ML20216B133
| ML20216B133 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 03/06/1998 |
| From: | Joshua Wilson NRC (Affiliation Not Assigned) |
| To: | Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| References | |
| NUDOCS 9803120417 | |
| Download: ML20216B133 (3) | |
Text
. - _ __- - - - __________-_-__-______________ _____-______-_ _ _ _ _ _ _ _
March 6, 1998 Mr. Nicholas J. Uparuto, Manager Nuclear Safety and Regulatory Analysis Nuclear and Advanced Technology Division Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, PA 15230
SUBJECT:
APr/'O.NSPECTIONS, TESTS, ANALYSES, AND ACCEPTANCE CRITERIA (ITA/.0)
Dear Mr. Liparulo:
The enclosure to this letter contains requests for additional information or corrections to Revision 3 of the AP600 Tier 1 infonnation including the ITAAC. If you have any questions regarding this matter, you may phone me at (301) 415-3145.
Sincerely, original signed by:
Jerry N. Wilson, Senior Policy Analyst Standardization Project Directorate
> Nision of Reactor Program Management
(
1e of Nuclear Reactor Regulation Docket No.52-003
Enclosure:
As stated cc w/ encl: See next page DISTRIBUTION:
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Mr. Nicholas J. Liparulo Docket No.52-003 Westinghouse Electric Corporation AP600 cc:
Mr. B. A. McIntyre 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 Ms. Cindy L Haag Ms. Lynn Connor Advanced Plant Safety & Licensing Doc-Search Associates Westinghouse Electric Corporation Post Office Box 34 Energy Systems Business Unit Cabin John, MD 20818 Box 355 Pittsburgh, PA 15230 Dr. Craig D. Sawyer, Manager Advanced Reactor P;ograms 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 Ecker1 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 U'. 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 y
o RAls for AP600 ITAAC 640.185 Your response to RAI 640.168 requires clarification. You committed to add item 1.f to ITAAC 3.3, " Buildings,"in your revised response to RAI 640.140, dated December 19, 1997 that will verify certain dimensions of the Nuclear Island. You also committed to add a different item 1.f to ITAAC 3.3 in your response to RAI 640.168, dated Jan-uary 30,1998, to verify the above dock region of the AP600 containment volume. If both Design Commitments are included in the AP600 ITAAC, they will satisfy a portion of the NRC staff's concom. However, ITAAC 3.3 does not verify the volumes and flow paths to the level of detail assumed in the Containment Evaluation Model (WCAP-14407, Section 4). Also, your response refers in " structures" and " major equipment,"
as important heat sinks within the containment, but it does not demonstrate that the
)
heat sinks identified in reference 640.168-1 are verified by ITAAC nor does it indicate what fraction of these heat sinks are verified by ITAAC. Because the design basis analyses for AP600 show little, or no, difference between the calculated pressure and the design pressure, it is important to demonstrate that es assumptions used in the design basis analyses are verified. Also, because the coatings below the operating dock are not safety-related, it is important to assure that the heat transfer characteriza-tion of these coatings are covered in the design basis analyses used to support design certification. Therefore:
(a) Identify the fraction of the heat sinks that are captured in your ITAAC. What is the minimum set necessary to assure that the assumptions in the design basis analyses that support design certification will not result in an unacceptable evaluation?
(b) Explain how the proposed ITAAC demonstrate that the heat transfer characteriza-tions of these heat sinks are verified to a level of detail described in the AP600 Containment Evaluation Model.
(c) Provide an ITAAC that verifies the heat sinks, volumes, and flow paths to a level of detail described in WCAP-14407, Section 4.
640.186 Your responses to RAI 640.176 and OITS #6590, dated February 27,1998, are unacceptable. You did not provide a Tier 1 design commitment and ITAAC for the safety-related coatings that will be applied to the intemal and extemal surfaces of the passive containment cooling system. Also, the PXS ITAAC must verify the safety-related coatings that will be applied to the areas close to the recirculation screens, e.g.
screen plates, and the size of the screen plates. These are important assumption in your debris transport analysis.
640.187 Your response to RAI 640.53 is not sufficient. Your Tier 1 information must include all structures and systems that are in the AP600 design scope and this information must be extracted from the AP600 SSAR. For example, the Turbine Building is described in SSAR Section 1.2.8 but is not currently in Ter 1; whereas the Hydrogen Seal Oil System is item # 2.4.15 of Tier 1 but is not tescribed in the SSAR.