ML18153B338
| ML18153B338 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 10/08/1993 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18151A518 | List: |
| References | |
| 93-608, NUDOCS 9310150178 | |
| Download: ML18153B338 (23) | |
Text
{{#Wiki_filter:ACCELERATED DOCUMENT DISTRIBla(ION SYSTEM _;. _ , 1 REGULATC.- INFORMATION DISTRIBUTION.STEM (RIDS) ACCESSIO~ NBR:9310150178 DOC.DATE: 93/10/08 NOTARIZED: NO DOCKET# FACIL~50~2a1 Surry Power Station, Unit 2, Virginia Electric & Powe 05000281 AUTH.NAME AUTHOR AFFILIATION .. ... R STEWART,W.L. Virginia Power (Virginia Electric & Power Co.) RECIP.NAME RECIPIENT AFFILIATION I Document Control Branch (Document Control Desk)
SUBJECT:
Forwards ISI program Relief Request SR-021 for partial exams D conducted during 1993 Surry Unit 2 refueling outage. s DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR _JENCL _j_ SIZE:-~~------1/....._~~ 1 TITLE: OR Submittal: Inservice/Testing/Relief from ASME Code I NOTES:lcy NMSS/SCDB/PM. 05000281 A RECIPIENT COPIES RECIPIENT COPIES D ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 0 PD2-2 PD 1 1 D BUCKLEY,B 2 2 INTERNAL: ACRS 6 6 AEOD/DSP/ROAB 1 1 s NRR/DE/EMEB 1 1 NRR/EMCB 1 1 NUDOCS-ABSTRACT 1 1
~~~CB 1 0 OGC/HDS2 1 0 iG(IL]} 01 1 1 RES/DSIR/EIB 1 1 EXTERNAL: EG&G BROWN,B 1 1 EG&G RANSOME,C 1 1 NRC PDR 1 1 NSIC 1 1 NOTES: 1 1 R'
I D s I A NOTE TO ALL "RIDS" RECIPIENTS: D PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATE YOUR NAME FROM DISTRIBUTION D LISTS FOR DOCUMENTS YOU DON'T NEED! s TOTAL NUMBER OF COPIES REQUIRED: LTTR 23 ENCL 20
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 October 8, 1993 United States Nuclear Regulatory Commission Serial No. 93-608 Attention: Document Control Desk NO/ETS RO Washington, D. C. 20555 Docket Nos. 50-281 License Nos. DPR-37 Gentlemen: VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PROGRAM RELIEF REQUEST Surry Power Station Unit 2 is presently in the third period of its second ten-year interval for inservice inspections. Examinations during this interval have been conducted to the requirements of the 1980 Edition and Winter 1980 Addenda of ASME Section XI. Pursuant to 10 CFR 50.55a (g) 5, relief is requested from certain requirements of ASME Sec.1ion XI associated with partial examinations conducted during the 1993 Surry Unit 2 refueling outage. Relief request, RR-021, is provided detailing the basis of these requests. These relief requests have 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, Jt ~c9 _(..--.. -7*
~'"' / ,...._
W. L. Stewart
/ -.
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Senior Vice President - Nuclear Attachments 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 1/0'fJ L
.r i. I Attachment 1 Surry Power Station Unit 2 ISi Examination Relief
.l ,, I Relief Request SR-021 I. Identification of Components Weld No. Line/Mark No. System Drawing Number Class 1-01 02-RC-R-1 RC 11548-WMKS-RC-R-1.2 1 1-10 31 "-RC-308-2501 R RC 11548-WMKS-RC-10-1 1 1-12 27.5"-RC-309-2501 R RC 11548-WMKS-RC-10-1 1 1-13 27.5"-RC-309-2501 R RC. 11548-WMKS-RC-10-1 1 1-14 27.5"-RC-309-2501 R RC 11548-WMKS-RC-10-1 1 1-22 29"-RC-307-2501 R RC 11548-WMKS-RC-10-1 1 2-02 02-RC-E-1A RC 11548-WMKS-RC-E-1 A.1 2 02-RC-E-18 11548-WMKS-RC-E-1 8.1 2 02-RC-E-1C 11548-WMKS-RC-E-1C.1 2 2-06 02-RC-E-1A RC 11548-WMKS-RC-E-1A.1 2 02-RC-E-1C 11548-WMKS-RC-E-1 C.1 2 1-A01 02-RH-E-1A RH 11548-WMKS-RH-E-1 A 2 1-801 02-RH-E-18 RH 11548-WMKS-RH-E-18 2 System Abbreviations RC - Reactor Coolant System RH - Residual Heat Removal System
- 11. Impracticable Code Requirements The 1980 Edition, Winter 1980 Addenda (inclusive) of ASME Section XI in Tables IW8-2500-1 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%.
111. 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-021-1, 2, 3, 4 and 5 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
I 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-021- 1 SUrry ~ft 2 9£.l!l!!!!in!!t!m ~ E:tf=t= (lle=:to;- Veasel) category B-A. ltm B1 .40 Weld No. Beam Angle Exam Area Scan Direction XExam Reason For Partial Sketch/Drawing No. 1-01 0 Weld 97 Proximity to 1 (0°-360°) 45 Weld 2 28 Flange and lifting 11548-WMKS-RC-R-1.2 45 Weld 5 97 Lug Interference. 45 Weld 7 97 Lifting lugs are 45 Weld 8 97 approximately 511 60 Weld 2 14 in width. 60 60 60 Weld Weld Weld 5 7 8 97 97 97 e 45 &60 Base 2 36 45 &60 Base 5 96 45 &60 Base 7 84 45 &60 Base 8 84 0 Base 84
- Estimates are based on 1991 and 1993 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 D1rect1on Det1n1t1ons. 2 - Axial scan flange side of weld 5 - Axial scan head side of weld 7 - Circunferential scan, clockwise (looking down on head) 8 - Circunferential scan. couiterclockwise (looking down on head)
Table sa-021-2 Slrry U,ft 2 EJuainatfan Coverage Estf*tes (Pfpins> UT Scan Coverage X Weld No. Category Item No. 2 5 7 8 Reason For Partial Sketch/Drawing No. 1*10 B*J B9.11 100 60 100 100 Pipe to elbow Jofnt 2 configuration. 11548*WMKS*RC*10*1 1*12 B*J B9.11 56 86 100 100 Pipe to Reactor 3 Coolant~ config* 11548-WMKS*RC-10*1 uretion. 2t Calibre* tion 1chlved IIIDXflllll 1*13 B*J B9.11 86 56 100 100 coverage practicable. Pipe to valve conflg* 3 e uretlon. 2t callbr1* 11548-WMKS*RC-10*1 tlon achieved 1111xt111111 coverage practicable. 1*14 B*J B9.11 56 86 100 100 Pipe to valve conflg* 3 uretfon. 2t calibre* 11548*WMKS*RC*10*1 tion tchfeved 11axi111111 coverage practicable. 1-22 B*J B9.11 98.6 61 100 100 Valve to elbow conflg* 4A/4B uretlon. 11548*WMKS*RC*10*1
Table SR-021-3 SUrry lhit 2
*Ex*ination ~ Estil!:stes (Sts- Gei1ea~aturi category C-A, ltea C1.30 lleld No. Beam Angle Exam Area Seen Direction XExam Reason For Partial Sketch/Drawing No.
2-02 0 lleld &Base 96 Handholes, 1154S*"'4KS*RC-E*1A.1 (0°-360°) 45 lleld &Base 2 96 blowdown piping, 11548*"'4KS*RC-E*1B.1 45 lleld &Base 5 80 end nozzles 1154S*11MKS*RC-E*1C.1 45 lleld &Base 7 96 45 lleld &Base 8 96
&Base 60 60 60 60 lleld lleld lleld lleld
&Base
&Base
&Base 2
5 7 8 96 80 96 96 e
- Estimates ere based on 1988 end 1993 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 11A11 1983 Examined 21 11 - 14411 Steam Generator 11 811 1988 Examined 14411
- 284 11 Steam generator 11 c11 1993 Examined 284 11 - 21 11
Table SR-021-4 Slrry lklit 2
*Exaination Coverage Esti*tes (Stea Gener!!tor) category C-A. ltea C1.10 Weld No. Beam Angle Exam Area Scan Direction XExam Reason For Partial Sketch/Drawing No.
0 Weld & Base 96.4 Insulation supports. 11548*WMKS*RC*E*1A.1 45 &60 Weld &Base 2 96 welded pads, 11548-MMKS*RC*E*1C.1 45 &60 Weld &Base 5 82.8 and nozzles 45 &60 Weld, Base 1 96.4 45 &60 Weld &Base 8 96.4
- Estimates are based on 1991 ind 1993 examination.results. Earlier ex11111ination 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.
e UT Scan Direction Definitions. 2
- Axial scan transition side of weld 5 - Axial scan shell side of weld 7
- Circllllferential scan, clockwise 8 - Circllllferential scan, counterclockwise Steam Generator 11A11 1983 Examined 011 - 18411 Steam Generator 11 c11 1991 Examined 18411 - 36911 Stearn generator 11 c11 1993 Examined 36811 - 552 11
Table SR-021-5 Slrry ltli t 2
'*Exaaination Coverage Estimtes (RH heat Exchareer>
category C-A. I tea C1 .20 Weld No. Beam Angle Exam Area Scan Direction XExam Reason For Partial Sketch/Drawing No. 1*A01/ 45 Weld &Base 2 62 welded supports, 11548*WMKS*RH*E*1A 1-801 45 Weld &Base 5 54.5 and nozzles. 11548*WMKS*RH*E*1B (0°-360°) 45 Weld &Base 7 62 45 Weld &Base B 62
- 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 seen. An extended beam bath was used to increase coverage. e UT Scan Direction Definitions.
2
- Axial seen bottom side of weld 5
- Axial seen top side of weld 7 - Circ1.111ferentlel seen, clockwise B
- Circ1.111ferentiel seen, counterclockwise 02*RH-E-1A "Yeld 1*/\01 11 1988 Examined 44n - 8811 02*RH*E*1B "Weld 1*B01" 1986 Examined 011
- 44 11 02*RH*E*1B "Weld 1*901 11 1993 Examined 8811
- 011
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""'- ' - TYPICAL CONTROL ROO DRIVE HOUSING WELD SECTION A-A
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Weld 1-10 OD Line 31 11 -RC-308-2501R I<!- -l>I 2" 5 scan 2 scan 2 scan e Reactor Coolant p~ Elbow D C 0.968" (1/3t) 1/4" F 3" 1/4"
.I 3.5" Exam. Vol.
C-D-E-F l)"awlng ~t To Sc11Je Sketch 2
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Weld 1-22 OD Line 29 11 -RC-307-2501R 5 scan 2 scan 2 scan e Valve t.OV-2594 D
- 1. 090" (1/ Jt) 1/4" F
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- OVERSIZE DOCUMENT PAGE PULLED SEE APERTURE CARDS NUMBER OF OVERSIZE PAGES FILMED ON APERTURE CARDS _..__I__
APERTURE CARD/ HARD COPY AVAILABLE FROM RECORDS AND REPORTS MANAGEMENT BRANCH
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. I M A R V FILE LOCATION/LEVEL CSB ~: I I I I I I I I ,,,,l FCEN F'I F2 F3 NOTES/SPECIAL INSTRUCTIONS INDEXER QC DOC Generate New Label Geneictle New klDS ~heel NUCLEAR DOCUMENTS SYSTEM Encl Contains Prop Info Refilm: PDR CF PROP Encl Contains Foldout Paqe, Do Not Refilm ACM IN : L..J.......J._..L...J RIOS:
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