ML20205N485

Forwards Request for Addl Info Re Chapter 5,Amend C to CESSAR-DC,Sys 80+ on Steam Generators.Info Needed by 881230

ML20205N485
Person / Time
Site:	05000470
Issue date:	10/28/1988
From:	Vissing G Office of Nuclear Reactor Regulation
To:	Scherer A ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
References
PROJECT-675A NUDOCS 8811040166
Download: ML20205N485 (5)

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October 28, 1988 c

Project No. 675 gNW Mr. A. E. Scherer, Director Nuclear Licensing Combustion Engineering  ;

1000 Prospect Hill Road r Post Office Box 500 4 Windsor, Connecticut 06095-0500

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION CONCERNING CHAPTER 5, AMENDMENT C, CESSAR-DC, SYSTEM 80+, STEAM GENERATORS, MATERIALS ENGINEERING BRANCH Our Materials Engineering Branch has reviewed Amendment C of Chapter 5 of  ;

CESSAR-DC, System 80+ transmitted by your letter dated June 30, 1988 and has identified the need for additional information related to Section 5.4.2, Steam Generators. The enclosed Request for Additional Informatien describes the needed information. Our schedule calls for the information to be received by l Decen6er 30,1988. .

Sincerely,

/s/

Guy S. Vissing, Project Manager Standardization and Non-Power  !

Reactor Project Directorate .

Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation

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l Project No. 675 Mr. A. E. Scherer, Director Nuclear Licensing Combustion Engineering 1000 Prospect Hill Road Post Office Box 500 Windsor, Connecticut 06095-0500

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION CONCERNING CHAPTER 5. AMENDMENT C, CESSAR-DC, SYSTEM 80+, STEAM GENERATORS MATERIALS ENGINEERING BRANCH Our Materials Engineering Branch has reviewed Amendment C of Chapter 5 of CESSAR-DC, System 80+ transmitted by your letter dated June 30, 1988 and has identified the need for additional inteatinn ra'ned to Section 5.4.2, steam Generators. The enclosed Request for Additional Information describes the needed information. Our schedule calls for the information to be received by Decerber 30, 1988.

Sincerely,  !

Guy S. Vissing, Project Manager  !

, Standardization and Non Power Reactor Project Directorate l Division of Reactor Projects - III, IY, Y and Special Projects Office of Nuclear Reactor Regulation

Enclosure:

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Combustion Engineering, Inc. Project No. 675 Advanced CESSAR cc: Mr. C. B. Brinkman, Manager Wadhington Nuclear Operations Combustion Engineering, Inc.

7910 Woodmont Avenue, Suite 1310 Bethesda, Maryland 20814 Mr. Ernest Kennedy Manager of Licensing Combustion Engineer'ng 1000 Prospect Hill Road Post Office Box 500 Windsor, Connecticut 06095-0500 s

, ENCLOSURE 1 REQUEST FOR ADDITIONAL INFORMATION COMBUSTIONENGINEERING(CE)

CESSAR - DC MATERIALS ENGINEERING BRANCH DIVISION OF ENGINEERING AND SYSTEMS TECHNOLOGY 251.0 The infonnation provided concerning the steam generators is not suffi-cient for '.he staff to evaluate the adequacy of the new design or to ascertain if necess6ry improvements and features have been incorporated into the design to prevent the occurrence of anticipated and kncren problems which have occurred in operating plants. Please address how CESSAR-DC will incorporf.te the reconsnenda-tions in Chapter 4 of the ALWR Requirements Document concerning the steam gener-ator. The following questions are meant to elicit this mi:ising infonnation.

Your response on design improvements incorporated in the steam generators need not be limited to the specific areas addressed below.

251.1 A discussion of past corrosion problems that have occurred in Combustion Engineering steam generators should be presented with a discussion of specific features or operating recocnendations that will prevent similar problems in the CESSAR-DC steam generators.

250.2 Are all crevices between the tube and tubesheet removed? Is an explosive or hydraulic expansion method used? How is the expansion method qualified with respect to minimizing residual stresses that could lead to 1GSCC 7 250.3 Is stress relief used to minimize residual stresses after the tube bundle is assembled?

251.4 Are tube supports designed to ensure that continous dry out does not occur ,

at tube-to-support locations? In what manner is fretting and wear prevented? i Does the support grid act as a structural node under all operating conditions?

How it resistance to fluidelistic vibration prevented in cross flow regions?

Do support crids present a convex surface to the tube?

251.5 How is resistance to corrosion and fretting or wear prevented considering the possible concentration of corrodants that may take place in upset chemistry?

251.6 Is blowdown capacity in excess of 1% to allow rapid cleanup? Is the blowdown designed to facilitate removal of particulates?

251.7 The ALWR Requirements Document specifies that access openings and/or inspection ports shall be provided for the primary side manway having a minimum of 21 inch ID and that ports shall be provided for secondary side tube

1 -2 sheet access ano access to inspect the U-bend area. The staff is especially concerned that provision be provideo for loose parts surveillance. Please describe access for loose parts surveillance, cleaning and maintenance, as well as eddy current inspection.

251.8' Art a sufficient number of manways incorporated so that access is available to untubed regions of the secondary side? Are hand holes installed to provide access at tube support elevations?

251.9 Describe the program for inservice inspection of steam generator tubing r,1ving details of the necessary inspection equiptaent and procedures, including the sarple selection requirements.

251.10 An evaluation should be presented to determine the extent of steam generator tube wall thinning that can be tolerated under accident conditions.

Using this calculation and allowances for postulated operational degradation (from corrosion) and for eddy current testing error, a value for the recom-mended plugging limit should be determined.

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