ML20151X404

Discusses Revised Tier 2 Info for AP600 Design.Staff Revised Decision on Whether Fire Protection Should Expire at First Full Power Encl

ML20151X404
Person / Time
Site:	05200003
Issue date:	09/11/1998
From:	Joshua Wilson NRC (Affiliation Not Assigned)
To:	Mcintyre B WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
References
NUDOCS 9809170070
Download: ML20151X404 (5)

Text

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• September 11, 1998 Mr. Brian A. McIntyre, Manager Advanced Plant Safety and Licensing Energy Systems Business Unit Westinghouse Electric Company P.O. Box 355 Pittsburgh, PA 15230-0355

SUBJECT:

REVISED TIER 2* INFORMATION FOR THE AP600 DESIGN De'ar Mr. McIntyre:

In my letter dated July 29,1998, I enclosed a list of Tier 2* information. The expiration for the fire protection information was incorrect. The Tier 2* information for the AP600 design and the staff's revised decision on whether it should expire at first full power is listed in Enclosure 1 to this letter._ If you have any questions on this matter, you may contact me at 301-415-3145.

Sincerely, original signed.by: I Jerry N. Wilson, Senior Policy Analyst l Standardization Project Directorate  !

Division of Reactor Program Management l Office of Nuclear Reactor Regulation l Docket No.52-003 l

Enclosure:

As stated l cc w/ enclosure: See next page i

l- DISTRIBUTION:

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- ' DOCUMENT NAME: A: TIER 2-LTR.JNW T3,eceive a copy of this document. Indicate in the box: "C' = Copy without attachment / enclosure *E' = Copy with attadiment/ enclosure "N" - No copy OFFICE PA:PDST:DRM- f. D:PDST:DRPMl BC:SPLB:DiiSA NAME JNWilsonig/J4'u TRQuay T/W LBMarsh DATE 09/f /98 (/ 09/9 /98 09/R /98 Ml -

OFFICIAL RECORD CODF 150121

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. l Mr. B. A. McIntyre Docket No.52-003 I Westinghouse Electric Company - AP600 cc: Mr. H. A. Sepp Mr. Russ Bell l Advanced Plant Safety & Licensing Senior Project Manager, Programs ]

Westinghouse Electric Corporation Nuclear Energy Institute Energy Systems Business Unit 1776 l Street, NW P.O. Box 355 Suite 300 Pittsburgh, PA 15230 Washington, DC 20006-3700 )

Ms. Susan Fanto Ms. Lynn Connor ,

Advanced Plant Safety & Licensing Doc-Search Associates l Westinghouse Electric Corporation Post Office Box 34 Energy Systems Business Unit Cabin John, MD 20818 l P.O. Box 355 Pittsburgh, PA 15230 Dr. Craig D. Sawyer, Manager j Advanced Reactor Programs  !

Mr. Sterling Franks GE Nuclear Energy U.S. Department of Energy 175 Curtner Avenue, MC-754 NE-50 San Jose, CA 95125 19901 Germantown Road 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.

Germantown, MD 20874 Eckert Seamans Cherin & Mellott 600 Grant Street 42nd Floor Mr. Charles Thompson, Nuclear Engineer Pittsburgh, PA 15219 AP600 Certification NE-50 Mr. Ed Rodwell, Manager 19901 Germantown Road PWR Design Certification Germantown, MD 20874 Electric Power Research Institute 3412 Hillview Avenue Mr. Robert Maiers, P.E. Palo Alto, CA 94303 Pennsylvania Department of Environmental Protection Bureau of Radiation Protection Rachel Carson State Office Building P.O. Box 8469 Harrisburg, PA 17105-8469

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m . . .

SSAR locaton Subject 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 111, 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

'3.8.4.5.1 ACI 349 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-

'4 + Table 1.6-1 ' WCAP-12488-A, " Fuel Criteria Evaluation Process" No

. 4.1 Maximum Fuel Rod Average Burnup No ,

L4.1.1' Principal Design Requirements' No

[ .. . Table 4.3-1.. Reactor Core Description (First Cycle) Yes t

l' Table 4.3 2 Nuclear Design Parameters (First Cycle) Yes p

-. Table _4.3-3 . Reactivity Requirements for Rod Cluster Control Assemblies Yes l5.2.1.1 ASME Code, Section Ill, Edition and Addenda Yes

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L 5.4.8.1.2 MOV Design and Qualification Yes

. -5.4.8.1.3- POV Design and Qualification Yes A

[, Enclosure 1 rs

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r ..

y SSAR location Subject Expiration ,

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3 5.4.8.5.2 Motor- Operated Valves Yes 5.4.8.5.3- Power- Operated Valves Yes 7 + Table 1.6-1 .WCAP-13383, "AP600 instrumentation and Control Hardware & Yes  ;

Software Design, Verification, & Validation Process Report," Rev.1 L 7 + Table 1.6 WCAP-14605," Westinghouse Setpoint Methodology Yes for Protection Systems, AP600," Rev. 0 7.1.2.15 Verification & Validation ~ Yes i l

I 7.1.4.1.8. Conformance with Industry Standards Yes l

Figure 9A-1 Nuclear Island Fire Areas No' Figure 9A-2 Turbine Building Fire Areas No l l Figure GA-3 Annex l & ll Building Fire Areas No Figure 9A-4 Radwaste Building Fire Areas No n Figure 9A-5 Diesel Generator Building Fire Areas No ,

! I 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 )

i 18 + Table 1.6-1 .WCAP-14651," Integration of Human Reliability Analysis with No Huma'n Factors Engineering Design implementation Plan," Rev. 2 l ~ 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,"Methodolegy & Results of Defining Evaluation No Issues for the AP600 Human System Interface Design Test i Program," Rev.1

)~ 18 + Table 1.6-1 WCAP-14822,"AP600 Quality Assurance Procedures Supporting No j

NRC Review of AP600 SSAR Sections 18.2 and 18.8," Rev. 0 118.2.1.3 Applicable Facilities No i 1

Enr.losure 1

1

7. .- l 1

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SSAR location Subiect Exoiration 18.2.1.4 Applicable Human System Interfaces No 18.2.1.5 Applicable Plant Personnel No 18.2.1.6 Technical Basis No 18.2.2.1 Responsibility No 18.2.2.3 Composition [first paragraph & listing of design team disciplines) No 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 18.5.2 Task Ana!ysis implementation Plan No 18.7 Integration of Human Reliability Analysis with HFE No )

18.8.2 Safety Parameter Display System (through 18.8.2.7, inclusive) No i

18.8.3.2 Main Control Area Mission and Major Tasks No  !

18.8.3.4 Remote Shutdown Workstation Mission and Major Tasks No 18.8.3.5 Technical Suppott Center Mission and Major Tasks No 18.11 Human System Interface Design Test Program No 18.12 Inventory [through 18.12.3] No Enclosure 1