ML20147G566

Forwards Draft LTC Agenda for ACRS 970328 Meeting

ML20147G566
Person / Time
Site:	05200003
Issue date:	03/10/1997
From:	Novendstern E WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:	Boehnart P NRC
Shared Package
ML20147G451	List: ML20147G463 ML20147G474 ML20147G485 ML20147G514 ML20147G530 ML20147G539 ML20147G545 ML20147G555 ML20147G566 NSD-NRC-97-5033, Submits Formal Transmittal of Correspondence Previously Sent Informally Covering Period 970205-0316.Index of Encl Matl Attached
References
ACRS-GENERAL, NUDOCS 9703280194
Download: ML20147G566 (5)

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Brian A. Mc Intyre r ,

-4 S H E E T To: Paul Boehnart (NRC)

Subject:

Draft LTC agenda for ACRS 3/28/97 Meeting Date: March 10,1997 l

Pages: Two, including this cover sheet.

COMMENTS:

Paul, 4

Attached is a draft agenda that we would propose for the above meeting. Please use as " straw-man" and call me with any suggested changes. Thanks.

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l From the desk of...

cc: B. McIntyre (NRC Informal File), D. Garner, Earl H. Novendstern Managw. Advanewand WER Plant Safety R. Kemper, L. Hochreiter(FAX)

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PO Box 355 Pittsburgh, PA 15235 (412)374 -4790 Fax: (412) 374-4011 steren 13 1999 g NB C ' 1.*C,13 }9*

9703200194 970321 3 PDR ADOCK 0520 E

E l DRAFT AGENDA i Friday, March 28,1997 LONG TERM COOLING MEETING  !

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1. Introduction

a. Computer Code Selection 1

b. Window Mode Approach Definition l

2. PIRT

3. WCfr Validation

a. OSU Model

b. Sensitivity Calculations

c. Comparisons with Data 1

4. AP600 Plant Model ,

a. Plant Model l

b. Containment Boundary Conditions l

5. Conclusions I i

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Meren 10, .997 I NRCiL R &D 197

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's RECIPIENT INFORMATION SENDER INFORMATION DATE: Myeg /( /997 NAME: J m gg TO:

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ENERGY CENTER -

Io A /dN /od EAST i PHONE: FACSIMILE: PHONE: omes:g nq_3_ggg i

. COMPANY: Facsimile: win: 284 4887 d5 MEC outside: (412)374 4887 i LOCATION: I 1

i Cover + Pages 1 + 2.

4 The following pages are being sent from the Westinghouse Energy Center, East Tower, Monroeville, PA. If any problems occur during this transmission, please call:

WIN: 284-5125 (Janice) or Outside: (412)374 5125.

COMMENTS:

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NSD-NRC-97-5019 DCP/NRC0768 Docket No. STN-52-003 March 13,1997 I

' Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: T. R. QUAY

SUBJECT:

- AP600 DESIGN CERTIFICATION, CLARIFICATION OF SAMPLING ROOM FOR RAI RESPONSE 471.26

REFERENCE:

Westinghouse letter NTD-NRC-94-4337, " Westinghouse Response to NRC Request -

for Additional Information on the AP600", dated November 7,1994.

Dear Mr. Quay:

l This is to formally respond to an NRC telephone request to verify the identity of a radiation monitor. l The Westinghouse response to RAI 471.26 submitted by the Reference included a " Post Accident ,

Sample Room Monitor" Revision 8 of the AP600 SSAR, of June 19, 1996, includes a " Primary Sampling Room Monitor" This letter verifies that these are one and the same monitor and that the SSAR has the correct nomenclature.

Please call J. W. Winters (412-374-5290) if you have questions on this submittal.

kY Brian A. McIntyre, h anager Advanced Plant Safety and Licensing jmi' cc: T. J. Kenyon, NRC N. J. Liparuto, Westinghouse Electric Corporation l

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l l NSD-NRC-97-5020 l DCP/NRC0769 Docket No.. STN-52-003 l

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-. March 13,1997 Document Control Desk U. S. Nuclear Regulatory Conmlission Washington, DC 20555 l.

ATTENTION: T. R. QUAY l I

SUBJECT:

AP600 DESIGN CERTIFICATION - PROHIBITIONS ON ANTIMONY  !

This provides a formal response to the NRC on a question received during a telephone conversation ,

on Chapter 12 of the AP600 SSAR. The NRC requested a definition of our prohibitions on antimony in reactor coolant, especially in reactor coolant pump journal bearings.

The last paragraph of the AP600 SSAR subsection 6.1.1.2 contains general prohibitions on antimony and other lew melting paint metals. In general, antimony is prohibited from coming into contact with engineered safety feature component parts and limited to less than 1 percent in bearings in contact

• l with reactor coolant water. In addition, because of the water bearing design in the AP600 canned

- motor pumps, the reactor pump mechanical design criteria prohibits antimony completely from the j reactor coolant pump and its bearings. )

This should resolve Open Item #5010. If you have any questions on this submittal, please contact J. W. Winters (412 374-5290).

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h ffh9 Brian A. McIntyre, h an er

' Advanced Plant Safety and Licensing J

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i cc: T. J. Kenyon, NRC N. J. Liparuto, Westinghouse Electric Corporation i

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