ML20140B640

Forwards RAI on AP600 Shutdown ERGs for Westinghouse Response

ML20140B640
Person / Time
Site:	05200003
Issue date:	06/03/1997
From:	Huffman W NRC (Affiliation Not Assigned)
To:	Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
References
NUDOCS 9706060277
Download: ML20140B640 (4)

Text

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June 3, 1997 l

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

SUBJECT:

REQUESTS FOR ADDITIONAL INFORMATION (RAIs) ON AP600 SHUTDOWN EMER-GENCY RESPONSE GUIDELINES (ERGS)

Dear Mr. Liparulo:

The Nuclear Regulatory Commission Reactor Systems Branch needs additional information to complete its review of the AP600 shutdown ERGS. Enclosed are RAls on the AP600 shutdown ERGS for which Westinghouse responses are requested.

l If you have any questions regarding this matter, you can contact me at  !

(301) 415-1141.

Sincerely, I

original signed by: '

William C. Huffman, Project Manager Standardization Project Directorate i Division of Reactor Program Management 1 Office of Nuclear Reactor Regulation Docket No.52-003

Enclosure:

As stated e ex e

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PDR ADOCK 05200003 A PDR 3 DOCUMENT NAME: A:RX-SDERG.REV Ta ,eceive a copy of this document, indicate in the boa: "C" = Copy without attachmentlenclosure 'E' = Copy with attachrnentlenclosure "N" = No copy 0FFICE PM:PDST:DPRM SC:SR)(SJDJSA D:PDST:DRPM l NAME WCHuffman:tg3c w Ale (M/ f* A?L- TRQuayMF4 DATE 06/ff/97 06/7/97 06/ 3/97 g g gj g 0FFICIAL RECORD COPY

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

cc: Mr. B. A. McIntyre Mr. Ronald Simard, Director Advanced Plant Safety & Licensing Advanced Reactor Programs Westinghouse Electric Corporation Nuclear Energy Institute ,

Energy Systems Business Unit 1776 Eye Street, N.W. l 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 i Energy Systems Business Unit Cabin John, MD 20818  !

Box 355 l Pittsburgh, PA 15230 Mr. James E. Quinn, Projects Manager l LMR and SBWR Programs  !

Mr. M. D. Beaumont GE Nuclear Energy l Nuclear and Advanced Technology Division 175 Curtner Avenue, M/C 165 i Westinghouse Electric Corporation San Jose, CA 95125 l One Montrose Metro 11921 Rockville Pike Mr. Robert H. Buchholz Suite 350 GE Nuclear Energy Rockville, MD 20852 175 Curtner Avenue, MC-781 San Jose, CA 95125 l Mr. Sterling Franks U.S. Department of Energy Barton Z. Cowan, Esq.

NE-50 Eckert Seamans Cherin & Mellott 19901 Germantown Road 600 Grant Street 42nd Floor Germantown, MD 20874 Pittsburgh, PA 15219 ,

Mr. S. M. Modro Mr. Ed Rodwell, Manager Nuclear Systems Analysis Technologies PWR Design Certification Lockheed Idaho Technologies Company Electric Power Research Institute Post Office Box 1625 3412 Hillview Avenue Idaho Falls, ID 83415 Palo Alto, CA 94303 ,

i Mr. Frank A. Ross Mr. Charles Thompson, Nuclear Engineer U.S. Department of Energy, NE-42 AP600 Certification Office of LWR Safety and Technology NE-50 19901 Germantown Road 19901 Germantown Road Germantown, MD 20874 Germantown, MD 20874

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i ij AP600-SHUTDOWN ERGS I

GENERAL COMMENT

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! .440.648 Westinghouse should explain why the shutdown safety status tree SDF-0.1 does not show the conventional critical safety functions

, such as Subcriticality,_ Core Cooling, Heat Sink, Integrity,  ;

f Containment and Inventory. >

440.649 The ERGS, in general, should provide symptom-based, as opposed to 5 event-based guidance to the operator. It is not clear that the  ;

AP600 Shutdown ERGS are symptom based. The shutdown safety status i tree " BLOCKS" I to 9 shown in SDF-01 may not cover all possible symptoms during' shutdown conditions. In addition, the six shut-down ERGS, SDG-1 to SDG-6, seems to be event-based procedures.

These six shutdown ERGS also may not comprehensively cover all the critical safety functions for shutdown conditions. Clarify the ERG philosophy used for shutdown conditions.

440.650 A number of shutdown ERGS contain the statement: " Include addi-tional AP600 details in the E0Ps." Please explain why these details are not included in the ERGS and how these details will be developed.

440.651 A number of shutdown ERGS state: "Go to appropriate plant proce-dure." How is the appropriate plant procedure determined? Should not criteria for exiting the ERGS in these situations be verified to exist and specified in the ERGS?

440.652 What is a " BLOCK" in the Shutdown Safety Status Tree?_ Are they alarms in the control room?. Are there any symptoms or entry l conditions to the shutdown ERGS besides the condition of the i shutdown safety status tree?

SDG-1 RESPONSE'TO LOSS OF RCS INVENTORY DURING SHUTDOWN 440.653 Background information Section 3.2, Page 3-3: Change reference from step 9 to step 11, and from step 25 to 27 to correctly refer to the containment evacuation steps.

440.654 Step Sb, Page 3 of 12: If the RCS hot leg level can not be estab-lished, what is the alternate action?

440.655 Step 8c, Page 4 of 12: Confirm that step 11 is correct.

440.656 Step 10a, Page 5 of 12: Change the RNO step from a.3) to a.2).

Enclosure i l

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440.657 The background for step 11 describes core boiling and release of steam and/or gases to the containment through vents in the RCS.

Since containment steaming is possible during shutdown conditions, why is only containment radiation included in the Shutdown Safety Status Tree? Why are not containment temperature and containment .

pressure included?

SDG-5 RESPONSE TO RCS COLD OVERPRESSURE DURING SHUTDOWN 440.658 Steps 3, 4 and 5, page 2 of 3: The action statement " Determine cause of RCS pressurization" does not seem sufficient. West-inghouse should provide additional guidance for the operator to

find the cause of RCS pressurization and specify additional corrective actions. l l l s

a W

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