ML18153B022
| ML18153B022 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 07/25/1994 |
| From: | Ohanlon J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 94-276A, NUDOCS 9408020083 | |
| Download: ML18153B022 (4) | |
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VIRGINIA. ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 July 25, 1994 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PROGRAM RELIEF REQUEST Serial No.
94-276A NO/ETS Docket Nos.
50-280 License Nos. DPR-32 In our April 29, 1994 letter (Serial No.94-276), we requested relief from certain requirements of ASME Section XI associated with partial examinations conducted during the 1994 Surry Unit 1 refueling outage. During a telephone conference call with your staff on July 12, 1994, additional information regarding the specific examination coverage of weld 1 "'.12 was requested. Relief Request, SR-020, has been revised to provide the additional examination information. The affected pages of SR-020 are attached.
This revised relief request has been reviewed and approved by the Station Nuclear Safety and Operating Committee.
Should you have any additional questions or require additional information, please contact us.
Very truly yours,
~uYcW-~
James P. O'Hanlon Senior Vice President - Nuclear Attachment cc:
U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station
Surry Power Station Unit 1 Revised Relief Request SR-020
Relief Request SR-020, Revision 1 I.
Identification of Components Weld No, Line/Mark No.
System Drawing Number Class 1-12 27"-RC-6-2501 R RC 11448-WMKS-0101 AZ.-1 1
1-19 31 "-RC-8-2501 R RC 11448-WMKS-0102AZ.-1 1
2-09 1-RC-E-1A RC 11448-WMKS-RC-E-1 A.2 2
2-02 1-RC-E-1A RC 11448-WMKS-RC-E-1 A.1 2
1-RC-E-18 RC 11448-WMKS-RC-E-18.1 2
1-RC-E-1C RC 11448-WMKS-RC-E-1 C.1 2
System Abbreviations RC - Reactor Coolant System II.
Impracticable Code Requirements The 1980 Edition, Winter 1980 Addenda (inclusive) of ASME Section XI in Tables IWB-2500-1 and IWC-2500-1 does not allow any limitations to the required volumetric and surface examinations. Code Case N-460 (Alternative Examination Coverage For Class 1 and Class 2 Welds) allows a reduction in coverage, if the reduction is less than 10%.
Ill.
Basis For relief The components listed above have been examined to the extent practicable as required by the Code. Due to interferences of other components or weld joint geometry the reduction in coverage for the listed components was greater than 10%. Tables SR-020-1, 2 and 3 are provided detailing the limitations experienced. Amplifying sketches or drawings are also provided. Alternative components could not be substituted for examination due to the mandatory selection requirements of the Code, or because the examination coverage attained was representative of what could be expected for that type configuration.
IV.
Alternate provisions It is proposed that the examinations already completed at the reduced coverage be counted as meeting the Code requirements.
Weld No, Category Item No, 1-12 B-J B9.11 1-19 B-J B9.12 Table SR-020-1, Revision 1 Surry Unit 1 Examination Coverage Estimates (Piping)
UT Scan Coverage %
- 2.
- 5.
z 38 57 100 84 84 92
.a 100 92 Reason For Partial Pipe to Reactor Coolant pump config-uration. 2t Calibration achived maximum coverage practicable.
Code* Fabrication Tag configuration.
Sketch/Drawing No, 1/
11448-WMKS-0101AZ-1 (see note 1) 2/
11448-WMKS-0102AZ-1 Note 1: Coverage shown on Sketch 1 for weld 1-12 represents coverage attained with a custom designed focused 45° dual element longitudinal wave (TRL) search unit supplemented by an extended 45° shear wave examination. The extended 45° shear wave examination was applied only to the forged side (pipe side) of the weld. The forged side of weld 1-12 was covered in two directions while the cast side could only be partially covered in one direction. Virginia Electric and Power Company has demonstrated the 45° TRL search unit used for this examination to the ANII on the Westinghouse Owner's Group cast austenitic blocks. The selection of the 45° TRL search unit for this examination is based upon Westinghouse Report 11778 "Demonstration of Flaw Detection and Characterization Capability for Ultrasonic Examination of Main Coolant Loop Welds" of March, 1988. Virginia Power has not qualified a UT procedure employing higher (S0° or 70°) beam angles to detect planar flaws in cast austenitic material because we do not believe that a so* or 70° beam angle would provide meaningful results on the cast austenitic side of the weld.
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