ML20195G182

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Requests NRC Review & Approval of ASME Code Relief for ISI Program.Encl 1 Provides Relief Request 1-ISI-14 That Includes Two Attachments.Encl 2 Provides Copy of Related ASME Code Page
ML20195G182
Person / Time
Site: Sequoyah Tennessee Valley Authority icon.png
Issue date: 06/08/1999
From: Salas P
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9906150263
Download: ML20195G182 (32)


Text

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.r Tennessee valley Autnonly. Post Oftce Box 2000, Soddy-Daisy. Tennessee 37379 June 8, 1999 j

10 CFR 50.50a (g) (5) (iii) j i

U.

S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C.

20555 Gentleman:

In the Matter of

)

Docket No. 50-327 Tennessee Valley Authority

)

SEQUOYAH NUCLEAR PLANT (SQN)

AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI INSERVICE INSPECTION (ISI) RELIEF REQUEST FOR UNIT 1 CONTAINMENT SPRAY HEAT EXCHANGER NOZZLE-TO-SHELL WELDS The purpose of this letter is to request NRC review and approval of a new ASME code relief request for SON's ISI Program.

The proposed relief request (1-ISI-14) is based on I

limitations that preclude full code examination of two ASME Class 2 welds (CSHXW-6-B and CSHXW-7-B).

These welds are nozzle-to-shell welds and are located on the Unit 1 containment spray heat exchanger 18.

The design Tp )

configuration of the nozzle-to-shell welds preclude a

/

1 100 percent preservice ultrasonic examination of the required volume.

The proposed relief request is submitted in accordance with 10 CFR 50. 55a (g) (5) (iii).

TVA requests that NRC provide approval in accordance with 10 CFR 50.55a (g) (6) (i).

NRC response is requested for the subject relief request by May 31, 2000.

This date will support TVA's schedule for planning inservice inspections. provides Relief Request 1-ISI-14 that includes l

two Attachments (Attachment 1, Examination Data Reports; and, TVA procedure for calculation of the ASME code l

coverage). provides a copy of the related ASME l

code page.

9906150263 990600 37 PDR ADOCK 05000327 P

PDR ja

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1 U.S.' Nuclear Regulatory Commission

.LPage 2-June 8, 1999.

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If you.have any' questions regarding1this response, please contact me at. extension' (423) 843-7071 or J. D.' Smith at-extension (423) 843-6672.

Sincerely

~_J o Salas.

Licensing and Industry Affairs Manager Enclosures.

Lcc (Enclosures):

j

-Mr.

R. W.

Hernan, Project Manager Nuclear Regulatory Commission One-White. Flint,. North.

i

-11555-Rockville Pike-

'Rockville, Maryland 20852-2739-NRC-Resident Inspector.

Sequoyah Nuclear ~ Plant 2600 Igou Ferry' Road Soddy-Daisy, Tennessee 37384-3624 Regional Administrator

.U.S.

Nuclear. Regulatory Commission RegionLII Atlanta Federal Center 61-Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-3415-l i

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cr ENCLOSURE 1 TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT (SQN)

UNIT 1 REQUEST FOR RELIEF FOR REQUEST 1-ISI-14 EXECUTIVE

SUMMARY

This request for relief addresses the containment spray heat exchanger nozzle-to-shell welds CSHXW-6-B (outlet nozzle) and CSHXW-7-B (inlet nozzle).

The containment spray heat exchanger 1B was replaced during the Unit 1 Cycle 9 refueling outage of the first period of the second 10-year inspection interval.

The design configuration of the nozzle-to-shell weld precludes a 100 percent preservice ultrasonic examination of the required volume for the nozzle-to-shell weld.

The nozzles are fabricated from a pipe segment using a 12-inch pipe size schedule 40 (0.375 inch thick) with a " set-on" type configuration to the vessel.

These physical examination limitations occur when the set-on type nozzle of this thickness is welded to a vessel shell only 1.0 inch thick with a full penetration fillet reinforced weld.

A 100 percent preservice surface examination was performed on each weld.

A preservice ultrasonic examination was performed on the accessible areas to the maximum extent practical, given the physical limitations of the subject weld, due to the set-on type nozzle with fillet reinforcement.

The design configuration limits ultrasonic examination to approximately 64 percent of weld CSHXW-6-B and 64 percent of weld CSHXW-7-B.

Performance of an ultrasonic examination of essentially 100 percent (i.e.,

lower 1/3 volume) of full penetration fillet reinforced welds in the nozzle-to-shell welds, CSHXW-6-B and CSHXW-7-B, would be impractical.

A surface examination and the maximum extent practical ultrasonic examination of the subject #alds provides an acceptable level of quality and safety because the data obtained from the weld surface and weld volume examined provides sufficient information to judge the overall integrity of the welds.

Therefore, pursuant to 10 CFR 50.55a (g) (5) (iii), it is requested that relief be granted for the second inspection interval.

t UNIT:

1 SYSTEM:

Containment Spray - System 72 COMPONENTS:

Containment Spray Heat Exchanger 1B Nozzle-to-Shell Welds (2)

ASME CODE CLASS:

ASME Code Class 2 (Equivalent)

SECTION XI EDITION:

1989 Edition CODE TABLE:

IWB-2500-1 EXAMINATION CATEGORY:

C-B, Pressure Retaining Nozzle Welds in Vessels EXAMINATION ITEM NUMBZ".R: 'C2.21, Nozzle-to-Shell (or Head)

Weld CODE REQUIREMENT:

ASME Section XI, Table IWC-2500-1, Examination Category C-B, Item Number C2.21, Requires Surface and Volumetric Examinations CODE REQUIREMENT FROM WHICH RELIEF IS REQUESTED:

Volumetric Examination Coverage Of-Essentially 100 Percent Of Nozzle-to-Shell Welds LIST OF ITEMS ASSOCIATED WITH THE RELIEF REQUEST: CSHXW-6-B, Nozzle-to-Shell Weld CSHXW-7-B, Nozzle-to-Shell Weld BASIS FOR RELIEF:

The design configuration of the cont.inment spray heat exchanger nozzle precludes an ultrasonic examination of the required volume for the following nozzle-to-shell welds:

CSHXW-6-B and CSHXW-7-B.

The design configuration limits ultrasonic examination to approximately 64 percent of the required examination volume on each weld.

I ALTERNATIVE EXAMINATION:

-In lieu of the code requiring 100 percent ultrasonic examination, an ultrasonic examination was performed on accessible areas of each weld to the maximum extent 1

1 1

]

I, l practical,~given the physical limitations of the set-on type nozzle,to-shell weld.

The code ~ required' surface examination.(PT) of 100 percentof' each' weld'was also performed.

Refer to Attachment 1 for the examinationidata reports.

1 Justification For The Granting Of Relief:

In.accordance with NRC Information Notice 98-42, " Implementation Of 10. CFR 50.55a.(g) Inservice Inspection' Requirements," the expected examination coverage'of an ASME Section XI required

- examination is at least greater than 90-percent of the ASME Section XI specified volume or area.

NRC states in-the Information Notice!. "The NRC has adopted and further refined the definition of ' essentially 100 percent' to mean ' greater than 90

-percent' in 10 CFR 50.55a (g) (6) (ii) (A)'(2) for required examination coverage of reactor pressure vessel welds.

This standard has been applied to all examinations of welds or other areas required.by ASME Section XI."

The1 design configuration of the subject set-on type nozzle-to-shell welds precludes ultrasonic examination of essentially-100 percent of the required lower 1/3 examination volume.

The weld joint. configuration' consists oof:a set-on type nozzle (12-inch schedule 40 pipe) with a wall thickness of-0.375 inch welded to'the vessel shell with-wall thickness of 1.0 inch.

Each nozzle-to-shell weld is a.

full penetration fillet reinforced weld.

The nozzles and vessel snell are fabricated from austenitic stainless steel

materials.

The-ultrasonic volumetric examination is limited due to

' design configuration of-a set-on type nozzle, which-is welded to the shell with full penetration fillet reinforced weld.

Scanning from the vessel side of the weld is not practical due to the asymmetrical inside surface of the vessel. wall relative to thelnozzle.

Scans for flaws located transverse to the weld were limited due to the weld joint configuration which limited search unitfcontact and movement.

Approximately 50 percent of the required coverage was achieved for detection of transverse oriented flaws.

The axial scans were limited due to the fillet weld size which was equal to the nozzle wall

' thickness.

Each weld received 78 percent of the required coverage for detection of parallel oriented flaws with the axial scans from the nozzle side utilizing both 45-degrees shear. waves and 60-degrees refracted longitudinal waves.

l uThese examinations and coverage obtained. provide' reasonable l

assurance.that flaws:would be detected. : Total ultrasonic examination.' overage was approximately 64 percent for-c CSHXW-6-B'and;64 percent for CSHXW-7-B of the required code weld? volume for each weld.

]

' Performance of.an ultrasonic. volumetric examination of-essentially 10(Epercent'of'the required volume of the~ full s

penetration. fillet reinforced welds'CSHXW-6-B and CSHXW-7B

.would.be impractical.

The surface examination on 100 percent of the. weld and; adjacent' metal, the maximum extent'

practical ultrasonic examination of:the subject welds, provides reasonable assurance of an acceptable levellof quality and safety.--Significant degradation,.if present,.

would have been' detected during:the surface examination and ultrasonic examination that was-performed on.the subject welds.

As a result, assurance of structural integrity for these welds is provided by the alternative examinations that were performed.

LTherefore, pursuant to 10CFR50.55a (g) (5) (iii), it is

requested that relief be granted for the preservice examination that was performed during the Unit 1 Cycle 9 refueling out' age of.the first period of the second 10-year
inspection interval and the inservice examination to be performed during the second 10-year. inspection interval.

IMPLEMENTATION SCHEDULE:~

ThisJrequest for; relief is applicable to the second 10-year inspection interval for SON Unit 1.

Welds CSHXW-6-B and CSHXW-7-B:were examined for preservice following containment

spray.heatiexchanger replacement during the Unit 1. Cycle 9 refueling. outage (end of the first period of.the second 10-year inspection: interval).

Welds CSHXW-6-B and CSHXW-7-B are scheduled for-inservice examination ~in the third period of'the second 10-year inspection interval.

REFERENCES:

Examination Data Reports: R-7185, R-7186, R-7335, and R-7336. 2: Nondestructive Examination Procedure N-GP-28 "Calculationfof ASME Code Coverage'for l

Section XI NDE Examinations," Revision 1 I

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ATTACHMENT 1 EXAMINATION DATA REPORTS i

R-7185 R-7186 R-7335 R-7336

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/D TENNESSEE VALLEY

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RECORD OF LIQUID REPORT NO.

AUTHORITY PENETRANT EXAM R-7/ 95 PROJECT: SQN UNIT: 1 / c-7 EXAMINATION DATE:

09/01/98

/

START TIME:

13:35 END TIME: 14:35

~ ~ '.... SYSTEMj CSSn0 4

WELD / COMPONANT 1.D.:

CSHXW-6-B EXAM SURFACE:

ID 0 OD CONFIG.: - NOZZLE TO VESSEL ORIGINAL EXAM RE-EXAM O PROCEDURE: N-PT-9 REV 16 TC 98-04 REF. DRAWING NO.: ISI-0462-C-02 EXAMINATION CODE: ASME SECTION XI ACCEPTANCE CRITERIA CODE CLASS:1 CATEGORY:.C - 0 N-PT-9 APPDX. A O APPDX. B @

OTHER:

METHOD OF EXAMINATION METIlOD PENETRANT MATERIALS 0 WATER WASHABLE FLUORE,6C,ENT DYE BRAND NAME:

MAGNAFLUX

, - y,, -.

O POST-EMULS1FIABLE FLUORESCENT DYE PENETRANT SV1-SP BATCH 93A02K O SOLVENT-REMOVABLE FLUORSECENT DYE REMOVER SKC-S BATCH 97H12K O WATER-WASHABLE VISIBLE DYE DEVELOPER SKD-S2 BATCH 97J05K O POST-EMULSIFIABLE VISABLE DYE BLACK LIGHT METER S/N: N/A

@ SOLVENT REMOVABLE VISIBLE DYE CAL. DUE DATE:

N/A i

PART TEMP.: 77 'F PYROhETER S/N: 522355 CAL. DUE DATE. Gi6/99 EXAMINATION RES11LTS: SATISFACTORY @

UNSATISFACTORY O NOI NO.: N/_A EXPLANATION OF EXAM RESULTS:

N/A COMMENTS / LIMIT 4TIONS:

CS HEAT EXCHANGER 8 t/74W A4 y,2L 6~

79fGSEA v7c5 EXAQ EXAMINER:

b tir W LEVEL EXAMINER:

LEVEL 94648 REVIEWER:

MD LEVEL [DATE: 9[5 PT PAGE:

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N TE.NNESSEE VALLEY RECORD OF LIQUID REPORT NO.

AUTHORITY -

PENETRANT EXAM R

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PROJECT: SON UNIT: 1 EXAMINATION DATE:

09/01/98 SYSTEM: CSSno START TIME 12:30 END TIME: 13:30 WELD / COMPONANT I.D;: CSHXW-7-B EXAM SURFACE:

ID D

~OD L

CONFIG.: VESSEL TO NOZZLE ORIGINAL EXAM RE-EXAM O

l' PROCEDURE: N-PT-9 REV 16 TC 98-04 REF, DRAWING NO.: ISI-0462-C-02 l

EXAMINATION CODE: ASME SECTION XI ACCEPTANCE CRITERIA' CODE CLASS:2 CATEGORY: AB N-PT-9 APPDX. A O APPDX. B @

OTHER-METHOD OF EXAMINATION METHOD PENETRANT MATERIALS s

O WATERWASHABLEFLUORESCENTDYE BRAND. _ _. _AME:

MAGNAFLUX.

0 POST-EMULSIFIABLE FLUORESCENT DYE PENETRANT SKL-SP BATCH 93A02K O SOLVENT-REMOVABLE FLUORSECENT DYE REMOVER SKC-S BATCH 97H12K O WATER WASHABLE VISIBLE DYE DEVELOPER SKD-S2 BATCH 97J05K O POST EMULSIFIABLE VISABLE DYE BLACK LIGHT

-.enl METER S/N: N/A

@ SOLVENT REMOVABLE VISIBLE DYE CAL. DUE DATE:

N/A PART TEMP.: 77 'F PYROMETER S/N: 522355 CAL. DUE DATE: 8/6/99 EXAMINATION RESULTS: SATISFACTORY @

UNSATISFACTORY 0. NOI NO.: N/A EXPLANATION OF EXAM RESULTS:

N/A COMMENTS / LIMITATIONS:

CS HEAT EXCHANGER

/>/L 6Ts&'/c 6 6X// M DL ET~

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LEVEL EXAMINER:

EXAMINER:

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REVIEWER:

LEVEL DATE:

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EXAMINATION

SUMMARY

TENNESSEE VALLEY AND REPORT NUMBER:

AUTHORITY RESOLUTION SHEET 4 733.F' PROJECT: SQN UNIT: 1 CYCLE: 9 COMPONENT ID: CSHXW-7-B EXAMINATION METHOD SYSTEM: CS t

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PT O UT B VT O CONFIGURATION:

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TO SHELL PROCEDURE: N-UT-18 REV:22 TC:97-23 NOZZ1:E -

EXAMINER: Srt.a: su/. s EXAMINER: cAery4 4f*p EXAMINER:

EXAMINER:

g LEVEL:.1Z'-

LEVEL:

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LEVEL:

LEVEL:

EUWFs#WWMM@EsJ% dime &nraR$dMMMs@M #3NNdN%$$d#bedish i@

  • MWi$tmeMdRes?nd3 THIS REPORT CONTAINS THE DATA ASSOCIATED WITH THE ULTRASONIC EXAMINATION OF WELD CSHXW-7-B, A STAIN-LESS STEEL NOZZLE TO SHELL CONFIGURATION. THIS EXAMINATION WAS PERFomfED IN ACCORDANCE WITH

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ASME SECTION XI CODE REQUIREMENTS. PRE-SERVICE

EXAM, THE WELD WAS EXAMINED WITH A 45 DEGREE SHEAR WAVE 1 V PATH TECHNIQUE FROM NOZZLE SIDE OF THE WELD.

A 60 DEGREE SHEAR WAVE % V PATH TECHNIQUE FROM THE NOZZLE SIDE OF THE WELD.

.ql A SUPPLEMENTAL EXAMINATION WAS PERFORMED WITH V

A 70 DERGEE RL FROM THE NOZZLE SIDE OF THE WELD.

ID GEOMETRY WAS RECORDED WITH THE 60 NO RECORDABLE INDICATIONS WERE OBSERVED WITH THE 45 OR 70RL.

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DUE TO NOZZLE TO SHELL CONFIGURATIONp4. BI-DIRECTIONAL COVERAGE WAS OBTAINED.

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VERIFY INSTRUMENT SETTINGS AND CALIBRATION SEQUENCE ARE LN ACCORDANCE WITIl TABLE 2 OF TIIE APPLICABLE PDI QUALIFICATION IMPLEMENTATION PROCEDURE !

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PROCEDURE: N-UT-18 REV:22 TC:97-23 CALIBRATION BLOCK NO. BNP-17 TEMP: 73 l

INSTRUMENT: KB DUE DATE: 06-17-98 SIMULATOR BLOCK NO: 6026-83 MODEL/ TYPE: USNN51 S/N: E23946 THERMOMTER S/N: 575363 DUE DATE: 11 21-98 ff,,,,.,,

TRANSDUCER MANUF: KB COUPLANT ULTRAGEL BATCH: 94125 S/N 24490

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FREQ:

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  • PDI QUALIFIED INSTRUMENT SETTINGS:

VERIFY INSTRUMENT SETTINGS AND CALIBRATION SEQUENCE ARE IN ACCORDANCE WITH TABLE 2 OF THE APPLICABLE PDI QUALIFICATION LNLPLEMENTATION PROCEDURE !

LINEARITY CHECK VERTICAL SIGNAL 2 l50 45 40 35 l 30 25l20 15l10 GAIN l SET l

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REPORT NUMBER:

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DATA SHEET PROJECT SONP UNIT / CYCLE 1/C9 CALIBRATION DATE: 10-02-98 PROCEDURE:.N-UT-18 REV:22 TC:97-23 CALIBRATION BLOCK NO.* BN'/-17 TEMP: 73 il INSTRUMENT: KB DUE DATE:J14.17-98 SIMULATOR BLOCK NO: 6026-83 MODEL/IYPE: USN)d.f h.,,y S/N: E23946 THERMOMTER S/N: 575363 DUE DATE: _11 21-98 TRANSDUCER MANUF:SB'RTD COUPLANT ULTRAGEL BATCH: 94125 S/N 95-854 SIZE:.2(7x d FREQ:

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  • PDI QUALIFIED INSTRUMENT SETTINGS:

VERIFY INSTRUMENT SETTINGS AND CALIBRATION SEQUENCE ARE IN ACCORDANCE WITH TABLE 2 OF THE APPLICABLE PDI QUALIFICATION IMPLEMENTATION PROCEDURE !

LINEARITY CHECK VERTICAL SIGNAL 2 50 45 40 35 l 30 25l20 15l10 m,

GAIN l SET

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+12 l

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32 TO 48 16 TO 24 l 20 %

64 TO 96 40 %

64 TO 96 40 20 80 80 L COMMENTS l:

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PIPING EXAMINATION REPORT NUMBER:

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PROJECT: SQN UNIT: 1 CYCLE: 9 EXAMINATION DATE: 10-02-98

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REFERENCE:

CENTERLINE OF WELD-CIRC. SCAN SENSITIVITY 55 dB 59 dB Lo

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NO.

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s AUTHORITY DATA SHEET 233S

PR.OJECT: SQN UNIT: 1 CYCLE: 9 EXAMINATION DATE: 10-02-98

<N PROCEDURE: N UT 18 REV:22 TC:97 23 START TIME: 1400 END TIME: 1443 SYSTEM: CS EXAM SURFACE O ID

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REFERENCE:

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SUMMARY

w TENNESSEE VALLEY AND REPORT NUMBER [: g.7 g AUTHORITY RESOLUTION SHEET PROJECT: SQN UNIT: 1 CYCLE: 9 COMPONENT ID: CSHXW-6-B EXAMINATION METHOD SYSTEM: CS MT O l PT C 1.TT @ VT O CONFIGURATION: PROCEDURE: N-UT-18 REV:22 TC:97-23 SHELL TO NOZZLE EXAMINER: EXAMINER: EXAMINER: EXAMINER .S7f/C wi/dans 6'W~L W'M y LEVEL: M LEVEL: -T '. LEVEL: LEVEL: f d@dEldGWuFA$ $ $G% WOW 4sMstM3MM2d&#n#Wde!dd4NsWe@#6@ ?nkDn4%ENL S!MM@Y@ f THIS REPORT CONTAINS THE DATA ASSOCIATED WITH THE ULTRASONIC EXAMINATION OF WELD CSHXW-6-B, A STAIN-LESS STEEL SHELL TO N,0ZZLE CONFIGURATION. THIS 4 EXAMINATION WAS PEdFORNED IN ACCORDANCE WITH AShE SECTION XI CODE REQUIREMENTS. PRE-SERVICE EXAM ~ THE WELD WAS EXAMINED WITH A 45 DEGREE SHEAR WAVE 1 V PATH TECHNIQUE FROM NOZZLE SIDE OF THE WELD. A 60 DEGREE SHEAR WAVE % V PATH TECHNIQUE FROM THE NOZZLE SIDE OF TIE WELD, J ,,,.c,3 1 A SUPPLEMENTAL EXAMINATION WAS PERFORNED WITH 'b A 70 DERGEE RL FROM THE NOZZLE SIDE OF THE WELD. ID GEOMETRY WAS RECORDED WITH THE 45 AND 60 NO RECORDABLE INDICATIONS WERE OBSERVED WITH l THE 70RL, b Yo DUE TO SHELL TO NOZZLE CONFIGURATION)5% B1-DIRECTIONAL COVERAGE WAS OBTAINED, M_ a,- (UA l Y/of.T9 v i RESOLUTION BY: REVIE\\ ' D BY: ANII: 4 17 lir

  • f DATE: }l J ( % k LEVEL: 32., DATE: 10-02 92 LEVEL:

DATE: [g "A h PG. / O'F /h fnl4Qtr I'

~ TENNESSEE VALLEY DIGITAL ULTRASONIC REPOIhT NUMBER: ff g ( AUTIIORiTY CALIBRATION DATA SHEET l w PROJECT SONP UNIT / CYCLE 1/C9 CALIBRATION DATE: 10 02-98 I PROCEDURE: N lTT-18 REV:22 TC:97 23 CALIBRATION BLOCK NO. BNP-17 TEMP: 73 INSTRUMENT:KB m __ DUE DATE: 06-17-98 SIMULATOR BLOCK NO: 6026-83 MODELfrYPE: Mi@IGO'U$/35z 'S/N: E23946 TIERMOMTER S/N: 575363 DUE DATE: 11-21-98 TRANSDUCERMANUF KB amJ COUPLANT ULTRAGEL BATCH: 94125 S/N 25078 SIZE:.250 FREQ: 2 25 MHE EXAM TYPE: SHEAR @ LONGO RLD CABLE TYPE: RG-174 - LENGTH: 72" ANGLE VERIFICATION BLOCKTYPE: nnMP AS S/N: 60%R3 DAC NOMINAL ANGLE: 45 ACTUAL ANGLE: 44 INSTRUMENT SETTINGS 100 A REFLECTOR REFERENCE MEMORY 1 M SCAN DIRECT. NTCH SDH SENSITIVITY NUMBER \\ P gal-O 37 dB 3 60 N \\ l FREQ: HIGH MHz REJECT: 0 \\ cD1 -f ANGLE: 44 deg DAMPING: 1006 - ohms 40 U DELAY: O msec PULSER: SING. msec FR.R M 20 E VELOCITY: 1223 msee REP RATE: HIGH j RANGE: 1.769 inches TOF: @ PEAK O FLANK 0 RECTIFER: FULL POWER

  • DC DISPLAY WIDTH: 1.769 DUAL: O ON

@ OFF TCG: O ON @ OFF e-REF. REFLECTOR: ROMPAS GAIN: 37 dB CALIBRATION TIMES AMPLITUDE: 65 METAL PATH:.464 INITIAL TIME: 1135 FINAL TINE: 1600 VERIFICATION TIMES l 1)l400 l 2)l505 l3)N/A 4)N/A l 5)N/A l 6)N/A l 7)N/A l 8)N/A l 9)N/A

  • PD1 QUALIFIED INSTRUMENT SETTINGS:

VERIFY INSTRUMENT SETTINGS AND CALIBRATION SEQUENCE ARE IN ACCORDANCE WITH TABLE 2 j OF THE APPLICABLE PD1 QUALIFI. CATION IMPLEMENTATION PROCEDURE ! LINEARITY CHECK y ~ ,( p SIGNAL 1 l 100 90 80 70l60 50l40 30 ~ 20 VERTICAL SIGNAL 2 l50 45 40 35 l 30 25l20 15 10 GAIN } SET l -6 dB -12 dB l SET l +12 SET l +6 y I 32 TO 48 16 TO 24 20 % l 64 TO 96 40 % 64 TO 96 ,V ATTENUATOR AMP l 80%. 40 20 80 80 i 4 WELDS /ITEMSIXAMINED ? f@ M$ e L:COMMENTSi- /$ CP1WM R N n /JT7s d *0 fh 0 C # mrH 2 wMg l CSHXW-6-B l CSHXW-7-B f J / \\ / l uf (t//p$,~37 \\ i / a isl-M2-c-62 I l ,. 3 EXAMINER [ cad.47~4NA-LVL 22' DATE: (l50 C)8 } EXAMINER kc. LVL J2C ~ f r.. ~ Qb /b M DATE REVEWER 4 LVL i / 04/01/1998 TVA/1SO REV1

E. 4 ^ TENNESSEE VALLEY T DIGITAL ULTRASONIC REPORT NUMyER: 9g.g3( CALIBRATION g AUTIIORITY DATA SHEET O PROJECT SONP UNIT / CYCLE 1/C9 CALIBRATION DATE: 10-02-98 PROCEDURE: N-UT-18 REV:22 TC:97-23 CALIBRATION BLOCK NO.: BNP-17 TEMP: 73 INSTRUMENT: KB & DUE DATE:M-17-98 SIMULATOR BLOCK NO: 6026-83 MODEL/FYPE:.U$sk/ OYOh S/N: E23946 THERMOMTER S/N: 575363 DUE DATE: 11-21-98 TRANSDUCERMANUF, KB W.n COUPLANT ULTRAGEL BATCH: 94125 S/N 24490 SIZE:.250 FREQ: 2.25 MHz EXAM TYPE: SHEAR @ LONGO RLD CABLE TYPE: RG-174 . LENGTH: 72" ANGLE VERIFICATION BLOCK TYPE: RnMPAS S/N: 6026-83 DAC NOMINAL ANGLE: 60 ACTUAL ANGLE: 59 INSTRUMENT SETTINGS 100 A REFLECTOR REFERENCE MEMORY M SCAN DIRECT. NTCH SDH SENSITWITY b % IBER Q'\\ 80 t p AMAL O 45 dB 5 \\ L CIRC O O N/A dB N/A 60.- 1 FREQ: HIGH MHz REJECT: 0 \\

  • 3 40

\\ U DELAY: 0 msec PULSER: SING. j \\ 0: 4m

  • msec M R: F M D 20 E

VELOCITY: 1188 msee REP RATE: HIGH \\cc O RANGE: 1.401 inches TOF:@ PEAK O FLANK f O RECT 1HER: FULL POWER: DC pu. DISPLAY WIDTH: 1.401 DUAL: O ON @ OFF TCG: O ON @ OFF (' REF. REFLECTOR: ROMPAS GAIN: 37 dB CALIBRATION TBIES AMPLITUDE: 65 METAL PATH: 464 INITIAL TIME: 1345 FINAL TIME: 1604 VERIFICATION TB1ES l 1)l445 l 2)N/A l 3)N/A 4)N/A l 5)N/A j 6)N/A l 7)N/A l 8)N/A l 9)N/A j

  • PDI QUALIFIED INSTRUMENT SETTINGS:

VERIFY INSTRUMENT SETTINGS AND CALIBRATION SEQUENCE ARE IN ACCORDANCE WITH TABLE 2 OF THE APPLICABLE PDI QUALIFI. CATION BIPLEMENTATION PROCEDURE ! l LINEARITY CHECK 1 2H ^ VERTICAL s SIGNAL 2 l50 45 40 35 l 30 25l20 15l10 F> GAIN l SET l -6 dB 12 dB l SET l +12 l SET l +6 + ATTENUATOR AMP l 80% l 32 TO 48 16 TO 24 20 % 64 TO 96 40 % 64 TO 96 ~, M E 40 20 80 80 MCOMMENTSA - M+d @ iMs BWELDS/ ITEMS EXAMINEDW ^( s BPT?M M,7m unes cirrxwey a jm y,2c y, l CSilXW-6-B l CSHXW 7 B / I ~ J / l / I l / n I ANH: Q EXAMINER,hm p,.h LE. C . g? i. EXAMINER [ I LVL. p +, /c PAGE 3 OF REVIEWER - M M Y LE DATE 04/01/1998

TENNESSEE VALLEY DIGITAL ULTRASONIC REPORT NUMJER: 9 g, y AUTHOI8TY CALIBRATION g DATA SHEET PROJECT SONP ' UNIT / CYCLE 1/C9 CALIBRATION DATE: 10-02-98 PROCEDURE: N-UT-18 REV:22 TC:97-23 CALIBRATION BLOCK NO/ BNP-17 TEMP: 73 INSTR'JMENT: KB DUE DATE: 06-17-98 SIMULATOR BLOCK NO: 6026-83 MODE!/ TYPE"y$NIIPM,((;, S/N: E23946 THERMOMTER S/N: 575363 DUE DATE: 11-21-98 TRANSDUCER MANUF:JB'RfD COUPLANT ULTRAGEL BATCH: 94125 S/N 95-854 SIZE:.2(nid FREQ: 2 MHz EXAM TYPE: SHEARD LONGO RL@ CABLE TYPE: RG-174 LENGTH: 72" ANGLE VERIFICATION BLOCK TYPE: ROMPAS S/N: 6026-R3 DAC NOMINAL ANGLE: 70 ACTUAL ANGLE: 69 INSTRUMENT SETTINGS 100 ,,,, l A REFLECTOR REFERENCE MEMORY W" M scan DIRECT. NTCH SDH SENSITIVITY NUMBER x 80 J' g P ^m^!- O 60 dB 6 ^ ^ 60 i FREQ: HIGH MHz REJECT: 0 m deg Mm WI hs ~ 40 U DELAY: 0 msec PULSER DUAL 20 E VELOCITY: 2224 msec REP RATE: HIGH RANGE: 2 041 inches TOF: @ PEAK O FLANK 0 RECTIFIER FULL POWER-DC DISPLAY WIDTH: 2.041 DUAL: O ON @ OFF TCG: O ON @ OFF q} REF. REFLECTOR: ROMPAS GAIN: 60 dB CALIBRATION TIMES AMPLITUDE: 75 METAL PATH:.941 INITIAL TIME: 1300 FINAL TIME: 1610 VERIFICATION TIMES l 1)l420 l 2)l530 l3)N/A 4)N/A l 5)N/A l 6)N/A l 7)N/A l 8)N/A l 9)N/A

  • PDI QUALIFIED INSTRUMENT SETTINGS:

VERIFY INSTRUMENT SETTINGS AND CALIBRATION SEQUENCE ARE IN ACCORDANCE WITH TABLE 2 OF THE APPLICABLE PDI QUALIFICATION IMPLEMENTATION PROCEDURE ! LINEARITY CHECK SIGNAL 1 l 100 90 80 70 l 60 50l40 '30 20 y ]g VERTICAL SIGNAL 2 l50 45 40 35 l 30 25l20 15 10

  • W
  • 8 GAIN l SET l

-6 dB -12 dB l SET l +12 SET l +6 16 TO 24 20 % l 64 TO 96 40 % l 64 TO 96 f".h' " ATTENUATOR AMPj 80 % l 32 TO 48. , M 40 20 80 80 _,me ac eCOMM NTs w "+ wan o avEtDs/rrEMS EXAhDNEDe l CSHXW-6-B l CSHXW-7-B / I J/ \\ / l a l l ^""

  • ExAwNea u n ;a u
a. r DATE: \\)-SO'-Q B fr f-EXAMINER [a.as [

LVL. g__ V" ^ REVIEWER LVL [ DATE TVA/ ISO REV1 04/01/1998 j j

ULTRASONIC REPORT NUMBER [- . TENNESSEE VALLEY PIPING EXAMINATION 'N /( h 3 AUTIIORITY D ATA SHEET i PROJECT: SQN UNIT: 1 CYCLE: 9 EXAMINATION DATE: 10-02-98 PROCEDURE: N lTT 18 REV:22 Tl 97 23 START TIME: 1400 END TIME: 1445 EXAM SURFACE O ID E OD SYSTEM: CS MATL. TYPE: O CS S SS ocsct ocess COMPONENT ID: CSHXW-7-B CONFIGURATION SURFACE TEMP.: 81 *F PYRO. NO.: 575363 CAL DUE DATE: 11 21 98 SHELL TO NOZZLE EXAM ANGLE 45 DEG 60 DEG FLOW y CIRC. SCAN SENSTTIVITY 55 dB 59 dB Wo

REFERENCE:

CENTERLINE OF WELD AXI^l. SCAN SENSITIVITY 51 dB N/A dB Lo

REFERENCE:

TDC IND. L (in) FROM REF, AT MAX AMP MAX EXAM NOM. N IND. INFO: NO. L1 L L2 W MP D AMP NO. ANG. R TYPE, DAMPING, MAX MAX MAX MAX %DAC 3-14 I ETC. .500 .520 N/A 32 % 4 45 ID GEOMETRY 777>F c %2C 28 1 5 45 X 6 45 X .500 .771 N/A 100 % 4 60 ID GEONETRY 26.5 n.er 2 5 60 X 6 60 X / / M p rT / 'i) p / /0 ~ / y REMARKS / LIMITATIONS:

  • OBSERVED 360 ABOVE AND BELOW~ RECO INTERMITTELY, l

l ANil: LEVEL: 7 g $m 4. n/ e / / EXAMINER: .r>r DATE:h30-9 B / / LEVEL: l EXAMINER: jim-m M- [- 2-REVIEWER: g LEVEL-DATE: PAGE OF 7

ULTRASONIC l, . TENNESSEE VALLEY PIPING EXAMINATION \\ REPORT NUMBER: AUT110RITY l DATA SIIEET g733 d PROJECT: SQN UNIT: 1 CYCLE: 9 EXAMINATION DATE: 10-02-98 ] PROCEDURE: N-UT-18 REV:22 TC:97-23 START TIME: 1450 END TIME: 1545 SYSTEM: CS EXAM SURFACE O ID @ OD COMPONENT ID: CSHXW-6-B MATL TYPE: O CS S SS ocsct Occss CONFIGURATION SURFACE TEMP : 81 'F PYRO. NO.: 575363 SHELL TO NOZZLE CAL DUE DATE: 11-21-98 i FLOil' EXAM ANGLE 70 DEG N/A DEG l Wo

REFERENCE:

CENTERLINE OF WELD CIRC. SCAN SENSITIVITY 55 dB N/A dB ^X1AL SCAN SENSITIVITY N/A dB N/A dB Lo

REFERENCE:

TDC IN D.- L (in) FROM REF. AT MAX AMP MAX EXAM NOM. N IND. INFO: NO. L1 L L2 W MP D AMP NO. ANG. R TYPE, DAMPING, MAX MAX MAX MAX %DAC 3-14 1 ETC. N/A N/A N/A N/A N/A N/A% 3 70L X 1 I / / /. y / / 7 / ,,,,5

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4 O 9' O ATTACHMENT 2 TVA PROCEDURE FOR CALCUIATION OF ASME CODE COVERAGE FOR SECTION XI l i l t yhk.O ID-kd'~ -

N s um, NONDESTRUCTDE EXAMINA110N PROCEDURE Procedure No. N-GP-28 TVA Nuclear Power Revision 1 Page 3 of 16 1.0 Scope The scope of this procedure is to provide generic guidelines for calculating the ASME Section XI code coverage obtained during volumetric and surface' examinations. This procedure incorporates the requirements of Code Case N-460. 2.0 Purpose This procedure applies to the calculation of AShE Section XI Code coverage for vessel welds, piping welds, and integral attachments. This procedure applies to personnel perfonning surface or volumetric examinations and may be used as a guide when calculating the examination coverage for preservice and inservice examinations when the coverage is less than that required by ASME Section XI. Coverage limitations may be due to an obstruction, interference 9 geometric configuration or other applicable reason. 3.0 References 3.1 ASME Section XI 1989 Edition 3.2 AShE Code Case N-460 sk 4.0 Definitions 4.1 Examination Coverage-The percentage of the examination surface or volume obtained during the performance of the examination. 4.2 Examination Surface The surface of the weld and base material required to examined by ASME Section XI using a surface examination method. 4.3 Examination Volume The volume of weld and base material required to be examined by ASME Section XI using a volumetric examination method. 4.4 Scan Limitation-A limit on the ability to scan the surface (s) as required by procedure. 4.5 Surface timitation,A, limit on the ability to perform a surface examination of the required surface (s) because of an interference. 46 Volumetric Limitation-A limit on the ability to scan the required examination volume I because of the geometric configuration, a physical interference, or a metallurgical l condition of the material being examined. 9 9 e ./ t

r -s( ) f NONDESTRUCTIVE EXAMINATION PROCEDURE TVA Nuclear Power Procedure No. N-GP-28 Revision 1 Page 4 of 16 / 5.0 General 5.1 During the performance ofinservice inspections, ASME Section XI requires examination coverage to be essentially 100% of the weld area or volume. For examination coverage le than 100%, TVA has implemented ASME Code Case N 460 which states that when the entire examination volume or area cannot be examined due to interference by another component or part geometry, a reduction in examination coverage for Class I or Class 2 welds may be accepted provided the reduction in coverage for that weld is less than 10% 5.2 Surface examinations are typically conducted on the weld area plus a denned amount of base material on each side of the weld. Volumetric examinations specify a panicular volume to be examined. The Section XI required examination volume or surface examination area for each type of weld is depicted in figures ofIWB-2500 or IWC-2500 as applicable. As depicted for piping welds, volume width generally constitutes the weld plus 1/4t on each side while volume thickness generally constitutes the lower 1/3 of the piping thickness for the length of the weld. The exception normally' includes code category B-O which includes the weld plus 1/2 inch and full volume for the length of the weld. As depicted, for vessel welds, the volume width generally constitutes the wc!d plu 172t on each side of the weld while volume thickness generally constitutes the entire component-thickness (i.e. full volume). The volume changes with variations in weld configuration (e.g. transition between different pipe thickness or vessel weld configurations). 5.3 The Section XI required examination volume or area shall be verified prior to calculation of the limitation. 7 i., 6.0 Documentine and Calculatine Examination Coverace 6.1 While performing a surface or ultrasonic examination, the NDE Examiner shall make every attempt to examine 100 percent of the examination area or volurne. 6.2 When practical, the two beam path directions for ultrasonic examinations should be performed from two sides of the weld or additional angles employed in order to maximize coverage. 6.3 If 100% percent of the examination surface or volume cannot be examined, the NDE Examiner should perform the following under the direction of the inspection coordinator or the NDE LevelIII: 6.3,1 Perform additional examinations with higher angles in order to maximize cover for ultrasonic exams. 6.3.2 Perform another surface method (i.e., PT in lieu of hfT) in order to maximize coverage. 6.3.3 Perform alternative NDE methods if applicable. k I i

4 NONDESTRUCTIVE EXA},G4AT10N PROCEDURE Procedure No. N-GP-28 TVA Nuclear Power Revision 1 Page 5 of 16 6.4 The examiner shall accurately document all limitations, obstructions interferences, geometric configurations or other applicable reasons for not obtaining the required code coverage. 6.5 The examiner shall document the limitation on a sketch. Examination coverage estimates may be performed by the examiner or the reviewer. 7.0 -Calculation Balj i 7.1 Volumetric Examinadons-Piping Welds and Vessels less than 2 inches in thickness a) For welds with access from both sides, each of the four required scans are equal to 25 % b) For welds with access from one side only due to interference / configuration (e.g. pipe to valve), the axial scan (scan 3 or 4) equals 50% and the circumferential scans (scan 5 and 6) each equal 25% for total of 100% c) Examination volume coverage may be increased as previously discussed or by use of refracted longitudinal wave techniques on stainless steel or dissimilar metal welds. Use of refracted longitudinal waves to penetrate stainless steel weld material will increase the examination volume coverage by the amount depicted on the examination coverage drawing.* - -g d) The effects of adjacent component interferences (e.g. welded lug attachments) along _o the weld length are also taken into account with the reduction in coverage identified as a percentage of reduced volume. 7.2 A typical method for caiculating coverage due to ultrasonic piping limitations is contained in Attachments 2 and 2A. 8.0 Surface Examinations - Pioine Welds And Integral Atta:hments 8.1 Examination area coverage calculations are based upon one of the following suppositions: a) The total examination area is calculated, typically length x width, then the total area of limitation or interference is subtracted from the total examination area. ~ b) The area of achieved coverage achieved is divided by the total examination area for percentage of examination achieved. 8.2 A typical method for calculating surface examinations is contained in Attachment 4. e

I 4 NONDESTRUCTIVE EXAMINATION PROCEDURE Procedure No. N-GP-28 TVA Nuclear Power Revision 1 Page 6 of 16 9.0 Ultrasonic Examinations - Vessel Welds 9.1 Examination volume coverage calculations are based upon the following suppositions: a) To achieve full examination coverage nine different scans are required for a typical nozzle examination The following may be used for other vessel configuradons: 1) 0 degree (weld metal scan) 2) 45 degree Transverse-scan from vessel side of the weld 3) 45 degree Transverse-scan from nozzle side of the weld j 4) 60 degree Transverse-scan from vessel side of the weld j 5) 60 degree Transverse-scan from nozzle side of the weld 6) 45 degree Parallel-scan CW direedon 7) 45 degree Parallel-scan CCW direction 8) 60 degree Parallel-scan CW direction 9) 60 degree Paralle!-scan CCW direction 9.2 describes ASME code compliance for full volume examination coverage for transverse scans in vessel applications. I 9.3 Typical niethods for calculating coverage due to ultrasonic vessel limitations is contained in Attac!unents 3 A,3B,3C, and 3D. - 1 10.0 Responsibilities 1 1 ~ 10.1 The examiner or designee shall document the amount of code coverage obtained on ( Attachment I after all necessary steps to perform additional examinations has been completed in order to maximize coverage. 10.2 Attachment I shall be reviewed by another individual with the same or higher NDE certification. 10.3 The NDE Level III or data reviewer shall review Attachment 1 in order to verify that the information is accurate and correct. 10.4 The NDE Level Ill may recalculate the examination coverage to obtain a more accurate value of the examination surface or volume examined. The calculation shall be documented on the exam repon. 10.5 The NDE Level III may require an alternate examination technique or method, or request that the interference be removed. For nozzle examinations, supplemental scans from the nozzle bore or flange face may provide complete coverage of the weld. 10.6 If the examination coverage indicates less than 90 percent of the required examination, volume or surface, the site ISI supervisor shall be notified. 10.7 The site ISI supervisor shall ensure that examination results are accurately documented and incorporate results into a Request for Reliefif necessary. -i \\ O

s NONDESTRUCTIVE EXAhCNATION PROCEDURE

  • Procedure No. N-GP-28 TVA Nuclear Power Revision !

Page 7 of 16 ATTACHMENT 1 EXAMINATION RIrog No, nwwr VAunAumoerrr

SUMMARY

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1 g-ge-e m _-1 t- ' NONDESTRUCTIVE EXAMINATION PROCEDURE Procedure No. N-GP-28 {' TVA Nuclear Power Revision I - Page 8 of 16 I F ATTACHME?TT 2 i l' s ^ i \\ t-i f 1.25" +- )/4, 374 H, -+ P l l 40.05" { q ClRCUMFERENG:. ~ 3/8" \\/ l 12" Schedule 140 g Outside Diameter = 12.75" Wall thickness-1.125" 13/4" i Circumference-40.05" j i TOTAL VOLUME = (.375)(1.75)(40.05) TOTAL VOLUME 26.28 cu. inches m O e

m = NONDESTRUCTIVE EXAMINATION PROCEDURE 'Prortdure No. N-GP-28 TVA Nuclear Power Revision 1 Page 9 of 16 ATTACHMENT 2A ATTACHWNT 2A - PPNG/ VESSELS 4.ESS .875'- A THAN 2 NCHES N THKXNESS EXAMPLE 2 NO COVERAGE FOR 6 NJ' ES N m c:vutaa / 45 DEGREE LENGTH DUE TO ATTACHMENT .375" nu.Locm COVERAGE 1 MNMEAM h y A.2578 SQ.!N .500"-B VOL.-(.2578)(6") VOL-1.5468 CU.!N. 45 DEGREE-i COVERAGE NO COVERAGE-1.5468/26.28 I \\ UPSTREAN NO COVERAGE.0525(100)-5.88% COVERAGE-100-5.25=94.75% L 1.75,, V/A M 100% 45 CRC SCAN-100% 45 CIRC SCAN-100% 94.75% EXAMPLE 1 NO COVERAGE, FULL LENGTH ASSUME ALL OTER SCANS =100% 98 A3% TOTAL COVERAGE 100 100%100W60.74-360.74 A-H/2(A+B) 360.74/4 90.185% TOTAL EXAM CDVERAGE A.375/2(.875+.5) EMNM.E 1 A.2578 VOL.-( 2578)(40.05) FULL COVERAGE-(.375)(1.75){40.05)=26.28 CU.N. WL-10.32CUJN. HO COVERAGE-10.32/26.28 NO COVERAGE =.3926 (100)-39.26% COVERAGE-1CO-39.26-60.74% ~ e gs

NONDESTRUCTIVE EXAMINATION PROCEDURE Procedure No. N<sP-28 TVA Nuclear Power Revision 1 , Page 10 of 16 ATTACHMENT 3 s l l 45 DEGREE-100% ASME SECTION XI COVERAGE (T-SCAN) l (~ te. / / N I 60 DEGREE-100% ASME SECTION XI COVERAGE (T-SCAN) THE ASME SECTON XI CODE REQUIRES THE WELD TO BE COMPLETELY EXAMINED IN TWO DIRECTONS. THE ABOVE axe EXAMPLES OF100% BlDIRECTIONAL COVERAGE (T-SCANS). 6

R;' ) s J l j i i NONDESTRUCTIVE EXAh0NA110N PROCEDURE Procedure No. N-GP-28 TVA Nuclear Power Revision 1 Page 11 of 16 ATTACHMENT 3A s 1/2 T-1.5" [* 1.2 5" 3/16, LENG W-85" A 4 T A A 4L ___ V.2 5 " l n 2-5/8" 60 D .75" 3.0" ) y I h y b \\ ( y ,1.5" \\ TOTAL VOLUME- (L)(W)(H) 45 DEG TC TAL VOLUME- (85)(4.25)(3) 41/4-TOTAL VOLUME-1083.75 CU. INCHES EXAMPLE 1-45T AND 60T SCANS AS SHOWN UMITED FOR FULL LENGTH. EXAMPLE 2 45T AND 60T SCANS AS SHOWN LIMITED FOR A LENGTH OF 12 INCHES. ,d'

s S NONDESTRUC11VE EXAMINATION PROCEDURE Procedure No. N-GP.28 TVA Nuclear Power Revision 1 Page 13 of 16 ATTACHMENT 3C l AREA 1 2.75" 1.5" / ;c DETERMINE TOTAL 7 EFFECTIVE 866 Y COVERAGE A.375 B-2.812 5" 3.0" O-100% j 45T-29.76% / 45T-100% H=4.25" \\ 60T-55.9% 4.25" AREA 2 60T-100% TOTAL AREA-(3)(4.25)=12.75 45Pcw-100% 1.0-DETERMlNE REA EXAMINED. VOL=(12.75)(85)=1083.75 CU.IN. 45Peew-100% A-H/2(A+B) 60Pcw-100% A-4.25/2(.375+2.8125)=6.77 SQ.IN. DETERMINE AREA REQUIRED TO BE 60Pecw-100% EXAMINED BY THE CODE. VOL.=(6.77)(85!N.)= 575.45 CU8C IN. TOTAL-785.66 AREA 1-1/2BH-1/2(.866)(1.5)- AVERAGE-785.66/9 AREA.649 SQ.IN. AVERAGE-87.29% VOL-(.649)(85)=55.165 CU.IN. AREA 2-TOTAL AREA-AREA 1 AREA 2-12.75 SQ.!N..649 SQ.IN.- 12.10 SQ.IN. 2.0 DETERMINE 45 DEGREE COVERAGE COVERAGE = VOLUME COVERE,D/ VOLUME REQUIRED 45 DEGREE COVERAGE-575.45/1028.585=.559(100)- 55.9% a e

~ NONDESTRUCTIVE EXAMINATION PROCEDURE Procedure No. N-GP-28 TVA NuclearPower Revision 1 Page 12 of 16 / ' ATTACHMENT 3B EXAMPLE 1 AREA 1 1.5" g H-2. 75" B-2.75 " 4.25" AREA 2 1.0-DETERMINE AREA EXAMINED. TOTAL AREA-(3)(4.25)-12.75 A-1/2(2 75).75)-3.78 SQ.IN. VOL-(12.75)(85)-1083.75 IN VOL=(3.78)(85lN.)- 321.3 CUBC IN. DETERMINE AREA REQUIRED TO BE EXAMINED BY THE CODE. (~ AREA 1-1/2BH-1/2(1.5)(1.5)-1.125 AREA 2-TOTAL AREA-AREA 1 AREA 2-12.75-1.125 - 11.625 SQ.N. VOLUME AREA 2-(11.625)(85) VOLUME AREA 2-988.125 CU.lN. 2.0 DETERMlNE 45 DEGREE COVER GE COVERAGE-VOLUME COVERED / VOLUME REQUIRED 45 DEGREE COVERAGE =321.3/988.125.3251(100)- 32.51% e-l i

F~ s NONDESTRUCTIVE EXAMINATION PROCEDURE Procedure No, N-GP-28 TVA Nuclear Power I Revision 1 Page 14 of 16 ATTACHMENT 3D EXAMPLE 2 45 DEGREE DETERMINE TOTAL AREA NOT COVERED- (AREA 2)-(AREA EXAMINED) COVERAGE FOR AREA NOT COVERED-11.625 SQ.lN.-3.78 SQ.IN-7.845 SQ.IN. WELD VOLUME NOT COVERED- (7.845 SQ.IN.)(121N.)=94.14 CU.IN. ~ 45 DEG. (NO COVERAGE)- 94.14/1083.75*100-8.68 % O-100% 60 DEG. (NO COVERAGE)- 67.44/1083.75*100-6.22 % 45T-91.32% 45T=*.00 45 DEG. (COVERAGE)= 100-8.68-91.32% 60T-93.78% 60 DEG. (COVERAGE)-100-6.22-93.78% 60T-100% 45Pcw=100% 45Peew-100% 60Pcw=100% ( 60Peew-100% TOTAL =885.1 TOTAL AVERAGE-88.5.1/9 TOTAL AVERAGE-98.34% 6 e 4

7 { 3 ^ .N NONDESTRUCTNE EXAMINATION PROCEDURE Procedure No. N-GP-28 TVA Nuclear Power Revision 1 4 Page 15 of 16 i ATTACHMENT 4 ( Examples for calculating code coverage when er.amining integral attachments: EXAMPLE t Luc welded on Two sides! ~ . l I 1/2*

  • --*l 1/2" lLi L2 La!

l l l l Hanger clamp around lL4 Ls Ls: pipe on this side of l 3" Lug l Lug. l l [ Area to be examined l l' i for ASME code coverage-Total weld length to be examined = L1 + L2. L3 +L4 + ls + Le Total weld length to be examined = 1/2 + 3 + 1/2 + 1/2 + 3 + 1/2 = 8" .I Total weld length inaccessible =.L3 + Ls Total weld length inaccessible = 1/2 + 1/2 = 1

  • Therefore,7 inches were examined out of 8 giving a "per-cent coverage" of 7/8 = 87.5%

EXAMPLE 2: Luc welded on Three sides! l l 1/2"," " 1/2' l Li L2 L3 -l l t l' clamp around pipe ,1 'L7 on this side of lug! fL4 Ls Le ! i 1/8' .l 3* Lug l l l .l l l Total weld length t'o be examined Li + L2. L3 +L7 + L4 + Ls + Le Total weld length to be examined = 1/2 + 3 + 1/2 + 1/8 + 1/2 + 3 + 1/2 = 81/8* (8.125") Total weld length inaccessible = L3 + Ls . Total weld length inaccessible = 1/2 + 1/2 = 1" Therefore. 8.125

  • were examined out of 9'so code coverage is 8.125/9 = 90.28%

s 3,- -m._ se e j 1 i NONDESTRUCTIVE EXAMINATION PROCEDURE ' Procedure No. N-GP-28 TVA Nuclear Pour I Revision ! Page 16 of 16 ATTACHMENT 4A Examples for calculating code coverage when examining integral attachments (cont.): s Examole 3: Full oenetration lucs $5 l l Clamp around l Li L2 La:, pipe-this side r y only! lI7 '~ ~ t_. / i l-N l L4 Ls Lej 2* l l 2* j l 4* Lug l 4 l Total weld length to be examined = L1 + L:. Ls +L7 + L4 + Ls + Le + La f -Total weld length to be examined = 1/2 + 4 + 1/2 + 2 + 1/2 + 4 + 1/2 + 2 = 14* Total weld length inaccessible = L3 + Le + Le Total weld length inaccessible = 1/2 + 2 + 1/2 = 3* Therefore,11' were examined out of 14*, so code coverage is 11/14 = 78,57% Examole 4 Luo coverace computation usino area versus lenoth. Use measurements in examole 1 above! ,M M l l Hanger around pipe .l l this side only. l / l l 3* Lug { l welded 2 sides l ) I with 1/4* fillet weld. l i l From first example, totallength = 8* The width of weld face for this example is.350' plus 1/2" above and below weld toes, for a total of 1.350' weld width. The required area of examination is then 8 fong x 1.350 wide = 10.8 sq. in. The length inaccessible is ( %* + %* = 1* length) so total area that is inaccessible is 1* x 1.350' (width) = 1.350 sq. in., Therefore. calculate code coverage by dividing total area examined (9.45 sq in) by total area which should be examined (10.8 sq. in.) equals 87.5%. Same as in first example using-length.

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