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"
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- 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
l 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 I 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 l subject relief reauests by May 31, 1999. This date will i support TVA's schedule for planning inspections during SON's ) Cycle 10 refueling outages. l Enclosure 1 provides the Unit 1 relief requests. Enclosure 2 provides the Unit 2 relief requests. Enclosure 3 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 l 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 1 Sincereiy, 9
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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 ,
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- l. ENCLOSURE 1 i
i SEQUOYAH NUCLEAR PLANT- ! UNIT 1 ASME REQUESTS FOR RELIEF l l 1-ISI-9 AND 1-ISI-10 l l l 1 L I I i l 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 i obtained from the volume examined provides 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 i outside wall surfaces of the nozzle,
.recludes
) ultrasonic examination from t
1-ISI-9 El- 2 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 i I 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 I 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 1 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 l
- (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 7 integrity for these welds is provided 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 I
.information: It should be noted that a request for relief I 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. I M92454 and M92455)." l
- Attachment 1 - Examination Data Reports
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R-6886 and R-6933. i i Attachment 2 - 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
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1 ATTACHMENT 1 EXAMINATION DATA REPORTS R-6886 R-6933 4 4 a
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EXAMINATION REPORT No. i TENNESSEE VALLEY AUTHORITY
SUMMARY
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Request For Relief 1-ISI-10 1 Executive Summary: This request for relief addresses circumferential pressure retaining welds l in the reactor coolant system. The design l configuration and materials used in the l l fabrication of the subject piping welds l l precludes a 100% ultrasonic examination of I l the required volume for the following l l welds: RC-06 (pipe elbow to pump casing) i and RC-07 (pump casing to pipe). These I physical examination limitations occur when the 1989 code examination i requirements are applied in areas of I components constructed and fabricated to f early plant physical designs. Based on l i the date of SQN's construction permit ; l (May 27, 1970), SQN is exempt from code I l requirements for examination access as l l allowed in 10 CFR 50.55a(g) (4) . . l l l 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 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 I approximately 75% of Weld RC-07. It was concluded that performance of an l ultrasonic examination of essentially 100% l of the circumferential pressure retaining welds, RC-06 and RC-07, would be impractical. A surface examination and i the maximum extent practical ultrasonic l 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 inspection interval.
l 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 Pipingi Examination Item. , Ndmber: B9 .11,, Circumferential Welds Nominal Pipe
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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 RC-06, Piping To Reactor Coolant Pump The Relief Request: 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 ( w- ' consists of a pump casing to pipe 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 I
pump. No scans were performed from 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 l levels. !
(3) Westinghouse plants have no history of i pipe cracking failure in the reactor l 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 I corrosive environment (reference l
. 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:
Attachment 1 - Examination Data Reports: R-6824, R-6826, R-6836, and R-6837. Attachment 2 - ISI Program Drawings: l l ISI-0325-C-02, Revision 2 and ) ISI-0482-C-01, Revision 1. I l l l 1 1 l l l l. i 1-ISI-10 El-5
. ATTACHMENT 1 EXAMINATION DATA REPORTS j R-6824 R-6826 R-6836 R-6837 I
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//A _ FOR PREVIOUS S ATISFAct'ORY UNEARITY 5 Mods WELD (s) EXAMINED: JC- N COMMENTS: dCA/700fE/3 a/ a/
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PROCEDUP,E:NNT. 33 _ REV.: 7 TC: 9(o-08 CAUBRATION BLOCK NO.:50 -G # TEMP.: Ep_ F Dd7'A'2A/v/Eg SIMULATOR BLOCK NO2 790398
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MANUAL ULTRASONIC REPORT NO. TENNESSEE VALLEY A UTilORITY PIPING EXAMINATION DATA SIIEET N-II3 ; ROJECT:g6000 YAM UNIT: 1 , EX AMINATION DATE: ___.3 -d 7- 9 7 ' 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 - PROCEDURE:N[dT.M__ REV.: 7 TC: 76-C6 CAllBRATION SIIEET NO. C- N/A C' e4/A Wo
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I l I ENCLOSURE 2 SEQUOYAH NUCLEAR PLANT l I UNIT 2 ASME REQUESTS FOR RELIEF 2-ISI-8, 2-ISI-9, AND 2-ISI-10 l i l i i l 4 l i 4 a
l Request For Relief 2-ISI-P 1 l 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 l early plant physical designs. Based on I 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) . l A liquid penetrant surface examination of l essentially 100% of the weld was I performed. An ultrasonic examination was l performed on accessible areas to the l 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
l l the code requirement, the branch ; connection would require extensive l redesign and changing of piping ' H material. l l 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 I diameter of the large bore reactor coolant system piping). The branch connection is stainless steel material I and the large bore reactor coolant I 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 l 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
1 Also, the wide variation in component ! thickness and joint configuration does-
- j not make radiography an amenable l
option to increase code required l coverage. l (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 l 100% of the required volume of the ( pressure retaining branch connection j Weld SIW-07 would be impractical. As l previously discussed, TVA determined that it would be impractical to attempt other volumetric examinations I 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
- I 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 result, assurance of structural l 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:
Attachment 1 - Examination Data Reports: R-5568 and R-5584. ISI Program Drawing: ISI-0002-C-05, 4 Revision 10.
'2-ISI-8 E2-4
. . . _ . _ . . . . . .. . _ _ _ _ _ _ . - _ _ _ _ . . . . - . . _ . ~ _ _ _ . _ _ - . . . . _ _ _ _ _ _ _ _ . . . _ _ . . _ _ . _ _ . _ .
i e s . 4-4 4 ATTACHMENT 1 4 i EXAMINATION DATA REPORTS a
- - R-5568 i
i, -R-5584 4 t I i, i 4 J. J {. 1 l l 4 e
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RECORD OF REPORT NO. TENNESSEE VALLEY AUTHORITY LlQUID PENETRANT ' EXAMINATION R 5.6 % 8 .
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- S tG bj P _ UNIT :
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{ TVA 19470C (NP 7/92)
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?h $ k- %@f USN-50 ULTRASONIC CALIBRATION NO.
TENNESSEE VALLEY AUTIIORITY CALIBRATION i/ DATA SilEET C- O ,7 f ,
. ROJECT:____6o M P uNrr: 2 CAUBRATION DATE: o A ,/2 3 / Ct h PROCEDURE: N.tcr. 18 R EV.: 2o TC: 4/A CAllBRATION BLOCK NO.: _60 G7 TEM P.: 3.6.*F INSTRUMENT: KeAu-rtt" AME* E. SIMULATOR BLOCK NO.: h2770 MODEL/ TYPE: las 0 - 60 TilERMOMETER SERIAL No.: 552m6 hc 11193 SERALNUMBEli? ElB5oz l-l6 01 COUPLANT: llerem II~ BATCll: 093081 TR ANSDUCER MANUF.: 'K T O SERI AL NO.: 7 b-iui.s= M - I M.= ANm MRIFIC ATION SIZE:JM x253 N : 1 Milz BLOCK TYPE:kAs SERIAL NO. E2770 CABLE TYPE:~R61 M DUAL LENGTII: 7Z NOMINAL ANGLE: 60 ACTUAL ANGLE: 69 INSTRUMENT SETTINGS 100 2..,
REFLECTOR REFERENCE DATA g . ORIENTATION SENStrlVTrY SET
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- INTTIALTIME: 1*f2 e FINAL TIM E: ILA 5 REF. R EFLECTOR: *6 4Dil CAIN: _@ .6 dB VERIFICATION TIMES AMPLITUDE: 40 7. METAL PATH: I.267 *
) ) g 7 7 C VERTICAL SIMALI W 80 M 60 50 40 30 20 to L !! SIGNAL 2 50 g g g % y 3 gg go _ g_
OAIN SET 6 12 SET + 12 SET +6 ATTENUATOR SIGNAL AMP. 80 7. 32 to 48 16 to 24 20 f. 64 to 96 40-7. 64 to 96 K m w y y REFER TO CALIBR ATION REPORT 9/A FOR l'REVIOUS S ATISFACIORY LINEARITY COMMENTS: WELD (s) EXAMINED: _61W - 07
,/, ~ . AMINER: .. LEVEL: lI~ ANII: N EXAMINER: 64 4!h! at b b LEVEL: M DATE: f/h[fz REVIEWED BY: !A IM LEVEL: <
M DATE: k'N' b PACE 2 OF bb
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{ k - bk . USN.50 ULTRASONIC CALIBR ATION NO. l CALIIlRATION TENNESSEE VALLEY AUTHORITY DATA SIIEl.r C- 657p/ . ROJECT: 6 CMP - UNrt: Z CALIBRAT10 \TE: 04,/2. 7,/% PROCEDURE: N.tfr. 18 R EV.: Zo TC: 4/A CAllBR ATION BLOCK NO.: 6 0 6'? TEM P.: lfL
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<a w FOR PREVIOUS SATISFACIORY LINEARITY REFER TO CALII1R ATION REPORT u/A WELD (s) EXAMINED: W - G7 COM MENTS:
# LEVEI; Y~ ANII: M
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EXAMINER Ab [ LEVEL: I Ol' b DATE: d'SO'N PAGE REVIEWED DY: ~ t tie LEVEL: I. . . -
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USN.50 ULTRASONIC CALIBRATION NO. TENNESSEE VALLEY AUTHORITY CALIBRATION D ATA SIIEET C- OI b
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cd u>..m Qt: MANUAL ULTR ASONIC REPORT NO. TENNESSEE VALLEY A UTilORITY PIPING EXAMINATION .- DATA S11EET N-) gl ROJECT: 6OMP UNIT: 2 EXAMINATION DATE: o4!z7!96 SYSTEM : 6% 616 START TIME: ISZE END TIME : IGO WELD !.D. : 6tW- O 7 EXAM SURFACE: O ID E OD CONFIOE KPC TO DO66 MATERIALTYPE: O Cs a ss o CsCL 0 CCss N SURFACE TEMP: A7 *F PYRO NO.: 552iBG FLOW PROCEDURE: N.'llr. IB REV.:_2O TC: N /A CALIBRAT10N SilEET NO. C. Of f 9~(%.D C of7'/<eom i-ii.sv. Wo
REFERENCE:
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l i l l 1 [ I ! i l Request For Relief 2-ISI-9 ; 1
- I I
Executive Summary: This request for relief addresses the ; pressurizer nozzle full penetration welds. l 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 l nozzle) and RCW-21 (14-inch surge nozzle). i These physical examination limitations i 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 l (May 27, 1970), SQN is exemp t from code l i-requirements for examinatica access as allowed in 10 CFR 50.55a (g' (4) . 1 1 An ultrasonic examination was performed on accessible areas to the maximum extent l practical, given the physical limitations l 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 l 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.
Unit : 2 System: Reactor Coolant - System 68 Components: Two Pressurizer Nozzles, Full Penetration 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 ' I 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. l 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 requirements, the pressurizer would l ' 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-o side surface of the pressurizer to 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 l 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 R j 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 F maximum extent practical ultrasonic examination of the subject welds l provides reasonable assurance of an i acceptable level of quality and safety. Significant degradation, if present, would have been detected 4 during the ultrasonic examination that
' 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) ."
Attachment 1 - Examination Data Reports: R-5668 and R-5673. Attachment 2 - 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
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EXAMINATION REPORT NO.
SUMMARY
AND R .52'4F TENNESSEE VALLEY AUTHORITY RESOLUTION SHEET I l 2 exAutNER M . A. C)UO A ZE5 LV: E unit: PROJECT: 6C)OP f EXAMINER: D ld $dEVI LV: I
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.M EXAMINATION REPORT No.
TENNESSEE VALLEY AUTHORITY
SUMMARY
AND RESOLUTION SHEET R- oT73 PROJECT: 60 dp UNIT: 2, EXAMINER: d , A . OLi\J A R.N LV: f SYSTEM: PZR /,069h ~I%T -oM 6 - t- O i 2co . ~2 EXAMINER ~O.ld . b CN, LV; 1 WELO I.O.: TCl>3 - ZI EXAMINER d[ LV: kl[ CONFIO: de 22LE, TO: WC L.L EXAMINER !A LV: !A
CAL SHT NO'S: C# l' $, C'll0 CO s 7//' Col /
PROCEDUAE: N- t f T 19 REV.: 9 TC: 4[A - NDE METHCO- E Ur O PT O uT O vT T *, gort r ('c u T N5 TM bArA mmc., ATm ld t-r8 "'Tht-LI4 odA t (ILwwo ot em E<Aub,Jo .:s or T CLG - 2. I L A6ME 6tr. 'IT Czer$ n , l N6 E' E Z'o C2 O A E 3D CAv7bD MPJ24 doTrrD a o r-FYA u uATt'n A bku'e m . b u bCAA b blDF'3 (0 t7 H A 3.76 ut T, i TP LL MEE NT A7 [c A E M ATI2. A T t 6 A CA b'TTa M O C' NR. I ws um r ~o n ue a. swg St.g re aco xa iMuL Or fec uMTrod . l WWL S'e? ?"_L - CO Vd~A WoG~ f~dA THff (: YAM IS 5~ 9. T2. fn
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-i C R-6/o'7 5 USN-50 ULTRASQNIC CALIBR ATION NO.
TENNESSEE VA T1FY A UTHORITY CALIDRATION DATA SIIEET C # 7# _
. ..OJ ECr: do u P UNrt: 2 CALIBRATION DATE: 64[Jo/96
/
PROCEDURE:N.(Tr. /9 REY.: 7 TC: A/A CALIBRATION BLOCK NO.: A N P 79 TEMP 79 F l SIMULATOR BLOCK NO.: 79/ 7/9' ' . INSTRUMENT: Mm/ 7.*'EANCE
//dA/* 60 T!!ERMCMETER SERIAL NO.: 65 2 /26 du D,c /-//.yg MODEUTYPE: '
SERAL NUMBER: E/8602 COUPLANT: /Ar#A4CL T BATCH: 9V/2f EXAM TYPE: C S!! EAR E LONO. RL TRANSDUCER MANUF.: 8N-M/>/ 4/g gW9 ' ANGLE VERIFIC ATION f SERIAL NO.: FREQUENCY: 2,2f Milt BLOCKTYPE: N NN 2 SERIAL NO. 7M9/ 7/ SIZE:_ / d ON CABLETYPE:, #4Edfd M2 LENGTil: 244/ NOMINAL ANGLE: O ACTUAL ANGLE: C* I INSTRUMENT SETTINGS REFLECTOR REFERENCE DATA 100 SENSITIVTTY SET ORIENTATION y , AXIAL h /A N /A 80 CIRC 2 3.S' M
~
NMX ANGLE: M6 D EC. P \ '
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TENNESSEE VALLEY AUTilORITY CALIBRATION DATA SIIEET C- # 7// _
.,OJECT: 5OOP UNm 5k- CAUBRATION DATE: kJd/f6 0*'P a" K " '-
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F 1RAiuNG my ,wn R.G.1.150 RESOLUTION VERFICATION NEAR SURFACE REFLECTCA: N[ DEPTH: d/ IN. SIZE: M/ FAR SURFACE REFLECTOR: !A DEPTH: !A IN. SIZE: !A SCANNING (REFLECTORS PROVIDE SC% DAC SIGNALS AT SCANNING SPEED- OYES O NO REMARKS: bt bl4 k)NP- 79 EXAMINER: . LEVEL: Y EXAMINER aj LEVEL: f DATE: f[fg MMr: 60 BY: - s LEVEL: Is - DATE: b PAGE _7 CF /b f TVA 1967CA (NP 7,92)
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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 l 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 l Is Requested: Volumetric Examination Coverage l List Of Items' I
~ Associated With I The Relief Request: RC-06, Piping To Reactor Coolant Pump l l Circumferential Weld I l RC-07, Piping To Reactor Coolant Pump Circumferential Weld l
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
\ RC-07. The design configuration and L \
l materialslimit/ultrasonicexaminationto approximately 50% of weld RC-06 and approximately 50% of weld RC-07. L Alternative l Examinations: In lieu of the code required 100% i ultrasonic examination, an ultrasonic 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, 2-ISI-10 E2-2 f
=
k Justification For The Granting Of Relief: (1) The design configuration and materials *
- used in the fabrication of the subject l piping welds preclude ultrasonic '
examination of essentially 100% of the 3 required examination volume. In order to examine the welds in accordance J with the code requirement, the reactor l 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 l cast CF8M material welded to a static j cast CF8M material pump casing. The l weld joint detail for Weld RC-07 l 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 ; 4 safety. Significant degradation, if present, would have been detected during the ultrasonic examination and 1 4 2-ISI-10 E2-4
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.
References:
Attachment 1 - Examination Data Reports: " R-5560, R-5566, R-5590, and R-5591. Attachment 2 - ISI Program Drawings: ISI-0008-C-01, Revision 6 and ISI-0307-C-01, Revision 8. I l l 1 l l-F I l i i 1 9 4 i E2-5 ISI-10
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/
SYSTEM : C 6A START TIME: __ O 9 0 0 END TIME : /O OO , WELD / COMPONENT 1.D. AC -Ob EXAM SURFACE: ID OD 7 CONFIG.: E/- So O .TO Po F ORIGINAL EXAMINATION [ REEXAMINATION FROCEDURE: N.PT. 9 REV.: / 2 TC: Sh..os o4 REFERENCE DRAWING NO. 7S7' OCO8-c-O/ f(:,
' ASME SEGON I ASME SECTION XI g. CODE CLASS / CATEGORY I , / BJ ACCEPTANCE CRITERIA O
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/ (34 LEVEL: DATE d' N 9h PAGE _/__ OF l._ ,
REVIEWED'BY:
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RECOR'D OF REPORT NO. ' TENNESSEE VALLEY AUTHORITY LIQUID PENETRANT EXAMINATION R 5546 edOJECT : S(14 UbTT: 1 EXAMINATION DATE: l- 11
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t?4 - rl.: u y,l Y EXAMINATION REPORT NO. l TENNESSEE VALLEY AUTHORITY
SUMMARY
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. ROJECT: 60MP UNIT: 2 CALIBRATION DATE: 4 27-9/*
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TEllflESSEE VALLEY AUTHORITY
SUMMARY
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. TVA 19670C (NP 7,92)
{ 4 Q-659l j USN 50 ULTRASONIC CALIBR ATION NO. TENNESSEE VALLEY AUTIIORITY CALIBRATION - DATA SilEET C-0IO5
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ENCLOSURE 3 TVA PROCEDURE FOR CALCULATION OF ASME CODE COVERAGE FOR SECTION XI NONDESTRUCTIVE EXAMINATIONS 1 l l l i
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Trecedure No. N-GP.23 NONDESTRUCTIVE EXAhENATION PROCEDURE - ; TVA Nuclear Power Revinon ( Page 1 of 16 1 i
'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 l l l Prepared By:
- Date: _b 'l!" 7
/, b elIII, Date: E -//- 9 Technical Review: -
Date: 8 -/ 5~-7 7. ISO Approval:
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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. 1 s l l l i 1 i 9
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) ~ 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 This procedure applies to the calculation of ASNE Section XI Code coverage for vessel welds. f J l piping welds, and integral attachments. This procedure applies to personnel performing surface or ' volumetric examinations and may be used as a guide when calculating the examination coverage for preservice and inservice examinations when the coverage is less than that required by 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
- l 4.1 Examination Coverage.The percentage of the examination surface or volume obtained during the performance of the examination.
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4.2 Examination Surface- The surface of the weld and base material required to enmined by ASNE Section XI using a surface examination method.
- 4.3 Examination Volume- The volume of weld and base material required to be examined by j
ASNE Section XI using a volumetric examination method.,
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4.4 Scan Limitation- A limit on the ability to scan the surface (s) as required by procedure. 4.5 Surface timitation ,A, limit on the ability to perform a surface examination of the required surface (s) because of an interference. 4.6 Volumetric Limitation- A limit on the ability to scan the required examination volume because of the geometric configuration, a physical interference, or a metallurgical condition of the material being examined. 4 4 i E l /
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- h i NONDESTRUCTTVE EXAMINATION PROCEDURE Procedure No. N-GP-23 TVA Nuclear Power Revision 1 Page 4 of 16
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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%.
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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 j 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 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. 7 w - 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
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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%. l 1 b) For welds with access from one side only due to interference / configuration (e.g.
, pipe to valve), the axial scan (scan 3 or 4) equals 50% and the circumferential scans (scan 5 and 6) each equal 25% for total of 100%. !
c) Examination volume coverage may be increased as previously discussed or by use of ) refracted longitudinal wave techniques on stainless steel or dissistilar metal welds. ! e Use of refracted longitudinal waves to penetrate stainless steel weld material will increase the examination volume coverage by the amount depicted on the
- examination coverage drawing /
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' - '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.
. l 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. ,
1 b) The area of achieved coverage achieved is divided by the total examination area for percentage of examination achieved.
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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-
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Procedure No. N-GP-23 NONDESTRUCTIVE EXAMINATION PROCEDURE Rmsien i TVA Nuclear Power Page 6 of 16 9.0 Intrasonic Examinations Vessel Welds 9.1 Examination volume coverage calculations are based upon the following suppositions: a) To achieve full examination coverage nine different scans are required for a typical nozale examination. The following may be used for other vessel configurations: s 1) 0 degree (weld metal scan)
- 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 45 degree Parallel-scan CCW direction i 7)
- 8) 60 degree Parallel-scan CW direction *
- 9) 60 degree Parallel-scan CCW direction ,
9.2 Attachment 3 describes ASME code compliance for full volume examination coverage for transverse scans in vessel applications. , 9.3 Typical nTethods for calculating coverage due to ultrasonic vessel limitations is contained in Attachments 3 A,3B,3C, and 3D. 10.0 Responsibilities -: The examiner or designee shall document the amount of code coverage obtained on i' 10.1 Attachment I after all necessary steps to perform additional examinations has been* completed in order to maximize coverage. 10.2 Attachment I shall be reviewed by another individual with the same or higher NDE cerdfication. 10.3 The NDE Level III or data reviewer shall review Attachment 1 in order to verify that the information is accurate and correct. 10.4 The NDE Level III may recalculate the examination coverage to obtain a more accurate value of the examination surface or volume examined. The calculation shall be documented on the exam report. j 10.5 The NDE Level III may require an alternate examination technique or method, or request that the interference be removed. For nozzle examinations, supplemental scans from the nozale bore or flange face may provide complete coverage of the weld.- l 10.6 If the exanunation coverage indicates less than 90 percent of the required examinatio volume or surface, the site ISI supervisor shall be notified. l 10.7 The site ISI supervisor shall ensure that examination results are accurately docum - and incorporate results into a Request for Reliefif necessary. I
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W.e* : '-' ::- ) NONDESTRUCTNb EXAMINNnON PROCSDURE . I Prc:edtire No. N-GP-20 TVA Nule.tr Power Revision 1 ,
. Pase 7 of 16
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ATTACHhEb71 EXAMINATION REPOfTNO. nuAersar VALLEr AumorrrY
SUMMARY
AND i i tescumON SHEIT R- i
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I Procedure No. N-GP 28 ) NONDESTRUCTIVE EXANENATION PROCEDllRE Resision I l TVA Nuclear Power Page 8 of 16 a
- ATTACHMENT 2 1
J j J l 1.25" 1/4" < - 1/4"
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1 3/4,, l Outside Diameter- 12.75" , 1 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 ,
5 5 f. 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
.375" Fua.w cm / COVERAGE LENGTH DUE TO ATTACHMENT y DOWNSTREAM A .2578 SQ.lN 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) - EXANPLE 1 A=.3 75/2(.675+.5) , 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
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ATTACHMENT 3 s I
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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
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f4 ?r ?* NONDESTRUCTIVE EXA. \ENAT10N PROCEDURE Prc:edure No. N-GP 23 TVA Nuclear Power Revision 1 i Page 11 of 16 l l ATTACHNENT 3 A i I s
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1 1 1/2 T-1.5"
> EN -85" 3/16" !
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2.75" 3.0" 60 D T
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1 TOTAL VOLUME- (L)(W)(H) e ; - TCI AL VOLUME- (85)(4.25)(3) 41/4- l 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.
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Ej; . NONDESTRUCTEE EXANGNATION PROCEDtJRE . ! Procedure No N-GP-28 TVA Nuclear Power l Revision 1 j Page 13 of 16 ATTACHNENT 3C AREA 1 s 1.5" / ;c 2.75" O! DETERMINE TOTAL T f EFFECTIVE
.866 T / COVERAGE A .375 B-2.812 5" 3.0" o.100% l 45T-29.76%
/. - / 45T-100%
H- 4.2 5" 4.25 60T45.W AREA 2 60T-100% A A -( = .; cw 6 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 AVERAGE-785.66/9 '- AREA 1 =1/2BH-1/2(.866)(1.5)- ' AREA .649 SQ.lN. AVERAGE-87.29% , VOL-(.649)(85)-55.165 CU.lN. l AREA 2- TOTAL AREA-AREA 1 l AREA 2- 12.75 SQ.IN. .649 SQ.IN.- 12.10 SQ.lN. ! 2.0 DETERM!NE 45 DEGREE COVERAGE
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- COVERAGE = VOLUME COVERE,D/ VOLUME REQUIRED 45 DEGREE COVERAGE-575.45/1028.585 .559(100)- 55.9%
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i EI,: l 1 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. DETERMINE AREA REQUIRED TO BE VOL-(3.78)(851N.)= 321.3 CUBlC IN. 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 l COVERAGE-VOLUME COVERED / VOLUME REQJIRED 45 DEGREE COVERAGE-321.3/988.125 .3251(100)- 32.51% l W
9 F.4 , .d.} l , NONDESTRUCTIVE EXAMINATION PROCEDURE ! Procedure No. N-GP-28 l TVA Nuclear Powei I Revision ! Page 14 of 16 ; ATTACH.NEW 3D i i N i EXAMPLE 2 45 DEGREE DETERMINE TOTAL AREA NOT COVERED- (AREA 2)-(AREA EXAMINED) COVERAGE FOR I AREA NO.T COVERED- 11.625 SQ.tN.-3.78 SQ.lN=7.845 SQ.lN. . WELD l VOLUME NOT COVERED- (7.845 SQ.!N.)(121N.)-94.14 CU.lN. , l 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% l
- 45T=100 l 45 DEG. (COVERAGE)- 100-8.68-91.32% 60T-93.78% l 60 DEG. (COVERAGE)-100-6.22=93.78% 60T-100%
45Pcw=100% l 45Pccw=100% -- l 60Pcw=100% T 60Peew=100% ; TOTAL -885.1
'. TOTAL AVERAGE-88.5.1/9 TOTAL AVERAGE-98.34%
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. 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
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!Li L2 La i l l s l l Hanger clamp around 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
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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
* . . , only!
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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 Total weld length to be examined = 1/2 + 4 + 1/2 + 2 + 1/2 + 4 + 1/2 + 2 = 14* f 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.
l f 3* Lug l 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}}