ML20210Q837

Discusses Open Issues Re AP600 Radiological Consequence Assessment at 970807 Meeting

ML20210Q837
Person / Time
Site:	05200003
Issue date:	08/28/1997
From:	Huffman W NRC (Affiliation Not Assigned)
To:	Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
References
NUDOCS 9709020178
Download: ML20210Q837 (7)

Text

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l, August 28, 1997 l

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

SUBJECT:

OPEN ISSUCS RELATED TO AP600 RADIOLOGICAL CONSEQUENCE ASSESSMENTS

Dear Mr. Liparulo:

During an August 7, 1997, meeting between the staff and Westinghouse on AP600 main control room habitability system, the staff indicated that it must now agree with the Westinghouse dose rate calculation assumptions and methodology before it can issue an acceptable safety evaluation report. This is somewhat different from previous safety evaluations where the staff primarily evaluated accident dose rate consequences for a given applicant using independent analyses and could reach an acceptable conclusion provided that the staff results corroborated the results of the applicant's analyses. As a consequence of this approach, Westinghouse and the staff must reach resolution of a number of differences in the dose rate assessments for AP600 which may require Westinghouse to change its methodology and reanalyze its calculations.

A commitment was taken by the staff during the August 7,1997, meeting to compile a list of differences between the staff and Westinghouse involving source term and related radiological consequence assessments.

Those differences are provided as an enclosure to this letter. Westinghouse is requested to provide an open item tracking system action item to capture this issue with the status listed as action Westinghouse.

If you have any questions regarding this matter, you may contact me at (301) 415-1141.

Sincerely, original signed by:

William C. Huffman, Project Manager Standardization Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No.52-003

Enclosure:

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O Mr. Nicholas J. Liparule Docket No.52-003 Westinghouse Electric Cct.oeration 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 Dusiness Unit 1776 i Street, NW P.O. Box 355 Suite 300 Pittsburgh, PA 15230 Washington, DC 20006-3706 Mr. Cindy L. llaag 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 Programs Mr. t. M. Modro GE Nuclear Energy Nuclear Systems Analysis Technologies 175 Curtner Avenue, MC-754 Lockheed Idaho Technologies Company San Jose, CA 95125 Post Office Box 1625 Idaho falls, ID 83415 Mr. Robert H. Buchholz GE Nuclear Energy Mr. Sterling franks 175 Curtner Avenue, MC-781 U.S. Department of Energy San Jose, CA 95125 NE-50 19901 Germantown Road Barton Z. Ccwan Esq.

Germantown, MD 20874 Eckert Seamans Cherin & Mellott 600 Grant Street 42nd floor Mr. Frank A. Ross Pittsburgh, PA 15219 U.S. Department of Energy, NE-42 Office of LWR Safety and Technology Mr. Ed Rodwell, Manager 19901 Germantown Road PWR Design Certification Germantown, MD 20874 Electric Power Research Institute 3412 Hillview Avenue Mr. Charles Thompson, Nuclear Engineer Palo Alto, CA 94303 AP600 Certification NE-50 19901 Germantown Road Germantown, MD 20874

AP600 DESIGN CERTIFICAT!DN REVIEW - AREAS OF DISAGREEMENT BETWEEN THE NRC staff AND WESTINGHOUSE CONCERNING SOURCE TERM RELATED RADIOLOGICAL CONSEQUENCE ASSESSMENTS (1) Core Release Fractions for the low-Volatile Elements Staff Position:

SECY 96-128 (Item 1) dated June 12, 1996

References:

AP600/SSAR Section 15.6.5.3.1.2 Lead Branch:

PERB/ DRPH (2) Gap Activity Release Timing Staff Position:

SECY 96-128 (item 1) dated June 12, 1996

References:

AP600/SSAR Section 15.6.5.3.1.2 Lead Branch:

SCSB/DSSA (3)

In-Containment Aerosol Removal Rate Staff Position:

Summary of Source Term Meeting dated March 14, 1997

References:

AP600/SSAR Appendix 15B Lead Branch:

PERB/DRPM (4) Unfiltered Air inleakage into the Main Control Room (MCR)

Issue:

Westinghouse proposes an administrative limit of 9 ingresses / egresses into the main contrl room over the fir.at 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> into a DBA to limit MCR inleakage to 2.5 CFM Staff Position:

Still under consideration

Reference:

AP600/SSAR Section 15.6.5.3.5 Lead Branch:

SPLB/DSSA (5) Atmospheric Relative Concentrations at Main Control Room Air intake Staff Position:

NRC Letter to Westinghouse dated July 23, 1997

References:

(1)

Response to RAI 470.3 (Revision 1)

(2)

AP600/SSAR Table 15A-5 Lead Branch:

PERB/DRPM Enclosure

s 2-(6) Main Control Room Operator Occupancy Factors Staff Position:

SRP Section 6.4

References:

AP600/SSAR Table 15.6.5 Lead Branch:

PERB/DRPM (7) ' Radiological Consequence Doses at EAB and LPZ lssue:

The results of the Westinghouse radiological consequence assessment in the AP600 SSAR are reported simply as "less than the limits" rather than actual dose numbers Staff Postion:

Provide actual dose calculational results in the SSAR

Reference:

AP600/SSAR Chapter 15 (Amendment 13)

Lead Branch:

PERB/DRPM

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August 28, 1997 Mr. Nicholas-J. Liparulo, Manager Nuclear Safety and Regulatory Analysis Nuclear and Advanced Technology Division Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, PA 15230

SUBJECT:

OPEN ISSUES RELATED TO AP600 RADIOLOGICAL CONSEQUENCE ASSESSMENTS

Dear Mr. Liparulo:

During an August 7, 1997, meeting between the staff and Westinghouse on AP600 main control room habitability system, the staff indicated that it must now agree with the Westinghouse dose rate calculation assumptions and methodology before it can issue an acceptable safety evaluation report.

1his is somewhat different from previous safety evaluations where the staff primarily evaluated accident dose rate consequences for a given applicant using independent analyses and could reach an acceptable conclusion provided that the staff results corroborated the results of the applicant's analyses. As a consequence of this approach, Westinghouse and the staff must reach resolution of a number of diffe ences in the dose rate assessments for AP600 which may require Westinghouse to change its methodology and reanalyze its calculations.

A commitment was taken by the staff during the August 7, 1997, meeting to compile a list of differences between the staff and Westinghouse involving source term and related radiological consequence assessments.

Those differences are provided as an enclosure to this letter.

Westinghouse is requested to provide an open item tracking system action item to capture this issue with the status listed as action Westinghouse.

If you have any questions regarding this matter, you may contact me at (301) 415-1141.

Sincerely, original signed by:

William C. Huffman, Project Manager Standardization Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No.52-003

Enclosure:

As stated cc w/ encl:

See next page DISTRIBUTION:

See next page DOCUMENT NAME: A:PERB.!SU

• See previous c m urrence n +...,.e w. *.-

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