ML18153A937
| ML18153A937 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 04/29/1994 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 94-276, NUDOCS 9405100299 | |
| Download: ML18153A937 (9) | |
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 29, 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.94-276 NO/ETS Docket Nos.
50-280 License Nos.
DPR-32 During the recent refueling outage, Surry Unit 1 completed its second ten-year interval inservice inspections.
Examinations during this interval were conducted to the requirements of the 1980 Edition and Winter 1980 Addenda of ASME Section XI.
Pursuant to 1 O CFR 50.55a (g) 5, relief is requested from certain requirements of ASME Section XI associated with partial examinations conducted during the 1994 Surry Unit 1 refueling outage. Relief request, RR-020, is attached and provides the basis of this raque~.
This 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, Q,PCWJ~
~i:Y' W. L. Stewart 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
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9405100299 940429 PDR O ADOCK 05000280
. Q PDR Surry Power Station Unit 1 ISi Examination Relief
e Relief Request SR-020 I.
Identification of Components Weld No.
Line/Mark No.
System Drawing Number Class 1-12 27\\"-RC-6-2501R RC 11.4 4 8-WMKS-O 10 lAZ-1 1-19 31"-RC-8-2501R RC 11448-WMKS-0102AZ-1 2-09 1-RC-E-lA RC 11448-WMKS-RC-E-lA.2 2-02 1-RC-E-lA RC 11448-WMKS-RC-E-lA.1 1-RC-E-1B RC 11448-WMKS-RC-E-lB.1 1-RC-E-lC RC 11448-WMKS-RC-E-lC.l 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%.
III. 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 limita-tions 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 require-ments.
1 1
2 2
2 2
Table SR-020-1 Surry Unit 1 Exanination Coverage Estimates (Piping)
UT Scan Coverage%
\\.leld No.
Category Item No.
2 5
7 8
Reason For Partial Sketch/Drawing No.
1-12 B-J B9.11 38 57 100 100 Pipe to Reactor 1/
Coolant pump config-11448-\\.IMKS-0101AZ-1 uration. 2t Calibre-tion achived maximum coverage practicable.
1-19 B-J B9.12 84 84 92 92 Code Fabrication Tag 2/
configuration.
11448-\\.IMKS-0102AZ-1
IJeld No.
2*09 (0°*360°)
Beam Angle 0
45 45 45 60 60 60 Table SR-020-2 Surry Unit 1
- Examination Coverage Estimates (Nozzle To Shell)
Category C-B, Item CZ.21 Exam Area Scan Direction
%Exam IJeld & Base 100 IJeld & Base 2
83 IJeld & Base 5
83 IJeld & Base 7 & 8 100 IJeld & Base 2
90.4 IJeld & Base 5
91 IJeld & Base 7 & 8 100 Reason For Partial Sketch/Drawing No.
IJeld configuration, 3
and support band.
11448*1JMKS*RC*E*1A.2 011 to 1611 examined in 1986 and 1611 to 33 11 examined in 1988. 360° was examined in 1994, because examination results from earlier examinations did not give specific scan coverage percentages. The examination reports indicated what caused limitations, but not the degree of limitation by scan.
UT Scan Direction Definitions.
2 - Axial scan pipe side of weld 5 - Axial scan nozzle/shell side of weld 7 - Circumferential scan, clockwise 8 - Circumferential scan, counterclockwise
Weld No.
Beam Angle 2*02 0
0 co 0 -360°>
45 45 45 45 45 60 60 60 60 60 Table SR-020-3 Surry Unit 1
- Examination Coverage Estimates (Steam Generator)
Category C-A, Item C1.30 Exam Area Scan Direction
%Exam Weld 100 Base Metal 100 Weld 2
98.6 Weld 5
91.7 Weld 7 & 8 100 Base Metal 2 & 5 99 Base Metal 7 & 8 100 Weld 2
95 Weld 5
84.5 Weld 7 & 8 100 Base Metal 2 & 5 99%
Base Metal 7 & 8 100%
Reason For Partial Sketch/Drawing No.
Handholes, 11448*WMKS*RC*E*1A.1 nozzles and 11448*WMKS*RC*E*1B.1 welded lugs 11448*WMKS*RC*E*1C.1
- Estimates are based on 1988 and 1994 examination results. Earlier examination results (Period 1) occurred prior to our procedures requiring specific scan coverage percentages. The examination reports indicated what caused limitations, but not the degree of limitation by scan.
UT Scan Direction Definitions.
2
- Axial scan tube sheet side of weld 5
- Axial scan shell side of weld 7 - Circumferential scan, clockwise 8
- Circumferential scan, counterclockwise Steam Generator "A" 1994 Examined 284"
- 0" Steam Generator "B" 1988 Examined 142"
- 284 11 Steam generator "C" 1986 Examined 011
- 14211
Weld 1-12 on line 27~"-RC-6-2501R
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27.5" COLD LEG PIPE Sketch 1
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I
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I
- a, RCP
e Weld 1-19 on line 31"-RC-8-2501R Look ng down on elbow W-1-09 L 2"
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W-1-19
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_:: ii,, - -- -
w-1-09
i 1 "
J W-1-19 4
L 2
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Sketch 2 ntr-odos
- 1 Steam Generator Weld 2-09 5 75" ~
. 7"
%%0 VESSEL SIDE (2 SIDE) 5 75" ~
. 7**
VESSEL SIDE (2 SIDE)