ML20056D983

Forwards Request for Addl Info to Continue Review of Licensee June 1992 Application for Design Certification of AP600.Response Requested within 90 Days of Date of Receipt of Ltr

ML20056D983
Person / Time
Site:	05200003
Issue date:	07/20/1993
From:	Kenyon T Office of Nuclear Reactor Regulation
To:	Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
References
NUDOCS 9308190130
Download: ML20056D983 (5)

Text

.

p OECgff UNITED STATES y

3 ()2/

j NUCLEAR REGULATORY COMMISSION 1

{

' ", I

'g.

WASHINGTON, D.C. 20555 0001

%,"..+/

July 20,1993 1

Docket No.52-003 i

Mr. Nicholas J. Liparulo Nuclear Safety and Regulatory Activities i

Westinghouse Electric Corporation i

P.O. Box 355

[

Pittsburgh, Pennsylvania 15230

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION (RAI) ON THE AP600

)

As a result of its review of the June 1992 application for design certifica-tion of the AP600, the staff has ' determined that it needs additional informa--

tion in order to complete its review. The additional information is needed in -

.the area of source term calculations (Q470.3-Q470.15).* Enclosed are the staff's questions.

Please respond to this request within 90 days 'of the date of. receipt of this letter.

You have requested that portions of the information submitted.in the June 1992 application for design certification be exempt from mandatory'public disclo-sure. 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 submit-ted information is being withheld from public disclosure pending the staff's final determination. The-staff concludes that this RAI does not contain those' portions of the information for which exemption is sought.

However, the staff e

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 disclo-sure in accordance with 10 CFR 2.790, this letter will be placed in the Nuclear Regulatory Commission's Public Document Room.

I i

• The numbers in parentheses designate the tracking numbers assigned to the questions.

j RC HLE CBITER CWY

%g-9308190130 930720 PDR ADDCK 0520 3

c.

, 9 l

Mr. Nicholas J. Liparulo July 20,1993 This RAI affects nine or fewer respondents, and therefore, is not subject to review by the Office of Management and Budget.under P.L.96-511.

If you have any questions regarding_this matter, you can contact me at (301) 504-1120.

Sincerely, i

Thomas J. Kenyon, Proje t Manager Standardization Project Directorate Associate Director for Advanced Reactors and License Renewal Office of Nuclear Reactor Regulation

Enclosure:

As stated cc w/ enclosure:

See next page DISTRIBUTION:

• Central File-PDST R/F TMurley/FMiraglia DCrutchfield

• PDR RBorchardt TEssig-TKenyon RHasselberg TGody, Jr., EDO JMoore, 15B18 MSiemien, 15B18 PShea JHayes, 1004 ACRS (11) w/o encl.

t i

I 0FC:

LA:PDST:ADAR PM:P,g,jTpApAj PM:PDST:ADAR-(A)SC:PDST:ADAR NAME:

PShea 60 TKedoN79 RHasskfg TEssig/[L DATE:

07/10/93 07/2e/93 07/to/93 07/72/93 0FFICIAL RECORD COPY:

DOCUMENT NAME: SOURCE-T.RAI b

c l

f L

Mr. Nicholas 'J. Liparulo' Westinghouse Electric Corporation Docket No.52-003 AP600 cc:

Mr. B. A. McIntyre Advanced Plant Safety & Licensing Westinghouse Electric Corporation i

Energy Systems Business Unit P.O. Box 355 i

Pittsburgh, Pennsylvania 15230 Mr. John C. Butler Advanced Plant Safety & Licensing i

Westinghouse Electric Corporation Energy Systems Business Unit Box 355 Pittsburgh, Pennsylvania 15230 Mr. M. D. Beaumont Nuclear and Advanced Technology Division Westinghouse Electric Corporation One Montrose Metro 11921 Rockville Pike Suite 350 Rockville, Maryland 20852 Mr. Sterling Franks U.S. Department of Energy NE-42 Washington, D.C.

20585 Mr. S. M. Modro EG&G Idaho Inc.

Post Office Box 1625 Idaho Falls, Idaho 83415 Mr. Steve Goldberg Budget Examiner-725 17th Street,.N.W.

Room 8002 Washington, D.C.

20503 Mr. Frank A. Ross U.S. Department of Energy, NE-42 Office of LWR Safety and Technology 19901 Germantown Road Germantown, Maryland 20874 4

.9 a

e e

REQUEST FOR ADDITIONAL INFORMATION ON THE AP600 DESIGN SOURCE TERM 470.3 For each of the postulated accidents, provide the X/Q values from the release point to the location where the release is drawn into the control room envelope. Values should be for the following time periods: 0-2 hours, 0-8 hours, 8-24 hours, 1-4 days and 4-26 days (Section 2.3.4).

470.4 Provide the doses that were calculated for the control room operators for each of the postulated accidents (Chapter 15).

470.5 For the failure of a small line carrying primary coolant outside containment, what are the temperature and pressure of the liquid at the time of the break (Section 15.6.2)7 470.6 Figures 15.6.3-5, 15.6.3.5-7, 15.6.3-8, and 15.6.3-11 of the SSAR provide an insufficient amount of information to determine the flows and flashing fractions.

Provide this information in tabular form as a function of time following the accident (Section 15.6.3).

470.7 Does the steam generator tube rupture event result in fuel failures?

If it does, what is the extent? If it does not, what is the basis for concluding that it does not (Section 15.6.3)?

470.8 Provide the mass of fluid released through the condenser air removal system discharge, the steam generator PORVs, and the steam generator safety. valves (Section 15.6.3).

470.9 Provide the doses from a postulated LOCA based upon the release rate and timing of NUREG-1465 (Section 15.6.5).

470.10 Provide those portions of Reference 1 of Section 15.7 that provide the basis for the assumption of the amount of activity that is in the fuel gap. The value used in the AP600 SSAR is a minimum of a factor of 3 less than the values assumed in Regulatory Guide 1.25 (Section 15.7.4).

470.11 Provide the basis for the assumption that the fuel gap activity of iodine consists of 97 percent in the particulate form and 3 percent in the elemental form (Section 15.7.4).

470.12 Provide those portions of Reference 2 of Section 15.7 that provide the basis for the fuel scrubbing decontamination factor of 250 (15.7.4.3.1.2).

470.13 Provide the basis for the iodine partition coefficient in Table 15.7-1.

Enclosure

_2-470.14 Section 15.7.4 of the Standard Review Plan (SRP) indicates that for fuel handling accidents inside a fuel handling building, it should be ensured that an ESF atmospheric cleanup system is included in the design of the fuel storage facility to mitigate the consequences of a fuel handling accident. The AP600 design does not include such an ESF system.

Provide the basis for this exclusion (Section 15.7.4'.

470.15 Provide the basis for not including safety grade radiation monitors to isolate the containment in the event of a fuel handling accident (Section 15.7.4).

k....