View source for TXX-4010, Submits Addl Info Re FSAR Submittal Concerning D4/D5 Steam Generator Tube Vibration Fix.Existing Chapter 15 Accident Analyses Envelop All Changes in Parameters Resulting from Vibration Fix

{{Adams
| number = ML20077B674
| issue date = 07/19/1983
| title = Submits Addl Info Re FSAR Submittal Concerning D4/D5 Steam Generator Tube Vibration Fix.Existing Chapter 15 Accident Analyses Envelop All Changes in Parameters Resulting from Vibration Fix
| author name = Schmidt H
| author affiliation = TEXAS UTILITIES SERVICES, INC.
| addressee name = Youngblood B
| addressee affiliation = NRC
| docket = 05000445, 05000446
| license number = 
| contact person = 
| document report number = TXX-4010, NUDOCS 8307250370
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 1
}}

=Text=
{{#Wiki_filter:TEXAS UTILITIES SERVICES INC.           Log # TXX-4010 mn nnus u,w nnuu_mmum   n.=        File # 905.4 July 19, 1983 Mr. B. J. Youngblood U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C. 20555

==SUBJECT:==
COMANCHE PEAK STEAM ELECTRIC STATION DOCKET NOS. 50-44E AND 50-446 D4/D5 STEfe! GENERATOR MODIFICATIONS ADDITIONAL INFORMATION

==Dear Mr. Youngblood:==

The following additional information addresses items of concern voiced by tha NRC regarding the CPSES FSAR submittal describing the D4/D5 Steam Generator Tube Vibration Fix.
Item 1. Accident Analysis Satement The existing CPSES Chapter 15 accid;nt analyses envelope all changes in parameters resulting from the Steam Generator Tube Vibration Fix.
Item 2. Quality Assurance Statement CPSES applies 10 CFR 50 Appendix B, quality assurance to the steam generator modifications. All field work is performed in accordance with the appropriate sections of Westinghouse WCAP-8370 Rev. 9A and Addendum #1 "WRD Quality Assurance Plan",
Westinghouse NSID, " Quality Assurance Program Plan" WCAP-9245 Rev. 6, and pertinent CPSES quality assurance requirements.
Eddy current testing complies with the procedures established by the ASME Code, Section XI, "In-service Inspection", and Regulatory Guide 1.83, "In-service Inspection of Pressurized Water Reactor Steam Generator Tubes", for the selection of
           -tubes to be tested and the frequency of testing.
Should you have additional questions, please contact me.
                                                            'ncerely, H. C. Schmidt 4
BSD: tis 8307250370 830719                                                                 I 0 PDR ADOCK 05000445 A                 PM     .}}