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{{#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 a
{{#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:
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1Afh-14-2003 FRI 12:13 PM ODMIN 8NNEX 1ST FLR         _      FAX NO. 2548970530                   P. 02
1Afh-14-2003 FRI 12:13 PM ODMIN 8NNEX 1ST FLR FAX NO.
: 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
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:==
==SUBJECT:==
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
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                   I 1986 EDITION OF ASME CODE, SECTION XI, NO ADDENDA (INTERVAL START DATE: AUGUST 3,1993, FIRST INTERVAL)
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:==
==REFERENCE:==
TXIJ Energy Letter logged TXX -02122 dated July 11, 2002 from C. Lancc Terry to the NRC                                           I
TXIJ Energy Letter logged TXX -02122 dated July 11, 2002 from C. Lancc Terry to the NRC I
I


==Dear Sir or Madam:==
==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.
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.
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.
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:
Sincerely, TXU Generation Company LP 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
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 Attachment 1 to TXX-OXXXX Page 1 off /,
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)
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:
-INSERVICE INSPECTION IMPRACTICALITY-I.
SystemlComponent for Which Relief is Requested:
ASME Class I Reactor Pressure Vessel (RPV) closure head to flange weld (Weld No.
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)
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:
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)
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.
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.
Line 58: Line 74:
Weld No. TCX-1-1300-2:
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.
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:
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).
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.
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       \\"
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)
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)
-INSERVICE INSPECTION IMPRACTICALITY-(Continued)
IXV. Burden Caused by Compliance:
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.
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:
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 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.
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 %
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.
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:
VI.
This relief is requested for the Comanche Peak Steam Electric Station Unit 2, third period of the first 10-year interval vessel examination.
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)
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:
-INSERVICE INSPECTION IMPRACTICALITY-VII.
: 1)   TXU Energy letter logged TXX-98170 dated July 22, 1998, NRC response dated July 8, 1999, reference TAC NO. MA3632.
Precedents:
: 2)     TXU Energy letter logged TXX-95042 dated March 6, 1995. NRC response dated December 28, 1995, reference TAC NO. M93333 and M93334.
: 1)
: 3)     NRC SER dated November 29, 1994, reference TAC NO. M83 125.
TXU Energy letter logged TXX-98170 dated July 22, 1998, NRC response dated July 8, 1999, reference TAC NO. MA3632.
: 4)     TXU Energy letter logged TXX-01110 dated June 22, 2001. NRC response dated October 11, 2001, reference TAC NO. MB 1l90.
: 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
MAR-14-2003 FRI 12:15 PM ADMIN ANNEX IST FLR -
                                                                      --                                                        I Attachment I to TXX-OX.XXX                                                                                                     i Page 5 of/
FAX NO. 2548970530 P. 08 I
1\                         TXU GENERATION COMPANY LP COMANCHE PEAC STEAM ELECTRIC STATION UNIT 2 FIRST TEN-YEAR INTERVAL IST RELIEF REQUEST NO. B-7 REV 1                                                             I PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10 CFR 50.55a(g)(5)(iii)
Attachment I to TXX-OX.XXX Page 5 of/
                              -INSERVICE INSPECTION IMPRACTICALITY-(Continued)                                                         I 0trxu wREORTN. UTr22 wESTINGHOUSE NUCLEAR SERVCES DMSION                     PAGE     3     or   5 UMITATION TO EXAMINATION
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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)
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-INSERVICE INSPECTION IMPRACTICALITY-(Continued) i I
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                                  -INSERVICE INSPECTION IMPRACTICALITY-TXU 0a                          WESTINGHOUSE NUCLEAR SERVICES DIVISION INSPECTION SERVICES SURFACE EXAMINATION DATA REPORT NO MT.02 PAGE     1   OF 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
-INSERVICE INSPECTION IMPRACTICALITY-P. 09 WESTINGHOUSE NUCLEAR SERVICES DIVISION REPORT NO MT.02 0a INSPECTION SERVICES PAGE 1
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__ __    _                      holt 14             -
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                                              .\_
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rm-iq-auu3 FRI 12:15 PH ADMIN ANNEX 1ST FLR                                                                   FAX NO. 2548970530                                           P. 10 Attachment I to TXX-OXXlXX Page 7 of -
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)
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                     -
-INSERVICE INSPECTION IMPRACTICALITY-PDI Calibration Data Sheet PlanVtUnit Comanche Peak 12 Dale Sheet #
Company                 WesDyne                 Page         1     of     5           _ __                                                    r Comp/Systern           RV Closure Head Procedure ND           TX-IS1-210                   1alChecks          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           _
UT-22 Company WesDyne Page 1
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                   l Ye I..     l IINo ln                     l             Saarc   U   . Cb -1t                                         --
of 5
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
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
_                        Instrument Settings                           Inslrument Settings
::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
__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                                       Calel 23301us Pulser SINGLE             M l Calrel l32O-isPulser PMI      SINGLE Damping       1000I I     Rejecl .OFF       Damping         t 1000      Reject OFF Rep Rate HIGH             Freq 2-8 Mhz       Rep Rate HIGH             Freq 2-8Mhz Fier Ft_            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)
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
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   -
Recordable Measured Angle 0o Measured Angle 45S Access Indications Exam lWedge Style NJA Wedge Style NON-INTEGRAL ExIrarnnatiin AraNIeII I..
I VWMTI, ir   14, I'. 1 Wit                                                             I Valf                               ANU At.k. /Its, 4i rn L7,                         +1),1, Z,                     _;?,
l II Ye l No ln l
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                                                                                                                            -- AL C.
-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.


FAX NO. 2548970530            P. 11 MAR-14-2003 FRI 12:16 PM ADMIN ANNEX 1ST FLR Attachment 1 to TXX-OXXXX Page 8 of 4-TXU GENERATION COMPANY LP UNIT 2 COMANCHE PEAK STEAM ELECTRIC STATIONNO. B-7 REV 1 REQUEST FIRST TEN-YEAR INTERVAL ISI RELIEF WITH 10 CFR 50.55a(g)(5)(iii)
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)
PROPOSED ALTERNATIVE IN ACCORDANCE
-INSERVICE INSPECTION IMPRACTICALITY-III  
                      -INSERVICE INSPECTION IMPRACTICALITY-III     oIt
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FAX NO. 2548970530                    P. 12 MAR-14-2003 FRI 12:16 PM ADMIN ANNEX 1ST FLR Attachmnent I to T-OXXX Page 9 of 4-TXU GENERATION COMPANY LP 2
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)
COMANCHE PEAK STEAM ELECTRIC STATION UNIT B-7 REV 1 FIRST TEN-YEAR INTERVAL ISI RELIEF REQUEST NO.
-INSERVICE INSPECTION IMPRACTICALITY-
CFR 50.55a(g)(5)(iii)
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MAR-14-2003 FRI 12:17 PM ADMIN ANNEX 1ST FLR       FAX NO. 2548970530               '. 13 P. f3 Attachment 1 to TXX-OXXXX Page 10 of 4, TXU GENERATION COMPANY LP COMANCHE PEAK STEA-M ELECTRIC STATIONNO.        UNIT 2 FIRST TEN-YEAR INTERVAL 1SI RELIEF REQUEST               B-7 REV I PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10 CFR 50.55a(g)(5)(iii)
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-
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MAR-14-2003 FRI 12:17 PM ADMIN ANN-EX 1ST FLR                 FAX NO. 2548970530                     P. 15 Attachment 2 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)
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-
-INSERVICE INSPECTION IMPRACTICALITY-
: 1. SystemlComponent for Which Relief is Requested:
: 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).
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:
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)
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.
Boiler and Pressure Vessel Code, Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components.
Weld No. TCX-l-l 100-5:
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.
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:
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).
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),
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.
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.
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 Attachment 2 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)
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:
-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.
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:
V.
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:
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.
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:
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.
: 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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RPV COVERAGE ESTIMATE BREAKDOWNS DIRECTION / ORIENTATION PARALLEL SCANS PERP. SCANS WELD NO.
                                                                                                                              >i2 RPV COVERAGE ESTIMATE BREAKDOWNS                                             PARALLEL SCANS           CCW / CW                                       I-PERP. SCANS              =UP/DN m P 1>
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rO ITEM / AREA                             Lower Head Circ                     WELD NO.         TCX-1-1100-5                                            '-3
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                                                                                                                                                      -o


MAR-14-2003 FRI 12:19 PM ADMIN ANNEX 1ST FLR                 FAX NO. 2548970530                 P. 21 Attachment 3 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)
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:
-INSERVICE INSPECTION IMPRACTICALlTY-I.
System/Component for Which Relief is Requested:
ASME Class I Reactor Pressure Vessel (RPV) Outlet Nozzle to Shell Welds.
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-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-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-23)
RPV Nozzle-to-Vessel     Weld (Weld No. TCX-1-1 IOOA-26)
RPV Nozzle-to-Vessel Weld (Weld No. TCX-1-1 IOOA-26)
II. Code Requirement from Which Relief is Requested:
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)
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.
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:
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.
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).
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:
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
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 Attachment 3 to T-OXXXX.X Page 2 of,#
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)
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.
-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:
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.
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.
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 %
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:
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.
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:
VII.
: 1)     TXU Energy letter logged TXX-99030 dated February 17, 1999. NRC response dated September 24, 1999, reference TAC NO. MA4845 and MA6322.
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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NO. 2548970530 FAX NO.                              P.24 MAR-14-2003 FRI 12:20 PM ADMIN ANNEX IST FLR                         FAX       2548970530               P. 24 I
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
Attachment 3 to TXX-OXXXXX Page 4 of TXU GENERATION COMPANY LP STATION UNIT 2 COMANCHE PEAK STEAM ELECTRIC REQUEST NO. B-9 REV 1 FIRST TEN-YEAR INTERVAL IS1 RELIEF WITH 10 CFR 50.55a(g)(5)(iii)
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)
PROPOSED ALTERNATIVE IN ACCORDANCE
-INSERVICE INSPECTION IMPRACTICALITY-Continued I
                                -INSERVICE INSPECTION IMPRACTICALITY-Continued I
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MAR-14-2003 FRI 12:21 PM ADMIN ANNEX IST FLR                   FAX NO. 2548970530               P. 26 Attachment 4 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)
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-
-INSERVICE INSPECTION IMPRACTICALITY-
: 1. SystemrComponent for Which Relief is Requested:
: 1.
SystemrComponent for Which Relief is Requested:
Chemical and Volume Control (CVCS) Pump TCX-CSAPCH-01. ASME Class 2 Integrally Welded Pump Attachments.
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:
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)
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.
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:
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.
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.
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       2PJ 1 MM1XADMIN ANNEX 1ST FLR             FAX HO. 2548970S3             -      27 Attachment 4 to TXX-OXCXXX Page 2 of#
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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)
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:
-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.
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:
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.
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.
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:
VI.
This relief is requested for the Comanche Peak Steam Electric Station Unit 2, third period of the first 10-year interval vessel examination.
Duration of Proposed Alternative:
VII. Precedents:
This relief is requested for the Comanche Peak Steam Electric Station Unit 2, third period of the first 1 0-year interval vessel examination.
I)     TXU Energy letter logged TXX-93107 dated March 15, 1993. NRC response dated November 29, 1994, reference TAC NO. M83 125.
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)
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FAX NO. 2548970530            P. 28 MAR-14-2003 FRI 12:22 PM ADMIN ANNEX_1ST FLR Attachment 4 to TXX-OXXXXX Page 3 off TXU GENERATION COMPANY LP STATION UNIT 2 COMANCHE PEAK STEAM ELECTRIC                              I RELIEF REQUEST NO. C-6 REV FIRST TEN-YEAR INTERVAL ISI WITH 10 CFR 50.55a(g)(5)(iii)
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FAX NO. 2548970530                                P. 29 MAR-14-2003 FRI 12:22 PM ADMIN ANNEX 1ST FLR Attachment 4 to TXX-OXXXXX Page 4 of Y LP TXU GENERATION COMPANY                                            UNIT 2 STATION COMANCHE PEAK STEAM ELECTRIC                                                  NO. C-6 REV 1 TEN-YEAR            INTERVAL        ISI RELIEF REQUEST FIRST IN  ACCORDANCE              WITH 10 CFR 50.55a(g)(5)(iii)
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Latest revision as of 11:15, 16 January 2025

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)
v • d • e


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.

,i-oc CPSE UN1 2 0;°c 9 .za-'-! 0% -0 0 -4 _q M sla En rr' -~- INSERVICE INSPECTION 6C LOCATION ISOMETRIC yms ~~,

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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0. 3OCTU PIst,. 70 D1S trm DEVAtI4 3,2P40 '314 323 AVC 41.42 S4 21 122 " e1 42.44 s12s 027 2?A c 43-4647 "at0 t?A 277U AVG 4n.4n, BOs Lis 277I AVG 34341 6A3 mg 2LS] AVG 3312,24 5 W40 E 32710 Sr "02 -123 271 AVuirg VMLuEZ wITI4I 02' cn m Ut v I 4J-n H m oN _Cs 0 ; &nm Ubt

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Ii Uomanche Peak Unit #2 I (;X) RPV COVERAGE ESTIMATE BREAKDOWNS DIRECTION / ORIENTATION PARALLEL SCANS PERP. SCANS WELD NO. CCW / CW =UP/DN TCX-1-1100-5 ITEM / AREA Lower Head Circ BEAM ANGLES BEAM 450 L Dual 45D L Single 45 Shear DIRECTION WELD VOLUME WELD VOLUME WELD VOWUME WEL VOLUME WELD VOLUME CCW 78.8 78.8 78.8 78.8 78.8 78.8 CW 78.8 78.8 78.8 78.8 78.8 78.8 UP (IN) 74 71 71 70 75 72 DOVN(O))7 (1) (1) (1) (1) 72 DOWN (OUT) 74 71 71 70 75 72 BORE AXIAL 0IV 0W C, 0 d CMI U' >i2 m P HOO Z c0 Cj,! tHto zz )o S a, H I I _a -Ir r O I- '-3 CZ) 1> -ri IMX _t= I E I ) Combination or aual sieda ana single sioca exams Combined Coverage = 75.5% ANALYST gL 9;_ -o

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-

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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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