ML030990109

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Fax, Draft Revised Relief Request Regarding RR B-7, B-8, B-9 and C-6
ML030990109
Person / Time
Site: Comanche Peak Luminant icon.png
Issue date: 03/14/2003
From: Terry C
TXU Generation Co, LP
To: Jaffe D
NRC/NRR/DLPM/LPD4
Jaffe D, NRR/DLPM, 415-1439
Shared Package
ML030980062 List:
References
Download: ML030990109 (36)
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Text

{{#Wiki_filter:MAR-14-2003 FRI 12:13 PM ADMIN ANNEX 1ST FLR FAX NO. 2548970530 P. 01 TXU Fax Cover TXU Electric Technical Support FAX # 254-897-0530 Date: 3,/ /o 3 To: a /44<e-Company: Fax: From: it,~ Phone: -5 ~* - F ) -.o -? C, Dept: Fax: Re: 1;'Urgent Vfor Review OPlease Reply OPiease Reply When Received If any pages are not received, please call: 254-897-6093 r Number of pages (include cover page): f

1Afh-14-2003 FRI 12:13 PM ODMIN 8NNEX 1ST FLR FAX NO. 2548970530 P. 02

1.

2 Refi 10 CFR 50.55a(g) I CPSES-)DLXXXXX Log # TXX-OXXXXX File# 10010 February XX, 2003 I U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) DOCKET NO. 50-446; REQUEST FOR ADDITIONAL INFORANTION REGARDING RELIEF REQUESTS B-7, B-8, B-9 AND C-6 TO THE UNIT 2 INSERVICE INSPECTION (ISI) FROM 1986 EDITION OF ASME CODE, SECTION XI, NO ADDENDA (INTERVAL START DATE: AUGUST 3,1993, FIRST INTERVAL)

REFERENCE:

TXIJ Energy Letter logged TXX -02122 dated July 11, 2002 from C. Lancc Terry to the NRC I I

Dear Sir or Madam:

Based on the telephone conversation with your staff TXU Energy is revising its relief requests submitted via the above referenced letter. This communication contains no new licensing basis commitments regarding Comanche Peak Steam Electric Station (CPSES) Unit 2.

MAR-14-2003 FRI 12:13 PM ADMIN ANNEX IST FLR FAX NO. 2548970530 P. 03 TXX-XXxx Page 2 of 2 If you have any questions or need additional information regarding this matter, please feel free to contact Obaid Bhatty at (254) 897-5839 or Douglas W. Snow at (254) 897-8448. Sincerely, TXU Generation Company LP By: TXU Generation Management Company LLC Its General Partner C. L. Terry Senior Vice President and Principal Nuclear Officer By: Roger D. Walker Regulatory Affairs Manager OAB/ob Attachments c - E. W. Merschoff, Region IV W. D. Johnson, Region IV D. H. Jaffe, NRR Resident Inspectors, CPSES Chief Inspector, TDLR I

MAR-14-2003 FRI 12:13 PM ADMIN ANNEX 1ST FLR FAX NO. 2548970530 P. 04 to TXX-OXXXX Page 1 off /, TXU GENERATION COMPANY LP COMANCHE PEAK STEAM ELECTRIC STATION UNIT 2 FIRST TEN-YEAR INTERVAL 1SI RELIEF REQUEST NO. B-7 REV I PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10 CFR 50.55a(g)(5)(iii) -INSERVICE INSPECTION IMPRACTICALITY-I. SystemlComponent for Which Relief is Requested: ASME Class I Reactor Pressure Vessel (RPV) closure head to flange weld (Weld No. TCX-1-1300-1) and RPV closure head to disc weld (Weld No. TCX-1-1300-2) II. Code Requirement from Which Relief is Requested: Comanche Peak Unit 2 is currently required to perform inservice examinations of selected welds in accordance with the requirements of 10 CFR 50.55a, and the 1986 Edition with no Addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components. The Code invokes the examination volume requirements of Figures IWB-2500-3 and IWB-2500-5. Weld No. TCX-l-1300-1: Table IWB-2500-1. Examination Category B-A, Code Item BI.40, Figure IWB-2500-5. The subject weld is a full penetration weld, and requires 100 volumetric and surface examination of the RPV head to flange welds as defined by Figure IWB-2500-5. Weld No. TCX-1-1300-2: Table IWB-2500-1. Examination Category B-A, Code Item B1.21, Figure IWB-2500-3. The subject weld is a full penetration weld, and requires 100 percent volumetric examination of the accessible portion of all circumferential welds, as defined by Figure IWB-2500-3. III. Impracticality of Compliance: The examination coverage is limited by physical interferences from the reactor head flange, shroud, and lifting lugs (refer to the attached sketches on pages 3 through 9). Therefore, pursuant to the requirements of 10 CFR 50.55(g)(5)(iii) relief is requested from performing 100% volumetric examination requirements Figures IWB-2500-3 and IWB-2500-5.

MAR-14-2003 FRI 12:14 PM ADMIN ANNEX 1ST FLR FAX NO. 2548970530 P. 05 Attachment I to TXX-OXXXX Page2of \\\\" TXU GENERATION COMPANY LP COMANCHE PEAK STEAM ELECTRIC STATION UNIT 2 FIRST TEN-YEAR INTERVAL ISI RELIEF REQUEST NO. B-7 REV 1 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10 CFR 50.55a(g)(5)(iii) -INSERVICE INSPECTION IMPRACTICALITY-(Continued) IXV. Burden Caused by Compliance: The examination coverage is limited by physical interferences from the reactor head flange, shroud, and liffing lugs as indicated via the attached sketches. These conditions make 100 percent examination impractical for these welds. To gain access for examination, the RPV head would require design modification. Imposition of this requirement would be a significant burden on TXU Energy. V. Proposed Alternative and Basis for Use: There are no proposed alternatives. TXU has examined a significant portion of these welds, obtaining approximately 84 percent of weld TCX-1-1300-2, and 85 percent of weld TCX-1-1300-1 of the required volumetric examination coverage. Additionally, 100 percent of the required surface examination of weld TCX-1-1300-1 was performed. There were no recordable indications identified by the volumetric examinations or surface examination. The subject welds were examined to the maximum extent possible (approximately 84 % and 87 % of examination completed in all cases) and yielded no indications. Based on the high percentage of the examination volume completed, and the lack of any reportable indications, there is a high level of confidence in the continued structural integrity of the welds. There is no anticipated impact upon the overall plant quality and safety, and the health and safety of the public should not be jeopardized by the granting of relief The CPSES ISI plan requires 1/3 of each weld be examined each inspection period. The limitations of the first two inspection periods have been previously reviewed and approved under relief request identified in precedents No. 2 and No. 4. VI. Duration of Proposed Alternative: This relief is requested for the Comanche Peak Steam Electric Station Unit 2, third period of the first 1 0-year interval vessel examination.

MAH-14-2003 FRI 12:14 PM ADMIN ANNEX IST FLR FAX NO. 2548970530 P. 06 Attachment I to TXX-OXXXX Page 3 oft4' TXU GENERATION COMPANY LP COMANCHE PEAK STEAM ELECTRIC STATION UNIT 2 FIRST TEN-YEAR INTERVAL ISI RELIEF REQUEST NO. B-7 REV I PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10 CFR 50.55a(g)(5)(iii) -INSERVICE INSPECTION IMPRACTICALITY-VII. Precedents:

1)

TXU Energy letter logged TXX-98170 dated July 22, 1998, NRC response dated July 8, 1999, reference TAC NO. MA3632.

2)

TXU Energy letter logged TXX-95042 dated March 6, 1995. NRC response dated December 28, 1995, reference TAC NO. M93333 and M93334.

3)

NRC SER dated November 29, 1994, reference TAC NO. M83 125.

4)

TXU Energy letter logged TXX-01110 dated June 22, 2001. NRC response dated October 11, 2001, reference TAC NO. MB 1l90.

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MAR-14-2003 FRI 12:15 PM ADMIN ANNEX IST FLR - FAX NO. 2548970530 P. 08 I Attachment I to TXX-OX.XXX Page 5 of/ 1\\ TXU GENERATION COMPANY LP COMANCHE PEAC STEAM ELECTRIC STATION UNIT 2 FIRST TEN-YEAR INTERVAL IST RELIEF REQUEST NO. B-7 REV 1 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10 CFR 50.55a(g)(5)(iii) -INSERVICE INSPECTION IMPRACTICALITY-(Continued) i I I 0 trxu ._AN wREORTN. UTr22 wESTINGHOUSE NUCLEAR SERVCES DMSION PAGE 3 or 5 UMITATION TO EXAMINATION COMANCHE PEAK SYSTiCOWP LV, CLOSURE HEAD W LMINER W.BoIningmo In D-h EXA.INER S E nckson ,w 2?. 'RCO uNrr 2 SKETCH TCX..1;O00 PROCEDURE TX.1S1S210 REV.4 LEVEL III DATE J.062 I LEVEL 11 DATE 4DS. 2 cOWPoNENTIO TCX-.113C0.I RELArEDlTO O LUT D-V PRCADE SUEFNCIENT INFOCM&TlON TO DESCRISE SIZE LOCATION AND TYPE OF WTATION rnUkFkTC f srtw riFTslr t 15% Of nquged Volume nd examed. 9SN uwnned w~h 45' and S Cn atIeaZst one dractoft 3% of requred volume not examxned, 45'. and 15% of mquired vohm nol zanned wiyi 6C. IL-. I CA. Lo. .1. I YL et' Sri "1 FL.^5. %.f sitf ffld So 5S C+t"-ce! c-aerLL5 plots ALU.-tifa.

[nr_4-f-UU\\ J rrj W;lb FM QDMIN ANNEXIST FLR FIX NO. 2548970530 to TXX-OXXXX Page 6 ofA-lk TXU GENERATION COMPANY LP COMANCHE PEAK STEAM ELECTRIC STATION UNIT 2 FIRST TEN-YEAR INTERVAL ISI RELIEF REQUEST NO. B-7 REV 1 PROPOSED ALTERNATIVE IN ACCORDANCE WVITH 10 CFR 50.55a(g)(5)(iii) -INSERVICE INSPECTION IMPRACTICALITY-P. 09 WESTINGHOUSE NUCLEAR SERVICES DIVISION REPORT NO MT.02 0a INSPECTION SERVICES PAGE 1 OF TXU SURFACE EXAMINATION DATA PLANT COMANCHE PEAK UNIT 2 3KETCH TCX-1-)300 SYSTICoMP ReactarVecsselClosurrHead PROCEDURE TX-ISI-70 Re% 6 EXAMINER 1 Ackerman LEVEL 1I DATE 4-06-02 EXAMNER LEVEL 1I DATE 4-06-02 PT "T CH NUMBEPA IUT CLEANER N'A YOKE TV'-1631 Magnoflu% 1-6 COIL N A PENETRANT N A EXAM MEDIUM Red hkrdros MaeLn-Tech DEVELOPER N'A GLACK-LIGHT EA REMOVER NA CHECXTIME N'A SURFACE THERMOMETER N'A SURFACE THERMOMETER T1.-242J COMPONENT ID RESULTS REMARKS UIMrAeCN TEMP 'r Weld I ]I Examnmed wcId from center ofstud hole 50 thru I to center Ime of NONE 75'F .stud holt 14 7U ELECTRIC AEWCVTA7E TU ELEC7R:C LEVEL IIT REVEW)DATE ANII REVIEW1 O~AT L = =- .\\_

rm-iq-auu3 FRI 12:15 PH ADMIN ANNEX 1ST FLR FAX NO. 2548970530 P. 10 Attachment I to TXX-OXXlXX Page 7 of - TXU GENERATION COMPANY LP COMANCHE PEAK STEAM ELECTRIC STATION UNIT 2 FIRST TEN-YEAR INTERVAL ISI RELIEF REQUEST NO. B-7 REV 1 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10 CFR 50.55a(g)(5)(iii) -INSERVICE INSPECTION IMPRACTICALITY-PDI Calibration Data Sheet PlanVtUnit Comanche Peak 12 Dale Sheet # UT-22 Company WesDyne Page 1 of 5 r Comp/Systern RV Closure Head Procedure ND TX-IS1-210 1al Checks Time Rev/Chng No Rev 4 nitial Calib 1418 Cal Block No TBX-RV-29 nftial Calib Date 4-06-02 Cal Block Temp 7R. Comp Temp 82a lermediale N/A Therm S/N TU-2261 nt-ermedlite NJA Size N/A Sch 6 7' 'T

ra alb 15 Kerril c E ustenilic mnal Calib Date 4-06-02 Each Mal or CRT Div = 1 0611 56 Stareh Unit W1 M

Search Unit c2 Cal Direction Axial Clrc Both X Couplant Manufacture KBA Manulacture KBA Scan Area I loWeld X Type ULTRAGELII Serial No 009Y57/2 25 MHz Serial No 008954J2 25 MHz 11 to Weld X Batch 01225 Size I 0C Shape ROUND Size 05' x 1 C' Shape RECT Exam Angle 0o Model HP ExamAngle 45-Mcdel GAMMA l Recordable Measured Angle 0o Measured Angle 45S Access Indications Exam lWedge Style NJA Wedge Style NON-INTEGRAL ExIrarnnatiin AraNIeII I.. l II Ye l No ln l Saarc U -1t Cb ICX-1-1300 1 2 SIDED X NONE 30 5/596 Type eR-14 Length 20 Type rGi74 Length 20 l Inlermediale Connectors 0 Intermediate Connectors 0 Instrument Settings Inslrument Settings __IIIIIIMake/Model KBAIUSN 52R Make/Model KBAtUSN 52R Remarks/Reasons lor incomplete Scants) See attached Senal No i SAP 102352 Serial No SAP 102352 Limitation ToExamination sheet Examined from CIL ot stud Delay -1 813 Range 1064' Delay 5 438 Range 1564 hole 14 thru stud hole t to CIL of stud hole 50 PMI Calel 23301us Pulser SINGLE M l Calrel l32O-isPulser SINGLE Damping 1000I I Rejecl.OFF Damping 1000 t Reject OFF Rep Rate HIGH Freq 2-8 Mhz Rep Rate HIGH Freq 2-8Mhz Ft_ Fier N/A Mode FULtWAVE Filler. N/A Mode fULLWAVE Examiners N Bolling=m2 Al Level It Date 4-06-02 Relerence Sensitivity (Sens ) Reference Sensitivity (Sens) Axial N/A Circ NtA Axial 416 dB Ctrc 416 dB S Ercks0rt2 tLevel 11 Dale 4-06-02 SHD Sensitivty 12 5 dB D Sensitivity N/A Revieer Date ( r.'Yurther Evaluation Required? Yes I V WMT I, ir 14, I'. 1 Wit I Valf ANU At.k. /Its, 4i rn L7, +1),1, Z, _;?, 4/,,,/,, T ___-1 --AL C.

MAR-14-2003 FRI 12:16 PM ADMIN ANNEX 1ST FLR FAX NO. 2548970530 P. 11 to TXX-OXXXX Page 8 of 4-TXU GENERATION COMPANY LP COMANCHE PEAK STEAM ELECTRIC STATION UNIT 2 FIRST TEN-YEAR INTERVAL ISI RELIEF REQUEST NO. B-7 REV 1 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10 CFR 50.55a(g)(5)(iii) -INSERVICE INSPECTION IMPRACTICALITY-III &,,~k oIt IIe4CvirwI 1X181 kerl cam ft-S?/

MAR-14-2003 FRI 12:16 PM ADMIN ANNEX 1ST FLR FAX NO. 2548970530 P. 12 Attachmnent I to T-OXXX Page 9 of 4-TXU GENERATION COMPANY LP COMANCHE PEAK STEAM ELECTRIC STATION UNIT 2 FIRST TEN-YEAR INTERVAL ISI RELIEF REQUEST NO. B-7 REV 1 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10 CFR 50.55a(g)(5)(iii) -INSERVICE INSPECTION IMPRACTICALITY- ,PX, Ii1 -~-..C AN -!4 1-,-(1. '1 '-.1 t--l---l-

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13 MAR-14-2003 FRI 12:17 PM ADMIN ANNEX 1ST FLR FAX NO. 2548970530 P. to TXX-OXXXX Page 10 of 4, TXU GENERATION COMPANY LP COMANCHE PEAK STEA-M ELECTRIC STATION UNIT 2 FIRST TEN-YEAR INTERVAL 1SI RELIEF REQUEST NO. B-7 REV I PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10 CFR 50.55a(g)(5)(iii) -INSERVICE INSPECTION IMPRACTICALITY-I I Pt n _j+i I N = re. *:-k.i rtv.P t I

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MAR-14-2003 FRI 12:17 PM ADMIN ANN-EX 1ST FLR FAX NO. 2548970530 P. 15 to TXX-OX)XX.l Page 1 of S TXUJ GENERATION COMPANY LP COMANCHE PEAK STEAM ELECTRIC STATION UNIT 2 FIRST TEN-YEAR INTERVAL IS! RELIEF REQUEST NO. B-8 REV 1 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10 CFR 50.55a(g)(5)(iii) -INSERVICE INSPECTION IMPRACTICALITY-

1.

SystemlComponent for Which Relief is Requested: ASME Class I Reactor Pressure Vessel (RPV) Lower Vessel Head Circumferential Weld (Weld No. TCX-1-1 100-5). II. Code Requirement from Which Relief is Requested: Comanche Peak Unit 2 is currently required to perform inservice examinations of selected welds in accordance with the requirements of 10 CFR 50.55a, and the 1986 Edition with no Addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components. Weld No. TCX-l-l 100-5: Table IWB-2500-1. Examination Category B-A, Code Item B 1.21, Figure IWB-2500-3. The subject weld is a full penetration weld, and requires 100 percent volumetric examination of the accessible portion of all circumferential welds, as defined by Figure IWB-2500-3. III. Impracticality of Compliance: The examination coverage is limited by physical interferences from the reactor vessel bottom mounted instrument tubes (refer to the attached sketches on pages 3 thru 6). Specifically, refer to page 4 of this attachment (lower left hand corner of the sketch), which depicts the periphery penetration. These areas behind the penetrations were not accessible to the ultrasonic scanning sled. However, cameras on the examination tools were used to visually access the areas that were not accessible to the ultrasonic transducer scanning sled. Additionally, Page 6 of this attachment depicts best effort examination coverage results for each examination angle and scan direction. Therefore, pursuant to the requirements of 10 CFR 50.55(g)(5)(iii) relief is requested from performing 100% volumetric examination requirements Figures IWB-2500-3.

MAR-14-2003 FRI 12:18 PM ADNIN ANNEX IST FLR FAX NO, 2548970530 P. 16 to TXX-0X0XXl Page 2 ofj' TXU GENERATION COMPANY LP COMANCHE PEAK STEAM ELECTRIC STATION UNIT 2 FIRST TEN-YEAR INTERVAL ISI RELIEF REQUEST NO. B-8 REV I PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10 CFR 50.55a(g)(5)(iii) -INSERVICE INSPECTION IMPRACTICALITY-Continued IV. Burden Caused by Compliance: The examination coverage is limited by physical interferences from the reactor bottom mounted instrument tubes as indicated via the attached sketches. These conditions make 100 percent examination impractical for these welds. To gain access for examination, the RPV head would require design modification. Imposition of this requirement would be a significant burden on TXU Energy. V. Proposed Alternative and Basis for Use: There are no proposed alternatives. The subject welds were examined to the maximum extent possible (approximately 75 %) and yielded no indications. Based on the high percentage of the examination volume completed, and the lack of any reportable indications, there is a high level of confidence in the continued structural integrity of the welds. There is no anticipated impact upon the overall plant quality and safety, and the health and safety of the public should not be jeopardized by the granting of relicf VI. Duration of Proposed Alternative: This relief is requested for the Comanche Peak Steam Electric Station Unit 2, third period of the first 10-year interval vessel examination. VII. Precedents:

1. TXU Energy letter logged TXX-99030 dated February 17, 1999. NRC response dated September 24, 1999, reference TAC NO. MA4845 and MA6322.

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MAR-14-2003 FRI 12:19 PM ADMIN ANNEX 1ST FLR FAX NO. 2548970530 P. 21 to TXX-OXXXl Page I of 0 St TXU GENERATION COMPANY LP COMANCHE PEAK STEAM ELECTRIC STATION UNIT 2 FIRST TEN-YEAR INTERVAL ISI RELIEF REQUEST NO. B-9 REV 1 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10 CFR 50.55a(g)(5)(iii) -INSERVICE INSPECTION IMPRACTICALlTY-I. System/Component for Which Relief is Requested: ASME Class I Reactor Pressure Vessel (RPV) Outlet Nozzle to Shell Welds. RPV Nozzle-to-Vessel Weld (Weld No. TCX-1-1 I OOA-1 9) RPV Nozzle-to-Vessel Weld (Weld No. TCX-l-1 1OOA-22) RPV Nozzle-to-Vessel Weld (Weld No. TCX-1-1 IOOA-23) RPV Nozzle-to-Vessel Weld (Weld No. TCX-1-1 IOOA-26) II. Code Requirement from Which Relief is Requested: Comanche Peak Unit 2 is currently required to perform inservice examinations of selected welds in accordance with the requirements of 10 CFR 50.55a, and the 1986 Edition with no Addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components. The subject welds are described in Table IWB-2500-1, Examination Category B-D, and Full Penetration Welds of Nozzles in Vessels, Code Item B3.90, Figures IWB-2500-7(b), and requires volumetric examination of these welds. III. Impracticalitv of Compliance: The examination coverage is limited by area geometries of the reactor vessel outlet nozzles. Best effort examination resulted in volumetric coverage of approximately 84.4 percent due to weld and vessel shell configuration. It is impractical to obtain a volumetric coverage of 100 percent required by the Code for each of the subject welds unless the RPV is redesigned to improve access to the welds. Therefore, pursuant to the requirements of 10 CFR 50.55(g)(5)(iii) relief is requested from performing 100% volumetric examination requirements Figures IWB-2500-7(b). IV. Burden Caused by Compliance: The examination coverage is limited by area geometries of the reactor vessel outlet nozzles, as indicated via the attached sketch on page 3. These conditions make 100 percent examination impractical for these welds. The examination tool used for this volumetric exam has been used to examine reactor vessels of similar designs at other plants with similar coverage results. To gain access for examination would require

MAR-14-2003 FRI 12:20 PM ADMIN ANNEX 1ST FLR FAX NO. 2548970530 P. 22 to T-OXXXX.X Page 2 of,# S TXU GENERATION COMPANY LP COMANCHE PEAK STEAM ELECTRIC STATION UNIT 2 FIRST TEN-YEAR INTERVAL ISI RELIEF REQUEST NO. B-9 REV I PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10 CFR 50.55a(g)(5)(iii) -INSERVICE INSPECTION IMPRACTICALITY-Continued design modification. Imposition of this requirement would be a significant burden on TXU Energy. V. Proposed Alternative and Basis for Use: The are no proposed alternatives. TXU has examined a significant portion of the weld, obtaining approximately 84.4 percent of the required volumetric examination coverage (see typical Table on page 4). Essentially 100 percent of the examination volume for each weld was examined in the axial scan direction from nozzle inside bore by techniques designed for the detection and sizing of surface and subsurface flaws oriented in a plane normal to the vessel inside surface and parallel to the weld. The examination performed in this manner emphasizes the detection of the types of flaws that can result from welding processes or inservice conditions. There were no recordable indications identified by the volumetric examination. Additionally, cameras on the examination tool were used to visually access areas that were not accessible to the ultrasonic transducer scanning sled. The subject welds were examined to the maximum extent possible (approximately 84 % and 84.4 % of examination completed in all cases) and yielded no indications. Based on the high percentage of the examination volume completed, and the lack of any reportable indications, there is a high level of confidence in the continued structural integrity of the welds. There is no anticipated impact upon the overall plant quality and safety, and the health and safety of the public should not be jeopardized by the granting of relief VI. Duration of Proposed Alternative: This relief is requested for the Comanche Peak Steam Electric Station Unit 2, third period of the first 10-year interval vessel examination. VII. Precedents:

1)

TXU Energy letter logged TXX-99030 dated February 17, 1999. NRC response dated September 24, 1999, reference TAC NO. MA4845 and MA6322.

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FAX NO. 2548970530 P. 24 MAR-14-2003 FRI 12:20 PM ADMIN ANNEX IST FLR to TXX-OXXXXX Page 4 of FAX NO. 2548970530 P. 24 I TXU GENERATION COMPANY LP COMANCHE PEAK STEAM ELECTRIC STATION UNIT 2 FIRST TEN-YEAR INTERVAL IS1 RELIEF REQUEST NO. B-9 REV 1 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10 CFR 50.55a(g)(5)(iii) -INSERVICE INSPECTION IMPRACTICALITY-Continued I -a 30 2 N 0 z 0 20 9 8f E; CZ n,, L?. Li k .80 o20 no 100 90 DISTAN4CE FROM VESSEL CENTERLINE (in) NGTE' CENSERVATIVE UPPER SHELL 'T-0cx R.V. ISI 200Z l OTE al ASSUwrDl esoc TA_

~ A At W ^ - - - - - - - -re MAR-14-2003 FRI 12:21 PM ADMIN ANNEX 1ST FLR FAX NO. 2548970530 P. 2b I to TXX-OXXXXX Page 5 of t TXU GENERATION COMPANY LP COMANCHE PEAK STEAM ELECTRIC STATION UNIT 2 FIRST TEN-YEAR INTERVAL ISI RELIEF REQUEST NO. B-9 REV 1 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10 CFR 50.55a(g)(5)(iii) -INSERVICE INSPECTION IMPRACTICALITY-Continued I _JIREU.. ,,IC1N I] /I I.1Tir'& C Comanche Peak Unft (T (IX) RPV COVERAGE ESTIMATE BREAKDOWNS EDRL;t I IUN I UK~r-N 1A I lU[M4 PARALLEL SCANS PERP. SCANS CCWICW Bore Axial ITEM / AREA Outlet Nozle to Shell @ 22° WELD NO. TCX-1 -1 I OA-f ff7,v,r,* BEAM ANGLES BEAM 10- L 50" L 45@ L Dual 450 L Single 450 Shear DIRECTION WELD voLU&C WELD WELDUE WELO VOLUME WELD VOLUME WELD VOWUE I _ _ _ _ __6 2___ ccw 100 100 5 62 55 90 cw100 100 5162 55 90 UP (IN) DOWN (OUT) BORE AXIAL 100 100 100 100 A_ AA I-I= I-

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MAR-14-2003 FRI 12:21 PM ADMIN ANNEX IST FLR FAX NO. 2548970530 P. 26 to TXX-OXXXXX Page 1 ofeS6 TXU GENERATION COMPANY LP COMANCHE PEAK STEAM ELECTRIC STATION UNIT 2 FIRST TEN-YEAR INTERVAL ISI RELIEF REQUEST NO. C-6 REV 1 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10 CFR 50.55a(g)(5)(iii) -INSERVICE INSPECTION IMPRACTICALITY-

1.

SystemrComponent for Which Relief is Requested: Chemical and Volume Control (CVCS) Pump TCX-CSAPCH-01. ASME Class 2 Integrally Welded Pump Attachments. Weld No. TCX-2-3 11 0-3WS Weld No. TCX-2-3 110-4WS II. Code Requirement from Which Relief is Requested: Comanche Peak Unit 2 is currently required to perform inservice examinations of selected welds in accordance with the requirements of 10 CFR 50.55a, and the 1986 Edition with no Addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components. The subject welds are described in Table IWC-2500-1, Examination Category C-C, Code Item B3.30, Figures IWC-2500-5, and requires surface examination of these welds. III. Impracticality of Compliance: The examination coverage is limited due to interference from the housing seal and pump base plate, refer to the attached pictures of the welded attachment (typical for all 4 attachments). Therefore, the Code required 100 percent surface examination by liquid penetrant method can not be achieved. Best effort examination resulted in coverage of approximately 77 percent of the area. As depicted via the pictures, it is impractical to obtain coverage of 100 percent required by the Code for each of the subject welds unless the CVCS Pump is redesigned or completely removed of the pedestal to improve access to the welds. Therefore, pursuant to the requirements of 10 CFR 50.55(g)(5)(iii) relief is requested from performing 100% volumetric examination requirements of Examination Category C-C, Code Item B3.30, Figures JWC-2500-5.

r1N-'4-fUUl PJ 1X 2 1 MM ADMIN ANNEX 1ST FLR FAX HO. 2548970S3 27 to TXX-OXCXXX Page 2 of# TXU GENERATION COMPANY LP COMANCHE PEAK STEAM ELECTRIC STATION UNIT 2 FIRST TEN-YEAR INTERVAL ISI RELIEF REQUEST NO. C-6 REV I PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10 CFR 50.55a(g)(5)(iii) -INSERVICE INSPECTION IMPRACTICALITY-Continued IV. Burden Caused by Compliance: The examination coverage is limited by area geometries of the CVCS pump housing seal and pump base plate, as indicated via the attached sketches on pages 3 thru 5. These conditions make 100 percent examination impractical for these welds. To gain access for examination would require design modification. Imposition of this requirement would be a significant burden on TXU Energy. V. Proposed Alternative and Basis for Use: There are no proposed alternatives. TXU has examined a significant portion of these welds, obtaining approximately 77 percent of the required volumetric examination coverage. There were no recordable indications identified by the liquid penetrant surface examination. An attempt to visually inspect the welds was done, however, physical geometry of the location would not permit the visual examination of the entire weld area, which was obstructed by the base plate. The best effort visual exarmination did not reveal any matters of concern regarding the structural integrity of the accessible weld. The subject welds were examined to the maximum extent possible (approximately 77 percent of the weld) and yielded no indications. Based on the high percentage of the examination volume completed, and the lack of any reportable indications, there is a high level of confidence in the continued structural integrity of the welds. There is no anticipated impact upon the overall plant quality and safety, and the health and safety of the public should not be jeopardized by the granting of relief. VI. Duration of Proposed Alternative: This relief is requested for the Comanche Peak Steam Electric Station Unit 2, third period of the first 1 0-year interval vessel examination. VII. Precedents: I) TXU Energy letter logged TXX-93107 dated March 15, 1993. NRC response dated November 29, 1994, reference TAC NO. M83 125.

MAR-14-2003 FRI 12:22 PM ADMIN ANNEX_1ST FLR FAX NO. 2548970530 P. 28 to TXX-OXXXXX Page 3 off TXU GENERATION COMPANY LP COMANCHE PEAK STEAM ELECTRIC STATION UNIT 2 FIRST TEN-YEAR INTERVAL ISI RELIEF REQUEST NO. C-6 REV I PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10 CFR 50.55a(g)(5)(iii) -INSERVICE INSPECTION IMPRACTICALITY-Continued

MAR-14-2003 FRI 12:22 PM ADMIN ANNEX 1ST FLR FAX NO. 2548970530 P. to TXX-OXXXXX Page 4 of Y TXU GENERATION COMPANY LP COMANCHE PEAK STEAM ELECTRIC STATION UNIT 2 FIRST TEN-YEAR INTERVAL ISI RELIEF REQUEST NO. C-6 REV 1 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10 CFR 50.55a(g)(5)(iii) -INSERVICE INSPECTION IMPRACTICALITY-Continued WESIIN6HOUSE NOcF.ARSERV¶CES NISI0N tR PT02 INSPECTOl SERVICES PAE 2 SURFACE E(AMNATON OATA PLt CMANCM PEAK t 1... T TCX.NUO sys-Tcomp CczmfuL hm"Itchtl ououE TX-TSI~ R." 6~ EDW4'NGS L Fv L-W DATE 3-4 E)A~NSER L MuS1 LEVE-L OATE

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fflA flu. J*UJIUUJU A. ..)U NAR-14-2UUb Ml 12:2Th fiUrTE" FNt5LK to TXX-OXXXXX Pagei ofS 6 TXU GENERATIC I4UX Nll X-.[l^F{7Tl5Fr r 511 rnzs 11U, C;J5DG f UUU I. )v I )N COMPANY LP o I;TATt(lrh rTn UNIT 2 COMANCHE PEAK STEAM A-I-kox-A-I FIRST TEN-YEAR INTERVAL ISI RELIEF REQUEST NO. C-6 REV 1 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10 CFR 50.55a(g)(5)(iii) -INSERVICE INSPECTION IMPRACTICALITY-Continued I ThU P-AXT COMA acOm NO P.02 WS1nNGHOUSE NUCLEAR SERVICES OMSION PAGE 2 OF 2. UMIATION TO EXMI N tla lp~ff 2L wrKETMH l2.1110 .NCHE PFA ppCCEDURE -TSL( StnT I COMP CtslU*alI Cbil PuM I WNINER i Fu L L L U CAT! 3-EXALONE-~t LEMsl j~- VEL fl AT COMPON!WTto 3WS &*WS REL.ATED TO F MT, El PT F u Ppovit SU~FFICENT INFORpMATON TO OESCRIS. SaEL LOCATION ANOD PE OF UWIAI 0uUENT.SI Ur.04 l AILS C T. ga.W.4 SEAL DUCt h) SEs KeTAL. S"ArOf M rFL-ro s.~ppetr BASE~ T% N.PA. 3 w5 L&WS 23 I. VOf 9ulECL I'4of-I Dy O 1S to TXX-O)XXXXX Page 9 of 10 TXU GENERATION COMPANY LP COMANCHE PEAK STEAM ELECTRIC STATION UNIT 2 FIRST TEN-YEAR INTERVAL ISI RELIEF REQUEST NO. C-6 REV I PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10 CFR 50.55a(g)(5)(iii) -INSERVICE INSPECTION IMPRACTICALITY-Continued PICTURES VIA E-MAIL I

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