Text

American Society of Mechanical Engineers (ASME) Inservice Inspection (ISI) Program Request for Relief 1-ISI-14 and 1-ISI-15
	ML040900299
Person / Time
Site:	Watts Bar
Issue date:	03/19/2004
From:	Pace P; Tennessee Valley Authority
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML040900299 (74)
	v • d • e

Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 MAR 1 9 2004 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTN:

Document Control Desk Washington, D. C. 20555 Gentlemen:

In the Matter of

)

Docket No.50-390 Tennessee Valley Authority WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 -

AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) INSERVICE INSPECTION (ISI) PROGRAM REQUEST FOR RELIEF 1-ISI-14 AND 1-ISI-15 The purpose of this letter is to request relief from ASME Section XI Code required examinations due to limitations which were identified in the WBN Unit 1 Cycle 5 refueling outage.

These requests for relief are being submitted in accordance with 10 CFR 50.55a(g)(5)(iii).

TVA stated in the ASME Section XI ISI Summary Report for the Fifth Refueling Cycle dated January 14, 2004, that two requests for relief were required to be written for components examined during the inspection and those requests would be submitted under separate letter.

The required examination coverage could not be achieved due to configuration of the pressurizer nozzle-to-vessel welds and safety injection system piping welds. provides Request for Relief 1-ISI-14 for the pressurizer nozzle-to-vessel welds. provides Request for Relief 1-ISI-15 for the safety injection system piping welds.

Pnoted on -cyCdd paper

U.S. Nuclear Regulatory Commission Page 2 MAR 19 2004 There are no regulatory commitments being tracked from this letter.

If you have any questions concerning these relief requests, please contact me at (423) 365-1824.

Sincerely, P. L. Pace Manager, Site Licensing and Industry Affairs Enclosures cc (Enclosures):

NRC Resident Inspector Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381 Ms. Margaret H. Chernoff, Project Manager U.S. Nuclear Regulatory Commission MS 08G9 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303

ENCLOSURE 1 WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME)

FIRST TEN YEAR INSERVICE INSPECTION INTERVAL REQUEST FOR RELIEF, 1-ISI-14

ENCLOSURE 1 WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME)

FIRST TEN YEAR INSERVICE INSPECTION INTERVAL REQUEST FOR RELIEF, 1-ISI-14 I. Summary:

This request for relief addresses the pressurizer nozzle full penetration welds.

The design configuration of the pressurizer nozzle to vessel welds precludes a 100 percent ultrasonic examination of the required volume for the spray nozzle-to-vessel weld WP-11 and the four safety/relief nozzle-to-vessel welds WP-12, WP-13, WP-14 and WP-15.

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.

An ultrasonic examination was performed on accessible areas to the maximum extent practical, given the physical limitations for welds WP-11, WP-12, WP-13, WP-14 and WP-15 during the Unit 1 Cycle 5 Refueling Outage.

The design configuration limits ultrasonic examination to approximately 68 percent for the five welds.

It was concluded that performance of an ultrasonic examination of essentially 100 percent of full penetration welds in the pressurizer nozzle to vessel welds, WP-11, WP-12, WP-13, WP-14 and WP-15, 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.

The WBN Code of Record is ASME Section XI, 1989 Edition.

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

The WBN pressurizer is of the same design as TVA's Sequoyah Nuclear Plant's (SQN) Units 1 and 2 pressurizers.

SQN has experienced the similar examination coverage during inservice inspection of these nozzles.

NRC approved Sequoyah Nuclear Plant's request for relief 1/2-ISI-09, (Nozzle RCW-15 which is equivalent to WBN's spray nozzle WP-11), in a safety evaluation dated February 9, 2000.

SQN's relief requests 1/2-ISI-19, which is the same as WBN's safety/relief nozzles WP-12 through WP 15, was approved by NRC in a safety evaluation dated August 8, 2003.

El-1

ENCLOSURE 1 WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME)

FIRST TEN YEAR INSERVICE INSPECTION INTERVAL REQUEST FOR RELIEF, 1-ISI-14 II.

Component:

Five Pressurizer Nozzle Welds - Examination Category B-D Weld Identifiers WP-11, WP-12, WP-13, WP-14, WP-15.

Reference ISI drawing CHM-2570-C-01 (Attachment 1)

III. Code Requirement:

ASME Section XI, 1989 Edition, Table IWB-2500-1, Examination Category B-D, Item Number B3.110, Pressurizer Nozzle-to-Vessel Welds.

Examination requirement as defined by Figure IWB-2500-7(b).

(Attachment 2)

IV. Code Requirements From Which Relief Is Requested:

Relief is requested from performing the required volumetric examination on essentially 100 percent of the full volume of the pressurizer nozzle-to-vessel welds.

V. Basis for Relief:

The design configuration of the pressurizer precludes an ultrasonic examination of the required volume for the following nozzle-to-vessel welds:

WP-ll, WP-12, WP-13, WP-14 and WP-15.

The design configuration limits ultrasonic examination to approximately 68 percent of the required examination volume as calculated in the Examination Reports (See Attachment 3).

VI. Alternative Examination:

In lieu of the code required 100 percent ultrasonic examination, an ultrasonic examination was performed on accessible areas to the maximum extent practical, given the physical limitations of the pressurizer nozzle-to-vessel welds.

(See Attachment 3 Examination Data Reports).

VII. Justification For The Granting Of Relief:

1)

The design configuration of the subject nozzle-to-vessel welds precludes ultrasonic examination of essentially 100 percent of the required examination volume.

In order to examine the welds in accordance with the code E1-2

ENCLOSURE 1 WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME)

FIRST TEN YEAR INSERVICE INSPECTION INTERVAL REQUEST FOR RELIEF, 1-ISI-14 requirements, the pressurizer would require extensive design modifications.

The physical arrangement of the subject nozzle welds in conjunction with the close curvature of the outside wall surfaces of the nozzle precludes effective 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 76 percent of the required ultrasonic examination volume for flaws transverse to the weld was performed from the vessel head side.

Total combined examination coverage of welds WP-l1, WP-12, WP-13, WP-14 and WP-15 is approximately 68 percent of the code required volume.

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 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 ultrasonic from the inner surface are impractical when weighed against the radiological concerns.

WBN has not opened the pressurizer manway since beginning operation and does not have a history of radiological conditions inside the pressurizer.

The estimated radiological conditions referenced in SQN's similar request for relief were determined to be the following:

35-40 rad/hour beta (uncorrected) 10-12 rem/hour gamma 1 rad/hour per 100 square centimeters Maximum stay time to maintain exposure to < 1 rem is approximately 5 minutes.

Special clothing, including respiratory protection, would be required for protection from the extremely high contamination levels and from the high beta dose rate.

Industrial safety would also be a major concern (heat stress, confined space, and E1-3

ENCLOSURE 1 WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME)

FIRST TEN YEAR INSERVICE INSPECTION INTERVAL REQUEST FOR RELIEF, 1-ISI-14 climbing/falling hazards).

Estimates are based on actual experience inside primary components such as steam generators.

3) Percentage sampling approach of ASME Section XI code, in combination with examinations performed on similar items provides reasonable assurance that significant degradation if present would have been detected.

It is concluded that performing an ultrasonic volumetric examination of essentially 100 percent of full penetration welds in the pressurizer nozzle-to-vessel welds WP-11, WP-12, WP-13, WP-14 and WP-15, would be impractical.

In addition, it would be impractical to perform other volumetric examinations which may increase examination coverage.

A maximum extent practical ultrasonic examination of the subject welds provides reasonable assurance of an acceptable level of quality and safety.

It is concluded that significant degradation, if present, would have been detected during an ultrasonic examination performed to the maximum extent possible, of the subject welds.

As a result, reasonable assurance of component structural integrity has been provided.

Therefore pursuant to IOCFR50.55a(g)(5)(iii), it is recommended that relief be granted, for the first inspection interval.

VIII.Implementation Schedule:

This Request for Relief is applicable to WBN's first inspection interval.

E1-4

ENCLOSURE 1 WATTS BAR NUCLEAR PLANT (WBN)

UNIT 1 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME)

FIRST TEN YEAR INSERVICE INSPECTION INTERVAL REQUEST FOR RELIEF, 1-ISI-14 List of Attachments Weld Location ISI drawing CHM-2570-C-01 ASME Section XI, 1989 Edition, Figure IWB-2500-7(b),

Nozzle In Shell or Head Examination Data Reports WP Report R0875 WP Report R0876 WP Report R0877 WP Report R0878 WP Report R0879 E1-5

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ENCLOSURE 1 ATTACHMENT 2 WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 INSERVICE INSPECTION PROGRAM REQUEST FOR RELIEF, 1-ISI-14 FIGURE IWB-2500-7(b) NOZZLE IN SHELL OR HEAD Mg. NB-2500-7(b) 19S9 SECJ1ON XI- -DVISION I tgltn2

noS bvalltchkaW I, -*ew wot heatd)d dclew r-noze hIntldc ontmr tedhns vr I-1 1

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ENCLOSURE 1 ATTACHMENT 3 WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 FIRST TEN YEAR INSERVICE INSPECTION INTERVAL REQUEST FOR RELIEF, 1-ISI-14 EXAMINATION DATA WP Report WP Report WP Report WP Report WP Report REPORTS R0875 R0876 R0877 R0878 R0879

TENNESSEE VALLEY EXAMINATION

SUMMARY

REPORT NUMBER:

AUTHRITYAND AUHRIYRESOLUTION SHEET (P087S PROJECT: WERN UNIT: I CYCLE 05 COMPONENT ED: "/-II EXAMINATION METHOD SYSTEM: PZR IISI DWG NO: CHIM-2S70-C-01 I ]UT W,

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TENNESSEE VALLEY EXAMINATION

SUMMARY

REPORT NUMBER:

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TENNESSEE VALLEY DIGITAL ULTRASONIC REPORT NUMBER AUTHORITY CALIBRATION R01-7b DATA SHEET

'PROJECT WVBN UNITICYCLE 1If S CALIBRATION DATE: 9-18-03 CALIBRATON BLOCK NO. W-S-5 TEM:

7,9@E PROCEDURE: N-UT-19 REV:

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ELEMENTS: I

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CABLE TYPERG-174

_ LENGTH: 6' 1STRUME_-

MANUFACTURER: KrautArmer DUE DATE 5-27-04 MODE: E SHEAR 2 LONG El RL MODEL NO.:

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N/A 6 F N/Am rwAV NZA9 N/A

PDI QUALIFIED INSTRUMENT SETTINGS:

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

LINEARITY CHECK VERTICAL I SIGNAL 1 100 ! 90 l80 1 70 60 50 40 i 30 i0 SIGNAL2 0

50i 45 4sl3S 251 20 15 10 i

GAIN SET

-6 diB

-12dB SET 512 SET

+6 lTENUATOR-

-So%

l80 32 TO 48 16 TO 24 20%

64 TO 96 40%

._64T096 40 0

80 802

, MMET WELD /.ITEMS EXAMINED WP-12 EXAMINER:_

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EXAMINER:NA LVL::

N/A DATE:, /0 REVIEWERL:

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PAGE

2.

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.-AG~S&-FGRMS-OAMABSeK4O-27-#4----

TENNESSEE VALLEY DIGITAL ULTRASOMC REPORT NUMBER AUTHORITY CALIBRATION R

DATA SHEET PROJECT WRN UNIT/CYCLE 1/ 05 PROCEDURE: N-UT-19 REV:JL TC:

TRANSDUCER MANUFACTURER KBA MODEL:

AAMkMA S/N J15203 SIZE: 0.5x1.0" FREQ:

2.25 MHz SHPE:!kectange # ELEMENTS: I

CONS: 0 CABLE TYPE RG-174 LENGTH:- 6' MODE:

&5 SHEAR EJ LONG C RL CALIBRATION DATE: 9-18-03 CALIBRATION BLOCK NO. WB-55 TEIP:.

7VF SIMULATOR BLOCK:Ro'pas THERMOMETER SIN: 522352 DUE DATE: 6-16-04 COUPLANT: U 1fragdI!

BATCH: 002JS ANvG1VFJCATION BLOCK TYPE: Rompas _

S/N:

791413 NOMINAL ANGLE: 45' ACTUAL ANGLE 45 4

INSTRUMENT MANUFACTURER: Krawakramer DUE DATE 5-27-04 MIODEL NO.;

USN-S2L S/N: E30217 DAC llilrljM&:rrRS vl 1 ll,%li-rb 1

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A M

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ANGLE:

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13.871 masec VELOCITY

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-/A

PDI QUALIFIED INSTRUNIENT SETTINGS:

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

LINEARITY CHECK VERTICA L IGNAL 1

__._2_1~e SiG-NAC1 100 90 80 1 70 j60 50 40' SIGNAL1 r 25 20!

15 10 N

SET dB

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78' PROCEDURE: N-UT-19 REV: -

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16.404 msec 20 D

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

LINEARITY CHECK

!.SINA I10 90 80 70

'60 I 50 40 30 20 VERTICAL SGA VR A SIGNAL2 50 l45 40 35 30; 25 20 15 10 GAIN I SET

-6dB

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REPORT NUMBER I

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TVA Office of Nuclear Power PROJECT:

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ldk TC: __

TRANSDUCER MANUFACTURER "A MODEL:

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4.Oinches TOF:

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METAL PATH:_L 0.728 INITIAL TIME: 22:00 FLNAL TIME: 04.20 VERIFICATION TIMES l

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PDI QUALIFIED INSTRUMENT SETTINGS:

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

LINEARITY CHECK 10 90 8

___7

_6 5

W 730 I 120.

VERTICAL SIGNAL o

9 0

70 SIGNAL2 so 45 40 35 i 50 25' 20 s

10 I

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VERTICAL SIGNAL 1 100 I 90 SIGNAL 2 50 45 GAIN ! SET

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

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_ 1 CALIBRATION BLOCK NO. WB-55 TEMP:

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PDI QUALIFIED INSTRUMENT SETTINGS:

VERIFY INSTRUMENT SETTINGS AND CALIBRATION SEQUENCE ARE 1N ACCORDANCE WITH TABLE 2 OF THE APPLICABLE PDI QUALMIICATION IAILEMENTATION PROCEDURE!

LINEARITY CHECK SIGNAL 100 WT90 I80 j 70 I60 150 I 40 0

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TENNESSEE VALLEY DIGITAL ULTRASONIC REPORT NUMBER AUTHORITY CALIBRATON DATA SHEET PROJECT WBN UNIT/CYCLE 1/ S CALIBRATION DATE: 9-18-03 CALIBRATION BLOCK NO. WB-55

_ TEMP:

72 F PROCEDURE: N-UT-I9 REV:

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PDI QUALIFIED INSTRUMENT SETTINGS:

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TENNESSEE VALLEY AUTHORITY MANUAL ULfRASONIC VESSEL EXAMINATION DATA SHEET I

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TENNESSEE VALLEY DIGITAL ULTRASONIC REPORT NUMBER AUTHORITY CALIBRATION 7

D DATA SHEET

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

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TENNESSEE VALLE DIGITAL ULTRASONIC REPORT NUMBER AUTHORITY CALIBRATION 9

DATA SHEET R

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CALIBATION DATE: 98-03 CALIBRATION BLOCK NO. fW-5S TEMP:_

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BATTERY DISPLAY WIDTH 85 inches

____________________________________________________________________ 1.

[REF. REFLECTOR:

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35 30 1 25s 20 15 10 GAINJ SET

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64 6496 40 20 80 COMMENTS.

I WELD I ITEMS EXAMTNED A'

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J/A DATE:

2 REVIEWER:

LVL4 DATE:

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TENNESSEE VALLEY AUTHORITY MANUAL ULTlRASONIC VESSEL EXAMINATION DATA SHEET I

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ENCLOSURE 2 WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME)

FIRST TEN YEAR INSERVICE INSPECTION INTERVAL REQUEST FOR RELIEF, 1-ISI-15 WATTS BAR NUCLEAR PLANT AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME)

FIRST TEN YEAR INSERVICE INSPECTION INTERVAL REQUEST FOR RELIEF, 1-ISI-15 I. Summary:

This request for relief addresses safety injection system circumferential pressure retaining welds SIF-D086-02 and RHRF-D054-09.

The design configuration of the subject austenitic piping welds provides single side access for examination.

Single side access precludes meeting the examination requirements.

An ultrasonic examination, using the Performance Demonstration Initiative (PDI) procedures, 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 the best effort ultrasonic examination to approximately 50 percent for pipe to valve welds SIF-D086-02 and RHRF-D054-09.

It was concluded that performance of an ultrasonic examination of essentially 100 percent of the lower one third of the subject circumferential pressure retaining welds would be impractical.

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.

The WBN Code of Record is ASME Section XI, 1989 Edition.

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

II. Component:

One 6-inch Safety Injection System Piping Weld One 8-inch Safety Injection System Piping Weld.

Reference ISI drawing CHM-2636-C-07 and ISI-0375-C-16 Weld Identifiers RHRF-D054-09 and SIF-D086-02, (See Attachment 1).

III. Code Requirement:

1989 Edition of ASME Section XI and WCAP-14572, Westinghouse Owners Group Application of Risk-Informed Methods to Piping Inservice Inspection Topical Report, Revision 1-NP-A, dated February 1999, Table 4.1-1, Examination Category R-A, Risk-Informed Piping Examinations, Item Number R1.1l, Elements Subject to Thermal Fatigue (See Attachment 2).

NRC approved the use of the WCAP for WBN in NRC's safety evaluation for the E2-1 WATTS BAR NUCLEAR PLANT AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME)

FIRST TEN YEAR INSERVICE INSPECTION INTERVAL REQUEST FOR RELIEF, 1-ISI-15 Risk Informed Inservice Inspection Program dated January 24, 2002 (TAC No. MB 2082).

The examination requirement is defined in Figure IWB-2500-8(c)

(Attachment 3).

IV.

Code Requirements From Which Relief Is Requested:

Relief is requested from performing the required volumetric examination on essentially 100 percent of the lower one-third volume of the referenced welds.

V. Basis for Relief:

The 10 CFR 50.55a(b) (2) (xv) (A) requires that if access is available, the weld shall be scanned in each of the four directions (parallel and perpendicular to the weld) where accessible.

Coverage credit may be taken for single side exams on ferritic piping.

However, for austenitic piping, a procedure must be qualified with flaws on the inaccessible side of the weld.

There are currently no qualified single side examination procedures for austenitic piping welds.

Current technology is not capable of reliably detecting or sizing flaws on the far side of an austenitic weld for configurations common to United States nuclear applications.

The PDI Program conforms to the 10 CFR 50.55a(b) (2) (xv) (A) regarding single side access for piping.

PDI Performance Demonstration Qualification Summary (PDQS) personnel certificates for austenitic piping list the limitation that single side examination is performed on a best effort basis.

The best effort qualification is provided in place of a complete single side qualification to demonstrate that the examiners qualification and the subsequent weld examination is based on application of the best available technology.

When the examination area is limited to one side of an austenitic weld, examination coverage does not comply with 10 CFR 50.55a(b)(2)(xvi)(B) and full coverage credit may not be claimed.

The design configuration and materials used in fabrication of the subject safety injection system E2-2

WATTS BAR NUCLEAR PLANT AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME)

FIRST TEN YEAR INSERVICE INSPECTION INTERVAL REQUEST FOR RELIEF, 1-ISI-15 welds precludes an ultrasonic examination of the required volume because there are no current qualified single side examination procedures that demonstrate equivalency to two-sided examination procedures on austenitic piping.

The design configuration and material limits ultrasonic examination to the extent indicated:

Best Effort ASME Section XI Weld Coverage Coverage (NOE 1)

SIF-D086-02 50%

100%

RHRF-DO54-09 50%

100%

NOTE 1 - Coverage does not consider the inherent limitations associated with the PDI for one side access.

VI. Alternative Examination:

In lieu of the code required examination coverage and qualification demonstration requirements, a best effort ultrasonic examination was performed, as qualified through the PDI for Supplement 2 to ASME Section XI, Appendix VIII with demonstrated best effort for single side examination.

Refer to the examination data reports in Attachment 4.

VII. Justification For The Granting Of Relief:

The best available techniques, as qualified through the PDI for Supplement 2 of Appendix VIII with demonstrated best effort for single side examination, were used from the accessible side of the weld.

(1) The design configuration and materials used in the fabrication of the subject piping welds precludes ultrasonic examination of essentially 100 percent of the required examination volume.

In order to examine the welds in accordance with the code requirements, the safety injection system would require extensive modification.

The design configuration and materials used limits the best effort ultrasonic examination to approximately 50 percent for pipe to valve welds SIF-D086-02 and RHRF-D054-09.

E2-3

WATTS BAR NUCLEAR PLANT AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME)

FIRST TEN YEAR INSERVICE INSPECTION INTERVAL REQUEST FOR RELIEF, 1-ISI-15 The subject welds were examined using application of the best available ultrasonic technology currently qualified.

(2) Radiographic examination as an alternate volumetric examination method was determined to be impractical due to the material thickness variation and the ASME Section XI Code requiring an extended coverage (weld plus M-inch of base material from the transition point).

The radiographic density variation does not lend for compliance with ASME Section V, Nondestructive Examination, requirements without extensive radiographic exposures to obtain the density for the base material on the fitting (valve) side.

The additional radiography required would increase personnel radiation exposure.

(3) A Risk-Informed approach provided by the WCAP-14572, 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 percent of the required volume of pressure retaining circumferential welds SIF-D086-02 and RHRF-D054-09 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 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 best effort ultrasonic examination that was performed on the subject welds.

As a result, reasonable assurance of operational readiness has been provided.

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

E2-4 WATTS BAR NUCLEAR PLANT AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME)

FIRST TEN YEAR INSERVICE INSPECTION INTERVAL REQUEST FOR RELIEF, 1-ISI-15 VIII.Implementation Schedule:

This Request for Relief is applicable to WBN's first inspection interval.

E2-5 WATTS BAR NUCLEAR PLANT AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME)

FIRST TEN YEAR INSERVICE INSPECTION INTERVAL REQUEST FOR RELIEF, 1-ISI-15 List of Attachments Weld Location ISI drawing CHM-2636-C-07 and ISI-0375-C-16 WCAP-14572, Westinghouse Owners Group Application of Risk-Informed Methods to Piping Inservice Inspection Topical Report, Revision 1-NP-A, dated February 1999, Table 4.1-1, Examination Category R-A, Risk-Informed Piping Examinations, ASME Section XI, 1989 Edition, Figure IWB-2500-8(c),

Similar and Dissimilar Metal Welds in Components and Piping Examination Data Reports SIF-D086 Report R0899 RHRF-D054 Report R0907 E2-6

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Table 4.1-1 EXAMINATION CATEGORY R-A, RISK-INFORMED PIPING EXAMINATIONS Examination Deferral of Requirement/

Acceptance Examination to Item No.

Parts Examined Fig. No.

Examination Method Standard" Extent' and Frequency End of interval Successive' slt Interval Intervals R1.10 High Safety-Significant Piping Structural Elements R1.1 I Elements Subject to Thermal IWB-2500-8(c)'

Volumetric IWB-3514 Element" Same as 1st Not Permissible Fatigue IWB-2500-9,10,11

[WC-2500-7(a)'

R1.12 Elements Subject to High IWO-2500-8(c)'

Visual, VT-2" IWB-3142 Each Same as 1st Not Pcrmissible Cycle Mechanical Fatigue IWB-2500-9,10,11 Refueling IWC-2500-7(a)'

to RI.13 Elements Subject to Corrosive, Note 8 Volumetric' (for Internal IWB-3514 Element' Same as 1st Not Permissible Erosive, or Cavitation Wastage) or Surface (for Note 8 Element' Wastage External Wastage)

RI.14 Elements Subject to Crevice Note 7 Volumetric IWB-3514 Element' Same as 1st Not Permissible Corrosion Cracking RI.15 Elements Subject to Primary Note 7 Visual, VT-2" IWO-3142 Each Same as Ist NotPermissible Water Stress Corrosion Refueling Cracking (PWSCC)'

R1.16 Elements Subject to IWB-2500-8(c)

Volumetric IWB-3514 Element Same as 1st Not Permissible Intergranular Stress Corrosion IWB-2500-9,10,11 Cracking (ICSCC)

R1.17 Elements Subject to IWB-2500-S8(c)

Visual, VT-3 Internal Note 8 Element' Same as lst Not Pcrmissible Microbiologically Influenced IWB-2500-9,10,11 Surfaces or Volumetric" Corrosion (MIC)

R1.18 Elements Subject to Flow Note 9 Note 9 Note 9 Note 9 Note 9 Note 9 Accelerated Corrosion (PAC) pa

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Table 4.1-1 (cont.)

EXAMINATION CATEGORY R-A, RISK-INFORMED PIPING EXAMINATIONS Notes:

(1) The length for the examination volume shall be increased to include 1/2 in. beyond each side of the base metal thickness transition or counterbore.

(2) Includes all examination locations identified in accordance with the risk-informed selection process in Section 3.7.

xti (3) lirludeni 1001/, of the examination location. When the required examination volume or area cannot be examined due to interference by t

l another component or part geometry, limited examinations shall be evaluated by the Expert Panel for acceptability. Areas with En acceptable limited examinations, and their bases, shall be documented.

n 3

txi (4) Thc examination shall include any longitudinal welds at the location selected for examination in Note 2. The longitudinal weld examination requirements shall be met for both transverse and parallel flaws examination volume defined in Note 2.

(5) Initially-selected examination locations are to be examined in the same sequence during successive inspection intervals, to the extent l

m practical.

(6) Applies to mill annealed Alloy 600 nozzle welds and heat affected zone (HAZ) without stress relief.

F3 P

(7) The examination volume shall include the volume surrounding the weld, weld heat affected zone, and base metal, where applicable, in H

HIH the crevice region. Examination should focus on detection of cracks initiating and propagating from the inner surface.

H (8) The examination volume shall include base metal, welds and weld HAZ in the affected regions of carbon and low alloy steel, and the welds and weld HAZ of austenitic steel. Examinations shall verify the minimum wall thickness required. Acceptance criteria for be localized thinning is in course of preparation. The examination method and examination region shall be sufficient to characterize the extent of the element degradation.

(9) In accordance with the Owner's existing FAC program.

(10) Paragraph and Figure numbers refer to the 1989 Edition.

(11) VT-2 examinations may be conducted during a system pressure test or a pressure test specific to that component/element.

ENCLOSURE 2 ATTACHMENT 3 WATTS BAR NUCLEAR PLANT FIRST TEN YEAR INSERVICE INSPECTION INTERVAL WELD LOCATION ISI DRAWINGS IWB-2500-8(c)

F41. K1-2so 1919 SECTION DIVISION a Proftl. of %*he bady.

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FlG. rWB250WO4 SIMILAR AND DISSIMILAR METAL WELDS IN COMPONENTS AND PIPING (CONrD) 94 E2A3-1

ENCLOSURE 2 ATTACHMENT 4 WATTS BAR NUCLEAR PLANT FIRST TEN YEAR INSERVICE INSPECTION INTERVAL EXAMINATION DATA REPORTS SIF-D086 Report R0899 RHRF-D054 Report R0907

TENNESSEE VALLEY EXAMINATION

SUMMARY

REPORT NUMBER:

AUTHRITYAND A ORITY RESOLUTION SHEET l

cl-c PROJECT: WEN UNIT: I CYCLE eS COMPONENT ID: SIF-D086-02 EXAMINATION METHOD SYSTEM: SIS ISIDWG NO: ISI-0375-C-16 MT O

PT UT T VT CONFIGURATION:

lCATEGORY PROCEDURE: N-UT-64 PCPRPE TO PCVLV R-A BEXAMINEI>X?

EXAMINER:

EXAMNER E

ER f4.

A_

A..

LEVEL: H LEVEL: AYA LEVEL N/A LEVEL: NIA Total coverage calculated to be sproximately so Ihis reDort contains the manual ultrosonic examination data associated wirh weld

SIF-D086-02. A 3%. SS. pipe to valve confiuration.

0. S,02 JW2,45 & 70 gegree shear wave transducers were used Limited examination volume coverao c was achieved due to~c~opfijziration see attached sketch.

jiwetdahleindications. were-detected., _

RESO N BY:

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DATE-~/

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LEVEL,-1 DATE: 9 a?

Page:.J.O~

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TENNESSEE VALLEY DIGITAL ULTRASONIC REPORT R

AUTHORITY CALIBRATION NUMBER DATA SIEET _-&nl PROJECT FWfJN UNITJCYCLE 1105 PROCEDURE: N-UT-64 REV: 6 TC: 4 TRANSDUCER MANUFACTURER KBA MODEL: COMP-G SIN O0Y7FF -

SIZE:

.25" FREQ:

225 MHz SHAPE:Round E ELEMENTS: 1

CONS: 0 CABLE TYPE RG-174 LENGTH: 6' MODE:

Ea SHEAR a LONG 1 RL CALIBRATION DATE: 9-23-03 CALIBRATION BLOCK NO. FFr-li TEMP:

78'F SIMULATOR BLOCkCROi as.

THERMOMETER SIN: 558270

'DUE DATE: 12-9-03 COUPLANT: Ultrafel II BATCH: 01225 GEI--G-LCVE-TIATON BLOCK TYPE: Rompas SIN: -89631 NOMINAL ANGLE: 4S' ACTUAL ANGLE 44' INSTRUMENT MANUFACTURER: Krautkramer _DUE DATE 5-27-04 MODEL NO.:

USN-S2L S/N: E30217 -'

I DAC INSTRUMENT SETEINGS 100 80 60 40 20 0

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44deg DAMPING:1000

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4.673 msec VELOCITY 0.1233 msec PRR/PRF: HIG1!

RANGE:

1.50 inches TOF:

E4AK DISP. MODE: FULL WA r POWER:

BA 77ERY"'

DISPLAY WIDTH 1.50 Inches I.

REF. REFLECTOR:.

RomasSDH GAIN:

3fdB CALIBRATION TIMES AMPLITUDE:

30 %

METAL PATH: 1.041 INITIAL TIME: 20:45 FINAL TIME: 23:25 6 9-TINM ES T') 2h.3eOTW N1 3

N/ I ) /

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PDI QUALIFIED INSTRUMENT SETTINGS:

VERIFY INSTRUMENT SETTINGS AND CALIBRATION SEQUENCE ARE IN ACCORDANCE WITH TABLE 2 OF THE APPLICABLE PDI QUALIFICATION IMPLEMENTATION PROCEDUREI LINEARITY CHECK VERTICAL SIGNALT

100 1 90 I S0 70 60 ' 50 40130 i

SIGNAL2

' 50 i 4 i 40 35' 30, 2f 20 15 10 GAIN d7EBT 6 t

-12dB SET

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UDMMENS WELD J ITEMS EXAMINED Completc exa from pipe side only due to configuratien)NJ

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II JANII:

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n. N/A DATE:

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- LVEZ DATE:

PAGE Z

.,J/0,3 I OF ;r-I

-AGCEGCS4-FePRMS-QAT ASE-4021 a

I I

I TENNESSEE VALLEY AUTHORITY I

PROJECT JWBN UNIT/CYCLE lie PROCEDURE: N-UT-64 REV; 6 TC:_,J>

TRANSDUCER MANUFACTURER KBA -

MODEL: COMP-G SIN 00Y7FF SIZE:

25" FREQ:

2.25 MHz SHAPE:Round

ELEMENTS: I

CONS: 0 CABLE TYPE RG-174 LENGTH: 6' n~nr.'

Cl 1

nn CALIBRATION BLOCK NO. _-II TEMP:

78'F SIMULATOR BLOCICKloas THERMOMETER SIN: 555270 DUE DATE: 12-9-03 COUPLANT: UltraclH BATCH: 10225 ANGVERICATION BLOCK TYPE:. RomLs SIN:.78963!

NOMINAL ANGLE: 70 ACTUAL ANGLE 67'

-INSTRUMENT MANUFACTURER: Krautkramer DUE DATE 5-27-04 MODEL NO.:

USNV-52L SIN: E30217 A A%01" er oxrXl LJi LAilu L" A%

DAC INSTRUMENT SETTINGS 100 80 60 40 20 0

A M

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NTC j SDH SENSIlTVITY NUNIBER A2IAL 5

1 54 dB I 4

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2.&0g1Hz z REJECT:-

0. /,

ANGLEL 67deg

DAMPING:1000

, ohms DELAY:

-0 329 rnsec PULSER: SINGLE -

ZERO:

7.183 msec VELOCITY 0.1234 msec PRRJPRF: HIGH RANGE: _

2. inches TOF:

PE4K DISP. MODE: FULL WA V POWER:

BAT7ERY DISPLAY WIDTH 2.0 inches 4

REF. REFLECrOR:

Rompas SDH GAIN:

42 dB [

CALIBRATION TIMES AMPLITUDE:

50 %

METAL PATH: 0.765 INITIAL TIME: 21:00 FINAL TIME: 23:20 VERIFICATION 1

S.

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N/Al T

PDI QUALIFIED INSTRUMENT SETTINGS:

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

LINEARITY CHECKI VERTCSIGNAL I

,0 r70 050 4030 1 20 SIGNAL2 75 0

45 35 30 25 20 15 10 GAIN SET

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WELD / ITEMS EXAMNED Complee exam on pipe side only due to configiratlon,supplement to SIF-D086-02 K4SSdegrefor adritional coverage andfarIi-brcerigafron-nIr

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DATE:

A/?/3 REVIEWER: V LVLE W

DATE:

uPAGE, OF I

-AGrGESS.-FePAu3-aA*4tAB~EI 71-

TENNESSEE VALLEY ALNA ULRASOC REPORTNUBR.

AUTHORITY PIEPING EXAMIUNATION Rom9 PROJECT: WBN UNIT/CYCLE I105 EXAMNATION DATE 9-23-03 STEM: SIS STR

=TIE:

21:30 ENDTIM 21:55 WELD LD.: SIF-D086-02 EXAM SURFACE fl1D JZOD CONFIG.: PC,PIPE TO PC, VL V COF.

MATERIAL TYPE: rCS ZSS CJCSCL jCCSS FLOW SURFACE TEMP. 73 F PYRO NO. 558270 PROCEDURE: N-UT-64 REV:

6 TC:.

EXAMINATION ANGLE 45 DEG.

70 DEG Wo

REFERENCE:

WELD CENTER LINE AXIAL SCAN SENSITIVITY 41 d 48 dB Lo

REFERENCE:

TDC CIRC. SCAN SENSll T

43 id N/A dB NCL (Ln) FROM REF.

AT MAX AMP MAX EXAM NOM.

DICATON INFORMATION:

AMP NO.

NRI.

INDIAINIFRAIN NO.

Li1 L Max LU W MAX MP MAX MAX

% DAC 314 ANG.

IYP£ DAMPING, ETC.

45 RI,

_6 45 6?

__~

7__

0 REMARKS/LIM1TATIONS i Faminationmj mited to pie side only due to confirwatdon,no recordable Indications were detecred.

hL E

IEXAMINER:

4 LEVEL: u ANII:

&l-4 EXAMINER: N/A LEVEL: N/A DATE: jo/3)03 R

Bf DA:

/

A/ E REVIEWED BY-G={<&

LEVEtjDT:

s

.GE/O I

ACCESS: FORMS DATABASE tWM&1

_I_

TVA WALL THICKNESS REPORT NO:

PROFILE SHEET R o PROJECT:

VB WELD NO:

SI F

- otL UNIT:

i l

SYSTEM:

S__

Record Thickness Measurements As Weld

Weld Edge Indicated, Including Weld Width.

C*nterline Edge-To-Edge At a,'

25l Position 0'

90' 180l 270}

l/

Iow CROWN HEIGHT:

US4 DIAMETER:

CROWN WIDTH:

0. oe" WELD LENGTH:

i tlo"

XAIHER REVIEWED SIP:......

L E VEL,

OATT, DATE:PA

.S______

.A168(N..9 1.10-1VA 19669 (p 99) 1-1014"_"

TENNESSEE VALLEY EXAMNATION SUARY REPORT NUMER:

A O

RESOLUTION SHEET R 01C7 PROJECT: OBN UNIT: I CYCLE OS COMPONENT 1: RHRF-DO54-09 EXAMINATIONMlETHOD SYSTEM: SIS

-IS DWG NO: CHM-263-C--07 T

° PT

-° UT Ql VT al CONFIGURATION:

FGOR PROCEDURE: N-UT-64 REV 6 TC 1,

PC,VLV TO PC,PIPE R-A EXAM EXAMINER EXAMINER:

EXAMINER:

E:L LEVL NN/A NL LEVEL: H LEVEL: NIA LEVEL: NMA

=L:

NIA i0X.

iE

.;.v-;;%9,*k W

'. -!377 Total covierage calculated to be approximately So This rei rt cntaljs the mauual ultrasoni am rsaton data associated with weld

RHRF-DO54-09. an 8". SS'. valve t Dine confiuraion.

=

A 0.375"J.50 Mhz.45 derrg shecr wave transducer anda 2. Ojz, 6p degLe£RL tr#.aWucer were used.

Tex praminahinM wasn penrmed orizly-dle toithe.cagflguralon...

evlePn.oint Jw*ezhoaezvg (rrrywadseend O dpttere eoetrv Lfiegre ordak.

as se=

ces wth th 60 degrewRL, I

Affree D~IA^Aq O.tA

TENNESSEE VALLEY DIGITAL ULTRASONIC REPORT NUMBER AUTHORITY CALIBRATION 1

OS 07 DATA SHEET PROJECT WBN UNIT/CYCLE I/ O CALIBRATION DATE: 9-24-03 P D _

CALIBRATION BLOCK NO. FW-02 TEMP:

78F TRANSD)UCR SIMULATOR BLOCK.RomPas MANUFACTURER A

o THERMOMETER SIN: 552870 DUE DATE: 12-9-03 MOELOCMPGLAN

~~

T: Ultragelff BATCH: 01225 MODEL: COMI-G SIN *seX_ =

___________ SI

________ANGLEV!WKFICATION-SIZE:

375" FREQ: J.5 MHZ BLOCK TYPE: Rompas SIN: 789631 SHAPE:Round

ELEMENTS: 1

CONS:

0 NOMINALANGLE:45_

ACTUAL ANGLE 44 CABLE TYPE RG-1 74 LENGTH 6'

INSTRUMENT MODE:

0 SHEAR O] LONG O RL MANUFACTURER: Krautkramer DUE DATE 5-27-03 A

MODELNO.:

USN-52L S/N: E30217 DAC INSTRUMENT SETTNGS 100 REFLECTOR REFERENCE MEMORY A

SCAN DIRECT.

NTC SDH SursnTVITY NUMER 80 M

AXIAL 24_

2B

.ICIRC.

5dBj 8

60 _

L FREQ:

2.0-.OMHz REJECT:

0 %

I ANGLE deg DAMPING:100 ohms 40 T

DELAY:

-0.063msec PUISER: SINGLE U

ZERO:__

5. 786 msec 20

_D VELOCiTY 0.122Snsec PRR/PRF:

IGH E

RANGE:-.,

3.00inches TOF:_

PEAK 0

DISP. MODE. FULL WAY POWER:

BATTERY DISPLAY WIDTH 3.00 inches REF. REFLECTOR:_ RonmpAsSDI GAIN:

24 dE I

CALIBRATION TIMES AMPLITUDE:

30 %

METAL PATH: 1.027 INITIAL TIME: 21:05 FINAL TIME: 23:10 VERIFICATIONTIMES F) 22.3e Z)

NI/AP3 N/A 4)

N/AI5 N/A's N/A7)

/Al 8)

N/A

PDI QUALIFIED INSTRUMENT SEITINGS:

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

LINEARITY CHECK VERTICAL SIGNAL I 100 90 s8 I 70 60 50 s

40 j 30 20 6 KS-GNiLi 50 45 ito 35 301 25t 20i 15 101 Q,-

¢

GAIN {

ET

-6 dB j

12du i

SET l+12

SET

!+6_

TTENUATOR AMP 80%

32 TO 48 16 TO24 20%

64 TO196O

,40%

164TO96 F ' ' l 40 2 Z0 WL0 / ITmS

-XAMI

~. 1....CQ..ENTS>.'d,`,;.

VM WLD I ITEM<S 1 ;bUINED:

Examfrom pipeside only due to conflguration,rootand counterbore RJRF-D054-09 geometry seen 360 degrees below recordable levels,!

EXAMINER:

S.Q LVL: __

IANM:

I/

&-17' 1VrAMTWNTD Yv/4 Ivj,.

N/A

/

,l DATE: jalula REVIEWER LV-J9 DATE/'<

PAGE 7

OF S-I I

~ ~

~

2-S

/^j.

TENESEE VALLEY DIGITAL UILTRASONIC REPORT NUBR AUTrHORITY CALIBRATION R o9 Oz DATA SHEET PROJECT WBN UNIT/CYCLE I/ 05 CALIBRATION DATE: 9-24-03 PROCEDURE: l-UT.64 REV: 6 TC-CALIBRATION BLOCK NO. ;fB-02 TEMP:

78F PRCEUR:

__T__

EV TC__

-!N SIMULATOR BLOCK:RolTads______

TRANSDUCER MANUFACTURER MEGASONICS THERMOMETER S/N: SS8270 DUE DATE: 12-9-03 MODEL: CGD SIN UZW i COUPLANT: ntat!

eiI ACH S

SIZE:

0.25x0.5" FREQ:

2.0 MHz BLOCK TYPE:_Ro+/-Mas S/N: 729631_/

SHAPE:Rectdang tY ELEMENTS: 2

CONS: 0 NOMINAL ANGLE: 60' ACTUAL ANGLE 60 CABLE TYPE RG-174

LENGTH, 6

LSTRUMENT MODE:

-SHEAR G

63RL MANUFACTURER: Krautkramer DUE DATE 5-27-03 DAC MODEL NO.:

USN-52L S/N: C30217 100 I

REFLECTOR REFERENCE MEMORY I

A SCAN DIRECr., NTC SDH SENSTIVITY NUMBER 8

M AXIAL 6sdB 29 P

CIRC.

t*

N

/A dB N/A 60

_I_

L FREQ:

2.0.0oMHz REJECT:=

0 %

I ANGLE:....--

60deg DAMPING:1000

_ ohms 40 T

DELAY:

0.00msec PULSER: DUAL

_p I_

U ZERO:

6.909 Mnsec 20 D

VELOCITY 0.2317msec PRRIPRF: HIGH E

RANGE:

3.00 inches TOF:

PEAK_

O _D1SP.

MODE: FULL WAY POWER:

BA__ERY DISPLAY WIDTH 3.00 inches REF.REFLECTOR:

RompasSDH GAIN:

49 dB CALIBRATION TIMES AMPLITUDE:_

50 %

METALPATH. 1.432 __

INITIAL TIME: 21:15 FINAL TIME: 23:06 VERIFICATION TIlMES I I) 2 2,0 4)

N/Q 3,)

N/AV4) i N/A4)

N

)

]'A7)

NKA'-

N/Ai 9 )

NM

PDI QUALIFIED INSTRUMENT SETTINGS:

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

LINEARITY CHECK SIGNAL I TTiiI7;05:0 3

0 VERTICAL l8 70 i60 l SO 4

30 20 SIGNAL2 o50 45 4

40 35l 30i 2S

20.

1S i:

GAINg SET

-6 dB

-12dB SET 12 SET

+6 TTENUATOR, AMP 80%

32 TO 48 16 TO 24 1 20%

64 TO 96 40%

6 C

~.

-1:

'20 80 I

sr;., I

-1.

WELDC/

ITEMS:EO 50 S7ppktmenl to 4 degreeforfar side Mterrogarlon,recordable root 05F-D054-09 gometry seen 360 degrceiscounbg r6d e

e gr-________.

recordable levels.

EXAMINER:

I-2.

__ rVYATNF-W1 I REVIEWER-:

I. -...

--7 17 LVL:

I I AMU iVr.

I/A

/

DATE: /J3103 LVLHW'DATE:1Zt '/ I PAGE

? (

Wre Li

.ACCC'Irone D~~EJ E-4.zt1 a

i TENNESSEE VALLEY MANUALU AUTHORTY PIPING EX DATA CT: WEN UNIT/CYCLE 1105 SYSTEM: SJS WELD LD.: PHIRF-D054-09 CONFIG.:

PCVLV TO PCPIPE FLOW REPORT NUMBER

,Z 09V7 EXAMINATION DATE 9-24-03 START TIME: 21:50 END TIME: 22:50 EXAM SURFACE EID 00OD MATERIAL TYPE: rlCS gSS OCSCL OCCSS SURFACE TEMP. 64 F PYRO NO. 558270 EXAMINATION ANGLE 45s DEG.

60R DEG.

AXIAL SCAN SENSIVITY 36 dl 59 dB PROCEDURE: N-EUT-64 REV:

6 Wo

REFERENCE:

WELD CENTER LINE Lo

REFERENCE:

TDC TC: -

CIRC. SCAN SENSITIVI1Y 43 dBI N/A dB

_______ L. --

IND L (In) FROM REF.

AT MAX AMP MAX EXAM NOM.

NFU INDICATION INFORMATION:

~~~AMP No.

AG YE APNEC NO. Li L Max L2 W MAX MP MAX D MAX

% DDAC 4

ANG.

TYPE DAMPIN. ETC 4

45 5

45 v

6 45 f

5ccw 1.40'

.8085

.904 200 4

60 Root geometry O3

=__

= =_

=

=__a T4C.. e 2700 VALF REMAR SIMITATIONS

...Root geone try s~een 360 derrees wltk 60 R%,vertiied with 0 dezree

~kILt1+/-~4.--

EXAMINER:

-LEVEL: q AN:

EXAMER: )_I_

LEVEL: N/A DATE:

,,/31D1 1E VIEWEDBY:

S LEVBY:

4 UA -k S/Q-l PAGE 0 OF L EJS-e l

_~l

_ L 0

ACCESS. FORMS OATABASW 1W1I

WALL THICKNESS REPORT NO:

TVA PROFILE SHEET i

o007 PROJECT:__

i WELD NO:

Rtiiv1-DPO4-0q UNIT:

CA.

/ CYLE 5

SYSTEM:

51S Record Thickness Measurements As Wld Weld Edg Indicated, Including Weld Width.

Cnleriline Edge-To-Edge At 0

-2 2.5 5--

Position 0

190 180- 1 27 Efl/

ED l

l

/

t.l Side Pipe Sid*

<i T

<.2"Flow.,

CROWN HEIGHT:5^

DIAMEYER:_io CROWtl WIDTH:

ltt WELD LENGTH:

0_

jExAmiNrR fU REVIEWEDla LEVEL' LIEVEL' V ATF-fr 4

DATE DATE:

.{

5PAGE

........-Z OF

ML040900299

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SUMMARY

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