ML20236T677
| ML20236T677 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak |
| Issue date: | 07/22/1998 |
| From: | Terry C, Walker R TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TXX-98170, NUDOCS 9807280326 | |
| Download: ML20236T677 (53) | |
Text
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""" 9 Log # TXX-98170 I
5 File # 10010.1 905.2 (clo)
MtELECTRIC Ref. # 10CFR50.55a(g)(5)(iii)
July 22,1998 i
. c.tm nrry j'
5enior Hee Pmident
& PrincipalNuclear Oficer L
' U. S. Nuclear Regulatory Commission L
Document Control Desk l
Washington, DC 20555 1
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)- UNIT 1 y
DOCKET NO. 50-445 RELIEF REQUESTS TO THE UNIT 1 INSERVICE INSPECTION PROGRAM (1986 EDITION OF ASME CODE, SECTION XI, NO ADDENDA, INTERVAL START DATE: AUGUST 13,1990, FIRST INTERVAL)
TU Electric has determined that certain inspection requirements of Section XI of the ASME are impractical, and is requesting relief in accordance with the requirements of 10CFR50.55a(g)(5)(iii). This transmittal submits relief requests B-6 Revision 2, B-7 Revision 2, B-12, B-13, B-14, and C-9 (Attachments 1, 2, 3, 4, 5, and 6 respectively) for your approval.
This communication contains no new licensing basis commitments regarding CPSES Unit 1.
If you have any questions, please contact Mr. Carl B. Corbin at
(
_ 254) 897-0121.
(
Sincerely, C. L. Terry B:
OELAr b 9807280326 990722 '
Y PDR ADOCK 05000445-RogFD. Walker
/
-P PDR Regulatory Affairs Manager CBC:cc
- Attachments i
.c-Mr. E. Merschoff, Region IV
' Mr. J. l. Tapia, Region IV (clo).
Mr. T. J. Polich, NRR Mr. G. : Bynog, TDLR Resident inspectors, CPSES
' { j C {)tr. J.' C. Hair, ANil.
COMANCHE PEAK STEAM ELEcrRIC STATION P.O. Box 1002 Glen Rose. Texas 76043 1002 I
f,, j,
' Attachment 1 to TXX-98170 Page 1 of 11 CPSES UNIT 1 RELIEF REQUEST B-6 REVISION 2 A.
Item (s) for which reliefis requested:
TBX-1-1300-1 TBX-1-1300-2 Reactor Vessel Closure Head B.
Item (s) Code Class:
1 C.
Examination requirement from which reliefis requested:
The requirement for volumetric examination of 100% of the weld lengths as described in Table IWB-2500-1, Examination Category B-A, Item No.'s Bl.40 and Bl.21.
Note - The CPSES ISI Plan requires that 1/3 of each of these welds 1,e examined each inspection period. A relief request revision is processed to document the specific limitations encountered during each examination.
D.
Basis for relief; Interferences from the reactor head flange, shroud and lifting lugs preclude the complete ultrasonic examination of the volume required by Fig.'s IWB-2500-3 and IWB-2500-5 as applicable.
Approximately 13% of the examination volume of weld TBX-1-1300-1 and 17% of the examination volume of weld TBX-1-1300-2 did not receive the full code required coverage during the first period examinations.
Approximately 15% of the examination volume of weld TBX-1-1300-1 and 17% of the examination volume of weld TBX-1-1300-2 did not receive the full code required coverage during the second period examinations.
Approximately 15% of the examination volume of weld TB>l-1-1300-1 and 17% of the examination volume of weld TBX-1-1300-2 did not receive the full code required coverage during the third period examinations.
l Page1of11
Attac$ ment 1 to TXX-98170 l
,Prge 2 of 11 CPSES UNIT 1 RELIEF REQUEST B-6 REVISION 2 I
(cont.)
Best effort examinations were performed during each period with the f circumferential scan coverage was obtained for both welds. Axial scan coverage w achieved in one beam path direction with two different beam angles fo i
of the examination volume of TBX-1-1300-1 and for approximately 97%
volume of TBX-1-1300-2.
See pages 3 through 11 for weldlocations and examination area config There were no recordable indications identified by the best effort volum performed or by the required surface examination performed on TB E.
Alternate examinations:
None Anticipated impact on the overail level of plant quality and safety:
F.
I None r
Page 2 of 11
^ ' - - - - - - - - - - _ _. _. _ _ _ _ _ _
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RELIEF REQUEST NO, B-6 REV. 2 PAGE 8 OF 11
, to TXX-98170 FIRST INSPECTION PERIOD RESULTS
' Pag) 8 of 11 WESTINGHOUSE NUCLEAR SERVICE DIVISION R $ 2, INSPECTION SERVICES j
i LIMITATION TO EXAMIN ATION PLANT
[QMAMAE PEAY N0 l YEX~I~lE00 AEV l UNIT SKETCH
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DATE avatn j
i RELATED TO: U/T X P/T MIT V/T ITEMISL I
I*I PROVIDE GENER AL INFORMATION TO DESCRIBE APPROXIMATE SIZE. LOCATION AND TYPE OF LIMITATION.
4 EX AM/ SCAN SURF ACE AREA
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AttIdiment 1 to TXX-98170 SECOND INSPECTION FERIOD RESULTS
- Page 9 of 11 I
WESTINGHOUSE NUCLEAR SERVICE DIVISION INSPECTION SERVICES
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LIMITATION TO EXAMINATION PLANT COMANCHE PEAK
. UNIT NO.1 SKETCH TBx-1-13OO REV.1 SYST./ COMP. R. V. CLOSURE HEAD PROCEDURE TX ISI-210 REV. 2 EXAMINER DATE 31295 F
K 3/ntfr RELATED TO:
1, 2, W PROVIDE OENERAL INFORMATIOtf TO DESCNE APPROXIMATE SIZE LOCAT1000 A8e TYPE OF LIMITAflON.
LIMITATIONS ARE DUE TO FLANGE. SHROUD AND LIFTING LUG. SEE WELD PROFILE 087AMED AT 1RF01 FOR EXAMMATION COVE WELD # 1 15% OF REQUmED EXAMWATION VOLUME NOT EXAMMED.
99% EXAMNED WITH THE 45 DEGREE AND SO DEGREE N AT LF.AST ONE DRECTION.
46 DEGREE - 8% NOT EXAMWED.
60 DEGREE 15% NOT EXAMWED.
WELD # 2 17% OF REQURED EXAMNATION VOLUME NOT EXAMesED.
97% EXAMINED WITH THE 45 DEGREE AND 60 DEGREE n AT LEAST ONE DmECTION.
45 DEGREE.11 % NOT EXAMMED.
60 DEGREE.17% NOT EXAMMED.
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'Page 1Q of 11
(
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WESTINGHOUSE NUCLEAR SERVICES DIVISION p
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en a
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LIMITATION TO EXAMINATION
=
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SKETCH TBX 11300 Rev.1 SYST/ COMP REACTOR COOLANT PROCEDURE TX4SI210. Rev. 4 FC N/A EXAMINER WiiNams. Mark MM[
LEVEL M
DATE 4/12/ss EXAMINER ' N/A LEVEL N/A DATE COMPONENT ID TBX-1 13001 RELATED TO O ur O PT e UT O vT PROVIDE SUFFICIENT INFORMATION TO DESCRIBE SIZE, LOCATION AND TYPE OF LIMITATION.
COMMENTS / SKETCH /DETAJL3 Limitations due to flange, shtoud and lifting lug. See 1RF01 prome for exam coverage.15% of requared volume not exarruned. 99%
exarruned with the 48* and 60* in at least one derection. 8% not examined with 45*.15% not exammed with 80*.
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RELIEF REQUEST NO. B-6 REV. 2 PAGE 11 OF 11 to TXX-98170 THIRD INSPECTION PERIOD RESILTS j
- P gs 11 of 11 1
---I-REPORT NO UT.st.132
==
WESTINGHOUSE NUCLEAR SERVICES DIVISION p
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LIMITATION TO EXAMINATION O
PLANT Comanche Peak UNIT 1
SKETCH TBX.1 1300 Rev.1 SYST/ COMP REACTOR COOLANT PROCEDURE TX4SI-21$
Rev. 4 FC N/A EXAMINER Will&arns. Mark M /M LEVEL 11 DATE 4/12/98 EXAMINER N/A LEVEL N/A DATE COMPONENT ID TBX.1 1300-2 f, ELATED TO O MT O PT (a) ur
.O vr PROVIDE SUFFICIENT INFORMATION TO DESCRIBE SIZE. LOCATION AND TYPE OF LIMITATION COMMENTS / SKETCH' DETAILS Lwnstations due to flange, shroud and liftmg lug. See 1RF01 profile for exarn coverage.17% of reqcited voeurne not examined. 97%
czamaned with the 46' and 60* m at least one direction.11% not exarruned with 48*.17% not exammed with 60*.
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= Attachment 2 to TXX-98170
- Page 1 of 14 CPSES UNIT 1 RELIEF REQUEST l
B-7 L~
REVISION 2 l
A.
Item (s) for which reliefis requested:
TBX-1-3100-1-1, TBX-1-3100-2-1, TBX-1-3100-3-1, TBX-1-3100-4-1 Steam Generator Tubesheet-to-Channel Head Welds B.
- Item Code Class:
1 C.
Examination requirement from which reliefis requested:
ASME Section XI 1986 Edition, no Addenda.
The requirement for volumetric examination of 100% of each of the steam generator tubesheet-to-channel head we!ds as described in Table IWB-2500-1, Examination Category B-B, Item No. B2.40.
l Note: The CPSES ISI Plan requires different steam generators to be examined during each inspection period. A relief request revision is processed to document the specific limitations encountered during the examination of each of the steam generators.
D.
Basis for relief:
Interference from the steam generator tube sheet flange configuration, welded insulation support pads and a welded component name tag preclude the complete ultrasonic examination of the volume required by Fig. IWB-2500-6.
Approximately 31% of the examination volume of weld TBX-1-3100-1-1 did not receive the full code required examination coverage.
Approximately 37% of the examination volume of weld TBX-1-3100-2-1 did not receive the full code required examination coverage.
Approximately 31% of the examination volume of weld TBX-1-3100-3-1 did not receive the full code required examination coverage.
Approximately 31% of the examination volume of weld TBX-1-3100-4-1 did not receive the full code required examination coverage.
See page 3 thru 14 for weld location and examination area configurations.
Page 1 of 14
Attac'hment 2 to TXX-98170
' Pag 3) 2 of 14 CPSES UNIT 1 RELIEF REQUEST B-7 REVISION 2 (cont.)
i i
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E.
Substitute examinations:
None - however, manufacturers shop volumetric exam records are available in permanent plant files.
F.
Anticipated impact on the overall level of plant quality and safety:
None i
b i
Page 2 of 14
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' Prg3 4 of 14 WESTINGHOUSE NUCLEAR SERVICE DIVISION INSPECTION SERVICES LIMITATION TO EXAMINATION CO M APJC H C fEAK "1
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' Pags 5 of 14 WESTINGHOUSE NUCLEAR SERVICE OlVISION INSPECTION SERVICES LIMITATION TO EXAMINATION PLANT CO M4titt4 r Pg n i<
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' to TXX-98170 TBX-1-3100-2-1 RESULTS
- P:gs 8 of 14 l
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i WESTINGHOUSE NUCLEAR SERVICE DIVISION
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INSPECTION SERVICES l
LIMITATION TO EXAMINATION l
PLANT COMANCHE PEAK UNIT NO.1 SKETCH TBx-13100 REV.1 SYST./ COMP. STEAM GENERATOR NO. 2 PROCEDURE TX-ISL210 REV. 2
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b EXAMINER /d DATE 311-95 V
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RELIEF REQUEST NO, B-7 REV. 2 PAGE 9 OF 14 to TXX-98170 TBX-1-3100-3-1 RESULTS
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' Page 11 of 14 l
REPORT NO.
UT48143
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WESTINGHOUSE NUCLEAR SERVICES DIVISION
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PAGE 2
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LIMITATION TO EXAMINATION
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PLANT comanche Peak UNIT 1
SKETCH TBX 14100 Rev.1 SYST/ COMP REACTOR COOLANT PROCEDURE TX4SI-210 Rev.4 FC N/A M LEVEL lli DATE 4/14/9s EXAMINER Delbusso..karnes 7
EXAMINER Magruder. Chris LEVEL 11 DATE 4/14/ss COMPONENT 10 TBX 1410041 RELATED TO O MT O PT
@ UT O v7 FAOVIDE SUFFICIENT INFORMATION TO DESCRIBE SIZE LOCATION AND TYPE OF LIMITATION.
COMMENTS / SKETCH /DETAfLS Four 24*X 24" Support pads restricts all scan for 22%. Seventeen 2.5"X 2J* welded pads approx. 7* from CL lets 60' scan.
' *2% not exammed. 46'.22% not exammed. 80* 41% not exammed. 31% of requred exam volume not exanwned.
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- Page 14 of 14
1 REPORT NO UT.88141 WESTINGHOUSE NUCLEAR SERVICES DIVISION e====-
77 PAGE 2
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LIMITATION TO EXAMINATION PLANT Comanche Peak UNIT 1
SKETCH TBX.13100 Rev.1 SYST/ COMP REACTOR COOLANT PROCEDURE TX4SI-210 Rev.4 FC N/A EXAMINER De6busso. James M
LEVEL lll DATE 4/13198 j
//
i EXAMINER Magruder. Chris LEVEL 11 DATE 4/13/9s COMPONENT 10 T8X.13100 41 RELATED TO O MT O PT
@ UT O VT PROVIDE SUFFICIENT INFORMATION TO DESCRIBE SIZE. LOCATION AND TYPE OF LIMITATION COMMENTS / SKETCH / DETAILS Four 24"X 24" Support pads restricts all scan for 22%. Seventeen 2.5"X 2.5" welded pads approx. 7" from CL limits 60* scan.
O'.22% not examined. 45'.22% not exarruned. 80*.31% not exarmned. 31% of required exam volume not examsned.
5 61bE SDf9DRT CDLLAR
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l to TXX-98170
- Page 1 of 4 CPSES UNIT 1 RELIEF REQUEST l
B-12
(
A.
Item for which reliefis requested:
TBX-1-2100-1 3
Pressurizer Lower Head to Shell Weld i
i.
i B.
Item Code Class:
l 1
L C.
Examination requirement from which reliefis requested:
The requirement for volumetric examination of 100% of the weld length as described in Table IWB-2500-1, Examination Category B-B, Item No. B2.11.
1 l
D.
Basis for relief:
l L
The specific examination area geometry of the lower head to shell weld and interferences from instrumentation lines, welded pads and the support skirt preclude the complete l
ultrasonic examination of the volume required by Fig. IWB.2500-1 for weld TBX-1-2100-1.
Approximately 16% of the volume did not receive the full code required coverage. Best effort examinations were performed. Full circumferential scan coverage was obtained. Axial scan coverage was achieved for approximately 97% of the required volume in at least one l
beam path direction with one angle.
l L
There were no recordable indications identified by the best effort examinations performed.
See pages 2 through 4 for weld location and examination area configuration.
E.
Substitute examinations:
None L
F.
Anticipated impact on the overall level of plant quality and safety:
None r
Page1of4
1 I
RELIEF REQUEST NO. B-12 PAGE 2 OF 4 to TXX-98170 Psge 2 of 4
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RELIEF REQUEST NO. B-12 PAGE 3 OF 4 Att chment 3 to TXX-98170
- Pags 3 of 4 M
REPORT NO.
UT 88469 WESTINGHOUSE NUCLEAR SERVICES DIVISION p
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[
FLANT Comanche Peak UNIT 1
SKETCH TBX 1-2100 Rev. 2 l
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&iLEVEL EXAMINER lit DATE 3/30/98 g
EXAMINER N/A LEVEL N/A DATE 9
l COMPONENT ID T5X.121081 EELATED TO O ur O PT
@ uT O vT PROVIDE SUFFICIENT INFORMATION TO DESCRIBE SIZE. LOCATION AND TYPE OF UMITATION.
COMMENTS / SKETCH / DETAILS Support restncts 2 scan for 40*.
5 1* 6 instrumentation hnes 3.5* from weed toe,5 side.
4 2.5* X 2.5" welded pads 2.75* Irom weed toe. 5 sade.
l 87% esammed with 45*. 85% examened with 60*.15% not examaned.
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___ to TXX-98170
- Page 1 of 13 l
CPSES UNIT 1 RELIEF REQUEST l
B-13 A.
Item (s) for which reliefis requested:
TBX-1-4102-7, TBX-1-4301-7, TBX-1-4402-7 Circumferential Piping Welds B.
Item (s) Code Class:
1 C.
Examination requirement from which reliefis requested:
The requirement for volumetric and surface examination of 100% of the weld length as described in Table IWB-2500-1, Examination Category B-J, Item No. B9.11.
D.
Basis for relief:
The specific pipe to valve examination geometries and interferences from reactor building structural steel members preclude the complete ultrasonic and liquid penetrant examinations of the volume and the surface area required by Fig. IWB-2500-8.
For weld TBX-1-4102-7, approximately 61% of the volume and 31% of the surface area did not receive the full code required examination coverage. See pages 3 through 6 for weld location and examination area configuration for weld TBX-1-4102-7.
For weld TBX-1-4301-7, approximately 55% of the volume did not receive the full code required examination coverage. See pages 7 through 9 for weld locacion and examination area configuration for weld TBX-1-4301-7.
' For weld TBX-1-4402-7, approximately 59% of the volume and 40% of the surface area did not receive the full code required examination coverage. See pages 10 tiuough 13 for weld location and examination area configuration for weld TBX-1-4402-7.
Best effort examinations were performed for the accessible areas of the welc. There were no -
recordable indications identified by the best effort volumetric or surface examinations performed.
Page1of13 L
L___
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Attac'hment 4 to TXX-98170
' P:ge 2 of 13 CPSES UNIT 1 l
RELIEF REQUEST B-13 (cont.)
E.
Alternate examinations:
None - however, welds at this se2ne location in loops 1, 3 and 4 are included in the ISI Plan and are scheduled for examination during this interval.
F.
Anticipated impact on the overall level of plant quality and safety:
None i
Page 2 of 13 1
RELIEF REQUEST NO. B-13 PAGE 3 OF 13
. to TXX 98170
- Page 3 of 13
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RELIEF REQUEST NO. B-13 PAGE 4 OF 13 to TXX-98170 P g3 4 of 13 i
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REPORT NO.
UT.ss.070 i
- = = = =
WESTINGHOUSE NUCt. EAR SERVICES DIVISION
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77 PAGE 3
OF 3
E C
LIMITATION TO EXAMINATION PLANT Cam.wehe Peak UNIT 1
SKETCH TBX.44102 Rev.1 SYST/ COMP REACTOR COOLANT PROCEDURE TX.4st-214 Rev. 2 FC N/A d
LEVEL NI DATE 4ttiss EXAMINER Ho4asek. Wade EXAMINER N/A LEVEL N/A DATE l
COMPONENT ID TBX-14102J r.EuTED TO o uT o PT
@ uT o vT PROVIDE SUFFICIENT INFORMATION TO DESCRIBE $1ZE. LOCATION AND TYPE OF L!MITATION COMME NTS/ SKETCH /CETAIt S L distances of scanned pepe measured in the CW d6riction frcen danan O. 2.0" to 8.8',22.0" to 25.5*, and 28.0" to 33.5". 87/8 scan also lumted m these areas. 39% of total area was asammed. (61% not exammed.)
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' Pegs 5 of 13 M
REPORT NO.
PT.ss 040 g=
WESTINGHOUSE NUCLEAR SERVICES DIVISION m
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LIMITATION TO EXAMINATION l
PLANT Comant.e Peak.
UNIT 1
SKETCH Tax-14102 Rev.1 '
SYST/ COMP *tEACTOR COOLANT PROCEDURE Tx4st.11 Rev.8 FC N/A EXAMINER McLeaek. Wade LEVEL M
DATE 3/31/es EXAMINER N/A LEVEL N/A DATE COMPONENT 10 TBX-14102-7 T. ELATED TO O uT
@ PT O uT o v7 FCOVIDE SUFFICIENT INFORMATION TO DESCRIBE SIZE, LOCATION AND TYPE OF LIMITATION.
COMMENTS / SKETCH / DETAILS 31% not exammed. Limitations from 7" to 12" and 15" to 21*.
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RELIEF REQUEST NO. : 13 PAGE 6 OF 13 Att:chment 4 to TXX-98170 j
- P:g3 6 of 13 i
M WESTINGHOUSE NUCLEAR SERVICES DIVISION REPORT NO.
UTes470 "7"
INSPECTION SERVICES
-2 OF 3'
picg PROFILE OF THE EXAMINATION VOLUME r
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COMMENTS / SKETCH /DE* TAILS No exa.nmation performed from 0* to 1J*. 8.5* to 10.E*,14.5" to 20.5*,23J* to 28" 31.5" to 34.4". All measurements taken CW from datum 0. Total circ measurement is 34.4*. 55 % not es.ammed.
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3 UMITATION TO EXAMINATION PLANT Cows.ene Peak UNIT 1
SKETCH TEX 1-4402 Rev. 2 S (ST/ COMP REACTOR COOUWT PROCEDURE TX.ast.214 Rev.2 FC NIA !
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@ UT O vT PROVIDE SUFFI;;ENT INFORMATION TO DESCRIBE SIZE. LOCATION AND TYPE OF UMITATION.
COMMENT 3/ SKETCH / DETAILS No examenstion performed from 4* to 21* and 33* to 2* CW with flow due to pope restraent. Tot.1 cwe -- -
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M WESTINGHOUSE NUCLEAR SERVICES DMSION REPORT NO.
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l PROFILE OF THE EXAMINATION VOLUME l
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'Page 1 of 3 CPSES UNIT 1 RELIEF REQUEST B-14 A.
Item (s) for which reliefis requested:
TBX-1-4404-1 Branch Pipe Connection Weld B.
Item (s) Code Class:
1 l
C.
Examination requirement from which reliefis requested:
The requirement for volumetric examination of 100% of the weld length as described in l
Table IWB-2500-1, Examination Category B-J, Item No. B9.31.
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D.
Basis for relief:
The specific examination area geometry of this pipe to br::nch connection weld precludes the complete ultrasonic examination of the volume required by Fig. IWB-2500-10.
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Approximately 26% of the examination volume did not receive the full code required coverage.
. A best effort examination was performed. Full circumferential scan coverage was obtained.
Axial scan coverage'was achieved in one beam path direction with at least one beam angle for 100% of the examination volume. See pages 2 and 3 for weld location and examination area configuration.
There were no recordable indications identified by the best effort volumetric examination or by the required surface examination performed.
E.
Alternate examinations:
. None F.
Anticipated impact on the overall level of plant quality and safety:
None L
l Page1of3 V.
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@ ur O vT PROV10E SUFFICIENT INFORMATION TO DESCRIBE S!ZE. LOCATION AND TYPE OF LIMITATION.
COMMENTS / SKETCH / DETAILS 100% of the requ, red volume is covered in at least i beam path direction. 74% of the requered volume is covered in 2 beam path daractions,
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l LIMITATION TO EXAMINATION 1
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SKETCH Tax-21110 Rev.1 l
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DATE 4/10/98 r
EXAMINER. N/A LEVEL NIA DATE COMPONENT 13 TBX.21110-1 RELATED TO O MT O PT
@ UT O v7 PROVIDE SUFFICIENT INFORMATION TO DESCRIBE SIZE. LOCATION AND TYPE OF LIMITATION COMMENTS / SKETCH / DETAILS Four noules located as shown below. Two 3" noules and two 4" noules on side 2. 50% not exarruned.
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' Pag 3 2 of 7 CPSES UNIT 1 RELIEF REQUEST C-9 A.
Item (s) for which reliefis requested:
TBX-2-Il 10-1 l
Excess Letdown Heat Exchanger Head to Flange Weld L TBX-2-1180-2-2 Containment Spray Heat Exchanger Shell to Flange Weld i
B.
Item (s) Code Class:
2 C.
~ Examination requirement from which reliefis requested:
The requirement for volumetric examination of 100% of the weld length as described in Table IWC-2500-1, Examination Category C-A, Item No.'s Cl.20 and C1.10.
D.
Basis for relief:
For weld TBX-2-1110-1, interferences from the heat exchanger inlet, outlet and instruments
- ion nozzles and from the flange taper preclude the complete ultrasonic examination of the volume required by Fig. IWC-2500-1. Approximately 50% of the weld.
length did not receive the full code required examination coverage. See pages 2 through 4 for l
weld location and examination area configuration for weld TBX-2-1110-1.
For. weld TBX-2-1180-2-2, interferences from the 1 at exchanger welded support pads preclude the complete ultrasonic examination of the _ volume required by Fig. IWC-2500-1.
Approximately 27% of the weld length did not receive the full code required examination coverage. See pages 5 through 7 for weld location and examination area configuration for weld TBX-2-1180-2-2.
There were no recordable indications identified by the be.,t effort volumetric examination performed on the accessible portions of the weld lengths.
E.
Alternate examinations:
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~ Anticipated impact on the overall level of plant quality and safety:
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.Page 1 of 7
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REPORT NO.
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INSPECTION SERVICES PAGE 2
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SKETCH TBX.2111c Rev.1 SYST/ COMP CHEMICAL & VOLUME CONTROL PROCEDURE TXJSI-214 Rev. 2 FC N/A EXAMINER Mormi. George
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LIMITATION TO EXAMINATION PLANT Comenche Peak UNIT 1
SKETCH 11X41180 Rev.1 l
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DATE 3/20/es EXAMINER 'i NIA LEVEL N/A DATE l
COMPONENT ID TBX.21100 24 l
@ UT O v7 PROVIDE SUFFICIENT INFORMATION TO DESCRIBE SIZE, LOCATION AND TYPE OF LIMfTATION.
COMMENTS / SKETCH / DETAILS 27% of weed voeume not exammed.
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