ML18153B022: Difference between revisions
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Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station | Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station | ||
Attachment 1 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. | 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. | IV. Alternate provisions It is proposed that the examinations already completed at the reduced coverage be counted as meeting the Code requirements. | ||
Table SR-020-1, Revision 1 Surry Unit 1 Examination Coverage Estimates (Piping) | Table SR-020-1, Revision 1 Surry Unit 1 Examination Coverage Estimates (Piping) | ||
UT Scan Coverage % | UT Scan Coverage % | ||
| Line 40: | Line 38: | ||
Coolant pump config- 11448-WMKS-0101AZ-1 uration. 2t Calibration achived maximum coverage practicable. | Coolant pump config- 11448-WMKS-0101AZ-1 uration. 2t Calibration achived maximum coverage practicable. | ||
(see note 1) e 1-19 B-J B9.12 84 84 92 92 Code* Fabrication Tag 2/ | (see note 1) e 1-19 B-J B9.12 84 84 92 92 Code* Fabrication Tag 2/ | ||
configuration. 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 | configuration. 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.}} | ||
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.}} | |||
Revision as of 22:09, 2 February 2020
| 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) | |
Text
e e VIRGINIA. ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 July 25, 1994 United States Nuclear Regulatory Commission Serial No. 94-276A Attention: Document Control Desk NO/ETS Washington, D. C. 20555 Docket Nos. 50-280 License Nos. DPR-32 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PROGRAM RELIEF REQUEST 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
Attachment 1 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.
Table SR-020-1, Revision 1 Surry Unit 1 Examination Coverage Estimates (Piping)
UT Scan Coverage %
Weld No, Category Item No, 2. 5. z .a Reason For Partial Sketch/Drawing No, 1-12 B-J B9.11 38 57 100 100 Pipe to Reactor 1/
Coolant pump config- 11448-WMKS-0101AZ-1 uration. 2t Calibration achived maximum coverage practicable.
(see note 1) e 1-19 B-J B9.12 84 84 92 92 Code* Fabrication Tag 2/
configuration. 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.