ML20148J248
| ML20148J248 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 03/23/1988 |
| From: | Counsil W, Walker R TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | Martin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| IEB-88-002, IEB-88-2, TXX-88330, NUDOCS 8803300213 | |
| Download: ML20148J248 (3) | |
Text
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MEE log i TXX-88330 2
File # 10119 l
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Ref. # Bulletin 88-02 nlELECTRIC March 23,1988
% mism G. Coumil Executhe Vwe hesiJmt Mr. Robert D. Martin Regional Administrator, Region IV U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011
SUBJECT:
COMANCilE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-4d5 AND 50-446 NRC BULLETIN 88-02 RAPIOLY PROPAGATING FATIGUE CRACKS IN STEAM GENERATOR TUBES Gentlemen:
The following CPSES information is provided in response to each item as required by the NRC Bulletin 88-02, "Rapidly Propagating Fatigue Cracks in Steam Generator Tubes:"
Response to Item A CPSES Unit 1 steam generators are Westinghouse Model 04.
CPSES Unit 2 steam generators are Westingbouse Model 05.
This bulletin is applicable to Unit I steam generators only.
A baseline eddy current test was performed in 1982, llowever, this inspection does not meet the 40 month bulletin requirement.
An inspection of rows 1 and
-2 was performed on each steam generator in 1986 as a result of heat treating Unit 1 tubes. Although not. a representative sample, this inspection accounted for more than 3% of the tubes in each steam generator.
No denting (tube deformation) was found at the upper tube support region.
Eddy current inspection activities (meeting applicable bulletin requirements) will be performed prior to or during the first refueling outage in accordance with the i
CPSES Technical Specifications.
The enhanced primary-to-secondary leak rate monitoring program is not applicable to CPSES since: 1) CPSLS Unit 1 is not yet operational and 2) denting due to corrosion, should it occur af ter becoming operational but prior to the first refueling outage, is not expected to degrade the tubes to the extent that enhanced monitoring is required.
Response to Item B Future eddy current test results for the Unit I steam generators will be examined for denting at the upper tube support plate as defined in item A of the bulletin.
These eddy current inspections will be conducted as per the requirements of the CPSES Technical Specifications.
Should evidence of d
denting be found, the requirements of Bulleting Item C will be implemented.
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l TXX-88330 March 23, 1988 Page 2 of 2 Response to item C This item is not applicable to CPSES.
Very truly yours, W. G. Counsil By:
@ k R. D. 1alker Manager, fluclear Licensing MCP/clk c - U.S. fluclear Regulatory Commission (original)
Document Control Desk Washington, D.C.
20555 Resident inspectors, CPSES (3)
Attachment to IXX-88330 March 23,-1988
-Page 1 of 1 UNITED STATES OF AMERICA i'
NUCLEAR REGULATORY COMMISSION In the Matter of
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Texas Utilities Electric Company Docket Nos. 50-445 50-446 (Comanche-Peak Steam Electric
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Station, Units 1 & 2)
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AFFIDAVIT R. D. Walker being duly sworn, hereby deposes and says that he is Manager, Nuclear Licensing of TV Electric,.the Applicant herein; that he is duly authorized to sign and file with the Nuclear Regulatory Commission this response to NRC Bulletin 88-02 that he is familiar with the content thereof; and that the matters set forth therein are true and correct to the best of his knowledge, information and belief.
OT$A R. 9. Walker Manager, Nuclear Licensing STATE OF TEXAS
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COUNTY OF DALLAS y
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M My commission expires: d02k /9)D
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