ML20236U783
| 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
_-_
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 the AP600 design control document (DCD). An index for this information should be provided in l
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 -
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Enclosure:
As stated I);8Q J cc w/ enclosure: See next'page -
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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 Westinghouse Electric Corporation Nuclear Energy Institute Energy Systems Business Unit 1776 i Street, NW P.O. Box 355 Suite 300 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 l
Pittsburgh, PA 15230 Dr. Craig D. Sawyer, Manager Advanced Reactor Programs Mr. Sterling Franks GE Nuclear Energy U.S. Department of Energy 175 Curtner Avenue, MC-754 l
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.
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
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__m_-_______.-._
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
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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
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