ML20202E770

Forwards List of Open Items Associated W/Chapter 3 of AP600 SER

ML20202E770
Person / Time
Site:	05200003
Issue date:	10/09/1997
From:	Joseph Sebrosky NRC (Affiliation Not Assigned)
To:	Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
References
NUDOCS 9712080137
Download: ML20202E770 (4)

Text

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4 October 9, 1997 Mr. Nicholas J. Liparuto, Manager Nuclear Safety and Regulatory Analysis Nuclear and Advanced Technology Division Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, PA 15230

SUBJECT:

OPEN ITEMS ASSOCIATED WITH CHAPTER 3 OF THE AP600 SAFETY EVALUATION REPORT (SER)

Dear Mr. Liparulo:

The Plant Systems Branch has provided an SER for Chapter 3.11

• Environmental Qualification of Mechanical and Electrical Equipment." However, the input to this section contained some open items. These open items have been extracted from the SER and can been found in the enclo-sure to this letter.

You have requested that portions of the information submitted in the June 1992, application for design certification be exempt from mandatory public disclosure. While the staff has not completed its review of your request in accordance with the requirements of 10 CFR 2.790, that portion of the submitted information is being withheld from public disclosure pending the staff's '

final determination. The staff concludes that these follow on questions do not contain those portions of the information for which exemption is sought. However, the staff will withhold this letter from public disclosure for 30 calendar days from the date of this letter to allow Westinghouse the opportunity to verify the staff's conclusions, if, after that time, you do not request that all or portions of the information in the enclosures be withheld from public disclosure in accordance with 10 CFR 2.790, this letter will be placed in the Nuclear Regulatory Commission Public Document Room.

If you have any questions regarding this matter, you may contact me at (301) 415-1132.

Sincerely, original signed by:

Joseph M. Sebrosky, Project Manager Standardization Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No.52-003

Enclosure:

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t' Mr. Nicholas J. Uparulo Docket No.52-003 Westinghouse Electric Corporation AP600 oc: Mr. B. A. McIntyre Ms. Cindy L Haag Advanced Plant Safety & Ucensing Advanced Plant Safety & Ucensing Westinghouse Electric Corporation Westinghouse Electric Corporation Energy Systems Business Unit Energy Systems Business Unit P.O. Box 355 Box 355 Pittsburgh, PA 15230 Pittsburgh, PA 15230 j Enclosure to be distributed to the following addressors after the result of the proprietary evaluation is received from Westinghouse:

Mr. Russ Boi Ms. Lynn Connor Senior Project Manager, Programs DOC-Search Associates Nuclear Energy Institute Post Office Box 34 1776 i Street, NW Cabin John, MD 20818 Suite 300 Washington, DC 20006-3706 Mr. Robert H. Buchholz GE Nuclear Energy Dr. Craig D. Sawyer, Manager 175 Curtner Avenue, MC 781 Advanced Reactor Programs San Jose, CA 95125 GE Nuclear Energy 175 Curtner Avenue, MC 754 Mr. Storiing Franks San Jose, CA 95125 U.S. Department of Energy NE 50 Barton Z. Cowan, Esq. 19901 Germantown Road Eckert Seamans Cherin & Mellott Germantown, MD 20874 600 Grant Street 42nd Floor Pittsburgh, PA 15219 Mr. Charles Thompson, Nuclear Engineer AP600 Certification Mr. Frank A. Ross NE 50 U.S. Department of Energy, NE-42 19901 Germantown Road Office of LWR Safety and Technology Germantown, MD 20874 19901 Germantown Road Germantown, MD 20874 Mr. Ed Rodwell, Manager PWR Design Certification r'ectric Power Research Institute

, '.1 Hillview Avenue P Mto, CA 94303

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OPEN ITEM ASSOCIATED WITH CHAPTER 3.11

• ENVIRONMENTAL QUALIFICATION OF  :

MECHANICAL AND ELECTRICAL EQUIPMENT  !

270.15F For the Loss of Coolant Accident source term, in SSAR Section 3D.5.5.1.1 it is l stated that the radionudede groups and elemental release fractions are consistent l w6th the accident source term information presented in NUREG 1465, " Accident Source Terms for Light Water Nuclear Power Plants Final Report," with the l exception of the release fractions for barium and strontium, lanthanides, and cerium groups,  ?

The timing of the release are based on NUREG 1465 assumptions as well as )

AP600 specific activity release projections. The noceptability of the exceptions to NUREG 1465 as discussed in SSAR Section 3D.5.5.1.1 is an open issue that it discussed in more detail in Chapter 15 of this report Consequently, h is also an Open Hem in this Sedion. This is Open Hem 3.11.3.12.

270.16F in SSAR Appendix 3D, Section 3D.5.5.1.1 reference is made to Attachment A, .

Section 1.74, the staff cannot locate this Sedion in Attachment A, therefore i

Westinghouse should provide Section 1.7.4 of Attachment A for staff review. Note 5 of Table 3D.5-4 states, "A blowout panel is designed to o.9en when tne pressure  :

difference exceeds 10 inches water gauge." It is the staffs understanding that the ,

design has been changed and the blowout panel will ac'ivate on temperature. -

Westinghouse should make a corredion to note 5 of Table 3D.5-4. These issues collectively are Open item 3.11.3.13 270.17F Equipment that is used to perform a necessary safety fundion must be demon- ,

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strated to be capable of maintaining functional operability under all service conditions postulated to occur during its installed life, for the time N is required to operate. This requirement, which is embodied in GDC 1 and GDC 4, and Critoria Ill, XI, and XVil of Appendix B to 10 CFR Part 50, is applicable to equipment located incide and outside the containment, in SSAR Section 3.11.2.1 and in 3D.4 of Appendix 3D, the AP600 design is committed to GDCs 1,2,4 and 23, and Section ill '

of 10 CFR Par 150, Appendix B. However, in accordance Wh both SRP Section 3.11 and Rev.1 of RG 1.8g, a commitment to Critorion XI regarding test control, and Criterion XVil regarding quality assurance records, of Appe'. dix B to .

10 CFR Part 50 should also be made. Therefore, this is Open item 3.11.3.1-4.

270.18F - In SSAR Sections 3.11.4 and 3.D.5.5.1.6 of Appendix 3D it is stated that there is no caustic containment spray in the AP600 design. Westinghouse should verify the validity of this statement because the staff understands that the AP600 design has been changed to include a containment spray systec.). This is Open item 3.11.3.15.

Enclosure

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