ML20154C451

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Interim Change Request ISI-1R5-01, Unit 1 ISI Plan,Rev 5
ML20154C451
Person / Time
Site: Comanche Peak Luminant icon.png
Issue date: 07/20/1998
From: Mays R
TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
Shared Package
ML20154C446 List:
References
PROC-980720-01, PROC-980720-1, NUDOCS 9810060275
Download: ML20154C451 (90)


Text

F INTERIM CHANGE REOUEST a

Plan Title /Rev. nee / !dWN6 !#M#N Olet f*' E ICR No.I5f'/#b of

Reference:

Page Table Relief Request, and/or Component:'

6eb N/ E h M'3

/

Arts's A,B Reason for Change:

p,,,,, W cf :4(.e igpop rst og fk snMaA"AMMM"

&d., AsauL Ad W

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.aacladoled n & & W. & W n'XaaazST& & A AswtE Sesta~ L'L a ccuan d g

& Ao&

, WM Y &

b N.

Proposed Revision:

k ('"'f w

1 hm Prg's 7[I r[18

/

Initiator

' Department Date Approved: % Yes

[ ] No 784fa /; Mk ao 7-10 -f P Enginee' ring Prfgrfis Supervisor Date i

Reason for Disapproval:

STA-703-5 Page1 of1 R-1 L'

9810060275 981002 PDR ADOCK 05000445 G

PDR a

I ICR No. ISI-lRS-01 1

l Proposed Revision (contd.):

Replace existing section 4.1,4.2 and 4.3 page numbers 10,35,36,39,51,55,74,75,94, 98,109,115,156,167,168,186,187,198, 205, 208, 214, 220, 233, 234, 235, 240 and j

247 with the attached marked up pages.

1 Add the attached pages 109.1 and 250 to sections 4.2 and 4.3 respectively.

Replace existing Appendix A, Index of Relief Requests with the attached revised index.

Add the attached relief requests B-6 rev. 2, B-7 rev. 2, B-12, B-13, B-14 and C-9 to Appendix A.

Add the attached Appendix B page 4.

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DATE: 01/22/SQ COMANCHE PEAK UNIT 1 FAGE:

10 INSERVICE INSPECTION PLAN CMSS 1 SCHED/COMPL COMPONENTS INSPECTION IN*ERVAL, P MN STATUS

,PRESERVid YEAR l

FIRST SECOND THIRD l

ASME l

PERICD PERIOD PERIOD l

SEC. XI 1.--.-.----.--...-..--...----.... I

SUMMARY

EXAMINATION AREA' CATGY NDE l-. -- - - 0UTAGE- --- - - l INSTRUCTIONS N"JMB ER IDENTIFICATION ITEM NO METH l1 2 3 1 2 1 2 l

" CALIBRATION BLOCF"

...s.......

PEA" TOR N LAYT TBX-PCPCRV-01 005640 TBX-1-1400-13 B-G-1 (IT 1-

- C 92, TDLR VET.IFICATION BOUNDARY.

RV STUD B6.30 Pfr

    • TBX.52**

1 0056'60 TBX 1-1400-14 B-G 1 17T 1-

- C 82 TDLR VERIFICATION BOUNDARY.

RV STUD B6,30 MT 1

    • TBX-52**

005680 TBX 1 1400 15 B-G-1 ITT 1

. C 82 TDLR VERIFICATION B3UNDARY, RV STUD B6.30 MT

    • TBX-52**

005700 TBX 1 1400 16 B-G 1 ITT 1-

- C 82 TOLR VERITICATION BOUNDARY.

RV STUD B6.30 Mr

    • TBX.52**

005720 TBX-1 1400-17 B-G-1 UT 1-X -

82 TDLR VERIFICATION BOUNDARY.

RV STUD

~ -

R160 905RB S(,.10

    • TBX-52**

005740 TEX 1 1400-18 B-G-1 177 1 - * -

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82 TCLR VERIFICATICN BOUNDARY.

RV STL";

B6.30 M!

R160 905RB

  • TEX - 5 2 "

l' 005760 TBX 1-1400-19 B-G 1 UT 1-C -

82 TCLR VERIFICATICN BOL"CARY.

EV STUC B6.30 MT R16* 905KB "TbX 5 2 "

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DATE: 01/33/98 COMAN"HE PEAK UNIT 1 PAGE 35 INSERVICE INSPECTION PLAN CLASS 1 SCHED/COMPL COMPONENTS IhSPE NION INTERVAL, PLAN STATUS

,PRESERVICE YEAR l

rIRST sECOND THIRD l

ASME l

PERIOD PERIOD PERIOD l

SEC. XI l ----------- ---+-- -.- ------...- l

SUMMARY

EXAMINATION AREA CATGY NDE l-


CUTAGE-- ---- l INSTRUCTICNS NUMB,ER IDENTIFICATION ITEM NO METH l1 2 3 1 2 1 2 l

  • CALIBRATION BLOCK" PEA MCP COOIAVT TEX 4CPCSS 02 010800 TBX-1-3100 2A B-D 17T 1-C -

NA TDLR VERIFICATION BOUNDARY.'

~$32 INLET NOZZLE INNER RADIUS B3.140 A25 812RB

..s0.I3..

1 010900 TBX-1-3100-28 B-D UT 1-C -

NA TDLR VERIFICATION BOUNDARY.

)

' SG2 OtTTLET NOZZLE INNER RADIUS B3.140 A25 812RB

    • SG-IR**

I C11000 TBX-1-3100-2Bl.16 B-G-2 VT-1 1 - - -

C -

84 TDLR VERIFICATION BOUNCARY.

532 HOTLEG MANWAY BOLTING B7.30 (2-B1/2-B16).

A25 412RB 011100 TBX 1-3100-2B17-32 B-G 2 VT-1 1-C -

84 TDLR VERIFICATION BOUNDARY.

SG2 COLCLEG MANWAY BOLTING B7.33 (2-B17/2-832)

A25 812R8 F E A'""OP COO'E *T TPX-RCPCSS-?3

.1200.TBX-1-3100 3-1 BB UT 1-X -

82 TDLR VERIFICATION BOUNDARY.

SG3 CHANNEL HEAD TO TUBESHEET B2.40 WELD R154F812RB

    • TBX-23**

011300 TBX-1-3100-3A BD ITT 1-X -

NA TDLR VERIFICATION BOUNDARY.

SG3 INLET NCZZLE INNER RADIUS B3.140 R154E812Rb

  • T;::

S G r R.

011400 TBX 1-3100-3B B-D L*!

1-X -

NA TDLR VERIFICATION BOUNDARY.

S33 0"77LET NCZZLE INNER RACIUS B3.14C R154K611RB

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DATER 01/23/98 COMANCHE PEAX UNIT 1 PAGE:

36 INSERVICE INSPECTION PLAN C1 ASS 1 SCHED/COMPL COMPONENTS l

INSPECTION INTERVAL, PLAN STATUS

,PRESERVICE YEAR l

IIRST SECOND THIRD l

ASMC l

PERIOD PERIOD PERIOD l

SEC. XI l ----------- ----------- ----------- l

SUMMARY

EXAMINATION AREA CATGY NDE l------0UTAOE-- - - - - l INSTRUCTIONS NUMBER IDENTIFICATION ITEM NO METH l1 2 3 1 2 1 2 l

    • CALIBRATION BLOCE**

PEA NOR COOIN G TBX PCPCSG-03 011500 TBX 1-3100-381-16 B-G-2 VT 1 1 X -

64 TDLR VERIFICATION BOUNDARY.

$G3 HOTLEG MANWAY BOLTING B7.30 (3-B1/3-BI6)

R154k812RB 011600 TBX-1-3100-3B17-32 B-G 2 VT-1 1-X -

84 TDLR VERIFICATION BOUNDARY.

SG3 COLDLEO MANWAY BOLTING B7.30 (3 B17/3-B321 R154K812RB PEA TOR CTLAN* TBX-PCPCS3-04 011700 TBX-1-3100-4-1 B-B W

1-X B2 TDLR VERIFICATION BOUNDARY.

SG4 CHANNEL HEAD TO TUBESHEET B2.40 WELD R154L812RB

    • TBX-20**

l 011800 TBX 3100-4 A B-D W

1-X -

NA TDLR VERIFICATION BOUNDARY.

l S34 INLET NCZZLE INNER RADIUS B3.140 R154L812RB

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64T k 1900 TBX-1-3100 4h B-D W

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NA TDLR VERIFICATION BOUNDARY.

SG4 OtfrLET NOZZLE INNER RACIUS B3.140 R154L812RB

.m.

6 6aT k l

C 2000 TBX-1-3100 4B1-16 D-G-2

\\"T 1 1 - - -

X -

84 TDLR VERIFICATION BOUNDARY.

l SG4 HOTLEO MANWAY BOLTING B7.30 14-B1/4 916) i R154 L812 RB C121LO TBX-1 310C-4B17-32 B-G-2

\\*' - 1 1-X -

84 TDLR VERITICATICN BOUNCARY.

SG4 CCLDLEG MANWAY BOLTINJ B7.3*

14 Bl*1/4-B32)

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DATEi 01/33/08 COMANCRE PEAF UNIT 1 PAGE:

39 INSERVICE INSPECTION PI.AN CLASS 1 SCHED/COMPL COMP UENTS INSPECTION INTERVAL, PLAN STATUS

,PRESERVICE YEAR l

FIRST SECOND THIRD l

ASME l

PERIOD PERIOD PERIOD l

SEC, X:

l.-*. ~*.--- =----- ---- =----~--.-- l

' SUMMAJtY EXAMINATION AREA -

CATGY NOE l--*

.-0UTAGE------

l INSTRUCTIONS HUMBEP IDENTIFICATION ITEM NO METH l1 2 3 1 2 1 2 l

    • CALIBRATION BLOCK" I

I FESIDUAL HEAT PEMOVAL 12-FH 1-001-2501P-1

]

015800 TBX.1-4101-8701A-BLT BG2 VT 1 1-

- C 84 VALVE BODY BOLTING B7.70 R154 C17RB C15810 TBX 1 4101 87 CIA INT B-M 2 VT-3 1-X 84 GROUP 2 - ONE VALVE W! THIN THE VALVE BODY INTERNAL SURPACES B12.50 CROUP TO BE EXAMINED R154Ia17RB REA T F COOLANT 10 PC-1-021-2501R '

016100 TBX-1-4102-3 B-J W

1C - -

82 PIPE TO ELBOW 89.11 PT A23 831RB

  • *TBX - 9 "

016200 TBX.1 4102-4 B-J UT 1C. -

82 ELBOW *O PIPE B9.11 PT A23 P31RB

  • TBX. 9 "

6500 TBX.1 4102-7 B-J UT 1-X.

J1 PIPE TO VALVE 89.11 PT R1541831RB

    • TBX-9'*

SAFETY TN?r"'T!*N 2 6 - F T 1 *' 9 - 2 5 "1 F - 1 C16600 TBX-1 4102 6 B-J UT 1 - -

X -

81 VALVE TO PIPE B9.11 PT l

R154I631RE l

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DATE: 01/32/98 COMANCHE PEAK UNIT 1 PAGE:

51 INSERVICE INSPECTION PLAN CLASS 1 SCHED/COMPL COMPONENTS INSPECTION INTERVAL, PLAN STATUS

,PRESERVICE YEAR l

FIRST SECOND THIRO j

ASME l

PERIOD PERIOC PER'OD l

SEC. XI l -- -------- ----------- ------ ---- l

SUMMARY

EXAMINATION AREA CATGY NOE l-----

0UTAOE- ----- l INSTRUCTIONS NUMBER IDENTIFICATION ITEM NO METH !1 2 3 1 2 1 2 l

  • 0ALIBRATION BLOCK *
  • SAFETY INJE NIOh 6-ff-1-101-2501 M 036400 TBX-1-4203-89498 BLT B-G-2 VT-1 1 - - -

X -

84 VALVE BODY BOLTING B7.70 R154J831RB 036410 TBX 1-4203-6949B-INT B-M-2 VT-3 1-84 GROUP 4 - ONE VALVE NITHIN THE VALVE BODY IITTERNAL SURFACES B12.50 GROUP TO BE EKAMINEC R154J831RB EEANOP COCUW' 6-PC-1-029-2501R-1 036500 TBX-1-4203-9 B-J UT 1-

- C 82 VALVE TO PIPE B9.11 PT R154J831RB l

    • TBX-5**

1 i

PEA 509 CO'"J.N' 1.5-PC-1-039-2501P 1 03790C TBX 1-4205-4 BJ PT 1-

- C 82 FIPE TO ELBOW B9.40 R154J831RB 038000 TEX 1-42C5 5 B-J PT 1-

- C 88 ELBOW TO PIFE 89.40 E1$4J631RB 03010C TEX-1+4205-f B-J PT I - - -

C 82 PIPE TO VALVE B 9.4 0 P154J831RB t

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CATE: 01/32/96 COMANCHE PEAK UNIT 1 PAGE:

55 INSERVICE INSPECTION PLAN CLASS 1 SCHED/COMPL COMPONENTS INSPECTION INTERVAL, P1AN STATUS

_PRESERVICE YEAR l

FIRST SECON THIRD l

ASME l

PERICO PERICO PERIOD l

sgC. 31 l................................. l l

SLwMY EXAMINATION AREA CATGY NDE l------0UTAGE- - - - - - l INSTRUCTIONS NUMBER IDENTIFICATION ITEM NO METH l1 2 3 1 2 1 2 l

' CALIBRATION BLOCK *

  • j PEANOR COOLANT 31 RC-1-041-WEST-1 045100 TBX-1 4300 16 BJ PT 1-

- C 82 TOLR VERIFICATION BOUNLARY.

PIPE TO BRANCH CONNECTION B9.32 A27 816RB REA NOR CCOLANT 10-PC 7-059-2501P-1 046200 TBX-1-4301 7 BJ Li 1-X.

82 PIPE TO VA!VE B9.11 PT R154K832RL

'TBX 9 "

SAFETY INJE NION 10-ST.1 191-2501R.1 044300 TBX 1-4301 8 B-J UT 1-X.

81

/ALVE TO PIPE B9.11 PT R154K832RB

    • TBX-9'*

047000 TBX-1-4301-15 B-J UT 1-X -

82 PIPE TO VALVE B9.11 F~

R154 KE 23RB

    • TEX-9'*

047200 TBX 1 4301 89560-BLT B-G-2 VT-1 1 - - -

X.

84 VALVE BODY BOLTIN3 B7.70 R154K823RB 047210 TBX-1 -4 3 01 - 6 9 5 6 C-INT B M-2 VT-3 1-

- C 64 CROUP 3 - CNE VALVE W!*'HIN THE VALVE BODY It'TERNAL SURFACES E12.50 GROUP TO BE EXAMINE 0 22' B23RB i

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DATE: 01/33/08 COMANCHE PEAK UNIT 1 FACE:

76 INSERVICE INSPECTION PLAN CLASS 1 SCHED/COMPL COMPONENTS INSPECTION INTERVAL, PLAN STATUS

,PRESERVICE YEAR l

FIRST SECOND THIRO l

ASME l

PERIOD PERIOD PERIOD l

SEC. XI l

l

SUMMARY

EXAMINATION AREA CATGY NCE l

0UTAGE--


l INSTRUCTIONS 90CER IDEN"IFICATION ITEM NO METH l1 2 1 1 2 1 2 l

    • C EIBRATION BLCCF**

PFA 70R C00LAtt 3-RC-1-111-2501k-1 086100 TBX-1-4502 11 BJ PT 1-X -

82 PIPE TO VALVE B9.21 R161A907RB 086200 TBX-1-4502 12 B-J PT 1-X -

82 TDLR VERIFICATION BCIA'OARY.

VALVE TO PIPE B9.21 R161A907RB 086900 TBX-1-4502 19 BJ PT 1-X -

88 TCLE VERIFICAT*0N BOUNCARY.

WELDOLET TO PIPE B9.32 R161A908RB I

RFA 70F COOLAN*

3-RT-1-148-2501P-1 087600 TBX-1-4502-26 B.J PT 1 - - -

- C 82 TDLR VERIFICATION EOUNDARY.

PIPE TO VALVE B9.21 R161A907RB 17900 TBX-1-4502 29 B-J PT 1-

- C 82 VALVE TD PIPE B9.21 R161A907RB 088000 TBX 1-45C2 30 B-J PT 1 - - -

- C 82 P!!E TO VALVE B9.21 R161A907RB F F A'"*SF SOLAN~ 4 9 '" ' ' O-?t'1F

  • X

$90200 TBX-1-4503-16 B-J UT 1 -

y.

8; FIP.i TO VALVE B9.11 PT R160B909RE l

    • TBX 4**

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DATE 01/32/93 COMANCHZ PEAK UNIT 1 PAGE:

75 INSERVICE INSPECTIC PIAN CLASS 1 SCHED/COMPL COMPONENTS INSPE:'"rION Ih7ERVA1, PLAN STATUS

_PRESERVICE YEAR l

FIRST SECONO THIRO l

ASME l

PERIOD PERIOD PERICD l

SEC. XI l ------ ---- -----.-----.-.-------- l

SUMMARY

EXAMINATION AREA CATGY NDE l------0UTAGE- - ---- l INSTRUCTIONS NUMBER IDEhi1PICATION ITEM NO METH l1 2 3 1 2 1 2 l

" CALIBRATION BLOCE" PEA" TOP COCIAN*

4-P?-1-089 2501P-1 090300 TBX-1-4503-19 B-J UT 1-X 82 VALVE TO PIPE 89.11 PT R160B909RB

  • *TBX - 4 "

PEA" TOP COOIRr-4-PC-i-091-21019-1 091000 TBX-1-4503-26 B-J UT 1C.

82 REDUCER TO PIPE B9.11 PT R161A913RB

    • TBX-4**

091100 TBX-1-4503-27 BJ ITT 1 - - -

- C 82 PIPE TO PIPE B9.11 PT R161A913RB

  • *TBX - 4 "

C91200 TBX-1-4503-28 BJ UT 1 - - -

- C 88 PIPE TO PIPE B9.11 PT R161A906kB j

  • TB X - 4 "

'1300 TBX 1-4503-29 B-J UT 1-

- C 82 PIPE TC PIFE B9.11 PT R161ASC6RB "TBX - 4 *

  • 091400 TBX-1-4503-30 B-J UT 1C - -

82 P!PE TO SAFE E!C B9.11 PT RI CI A9 0 *'RE

  • TEX - 4 "

09150^ TBX-1-4503-3; B-T UT 1

- C 8:

SAFE ENO TO FRESS"RIZER N02ZLE B5.40 P"

Rii,1A907RB

    • DMCB-I'*

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CATE 01/22/03 COMANCHE PEAK UNIT 1

PA3E, 94 INSERVICE INSPECTION PLAN CLASS 2 SCHED/COMPL COMPONENTS INSPECTION INTERVAL, PLAN STATUS

,PRESERVICE YEAA l

FIRST SECOND THIRO l

ASMI j

PERIOC PERIOD PERIOD l

SEC. XI l ----------

l SUMMAAY EXAMINATION AREA CATGY NOE l. - - - --0UTAGE------

l INSTRU~f10NS NUMBER IDENTIFICATION ITEM NO METH l1 2 3 1 2 1 2 l

    • CALIBRATION BLOCF**

FEEDWATEP 14 - FW 0 76 -13 0 3 2 164000 TBX-2-2401-1 C-F 2 UT 1-C -

82 TDLA VERIFICATION BOUN;ARY.

NOZZLE TO ELBOW C5.51 MT A29 841RB

    • TBX 20**

FEEDWATFF 18-FW-1 020-1301 2 166100 TBX-2-2401-2 C r-2 UT 1 - - -

X -

NA TOLR VERITICATION BCUNOARY.

ELBOW TO PIPE C5.51 MT R155K840RB

    • TBX-21**

164900 TBX-2 2401 10 C-F-2 UT 1-C -

82 TDLR VERIFICATION BOUNOARY.

PIFE TO PIPE (PENETRATION)

C5,51 MT R155A856RB

    • TBX-21**

FFE? WATER 18 FW- -037-2003-2 165300 TBX-2 2401-13 C-F 2 UT 1-X 82 TDLR VERIFICATION BOUNDARY.

PIPE TO VALVE C5.51 MT K10CA856SB

    • TBX-36**

165400 TBX-2 2401-14 C-F-2 UT 1-f ><

82 VALVE TO PIPE C5.51 MT RICCA856SB

    • TBX-3s**

FFEDWATEP 16-FW-1-02*-13'?-2 16571* TBX-2-2401-16 C-F-2 UT 1

X -

6:

TOLR VERIFICATION BOUNOARY.

FIFE TO FLANOE Cf.1*

MT R155A456EB

    • TBX 01**

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DATE: 01/32/C8 COMANCHE PEAK UNIT 1 PAGE:

08 INSERVICE INSPECTION PLAN CLASS 2 SCHED/COMPL COMPONENTS INSPECTION INTERVAL, PLAN STATUS

,PRESERVICE YEAR l

FIRST SECOND THIRD l

ASKE l

PERIOD PERIOD PERIOD l

SEC. XI l --..-....... --...-.............. l

SUMMARY

EXAMINATION AREA CATGY NDE l.--

-. OUTAGE- -


l INSTRUCTIONS

- NUMBER' IDENTIFICATION ITEM NO METH l1 2 3 1 2 1 2 l

    • CAL:BRATION DLOCF**

RESIDUAL HEAT PEMOVAL 12-RH 1-004-601R-2 179700 TBX-2 2501-12 C-F 1 UT 1-X -

82 ELBOW TO PIPE C5.11 PT R63 806S8

    • TBX-11**

PESIDUA! HEAT PEMOVAI.

16-PH-1-009 6019 2 181100 TTX-2-2501 26 C-F-1 UT 1-X -

82 FLANGE TO P!PE C5.11 PT RSI 180$B

    • TBX 15**

181200 TBX 2-2501-27 C-F 1 UT 1-X -

NA PIPE TO FLANGE C5.11 PT E51 776SB

    • TBX-15**

)

181300 TBX-2 2501 28 C-F-1 UT 1

X -

NA FLANGE TO ELBOW C5.11 PT R51 775SB

    • TBX-15**

1400 TBX-2-2501 29 C-F-1 UT 1-X -

NA ELBOW TO PIPE C5.11 PT K51 775SB

    • TBX-15**

181500 TBX-2 2501 30 C-F-1 UT 1

)(

82 PIPE TO ELBOW C5.11 PT R51 775SB

    • TBX-15**

181400 TEX.2 2501 31 C-F-1 UT 1 - - -

X -

82 ELLOW TO PIPE C5.1.

PT K51 77556

    • TEX-15**

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'DATE: 01/22/98 COMANCHE PEAK UNIT 1 PAGE.

109

':NSERVICE INSPECTION PLAN CL LSS 2 SCHED/COMPL COMPONEWS INSPECTION INTERVK PLAN STATUS

_PRESERVICE YEAR g

l FIRST SECOND THIRD l

ASME l

PERIOD PERIOD PERIOD l

SEC. XI l.................-......-........ l BUMMARY EXAMINATION AREA CATOY NDE l-.....OUTAOE.-

-..- l INSTRUCTIONS l

NUMBER IDENTIFICATION ITEM NO K TH l1 2 3 1 2 1 2 l

    • CALIBRATION BLOCK'*

CHEvfCAL & VOtt3b: C0hievt 4-CS-1-344-25019-2 303200 TBX 2-2569 21 C.F-1 ITT 1C..

NA PIPE TC TEE C5.2*.

PT R203 818AB

  • *TBX - 4 "

303300 TBX-2 2569 22 C-F-1 UT 1C -.

NA TEE TO PIPE C5.21 PT l

R201 818AB

..TBx....

CHEvfCAL & VCL WE CO WPOL 3-09-1-626 2501P-2 30$500 TBX-2-2569-44 C.F-1 ITT 1...

X.

NA PIPE TO REDUCER C5,21 PT R203 818AB

  • *TBX - 3 "

CHEMTCAL & V0ttWE CONTP?L 2-CS-1 6?0-7901P-2 305700 TBX-2 2569 46 C-F-1 PT 1.. -

X -

NA i

PIPE TO ELBOW C5.30 R203 818AB j

p 305600 TBX.2-2569 47 C-F.1 PT 1

X -

NA ELBOW TC PIPE C5.30 R233 818AB CHrv! CAL & VOLW T C^!-50.

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- DATE: 06/19/98 CONANCHE PEAK C]IT 1 PAGE:

109.l INSERVICE INSPECTION PIAN CLASS 2 ALL STATUS CONPONENTS j.

INSPECTICIf IlrrERVAL, PIAN STAWS

_PRESERVICE YEAR l

l FIRST SECOND THIRD l

ASME l

PERIOD PERIOD PERIOD l

SEC. XI l...-............-................ l

+

SUtelARY EXANIMATION AREA CATGY NDE l-..... OUTAGE-.....l INSTRUCTIONS j

NUMBER IDElfrIFICATICII ITEN NO NETH l l' 2 3 1 2 I 2 l

    • CALIBRATION BIDCK**

CHENICAL & VOLUME C00rrROL 4.CS.1 085 2501R.2 l

. 30'7300 TRE-2-2570 2 C.F.1 UT 1

C NA l

l FIAlf05 TO PIPE C5.21 PT

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R201 816AB

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    • TBX.4**

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j DATE: 01/22/08 COMANCHE PEAX UNIT 1 PAGE:

115 INSERVICE INSPECTION PLAN CLASS 2 SCHED/COMPL COMPONEFTS INSPECION INTERVAL, PLAN STATUS

_PRESERVICE YEAR l

FIRST SECOND THIRD l

ASME l

PERIOD PERIOS PERIOD l

SEC. XI l.----------..-. --...-.....-...- l

SUMMARY

EXAMINATION AREA CATGY NDE l------0UTACE--.

l INSTRU:"TIONS NUMBER IDENTIPICATION ITEM NO METH l1 2 3 1 2 1 2 l

  • CALIBRATION BLOCE*
  • SAFETY INJECTION 24-SI-1-901-1519-2 314900 TBX 2-2580-3 C-P-1 UT 1-C -

NA I

PIPE TO VALVE C5.11 PT R65D 814YD

    • TBX-50**

l SAFETY INJECTION 24-SI-1-029-1519-2 336200 TBX-2-2580 16 C-F-1 UT 1-C -

NA PIPE TO ELBOW C5.11 PT R85D 803YD

  • TBX 5 0 *
  • 336300 TBX-2-2580 17 C-F-1 UT 1-C.

NA ELBOW TO PIPE C5.11 PT R830 803YD

    • TBX-50**

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SUMMARY

EIAMINATION AREA CATGY NDE l------0UTAOE. --.-- l INSTRUC"IIONS NUMBER IDENTIFICATION ITEM NO METH l1 2 3 1 2 1 2 l

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SAFETY INJE"if0N 4-SI.1-306-2501R-2 702500,TBX.2 2566-H25 F-B VT-3 1 X.

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SUMMARY

EXAMINATION AREA '

CATGY NDE l------0UTAGE---

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SAFETY INJECTION 3-ST-1-336-1501R-2 X

793300 TBX-2-2563-H13 F-C VT-3 1-X -

NA SNUBBER SI-1-336 003-822K NOTE 1 R66 788SB SAFETY INJECTION 24-SI-1-901-151P-2 723400 TBX 2-2580-H30 F-C VT-3 1-X -

NA STRUT SI-1-901-701-Y32R NOTE 1 R85D 814YD

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703450 TBX-2-2580 H30 C-C PT 1-X -

NA 3/4" PAD 360 SI-1-901-701-Y32R C3.40 R8 5D 814 YD SAFETY INJECTION 16-ST-1-914-151P-2 793700 TBX-2-2579 H3 F-B VT-3 1-X -

NA ANCHOR SI-1 914-003-S32A NOTE 1 R66 802SB 793750 TBX 2-2579-H3 C-C PT 1-C -

NA la PAD 360 SI-1-914-003 S32A C3.40 R66 802SB FEr$ WATER 19 - FW 016 -2 0

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NA MOMENT RESTRAINT. SI-0681 cpi FWSSMR-C1 NOTE 1 R100A856SB i

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SUMMARY

EXAMINATION AREA CATGY NDE l-.

---0UTAGE- --- - - l INSTRUCTIONS l

NUMBER IDENTIFICATION ITEM NO METH l1 2 3 1 2 1 2 l

  • CALIBRATI ON BLOCK *
  • 1 l

AUXILARY FEEDWATEP 3-AF-1-076-2003-3 030350 D-A VT-3 1-X -

NA 2-2* SCH40 STANCHION AF-1-076-072-S33R D1.20 R74 792SB AUXILAPY FTEDWATER 3-AF-1-078-2003-1 930700 FC VT-3 1-X

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l 83125C D-A VT-3 1 - - -

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EXAMINATION AREA CATGY NDE l------0UTAGE- ----- l INSTRUCTIONS

' NUMBER IDENTIFICA* ION ITEM NO METH l1 2 3 1 2 1 2 l

  • CALIBRATION BLOCK *
  • j AUXILARY FEEDWATEP 4-AF-1 101-2003-3 851800 F-B VT-3 1-

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EXAMINATION AREA CATGY NDE l---

-0UTAGE-- --

- 1 INSTRUCTIONS NUMBER ICENTIFICATION ITEM NO METH [1 2 3 1 2 1 2 l

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NA STRUT CC-1 008-022 A33R NOTE 1

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----------- l

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EXAMINATION AREA CATGY NDE l


0UTAGE

- - - - - l INSTRUCTIONS NUMBER IDENTIFICATION ITEM NO METH l1 2 3 1 2 1 2 l

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SEC. XI l -....------ ----------- ----------- l

SUMMARY

EXAMINATION AREA CATOY NDE l-...-.OUTAOE--

... - l INSTRUCTICNS PrJMBER IDENTIFICATION ITEM NO METH l1 2 3 1 2 1 2 l

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l INSTRUCTIONS NUMBER IDENTIFICATION ITEM NO METH l1 2 3 1 2 1 2 l

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DATE: 07/01/98 COMANCHE PEAK UNIT 1 PAGE:

250 INSERVICE INSPECTION PLAN CLASS 3 SCHND/COMPL COMPONENTS INSPECTION IlffERVAL_

PLAN STATUS

_PRESERVICE YEAR l

FIRST SECOND THIRD l

ASME -

l PERIOD PERIOD PERIOD l

SEC. XI l................................. l 80te44RY EIAMINATION AREA CATUY NDE l-.....OUTAOE......l INSTRUCTIONS NUteER IDElff1FICATION ITEM NO METH l1 2 3 1 2 1 2 l

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APPENDIX A RELIEF REQUESTS It is impractical within the limitations of the CPSES plant design, geometry and accessibility for TU Electric to meet certain requirements of Articles IWA, IWB, IWC, IWD and IWF of the Code. Compliance with these requirements would result in hardships or unusual difTiculties without a compensating increase in the level of plant quality or safety. Therefore, pursuant to 10CFR50.55a(g)(5)(iii), the relief requested from the Inservice Inspection requirements of 10CFR50.55a(g)(4)(i) is discussed in detail in this appendix. Reliefis requested for the first 120 month interval of the CPSES inservice inspection program.

l P

f l

Appendix A - Page I

INDEX OF RELIEF REQUESTS i

Submittal RR.

Subject Letter NRC Evaluation Remarks A-1 Pressure Retaining Bolted Connections TXX-93290 Approved -

NRR-87% (07/26/94)

. A-2 Insulated Bolted Cnnections TXX-93290 Approved -

NRR-87% (07/26S4)

B-1 Reactor Coolant Piping VT-2 Exams TXX-91377 Approved -

RR not required within NRR-8158 (10-1-92) shield wall B-2 Circumferential Piping Weld (TBX-l-4103-4)

TXX-92138 Approved -

NRR-8893 (l1/29/94)

[

l B-3 Ci cumferential Piping Weld (TBX-1-4503-30)

TXX-92138 Approved -

NRR-8893 (lI/29/94) c B-4 Nozzle Inner Radii (Code Class 1)

TXX-93107 Denied -

Removed by Plan Rev. 4 I

NRR-8893 (l1/29/94)

B-4 Nozzle Inner Radii (Code Class 1)

TXX-94050 Denied -

Removed by Plan Rev. 4 Rev.I NRR-8955 (02/14/95) i i

B-5 Circumferential Piping Welds TXX-93107 Approved -

(TBX-1-4103-1,4202-1)

NRR-8893 (11/29S4) i B-6 Reactor Vessel Closure llead Welds - First Period TXX-93107 Approved -

NRR-8893 (lI/29/94)

[

t B-6.

Reactor Vessel Closure llead Welds - Second Period TXX-95192 Approved -

Rev.I NRR-9156 (12/28/95)

B-6 Reactor Vessel Closure llead Welds - Third Period iRF06 CPSES-9803379 Rev.2 i

B-7 Steam Generator Tubesheet - Channel llead Weld TXX-94050 Approved -

(Code Class 1)- First Period NRR-8955 (02/14/95)

Appendix A - Page 2

INDEX OF RELIEF REQUESTS (cont.)

Submittal RR Subject Letter NRC Evaluation Remarks B-7 Steam Generator Tubesheet - Channel IIead Weld TXX-95192 Approved -

Rev.1 (Code Class 1)- Second Period NRR-9156 (12/28/95)

B-7 Steam Generator Tubesheet - Channel liead Weld iRF06 CPSES-9803379 Rev. 2 (Code Class 1)-Third Period B-8 Dissimilar Metal Weld (TBX-1-4200-5)

TXX-95192 Approved -

NRR-9I56 (12/28/95)

B-9 Pressurizer Nozzle Welds TXX-97014 B-10 Branch Pipe Connection Welt' (TBX-t-4104-1)

TXX-97014 B-11 Circumferential Piping Weld (TBX-1-4201-7)

TXX-97014 B-12 Pressurizer Lower llead to Shell Weld (TBX-1-2100-1) lRF06 CPSES-9803379 B-13 Circumferential Piping Welds (TBX-1-4102-7,4301-7, IRF06 CPSES-9803379 4402-7)

B-14 Branch Pipe Connection Weld (TBX-1-4404-1) 1RF06 CPSES-9803379 C-1 Piping Integral Welded Attachment (TBX-2-2538-Ill7)

TXX-90543 Approved -

Removed by Plan Rev. 4 NRR-8158 (10/01/92)

C-2 lieat Exchanger Shell Welds (TBX-2-I l20-1-1,2)

TXX-92138 Approved -

NRR-8893 (lI/29/94)

C-3 Circumferential Piping Welds (TBX-2-2570-32,33)

TXX-92138 Approved -

NRR-8893 (lI/29/94)

C-4 Piping Integral Welded Att. (TBX-2-2536-il2)

TXX-92138 Denied -

Removed by Plan Rev. 4 NRR-8893 (lI/29/94)

C-5 Nozzle Inner Radii (Code Class 2)

TXX-93107 Denied -

Removed by Plan Rev.4 NRR-8893 (lI/29/94)

Appendix A - Page 3

~

1 INDEX OF RELIEF REQUESTS (cont.)

Submittal

.RR Subject Letter NRC Evaluation

. Remarks j

C-6 Circumferential Piping Weld (TBX-2-2580-3)

. TXX-93107 Approved -

NRR-8893 (lI/29/94)

C-7 Pump Integral Welded Att. (TBX-2-3110-1-3WS,4WS)

TXX-93107 Approved -

NRR-8893 (lI/29/94)

C-8 Circumferential Piping Welds (TBX-2-2530-29,30).

TXX-94050 Approved -

NRR-8955 (02/I4/95)

C-9

. Ileat Exchanger Head and Shell Welds 1RF06 CPSES-9803379 (TBX-2-1110-1,1180-2-2)

D-1 IIcat Exchanger VT-2 Exams (Code Class 3)

TXX-90543 Approved -

l NRR-8158 (10/01/92)

F-1 Component Supports (Code Class 3)

TXX-92138 Denied -

Removed by Plan Rev. 4 NRR-8893 (1I/29/94) k

'4 1

1-4 I

i I

Appendix A - Page 4

CPSES UNIT 1 RELIEF REQUEST B-6 REVISION 2 A.

Item (s) for which reliefis requested:

TBX-1-1300-1 TBX-1-1300-2 Reactor Vessel Closure Head B.

Item (s) Code Class:

.1 C.

Examination requirement from which reliefis requested:

The requirement for volumetric examination of 100% of the weld lengths as described in Table IWB-2500-1, Examination Category B-A, Item No.'s Bl.40 and Bl.21.

Note - The CPSES ISI Plan requires that 1/3 of each of these welds be examined each inspection period. A relief request revision is processed to document the specific limitations encountered during each examination.

D.

Basis for relief:

Interferences from the reactor head flange, shroud and lifting lugs preclude the complete ultrasonic examination of the volume required by Fig.'s IWB-2500-3 and IWB-2500 5 as applicable.

Approximately 13% of the examination volume of weld TBX-1-1300-1 and 17% of the examination volume of weld TBX-1-1300-2 did not receive the full code required coverage during the first period examinations.

Approximately 15% of the examination volume of weld TBX-1-1300-1 and 17% of the l

examination volume of weld TBX-1-1300-2 did not receive the full code required coverage l

during the second period examinations.

l Approximately 15% of the examination volume of weld TBX-1-1300-1 and 17% of the examination volume of weld TBX-1-1300-2 did not receive the full code required coverage during the third period examinations.

Page1of11 L

t

CPSES UNIT 1 RELIEF REQUEST B4 REVISION 2 (cont.)

Best effort examinations were performed during each period with thl circumferential scan coverage was obtained for both welds. Axial scan coverage 99 %

achieved in one beam path direction with two different beam angles for i

i of the examination volume of TBX-1-1300-1 and for approximately 97% o volume of TBX-1-1300-2.

See pages 3 through 11 for weld locations and examination area config There were no recordable indications identified by the best effort volu perfonned or by the required surface examination performed on TB E.

Altemate examinations:

None Anticipated impact on the oveisii level of plant quality and safety:

F.

None i

l Page 2 of 11

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RELIEF REQUEST NO, B-6 REV. 2 PAGE 8 OF 11 FIRSTINSPECTION PERIOD RESULTS i

WESTINGHOUSE NUCLEAR SERVICE DIVISION R $ P.,

INSPECTION SERVICES LIMITATION TO EXAMINATION PLANT CO*fANdME AfAI UNIT Md /

SKETCH ISX

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RELIEF REQUEST NO, B-6 REV. 2 PAGE9 F 11 SECOND INSPECTION PERIOD RESULTS WESTINGHOUSE NUCLEAR SERVICE DIVISION

~

INSPECTION SERVICES "T.'

LIMITATION TO EXAMINATION PLANT COMANCHE PEAK UNIT NO.1 SKETCH TBX-1 13OO REV.1 SYST./ COMP. R. V. CLOSURE HEAD PROCEDURE TX-ISI-210 REV. 2 A,eb M

DATE 3-12-95 EXAMINER "lPo shalfr RELATED TO:

UT X PT MT v7 CENT.NO.

1, 2. e4 4 FROVIDE GENERAL NeFORMATIOed TO DESCNE APPROXmeATE SIZE, LOCATION A8e TYPE OF userTATION, UMITATIONS ARE DUE TO FLANGE. SHROUD AND LFTNG LUG. SEE WELD PROFILE 08 TAMED AT 1RF01 FOR EXAMedATIO WELD # 1 15% OF REQUIRED EXAMMATION VOLUME NOT EXAMMED.

99% EXAMMED WITH THE 45 DEGREE AND 00 DEGREF M AT LEAST ONE DIRECTION 45 DEGREE 8% NOT EXAMMED.

60 DEGREE 15% NOT EXAMesED.

WELD # 2 17% OF RFJulRED EXAMINATION VOLUME NOT EXAMesED.

97% ext.McNED WITH THE 45 DEGRfE AND 00 DE' GREE N AT LEAST ONE D4RECTION.

45 DEGREE 11% NOT EXAMeeED.

60 DEGREE 17% NOT EXAMedED.

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RELIEF REQUEST NO, B-6 REV. 2 PAGE 10 OF 11 THIRD INSPECTION PERIOD RESULTS

---"-r---

REPORT NO UT.88132

= = = = = = =

WESTINGHOUSE NUCLEAR SERVICES DIVISION f7 PAGE 3

OF 3

~

E LIMITATION TO EXAMINATION

=

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<g ! "

PLANT Comanche Peak UNIT 1

SKETCH TBX.1 1300 Rev.1 SYST/ COMP REACTOR COOLANT PROCEDURE TX4St-210. Rev. 4 FC N/A EXAMINER Wil56ams. Mark MM//

LEVEL 1 DATE 4/12/9s EXAMINER ' N/A LEVEL N/A DATE COMPONENT ID TBX.1 13001 P. ELATED TO O MT O PT

@ UT O vT PROVIDE SUFFICIENT INFORMATION To DESCRIBE SIZE, LOCATION AND TYPE OF LIMITATION.

COMMENTSISKETCH/ DETAILS Lmtates due to flange, shroud and 16fting lug. See 1RF01 profile for exam coverage.16% of r% astad volume not exarruned. 99%

czamaned witti the 48' and 60* in at least one derection. 8% not examsned with 48*.18% not exammed tuth 60*.

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l RELIEF REQUEST NO, B-6 REV. 2 PAGE 11 OF 11 THIRD INSPECTION PERIOD RESULTS

- = = = =

WESTINGHOUSE NUCLEAR SERVICES DIVISION

)

REPORT NO UT.es.132 7

PAGE 2

OF 3

l E

E LIMITATION TO EXAMINATION T

f;

~

PLANT Comanche Peak UNIT 1

SKETCH TBX 11300 Rev.1 SYST/ COMP REACTOR COOLANT PROCEDURE TXJSt.210 Rev. 4 FC N/A l

EXAMINER WHhams. Mark M ///

LEVEL M

DATE 4/12/ss l

EXAMINER N/A LEVEL N/A DATE I

COMPONENTID TMX.14300 2

f. ELATED TO O MT O PT e UT

,Q VT PROVIDE SUFFICIENT INFORMATION TO DESCRIBE SIZE LOCATION AND TYPE OF LIMITATION COMMENTS / SKETCH / DETAILS Limstatens due to Range. shroud and lifting lug. See 1RF01 pronie for exam covarage.17% of required volume not exarruned. 97%

caammed wsth the 46* and 60* in at least one detection.11% not examened with 44*.17% not esamened wsth 60*.

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CPSES UNIT 1 i

RELIEF REQUEST

~B-7 REVISION 2 A.

Item (s) for which reliefis requested:

TBX-1-3100-1-1, TBX-1-3100-2-1, TBX-1-3100-3-1, TBX-1-3100-4-1 Steam Generator Tubesheet-to-Channel Head Welds B.

Item Code Class:

1 C.

Examination requirement from which reliefis requested:

ASME Section XI 1986 Edition, no Addada The requirement for volumetric examination of 100% of each of the steam generator i

tubesheet-to-channel head welds as described in Table IWB-2500-1, Examination Category B-B, Item No. B2.40.

Note: The CPSES ISI Plan requires different steam generators to be examined during each inspection period. A relief request revision is processed to document the specific limitations encountered during the examination of each of the steam generators.

D.

Basis for relief:

4

\\

l Interference from the steam generator tube sheet flange configuration, welded insulation support pads and a welded component name tag preclude the complete ultrasonic examination of the volume required by Fig. IWB-2500-6.

Approximately 31% of the examination volume of weld TBX-1-3100-1-1 did not receive the l

full code required examination coverage.

l Approximately 37% of the examination volume of weld TBX-1-3100-2-1 did not receive the full code required examination coverage.

Approximately 31% of the examination volume of weld TBX-1-3100-3-1 did not receive the full code required examination coverage.

i Approximately 31% of the examination volume of weld TBX-1-3100-4-1 did not receive the full code required examination coverage.

See page 3 thru 14 for weld location and examination area configurations.

l l

Page 1 of 14

CPSES UNIT 1 RELIEF REQUEST B-7 REVISION 2 (cont.)

i E.

Substitute examinations:

None - however, manufacturers shop volumetric exam records are available in permanent plant files.

F.

Anticipated impact on the overall level of plant quality and safety:

None Page 2 of 14 l

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RELIEF REQUEST NO B-7 REV. 2 PAGE 4 OF 14 TBX-1-3100-1-1 RESULTS WESTINGHOUSE NUCLEAR SERVICE DIVISION INSPECTION SERVICES LIMITATION TO EXAM. NATION pegur Co M4NC H E' f5AK 1

-l-00 kv.A UNIT SKETCH SYST/ COMP chm CNCLAYOES W IM-MD bO 3 PROCEOURE N'

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PROVIDE GENERAL INFORMATION TO DESCRIBE APPROXIMATE SIZE, LOCATION AND TYPE OF LIMITATION.

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TBX-1-3100-1-1 RESULTS l

l WESTINGHOUSE NUCLEAR SERVICE DIVISION

)

INSPECTION SE RVICES l

LIMITATION TO EXAMINATION PLANT CO N\\ddCI4 9 PtE 5 K UNIT 1

SK' ETCH T EX I 3 Ioo Re v.1 PROCEDURE TV-IS l-1iO bv. 2 SYST/ COMP E A f" CNEIAkOLS h

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RELIEF REQUEST NO. B-7 REV. 2 PAGE 6 OF 14 TBX-1-3100-2-1 RESULTS iq l l n.

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RELIEF REQUEST NO, B-7 REV. 2 PAGE 8 OF 14 TBX-1-3100-2-1 RESULTS WESTINGHOUSE NUCt. EAR SERVICE DIVISION

\\

INSPECTION SERVICES LIMITATION TO EXAMINATION

~;.

PLANT COMANCHE PEAK UNIT NO.1 SKETCH TBX-13100 REV.1 SYST./ COMP. STEAM GENERATOR NO. 2 PROCEDURE TX-ISI-210 REV. 2 EXAMINER I 5

-D DATE 3-11-95

[/

V RELATED TO:

UT X PT MT VT CENT.NO.

2-1 PROVIDE GENERAL INFORMATION TO DESCR:E APPROXIMATE SIZE LOCATION AND TYPE OF UMf7ATION.

SSCE FLANOE 4

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to" acab x c a ca acca ai ic o x

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l 2.5" X 2.5* MSULATION 2SDE 6.5" X 3.5* t.0. TAG 28' PAOS 19* APART 300*

FROM O' REFERENCE AROUNO WELD O' REF. t$ CENTERLME OF COL & LEG MANWAY 4EA. 2' X 2' GENERATOR SUPPORTS 30.7% OF TOTAL VOLUME NOT INSPECTED l

82.5" APART 300*

38.7% NOT WSPECTED B*flO* SCAN

(

22.8% NOT WSPECTED BY45' SCAN 22.8% NOT WSPECTED SYO' SCAN hl 3-io-M d

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l RELIEF REQUEST NO, B-7 REV. 2 PAGE 11 OF 14 l

TBX-1-3100-3-1 RESULTS

.-_7-.._...

REPORT NO.

UT-98143 WESTINGHOUSE NUCLEAR SERVICES DIVISION

= = = = = = = =

7 PAGE 2

OF 2

l E

E LIMITATION TO MMINATION l

T T

.;t -

PLANT Comanche Peak UNIT

.1 SKETCH ~ TBX 14100 Rev.1 l

SYST/ COMP REACTOR COOLANT PROCEDURE TX.4SI-210 Rev.4 FC N/A EXAMINER Delbusso. James h

LEVEL IN DATE 4/14/98

/

l EXAMINER Magruder. Chris

_ LEVEL _N_

DATE 4/14/ss COMPONENT 10 TBX-141004-1 KELATED TO O MT O PT

@ UT O vT PROVIDE SUFFICIENT INFORMATION TO DESCRIBE SIZE. LOCATION AND TYPE OF LIMITATION.

COMMENTS / SKETCH / DETAILS Four 24"X 24" Support pads restricts all scan for 22%. Seventeen 2.5"X 2J" welded pads approx. 7" from CL luvuts 60* scan.

0* -22% not exarruned. 46* -22% not examined. 80* 41% not exammed. 31% of requwed exam volume not examened.

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l RELIEF REQUEST NO, B-7 REV. 2 PAGE 14 OF 14 l

TBX-1-3100-4-1 RESULTS r '- - -

REPORT NO UT48141 WESTINGHOUSE NUCLEAR SERVICES DIVISION y =m p

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LIMITATION TO EXAMINATION PLANT Comar.che Peak UNIT 1

SKETCH TBX.13100 Rev.1

. SYST/ COMP REACTOR COOLANT PROCEDURE TX.isl.210 Rev. 4 FC N/A EXAMINER Delbusso. James LEVEL In DATE 4/13/98 EXAMINER Magruder. Chris LEVEL 11 DATE 4/13/9e i

COMPONENT ID TBX.1410041 l

l fiELATED TO O MT O PT

@ UT O VT PROVIDE SUFFICIENT INFORMATION TO DESCRIBE SIZE. LOCATION AND TYPE OF LIMITATION.

COMMENTSFSKETCH/ DETAILS Fout 24"X 24" Support pads tostricta all scan for 22%. Seventeen 2.5"X 2.5" welded pads approx. 7" from CL lmts 80* scan.

0'.22% not exarmned. 48'.22% not examened. 80* 41% not examsned. 31% of required exam volume not exarmned.

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CPSES UNIT 1 RELIEF REQUEST B-12

' A.

Item for which reliefis requested:

TBX-1-2100-1 Pressurizer Lower Head to Shell Weld B.

Item Code Class:

1 C.

Examination requirement from which reliefis requested:

The requirement for volumetric exammation of 100% of the weld length as described in Table IWB-2500-1, Examination Category B-B, Item No. B2.11.

D.

Basis for relief:

The specific examination area geometry of the lower head to shell weld and interferences from instrumentation lines, welded pads and the support skirt preclude the complete ultrasonic examination of the volume required by Fig. IWB-2500-1 for weld TBX-1-2100-1.

Approximately 16% of the volume did not receive the full code required coverage. Best effort examinations were performed. Full circumferential scan coverage was obtained. Axial scan coverage was achieved for approximately 97% of the required volume in at least one beam path direction with one angle.-

There were no recordable indications identified by the best effort examinations performed.

l See pages 2 through 4 for weld location and examination area configuration.

E.

Substitute examinations:

1 None F.

Anticipated impact on the overall level of plant quality and safety:

None i

1 1

Page 1 of 4 l

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RELIEF REQUEST Nd. B k2 PAGE 2 OF 4

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l REPORT No.

UT.esass

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WESTINGHOUSE NUCLEAR SERVICES DIVISION p

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SKETCH TEX.12100 Rev. 2

SYST/ COMP REACTOR COOLANT PROCEDURE TX4SS-210 Rev. 4 FC N/A EXAMINER De4busso. James hdLww [,

1//_ ;;>, LEVEL 101 DATE 3/30/0e EXAMINER N/A LEVEL N/A DATE COMPONENTID TEX.121001 RELATED TO O MT O PT

@ ur o vT PROVIDE SUFFICIENT INFORMATION TO DESCRIBE SIZE, LOCATION AND TYPE OF LIMITATION.

COMMENTS / SKETCH /DETAfLS Support restncts 2 scan for 80*.

5 1* 6nstrumentation hnes 2.8* from weed toe,5 side.

C. 2.5* X 2.5" welded pads 2.78* from weed toe,5 s&oe.

97% exammed with 44*, 85% enammed with 80* 15% pot examined.

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CPSES UNIT 1 RELIEF REQUEST B-13 A.

Item (s) for which reliefis requested:

TBX-1-4102-7, TBX-1-4301-7, TBX-1-4402-7 Circumferential Piping Welds B.

Item (s) Code Class:

i 1

C.

Examination requirement from which reliefis requested:

The requirement for volumetric and surface examination of 100% of the weld length as described in Table IWB-2500-1, Examination Category B-J, Item No. B9.11.

D.

Basis for relief:

The specific pipe to valve examination geometries and interferences from reactor building structural steel members preclude the complete ultrasonic and liquid penetrant examinations of the volume and the surface area required by Fig. IWB-2500-8.

For weld TBX-1-4102-7, approximately 61% of the volume and 31% of the surface area did not receive the full code required examination coverage. See pages 3 through 6 for weld location and examination area configuration for weld TBX-1-4102-7.

For weld TBX-1-4301-7, approximately 55% of the volume did not receive the full code required examination coverage. See pages 7 through 9 for weld location and examination ares configuration for weld TBX-1-4301-7.

For weld TBX-1-4402-7, approximately 59% of the volume and 40% of the surface area did not receive the full code required examination coverage. See pages 10 through 13 for weld location and examination area configuration for weld TBX-1-4402-7.

Best effort examinations were performed for the accessible areas of the weld. There were no recordable indications identified by the best effort volumetric or surface examinations l

performed.

l 2

L Page 1 of 13 I

i CPSES UNIT 1 RELIEF REQUEST B-13 (cont.)

E.

Alternate examinations:

None - however, welds at this same location in loops 1, 3 and 4 are included in the ISI Plan and are scheduled for examination during this interval.

F.

Anticipated impact on the overall level of plant quality and safety:

None i

2 j

Page 2 of 13 1

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M REPORT NO.

UT.48470

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WESTINGHOUSE NUCLEAR SERVICES DIVISION p

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6 LIMITATION TO EXAMINATION PLANT Com, A Peak UNIT 1

SKETCH TBX 14102 Rev.1 SYST/ COMP REACTOR COOLANT PROCEDURE TX ISI-214 Rev. 2 FC NIA EXAMINER Holasek. Wade LEVEL la DATE 4/1/98 EXAMINER N/A LEVEL _N lI DATE COMPONENT 10 TBX.14102-7 RELATED TO O MT O PT

@ UT C VT PROVIDE SUFFICIENT INFORMATION TO DESCRIBE SIZE. LOCATION AND TYPE OF LIMITATION.

COMMENTS / SKETCH / DETAILS L distances of scanned pope measured in the CW diriction from datum O. 2.0* to 8.5*,22.8* to 28J* and 28.O* to 33.5". #7/8 scan also lameted in these areas. 39% of total area was saamened. (61% not osamened.)

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PT.sa.e40 gg WESTINGHOUSE NUCLEAR SERVICES DMSION m

a LIMITATION TO EXAMINATION s

PLANT C-

-.Ce Peak.

UNIT 1

SKETCH TEX.141e2 Rev.1 1

SYST/ COMP REACTOR COOLANT PROCEDURE TX.ast 11 Rev. 8 FC WA EXAMINER Holasek. Wade LgVEL 11 DATE 3/31ses EXAMINER N/A LEVEL MA DATE COMPONENT ID TsX-14102J i

CELATED TO O MT

@ PT o ur O vr PROVIDE SUFFICIENT INFORMATION TO DESCRIBE SIZE LOCATION AND TYPE OF LIMITATION.

4 COMMENTS / SKETCH / DETAILS 31% not exammed. Lavutations from 7" to 12* and 18" to 21*.

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SKETCH TEX 14142 Rev.1

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REPORT NO.

UT.a. 144 g,=

WESTINGHOUSE NUCLEAR SERVICES DMSION m

a UMITATION TO EXAMINATION PLANT UNIT 1

SKsTCH Tsx.14301 Rev.1 1

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t COMMENTS / SKETCH / DETAILS I

No esamanation performed from 4* to 1J". $J" to 14J* 14J" to 20A*.23J" to 28* 31J* to 34J". All measuremords taken CW from datum e. Total carc measurement is 34A". SS % not osanoned.

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RELIkF REQUEST NO..B-13 PAGk 9 OF 13 WESTINGHOUSE NUCLEAR SERVICES DMSION REPORT NO.

UT.es.104 l

INSPECTION SERVICES PAGE 2

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i 73 PROFILE OF THE EXAMINATION VOLUME PLANT Came ude Peak UNIT 1

SKETCH TBX.1.4301 Rev.1 SYST/ COMP P2! ACTOR COOLANT PROCEDURE TX.488.214 Rev.2 FC NIA EXAMINER Slechs. Paul d>> f I8/1/d LEVEL E

DATE als/se EXAMINER Moreau. Ansere LEVEL E

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UMITATION TO EXAMINATION PLANT Com tmas Peak UNIT.

1 SKETCH TBX.14402 Rev. 2 SYST/ COMP REACTOR COOLANT PROCEDURE TX IS&414 5 av. 2 FC NIA EXAMINER Honesak. Wade d

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REPORT NO.

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SKETCH TEX.14482 Rev. 2 l

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UT.es.tes INSPECTION SERVICES PAGE 2

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PROFILE OF THE EXAMINATION VOLUME l

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UNIT 1

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CPSES UNIT 1 RELIEF REQUEST B-14 A.

Item (s) for which reliefis requested:

TBX-1-4404-1 Branch Pipe Connection Weld B.

Item (s) Code Class:

1 C.

Examination requirement from which reliefis requested:

The requirement for volumetric examination of 100% of the weld length as described in Table IWB-2500-1, Examination Category B-J, Item No. B9.31.

D.

Basis for relief:

The specific examination area geometry of this pipe to branch connection weld precludes the complete ultrasonic examination of the volume required by Fig. IWB-2500-10.

Approximately 26% of the examination volume did not receive the full code required coverage.

A best effort examination was performed. Full circumferential scan coverage was obtained.

Axial scan coverage was achieved in one beam path direction with at least one beam angle for 100% of the examination volume. See pages 2 and 3 for weld location and examination area configuration.

There were no recordable indications identified by the best effort volumetric examination or by the required surface examination performed.

E.

Alternate examinations:

None F.

Anticipated impact on the overall level of plant quality and safety:

None L

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6 LIMITATION TO EXAMINATION j

PLANT C M Peak UNIT 1

SKETCH TBX.14404 Rev.1 SYST/ COMP REACTOR COOLANT PROCEDURE TX.tSt 214 Rev. 2 FC N/A EXAMINER Wilelams. Mart d4 J

LEVEL 5

DATE 4/870s EXAMINER - NIA LEVEL NfA CATE i

l COMPONENT ID TBX.161 RELATED TO O MT O PT

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PROVIDE SUFFICIENT INFORMATION TO DESCRIBE SIZE. LOCATION AND TYPE OF LIMITATION.

COMMENTS / SKETCH / DETAILS iss% of the requwed volume is covered in at least 1 beam path direction. 74% of the requwed volume is covered in 2 beam path derectums.

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RELIEF REQUEST i

C-9 A.

Item (s) for which relief is requested:

TBX-2-1110-1 Excess Letdown Heat Exchanger Head to Flange Weld TBX-2-1180-2-2 Containment Spray Heat Exchanger Shell to Flange Weld B.

Item (s) Code Class:

l 2

C.

Examination requirement from which reliefis requested:

The requirement for volumetric examination of 100% of the weld length as described in Table IWC-2500-1, Examination Category C-A, Item No.'s C1.20 and C1.10.

D.

Basis for relief:

For weld TBX-2-1110-1, interferences from the heat exchanger inlet, outlet and instrumentation nozzles and from the flange taper preclude the complete ultrasonic examination of the volume required by Fig. IWC-2500-1. Approximately 50% of the weld length did not receive the full code required examination coverage. See pages 2 through 4 for weld location and examination area configuration for weld TBX-2-1110-1.

For weld TBX-2-1180-2-2, interferences from the heat exchanger welded support pads preclude the complete ultrasonic examination of the volume required by Fig. IWC-2500-1.

Approximately 27% of the weld length did not receive the full code required examination coverage. See pages 5 through 7 for weld location and examination area configuration for weld TBX-2-1180-2-2.

There were no recordable indications identified by the best effort volumetric examination performed on the accessible portions of the weld lengths.

E.

Alternate examinations:

None

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F.

Anticipated impact on the overall level of plant quality and safety:

(

None Page 1 of 7

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RELIEF REQUESi NO. C-9 PAGE 3 OF 7 REPORT NO (IT 98 129

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WESTINGHOUSE NUCLEAR SERVICES DIVISION p

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LIMITATION TO EXAMINATION PLANT M Peak UNIT 1

SKETCH TBX.21110 Rev.1 SYSTICOMP CHEMICAL & VOLUME CONTROL PROCEDURE Tx.tsl.214 Rev.2 FC N/A EXAMINER MonnL Geom LEVEL 5

DATE 4/10/98 EXAMINER N/A LEVEL NIA DATE COMPONENT ID TEX-21110-1 RELATED TO O ur O PT

@ UT O vr PROVIDE SUFFICIENT INFORMATION TO DESCRIBE SIZE. LOCATION AND TYPE OF UMITATION.

COMMENTS / SKETCH / DETAILS Four noules located as shown below. Two 3* noules and two 4* parvta= on side 2. 80% not exammed.

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RELIEF REQUEST NO. C-9 PAGE 4 OF 7 (M

. WESTINGHOUSE NUCLEAR SERVICES DIVISION '

REPORT NO.

UT.88129 lNSPECTION SERVICES prog o,

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PROFILE OF THE EXAMINATION VOLUME

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PLANT Comanche Peak UNIT 1

SKETCH TBX.21110 Rev.1 SYST/ COMP CHEMICAL & VOLUME CONTROL PROCEDURE TXJSt.214 Rev. 2 FC N/A EXAMINER Monni. George

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UT.es.e23 WESTINGHOUSE NUCLEAR SERVICES DMSION

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PAGE 3

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27% of weld vohame not osammed.

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WESTINGHOUGE NUCLEAR SERVICES DIVISION REPORT NO.

Lif.es423 INSPECTION SERVICES PAos 2

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PROFILE OF THE EXAMINATION VOLUME

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PLANT Comanche Peak UNIT 1

SKETCH TEX-21130 Rev.1 SYST/ COMP CONTAINMENT SPRAY PROCEDURE TX tsl.2.14 Rev. 2 FC N, A EXAMINER Wilhems. Mark M M //

LEVEL M

DATE 3/20tes EXAMINER, WA LEVEL WA DATE COMPONENTID TEX 211804 2 COMMENTS / SKETCH / DETAILS

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1 ISI l RS-01 Section 4, pgs.10,35,36,39,51,55, Change Calibration blocks. Add, delete 74,75,94,98,109,109.1,i15,156, and reschedule examination items. Add 167,168,186,187,198,205,208,214, relief requests.

220,233,234,235,240,247 and 250.

Appendix A,index and Relief Requests B-6 Rev. 2, B 7 Rev 2, B 12, B-13, B 14 and C-9. Appendix B page 4.

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Appendix B Page 4

. _ _ ~

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ACTIVITY SCREEN Page 1 of 2 L

Activity (include the number and revision of the document (s) being screened and a brief description)

Unit 1 Inservice inspection (ISI) Plan revision 5 Interim Change Request No. ICR ISI-lRS-01.

Update Plan per iRF06 outage implementation.

11.

Screening Questions (Recommend using the 10CFR50.59 REVIEW GUInE)

YES NO 1.

Will implementation of the proposed activity result in a test or experiment X

not described in the Licensing Basis Documents?

i 2.

Will implementation of the proposed activity change the facility as X

described in the Licensing Basis Documents?

i 3.

Will implementation of the proposed activity change the procedures as X

described in the Licensing Basis Documents?

4.

Will implementation of the proposed activity involve a change to the X

Technical Specifications?

5.

Will Implementation of the proposed activity involve a change to the X

l following LBDs: QA, Security, or Emergency Plan / Program? '

III.

If question 1,2 or 3 is answered YES, SE#

or CMCE #

and/orif question 4 answered YES, then process a Technical Specification Change per STA-120; and/or if question 5 is answered YES, then a 50.54 assesment is required as discussed below. NOTE
Evaluation / assessment criteria listed on reverse side.

50.54(a)QA Program (NOTE: SE also required)

YES _,,,,(STA-116)

NO f 50.54(p) Security Plans YES _(STA-119)

NO A 50.54(q) Emergency Plan YES __,(STA-119)

NO 2 l

IV.

List the documents (Licensing Basis / technical / commitments /other) reviewed, including section or page numbers where relevant information was found. NOTE: Licensing Basis Documents and search methods are listed on the reverse side.

Tech Spec 4.0.5 FSAR Sect. 5.4 & 6.6 ISI CDF's Continued V.

If the conclusion of the screen is that a Safety Evaluation is not required, then provide an overall justification for that determination. The 10CFR50.59 Review Guide should be consulted for the justification.

l

_ See attached continuation sheet.

I l

VI.

Review and Approval Continued Q l

be<

Date: Jul/17/1998 Preparer: J.DeBonis (Print and Sign) -

720.p7 SA Reviewer:

g y

Date:

Rev.15

I i

Page 2 of 2 ACTIVITY SCREEN I. Activity j

ICR ISI-lR5-01 i

V. Conclusion

}

Implementation of 1RF06 ISI activities has identified several examination items that required correction, that have had calibration block changes, that have been rescheduled or that require relief requests. The relief requests require separate NRC approval and are l

not considered implemented until that approval is obtained. The other changes made by ICR ISI-lRS-01 maintain ISI Plan compliance with the ASME Code requirements for sample percentages, schedules and examination methods. With the exception of the ISI Plan itself, the other LBD's do not contain the level of detail addressed by this ICR. No unreviewed safety questions have been created. A safety evaluation is not required.

.,