ML20045H823

Forwards Addl Info for 930128 Submittal of Revised ISI Program,In Response to NRC 930527 Telcon Request.Requested Exam Repts Containing Limitations Associated W/Relief Request 2-ISI-19 Also Encl

ML20045H823
Person / Time
Site:	Sequoyah
Issue date:	07/09/1993
From:	Fenech R TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9307210327
Download: ML20045H823 (46)

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p Tenressee Valley A#mty, Post Othce Box 2000. Soddy-Dasy. Tenrussee 37379-2000 L

Robed A. Fenech V4ce PresidenL Sequwah Nuclear Plant July 9, 1993 i

U.S. Nuclear Regu.atory Commission ATTN:

Document Coatrol Desk Washington, D.C. 20553 i

Gentlemen:

In the Matter of

)

Docket Nos. 50-327 1

Tennessee Valley Authority

)

50-328 SEQUOYAH NUCLEAR PLANT (SQN) - ADDITIONAL INFORMATION FOR IN-SERVICE s

INSPECTION (ISI) PROGRAM

Reference:

TVA letter to NRC dated January 28,1993, "Sequoyah Nuclear Plant (SQN) - Revised In-Service Inspection (ISI). Program" By the referenced letter, TVA submitted up-to-date copies of'SQN's ISI' I

program for Units 1 and 2.

The ISI program revision levels provided in

.l the r'eferenced letter were Revision 20 for Unit 1 and Revision 19 for

]

Unit 2.

No new relief requests were contained in the Unit 1 ISI program; however, the Unit 2 program contained one new relief request (2-ISI-19) to support ISI activities during SQN's Unit 2 Cycle 6 refueling outage.

Subsequently, NRC requested additional information in-order to complete the review of SQN's ISI program. A telephone conference was' held on j

May 27, 1993, between the NRC staff, NRC contract reviewers (Idaho j

National Engineering Laboratory), and TVA staf f, to discuss the ' amount and type of information that would be needed to support NRC review.

TVA -

has compiled the requested boundary diagrams, isometric and : component-

.q drawings, and itemized ISI component information. This information has been mailed separately to the contract reviewers as requested in the telephone conference. TVA's response to the remaining NRC questions is provided in Enclosure 1. provides requested examination reports that contain the limitations associated with Relief Request 2-ISI-19.

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i U.S. Nuclear Regulatory-Commission Page 2 July 9, 1993 Please' note that in accordance with Section XI of the American Society of-Mechanical' Engineers code (IWA-1400), TVA will soon be submitting program l

plans and schedules for SQN's second 10-year ISI interval for Units 1 and

.)

2.

TVA plans to submit these program plans and schedules six months before the end of the first 10-year ISI interval.

The end of the first 10-year ISI interval is September 15, 1994, for Unit 1 and February 21, 1995, for Unit 2.

NRC's review and approval of Relief Request 2-1S1-19 is requested in advance of the Unit 2 Cycle 6 (U206) refueling outage to support ISI l

activities during the outage. The U2C6 refueling outage is currently

)

scheduled to begin January 28, 1994, i

It is important to note that the Unit 1 10-year ISI interval will end on 1

September 15, 1994 SQN Unit 1 is currently in its Cycle 6 refueling i

outage. The Cycle 6 refueling outage is.the last scheduled outage for' j

performing ISI activities within the first 10-year ISI interval for J

Unit 1.

NRC's review of the Unit 1 ISI program is requested.as soon as possible to allow the timely completion of ISI' activities.during the i

current Unit-1 Cycle 6 refueling outage.

l As a separate item discussed during the May 27,'1993, telephone conference, TVA noted that the safety-evaluation' reports (SERs) issued for SQN's first 10-year ISI programs (reference NRC' letters dated April 19, 1990 February 7, 1991, October 21, 1991) requested that~any significant program changes such as additional requests _for relief should.

be submitted for staff review and should not-be implemented before approval by NRC.

TVA has complied with the SER recommendation and submitted significant program changes for NRC's review and approval.

In j

addition, TVA has periodically submitted to NRC up-to-date copies of j

SQN's ISI program for information purposes. Frequently, these copies would contain minor program changes and would not contain significant.

j changes such as relief requests.

Because of the large size of these

.]

reports and the administrative time associated with preparing these j

informational copies, SQN will no longer be submitting informational I

copies of SQN's ISI program.

Significant changes to SQN's ISI program will be defined as new relief requests, which will continue to be submitted to NRC in accordance with 10 CFR 50.55(a)(g)(5)(iii). Other changes to SQN's ISI program that do not involve a new relief request q

will be processed in accordance with 10 CFR 50.59.

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U.S. Nuclear Regulatory Commission Page 3 July 9, 1993 Please direct questions concerning this issue to D. V. Goodin at-(615) 843-7734 Sincerely, 4

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Robert A. Fenech Enclosures cc (Enclosures):

Mr. D. E. LaBarge, Project Manager U.S. 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 11 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323-2711 i

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,j ENCLOSURE l' i

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SEQUOYAH NUCLEAR PLANT FIRST 10-YEAR INTERVAL INSERVICEL INSPECTION TROGRAM, REVISIONS 20 AND 19 i

RESPONSE.TO ADDITIONAL QUESTIONS FROM NRC i

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i The following provides the requested information for specific NRC questions to support NRC's review of Sequoyah Nuclear Plant's (SQN) l in-service inspection (ISI) program for Units 1 and 2.

-i NRC Question f

i

" Augmented examinations'have been established by.the NRC when added assurance of structural reliability is deemed necessary. A substantial number of augmented examinations are being performed at Sequoyah Nuclear-Station, Units 1 and 2.

However, it appears that augmented examinations per Branch Technical Position MEB 3-1, 'High Energy Fluid Systems, Protection Against Postulated Piping Failures in Fluid Systems Outside j

Containment,' may have been omitted.

Please address the degree of compliance with this document during the first 10-year ISI interval'."

TVA Response SQN Final Safety Analysis Report Section 3.6.2.2.5 states that, "The criteria for piping which extends from the containment penetrations to j

the first isolation valve outside containment are identical to that used for the remainder of the piping.

Break exclusion criteria in these areas were not utilized for SQN."

The only application of the MEB 3-1 criteria has been in support of a i

short-range justication-of-continued-operation (JCO) evaluation-performed for Incident Investigation (II) II-S-92-059.

In order to allow continued

.i operation under this JCO, the break location exclusion criteria were l

invoked. However, it was made clear in the JCO.that the ISI inspections' had not been performed in accordance with the criteria, and:were not expected to be performed for this short duration. NRC responded to this JC0 by letter dated February-11, 1993, acknowledging the conditions set-1 forth in the JCO.

v In conclusion, SQN's licensing basis does not. include the performance of augmented ISIS to the criteria set forth in MEB 3-1.

The extent of adherence to this criteria is therefore not applicable to SQN.

i NRC Question

" Plans for inservice examination of the Reactor Pressure Vessel (RPV) welds should address the degree of compliance with Regulatory Guide 1.150, ' Ultrasonic Testing of Reactor Vessel Welds During Preservice and Inservice Examinations. '

Provide a discussion regarding Regulatory Guide 1.'50 and the reactor vessel examinations being performed at Sequoyah Nuclear Plant, Units 1 and 2.

In Section 20.5 of the Program Plan, augmented near surface examination of the RPV nozzle cladding is discussed. Are the same techniques being used to examine cladding on the vessel interior? Please provide a discussion of the near surface examinations and resolution with regards to finding service-induced flaws'and the use of electronic gating as related to the volume of material near the surfaces that is not being examined."

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TVA Response RG 1.150 is referenced in Section 4.0 of each unit's ISi program.

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The 10-year in-service examination just completed on SQN Unit 1 RPV was in compliance with RG 1.150.

The technique used in the augmented near-surface examination of the RPV nozzle cladding was also used to examine the required near-surface vessel 1 interior.

The near-surface examination technique performed on SQN RPV areas and nozzle bores has been demonstrated to be capable of detecting a crack' at-q the clad-base metal interface 250 mils long and.110 mils deep.

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4 The near-surface areas were examined, including the clad-base metal 1

interface area.

No near-surface areas were " gated-out."

i NRC Question i

" Paragraph 10 CFR 50.55a(b)(2)(iv) requires that ASME Code Class 2' piping welds in the Residual Heat Removal (RHR), Emergency Core Cooling (ECC),

I and Containment Heat Removal (CHR). systems be examined. These systems:

should_not be completely exempted from inservice volumetric examination l

based on 74S75 Section XI exclusion criteria contained in IWC-1220 or based on wall thickness.

The staff has previously determined that'a 7.5%

augmented volumetric sample constitutes an acceptable-resolution at j

similar-plants.

Based on the exclusion criteria of IWC-1220 of the

^

74S75 Code, it appears that Section 8.13.2 of each Program Plan exempts i

Class 2 piping welds in the RHR, ECCS, Land CHR. systems from inservice examinations when both the design pressure and temperature.are less'than.

-j or equal to 275 psig and 200*F, respectively.

In addition, it appears -

l that the Class 2 Safety Injection System may have been exempted from volumetric examination based on wall thickness.

Please provide a j

discussion on the examination of Class 2 piping welds and an itemized j

listing of all Class 2 piping welds included in the RHR, ECC, or CHR.

systems."

TVA Response The SQN ISI programs are based on the 1977 Edition, Summer 1978 Addenda, of ASME Section XI.

However, Class 1 and 2 piping welds are examined'in accordance with the 1974 Edition, Summer 1975 Addenda, of ASME Section XI as required by 10 CFR 50.55a(b)(2)(iv)(A) for Class 2 RHR, ECCS, and CHR.

systems and as permitted by 10 CFR 50.55a(b)(2)(ii) and

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10 CFR 50.55a(b)(2)(iv)(B). This includes utilieing the exemption or-exclusion criteria of IWC-1220 of the Summer 1975 Addenda for piping welds, including the pressure and temperature exemption (the chemistry exemption was not utilized).

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. The volumetric and surface examinations of the safety injection' system Class 2 piping welds are identified _in Table B of Attachment-4 of each unit's ISI program.

9 Safety evaluation reports (SERs) have been issued forLthe SQN Units-1 and 2 ISI programs (first 10-year interval). These SERs_and associated i

technical evaluation reports specifically evaluated _the ISI' programs for the correct application of system or component exclusion criteria (consistent with IWB-1220, IWC-1220, and 10 CFR 50.55a[b]).

The SERs found the ISI programs acceptable.

NRC Question 1

l "The control of water chemistry to minimize stress corrosion described in paragraph IWC-1220(c) of the 74S75 code is not an acceptable 1 basis for exempting components from examination because practical evaluation, review, and acceptance standards cannot be defined. Therefore, any components that have been exempted based on Paragraph IWC-1220(c) of.the 74S75 Code should be examined. Verify that the chemistry control exclusion is not being used or that the ISI Program Plans will be revised to include examination of these components."

TVA Response The chemistry control exclusion is not used-for the SQN ISI-programs.

j l

NRC Question

]

" Request for Relief 1-ISI-4:

In an' Safety Evaluation Report (SER) dated i

February 7, 1991, relief was granted provided that the same welds on the-other steam generators were examined such that the total length.of weld examined' equaled 100% of the Code-required weld length. The current i

revision of this request does not reflect this condition.

Please confirm that this provision has been or will be met'"

TVA Response i

NRC issued an additional SER on October 21, 1991,- that addressed the ISI-4 request for relief. This SER approved performing a volumetric

=

examination to the extent practical on one S/G lower-cone transition weld.

NRC Question

" Request for Relief 2-ISI-19: Relief is requested from performing the j

volumetric examinations of five Class 1 piping welds to the extent.

i required by the Code. The basis provided with this request does not-I

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adequately describe the limitations..In-addition,.the estimate of.the Code-required volume that can be examined appears low.

Please provide drawings and a more detailed description of the limitations."

TVA Response The examination reports are provided in Enclosure 2 for the. welds identified in Relief Request 2-ISI-19.

These reports provide the' requested information concerning the examination limitations.

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ENCLOSURE 2 SEQUOYAlf NUCLEAR PLANT l

1 FIRST 10-YEAR' INTERVAL INSERVICE'

'l INSPECTION PROGRAM, REVISIONS 20 AND 19 EXAMINATION REPORTS CONTAINING THE LIMITATIONS ASSOCIATED WITli RELIEF REQUEST.2-ISI-19

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4 Examination Limitations Associated With Relief Request 2-ISI-19 The examination limitations of Welds RC-19-SE, RC-26-SE, and RC-27-SE are

- in part because of the weld configuration (see Attachment 2).

The configuration only permits an ultrasonic examination (UT) in the axial direction from one side of the weld.

The material (cast stainless) does not permit a two-beam path examination from one side. Also, the weld' configuration, large " footprint"'(see ) and focused ef fect of the transducers required to penetrate the material, does not permit the sound to impinge the weld root area during circumferential scans. Therefore, only one of the required

- four-beam path examinations was completed (25 percent).

The examination limitations of Welds CVCW-1 and RCW-13 are because of weld configuration (see sketches). The UT was' performed from the nozzle i

forging that permits a two-beam path examination from one side.

However, the configuration does not permit circumferential scans in two directions (approximately 50 percent).

s Examination Requirements

Reference:

American Society of Mechanical Engineers,Section XI, Appendix III, 1986 Edition j

Paragraph 111-4420. " Reflectors Parallel To The Weld"

".. coverage of the required examination volume in two-beam path directions.

The examination shall be performed-from two sides 1

of the weld, where practicable, or from one side of the weld as a minimum."

Pcragraph III-4430, " Reflectors Transverse to The Weld" t

... examine the weld root in two directions along the weld..."

TVA satisfies the requirements of paragraph III-4420 by performing Scans 3 and 4 (see Attachment 1).

TVA satisfies the requirements of paragraph III-4430 by performing Scans 5 and 6 (see Attachment 1),

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Tennessee Valley Authority PIPING EXAMINATION DATA SHEET R-444 4 Pm3ect:

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TVA WALL THICKNESS REPORT NO:.

PROFILE Office of Nuclear Power SHEET (d - (4 4 4 5 PROJECT:

_ TOM WELD NO:

8,/g _{ c' unit:

J SYSTEM: Ic' DOE #

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4 MANUALULTRASONIC REPORT NO.

Tennessee VaHey Authority PIPING EXAMINATION i

DATA SHEET R-n W 5 Project S O K1 Unit:

ExaminationDate:

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Ae4c3dR e c e t n,a ExamSurface:ID 0 ODf3 Weld I.D.:

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RESOLUTION Office of Nuclear Power SHEET R - L 4 L43,7,,py

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M t-108 9H4I V

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'TVA WALL THICKNESS REPORT NO:

. l PROFILE

. Office of Nuclear Power SHEET R'N N..

PROJECT:

IOM WELD NO:

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Record Thickness Measurements As Weld

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TVA 19668 (ONP-6-BS)

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MANUALULTRASONIC REPORT NO.

Tennessee Valley Authority PIPING EXAMINATION DATA SHEET R-449 Na R%

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A RESOLUTION Office of Nuclear Power SHEET

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1/A MEASURED AMCLE-T R DAC INSTRUMENT SETTING 100 %

I 90 pw.ct FREQUENCY

/MM7 M

80

, _ fy g

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10 DAMPlNO O OFF O FIXED D OTHER //fa+033 REJECT E OFF C ON 0 1 2 3 4 5 6 7 8 9 10 REP RATE 5 FIXE O OTHER

> > /A RANGE SWEEP / METAL P Tp 7 -- -

SCREEN R ANCE: 0 79SM CALIBRATION VERIFICATION NMEM S/N:

FIELD StMULATOR:

k"8DM M

CA RATION REFLE CT OR

/fg g,

MAXIMUM I

AMPLITUDE

[ f0 M

FINAL Mg CALIBRATION MET AL P ATH gg+

/

TIME

/

L VERTICAL SIGNAL 1 100 90 80 18 de 50 40 30 20 10 h

b* W WO 3 s* ' 30 c9 Y hO

/C' l0 Y

A R

SIGNAL 2 SRALL EQUAL 50% OF SIGNAL I 2 5% OF FULL SCALE ATTENUATOR T

TESTER G AIN SET 6

12 SET

+ 12 SET

.6 SIGNAL AMP 80 %

32 to 48 16 to 34 10 %

64 to 96 44 %

64 to 96 i

E 4;L M

. yg j

fg l

^//4 DAILY LINEARITY CHECKS SAT 15 FACTORY RI7T.R TO CAL, NO j

K IN ATIONS COM MENT S: M0g O Vnu/- /

//b 8 b [ftK REVIEWED 8 :

A 1-f EXAMINER _

d

' N MSE M 7!

DA j

94-C t LEVEL:

M M-DATEM 1

DATE:

7M7 LE L:

EXAMINER:

t Y & %-h-n i

gi y,/yg w]q e u p, f

PACE OF

+

t,9engu LEVEL:

• DATE:

TV A 19674 (NP 5-89) j

^ ' ' " " ^ * " " -

ULTRASONIC TVA CALIBRATION DATA SHEET c-p.p V, p ex3 PROCEDURE NO:

//- /M /[

f PROJECT:

. T/d A/

i REVISION NO:

/O PCR NOF dllA

,$f7; fpf

[/M egg,,L g,,,

TRANsoucER:

/M 9/

CAL. sLx. THKMs: ' / 2/ -7 bbJ//77/4qrg SEniAL MuusEn-O.NO M / N INSTRUMENT:

m2E:

• 3 Y " FREQ:

1. 1. E,

//O //7 couPLANT:

//277/A ujj MODEL/TY PE:

M,h/M BATCH NO:

Ty' L

ENGW:

I4/ff3

///7 OL M UDIN AL.

SERIAL NO:

NOMIN AL ANGLE:

TYPE C#

[

g jg MEASUMED ANGLEt DAC INSTRUME NT SETTING 100 l l I i

/ /W E-FREOUENCY lg yok l A

COARSE O FINE AX1AL SCAN M

80 gl l l C AIN L

\\l l l COARSE FIN CIRC SCAN OARSE INE AXIAL SCAN

[p NOTCH SENS.

D 40 CARSE FINE CIRC SCAN N Y W5 E

30 DELAY 20

' Th w SWEEP /MATL. CAC

/ M

'7' T FILTER El CFF O ON O FIXED

$ g' 10 DAMPING O OFF O FIXED E OTHER //S*'aw725 REJECT E OFF C ON 0 1 2 3 4 5 6 7 8 9 10 REP RATE g FIXED C OTHER v/A RANGE SWEEPJWFTAL/ATH- # I SCREEN RANGE: 0-m FIELD SIMULATOR:

NU. SH: Y bM CAL!BRATION VERfFICATION REFLECTOR

'[/[ M Al CA RATION ME ff y g

f'

^

MAXIMUM AMPLITUDE 6Oh b

/

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'/

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METAL PATH

/. j *

'j-A E

/

l l

/

L VERTICAL SIGN AL IDR 90 80 l 70 60 50 40 30 20 l 10 f

E SIGN AL 2.

50 N

l l

R SIGNAL 2 SHALL EQUAL $0% OPSIG{AL 1 25% OF FULL SCALE 3

(, M 2 7 4 [e"..g/st/ &

ATTENUATOR r

TESTER G AN SET

.6 12 MET

+ 12 SET

.6 C

SIGNAL AMP 80 %

32 to 48 16 to 24 20 %N 64 to 96 44 %

64 to H

.N j

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2N DAILY LINT.ARITY CHECKS SATISFACTORY REFER TO CAL, NO K

EX AMIN ATIONS COMMENTS:

NME O V6U)- /

r!/M61Il

.d4'I[v REV EWED f:

ANil; EXAMINER

/[.

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EXAMINER:

2-7

~

PAGE OF O/M w e v A c. (. M e ixir vt LEVEL:

D ATE-TVA 19674 (h7 5-89)

o yyp WALL THICKNESS REPORT NO:

PROFILE Office of Nuclear Power SHEET R -L 4l f 4

PROJECT:

3 /)A/

WELD NO:

0 V A fj]. l UNIT:

M SYSTEM:

d /d Record Thickness Meesurements As Wald

• Wold Edge Indicated, including Wold Width, Centerline Edge To Edge At o' l:

2.5 "

2.5 "

e Position O'

90*

180*

270*

is

/

Ewd/_

ma

/

Side l

Side 2

/g g

k J/A

/

4

/

N

/

[3]

g/g Q

N/h /

CROWN HEIGHT:

(( MSM CIAMETER:

CROWN WlOTH:

O0

/7 &"

WELD LENGTH:

fl 0 W n

BEA w W Genwa 77W m ige, C[

i

?

\\

f

\\

x kf t e c i

l hhh Nl k-E 1

1

(\\CL*F

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REVIEW ED BY:

.Y l

L l

DATg:

• L 9"A ATE: 4/"1 <Y V k LEVEL:

h/Jt-9P M% f SChk &2 6-4 2.

I pact 3 y

7 DATE-TV A 19668 (ONP-6-88)

MANUALULTRASONIC REPORT NO.

Tennessee Valley Authority PIPING EXAMINATION DATA SHEET R-m s--

Project:

5&/

Unit A

P'amMationDate: __ Jh>/7A System-d /g StartThne: M VO

'EndThne: //.- 35 '

FramSurface:ID O OD 0 Weld I.D.:

C //' LJ - /

MaterialType:CSOSS ECSCL OCCSS O Config: Aeh e N TO:

[ fold /E6 Surface Temp: 7/'7

• F Pyro No: 57/ o o4 FLOW '

CalibrationSheet No.

C 267u /*'C. 2d w / fd r4 z-Procedun:: N-UT-

/f Rev. - /0 TC: s/M FramMntion Amle M **

d g,

Wo

Reference:

re/ra y Cire. Scan Sensttivity A#4 a

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Reference:

f /75ev Psa<!/S eP&'cw/& AxialScanSensitivity S'S dB d4 dB MSX E'"" NEN Indication Information-Ind.

L (in) Fruru Ref.

AtMaxAmp No.

L1 biax!L2 WMax lMPMax %

C 31; Ang.

PW. ek

/

'27f IS /) ll?

/,S' J. 4 7 57>%

3 40*

3

'K' /

I RemntLsil 1mitations: A9) (1//2C SG/4d5 fB2fortinE2) h2 78 lKbitLs o A 8tt/4'cH (%/MEs7~o v s l'l1Hfon%le(n 80%

$aYrsse C $ k rs c d.

R /$ d & W Cbe kz.-

If f

U

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_Y Af//

Framiner:

h'-[ Y7/

Level 7

Date: 7-70 Exammer:

Reviewed by: 7 %N $NL Lv3L Date: 3 '%-92.-

Page 4

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' N o'N'o" ae'oa' "o RESOLUTION Office of Nuclear Power SHEET k - LJ l45-L PROJECT: SQd PROCEDURE: u-UT-t 9 REV: 1O PCR: $4! A NCE METHOD

• UT h PT O ist O vT O CIRCUMF(Rf MTI AL SYSTEM: M E M i c

• L.

\\/o Lv" g m, u,-er o u WELD TYPE:

Lo mTuomAL 0 oT*.tn WELD NO:

CUCw-1 CAL. SHEET No. (S) CO A2 Y, Ce.2 7 5' EX AMINER: H 9e m sertm4 1

EX AMINER: S. N U flT 2 J.L.

p t *J b 1 c m o d *(O t5 A

Nod C E o M E T*rt s c.

Q G. n E cTo R Crto n A *.J

!NCLossoa WPE FLAQ tu TVE uetb M AT9.C i A L.

T'14 t 1 t s R

.S~O % one S Po7~ I Alb / C &*T7 0AJ a s ~iH pJ o i

M A'ibK die 4 f N S/O ^LT.

IU R e e o /2 0 & AIC E LAITH M A S.M.E. Con 2 SGCT1o& W i

i 4 T7 Gbi -n o 4 t J t TH 9-6G6HDA 77-/ftO' CH Sunnft /972 J

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i 0C A/dUfl/EWR

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2C!

LEVEL:

D ATE: 3 D LEVEL:

DATE: S* N N' D ATE:

Mk2

[

PAGE OF TVA 19672 (ONP 6 83)

~

l T. V. A. LIMITATION REPORT l

i froject: SGG Unit: 2.

Report No. __R-hul/6

' System: c4 emes vouune courace Veld No.:

e vce - i I

~

SUHFACE EXAMIN ATIONS Area To Be Examined (Length x Width - A)

A-Area 0f Limitation (Length x Width - Al)

A l-Percentage of Coverage (A - Al/A)

VOLUMETRIC EXAMINATIONS Parallel <

Example

> Transverse i

Obstruction M

\\

/

\\

1 l

\\

/M

\\

\\/

o J

1 h - Area of no examination

1. Compute Area a x 1

- Asq

i. o c

2. Multiply Asq by Weld Length

- Vt (Volume Total) n. co

/

.Io

3. Compute Area Not Covered

-a

4. Multiply "a" by Weld Length

- VI (Volume Limited) l 'N 1

90% M sed

5. Percentage of Coverage

- (Vt - Vl/Vt)

NOTE: Compute in a similar manner for indications perpendicular to the weld.

vi e uom4 Reviewedby- )/ h M reparedby-ek

~

Date: d2d92 Level:

RL-Date: 3 - 2 b clMevel:

T

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'~~ RCY~23 2-RC-co6w) e noe ao c

r RCS-049 MA TERIAL srECIFICA TIONS

--L__--_J._.--L------

see m o. aoenn un e=senartoocvmess-eaus m' girE ue eq se ace.es

,L.1%fr-l

.LM!*:k SEAM ESS STAIM ESS STEEL

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FCwGEO STAIM.Ess STEEL-50CnET bELDED A STN A-tB2 F-304 RCS-205 -

~~- Rrr"-Is 2* BORED la NA TCH SCH 160 PIT 1" W -93

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ULTRASONIC TM i

CAllBRATION DATA SHEET c _ o n c3 M~ b'[ ~ /8

$hh PROCEDURE NO:

PROJECT:

REVISION NO:

/O A//A UNIT:

PCR NO:

TRANSDUCER:

k'8A CAL. SLK. NO:

IO bf

/'7297 CAL. sLK. mg: ""/. 63

' EAU 7p g gg sEntAL Num,n INSTRUMENT:

'375

"* I' 5'" d ?

oeres'uz US h - 10 Coueu=r:

MODEL/TY P E:

I*bl7M /b

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CABLE TYPE /LENGTN:

Ibl9I3 o

7,g C Lomo:TuoeN AL SERIAL NO:

58MEAR o

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Ib COTMER WEASURED ANGLE-DA0 INSTRUMENT SETTING 100 b

FREQUENCY bj COARSE N/A FINE 7/.Y AX1AL SCAN A

o M

80

\\

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FILTER O OFF 0 ON 8 FtXED 10 DAMPlNG O OFF O FlXED B OTHERfIO *H A15 REJECT S OFF D ON 0 1 2 3 4 5 6 7 8 9 10 REP RATE

.g FIXED O OTHER RANCE 10 SWEEP / METAL PATH a

SCREEN RANGE: 0,,

c M PAS scw: 6 0 3 2 4F3 CALIBRATION VERfFICATION FIELD SIMULATCR:

VERIFICATION TIMES REFLECTOR

$QN

/

CA R ATION N0 c-lo3.'dB

/

7 AMPLI UDE CALYRATICH ' ~ g "!

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METAL PATN l.$

TIME L

VERTICAL SIGN AL i 100 l 90 80 7e de l 50 40 30 l 20 l 10 hf 5-YO 3{

30 26" 20

/ $~ l /C

.$~

SIGNAL 2 50 1

y SIGN AL 2 SHALL EQUAL 50% OF SIGN AL i 15% OF FULL SCALE l

j ATTENUATOR T

TESTER G AIN SET 6

12 SET

+ 12 SET

+6 C

SIGNAL AMP 80 %

32 to 48 le w 14 20 %

64 to M 44 %

64 w H

/,/0 7c 2C 'fi 79%

l

' M 80 j

"/*

DAILY LINEARITY CHECKS S AT1SFACTORY REFER TO CAL NO K

EX AMIN ATIONS.

EKRMadED FRoe51 B R A e/C e4 MMENTS:

)

co vacc.n oa Seo s c4a y'.

R c uJ - 13 A_I[dkd 84,, Jo hl RElEWED '.

VI G ANll:

EXAMINER:

.7!26!f 2 b

WO(7D LEVEL: 3 DATE:

7/7/1

_ QATE: 3 D

DATE:

EXAMINER:

to b A4 W [7Eoa LEVEL _

d% T hefiu.. 3 :sc-92 2

OF 4, A e'

/ /

PAGE LEVEL:

I DATE: 3/24/92 1YA 19674 (NP-5-89)

-tos et

...s

'TVA

• ^" T"'ck"5SS PROFILE Office of Nuclear Power SHEET R$ 2p?

1 PROJECT: -$ON WELD NO:

kCLAI-l3 R e. Acxo R. CwlMr.

j UNIT:

2 SYSTEM:

Record Thickness Measurements As Weld

• Wold Edge Indicated, including Wold Width, Centerline Edge-To-Edge At O' 2.5 "

I:

2.5 "

l.

1 5

% tion O'

90*

180*

270*

N

^

GN h

Side l

Side h

2 l

% \\

3

\\

1 4

B N

N b llb DIAMETER:

?

CROWN HEIGHT:

O[8 CROWN WIDTH:

WELD LENGTH:

3 r

Q YD b

y V)

Ws

~

9%

V-h n

s m

n et /

N sd 1

s

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dg d

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EX A MINE R:

/2 W REVIEWED BY:

.m

[M/hh LEVELr

.g L D ATE:

M24 dt, 3

-o, g, A caTE:

,,c, TVA 19668 (ONP 6-88)

E

TVA MANUAL ULMASONIC REPORT NO.

EXAMINATION DATA SHEET (2, - @ s. 7 I

Project:

50Al Unit-

-7 Material Type: OcS E SS O Other System:

M'g o e fe r r ce / o., +

-Exam Surface: Olo 9OD Weld I.D.:

R( W fj Surface Temp: M F Pyro No: 17G %

Config: Ar m A (,4nethcATo:

M.*

Exam Start: kf' //v)

( O'. /f / g Exam End:

4(*- // lo 60'. f / go Cal Sheet No: //6 4- 02 F9 60 C-C 9o db Procedurs:

Al-uT 19 Rev: 10 PCR N4 Ax Scan Sens: 45' 5 4t,/ W m 9 db Lo Reference 8a lo

1. f.,

Wo R e f e re n c e F-c Tu o,, r-L.,,, + I< e % 4 t,)

Ind L (In) From Ref At Max Amp Max Nominal Indication Type No Amp Scanning Remarks L

L MP 1

Max 2

Max Max . D A C Angle I

~

J +

~

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2. 8 6 ~'

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• 60' KSe s e T,,r-e ; n. + 1_. 3 M* e t...,. m,,,/, q 1, u&

Me,4cese n p n r Emiu,.ies,.

Sketch:

Remarks:

Me Cin c Sc ad Acuesma p ur ro B:eao fac~5 i

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7k

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'" 'o^T'o" a'"oa' "o=

RESOLUTION Office of Nuclear Power SHEET S - h46 7 PROJECT:

$Qd b

PROCEDURE: M-UT-(R REV: 10 PCR:

U NIT

• 2 NDE METHOD:

UT 3 PT O ur O vr O 0[nUTuonk"Norwen Ert**< d Co w se m mas SYSTEM: 2F e ci'e>c Go ova.sr WELD TYPE:

WELD NO:

RC L J - O CAL. SNEET NO, (S) d-039o EX AMIN ER: R. G <t u s y E

EX AMINER:

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