ML20195H789
| ML20195H789 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah |
| Issue date: | 11/17/1998 |
| From: | Salas P TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9811240106 | |
| Download: ML20195H789 (130) | |
Text
{{#Wiki_filter:_ 1 Tencessee VaHey AuthoMy Post Office Box 2000 So&ty Daisy Tennessee 37379 November 17, 1998 10 CFR 50.50a (g) (5) (iii) U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Gentleman: In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI INSERVICE INSPECTION (ISI) PROGRAM RELIEF REQUESTS
References:
1. NRC letter to TVA dated April 27, 1998, " Evaluation of the Second 10-Year Interval Inspection Program Plan and Associated Requests for Relief for Sequoyah Nuclear Plant, Units 1 and 2 (TAC Nos. M94115 and M94116 ) " 2. TVA letter to NRC dated November 21, 1995, "Sequoyah Nuclear Plant (SON) - American Society of Mechanical Engineers (ASME) - Section XI Programs for the Second Inspection /j Interval, Units 1 and 2" /// 3. NRC letter to TVA dated August 7,
- 1998,
" Safety Evaluation of Relief Requests for the Pump and Valve Inservice Testing Program - / Sequoyah Nuclear Plant Units 1 and 2 (TAC Numbers MA0417, MA0418, MA1595, and MA1596)" The purpose of this letter is to request NRC review and approval of five ASME code relief requests that were identified in SQN's second 10-year ISI interval for both units. The relief requests are based on limitations that 9811240106 90111'7"' gDR ADOCK 05000327 PDR I a
U.S. Nuclear Regulatory Commission l Page 2 November 17, 1998 1 preclude full code examination of ASME Class 1 and 2 welds. Code examination of the welds is limited due to design pipe configuration or cast material. SON's ISI Program has been evaluated and found acceptable by NRC in the referenced letter. Subsequent to NRC review of SQN's ISI Program, five new relief requests were identified during SQN's Unit 2 Cycle 7 and Unit 1 Cycle 8 refueling outages. The relief requests are 1-ISI-9, 1-ISI-10, 2-ISI-8, 2-ISI-9, and 2-ISI-10. The relief requests are 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) (1). We are currently planning our inspections for the second period of SON's 10-year interval (i.e., Cycle 10 and 11 refueling outages). NRC response is requested for the subject relief reauests by May 31, 1999. This date will support TVA's schedule for planning inspections during SON's ) Cycle 10 refueling outages. provides the Unit 1 relief requests. provides the Unit 2 relief requests. provides TVA's procedure for calculation of the ASME code coverage for Section XI nondestructive examinations. In Reference 2, TVA provided SQN's updated second 10-year ASME Section XI Programs (ISI and inservice testing) for NRC review. Reference 2 stated that SQN's second 10-year interval for these programs began on December 16, 1995. At that time, this start date was considered by TVA to be an estimated date that was based on SON's extended outage time. Extended outage time qualifies as "out of service" time that may shift the start date for 10-year intervals under the provisions of the ASME code. TVA's estimation of the start date was recognized by NRC as an action item (reference Action Item 4.1 of Reference 3) for TVA to establish the exact date for SON's 10 year interval. In response to this issue, we consider December 16, 1995, to be the exact date for the start of SQN's 10-year interval.
...........-.. -.-.~.-. _ _... - - -.-.-. -... -.. -. - _ -._ U.S. Nuclear Regulatory Commission Page 3 November 17, 1998 j LIf you have any questions regarding this response, please contact me at extension (423) 843-7071 or J. D. Smith at extension (423) 843-6672. 1 Sincereiy, 9 ~ alas Licensing.and Industry Affairs Manager Enclosures cc (Enclosures): Mr. R. W. Hernan, Project Manager Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 NRC Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy-Daisy, Tennessee 37379-3624 -Regional Administrator U.S. Nuclear Regulatory Commission Region II Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-3415 f ? L 1 !I 4
4 I i I 1 l. ENCLOSURE 1 i i SEQUOYAH NUCLEAR PLANT-UNIT 1 ASME REQUESTS FOR RELIEF 1-ISI-9 AND 1-ISI-10 l l l L I I i t l 1 J r i 3 a I l [
REQUEST FOR RELIEF 1-ISI-9 Executive Summary: This request for relief addresses the pressurizer nozzle full penetration welds. The design configuration of the pressurizer nozzle-to-head welds precludes a 100% ultrasonic examination of the required volume for the following nozzle-to-head welds: RCW-15 (4-inch spray nozzle) and RCW-21 (14-inch surge nozzle). These physical examination limitations occur when the 1989 code examination requirements are applied in areas of components constructed and fabricated to early plant physical designs. Based on the date of SQN's construction permit (May 27, 1970), SQN is exempt from code requirements for examination access as allowed in 10 CFR 50.55a (g) (4). An ultrasonic examination was performed on accessible areas to the maximum extent practical, given the physical limitations of the subject welds. The design configuration limits ultrasonic examination to approximately 78% of weld RCW-15 and approximately 64% of weld RCW-21. Performance of an ultrasonic examination of essentially 100% of full penetration welds in the pressurizer nozzle-to-vessel head welds, RCW-15 and RCW-21, would be impractical. The performance of the ultrasonic examination of the subject welds to the maximum extent i practical, provides reasonable assurance of an acceptable level of quality and l safety because the information and data obtained from the volume examined provides i sufficient information to judge the l overall integrity of the welds. Therefore, pursuant to 10 CFR
- 50. 55a (g) (5) (iii), it is requested that l
relief be granted for SQN's second i inspection interval. Unit: 1 System: Reactor Coolant - System 68 Components: Two Pressurizer Nozzles, Full Penetration Welds ASME Code Class: ASME Code Class 1 (Equivalent) 1-ISI-9 El-1
_~ Section XI Edition: 1989 Edition Code Table: IWB-2500-1 Examination Category: B-D, Full Penetration Welds Of Nozzles In Vessels Examination Item Number: B3.110, Pressurizer Nozzle-to-Vessel Welds Code' Requirement: ASME Section XI, Table IWB-2500-1, _ Examination Category B-D, Item No. B3.110, Volumetric Examination Code Requirement-From Which Relief Is Requested: Volumetric Examination Coverage List Of" Items Associated With The Relief Request: RCW-15, Pressurizer Nozzle-to-Head Weld RCW-21, Pressurizer Nozzle-to-Head Weld Basis for Relief: The design configuration of the pressurizer precludes an ultrasonic examination of the required volume for the following nozzle-to-head welds: RCW-15 (4-inch spray nozzle) and RCW-21 (14-inch surge nozzle). The design configuration limits ultrasonic examination to approximately 78% of Weld RCW-15 and approximately G4% of Weld RCW-21. - Alternative Examination: In lieu of the code required 100% ultrasonic examination, an ultrasonic examination was performed on accessible areas to the maximum extent practical, given the physical limitations of the pressurizer nozzle-to-head welds. Refer to Attachment 1 for the examination data reports. Justification For The Granting Of Relief: (1) The design configuration of the subject nozzle-to-head welds precludes ultrasonic examination of essentially 100% of the required examination i volume. In order to examine the welds in accordance with the code l requirements, the pressurizer would require extensive design i modifications. The physical arrangement of RCW-21, in conjunction with the close curvature of the outside wall surfaces of the nozzle, i .recludes ultrasonic examination from ) 1-ISI-9 El-2 t l
the nozzle side. For scans normal to the weld on the bottom vessel head side, examinations are' limited to areas up to approximately 4 inches from the weld centerline. Limitations on the bottom head side of RCW-21 are due to the presence of 78 immersion heaters penetrating the head, which restricts the scanning surface of the transducers. The scans for flaws oriented transverse to the weld are not obstructed. Therefore, 100% of the required examination coverage for flaws transverse to the weld was obtained. Total examination coverage of Weld RCW-21 was approximately 64% of the code required volume. The physical arrangement of RCW-15, in conjunction with the close curvature of the outside wall surfaces of the nozzle, precludes ultrasonic examination from the nozzle side. Scans normal to the weld.from the head side were not obstructed allowing complete coverage of the weld from one side. Examination coverage from the one side provides reasonable assurance that no flaws parallel to the weld are present. In addition, approximately 100% of the required ultrasonic examination volume for flaws transverse to the weld was performed from the vessel head side. Total combined examination coverage of Weld RCW-15 was approximately 78% of the code required volume. (2) Radiographic examination, as an alternate volumetric examination method, was determined to be impractical due to the thickness of the component. Gaining access to the in-side surface of the pressurizer to place radiographic film would require extensive personnel protection due to high radiation and contamination levels. The pressurizer manway would have to be removed, decontamination performed, and specialized scaffolding erected to gain access. The additional code coverage gained by radiography and/or ultrasonics from the inner surface is impractical when 1-ISI-9 El-3
weighed against the radiological I concerns. The estimated radiological conditions were determined to be: J l 35-40 rad / hour beta (uncorrected) ) l 10-12 rem / hour gamma ) I 1 rad / hour per 100 square cm j Maximum stay time to maintain exposure l to less than 1 rem is approximately 5 minutes. Special clothing would be required for protection from the extremely high contamination levels i and from the high beta dose rate. L Respiratory protection would be l required. Industrial safety would also be a major concern (heat stress, l confined space, and climbing / falling i hazards). Estimates are based on actual experience inside primary components such as steam gene.rators, j (3) A percentage sampling approach provided by the ASME Section XI Code, in combination with examinations performed on similar items, provides reasonable assurance that significant degradation, if present, would have been detected. 4 Performance of an ultrasonic volumetric examination of essentially 100% of full penetration welds in the pressurizer nozzle-to-vessel head (Welds RCW-15 and RCW-21), would be impractical. As previously discussed, TVA determined that it would be impractical to attempt other volumetric examinations in order to increase examiaation coverage. A maximum extent practical ultrasonic examination of the subject welds provides reasonable assurance of an i acceptable level of quality and safety significant degradation, if present, would have been detected during the ultrasonic examination that was performed on the subject welds. As a result, assurance of structural integrity for these welds is provided 7 by the alternative examinations that were performed. 1-ISI-9 El-4
l 1 Therefore, pursuant to 10 CER
- 50. 55a (g) (5) (iii), it is requested l
that relief be granted for the second - inspection interval. Implementation Schedule: This request for relief is applicable to the second inspection interval for SON Unit 1. Welds RCW-15 and RCW-21 were i examined during the first period of the second 10-year inspection interval. i
Background
.information: It should be noted that a request for relief for volumetric examination coverage limitations ] L for Welds RCW-15 and RCW-21 was previously submitted as 1-ISI-21 in SQN's first 10-year ISI interval and was approved by the staff with no additional augmented requirements.
Reference:
NRC letter to TVA dated February 7,
- 1996, j
" Relief Requests to Close-Out the,First 10-Year ) Inservice Inspection Program Interval - I Sequoyah Nuclear Plants Units 1 and 2 (TAC Nos. M92454 and M92455)." - Examination Data Reports: R-6886 and R-6933. i i ' - ISI Program Drawing: i ISI-0394-C-01, Revision 5 and ISI-0394-C-05, Revision 0. I i i I I 1-ISI-9 El-5 l ,,. - - - - -,. ~
1 ATTACHMENT 1 EXAMINATION DATA REPORTS R-6886 R-6933 4 4 a
.~.:" g .y EXAMINATION REPORT No. y-gg(, i TENNESSEE VALLEY AUTHORITY
SUMMARY
AND RESOLUTION SHEET j f I /C PROJECT: 8O W P UNtT: EXAMINER X 0,, A Q h c5TT LV: T SYSTEM: PRE 5h R I1EL EXAMINER C_' 1/7AF 4/6LO LV: 7 l WELO 1.0.: R e_ u - 11 EXAMINER: N /A LV: y /4 ) CONI ~tG: N 312 L i: TO- . CM L L EXAMINER: A /A LV: 4//1 / / 7 s FLOW CAL. SHT NO'S: / / /, ws,/ti pfg i' PROCEcuaE: n-or is Rev.: 9 Tc: NCE METHOO-QUT O PT O MT O vT w A o c omT ewa, e e rue ura rum,x r= n unra 7 up Oie hl3Al rJLT*94fnAi,e. S VP/r1 i n 13 Ti c h/ nff6fJ-C I $ A )0 </rtM CGM /. x/ 77' (' A A /f T i No ABC.o YA.6 ALF /'v/) sea 7~/o N S we #g r -w D usrw 6 9. umw Y5* ase do ".s um mv';c, W'W.m irdn co,m.rna '1 cins. wird 9vam,n.cr wi / A. u o.A 1.O f 0 o E 7'h e ir 57 4 vert z== x, r-47 ia ~; Asu A1 -'-Bee o -(/ ,\\ an a m o p o t s' as o ni u a % a um,n ar,mo on,,, u u, p c C' r D S. n g-of t O Oo A Tn O m u F e d, eR ATin a b 3.7 4 7* bte dove 4 A618 di",N tEVdD. EVALUATO LEVEL: T DATE: { 9, 7 x -sun CONCU E: 2
- '"W LEVEL:
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- TVA 196 0C (NP 7,92)
.~._.-m. I A ,'* * ~ f. .USN-50 ULTR' ASONIC CALIBRATION NO. TENNESSEE VALLEY AUTilORITY . CALIBRATION \\ DATA S!!EET C-R-Cffd ~ n'ROJECT:40A/P uNm 1 CAttBRATION DATE: 2 8 /Y)4 f. 9 7-PROCEDURE:N.lTT.19 REY.: 9 TC: N/A CAllBRATION BLOCK NO.: BNP-79 TEMP.:9 6 *F 1 INSTRUMENT: NON SIMULATOR BLOCK NO.: 5/D5 MODEIJTYPE: lL9N SO Ti!ERMOMETER SERIAL NO.: E 2. lo D Q 9 ( SERAL NUMBER:Y/2Y99 COUPLANT: luirog 6 / IC. B ATCil: 94126' ,-[ ] EXAM TYPE: SIIEAR @ LONG. RL' l TRANSDilCER MANUF.: A 6RO7 6cH-SERIAL NO.: M D 5 955" ANGLE VERTFIC ATION Sl7.E: .7-. O FREQUENCY: A. 2.5 Milz BLOCK TYPE: 80mDAS SERIALNO. Sl o c, a 9 2.~, " CABLE TYPE: R6 /M LENGTII: NOMINAL ANGLE: O ACTUAL ANGLE: O INSTRUMENT SETTINGS 10d REFLECTOR REFERENCE DATA ORIENTATION SENSITIVfrY SET ~3 /g, $" 1 y47' AXIAL
- 0 3
C1RC N/A N/g P-TOF(PEAK / FLANK): PEAK ANGLE: O D EG. L [ \\ //t f DELAY:.359 uS 7.ERO:.620 us N MATL VELOCITY:. 2 32/e s RANGE: 5 00o u k D REJECT: O 7. PULSER: /G/N-g \\,/4 7 ~ E 2' 20 DUAL: ON OFF A A ON O DISPLAY WIDTH SO INTifAL TIME: )O45 FINAL TIME: )52O ~ REF, REFLECTOR: Pr e c e 5 Cff' GAIN: 3b 6 dB VERIFICATION TIMES !)l4 15 2)1605 3) d/ d) dl AMPUTUDE: 40 f. METAL PATH:. 7/eO
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SIGNAL 1 100 90 80 70 60 50 40 ~ 30 20 '! O VERTICAL ~ L' !! SIGNAL 2 50 45 40 35 ~ 30 'A.5 2O 15 10 5 CA!N SU 6 -12 SET + 12 SET +6 ATTENUATOR SIGNAL AMP. 80 7, 32 to 48 16 to 24 20 ?, 64 to 96 40 7, 64 to 96 K go go go go REFERTOCALIDRATION REPORT uk FOR PREVIOUS SATISFACIORY LINEARITY h ' COMMENTS: NfA WELD (s) EXAMINED: ECAO -? l h, JXAMINER: boil LEVEL: 1 ANil: 4 EXAMINER: Ax2 b) b LEVEL: _ ~2Z'. DATE: [1/[9 7 REVIEWED BY: %M LEVEI.: 6 DATE: I Id h PAGE .Q 'OF
1 l l 1 USN-50 ULTRASONrc CALIBR ATION NO. TENNESSEE VALLEY AUTHORITY CALIBRATlON C-4-6f[f DATA SIIEET UNm l CAUBRATION DATE: Q9 mnM PROJECT: SQM9 PROCEDURE:N.UT H REV.: 9 TC: CALIBRATION BLOCK NO.:11bl9 'M TEMP.:A *F INSTRUMEM: f@Jh.Ti" N A cA g R SIMULATOR BLOCK NO.:._ d'I d 6' MODEIRYPE OA N '- SO T1'IERMOMETER SERIAL NO.: 6dL 0 7i SERAL NUMBER: EN\\bbS /ci -l 'f g COUPLANT: U.L?AA G E k BATCH: 99 /d# TRANSDUCER MANUF.: d -ffESoTneM ANGLE VERIFIC ATION SERI AL NO.: Etif a ig S!7,E:. E 'A 1,'O FREQUENCY: 0.95 Milt BLOCK TYPE: ;T7h) SERIAL NO. ') 7't i 9/ _ CABLE TYPE: 94 04 LENGTil: M~ NOMINAL ANGLE: hi ACTUAL ANGLE: li i INSTRUMENT SETTINGS DAC REFLECTOR REFERENCE DATA 100 ORIENTATION SENSmVITY SET ti AXIAL Nl& gg 80 CIRC 3[EE dO P T;c (PEAK / FLANK): PFM ANGLE li ( DEG. [ l 3k N T MY: 10L. Q Cl uS 7.ERO- ( 0.M')3 us ,n E ^ %d-U 40 \\ ggyge7 ogg put3gg g,44 D DUAL: O ON Q OFF 20 x l l INITI A L C ALIB R ATION DISPLAY WIDTH EAN INTT!ALTIME: C 9 04'~~ FINALTIME: i n.r G-REF. REFLECTOR: A adM SN GAIN: 36,0 da VERIFICATION TIMES OT I AMPLITUDE: 4 0 _% METAL PATH: 1, cYi 5) 6) 7) g) C STCNAL 1 1C0 90 80 'i0 60 50 40 30 20 10 VERTICAL ro f L !! SIGNAL 2 50 q5' 43 yg-3 e. cg-go /f l I N'C( GAIN SET 6 12 SET + 12 SET +6 i ATTENUATOR SIGNAL AMP. 80 % 32 to 43 16 to 24 20 % 64 to 96 40 % 64 to 96 K 9e ao I go so REFER TO CALIBRATION REi' ORT WA FOR l'REVIOUS SATISFAClORY LINEARITY 4 cl o n, N c a u e E i:Ac n WELD (s) EXAMINED: RC U 'A I ~ COMMENTS: 3/v ; U (LL AG A f) A IS L M s---.. ,[ LEVEL: ~;: - ANII; MM EXAMINE EXAMINEp re,re ! A<4a A !EVER___ E DATE Y[9//9'7 2 LJ M ' or // tEvEu m DATe T wM PACE REvtEwEo ny:
= e a USN-50 ULTRASONIC C ALIBR ATION NO. 'rENNESSEE VALLEY AUTIIORITY CALIDRATION C- $$7%. DATA SIIEET ( PROJECT: $OME UNIT: I CALIBRATION DATE: 4i rnf\\ R9 fl PROCEDURE: N.UT. I 'l. REV.: 9 TC: CALIBRATION BLOCK NO.: BAN 9 TEMP.- ')(."F SIMULATOR aLOCK NO.: El o6' INSTRUMEtrT: tcRawrdt/b fA MODEl/fYPE: s a < At -S6 TI(ERMOMETER SERIAL NO.: EnLo94 SERAL NUMBER: FofLLN to-1 qq COUPLANT: own e,n BATCH: 9Y/W "^ L TRANSDUCER MANUF.: KS-h IEcN ANGLE VERIFIC ATION SERI AL NO.: E'Ar att Y .o ' FREQUENC'Y: Q,2 C Milz ELOCK TYPE: //L' SERIAL NO. '759 /4 i l St7E:,5b kf 1O) LENGTil: R _" NOMINAL ANGLE: L0 ACTUAL ANCLE: bO CABLE TYPE: INSTRUM ENT SETTINGS REFLECTOR REFERENCE DATA ICO l ORIE?rrARON SENSTTIVTTY SET AXIAL fy /M. f, 4 Y A 30 ..i. CIRC 9 /. O 4) gg P l TOF (PEAK / FLANK): Pl~2 A k ANGLE: LO DEC. f DELAY: 1F,99 uS ZERO: IC99 uS 60 l MAT'L VELOCirY: J'lV% uS RANCE: lcm U 40 \\ \\ REJECT: O% PULSER: /+/61+ }N c DUAL: ON \\ OFF 0 e p j Sed INITI AL C ALIB R ATION O ~ DISPLAY WII7TH 9.D4O INTTIAL TIME: 0 tiO FINALTIME: /nR / VERIFICATION TI5fES REF. REFLECTOR: fon?M 3D4 GAIN: 4La dB /, f -
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- / 16 OnA M m a f4-A clNO WELD (s) EXAMINED: RW d I ~
'Y COMM E>ris: 3/f .t m t iS Q Pd i g // LEVEL: 3C ANil: EXAMINERh. p e e 1,5? *M A.IMEVEL: _ 1- - DATE: '3M/N '7 EXAMINER v bM'M7 LEVEL: 8 D ATE: '3 -9 N PACE CF REVIEWRO RY: .== i c. Ed.F M ANUAL ULTR ASONIC REPORT NO. TENNESSEE VALLEY A UTIIORITY PlPING EXAMINATION DATA SIIEET II_ 4, g i'ROJECT : sodP umT: 1-ExrMtNATION DATE: 03 >M *N SYSTEM : ? Z.C START TIME: /WD END TIME : /,500 WELD I.D. : RC W - 2.1 EXAM SURFACE: O 1D G OD CONRG.: NO 7 7 L6, TO 92 C MATERIALTYPE: O CS O ss O CsCL 0 Cgss SURFACE TEMP: Y4
- F PYRO NO.: 626099 FLOW d.d 33'9A s
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g. BEAM SPREAD REPORT No. TENNESSEE VALLEY AUTHORITY AND RESOLUTION fq DATA SHEET PROJECT: $ Q td P UNIT: }_ BEAM SPREAD DATE: 3 28-M SEARCH UNIT PROCEDURE: N.-UT-19 REV. 9 TC afa MANUFACTURER K6-A S!ZE: .6'x l.O' FREO.: 2.Z6 M5Z UTINSTRUMENT S!N: EZ511% NOM. ANGLE d5* MANUFACTURER: KB MEASUAED ANGLE: 45* DEG. MCDEL NUMBER: OM - Sc> BEAM SPREAO: ll M DEO-SERIAL NUMBER: E21 G G4 10-1-97 TRA! LING RAY (W1) W MAX LEADING RAY (W2) PO$li N 20% DAC 50% DAC 100% DAC 50% DAC 20% D AC W MP W MP W MP W MP W MP 1/4 T
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SUMMARY
AND R-4 fss RESOLUTION SHEET L PROJECT: 68000 yA // UNIT: / EXAMINER Mi c W c n t., 5. 5 ESSO MS LV: J SYSTEM: 22f EXAMINERbnLAs P4 6,12cNevict 0 LV: E I WELO l D.: 2C. k/ ~/8 EXAMINER; u/ LV: g/ !b CONFIG: A OF Ft.S TO: hE55Uf1EEZ EXAMINER LV; s FLOW / // /) CAL. SHT NO'S: PROCEDURE: N-U'T'- / 9 REV.: 9 TC: A//A A/j/ g NOE METHOO: [UT PT MT VT ~7Nis ~2rpner destrA/.us WE 2)Arn Atrocisrss Wnx me us wne. UL 72AStutie KMA&Y/A/A77eAl of W4'L / 2C v/-fS' A d A/220 At 3 rE CL Al072L E 7b VES$dL. YdLA dCA/f) G c)/24770AJ k/MW Si'N/ANK.15 N77~S< es t_ n o. ~7NC synM/A/A-ned n/As wer-Mxen is/ AdeMs4xxe w' irk Al-en'~- l 9 2&Vis/ex/ ' 9 ro M'rer' -n/E 2FousA'G&EM7~5 c A' A.:sNf6.SEc77eN Y/. 77/E EXAMiNA770Al WAs Wefo2Msn osss/G A 6 e' S
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A}e A xin t.- SEAM WAA Per! 2 M SD F2ckt ~rn/s 'u Jo : x ie sioe Cscnd sn bus rv we codficvesrion oe rus doane. 3CAa 9 tJAs coat 77Aluso Ac2cs3 71/2 WA' ? b A)o ZECDEaA8t.f lAl6 /eA770AJS H/fLG ~DR7 Ec' TSO. 78 4 Go vs24GE u/As AaWisvnD E'EpEREMce 289027-2-Gee 6 132 PEAM sot?sno D4rx. t I EVALUATCRt 4.5. %:m M S -a NEL: I DATE: 4-2-97 DATE: /# T u*>'92 CONCUARENCE: LEVEL:. -// L-DATE: / ( PAGE[CF . T/A 19670C (NP 7,92)
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- v USN-50 ULTRASONIC CALIBR ATION NO.
TENNESSEE VALLEY AUTHORITY CALLBRATION DATA SilEET C-4 / F.3 2ROJECT: S O /d 9 UNff: 1" CAllBRATION DATE: L A9R '97 PROCEDURE:N-UT. / 9 REV.: 9 TC: M/4 CALIB RATION BLOCK NO.: UE N TEM P.: 70 F SIMULATOR ELOCK NO.: NO 9/7 INSTRUMENT: KRAMT GA M?- MODEI/rYPE: ld;M 50 TilERMOMETER SERIAL NO.: N/M SERAL NUMBER: E. M 1.53 COUPLANT: utTRAC4L BATCil: 99/15 HA RL TRANSDUCER MANUF.: 14.B AER.oTEC.H SERIAL NO.: Mo5955 A Notr. v s a r riC Arro N Sl7.E: /.O FREQUENCY: #115 Mite. BLOCK TYPE: BAAS SERIAL NO. WO'?/f CADLE TYPE: RC-- IW LENGTII: U NOMINAL ANGLE: O ACTUAL ANGLE: O INSTRUMENT SETTINGS ^ 100 REFLECTOR REFERENCE DATA ORIENTATION SENSmVffY SET g. AXIAL 35 5 ^ 8 ht CIRC ^ /4 w/4 P RU \\ N TOF(PEAK / FLANK): cAC ANGLE: OE I-D EG. L sw "'s N I y'3/9 7 DELAY: 0M uS 7ERO:.58'o a T N MATL VELOCITY:
- Mb uS RANCE: 3D g 4g D
REJECT: 0 PULSER: NON' E 20 DUAL: O ON [OFF 0 INITI AL CALIBR ATION DISPl.AY WIDTH 3 %3 INmALTIME: /380 FINALTIM E: /863 REF. REFLECTOR:Neen bH CAIN: 35 es VERIFICATION TlatES
- 1) ///5 0
- 2) /503 3Dd4 -Q AMPLITUDE:
60 % METAL PATH: U 5) of a - glA 50 C A 1 9 0 20 m VERTICAL I-II SIGNAL 2 SG gg yg 33 36 13 .go 33 jo ,5 -1 1 g, ATTENUATOR GAIN SET 6 12 SET + 12 SET +6 SIGNAL AMP. 80 % 32 to 43 16 to 24 20 % 64 to 96 40 % 64 to 96 K 40 2.o 80 70 REFER TO CALIDRATION REPORT
- /4 FOR PREVIOUS SATISFACIORY UNEARITY COMMENTS:
e WELD (s) EXAMINED: Rc_tJ-15 -/ 4 , tww IXAMINERM \\ LRVEL: IL ANII; M EXAMINE. wwA LEVEL-U--- DATE: [5/fo REVIEWED D Y: D? LEVEL:. E DATE: 'M N OF PAGE TV A 1957dD; (NP. 3 /93)
e':..: E-USN.50 ULTR ASONIC CALIBRATION NO. TENNESSEE VALLEY AUTIIORITY CALIBRATION C-NbT 3 3 DATA SilEET 80M UNIT: 1 CALIBRADON DATE: /-/-77 . ROJECT: PROCEDURE:N.UT. /9 REV.: 9 TC: CAlfBRATION BLOCK NO.: 6N P 7@ TEMP.: Ed *F SIMULATOR BLOCK NO.: 9909/7 INSTRUMENT: KDALCTY3AMEI? MODEL/rYPE: U.s Al 50 TilERMOMETER SERIAL NO.: E 2G,10(. SERAL NUMBER: E M 53 COUPLANT: um.AscL - BATCII: 94//15 TRANSDUCER MANUF.: K6 AWOM ANGLE VERiFIC ATION SERI AL NO.- E 15 2.13 UU SERIALNO. 78 9/9/. . 5' % /.o" FREQUENCY: 125 Milt BLOCK TYPE: SIZE: NOMINAL ANGLE: 96 ACTUAL ' ANGLE: 45a CABLE TYPE: Q.G L74 LENGTit: 71 INSTRUMENT SETTINGS REFLECTOR REFERENCE DATA 100 ORIENTATION SENSITIVrTY SET %T-AXIAL 35 /9 30 CIRC 35 /9 P \\ j TOF (PEAK / FLANK): t-EAR ANGLE: 95 UEG. [ 2.2 k DELAY: /2.59 uS ZERO /1. 37/ uS 60 g. \\ MATL VELOCTrY: /2% uS RANGE: 8 A 72. U 40 o 'h '3 T REJECT: O PULSER: NLM 3 ~ c %'Sf A 20 DUAL: C ON DOFF ~ INI'TI A L C ALIB R ATION O DISPLAY WIDTH
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AMPLITUDE: NO % METAL PATH: /OG - M i6)
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~ Q USN-50 ULTRASONIC CALIBR ATION NO. TENNESSEE VALLEY AUTIIORITY CALIBRATION Q fgy C
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/ROJECT: $Q/39 UNm. I-CALIBRATION DATE: N~/~97 r PROCEDURE: N.tR. N REV.: 9 TC: CALIBRATION BLOCK NO.: M-79 TEMP. N0 F INSTRUMEtm K Q. AWi tG.A M eJt., SIMULATOR BLOCK NO.: 7iO9/7 MODEL/ TYPE: LASM 5O TilERMOMETER SERIAL NO.: E D/Ola SERAL NUMBER: E 1N 3 53 COuPLANT: uLh6 BATCit: 99/25 TRANSDUCER MANUF.: K6 AEhntc.H SERIAL NO.: E 15115 ANGLE vFRTFIC ATION SIZE: _. 5 " Y /. o" FREQUENCY: A 13 Milt BLOCK TYPE: E1W SERIAL NO. 79'9/9/ CABLE TYPE: % 19'1 LENGTit: 7 '2. NOMINAL ANGLE: GO ACTUAL ANGLE: 00 INSTRUMENT SETTINGS 100 REFLECTOR REFERENCE DATA ORIENTATION SENSmVTTY SET 1/qy AXIAL 4/1 2c y CIRC '/ 2 2O ~ P \\ TOF (PEAK / FLANK): EAL ANGLE: 6O DEG. L' I h[ 1 \\ DELAY: /E/.20 uS ZERO: /d 30i us MATL VELOCfTY:./295 uS RANGE: F. 2D k' 'o MAi r 40
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W ER: MM E \\@ 20 N DUAL: ON 30FF N,,5/97 g INITI AL CALIB R ATION DISPLAY WIDTH E.21) INmALTIME: /E A0 FINAL TIME: /555 REF. REFLECTOR:be bN GAIN: 'lk dB VERIFICATION TIMES -1) /539
- 2) /555 3T
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/c .5 ATTENUATOR GAIN I SET 6 12 SET + 12 SET +6 SIGNAL AMP. 1 80 % 32to48 16to24 20 % 64 to 96 40 % 64 to 96 .c. K yo go yo go REFER TO CALIBRATION REPORT N/4-FOR PREVIOUS SAllSFACIORY LINEARITY COMMENTS: M T, 5/4 T - 9 d6 hunnet. WELD (s) EXAMINED: RC.td-t5 EoC h %tA. t h n 7[g XAMINER: e-LEVEL: ~~7T-AN!!: EXAMINER: b/ LEVEL 2 DATE: Nf/ r w up R EVIEWED B Y ' NDe LEVEL: ud-DATE: b8'M [ OF h PAGE TVA 196ND f(NP 8/92)......
( MANUAL UtiRASONIC REPORT NO. TENNESSEE VALLEY AUTHORRY VESSEL EXAMINATION R-4 9 a 3 DATA SHEET EXAM! NATION DATE: A AN D PROJECT: bQ N h UNIT: _I._ wp_4 ( START TIME:N 6 END TIME: s SYSTEM. haSust.s 2 R Lo REFERENCE-V SE t. ""9* WELD t.D"- Rc O-15 C AL. SHT. NO. ANGLE SCAN SEN5tTIVITY SURFACE TEMP: CONFIG: AJO'2.2.LE-To: h1 '1 5 " ' / o-v/ de N 9'b ' da PROCEDURE: N-UT-I9 REV. 9 TC: N/4 PYRO. SERIAL NO. E 2/*/0 G I [ GO*__ SG dB .h RESULTS: (SCAN NUMBER) 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 'U 18 19 I #lA-. /* A/ A/ ~#fA- ~ ~ INDICATION RECORDED (Y/N) b AM MA ^ IND MAX $CAN HO AMP HO ANG Mp1 W1 L1 Mp1 WI L1 Mp1 W1 L1 l Mp W L Mp2 W2 L2 Mp2 W2 L2 Mp2 W2 L2 4 N N + N N N x fgh N ~ N N ',5 .r N_ l N nE,m.Um,1AuONS. no scm e s (som s,A A tt se u s b ro b a ss mh weus ca oo% looist Leow /oo he.cm demtr wbtumMs. hmens u3 cnmt. o*, W a b rue. Go WMS. tr-A' j ( r to i / X ~~ Exu.uNeR. d N d b teveu 1L neviewEo BY: r%- MS//M 7 i M %dM teveu % m>ee w-De 7 5 FP g,os.s%g mm,Nm u/ ( [ TVA M,5?OQ (NP 7m)
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Request For Relief 1-ISI-10 1 Executive Summary: This request for relief addresses circumferential pressure retaining welds in the reactor coolant system. The design configuration and materials used in the l fabrication of the subject piping welds l precludes a 100% ultrasonic examination of l the required volume for the following l welds: RC-06 (pipe elbow to pump casing) and RC-07 (pump casing to pipe). These physical examination limitations occur when the 1989 code examination requirements are applied in areas of components constructed and fabricated to f early plant physical designs. Based on i the date of SQN's construction permit l (May 27, 1970), SQN is exempt from code l requirements for examination access as l allowed in 10 CFR 50.55a(g) (4). l A liquid penetrant surface examination was l performed on 100% of the subject welds. An ultrasonic examination was performed on accessible areas to the maximum extent practical, given the physical limitations l and materials of the subject welds. The design configuration and materials used L limited ultrasonic examination to I approximately 75% of Weld RC-06 and approximately 75% of Weld RC-07. It was concluded that performance of an ultrasonic examination of essentially 100% of the circumferential pressure retaining welds, RC-06 and RC-07, would be impractical. A surface examination and the maximum extent practical ultrasonic examination of the subject welds provides reasonable assurance of an acceptable level of quality and safety because the information and data obtained from the 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 requestec that relief be granted for the second l
inspection interval. l 1-ISI-10 El-1
v Unit: 1 System: Reactor Coolant - System 68 ~ Components: Two Piping Circumferential Pressure Retaining Uelds ASME Code Class: ASME Code Class 1 (Equivalent) Section XI Edition: 198 9; Edit ion Code Table: IWB-2500-1 Examination Category: B-J,7 Pressure Retaining Welds In Piping i Examination Item. Ndmber: B9.11,, Circumferential Welds Nominal Pipe ' -
- 61-zE 'M Inches or Larger
.c Code Requirement: ASMElSection XI, Table IWB-2500-1, Examination Category B-J, Item No. 89.11 Surface And Volumetric Examinations Code Requirement From Which Relief Is Requested: Voluffetric Examination Coverage List Of Items Associated With The Relief Request: RC-06, Piping To Reactor Coolant Pump Circumferential Weld RC-Oln Piping To Reactor Coolant Pump Circ'smferential Weld Basis for Relief: The design configuration and mate. rials used in the fabrication of the reactor coolant pump and the reactor coolant . piping preclude an ultrasonic examination of the required volume of pressure re.taicing circumferential Welds RC-06 and RC-07. The design configuration and materials limit ultrasonic examination to apprpsimately 75% of Weld RC-06 and approximatel,y 75% of Weld RC-07. Alternative Examinations: In lieu of the code required 100% ultrasonic examination, an ultrasonic examination was performed og accessible areas to the maximum extent practical, given the physical limitations of the subject welds. A surface examination (PT) of 100% of Welds RC-06 and RC-07 was also f. performed. Refer to Attachment 1 for Examination Data Reports. 1-ISI-10 El-2
m. . _._. _ - _. _.. _. ~. -. _. _.. l [ Justification For The Granting Of Relief: (1) The design configuration and materials used in the fabrication of the subject-piping welds preclude ultrasonic examination of essentially 100% of the required examination volume. In order to examine the welds in accordance with the code requirement, the reactor coolant pump would require extensive redesign along with changing the pump and piping material. ~ The weld joint detail for Weld RC-06 consists of a pipe elbow welded to a l pump casing. The pipe elbow is static l cast CF8M material welded to a static l cast CF8M material pump casing. The weld joint detail for Weld RC-07 consists of a pump casing to pipe ( w-l configuration. The pump is static cast CF8M material welded to l centrifugal cast CF8M materia,1 piping. I The examination is limited due to the design configuration and the effects of the anisotropic coarse grain structure of cast stainless material L and the weld joint configuration, which limits search unit contact and movement. Total ultrasonic examination coverage for RC-06 and RC-07 was approximately 75% of the required code coverage for l' each weld. Due to the anisotropic coarse grain structure of cast stainless CF8M materials, the examination was limited to the 1/2 vee technique using refracted longitudinal waves. Circumferential scans for both welds were unlimited. Both welds received 100% coverage from one side I scanning in the axial direction with the sound beam directed toward the pump. No scans were performed from I the pump side in the axial direction i due to the pump taper interference; l therefore, 0% coverage was obtained from this direction. It is reasonable to assume that circumferential flaws would be detected-to the degree comparable with industry standards. (2) Radiographic examination, as an alternate volumetric examination method, was determined to be impractical due the material thickness (approximately 3 inches) and the pipe 1-ISI-10 El-3 l
i l being filled with water. Realignment l of the system to drain all water would~ L substantially increase radiation levels. (3) Westinghouse plants have no history of i pipe cracking failure in the reactor coolant primary loop. For stress corrosion cracking (SCC) to occur, the following tnree conditions must exist simultaneously: high tensile l stresses, a susceptible ~ material, and a corrosive environment. The potential for SCC is' minimized in Westinghouse PWR's by material selection and prevention of a corrosive environment (reference Westinghouse RCS Piping Flawbase i Handbook, WCAP-13670). j (4) A percentage sampling approach provided by the ASME Section XI Code, in combination with examinations performed on similar items, provides reasonable assurance that significant degradation, if present, would have been detected. Performance of an ultrasonic volumetric examination of essentially 100% of the required volume of pressure retaining circumferential Welds RC-06 and RC-07 in the reactor coolant main loop piping would be impractical. As previously discussed, TVA determined that it would be impractical to attempt other volumetric examinations in order to increase examination coverage. The surface examination of 100% of the weld area and adjacent metal and maximum extent practical ultrasonic examination of the subject welds provides reasonable assurance of an acceptable level of' quality and safety. Significant degradation, if present, would have been detected during the ultrasonic examination and the surface examination that was performed on the subject welds. As a result, reasonable assurance of operational readiness has been provided. 1-ISI-10 El-4
Therefore, pursuant to 10 CFR
- 50. 55a (g) (5) (iii), it is requested that relief be granted for the second~
inspection interval. Implementation Schedule: This request for relief is applicable to l the second inspection interval for SQN Unit 1. Welds RC-06 and RC-07 were examined during the first period of SON's second 10-year inspection interval. I
References:
- Examination Data Reports:
R-6824, R-6826, R-6836, and R-6837. - ISI Program Drawings: l ISI-0325-C-02, Revision 2 and ISI-0482-C-01, Revision 1. I l l 1 l l. i 1-ISI-10 El-5
. ATTACHMENT 1 EXAMINATION DATA REPORTS j R-6824 R-6826 R-6836 R-6837 I i s I i 1 t i 4 F r a_, m.. -m~ e
- -r*
.._ y i j-1.4., 7. 6E! m v t-RECORD OF TENNESSEE VALLEY AUTHORITY LIQUID PENETRANT REPORT NO. EXAMINATION R-4W . ROfECT: __5 Gdl A UNIT: l,! b EXAMINATION DATE: 03 -J(a - 4 7 l SYSTEM: RX STARTmtE /sW l WELD 1COMPONENTI.D. : R C. - O[O END nME: /037 EXAM SURFACE: ID 0 oD CONFIO.: 8/bou) _TO Pom o ORIGIN ^L Ex^ MIN ^TIox 3 REEx^MINATtoN O PROCEDURE:N.PT. ' 3 REY.: I3 TC: 7 7-/ REFERENCE DRAWING NO._yg-M8A -C, 3//, ASME SECrlONI ASME SECTION XI CODECLASS/CATEOORY I3-1 / / ASME SECTIONIII ANSIB3Lt C ACCEI"TANCE CRrrERIA ASMESECTIONVIII O ANStB3L O N.er.9 APeENDix A O A<eENDtxB B AWS D1.1 OTHER A//A O oTHER e//^ METHOD OF EXAMINATION ~ METHOD PENETRANT MATERIALS O WATER. WASHABLE FLUORESCENT DYE /I h 6 0 F !U Y ! 4(L BRAND NAME: S O POST. EMULSIFIABLE FLUORESCENT DYEPENETRANTTYPE:_4 BATCH NO. 93AcaK ~ O SOLVENT. REMOVABLE FLUORESCENT DYEREMOVERTYPE: 6 EC -b B ATCH NO.-jsAO3k' O WATER. WASHABLE VISIBLE DYE DEVELOPER TYPE: dN~ B ATCH NO. b b O POST. EMULSIFIABLE VISIBLE DYE @ SOLVENTREMOVEABLE VISIBLE DYE N/A ER CAL DUE DATE: A//d PARTTEMPERATURE: 3I
- F PYROMETER S/N: 3 763IO AL. DATE DUE:. b 'l347 RESULTS OF EXAMINATION:
SATISFACTORY @ UNSATISFACTORY O Not No.: e>/A EXPLANATION OF UNS ATISFACTORY RESULTS: A/[A l l REMARKS / LSIITATIONS: Alb U (AMINER : be/A LEVEL: [L. ANU 7d EXAMINER : /[o -fr/ ./ LEVEL: 7E DATE: $ f / REYlEWF.D BY: _ d LEVELF M DATE: D c PAGE_.LAFL h g n,ww
%5: &h RECORD OF REPORT NO. TENNESSEE VALLEY AUTHORITY LIQUID PENETRANT R-WE EXAMINATION s / b$ ~3'27" ?? .db1ECT: be90&V O TT: EXANHNAnON DATE: 8h&/6 / Co/d d [ STARTTIME: 0920 END TIME : /0/O SYSTEM : k(- O 7 EXAM SURFACE: ID OD WELD / COMPONENT I.D.
- TO p!? b ORIGINALEXANENAUON % REEXAMINATION O pMD CONFIO.:
PROCEDURE: NET. Y REY/3 TC: i7' / REFERENCE DRAWINO NO..T_-O @ -C-C[ C E CLASS / CATEGORY II- / ASME SECTIONI O ASME SEcTION xI-ACCEPTANCE CRITERIA ~ ASME SECTION III O ANSiB3tg ASME SECTION VIH C ANSI B31.7 C N-PT-9 APPENDIX A APPENDDC B M/A AM AWS DI.1 O OTHEn OTHER METHOD OF EXAMINATION METHOD PENETRANT MATERIALS Ak NI [M dI WATER WASHABLE FLUORESCENT DYE BRAND NAME: 7MO-2/( bNb ~0P B ATCH NO. POST EMULSIFIABLE bOORESCENT DYE PENETRANTTYPE: OM SOLVENT. REMOVABLE FLUORESCENT DYE R'EMOVER TYPE: 3kC*O B ATCH NO. / DEVELOPER TYPE: TCH NO. O WATER. WASHABLE ViSRLE DYE O POST-EMULSIFIABL$ VISIBLE DYE SOLVENT REMOVEABLE VISIBLE DYE ES - CAL. DUE DATE: O E7 $3 G /' CAL.,DATE DUE: h ~ /) ~ 7[ F PYROMETER S/N: PART TEMPERATURE: RESULTS OF EXAMINATION: SATISFACTORY 7 UNSATISFACTORY ] NOI NO.: / ENPLANATION OF UNS ATISFACTORY RESULTS: &C{ GEMARKS / LIMITAT!ONS: AlOkG/fh + E d'. b b 8 kJ P T t c n d /l( ) 1 Y LEVEL: // t'AMINER : LEVEL: DATE: I f'? EXAMINERbmI d.dwww REviEwEak[j.4'Mg LEvE1 8 7/M g,cging1 oATE:
- - ~. g5:3 Q ~ 'c v EXAMINATION REPORT NO. TENNESSEE VALLEY AUTHORITY
SUMMARY
AND y-gg3g RESOLUTION SHEET /II EXAMINER fAIC@EL 5. Sesscmstv: I . Pacf2CT: SEGOOYAN UNm .I-SYSTEM: 2N EXAMINER e4 /A LV: n /A / wEto i.o.: PO-07 EXAMINER N [ LV: g/ Y !b CONFIG: ) d M/ 4 TO: 18 8 EXAMINER - LV: s 1 FLOW CAL sur NO'S: /) [_ - PROCEDURE N-UTO.38,REV.: 7 TC: % 08 fyp h0E METHCO-BDT PT MT VT ~794(6 '2f Po27~' CD AJ7'M /AK ~7~NE *n/? 771 assoc /A77=D 1AI/rW*:~7~)/2 AnnsJuAL_. (JLTRA50s) /c 2XAM/A)AT70Al 6f u/sto 2& 07. A A772 bri_Linerre. CAST sint>JLEss pump rc 'D pe coufiGuennc>). Tis Eygirtingrpea) i R A< PE2fo2MED >Al &c'n204xlcd W r rat N'- uT*-33 EsVL5los) 7.70-76-68, I ~70 N/MEr" 77JS 2 E Qc)/2E M MA/73 M AR And SEc77ew x l. 4 ~77/d LAJE LD a/A_s EXAM >^)sa 05/AJG A 4W Eft-R w/ to t 6/JG/77/D/ A}A L Lt)A\\lf, b de ra -r%e cOAlf/GU2RTDA) of 71Jn POMP,, Alo AMIAL 60Ad (cc A Al 3 )' u)M 'Psefcemen renvy r;JF uhiesAW1 side \\ kW' CF ~)~Hf LA!Gl_.0. SeAU 4 g/As <*.o AJ77 Al Us) Acro.s_s 17sc u/ELO ~ ~T5 lA)ceeASE CoVERAGF. A)6 2fCC320ARLG / A)/]/G A770A/S WE/'E Dt:icGrc0' \\ 75% covsenew wox eaTnaico ~ .W', ^ h ANil EVALUATORe4,3. 5essogs w- ' c4EL: T DATE: _3 - Z7~ #77 / 8
- O 7' CONCURRENCE:
LEVEL: DATE: PAGE 1 CF_h_, TVA 19670C (NP 7,92)
i g',.r = USN-50 ULTRASONIC CALIBRATION NO. . -TENNESSEE VALLEY AUTHORITY CALIBRATLON Y ' # O b h3 DATA SIIEET l'ROIECr:5EGCOVA M UNIT: _. d._ /C Y CALIBRATION DATE: 3 - d 7 - 9 ~/ / PROCEDURE: N.UT.R REY.: 7 TC: % -O 8 CALIBRATION BLOCK NO.: 69-G3 TEM P.: 8Q F SIMULATOR BLOCK No.: 790398 INSTRUME.Afr: h'24 U7-@A/V/66 MODEI/ TYPE: Us5 Al -50 THERMOMETER SERIAL NO.:573'3CW B /c /97 SERAL NUMBER: E-2@ s'3 COUPLANT:vcr24GEC7 BATCH: 9 # / 2 5 TRANSDUCER MANUF.: dM ANGLE VERTFIC ATION SERI AL NO.: M//82O / /4 / / B / 9 S!7.E: _ FREQUENCY: />d Mlis BLOCK TYPE: //IM SERIAL NO. 79 I 53 6 /.0 " 4 [' - ACTUAL ANGLE: 45* CABLE TYPE: 243- / 7#/ LENCMI: /d O ~ NOMINAL ANGLE: INSTRUMENT SETTINGS REFLECTOR REFERENCE DATA 100 l l l ORIENTATION SENSTTIVITY SET l AXIAL (fS / co g CIRC aA N/A U {^l qe l l TOF (PEAK / FLANK):964k' ANGLE: 4[ DEG. P e L / I l l DELAY: 53d uS 7.ERO: /7 Gdfo uS '60 l l I M AT L VELOCITY:,23 9b u$ RANCE: /O.0 l l -l REJECT: O PUL5ER: 2d4 D DUAL: F ON h OFF 20 l l I INITI AL CALIBR ATION l l l l DISPC.AY %TUTH INTTIALTIME: O 90/ FINAL TIME: / a-Q A ~ VERIFICATION TIMES REF. REFLECTOR: 8 2AhlUS CACN: lO dB 1)/oa8
- 2) / 0 6 5
- 3) e//
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- 6) NA
- 7) /^
l8) /^ SicNAL t I tm l 90 so 70 60 50 40 30 20 to C ygg77 egg L II SIGNAL 2 l50 lM l@ 3.s-iJo as-ao , is-fo l s' CAIN SET I 6 12 l SET I + 12 SET +6 ATTENUATOR SIGNAL AMP. 30 % 32 to 43 16to24 l 20 % ) 64to96 40 %~ 1 64 to 96 K 39 16 l l 6'L i 61 REFER TO CALIB R ATION REl' ORT N /A FOR l'REVIOUS S ATISFACI'ORY LINEARITY j I COMMENTS: COA /TOO/26/) -S A/0 6.5 WELD (s) EXAMINED: 2 C - O ~~/ - a/ a/ l 4 4 ExAwNEResssemsttEE-ann: -yBL t.EvEu _u-ExAmNER: sA LEvEu ~ /A DATE: 5/g/5 7 LEvEn 2rL-DATE: 3M ? PAGE d. CF [ WTM2W$ nvmw o ny:
'^" ^^ .u.--.- ~ - ~. ". = (- ~ ~ ~ ' USN-50 ULTRASONIC CALIB R ATION NO. rENNESSEE VALLEY AUTHORITY CALIBRATION k-Ib$ DATA SHEET ~ / _1,/( ( CALIGRATION DATE: 3 - B 7-97 PROJECT: "5Eo o oy A 4 ' UNm P ROCEDURE: N.llT.31 REV.: 7 TC:_96 -O O CALIBRATION BLOCK NO.: SO-6 3 TEMP.: @ F SIMULATOR BLOCK NO: 790396 M A(.TT N ANigg INSTRUMENT: O,5 M-TC) T1IERMOMETER SERIAL NO.:95M4 6/i3 /97 1 ~ MODEI./ TYPE: N COUPLANT: (M466CIB ATCH: 9 #/2 7 ' b SERAL NUMB ER: E 2 4 A $~5 TRAN5DUCER MANUF.: OA ANGLE VERTFIC ATION SERIAL NO.: N //6/8 / Al // A /7 //d SERIAL NO. 79/8SB II FREQUENCY: /.O MII: BLOCK TYPE: Sl7.E: -/ 7Y . LENGTil /a0 NOMINAL ANGLE ' 4 ACTUAL ANGLE: W CABLE TYPE: INSTRUMENT SETTINCS ' REFLECTOR REFERENCE DATA icd l ..l l l OR.IDTATION SENSITIVITY SET kid. M l l l CIRC I 5'S I /8 A ga y lp l l l ll U[ D EC. TOF (PEAK / FLANK): Ak ANGLE: J/ l\\]Sg l l P / 5 Y6 Y u.5 i I Mlf l l'\\ j j ggtgy; jg,1 g us 7.ERO: 60 dl l d' $MA Ma-L yELOCrry:,93/ 9 uS RANCE: b.3d/ pgt3gg; QdA L D. ggygg7; O g E II i 1-l DUAL: 70N OFF 20 l N l INITI AL C ALIB R ATIO N
- 22b DISPLAY WIDTH (s. SC i INTTIALTIME: C 914 FINAL TIME:
VEIUFICATION TIMES REF. REFLECTOR: O 40f US _ CADf: d/ dB I) / o rg
- 2) f//s' l3) 3; /
9 a/ g g g 4 gg fg g) 4 AM PLITUDE: b % METAL PATH: d.CCG ~ srCNAL i Iico l 90 I so 70 60 l 50 40 l 30 l 20 to C ygg7c,g a/4
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- /4
) s/A ' RE ERTO CALD3 RATION REPORT 4 /A FOR PREVIOUS SATISFACI'ORY LINEARITY COMMDT3: CC 0772/12FA
- Wd65 WELD (s) E'GMINED
Ed-O7 N pll b IMfd7 E A g . L2 VEL: N/A DATE: a /A ( E;GMINER: ~.
l c,.2 :,_ ' ~ ' MANU AL ULTRASONIC REPORT NO. TENNESSEE VALLEY AUTilORITY PIPING EX AMINATION R- / Q [ DATA SIIEET 3 47-9"I ROJECT : M6COoYA)/ _ UNIT : 1 EXAMINATION DATE: SYSTEM : M STARTTIME: /030 _ ENDTIME : // /o WELD LD. ; 2d. 07 EXAM SURFACE: ID DD CONF 10.: Vf8 . TO __ /85 MATERIALTYPE: CS SS CSCL M CSS h SURFACETEMP: 93
- F PYRO NO.:S g73(oY B / /3 /9 7 FLOW CAUBRATION SIIEET NO.
C-N /A C' g/A s PROCEDURE: N.UT.M REV.: 7 TC: j6-06 __ EXAMlNATION ANGLE Nfl. DEG. 45*L DEG Wo
REFERENCE:
M6CA ( CIRC. SCAN SENSITIVITY 6g da y/4 an AXIAL SCAN SENSITIVITY g/A dB [p2 dB MAX EXAM INDICATION !NFORMATION: NOM. L(in)FROM REF, AT MAX AMP IND 3 l$ AE NO. L1 LMu. L2 W MAX MP MAX D M AX g Ac i _-/ Y Y$l. V ,) 7A 6 ff'4. V 7A / G Nst. v _/ / / / /- 1 r} ,7A / / p / / / No MANI ?d'ffo2M4h #EnW1 Vutv1P Sins of t</6? tL REMARKSILIMITATIONS: a n% - 30 % beexc nous o=mc. scannan Aneem -me .aaw A.5~E6 1Al21 h 17AJS <A wNER m
- M L tsyst:
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,i l 3 1
- 7
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cx FXAMINATION REPORT NO. ) 7 TENNESSEE VALLEY AUTHORITY
SUMMARY
AND RESOLUTION SHEET / //dA/4R 5.5Es.sems Lv: E PROJECT: .5 ECOo \\/AM UNIT: .I O EXAMINER: / N [A SYSTEM: 2X EXAMINER-N /A LV;. 1 WELD l.D.: 2d- (3 b EXAMINER: N/ LV: M/ !b CONFIG: 6/30 W TO-UN7 A EXAMINER: LV: FLOW CAL SHT NO'S: /7 / / PROCEDURE: N-Q j7~ REV.: 7 TC: 7[,-c8 fjf g NDE METHOO: @UT PT MT VT
- TN/S 22P627-Gos/rH/A)S THE ~D4771 Asso eiA 72B wmJ yn s urnduRL.
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- D oe ro r7/E cos> pig or Arrox) of rHe PUMP; Alo A v> AL L snAu (ScAAI 4 )
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..n...... - , h :. - a-,., L4., - ~ _ _. (y USN 50 ULTRASONIC CALIBRATION NO. TENNESSEE VALLEY AUTHORITY CALIBRATION k- (((( DATA SIIEET .1/N CAUBRAEON DATE: c3 - d 7-9 7 PROJECT: $6 coo Y4 N UNIT: / PROCEDURE:N.UT. 33 REY.:' 7 TC: 9G-O8. CAUBRATION BLOCK NO.: 50 - GY HMP.:32 F SIMULATOR BLOCK NO2 790398 NAU7-MN yJ6R _ INSTRUMENT:' L/SM-SD Ti!ERMOMETER SERIAL NO; S753M 8 //3h7 N MODEI/ TYPE: SERAL NUMBER: E MS 63 COUPLANT: Otr7P4ML II' BATCH: 94/36 S!IEAR h LONG. [RL EXAM TYPE: TRANSDUCER MANUF.: dd ANGLE VF,RIFIC ATION SERIAL MO.: MI/A/B / N // A/ 7 ' S(7.E: /.O" k ' FREQUENCY: /. O Mit: BLCCKTYPE: /IN SERIAL No. 79 / 5'38 CABLETY?E: IG-/74 LENGn{: /20 NOMINAL ANGLE: NI ACTUAL ANGLE: MT INSTRUMENT SETTINGS DAC REFLECTOR REFERENCE DATA gcf ORIENTATION SENSiHVITY SET l 3 j AXIAL g /A, xt /A (p { %l~ d.12@ l i ~ CIRC ) 57 I I7 M / '] l l TOF (PEAX / FLANK): NAM ANGLE: 4Y DEC. gg-g /l {q3pz. }j l l DELAY: /3.18 c3 ' ZERO: 13. @o4 uS 60 J[ f l I l MAM. VELOCITY:. '2 3 /8 uS RANGE: 8,218 \\ ggygc7; o g put337; 34t,, D e l I N 20 ~ DUAL: T ON h OFF' l l) INITI AL C ALIBR ATION DISPLAY WIUTH 8, & G B !NTnALTIME: 0 9 S'l FINAL TIME: I72.0 VERIFICATION TIMES REF. REFLECTOR: 2" ?_4bu% GAIN: 4% da
- 1) o 94/O
- 2) / 0 o5 l3) aj
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- 8) /A AMPLITUDE:
80 s METALPAra: 4.03 SIGNAL 1 100 90 so j 70 l 60 50 40 l 30 20 la C ygg7c3g 50 45 40 l 35 l 33 25 20 l 15 lo I5_ b II StGNAL2 1 -t F CAIN SET 6 l 12 SET + 12 SET- +6 N. C SIGNAL AMP. 80 % 32:a43 l 16 to 24 20 % I 64 to H 40 % 64 to 96 ATTENUATOR g 3.8 ) 18 i I 63 l 6i REFER TO CALIBRATION REPORT //A _ FOR PREVIOUS S ATISFAct'ORY UNEARITY COMMENTS: dCA/700fE/3 5 Mods WELD (s) EXAMINED: JC-N a/ a/ 4 A ANII: 7-g1 EXAMINER:Msse5 mss bI, b - LEVEO u-m 54r/n uh 0 ATE: A tEvEO ExAutNEx: -=r -_ _m x<, m. n _ q y L ^ ^
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- 2) / O p. 5' l3) 4/
d) 4/ AMPLITUDE: '7 0 % METAL PATII: M /58 *
- 5) N/A
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/^ l3) /A C SIGNAL 1 m 90 l 80 70 m 50 40 30 20 10 /[A N/ NM
- [A l /# fA VERTICAL 50 YA l N/g i M/
Nd l / /A u / jA b [I SIGNAL 2
- I F
CA!N SET 6 12 SET
- 12 SET i
+6 h, c' ATTENUATOR S'CNAL AMP. 80 % 32e43 16to24 l 20 % 64 m 96 40 % l 64to96 g 1 N /A ) N/A } l N /A l l N/A REFERTO CALIBRATION REPORT W / A. FOR PREV (OUS SATISFACI'ORY LINEARITY l l COMMENTS: ('o AN U/240.5'Ald6.5 WELO(s) EXAMINED: /2 C - O Co M/ HI /A '/3 ExAutntRM.swasitd10C -741 .:vEu T ANu: 54s/e a4 oATE: ~A LEvEu ExA asER. em nM .m.32 7y n gy (
. r '. !N.f: Y L' ~ MANUAL ULTRASONIC REPORT NO. TENNESSEE VALLEY A UTilORITY PIPING EXAMINATION DATA SIIEET N-II3 UNIT: 1 ___.3 -d 7-9 7 ' ROJECT:g6000 YAM EX AMINATION DATE: SYSTEM : MN START"DME: 09YI END TIME : /010 WELD 1.D. : D -Ob EXAM SURFACE: ID 70D CONFIC.: MQM TO UV/8 MATERIALTYPE: CS SS CSCL @ CSS h SURFACE TEMP: 8 3
- F PYRO NO.: S753(cY FLOW 8 /m /97 -
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REFERENCE:
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,e ~) -Ul PROJECT:.5EcodVA d SYSTEMi T2 X REPORT NO.: I,/C F WELD 'NO.: 26 -OG ~ fA7
- Office 'of Nuclear Power Unit:
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ENCLOSURE 2 SEQUOYAH NUCLEAR PLANT UNIT 2 ASME REQUESTS FOR RELIEF 2-ISI-8, 2-ISI-9, AND 2-ISI-10 l i i i 4 4 a
l Request For Relief 2-ISI-P 1 Executive Summary: This request for relief addresses a branch pipe connection weld in the safety injection system piping. The design configuration and materials used in the fabrication of the weld precludes a 100% ultrasonic examination of the required volume for Weld SIW-07 (10-inch branch connection welded to the outside diameter of 27.5-inch large bore piping). These physical examination limitations occur when the 1989 code examination requirements are applied in areas of components constructed and fabricated to early plant physical designs. Based on the date of SQN's construction permit (May 27, 1970), SQN is exempt from code requirements for examination access as allowed in 10 CFR 50.55a (g) (4). A liquid penetrant surface examination of essentially 100% of the weld was performed. An ultrasonic examination was performed on accessible areas to the maximum extent practical, given the physical limitations of the subject weld. The design configuration limits ultrasonic examination to approximately 63% of the weld. It is concluded that performance of an ultrasonic examination of essentially 100% of branch pipe connection Weld SIW-07 would be impractical. The performance of the surface examination, and the maximum extent practical ultrasonic examination of the subject weld, provides reasonable assurance of an acceptable level of quality and safety because the information and data obtained from the volume examined provides sufficient information to judge the overall integrity of the weld. Therefore, pursuant to 10 CFR
- 50. 55a (g) ( 5) (iii), it is requested that relief be granted for the second inspection interval.
Unit: 2 System: Safety Injection - System 63 2-ISI-8 E2-1
s Components: One Pressure Retaining Branch Pipe Weld ASME Code Class: ASME Code Class.1 (Equivalent) ~ Section XI Edition: 1989 Edition l' Code Table: IWB-2500-1 Examination Category: B-J, Pressure Retaining Welds In Piping Examination Item Number: B9.31, Branch Pipe Connection Welds, Nominal Pipe Size 4 Inches Or Larger Code Requirement: ASME Section XI, Table IWB-2500-1, Examination Category B-J, Item No. 89.31, Surface and Volumetric Examinations Code Requirement From Which Relief Is Requested: Volumetric Examination Coverage List Of Items Associated With The Relief Request: -SIW-07, Branch Pipe Connection Weld Basis for Relief: The design configuration and materials used in fabrication of the safety injection branch piping Weld SIW-07 precludes a volumetric ultrasonic examination of the requiredivolume. The design configuration and material limits the ultrasonic examination to approximately 63% of Weld SIW-07. Alternative Examinations: In lieu of the code required 100% ultrasonic examination,.an ultrasonic examination was performed on accessible areas to the maximum extent practical, given the physical limitations of the subject weld. A surface examination (PT) of essentially 100% of the weld was also performed. Refer to Attachment 1 for the Examination Data Reports. Justification For The Granting Of Relief: (1) The design configuration and materials used in fabrication of Weld SIW-07 precludes ultrasonic examination of essentially 100% of the required examination volume. In order to examine the weld in accordance with ISI-8. E2-2
the code requirement, the branch connection would require extensive H redesign and changing of piping material. The weld joint detail for Weld SIW-07 ] is a branch connection welded to a large bore piping configuration with the full penetration weld located in the branch connection (i.e., a branch connection welded to the outside diameter of the large bore reactor coolant system piping). The branch connection is stainless steel material and the large bore reactor coolant system pipe is centrifugal cast CF8M material (Cold Leg Loop #1 piping). The' ultrasonic volumetric examination is limited due to the effects of the anisotropic coarse grain structure of cast stainless material of the large bore piping and the weld joint configuration, which limits search unit contact and movement on the branch connection side, i The anisotropic coarse grain structure of centrifugal cast CF8M material, and the examination limitation parameters associated with refracted longitudinal waves, prevented a meaningful scan from the large bore piping side (main loop piping). Weld SIW-07 received 100% of the required coverage with the axial scans from the branch connection side utilizing both 45 shear waves and 60 refracted longitudinal waves. These examinations provide reasonable assurance that circumferential flaws would be detected. Scans for flaws f-located transverse to the weld were limited due to the weld joint configuration that limited search unit contact and movement. A 31% required coverage was achieved for detection of I transverse oriented flaws. The total ultrasonic examination coverage for SIW-07 was approximately 63% of the I code required volume. t 3 (2) Radiographic examination, as an alternative volumetric examination method, was determined to be impractical due to restricted access. 4 2-ISI-8 E2-3
Also, the wide variation in component thickness and joint configuration does-j not make radiography an amenable option to increase code required coverage. (3) A percentage sampling approach provided by the ASME Section XI Code, in combination with examinations performed on similar items, provides reasonable assurance that significant degradation, if present, would have been detected. Performance of an ultrasonic i volumetric examination of essentially 100% of the required volume of the pressure retaining branch connection j Weld SIW-07 would be impractical. As previously discussed, TVA determined that it would be impractical to I attempt other volumetric examinations in order to increase examination coverage. The surface examination of '100% of the weld, adjacent metal, and the maximum extent practical ultrasonic examination of the subject weld, provides reasonable assurance of an acceptable level of quality and safety. Significant degradation, if present, would have been detected l during the ultrasonic examination and the surface examination that was fl performed on the subjec't weld. As a l result, assurance of structural integrity for this weld is provided by the alternative examinations that were performed. l ( Therefore, pursuant to 10 CFR
- 50. 55a (g) (5) (iii), it is recommended that relief be granted for the second inspection interval.
Implementation Schedule: This request for relief is applicable to the second inspection interval for SQN Unit 2. Weld SIW-07 was examined during the first period of the second 10-year inspection interval.
References:
- Examination Data Reports:
R-5568 and R-5584. ISI Program Drawing: ISI-0002-C-05, Revision 10. 4 '2-ISI-8 E2-4
. _ _ _ _ _ _. - _ _ _ _.... -.. _. ~ _ _ _. _ _ -.... _ _ _ _ _ _ _ _... _ _.. _ _. _ _. _. i e s 4-4 4 ATTACHMENT 1 4 EXAMINATION DATA REPORTS i a R-5568 i -R-5584 i, 4 t I i, i 4 J. J {. 1 4 e
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REFERENCE:
k oF E~LD EXAMINATION ANGLE 4c;" 36* DEG. (86 (8ed)EC: Lo
REFERENCE:
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- NOM, INDICATION INFORMATION:
N O. L1 LMu L2 W MAX MP MAX D M AX % AC 31 3 GO' 6 / M E.1 3 / d at. V 912.1 3 e6 ozi. 5 38*6 / g e_ t /he &m A g 6 sc6 v' ue.t L _<c a m a / / / / / / / / / / A / REMARKS / LIMITATIONS: No w Eu 6En /6ma 4 nIerr rr'eI\\ 4. hrw Te~ h oF b rkinJc Atlu bT bvAietpfs d fE~CL k,~rbur*Y10c aTur.E-AMD "rt d 4 OC b [c r heu2Ab N. "N 2b usr I"I> e. O[cte., b A G CdE ~I D iD C >>-/ XAMINER : LEVEL: E-ANil .XAMINER : 54 -sN d LEVEL: I [ 0MW LEVEL: 6 DATE: 430' 6 PAGE[OF p REVIEWED BY: o e TVA 10@7@ h
.Y I... m.:u V/ALL THICKNESS ""a7 m: TVA I'FN PROFILE SHEET PROJECT: enP weto go; g g _ g,7 UNIT: 2 SYSTEM:_ _/.o'5 616 f Record Thickness Measurements As Wold . Wold Ed2e Indicated, including Weld Width, Cen terlin e Edge.To Edge At 0* (: 2.5" de 2.5*
- I I
i e e Po sitiort 0* 90* 18C* 270* b } 9 / & 36 gg ,p [ Side l Side / 1 2 s#2 \\ b
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h / A 5 t, fo.O" CROWN HEIGHT: N DIAMETER: 3' CROWN WIDTH: WELD LENGTH: i.d 5.8 = 45' .4 18 Y / / \\b / \\ l \\' / - 5.. l rh e ut r.t. \\ / e g \\ 1 Joe'$ 6ue:rM4~ alm 1 FLc4.0 447W54w uSAM d'd*4't, g /g w & 5 sec. No M 4 ouc m~ 64-5 M b A o f JJ ET.,D. ,, py g b ExAumsn._ psviews0 sy DATE: 8/.3/fl LEVEU 7 DATE: h* LEVEL: " [ bD OAYE: Y 6 PACE OF g.gos 999..
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TVA PitOJecr: 5 0 tJ svsreu: sI ItEPOltT NO.: Unit: 2-WELD NO.: SIW-07 R _5 G d[ Orrice of Nuclear Power l s e u 3 c,w i k // w (,s)(vi)(vi) =.ioi2s r-.' es,,,..=.ioiz r v 19. g = v. 99 ;a Ewnn k<-s= Gs)C Ac) =. een' nr -a,. ge x yp.2 = v.r, >', w ' s = ~ s % ~ ~~ + c c. sj & < s),. o r a [.,., _ p,gyy,,9,,,,,,,a ,w SCAud 3 tow'es % = fou o E38.T & = saa - Y" .s-a a -l o <=. + r t = -, -.c ,z. s = g/. - z gw c, camin = 12.<%,,7 = zi: 2 2 7, p s-ni, a,n., /DC)
- 83. 5~
J/. Y,z. 3/. r L t'/2so.h = (o 2.7352 70 M c, ~ n,s. 4 I, eo e 49 e O 4 4 TVA 19669 (br4P-6 88)
J ATTACHMENT.2 ISI PROGRAM DRAWING ISI-0002-C-05, REVISION 10 O d X I.
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l i l [ i Request For Relief 2-ISI-9 1 Executive Summary: This request for relief addresses the pressurizer nozzle full penetration welds. The design configuration of the pressurizer nozzle-to-head welds precludes 1 an 100% ultrasonic examination of the required volume for the following nozzle-to-head welds: RCW-15 (4-inch spray nozzle) and RCW-21 (14-inch surge nozzle). i i These physical examination limitations occur when the 1989 code examination requirements are applied in areas of components constructed and fabricated to early plant physical designs. Based on l the date of SQN's construction permit (May 27, 1970), SQN is exemp t from code requirements for examinatica access as l i-allowed in 10 CFR 50.55a (g' (4). 1 1 An ultrasonic examination was performed on accessible areas to the maximum extent practical, given the physical limitations of the subject welds. The design configuration limits ultrasonic examination to approximately 71% of Weld rcd-15 and approximately 60% of Weld ECW-21. Performance of an ultrasonic j examination of essentially 100% of full penetration welds in the pressurizer nozzle-to-vessel head welds, RCW-15 and RCW-21, would be impractical. The performance of the ultrasonic examination of the subject welds to the maximum extent practical, provides reasonable assurance of an acceptable level of quality and safety because the information and data obtained from the 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 SON's second inspection interval.
2 Unit : Reactor Coolant - System 68 System: Two Pressurizer Nozzles, Full Penetration Components: Welds f E2-1 2-ISI-9
l I^ l' l ASME Code Class: ASME Code Class 1 (Equivalent) Section XI Edition: 1989 Edition Code Table: IWB-2500-1 J l -Examination Category: B-D, Full Penetration Welds Of Nozzles In 1 Vessels Examination Item Number: B3.110, Pressurizer Nozzle-to-Vessel Welds l Code Requirement: ASME Section XI, Table IWB-2500-1, Examination Category B-D, Item No. B3.110, Volumetric Examination Code Requirement FromWhich Relief Is Requested: Volumetric Examination Coverage List Of Items ) i Associated With The Relief Request: RCW-15, Pressurizer Nozzle-to-Head Weld RCW-21, Pressurizer Nozzle-to-Head Weld Basis for Relief: 'The design configuration of the pressurizer precludes an ultrasonic examination of the required volume for the following nozzle-to-head welds: RCW-15 (4-inch spray nozzle) and RCW-21 (14-inch surge nozzle). The design configuration limits ultrasonic examination to i approximately 71% of Weld RCW-15 and approximately 60% of Weld RCW-21. Alternative Examination: In lieu of the code required 100% ultrasonic examination an, ultrasonic examination was performed on accessible areas to the maximum extent practical, given the physical limitations of the pressurizer nozzle-to head welds. Refer to Attachment 1 for the Examination Data Reports. ~ Justification For The . Granting Of Relief: -(1) The design configuration of the subject nozzle-to-head welds precludes ultrasonic examination of essentially l 100% of the required examination volume. In order to examine the welds l in accordance with the code l requirements, the pressurizer would require extensive design modifications. The physical arrangement of RCW-21, in conjunction with the close curvature of the 2-ISI-9 E2-2
l outside wall surfaces of the nozzle, L precludes ultrasonic examination from the nozzle side. For scans normal to~ ~ the weld on the bottom vessel head side, examinations are limited to areas up to approximately 4 inches from the weld centerline. Limitations on the bottom head side of RCW-21 are due the presence of 78 immersion heaters penetrating the heaa, which restricts the scanning surface or the transducers. The scans for flaws oriented transverse to the weld are i not obstructed. Therefore, 100% of ( the required examination coverage for l flaws transverse to the weld was l obtained. Total examination coverage of Weld RCW-21 was approximately 60% of the code required. volume. The physical arrangement of RCW-15, in j conjunction with the close curvature l of the outside wall surfaces of the nozzle, precludes ultrasonic examination from the nozzle side. l Scans normal to the weld from the head l side were not obstructed, allowing complete coverage of the weld from one side. Examination coverage from the one side provides reasonable assurance that no flaws parallel to the weld are l present. In addition, approximately l 81% of the required ultrasonic examination volume for flaws transverse to the weld was performed from the vessel head side. Total combined examination coverage of Weld RCW-15 was approximately 71% of the l code required volume. 1 (2) Radiographic examination, as an alternate volumetric examination method, was determined to be impractical due the thickness of the component. Gaining access to the in-side surface of the pressurizer to o i place radiographic film would require extensive personnel protection due to hign radiation and contamination levels. The pressurizer manway would have to be removed, decontamination performed, and specialized scaffolding erected to gain access. The additional code coverage gained by I 2-ISI-9 E2-3
radiography and/or ultrasonics from the inner surface is impractical when weighed against the radiological concerns. The estimated radiological conditions were determined to be the i following. l 35-40 rad / hour beta (uncorrected) 10-12 rem / hour gamma 1 rad / hour per 100 square cm l Maximum stay time to maintain exposure to less than 1 rem is approximately 5 minutes. Special clothing would be required for protection from the extremely high contamination levels l and from the high beta dose rate. I Respiratory protection would be required. Industrial safety would also be a major concern (heat stress, confined space, and climbing / falling hazards). Estimates are based on actual experience inside primary components such as steam generators. ) ) (3) A percentage sampling approach j R provided by the ASME Section XI Code, in combination with examinations performed on similar items, provides reasonable assurance that significant l degradation, if present, would have been detected. Performance of an ultrasonic volumetric examination of essentially 100% of full penetration welds'in the pressurizer nozzle-to-vessel head (Welds RCW-15 and RCW-21) would be impractical. As previously discussed, TVA determined that it would be impractical to attempt other volumetric examinations in order to increase examination coverage. A l maximum extent practical ultrasonic F l examination of the subject welds provides reasonable assurance of an i acceptable level of quality and safety. Significant degradation, if present, would have been detected during the ultrasonic examination that 4 was performed on the welds. As a 4 4 d 4 ISI-9 E2-4 f e
result, assurance of structural integrity for these welds is provided by the alternative examinations that - were performed. Therefore pursuant to 10 CFR
- 50. 55a (g) (5) (iii), it is requested that relief be granted for SON's second inspection interval.
Implementation Schedule: This request for relief is applicable to the second inspection interval for SQN Unit 2. Welds RCW-15 and RCW-21 were examined during the first period of SQN's second 10-year inspection interval.
Background
Information: In addition, it should be noted that a request for relief for volumetric examination coverage limitations for Welds RCW-15 and RCW-21 was submitted a-s 2-ISI-21 for Unit 2 in the first interval and was approved with no additional augmented requirements.
Reference:
NRC letter to TVA dated February 7,
- 1996,
" Relief Requests to Close-Out the First 10-Year Inservice Inspection Program Interval - Sequoyah Nuclear Plants Units 1 and 2 (TAC Nos. M92454 and M92455)." - Examination Data Reports: R-5668 and R-5673. - ISI Program Drawing: ISI-0396-C-01, Revision 4. 2-ISI-9 E2-5
ATTACHMENT l' EXAMINATION DATA REPORTS R-5668 R-5673 4 P W
'g? ci; EXAMINATION REPORT NO.
SUMMARY
AND R.52'4F TENNESSEE VALLEY AUTHORITY RESOLUTION SHEET I l f PROJECT: 6C)OP unit: 2 exAutNER M. A. C)UO A ZE5 LV: E EXAMINER: D ld $dEV LV: I 'PZR [C6BT T6T-03W C-Ol l'91.2 I SYSTEM: P4 [ LV: 4[ EXAMINER; WELO I.O.: TCLU-if !A /A LV: l CONFIO: dn.ca TO-EXAMINER: FLOW CAL SHT NO'S:, da 7 0 2, C.o 76 3, cp70 r/ PRCCEDURE: N-- LCT. R REV.: J _ TC: MfA c.o 70 V NCE METHoo: E uT O PT O uT O vT t T C O AAltLAL. %6 ~14C'90MT" CCg r A84 % TC *b An-A. Wacc.i b'rtm us r w dt. rsr a...o'i c F t. A A.L %-rE A oc" EatO-16 Ge A64E-b,. "Il dad -- LEm'ea scw mm. Oo ceroec a.ur 'A'fA A tm g[ T i,i Q gemr ah S~ 9 M })e - b w.. ast~ TwWec -a. Arg c.d4=~t G uit st r/dd -- - p Ines it3as car re G c'nst wi i c AL t /D2.zLG to VCC C El-- olet_.D. 90s ? hs = C/hMv't ARD C o D C ? o v a ~d & G d=~ I' 2 __ LEVEL: _ CATE: _46 Pk p$e&UJVA W EVALuATCR rr-- _ cATe _ P f-N ^' [CF $- 8M LSEt: PAGE CcNCunnENCe wm
l k ~ $bb S \\ USN 50 ULTRASQNIC CALIBRATION NO. TENNESSEE VALLEY AUTIIORITY CALIBRATION b- (> 76 A DATA SilEET PROJECT: 60MP UNm E CALIBRATION DATE: o*> /o z /% 4 /A CALIBRATION BLOCK NO.: EMP '29 TEM P.: 'J9 F PROCEDURE: N.IIT. 19 REY.: 9 TC: SIMULATOR BLCCK NO.: '7917 19 INSTRUMENn Mu r e.s> Au.ct TIIERMOMETER SERIALNOc 65'El8G btDur, l.tt.37 MODEUTYPE: tM 50 COUPLANT: NLTmM. "II.. B ATCli: M l Z6 SERAL NUMBER >__ C t6S O2. kCN TELH TRANSDUCER MANUF.: ANGLE VERIFIC ATION S ERI AL NO.: Mo 69 44 SI7.E: f.o Rouun FREQUENCY: 2.75 Mlit BLCCKTYPE: WiQEZ SERF AL NO. ~fB919 I CABLE TYPE: ~26 6 A c. /t1 --LENGTil: 2.0 4 NOMINAL ANGLE: O ACTUAL ANGLE: O' INSTRUMENT SETTINGS REFLECTCR REFERENCE DATA 100 ORIENTAT!ON SENSITIVITY SET AXIAL ~ g /A y /A l Yz.y ] Z 3. 5 8 g CIRC \\ y l ,R ) w TOF (PEAK / FLANK): EM M _ ANGLE: OFT ~ . CEG. Yq / \\' P q \\ "/ D l DELAY: O.Gi7 2 uS 7.ERO: a.67 7 u3 L 4 I-c v M ATL V ELCCITY:. 7 ~6'30 uS' RANCE: 4 CO Lr 40 ers- [ REJECT: O 5 PULSER: Nt6M DUAL: ON % OFF M l INITI A L C Af t D R ATIO N l 4.co INITIAL TIME-l71G FINALTIME: l~5'd6 Cf 5 PLAY WIDTil VERIFICATION TIMES 6DH. CA[N: 2E6.dB REF. REFLECTOR:3ye 36 OD U O/
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y , 29 zo j gy ,o ,es C vgg77c3g i GAIN SET 6 12 SET + 12 SET +6 N.[F SIGNAL AMP. ;80 % 32:o43 16 to 24 20 % 64 to 96 40 % 64 to 96 ATTENUATOR M "Zo 20 } } 8C REFER TO CALIB RATION REPORT u /A FOR PREVIOUS SAtlSFACI'ORY LINEARITY COM MENTS: M /A WELD (O EXAMINED: _ ECW "' lT. ) A ^NII LEVEL: _ .5' dpM( JAMINER: - DATE: N/. '- A LEVEL: 4-EXAMINER: LEVEL: [ DATE: PAGE Z. _ OF REVIEWED DY:
~. R-h h ,u . USN.50 ULTRASQNIC CALIBRATION NO. TENNESSEE VALLEY AUTIIORITY CALlBRATION DATA SIIEET C-8 70.3 PROJECT: 4oMP UNrr: 2 CAttBRATION DATE: O*5 /02 /C 6 t PROCEDURE: N.UT. 19 REV.: 9 TC: MIA CALIBRATION BLOCK NO.: BMP 'f9 TEM P.: '79 p 'IC I 719 SIMULATOR BLCCK NO.: f INSTRUMENT: t'reAu ree Aum MODEUTYPE: 093 Go T11ERMOMETER SERIALNO.: 552.te/Ah I.il-97 SERAL NUMBER > E 18 6 0 2. COUPLANT: Ut neA6rt_ E BATCH: 9412G I' TRANSDUCER MANUF.: _ _ lG Areart.ct4 RL ANGLE VERTFIC ATION SERIAL NO.: E26 2t g S!7.E:.50 X l.OO FREQUENCY: 2.25 Milt. BLOCKTYPE:TM ]yt 2 SERIAL NO. 38919 I CABLETYPE: ~% 5A C/LL LENGril: 204 NOMINAL ANGLE: 4 ACTUAL ANGLE: 46 INSTRUMENT SETTINGS ^ O REFLECrOR REFERENCE DATA geo / Rs. ORIENTATION SENStrIVITY SET '6 ) f AXIAL M /A 4 /A ./- o j CIRC 36 0 l TOF (PEAK / FLANK): he ANGLE: 46 DEG. P \\ L 60 \\ g-) DELAY: '5.38,3 uS ZERO: ll.494 us l MAT 1, VELCCITY:.17 3 8 uS' RANCE: 6.46 %i n 4isb REJECT: O PULSER: q8 x ,c \\ DUAL: C ON $ OFF 20 1 INITI AL C ALIBR ATION 0 DISPLAY WIDTH 6 40 INTTIALTIME: 12.2 0 FINALTIME: 13 % VERIFICATION TIMES E,oM 6DM CAIN: ~56 dB REF. REFLECTOR: ID D60 M / N M / AMPLITUDE: 40 % METAL PATH: 1.080 -
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- 12 SET
+6 .' ATTENUATOR SIGNAL AMP. 80 % 32 to 48 16 to 24 20 % 64 in 96 40 % 64 to 96 k, 1 20 8o 6o___ REFERTO CALIBRATION REPORT M/A FOR PREVIOUS SATISFACIORY LINEARITY COMME.VTS: 4 # Y' " WELD (s) EXAM!NED- 'ECU3-16 bs LEVEL: C ANII: d XAMINER: ' r// obi 'AJ Lla LEvEt: r p DArE: ExAuiNER: REVIEWED BY: LEVEL: DATE:.. PACE 3 OF /I
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0h$ USN.50 ULTRASQNIC CALIBRATION NO. TENNESSEE VALLEY AUTHORITY CALIBRATION DATA SIIEET C-6 70 PROJECT: AOQP UNrr: 2. CALIBRATION DATE: 05 /o2/ % ghe r sstt i.s r> ' PROCEDURE: N.tJT. 19 REV.: 9 TC: o/A CAllBRATION BLCCK NO.:'-++) 79 TEM P.: H *F INSTRUMENT: UAerrsrAu g SIMUI.ATOR B LOCK NO.: '49 W 19 MODE!/ TYPE: UM Go Tl!ERMOMETER SERIAL NO.: 552186 kb l.it.97 SERAL NUMB ER: El85CZ COUPLA.VT: dcTNsEL T BATCH: 9412::i TRANSDUCER MANUF.: M AreerEcF SERIAL NO.: F.2.szts ANGLE VERTFIC ATION SI7.E: 5 X.1 00 FREQUENCY: Z ~2T Milt BLCCK TYPE:TM Tv pC 2. SERfAL NO. 78919 i CABLE TYPE:~'iM A e /_a LENGTil: 264 NOM!NAL ANGLE: 60 ACTUAL ANGLE: 6I INSTRUMENT SETTINGS 100 REFLECTOR REFERENCE DATA l ] l ORIENTATION SENSITIVITY SET j AXIAL M /A c/A l / t/[ l CIRC 42..O 2 g P \\ TOF (PEAK / FLANK):7FAK ANGLE: Gl D EG. L [ \\ 60 . DELAY: 136'3 uS
- 7. ERG 15.55V us MATT VELOCITY:.1255 uS' RANCE:
9.O g'a glp,2 py REJECT: O PULSER: b6H E N /7 ,o DUAL: ON E OFF t g w. x p i /% 3N o r ^ ^ 0 DISPLAY WIDTH 9.0 INTTIAL TIME: 12'5 a FINAL TIME: 1416 VERIFICATION TIMES R EF. R EFT.ECTOR:Loe 6DH CAtN: 42.O da tm D M (T U M/ 9y / AMPLTTUDE: 40 % METAL PATH: 1.5'7 f 5) N /A 6) u /A D /A 8) /A C STCNAL t 100 30 M 60 50 40 30 20 10 VERTICAL L II SICNAL 2 50 49 4e .56
- So "t.T 2e IT to
.W f F*' CAIN SET 6 12 SET + 12 SET +6 g' ATTENUATOR f SIGNAL AMP. 30 % 32 to 48 16 to 24 20 % 64 to 96 40 % 64 to 96 K 3 go ge REFER TO CALIBRATION REPORT 4/A FOR PREVIOUS SATISFACI'ORY LINEARITY COMME.VTS: % Y Je src Gb SE 4 Pld6 ' WELD (s) EXA.WNED: h -lT // XAMINER: LEVEL: E~ ANII: Mm ,le M LEVEL: I DATE: /0/f/ EXAMINER: DATE: N '[ bF /I -, A LEVEL: - PACE REVIEWED BY:
~~ ^ . ~.c USN 50 ULTRASONIC CALIBR ATION NO. TENNESSEE VALLEY A UTHORITY CALIBRATION C-4705' DATA SIIEET 66'/d7 /9/, ROJECT: 4 AJ P UNIT: __ 2 CAltBR ATION DATE: b r/k tio P PROCEDURE: N.UT. /9 _ REV.: 9 TC: N/# CALIBRATION BLOCK NO.:M 7I TEMP.: ;r9 p StMULATOR BLOCK NO : 79/7/9 INSTRUMENT: 6ALTt'e4 NEg 462/A6 de Oag /.//..^<p TIIERMOMETER SERIAL NO.: MODEt/rYPE: ddN 60 COUPLANT: /[ve46E2. E~ BATCit: 94'/2 9 SERAL NUMBER: E'//3 6'C Z EXAM TYPE:. SilEAR LONG. C RL TRANSDUCER MANUF.: E6 Arm 7z?h/ SERI AL NO.: CZb 2)S' ~ S!7.E- ,5* n' / d o FREQUENCY: 2.26 Milt BLOCK TYPE: W W/E 2 SERIAL NO. 749/9/
- 4 59 d /I6 LENGTit: _ ZOM NOMINAL ANGLE: /d ACTUAL ANGLE: 6/
CAllLE TYPE: INSTRUMENT SETTINGS ^ REFLECTOR REFERENCE DATA ORIENTATION SENSmVirY SET 100 / ) AXIAL M /A Mk f Vd g
- /Z. 0 Z
/ CtRC 6/ D EG. TOF (PEAK / FLANK): o?E ANGLE: P \\ t -s 1 \\ \\ $ ] DELAY: E 583 uS 7,ER& /5'66F uS 60 \\. D M AT'L VELOCirY:. /263 uS RANCE: 9O U 40 s M/d N - M D R EJ ECT: ~~ O PULSER: \\ fl DUAL: C ON E OFF " E 20 (' 1 wo 7 \\ INITI AL CALIDR ATION DISPLAY WIDTH 9O INmAL TIME: d'7 d 5~ _ FINALTIME: //09 0 VERIFICATION TIMES REF. REFLECTOR: 46 60// GAIN: //2 O dB
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- 6
% METAL PAW: /67/ 3'C"^ 8 7 6 5 d I 3 20 la c vERTrCAL 50 g sj, g yo y yf , jg- , jo , g-L !! SIGNAL 2 I F GAIN SU 6 12 SET + 12 SET +6 g* c' ATTENUATOR . SIGNAL AMP. 1 80 % 32 to 43 16 to 24 20 % 64 to 96 40 % 64 to 96 'M 20 1 80 AO REFERTO CALIBRATION REl' ORT A/// FOR PREVIOUS SATISFACIORY LINEARITY N EA A o'## N " b o dd 5 M WELD (s) EXAMINED: _ N/d-#5'I 8641~2/ COMMENTS: L k %a /0my \\ //wn b ANII; LEVEL: ?I~' EXAMINER. ( // LEVEL: Z~~ DATE: Mfe[v4 XAMINER: $~~ ' OF /[ I8 PAGE LEVEL: DATE: i. REVIEWED BY: w
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- D : U R
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MANUAL UlistASONIC REPORT NO. 1ENNE55EE VALLEY AUTHORITY VESSEL EXAMINATION R-s/;tY DATA SHEET Wo
REFERENCE:
( dF Qab EXAMINAT!ON DATE: 6/7Md PROJECT: sci 4F uNm 2 6'2 *f M D STAN TIME M t4 ' END TIME: /4.W SYSTEM. M 2 M - d 0 f* Lo
REFERENCE:
/15 e
od 41sn.sdE u. WELD I.D.: .Nn[.,); - /5 C AL. SHT. NO. ANGLE SCAN SEN5fTIVITY SURFACE Teup. F CONFIG: 0 Z Z /E T0; $ tl(~/ I 7g co 7o( /g
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^/ dB PROCEDURE: N-UT-19 REV. 9 TC: tl/A PYRO. SERIAL NO. 552 / A c, delt. fur /////4 7 A dB RESULT 5: ($CAN NUMBER) 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 I 'i;
- INDICATION RECORDED (YIN) d d
j O# ^I ^ UI ^ IND MAX SCAN NO AMP NO ANG Mp1 W1 L1 Mp1 W1 L1 Mp1 WI L1 Mp W L Mp2 W2 L2 Mp2 W2 L2 Mp2 W2 L2 lb_ k r, Et' f.Kl)ilRfE b f) t(*i ! 7-if b kD* AR Dr WlE JT1 0 tc A r~t o ^1S El 6W 6 l tJ F s / p ~# [ / ga \\ p p A d!/7,sj.F'A/Mf~/) (#/Af) [(, / /. /O /d*[ M// lt[////f:',$MMgf gg',, REMARKSAJMITATIONS: 1 i. ^ J J / g EXAMINER. LEVEL: T REVIEWED BY: h v -t LEVEL: I LEVEL-MM DATE: 7 -d .-7 OF f f l EXAMINER: / PAGE i f / s M-TVA 106700 (NP 7/92)
I i G.E REPORT NO. Ffi BEAM SPREAD - AND RESOLUTION b5 TENNESSEE VALLEY AllTHORITY. DATA SHEET O6[n(/9[o PROJECT: 4D09 UNIT: 2 BEAM SPREAD DATE: PROCEDUAE: N.-UT- _19 FEV. 3 TC AfA SEARCH UNIT "8""*"*"
- 5 kss Ae r < 'r MANUFACTUAER UT INSTRUMENT
. SSx. l.co _ FREO: 2 25 MhZ SI2E: NOM. ANGLE 44 MANUFACTURER bA.ucrK5tAuE-10, . SM: _ E Z's Z t $ f MEASURED ANDLE-N/ DEG. MCOEL NUMBER ll4M-60 x. 11.O
- DEO.
SERAL NUMBER E(6SO 2, - BEAM SPAEAD-1 'W M AX LEADING RAY (W2) TRAltlNG HAY (WI) 20% DAC SC% DAC 100% DAC 50% D AC 20% D AC - HOLE W MP W M? W MP W MP 'W MP PO$mCN lid T o.s6 c.869 c.7 o Sec o.65 f.o'72 10 l.18J. l.cff 1234 1 1/27. 135 lA46 14's 2.o t'5 1.66 2.1o6, 1.87 Z.3 tT Zo4 2Ac5 3/4 T z.c8 "2S'56 2,16 3.c41 2.58 3.3c7 Z.88 3.Sc6 3.c5 3.452 \\ t=scsna nv ma w 3-E IMlUNG AAY Mn 4 R.G.1.150 RESOLUTION VERFICATION M! 4/ IN. SIZE: 4/ cEFTs- !A NeAn SunsACE nEFtECTCa: !A _ IN. S!ZE: !A CEFTH: FAA SURFACE REFLECTCA: O YES O NO SCANNING (AEFLECTCRS P90VICE 50% DAC SIGNALS AT SCANNIPf3 SPEED: sEuAnxs: & 6tg. M P. 79 4 l LEVEL: 2E~ g,/y ' EXAMINER ~ cATE: T AJ,./ A tEvEt: r L =Te MIL,,,, y c, fr Eu MiNEm 1 :-ED ey; ' W4Rak tEvEu . ) i - TVA 19670A (NP 7/92)
.i, % I
- p G BEAM SPREAD REPORT No.
\\ TENNESSEE VALLEY AUTHORITY AND RESOLUTION R-SET l DATA SHEET S 06!C1/9 PACUECT: MOP UNIT: 2. BEAM SPREAD DATE: SEARCH UNIT PROCEDURE: P4-TIT-19 AEV. 9 TC 4[A CAUBAATICN SHEET NO. C-d ~7cd-l MANUFACTUAER VJ5 Atro rrr9 SIZE:. S y, i. c3 FREQ.:
- 2. zG Mhz UT INSTRUMENT
$x. E24 2t6 NOM. ANGLE (oO MANUFACTURER dtAwr e.eAtt e 1P. MEASUAED ANGLE: /o l CEG. MOCEL NUMBER thQ 60 2 BEAM SFREAD-Iz.5* CEG. SERIAL NUMBER: C 18602 TRAluMG RAY (WI) W MAX LEADING RAY (W2) HOLE PostTION. 20% DAC 50% DAC 100% DAC 50% D AC 20% DAC W MP W MP W MP W MP W MP 114 T 1.1 1.184 12 1.3o z I.4 1.497 f.e.4 1 869 2.05 z.043 1/2 i z.24 2.568 2.4 z.t47 z.84 3.cvi '5.59 3.4'54 4.o 4 tc9 3/47 3.53' '2.o r? '6.75 4.22 8 4.26 4.G68 5.37 5.lj % (..I 6.3to \\ LEACtNO AAY M21 4 a TPAfUNG PAY M11 R.G.1.150 RESOLUTION VERFICATION Of N[ CEPTH: k) / IN. $1ZE: NEAR SUAFACE REFLECTCR !A ,! A !A IN. SIZE: CEPT}t _ FAR SUAFACE REFLECTOR: SCANNING (AEFLECTCRS PACVICE Sc% DAC SIGNALS AT SCANNING SPEED: OYES O NO - REMARKS: hat _. b 6HP -vel e 4 EXAMINER: EVEL: E [ff ~ EXAMINEA: 1 LEVEL: -4 DATE: 3 - ' EvtEWED BY: CATE: N 7 CF L,f LEVEL: PAGE j--- TVA 1967CA (NP 7,92)
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.M Y EXAMINATION REPORT No. TENNESSEE VALLEY AUTHORITY
SUMMARY
AND R-oT73 RESOLUTION SHEET PROJECT: 60 dp UNIT: 2, EXAMINER: d, A. OLi\\J A R.N LV: f ~O.ld. b CN, LV; 1 SYSTEM: PZR /,069h ~I%T -oM 6 - t-O i 2co. ~2 EXAMINER WELO I.O.: TCl>3 - ZI EXAMINER d[ LV: kl[ !A !A CONFIO: de 22LE, TO: WC L.L EXAMINER LV: CAL SHT NO'S: C# l' $, C'll0 CO 7//' Col / s PROCEDUAE: N-t f T 19 REV.: 9 TC: 4[A NDE METHCO-E Ur O PT O uT O vT ('c u T N5 TM bArA mmc., ATm ld t-r8 "'Tht-T *, gort r LI4 odA t (ILwwo ot em E<Aub,Jo.:s or T CLG - 2. I L A6ME 6tr. 'IT Czer$ n, N6 E' E Z'o C2 O A E 3D CAv7bD MPJ24 doTrrD a o r-(0 t7 H A 3.76 FYA u uATt'n A bku'e m. b u bCAA b blDF'3 TP LL MEE NT A7 [c A E M ATI2. A T t 6 A CA b'TTa M O C' NR. I ut T, i ws um r ~o n ue a. swg St.g re aco xa iMuL Or fec uMTrod. 5~ 9. T2. fn WWL S'e? ?"_L - CO Vd~A WoG~ f~dA THff (: YAM IS ^ EVALUATOR J -lAt,A.CbVA245 I OATE: 06 O t f 9(s _ LEVEL: 1'[9!/d CCNCUARENCE: LEVEL: E' OATE: / / PAGE l CF U / TVA 19670C (NP 7S2) m
R-6/o'7 5 -i C USN-50 ULTRASQNIC CALIBR ATION NO. TENNESSEE VA T1FY A UTHORITY CALIDRATION DATA SIIEET C
- 7#
64[Jo/96 ...OJ ECr: do u P UNrt: 2 CALIBRATION DATE: / PROCEDURE:N.(Tr. /9 REY.: 7 TC: A/A CALIBRATION BLOCK NO.: A N P 79 TEMP 79 F l INSTRUMENT: Mm/ 7.*'EANCE SIMULATOR BLOCK NO.: 79/ 7/9' ' MODEUTYPE: //dA/* 60 T!!ERMCMETER SERIAL NO.: 65 2 /26 du D,c /-//.yg SERAL NUMBER: E/8602 COUPLANT: /Ar#A4CL T BATCH: 9V/2f EXAM TYPE: C S!! EAR E LONO. RL 8N-M/>/ TRANSDUCER MANUF.: ANGLE VERIFIC ATION f SERIAL NO.: 4/g gW9 ' SIZE:_ / d ON FREQUENCY: 2,2f Milt BLOCKTYPE: N NN 2 SERIAL NO. 7M9/ 7/ CABLETYPE:, #4Edfd M2 LENGTil: 244/ NOMINAL ANGLE: O ACTUAL ANGLE: C* I INSTRUMENT SETTINGS REFLECTOR REFERENCE DATA 100 ORIENTATION SENSITIVTTY SET AXIAL h /A N /A y 80 CIRC 2 3.S' M NMX ANGLE: M6 D EC. P ~ \\ . 3j j TOF (PEAR / FLANK): L '( l DELAY: 6,4 7 2 uS ZERO: d.677 us 60 [ l l \\l l MATL VELOCrrY: 7330 uS RANCE: #do J 40 i /./,6 s D ggyge7 o y, put3gg: E DUAL: C ON E OFF 20 l INITI AL C ALIBR ATION 0 CISPI.AY WIDTH 4a Z INITIALTIME: /0 Mo FINALTIME: l/ A B VERIFICATION TIMES REF. REFLECrCR: boM :(o// GAIN: 23 5 dB 1)lu75
- 2) l6, gg 3) u/
l-9 e / AMPLITUDE: NO ?. METAL PATH: 0. 7 W "
- 5) @
l 0 g4 ,D M l 'd) M SIGNAL I 100 80 M 60 50 40 30 to 10 } C VERTICAL y.f yo fg-fo,gl L II SIGNAL 2 l 50 g ,,f, 34 go CA!N SET 6 12 SET ' + 12 SET +6 ~ ATTENUATOR SIGNAL AMP. l 30 ?. 32 to 43 16 to 24 20 ?. 64 to 96 40 ?, I 64 to 96 E <to Zo I 80 6 20 REFERTO CALIBRATION REPORT N /4 FOR PREVIOUS S ATISFAcrORY LINEARTTY l COMMENTS: GocC WELD (s) EXAMINED: MU '2. l I I >J LEVEL f AM M \\ MINER: Mt,[fl j/ LEVED I DATE: EXAMINER: s /I 2-CF . LEVER DATE: PACE REVIEWED BY:
[ 5673 +z / USN.50 ULTRASONIC CALIBRATION NO. TENNESSEE VMLFY AUTHORITY CALIBRATION DATA SIlEET C 67/0 0 V[3c/9d . 401ECT: 09f UNm O CAL!BRATION DATE: AI[A CALIBRADON BLOCK NO.: ANF-77 TEMP.7f 'F PROCEDURE:N.UT. I 9 REV.: 9 TC: i INSTRUMENT: UovY ba MeV-SIMULATOR BLOCK NO.: 7Tl3Y l 45IJ-4D ntERMOMETER SERrAt NO.: 554IFro e,My e fi.i.e ; MODE!JTYI'E: SERAL NUMBER:. f / 850 9: COUPLANT: (ANf 40ef I BATCit: 9 VI 6 EXAM TYTE: M SliEAR LONG. O RL TRANSDUCER MANUF.: h6-ItWWM ANGLE VERIFIC ATION SERI AL NO.: E25 2/5- # S!7.E:.go y /.O FREQUENCY: 7 2f MIIs BLOCKTYPE: _ RW 7'#( 2 SERIAL NO. 777/ 9/ A4. fM dz LENGTII: Zod NOMINAL ANGLE: W ACT11AL ANGLE: %* CABLETYPE: INSTRUMENT SETTINGS DAC REFLECTOR REFERENCE DATA 100 ORIENTATION SENSmVITY S e., i __ d AXIAL 4 la s %t l l V-gj l g 3 CIRC l Db / l. y y bc ANGLE: O DEG. TOF (PEAK / FLANK): l l \\ l l DELAY: 4 H3 uS 7.ERO: /t'/F us [ MSl t (o. Y.. \\ w - MAT'L VELOCITY:,12 3I uS RANCE: y #0 l l Wj M'['d 3I ) \\ REJECT: /*) PULSER: S N E ( ouAt: g og g opp 20 W A r \\ INITI AL C ALIBR ATION l o 'O // /I FINALTIME: M16 DISPLAY WTUTH
- 6. 2/
INmALEME: VERil:TCATION TIMES REF. REFLECTOR: D.y ABM GAIN: 30 dB I dI d AMPLITUDE: D % METAL PATTI: 1.O f30 -
- 5) g/A l6) e/A l7)
/A
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50 lW !W l J/, t L II SIGNAL 2 CAIN SET 6 12 SET + 12 SET +6 ATTENUATOR SIGNAL AMP. : 80 % 32 to 48 16 to 24 20 % 64 to 96 40 % 64 to 96 j K rio ,yc go yo REFER TO CALIBRATION REPORT FOR PREVIOUS SA1ISFACI'ORY LINEARITY COMMENTS: 3 /* 1 % D B eir:- 4 v bAo ben WELD (s) EXAMINED: W-Zl / \\$ (a b a. A. Thp LEVEL: f AW: AMINER: E / DATE: ((/4//4 e LEVEL: EXAM.*NER: Y# N LEVEL: DATE: PAGE - CF / REVIEWED BY:
1 ) a 9 -5673 l 3. USN-50 ULTRASQNIC CALIBRATION NO. TENNESSEE VALLEY AUTilORITY CALIBRATION DATA SIIEET C- # 7// .,OJECT: 5OOP UNm 5k-kJd/f6 CAUBRATION DATE: 0*'P a" K " '- PROCEDURE: N UT. /7 REY.: 9 TC: 4[# CALIBRATION BLOCK NO.: W 77 mt P.: 77
- F INSTRUMENT:
l< / o ut kNn e e. SIMULATOR BLOCK NO.: 79/ilT MODEUTYPE: t) 5 M - 60 T1IERMOMETER SERIAL NO.: IIS/N cr/c/ve./N 97 E/ F5cG-COUPLwT: a b;adf BATCH: f '// K SERAL NUMBER:. TRANSDUCER MANUF.: KO - A 5 AoTE"# SERIAL NO.: P!til/g ' ANGLE VERTFIC ATION SI7.E: ,,5'X l. o FREQUENCY: J.M Mitt BLOCK TYPE: 8 7"j o" d-SERIALNo. 779/9/ CABLE TYPE: RG 57 c/a LENGTil: 2M ~ NOMINAL ANGLE: bO ACTUAL ANGLE: 5/ INSTRUMENT SETTINGS UA gg' REFLECTOR REFERENCE DATA l l ORIENTNTION SENSITIVrTY SET AXIAL ~ M/A NM l ^ 80 CtRC iG Db I R. u ps l\\ t bo #k b/' P ANCLE: D EC. l l \\, TOF(PEAK /F1 ANK): l l DELAY: ~7,39.3 uS 7.ERO- /8. 537 uS J l l \\ 60 40 5 x 3 ^ D 8 RE.!ECT: O PUUiER: u,. 4
- e i
I s 20 DUAL: ON 5 OFF 0 DISP!AY WIDTH
- 9. O INTTIALTIME:
1200 FINALTIME: M38 REF. REFLECTOR: f_ece s 60// CAIN: M dB VERIFICATION TIMES } T AMPLrrUDE: 90 % METAL PATH: /,67/ 5) a /A
- 6) y /A l 7)
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l l' l l l Request For Relief 2-ISI-10 Executive Summary: This request for relief addresses circumferential pressure retaining welds in the reactor coolant system. The design configuration and materials used in the fabrication of the subject piping welds precludes a 100% ultrasonic examination of the required volume for the following welds: RC-06 (pipe elbow to pump casing) and RC-07 (pump casing to pipe). These physical examination limitations occur when the 1989 code examination requirements are applied in areas of components constructed and fabricated to early plant physical designs. Based on the date of SQN's construction permit (May 27, 1970), SON is exempt from code requirements for examination access as allowed in 10 CFR 50.55a(g) (4).. A liquid penetrant surface examination was performed on 100% of the subject welds. An ultrasonic examination was performed on accessible areas to the maximum extent practical, given the physical limitations and materials of the subject welds. The design configuration and materials used limits ultrasonic examination to approximately 50% of Weld RC-06 and approximately 50% of Weld RC-07. Performance of an ultrasonic examination of essentially 100% of the circumferential pressure retaining welds, RC-06 and RC-07, would be impractical. A surface examination, and the maximum extent practical ultrasonic examination of the subject welds, provide reasonable assurance of an acceptable level of quality and safety because the information and data obtained from the 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 l
relief be granted for the second inspection interval. 2-ISI-10 E2-1
. - - -. -.~-- - - ~... Unit: 2 System: Reactor Coolant - System 68 Components: Two Piping Circumferential Pressure Retaining Welds ASME-Code Class: ASME Code Class 1 (Equivalent) Section XI Edition: '1989 Edition Code Table: IWB-2500-1 Examination Category: B-J, Pressure Retaining Welds In Piping Examination Item Number: B9.11, Circumferential Welds Nominal Pipe Code Requirement: ASME Section XI, Table IWB-2500-l', Examination Category B-J, Item No. 89.11 Surface And Volumetric Examinations Code Requirement j From Which Relief Is Requested: Volumetric Examination Coverage List Of Items' ~ Associated With The Relief Request: RC-06, Piping To Reactor Coolant Pump l Circumferential Weld l RC-07, Piping To Reactor Coolant Pump l Circumferential Weld L Basis for Relief: The design configuration and materials used in the fabrication of the reactor l coolant pump and the reactor coolant L piping preclude an ultrasonic examination of the required volume of pressure retaining circumferential Welds RC-06 and L \\\\ RC-07. The design configuration and materialslimit/ultrasonicexaminationto l approximately 50% of weld RC-06 and approximately 50% of weld RC-07. L Alternative l Examinations: In lieu of the code required 100% ultrasonic examination, an ultrasonic i examination was performed on accessible areas to the maximum extent practical, b given the physical limitations of the subject welds. A surface examination (PT) of 100% of Welds RC-06 and RC-07 was also performed. Refer to Attachment 1 for the Examination Data Reports, f 2-ISI-10 E2-2 =
k Justification For The Granting Of Relief: (1) The design configuration and materials used in the fabrication of the subject piping welds preclude ultrasonic examination of essentially 100% of the required examination volume. In order 3 to examine the welds in accordance J with the code requirement, the reactor coolant pump would require extensive redesign along with changing the pump and piping material. The weld joint detail for Weld RC-06 consists of a pipe elbow welded to a pump casing. The pipe elbow is static cast CF8M material welded to a static j cast CF8M material pump casing. The l weld joint detail for Weld RC-07 consists of a pump casing to pipe configuration. The pump is static cast CF8M material welded to centrifugal cast CF8M material piping. 1 The examination is limited due to the design configuration and the effects of the anisotropic coarse grain structure of cast stainless material and the weld joint configuration, which limits search unit contact and movement. Total ultrasonic examination coverage for RC-06 and RC-07 was approximately 50% of the required code coverage for each weld. Due to the 'nisotropic a coarse grain structure of cast stainless CF8M materials, the examination was limited to the 1/2 vee technique using refracted longitudinal waves. Both welds received 100% coverage from one side scanning in the axial direction with the sound beam d,irected toward the pump. No scans were performed from the pump side in the axial direction due to the pump taper interference; therefore, 0% coverage was obtained from this direction. It is reasonable to assume that circumferential flaws would be detected to the degree comparable with industry standards. Circumferential scans were limited to 50% each, due to the loss of search unit contact associated with the pump taper on the pump side. 2-ISI-10 E2-3
(2) Radiographic examiriation, as an alternate volumetric examination method, was determined to be impractical due the material thickness (approximately 3 inches) and the pipe being filled with water. Realignment of the system to drain all of the water would substantially increase radiation levels. (3) Westinghouse plants have no history of pipe cracking failure in the reactor coolant primary loop. For stress corrosion cracking (SCC) to occur, the following three conditions must exist simultaneously: high tensile stresses, a susceptible material, and a corrosive environment. The ~ potential for SCC is minimized in Westinghouse PWR's by material selection and prevention of a corrosive environment (reference Westinghouse RCS Piping Flawbase Handbook, WCAP-13670). (4) A percentage sampling approach provided by the ASME Section XI Code, in combination with examinations performed on similar items, provides reasonable assurance that significant degradation, if present, would have been detected. L l Performance of an ultrasonic volumetric examination of essentially 100% of the required volume of pressure retaining circumferential Welds RC-06 and RC-07 in the reactor coolant main loop piping would be impractical. In addition, it would be j impractical to perform other volumetric examinations, which may ) increase examination coverage. The surface examination of 100% of the weld area, adjacent metal, and maximum extent practical ultrasonic examination of the subject welds, provide reasonable assurance of an acceptable level of quality and safety. Significant degradation, if 4 present, would have been detected during the ultrasonic examination and 1 2-ISI-10 E2-4 4
the surface 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. Therefore, pursuant to 10 CER
- 50. 55a (g) (5) (iii), it is requested that relief be granted for the second inspection interval.
Implementation Schedule: This request for relief is applicable to the second inspection interval for SQN i Unit 2. Welds RC-06 and RC-07 were examined during the first period of the second 10-year inspection interval. - Examination Data Reports:
References:
R-5560, R-5566, R-5590, and R-5591. - ISI Program Drawings: ISI-0008-C-01, Revision 6 and ISI-0307-C-01, Revision 8. l 1 l-F I l i i 1 9 4 i E2-5 ISI-10
.~..-.-..- -.--. - -. -..... -..... - -.... -.... -. - -. - -... ~ -. -.. - -. -.. 'i-i l i i f 1 ATTACHMENT 1 l-EXAMINATION DATA REPORTS R-5560 R-5566 l R-5590 R-5591 i l i e l i f i l P I l-i I f.i l 4 i 1 .9 9 ma -m w v M
5h t RECORD OF REPORT NO. TENNESSEE VALLEY AUTHORITY LIQUID PENETRANT R.5 3r 4 0 EXAMINATION 27/9d rdOJECT: M UNIT: 2 EXAMINATION DATE: t / SYSTEM : C 6A START TIME: __ O 9 0 0 END TIME : /O OO WELD / COMPONENT 1.D. AC -Ob EXAM SURFACE: ID OD 7 Po F ORIGINAL EXAMINATION [ REEXAMINATION CONFIG.: E/- So O .TO FROCEDURE: N.PT. 9 REV.: / 2 TC: Sh..os o4 REFERENCE DRAWING NO. 7S7' OCO8-c-O/ f(:, CODE CLASS / CATEGORY I / BJ ' ASME SEGON I ASME SECTION XI g. ACCEPTANCE CRITERIA ASME SECTION III ~ ANSI B31.1 O ASME SECTION VIII O ANSt B)t.7 0 N.eT.9 AreENDIx A O AeeENDtx B V g/A-AWS Dt.I O oTHER d'/4-OTHER METHOD OF EXAMINATION METHOD PENETRANT MATERIALS M apng[M O WATER. WASHABLE FLUORESCENT DYE BRAND NAME: IN 1-88 B'ATCH NO. N A d2 d POST.EMULSIFIABLETLUORESCEST DYE PENETRANT TYPE: dAON I B ATCH NO, ~ SOLVENT. REMOVABLE FLUORESCENT DYE llEMOVERTYPE: DEVELOPER TYPE: 3MI) -NE B ATCH NO. 8 7f 13 3 WATER. WASHABLE VISIBLE DYE ] POST. EMULSIFIABLE VISIBLE DYE FSOLVENT REMOVEABLE VISIBLE DYE ftETE S/N /YN CAL.DUE DATE:
- N,/4 PART TEMPERATURE:
7 M-
- F PYROMETER S/N: $2 2.3 CAL. ATE DUE: /O 7 34h '&'n i
RESULTS OF EXAMINATION: SATISFACTORY 7 UNSATISFACTORY C NOINO.: A EXPLANATION OF UNS ATISFACTORY RESULTS: Wo o R. REMARKS / LIMITATIONS: NoAE (AMINER : e8 LEVEL: A
- d A
LEVEL: DATE: f/ EXAMINER. DATE d' N 9h PAGE _/__ OF l._, REVIEWED'BY: / (34 LEVEL:
. _. -. -.~ -... G, is6 d. c. RECOR'D OF REPORT NO. ' TENNESSEE VALLEY AUTHORITY LIQUID PENETRANT R 5546 EXAMINATION edOJECT : S(14 UbTT: 1 EXAMINATION DATE: l-11
- 9 lo SYSTEM : R A 4eTc1t c n o LA M 7" STARTTIME: O 41 fo END TIME : O A t./.T WELD / COMPONENT I.D. : ltc - 0 '7 EXAM SURFACE:
ID OD @ CONFIG.: Pu m? . TO 7 i P C ORIGINAL EXAMINATION 5 REEXAMINATION PROCEDURE:N W.
- )
REV.: 11 TC:.16 d.E 4 04 REFERENCE DRAWING NO. IsT ocn A -t - o l C E CLASS / CATEGORY _ B J - 1 ASME SECTION t' O ASME SEatON xI ACCEPTANCE CRITERIA ASME SECTIONIII O ANSI B31.1 ~ ANSI B31.7 NN9 APPENDIX A APPENDIX B j -ASME SECTION Vill AWS Dl.1 O OTHER A/14 C OTHER
- /mi METHOD OF EXAMINATION-METHOD PENETRANT MATERIALS O wATEa WASHABLE FLUORESCENT DYE BRAND NAME: W M A/A F L L1Y POST EMULSIFIABLE-FLUORESCENT DYE PENETRANTTYPE:.5rL s P B ATCH NO. '13 A 01 K REMOVER TYPE: 3xc.S BATCH NO. _% A 0 A K
-] SOLVENT-REMOVABLE FLUORESCENT DYE WATER WASHABLE VISIBLE DYE DEVELOPER TYPE: S k B
- A1 r B ATCH NO. M R f 't 3 POST EMULSIFIABLE VISIBLE DYE
@ SOLVENT REMOVEABLE VISIBLE DYE ft ~ S : all A CAL DUE DATE: *a / A PART TEMPERATURE: 92 'F PYROMETER S/N: 57f 99k C'AL DATE DUE: II 9 4 RESULTS OF EXAMINATION: SATISFACTORY @ UNSATISFACTORY NOI NO.: __ _ A1,/ A EXPLANATION OF UNS ATISFACTORY RESULTS: d* A REMARKS / LIMITATIONS: d _~ A M 2 m/ /_
- m LEVEL: _7T
^W 7tA., sAMINER : LEVEL: I DATE: f f4 ^ . EXAMINE e PAGE_l_OF.I__ LEVEL: DATE: 6 REVIEWED B
t?4 rl.: y, u Y EXAMINATION REPORT NO. l TENNESSEE VALLEY AUTHORITY
SUMMARY
AND y ggy0 i resol.UTION SHEET \\ i PAOJECT: 6G 14P UNIT:
- 2..
EXAMINER To41 d:t. ABBOT Lv: ~]I" 1 SYSTEM: NC.D O(o8 EXAMINER (ME/Y LA5ey A tv n- ) WELD I.O.: RC - O*1 EXAMINER NIA LV: u,IA f CONFIO: 70 M P TO-P576 EXAMINER u!A Lv:,_ ufa CO[d[. d6 O Fl.O W',TC N CAL. SHT NO'S: "7 %-06 / PROCEDURE: mtK-$5_ REV.: NDE METHOO-NUT O pr O ur O vr; TAis Re?cer Onc4Aias TM bATA AssociATcc Wrru Th MAuvat. OLTRAsco tt. ExAMiMnTiOu or Wat.b* Rc-o7. Ydio ExAmioAnog WA5 PEMORMET 'M ACCORbANCE Wsr4 ASME 6Ec. h Doe. Te 714E ATi4; ATiVE ' d ATURE cF OFATRiFO(. Ally CAST STAiMLES$ / 6 TEEL 64E AR WAVE TECMtGOG'S dooCb Mor BE'Lhib Al\\ Ex.AMiMATioN'WERE PER.T bRMED W,W A A5* REi RACTEb l.out,iwbicAL W u t. n=c u w i o.os. _ team * $ - Nov PERFtiRMED bE. -ro dm.s pi e ust.A.TioM A c o,e
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i h b70 USN 50 ULT'RASONIC CALIBRATION NO. i TENNESSEE VALLEY AUTILORITY CALIBRATION DATA SIIEET C-O[ O 3 . ROJECT: 60MP UNIT: 2 CALIBRATION DATE: 4 27-9/* PROCEDURE: N.tJr. 33. REV.: '7 TC: 96-08 CALIBRATION BLOCK NO.: 60-63 TEM P.: ll.f. "F INSTRUMENT: K6 SIMULATOR BLOCK NO.: _95-5723 i MODEUTYPE: U $ L1-S O TilERMOMETER SERIAL No.: 652193 nee si.IS 96.. SERAL NUMBER:, E2425'1 COUPLAhT: OLTRAGE L TE._ B ATCil: 09308l EXAM TYPE: $ SilEAR LONG. [ RL 4 TR ANSDUCER MANUF.: KBA SERIAL NO.: Wil8IB / Hil867 ANGLE VERIFIC ATION Sl7.E: 1.0 " FREQUENCY:
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SERIAL NO. 95-5725 CABLE TYPE: R6 68 LENGTil: /20 NOMINAL ANGL E:M ACTUAL ANGLE: 45 INSTRUMENT SETTINGS ^ REFLECTOR REFERENCE DATA 100 I ORIENTATION SENSITIVITY SET AXIAL 'g/4 g/4 A 80 - U CIRC 55.5 Bo g P / - TOF (PEAK / FLANK): PEAK ANGLE: 45 DEG. [ h 60 DELAY: t%.09 uS ZERO: l3.08 us. y q p s MATL VELOCITY:.ZlM uS RANCE: 5.O J 40 \\ N.6 ~ ml8 ~ D 5 REJECT: O 7 PULSER: Dt.A L. \\ DUAL: @ ON 20 4 OFF INITI AL CALIBR ATION 0 DISPLAY WID' H
5.0 INITIALTIME
/208 FINAL TIME: /430 T VERIFICATION TIMES REF. REFLECTOR: MMPA$ CAIN: 55.6 dB
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$$0 H> C. ~ USN.50 ULTRASONIC CALIBR ATION NO. / TENNESSEE VALLEY AUTHORITY CALIBRATION C-O d k DATA SIIEET . ROJ ECT: __$ONP UNrt: 2. CAllBRATION DATE: 4.77-96 PROCEDURE: N.tJT. 33 _ REV.: 7 TC: 95-08 CALIB RA'I10N BLOCK NO.: So 6 3 TEM P.: 22 2 F INSTRUMENT: k'R SIMULATOR BLOCK NO.: 93-f72lo o a uw MODEL/rYPE: Ll S N IO T1tERMOMETER SERI AL NO.: 573.2o/ Mire. 9 t., ll-l3
- SERAL NUMBER; E / 8 5"0 0 COUPLANT: (1 LGA G EL BATCil: 093o9l U^
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FREQUENCY: /. o Milt BLOCK TYPE: Ros PA X SERIAL NO. 9 3-67J4 ~ CABLE TYPE: BNC-BMC LENGTil: 7.2 ~ NOMINAL ANGLE: 48 ACTUAL ANGLE: W INSTRUMENT SETTINGS REFLECTOR REFERENCE DATA 100 ORIENTATION SENSITIVITY SET AXIAL f2 /o g ca/ "o W A 80 X CIRC X P REr TOF(PEAK / FLANK): /LA Nk ANGLE: 4'S DEG. L-60 h DELAY: //_,. 8 3 uS 7.ER(h //. 8 7f nS [ MAT L VELOCrTY:.JW us RANCE: 4.44/ J 40 ~ REJECT: 0 7. PULSER: b ll A t. E 20 DUAL: ON O OrF INITI AL C ALIBR ATION O DISPLAY WilJTH
- l. 661 INTTIALTIME: / 2.* / o FINAL TIME: /VIJS VERIFICATION TIMES REF. REFLECTOR: Ro m f'A S 3 O M CAIN:
&V d8 0# AMPLITUDE: $0 7. METAL PATH:. N3 A 60 50 30 20 10 C VERTICAL L II SIGNAL 2 50 44 yo A Je 2 (. 24 ty fe y CAIN SET 6 12 SET + 12 SET +6 ATTENUATOR SIGNAL AMP. 80 7. 32 to 48 16 to 24 20 7. 64 to 96 40 7. 64 to 96 K yo go REFER TO CAL 111 RATION REPORT "/4 FOR PREVIOUS SATISFACIORY LINEARITY COMMENTS: C lf c d M FrAe'477Al AcA4 WELD (s) EXAMINED: RC-O7 C Al/b rA T* e# bOMW W Y 7 d
- L LEVEL:
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Hy; MANUAL ULTRASONIC REPORT NO' i TENNESSEE VALLEY AUTHOR]TY PIPING EXAMINATION R- > 9 f 8 DATA SIIEET 4 dOJECT: $QuP UhTT: E EXAMINATION DATE: 4 % SYSTEM : O to 8 START TIME: /f 46 END TIME : /320 WELD I.D. : 8 C. - O"I EXAM SURFACE: @ ID [OD f CONFIC.: Pour' TO Fe PE MATERIALTYPE: @ CS S SS @ CSCL @CCSS h SURFACE TEMP: 74.G
- F PYRO NO.: 552ik3 FLOW t>oe n.is.s s
PROCEDURE: N.tfr. $~$ REY.: 7 TC: % cA CALIBRATION S!!EET NO. C. 0 6 0 3 C-06OY Wo
REFERENCE:
WeLb ( EXAMINATION ANGLE 45 au DEc. r,eh Y5h Dec CIRC. SCAN SENSTTIVrTY-[#1* ' - m I 68 In d ~ u uf4 . AXIAL SCAN SENSITIVTTY '
- 3 dB dn IND L(in) FROM REF.
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WALL TH1'CKNESS TVA A-3 > NO PROFILE SHEET ~~ PROJECT: SONP wew no: RC-o7 OSb 1 SYSTEM: UNIT: Weld
- Weld Edge Record Thickness Measurements As Centerline Indicated, including Weld Width,
- l Edge-To Edge At C*
- 2. 5 "
- [:
2.5* Po sition 0* 90* 180* 270* G '/ / / Side Side [h g 2 5 2.2?( l l' / \\ I l w / Q m / O
- IO CROWN HEIGHT:
1 L fl u.S k Ol AMETER: /OI O-)I WELD LENGTH: CROWN WIDTH: WSI t WLrk Q k , T"O d g / \\ / \\ / \\ \\ / \\ p 7 - __f__ _. \\ l k l / \\ / f _..L -._\\ / I 1 a 1 ) yf A t. EXAM VoM ^ EXAMINER: /2Alo d REVIEWED BY: UM@ ' o n. 4 30 % o^m -m. 7 N LEvEu b. OF Y*.27*kb PACE i.no OATE: ~
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.. A k EXAMINATION REPORT NO. p-Myff TEllflESSEE VALLEY AUTHORITY
SUMMARY
AND RESOLUTION SHEET PROJECT: SC alp UN!T: ? EXAMINER 42,4.ts a.- LV: j / L-SYSTEM: r") /, B EXAMINER 3% 6. AMo ii Lv: In WELD 1.0.: R C - 0 (o EXAMINER W/4 t.v: w[4 CONFIG: EL B ou/ TO-Pu s P ExAuiNER sto tv: u;a CAL SHT NO'S: 6 8h6/b (6 [ PROCEDURE: N-#33. REV.: 7 TC: 9 /., -o 9 NOE METHOO. E UT O PT O uT O vT % r _f R t? Pe GT CO AlD lF1 S GG MAMtLAL t.L Lfk A $ o N (C D A TA \\ A SSMc 1 A YE b v/r Y'h v./fL b RC-o 6. Yht f*y A H f h1 AYr n+1 U/A _f "Y R fo R M T b /s) A c t o R b A M e ?' win (Ed Tjen _TT~ ?ods Pse u r R E met MM. (A KME) fYA M r/1 A noa.3 wfR6 Pen CnkM e b P'2c M % G GLGnul3rls o f 7'4 / e ar fi, ve s %s. dato calv ooc % o Sena#3 si R r SCA # d s_f o $d,44 Duf 7'o Cosi fiC JAAY e a S? A ff' //2 7 ses fin aRr A WA' AL !L LW A. S c All e 1'fe ktaJC ts/A 1 U YlI 2 fD b O C T's 7~h r RWA e A c T' 2 r s t're s o f er-t rPifua x//y CAST' 3 6/+1/655 J YC E l. EEta2bAk f G I AI D i c A n a xl _f o bJ'fR VE D. WhfAE ut fe 2 P si n APPeoxiMArefv J'o 2 or rh e s y i M, M Afr a J REddeREb Vo /uM F \\.A/A A O WA r a C O h t 1 R f alC., 1*h r 1 FX A m r M A Tic d - (CA>l 3 N* Sex a#~s 4L a s' 9-. Tafs / A cki ufo = Co Dr b 1' WALUATCR (2 d A /
- t-LEVEL:
DATE: k '3 0
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A LEVE1.: DATE: PAGE { CF . TVA 19670C (NP 7,92)
{ 4 Q-659l j USN 50 ULTRASONIC CALIBR ATION NO. TENNESSEE VALLEY AUTIIORITY CALIBRATION C-0IO5 DATA SilEET . ROJECT: 6 COP UNIT: 'Z CALIBRATION DATE: 4 - 7._7 -9 G PROCEDURE: N.tTT '4 5 REV.: 7 TC: 96-08 CALIBRATION BLOCK NO.: $G-64 TEMP.: !7.2 F SIMULATOR BLOCK NO.: 'i 5 - 67 2?> INSTRUMENT: KB MODEL/ TYPE: O S M - SO TilERMOMETER SERIAL NO.: 55219S bee 11 1s-90 SERALNUMBERY E 242.57 COUPLANT: OcrFAc2EL E_ B ATCil: _093o 81 TR ANSDUCER MANUF.: K6A ANGLE VERIFIC ATION S ERI AL NO.: 4 L18 t 8 / s.4 t t 8 t7 Sl7.E: 1 O' FREQUENCY:
- 1. O Mlit BLOCK TYPE: Ro@A$
SERIAL NO. 95-5723 CABLE TYPE: X/s - 58 LENGTII: /20 NOMINAL ANGLE: 45 ACTUAL ANGLE: 45 INSTRUMENT SETTINGS REFLECTOR REFERENCE D?~* 100 ORIENTATION SENSTTIVITY Sta AXIAL - urg g jg yzr r\\ go ~ CIRC 68.6 29 e M M/S W x \\ ~ TOF (PEAK / FLANK): PEAK ANGLE: 45 UEc. P I \\ . DELAY: l'S.09 uS 7.ERO-f5.08 id yn MATL VELOCr"Y:.2167 uS' RANCE: 8.2 t 5 a g gg 'D OEL- ~ D REJECT: 0 PULSER: E 20 DUAL: @ ON @ OFF A A ON g O DISPLAY WIDTH 8.216 INITIALTIME: /2fO FINALTIME: /429 VERIFICATION TIMES REF. REFLECTOR: RoMPA6 GAIN: 68.6 dB ^ AMPLITUDE: 75 % METAL PATH: 1.o7 G
- 5) a /,4 6) u/,
- 7) a/a
- 8) y/4 StGNAL I W
80 70 60 50 30 20 to C VERTICAL 50 45 Ao 35 So 26 to s5 lo 6 L 11 SIGNAL 2 GAIN SET 6 12 SET __ + 12 SET +6 ATTENUATOR SIGNAL AMP. 80 % 32 to 48 16 to 24 20 %, 64 to 96 40 % 64 to 96 K 4g gg g go go REFER TO CALIBRATION REPORT "/A FOR PREVIOUS SAT!SFACIORY LINEARITY COMMENTS: CAL F~cA Axs AL sca;J WELD (s) EXAMINED: U05 RC-OG C 0 A l T' n d Qf D 9 AMINEb LEVEL: ~2C ANil: g [g[ft LEVEL: I DATE: EXAMINER > 1+Ju a kA . REVIEW BY: T LEVEL: DATE: PACE Q._ OF ' \\ i 1
2-5691 USN 50 ULTRASONIC CALIBR ATION NO. TENNESSEE VALLEY AUTIIORITY CALIBRATION C-d 5 O b' DATA SilEET ~ AOJECT: SONP_ UNIT: .1 CALIBRATION DATE: 4-2 7-f 4 ~ PROCEDURE: N.UT. 3 3. REV.: 7 TC: 9 /s -O $ CALIRRATION BLOCK NO.: $O - / 4 TEMP.: D2 *F SIMULATOR BLOCK NO.: 93-8'7J6 INSTRUMENT: kRA a en MODEUTYPE: 1 L 5 N 80 TilERMOMETER SERIAL NO.: 5'73 2 o/ M% SERAL NUMBER: F / 9.5"co COUPLANT: LL LTRA G EL BATCll: C930 6 { EXAM TYPE: SilEAR E IDNG. U RL TRANSDUCER MANUF.: kBA ANGLE VERTFIC ATION SERIALNO, OLLAL H it 9 W /////9 2o S!7.E: (c2 )
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- 1. G AIN: __ 6 4 dB AMPLITUDE:
/o o METAL PATH:.998
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ENCLOSURE 3 TVA PROCEDURE FOR CALCULATION OF ASME CODE COVERAGE FOR SECTION XI NONDESTRUCTIVE EXAMINATIONS 1
' f-: NONDESTRUCTIVE EXAhENATION PROCEDURE - Trecedure No. N-GP.23 TVA Nuclear Power Revinon ( Page 1 of 16 1 'OARECORD W47 970815 271 I CALCULATION'OF ASNE CODE COVERAGE FOR SECTION XI NDE EXAMINATIONS " QUALITY RELATED" 4 IlliIIIlll'l 0352290533 CHAT ISOPM-SECO2 N-GP-28 082997 1 j _b 'l!" 7 Prepared By: - Date: Technical Review: - /, b elIII, Date: E -//- 9 Date: 8 -/ 5~-7 7. ISO Approval: / l l
1:(;- %'l NONDESTRUCTIVE EXAMINATION PROCEDURE Procedure No. N-GP-28 TVA Nuclear Power Revision i Page 2 of 16 i Rev No Date Descriotion 1 l 0 4/3/96' Inidal issue. I 8/15/97 Incorporate TC 97-09. s l i i 9 . > +. - j ii% l i e l 1 O 4 see 4 I
... - -. - _. - - - - _ -. - _. ~ _ _.. ) i pf.' ~ Procedure No. N-GP 28 NONDESTRUCTIVE EXAMINATION PROCEDURE Revision l TVA Nucitar Power Page 3 of 16 1.0 -Scope The scope of this procedure is to preside generic guidelines for calculating the ASNE Section XI code coverage obtained during volumetric and surface examinations. This procedure incorporates - the requirements of Code Case N-460. 2.0 Purpose l f This procedure applies to the calculation of ASNE Section XI Code coverage for vessel welds. J piping welds, and integral attachments. This procedure applies to personnel performing surface or l 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 ASNE Section XL Coverage limitations may be due to an obstruction, interference. geometric l configuration or other applicable reason. l i-3.0 [ References L 3.1 ASNE Sectico XI 1989 Edition 3.2 ASNE Code Case N-460 4.0 Definitions Examination Coverage.The percentage of the examination surface or volume obtained l 4.1 ,) during the performance of the examination. Examination Surface-The surface of the weld and base material required to enmined by ~. 4.2 ASNE Section XI using a surface examination method. Examination Volume-The volume of weld and base material required to be examined by 4.3 j ASNE Section XI using a volumetric examination method., ) Scan Limitation-A limit on the ability to scan the surface (s) as required by procedure. ] 4.4 Surface timitation,A, limit on the ability to perform a surface examination of the required 4.5 surface (s) because of an interference. Volumetric Limitation-A limit on the ability to scan the required examination volume 4.6 because of the geometric configuration, a physical interference, or a metallurgical condition of the material being examined. 4 4 i E l /
- ~. - _ _ _ - -- y) h 1 r NONDESTRUCTTVE EXAMINATION PROCEDURE Procedure No. N-GP-23 i TVA Nuclear Power Revision 1 Page 4 of 16 i. 1 I 5.0 Genera! 5.1 During the performance ofinsenice inspections. ASME Section XI requires enmination coverage to be essentially 100% of the weld area or volume. For examination coverage less than 100%. TVA has implemented ASME Code Case N-160 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 1 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 defined amount of base material on each side of the weld. Volumetric examinations specify a particular volume to be examined. The Section XI required examination volume or surface exammation 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 ger.erally constitutes the weld plus j 1/2t on each side of the weld while volume thickness generally constitutes the entire j component-thickness (i.e. full volume). The volume changes with variations in weld j s 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. 7w - 6.0 Documentine and Calculatine Examination Coverate 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 volume. 6.2 When practical, the two b.am path directions for ultrasonic examinations should be performed from two sides of the weld or additional angles employed in order to ma.dmize ceverage. 6.3 If 100% percent of the examination surface or volume cannct be examined, the NDE Examiner should perform the following under the direction of the inspection coordinator or the NDE 1.evel III: 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., Irr in lieu of Afr) in order to maximize, coverage. 6.3.3 Perform alternative NDE methods if applicable. M .m rs, a
~ - - ~. _. _ _. - _. _ _. _ _ _ l l l% NONDES7RUCTIVE EXANGNATION PROCEDURE Precedure No. N-GP-28 l TVA Nuclear Power Revision I Page 5 of 16 6.4 The examiner shall accurately document all limitations. obstructions, interferences, geometne 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 crumates I may be performed by the examiner or the reviewer. 7.0 Calculation Basis 7.1 Volumetric Examinations-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%. For welds with access from one side only due to interference / configuration (e.g. b) 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 dissistilar metal welds. Use of refracted longitudinal waves to penetrate stainless steel weld material will e increase the examination volume coverage by the amount depicted on the examination coverage drawing / 1 ' - 't d) The effects of adjacent component interferences (e.g. welded lug attachments) alo.ng i j the weld length are also taken into account with the reduction in coverage identified j as a percentage of reduced volume. 7.2 A typical method for calculating coverage due to ultrasonic piping limitations is containell in Attachments 2 and 2A. r, 8.0 Surface Examinations - Picing Welds And Integral Attachmentj 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 oflimitation 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 j ~ 4 11ys a w -.w mv w w-e e-
e,, , c.. s: Procedure No. N-GP-23 NONDESTRUCTIVE EXAMINATION PROCEDURE TVA Nuclear Power Rmsien i Page 6 of 16 9.0 Intrasonic Examinations Vessel Welds Examination volume coverage calculations are based upon the following suppositions: 9.1 To achieve full examination coverage nine different scans are required for a typical a) nozale examination. The following may be used for other vessel configurations: 1) 0 degree (weld metal scan) s 2) 45 degree Transverse-scan from vessel side of the weld 3) 45 degree Transverse-scan fror:i nozzle side of the weld l 4) 60 degree Transverse-scan from vessel side of the weld 5) 60 degree Transverse-scan from nozzle side of the weld 6) 45 degree Parallel-scan CW direction 7) 45 degree Parallel-scan CCW direction i 8) 60 degree Parallel-scan CW direction 9) 60 degree Parallel-scan CCW direction , describes ASME code compliance for full volume examination coverage for 9.2 transverse scans in vessel applications. Typical nTethods for calculating coverage due to ultrasonic vessel limitations is contained 9.3 in Attachments 3 A,3B,3C, and 3D. 10.0 Responsibilities i The examiner or designee shall document the amount of code coverage obtained on 10.1 Attachment I after all necessary steps to perform additional examinations has been completed in order to maximize coverage. Attachment I shall be reviewed by another individual with the same or higher NDE 10.2 cerdfication. The NDE Level III or data reviewer shall review Attachment 1 in order to verify that the 10.3 information is accurate and correct. The NDE Level III may recalculate the examination coverage to obtain a more accurate 10.4 value of the examination surface or volume examined. The calculation shall be documented on the exam report. j 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 10.5 nozale bore or flange face may provide complete coverage of the weld.- l If the exanunation coverage indicates less than 90 percent of the required examinatio 10.6 volume or surface, the site ISI supervisor shall be notified. l The site ISI supervisor shall ensure that examination results are accurately docum 10.7 and incorporate results into a Request for Reliefif necessary.
<- ? W.e* : ) NONDESTRUCTNb EXAMINNnON PROCSDURE. I Prc:edtire No. N-GP-20 TVA Nule.tr Power Revision 1 Pase 7 of 16 ATTACHhEb71 ~ e EXAMINATION REPOfTNO. nuAersar VALLEr AumorrrY
SUMMARY
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dE: 0;;j~ I NONDESTRUCTIVE EXANENATION PROCEDllRE Procedure No. N-GP 28 Resision I TVA Nuclear Power Page 8 of 16 a ATTACHMENT 2 J j J 1.25" 1/4" 1/4" .W W ) i 1 CIRCUMFEREN 40.05" (3/8" \\/ l .Y. i .12" Schedule 140 A { 4 Outside Diameter-12.75" 1 3/4,, l Wall thickness 1.125" ^ Circumference-40.05" f TOTAL VOLUME- (.375)(1.75)(40.05) TOTAL VOLUME-26.28 cu. inches e I e; 1-I
f. 5 5 NONDESTRUC1TEEXAhCNATION PROCEDURE l ocedure No. N-GP-28 TVA Nuclear Power Revision I Page 9 of 16 ATTACHMENT 2 A ATTAOMNT 2A - PPNG/ VESSELS 4.E55 I .87 5*-A THAN 2 NCHES N THKXNESS EXANPLE 2 NO COVERAGE FCR 6 POiES N m cumuz / 45 DEGREE LENGTH DUE TO ATTACHMENT .375" Fua.w cm COVERAGE DOWNSTREAM A.2578 SQ.lN y VOL.-(.2578)(6") .500"-B VOL-1.5468 CJJN. ERAGE NO COVERAGE-1.5468/26.28 UPSTREAN NO COVERAGE.0525(100)-5.88% COVERAGE-100 5.25-94.75% 1.75" 45 CRC SCAN-100% 45 CIRC SCAN-100% EXAMPLE 1 98.69% TOTAL CDVERAM NO COVERAGE, FULL LENGTH ASSUNE ALL OTER SCANS =100% ', 100b100h100M60.74-360.74 360.74/4-90.185% TOTAL EXAN COVERA @ A-H/2(A+8) A=.3 75/2(.675+.5) EXANPLE 1 A.2578 VOL.=(.2578)(40.05) FULL COVERAGE-(.375)(1.75)(40.05)-26.28 CJ.lN. WL.-10.32OJJN. NO COVERAGE-10.32/26.28 NO COVERAGE =.3926 (100)-39.26% COVERAGE 10439.26-60.74% d g,
6;? ' i!is NONDESTRUCTIVE EXA.\\CNATION PROCEDURE Procedure No. N.GP 28 TVA Nuclear Power Rev:sion I
- Page 10 of 16 t
ATTACHMENT 3 s I / N: 45 DEGREE-100% ASME SECTON XI COVERAGE (T-SCAN) j t, 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 ARE EXAMPLES OF100% BIDIRECTIONAL COVERAGE (T-SCANS). I i l l I )
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f4 ?r ?* NONDESTRUCTIVE EXA. ENAT10N PROCEDURE Prc:edure No. N-GP 23 \\ TVA Nuclear Power Revision 1 Page 11 of 16 ATTACHNENT 3 A i s ~ 1/2 T-1.5" EN -85" 3/16" [c 1.25" 4 a A A )J V.2 5" d - ( .2-5/8" 2.75" 3.0" 60 D T 1r 1r ,1.5" \\ 1 45 DEG TOTAL VOLUME- (L)(W)(H) e TCI AL VOLUME- (85)(4.25)(3) 41/4-TOTAL VOLUME-1083.75 CU, INCHES i EXAMPLE 1-45T AND 60T SCANS AS SHOWN UMITED FOR FULL LENGTH. EXAMPLE 2 45T AND 60T SCANS AS SHOWN UNITED FOR A LENGTH OF 12 INCHES. L . _,r
Ej; NONDESTRUCTEE EXANGNATION PROCEDtJRE. ! Procedure No N-GP-28 TVA Nuclear Power l Revision 1 j Page 13 of 16 ATTACHNENT 3C AREA 1 2.75" O! DETERMINE TOTAL 1.5" / ;c s T f EFFECTIVE .866 T / COVERAGE A.375 B-2.812 5" 3.0" o.100% l /. 45T-29.76% / 45T-100% 60T45.W H-4.2 5" 4.25 AREA 2 60T-100% cw 6 A A -( = 1.0-DETERMINE AREA EXAMINED-VOL=(12.75)(85)-1083.75 CU.IN. 45Peew-100% 60Pcw-100% A=H/2(A+B) DETERMINE AREA REQUIRED TO BE 60Peew-100% A-4.25/2(.375+2.8125)-6.77 SQ.IN. EXAMINED BY THE CODE. j VOL-(6.77)(851N.)= 575.45 CUBIC IN. TOTAL-785.66 AREA 1 =1/2BH-1/2(.866)(1.5)- AVERAGE-785.66/9 AREA.649 SQ.lN. AVERAGE-87.29% VOL-(.649)(85)-55.165 CU.lN. AREA 2-TOTAL AREA-AREA 1 AREA 2-12.75 SQ.IN..649 SQ.IN.- 12.10 SQ.lN. ^ ^ "( )( }" 2.0 DETERM!NE 45 DEGREE COVERAGE COVERAGE = VOLUME COVERE,D/ VOLUME REQUIRED 45 DEGREE COVERAGE-575.45/1028.585.559(100)- 55.9% e
EI,: NONDESTRUCTIVE EXAhCNATION PROCEDURE , Procedure No. N-GP.28 TVA Nuclear Power l Revision 1 l Page 12 of16 ATTACHNENT 3B s EXAMPLE 1 AREA 1 1.5" / A 1.5" H-2.7 5" 1 B-2.75" 4.25" AREA 2 1.0-DETERMINE AREA EXAMINED. TOTAL AREA =(3)(4.25)-12.75 VOL-(12.75)(85)-1083.75 IN A=1/2(2 75).75)=3.78 SQlN. VOL-(3.78)(851N.)= 321.3 CUBlC IN. DETERMINE AREA REQUIRED TO BE EXAMINED BY THE CODE. 1 AREA 1-1/28H-1/2(1.5)(1.5)-1.125 AREA 2= TOTAL AREA-AREA 11 AREA 2-12.75-1.125 - 11.625 SQN. VOLUME AREA 2- (11.625)(85) VOLUME' AREA 2-988.125 CU.IN. 2.0 DETERMINE 45 DEGREE COVERAGE COVERAGE-VOLUME COVERED / VOLUME REQJIRED 45 DEGREE COVERAGE-321.3/988.125.3251(100)- 32.51% W
9 F.4 ,.d.} l NONDESTRUCTIVE EXAMINATION PROCEDURE ! Procedure No. N-GP-28 TVA Nuclear Powei I Revision ! Page 14 of 16 ATTACH.NEW 3D i N i EXAMPLE 2 45 DEGREE DETERMINE TOTAL AREA NOT COVERED- (AREA 2)-(AREA EXAMINED) COVERAGE FOR AREA NO.T COVERED-11.625 SQ.tN.-3.78 SQ.lN=7.845 SQ.lN. WELD VOLUME NOT COVERED- (7.845 SQ.!N.)(121N.)-94.14 CU.lN. 45 DEG. (NO COVERAGE)= 94.14/1083.75'100-8.68% 0- 100% 60 DEG. (NO COVERAGE)- 67.44/1083.7S*100-6.22% 45T-91.32% 45T=100 l 45 DEG. (COVERAGE)- 100-8.68-91.32% 60T-93.78% 60 DEG. (COVERAGE)-100-6.22=93.78% 60T-100% 45Pcw=100% 45Pccw=100% 60Pcw=100% T 60Peew=100% TOTAL -885.1 TOTAL AVERAGE-88.5.1/9 TOTAL AVERAGE-98.34% i l l
~ n Kg Y NONDESTRUCTTVE EXAMNATION PROCEDURE - I ' Procedure No. N GP 28 TVA Nuclear Power Revision 1 Page 15 of 16 ATTACFB,ENT 4 Examples for calculating code C0verage when examining integral attachments: s EXAMPLE 1-Luc welded on Two sidest ~ l l 1/2* ,~ H 1/2* !Li L2 La i l l l l Hanger clamp around s lL4 Ls. Ls: pipe on this side of j 3*Lu { Lug. l l [ Area to be examined l l~ for ASM: Code coverage. Totai w !d length to be examined = Lt + L2 - L3 +L4 + Ls + Ls Tota! weld length to be examined = 1/2 + 3 + 1/2 + 1/2 + 3 + 1/2 = 8* .. I Total weld length inaccessible = L3 + Le 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! 1/2' F
- -~* 1/2*
j Li L2 La j lL7 j Ciamp around pipe on this side of lug! !L4 / ts Ls. 1/8* l 3* Lug l l l l ~ Total weld length to be examined = Lt + 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+ Le 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%
I O NONDESTRUCTTVE EXAMNATION PROCEDURE Procedure No N-OP 28 TVA Nuclear Power I Rmsion I Pap 16 of 16 ATTACHMEbri 4 A Examples for calculating code coverage when examining integral attachments (cont.): -s Examole 3. Full cenetration lues {S l Clamp around l Li L2 La i pipe-this side I' only! f l[7 . [_ l / l L4 Ls Lej, 2* l l - 2* 4* Lug l l Total weld length to be examined = Lt + L2 - La +L7 + L4 + Ls + Ls + 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 = La + La + Ls Total weld lengtn inaccessible = 1/2 + 2 + 1/2 = 3* Therefore,11* were examined out of 14*, so code coverage is 11/14 = 78.57% Example 4 Luc coverace computation usino area versus lencth Use measurements in example 1 abovel M M l l l l l Hanger around pipe l this side only. f l l 3* Lug l l welded 2 sides l with 1/4* fillet weld. l l t From first example, totallength = 3* 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 long x 1.350 wide = 10.8 sq. in. The length inaccessible is ( W + M* = 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-hmgth. A}}