Westinghouse Operator No Decision Making Model and Function Based Task Analysis Methodology," Rev. 0 18 + Table 1.6-1 WCAP-14701," Methodology & Results of Defining Evaluation No issues for the AP600 Human System Interface Design Test Program," Rev.1 18 + Table 1.6-1 WCAP-14822,"AP600 Quality Assurance Procedures Supporting No NRC Review of AP600 SSAR Sections 18.2 and 18.8," Rev. 0 18.2.1.3 Applicable Facilities No 18.2.1.4 Applicable Human System Interfaces No 18.2.1.5 Applicable Plant Personnel No i

18.2.1.6 Technical Basis No 18.2.2.1 Responsibility No Enclosure 1

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SSAR location Sublect Expiration 18.2.2.3 Composition [first paragraph & listing of design team disciplines) No l 18.2.3.1 General Process and Procedures No

[last paragraph of Design Review of HFE Products only)

Figure 18.2-1 Human System Interface Design Team Process No l

18.5.1 Task Analysis Scope No l 18.5.2 Task Analysis Implementation Plan No l

18.7 Integration of Human Reliability Analysis with HFE No i

18.8.2 Safety Parameter Display System (through 18.8.2.7, inclusive) No 18.8.3.2 Main Control Area Mission and Major Tasks No l l

18.8.3.4 Remote Shu'Idown Workstation Mission and Major Tasks No  !

18.8.3.5 Technical Support Center Mission and Major Tasks No 18.11 Human System Interface Design Test Program No 18.12 Inventory [through 18.12.3] No I

Enclosure 1

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