ML20080P502

Advises of Plans to Perform Approved Mod on Unit 2 Model D5 Steam Generators & Provides plant-specific Details Required by NUREG-1014.Mods to Unit 1 Steam Generators Will Be Completed Prior to Fuel Loading Date of 840501

ML20080P502
Person / Time
Site:	Catawba
Issue date:	02/20/1984
From:	Tucker H DUKE POWER CO.
To:	Adensam E, Harold Denton Office of Nuclear Reactor Regulation
References
RTR-NUREG-1014 NUDOCS 8402220564
Download: ML20080P502 (7)

Text

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DUKE POWEn GoxPm P.O. HOX 33180 CHAHLOTTE, N.C. 28242 HAI ll.Tt*CKER Trotenome 41448PWPSEDSWT (70-4)37'N 531 m . . P-==- February 20. 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Ms. E. G. Adensam, Chief j Licensing Branch No. 4 Re: Catawba Nuclear Station Docket Nos. 50-413 and 50-414

Dear Mr. Denton:

During October 1983 the NRC issued a Safety Evaluation Report related to the proposed modification of Westinghouse Model D4/D5/E Steam Generators (NUREG-1014).

This SER concluded that the proposed modification was acceptable pending plant-specific verification and that the modified steam generators could be operated at 100 percent of their design capacity.

The purpose of this letter is to advise the NRC of Duke Power Company's plans to perform this approved modification on the Catawba Unit 2 Model D5 steam generators and to provide the plant-specific details required by NUREG-1014.

The attached report addresses these items.

As described in my letter of May 18, 1983, the modification to the Catawba Unit 1 Model D3 Steam Generators has been completed prior to the anticipated fuel loading date of May 1, 1984.

Very truly yours, n>

0 W /$

Hal B. Tucker ROS/php Attachment cc: Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission Region ll 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303 NRC Resident inspector Catawba Nuclear Station 00 Palmetto Alliance ' I\

21351 Devine Street Columbia, South Carolina 29205 8402220564 840220 PDR ADOCK 05000413 A PDR

c Mr. Harold R. Denton, Director February 20, 1984 Page 2 cc: Mr. Robert Guild, Esq.

Attorney-at-Law P. O. Box 12097 ,

Charleston, South Carolina 29412 Mr. Jesse L. Riley '

Carolina Environmental Study Group 854 Henley Place '

Charlotte, North Carolina 28207 t

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i Duke Power Company Catawba Nuclear Station Unit 2 Steam Generator Modification

1.0 INTRODUCTION

The purpose of this report is to outilne the plant-specific details  ;

relative to the Catawba Unit 2 Model D5 steam generator modification.

During October,1983, the NRC issued the Safety Evaluation Report for the proposed modification to Westinghouse Model D4/DS/E steam generators (NUREG-1014). This SER is generically applicable to all nuclear units with counterflow steam generators since it approvas the modifications common to all plants while emphasizing that the extent of these modifica-tions depends on the number of loops and the specific model of steam generator. Catawba Unit 2 is a four-loop plant with Model D5 steam l generators. Therefore the modification for Catawba Unit 2 consists of I tube expansion for 124 tubes per steam generator and diversion of 10%

main feedwater flow to the auxiliary feedwater nozzle.

The piping changes for feedwater flow diversion consist of the addition of. an orifice in the main feedwater pipe to increase flow resistance downstream of the new auxiliary feedwater bypass connection (see attached figures). A path for reverse flushing of the feedwater line was also added for compatibility with the Unit I changes as shown by the 1" dashed lines. Appropriate logic and alarms will be added to inform the operator of high flow through the main nozzle. Work is nearing completion for this part of the modification with tube expansion scheduled to begin in February, 1984. All work on the modification of the Catawba Unit 2 steam generators will be completed prior to fuel loading.

The Technical Review Committee (TRC) in its report dated July 18, 1983, identified three specific items to be addressed by each utility. These l l Items are as follows:

l l 1) Transient analysis margins l 2) Tube plugging margins l l

l 3) First cycle inspection interval i As a result of the NRC Staff's review of the TRC report, the following additional requirements were noted in NUREG-1014:

1) On a plant specific basis, the minimum wall thickness and plugging

j. criteria for the expanded regions shall be established in accordance with Regulatory Guide 1.121.

2) The Staff requires that the basic document for the selection of tubes to be tested and for frequency of testing shall be NUREG-0452.

For the lead plant, the first inservice inspection of the steam generator tubes shall be conducted after 6 full-power monthe and

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g befor e 12 full-power months of operation, including a special inspection of the expansion regions in all expanded tubes. For the remaining plants, the first inservice inspection requirements will be based on available data. Future inservice inspections on all plants shall always include the expanded regions in a sample of expanded tubes as a special subset of inspections.

The means by which each of the above items will be implemented on Catawba Unit 2 are described in subsequent sections of this report.

2.0 Transient Analysis Ma. gins As a result of the 10% flow diversion to the auxiliary feedwater nozzle, the average temperature of the primary coolant will be increased by approximately 0.6 F to maintain the original steam pressure. This is not expected to have any impact on the current Chapter 15 analyses but may require documentation in Chapter 5. Westinghouse is currently investigating the transient analysis margins for Catawba Unit 2 and will provide an update to the FSAR in the near future.

3.0 Tube Plugging Margins The acceptance criteria for tubes following inservice inspection at Catawba Unit 2 are summarized in the Catawba Unit 2 Technical Specifica-tions. These minimum wall thickness and plugging criteria apply to the expanded tubes and are based on Regulatory Guide 1.121.

4.0 Inservice Inspection Based on current schedules, Catawba Unit 2 will not be the lead plant for the Model D5 modification. Therefore, the requirement that the lead plant shut down for tube inspection during its first cycle of full power opera-tion will not apply to Catawba Unic 2. The frequency of inservice inspec-tion and the selection of tube to be tested will be based on NUREG-0452.

Catawba Unit 2 steam generator inspections will always include samples of expanded tubes as a special subset of inspections.

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